Solicitation 31310020R0004 CO.pdf

31310020R0004

SOLICITATION, OFFER AND AWARD

4. TYPE OF SOLICITATION2. CONTRACT NUMBER 3. SOLICITATION NUMBER

7. ISSUED BY CODE 8. ADDRESS OFFER TO (If other than Item 7)

ORDER UNDER DPAS (15 CFR 700)

6. REQUISITION/PURCHASE NUMBER

NOTE: In sealed bid solicitations "offer" and "offeror" mean "bid" and "bidder".

NEGOTIATED (RFP)

SEALED BID (IFB)

5. DATE ISSUED

1. THIS CONTRACT IS A RATED RATING PAGE OF PAGES

1 131

C. E-MAIL ADDRESS

EXT.NUMBERAREA CODE

B. TELEPHONE (NO COLLECT CALLS)A. NAME

10. FOR

INFORMATION

CALL:

CAUTION: LATE Submissions, Modifications, and Withdrawals: See Section L, Provision No. 52.214-7 or 52.215-1. All offers are subject to all terms and conditions contained in this solicitation.

(Date)(Hour) local timeuntildepository located in copies for furnishing the supplies or services in the Schedule will be received at the place specified in Item 8, or if hand carried, in the

SOLICITATION

9. Sealed offers in original and

PART IV - REPRESENTATIONS AND INSTRUCTIONS

OTHER STATEMENTS OF OFFERORS

EVALUATION FACTORS FOR AWARD

INSTRS., CONDS., AND NOTICES TO OFFERORS

REPRESENTATIONS, CERTIFICATIONS AND

LIST OF ATTACHMENTS

CONTRACT CLAUSES

PART III - LIST OF DOCUMENTS, EXHIBITS AND OTHER ATTACH.

I

J

K

L

M SPECIAL CONTRACT REQUIREMENTS

CONTRACT ADMINISTRATION DATA

DELIVERIES OR PERFORMANCE

INSPECTION AND ACCEPTANCE

PACKAGING AND MARKING

DESCRIPTION/SPECS./WORK STATEMENT

SUPPLIES OR SERVICES AND PRICES/COSTS

SOLICITATION/CONTRACT FORM

PART II - CONTRACT CLAUSESPART I - THE SCHEDULE

H

G

F

E

D

C

B

A

SEC. DESCRIPTION PAGE(S) (X) DESCRIPTION SEC. (X)

11. TABLE OF CONTENTS

18. OFFER DATE17. SIGNATURE

SUCH ADDRESS IN SCHEDULE.

IS DIFFERENT FROM ABOVE - ENTER

15C. CHECK IF REMITTANCE ADDRESS

EXT.NUMBERAREA CODE

15B. TELEPHONE NUMBER

(Type or print)AND

ADDRESS

OF

OFFEROR

CODE FACILITY

16. NAME AND TITLE OF PERSON AUTHORIZED TO SIGN OFFER15A. NAME

DATEAMENDMENT NO.DATEAMENDMENT NO.

and related documents numbered and dated):

amendments to the SOLICITATION for offerors

(The offeror acknowledges receipt of

14. ACKNOWLEDGEMENT OF AMENDMENTS

CALENDAR DAYS (%)30 CALENDAR DAYS (%)20 CALENDAR DAYS (%)10 CALENDAR DAYS (%)

(See Section I, Clause No. 52.232.8)

13. DISCOUNT FOR PROMPT PAYMENT

designated point(s), within the time specified in the schedule.

by the offeror) from the date for receipt of offers specified above, to furnish any or all items upon which prices are offered at the price set opposite each item, delivered at the

NOTE: Item 12 does not apply if the solicitation includes the provisions at 52.214-16, Minimum Bid Acceptance Period.

OFFER (Must be fully completed by offeror)

IMPORTANT - Award will be made on this Form, or on Standard Form 26, or by other authorized official written notice.

28. AWARD DATE

(Signature of Contracting Officer)

27. UNITED STATES OF AMERICA

25. PAYMENT WILL BE MADE BY

26. NAME OF CONTRACTING OFFICER (Type or print)

CODE 24. ADMINISTERED BY (If other than Item 7)

ITEM

(4 copies unless otherwise specified)

23. SUBMIT INVOICES TO ADDRESS SHOWN IN

41 U.S.C. 253 (c) ( 10 U.S.C. 2304 (c) (

22. AUTHORITY FOR USING OTHER THAN FULL AND OPEN COMPETITION:

21. ACCOUNTING AND APPROPRIATION20. AMOUNT19. ACCEPTED AS TO ITEMS NUMBERED

AWARD (To be completed by government)

CODE

03/18/2020 X

NRCHQ

US NRC - HQ

ACQUISITION MANAGEMENT DIVISION

MAIL STOP TWFN-07B20M

WASHINGTON DC 20555-0001

jeffrey.mitchell@nrc.gov daniel.app@nrc.gov

1400 ET 04/20/2020

JEFFREY R. MITCHELL 301

Jeffrey.Mitchell@nrc.gov

415-5074

X

X

X

X

X

X

X

X

X

X

X

X

PAGE(S)

MONIQUE B. WILLIAMS

AUTHORIZED FOR LOCAL REPRODUCTION

Previous edition is unusable

STANDARD FORM 33 (Rev. 9-97)

Prescribed by GSA - FAR (48 CFR) 53.214(c) email

12. In compliance with the above, the undersigned agrees, if this offer is accepted within _____0_________ calendar days (60 calendar days unless a different period is inserted

B - Supplies or Services/Prices

B.1 BRIEF DESCRIPTION OF WORK ALTERNATE I

B.2 CONSIDERATION AND OBLIGATION—INDEFINITE-QUANTITY CONTRACT

B.3 PRICE/COST SCHEDULE

C - Description/Specifications

C.1 STATEMENT OF WORK

D - Packaging and Marking

D.1 PACKAGING AND MARKING

D.2 BRANDING

E - Inspection and Acceptance

E.1 INSPECTION AND ACCEPTANCE BY THE NRC (SEP 2013)

F - Deliveries or Performance

F.1 PLACE OF DELIVERY-REPORTS

F.2 PERIOD OF PERFORMANCE ALTERNATE I

G - Contract Administration Data

G.1 REGISTRATION IN FEDCONNECT® (JULY 2014)

G.2 ELECTRONIC PAYMENT (DEC 2017)

G.3 ORDERING PROCEDURES FOR MULTIPLE-AWARD INDEFINITE-

DELIVERY/INDEFINITE-QUANTITY CONTRACTS (MAR 2014)

G.4 2052.215-77 TRAVEL APPROVALS AND REIMBURSEMENT. (OCT 1999)

G.5 2052.216-71 INDIRECT COST RATES. (JAN 1993)

G.6 2052.216-72 TASK ORDER PROCEDURES. (OCT 1999)

G.7 2052.216-73 ACCELERATED TASK ORDER PROCEDURES. (JAN 1993)

H - Special Contract Requirements

H.1 SECURITY REQUIREMENTS FOR BUILDING ACCESS APPROVAL (SEP 2013)

H.2 SECURITY REQUIREMENTS FOR INFORMATION TECHNOLOGY LEVEL I OR LEVEL

II ACCESS APPROVAL (JUL 2016)

H.3 INFORMATION TECHNOLOGY (IT) SECURITY REQUIREMENTS – GENERAL (JUL

2016)

H.4 INFORMATION TECHNOLOGY (IT) SECURITY REQUIREMENTS – GENERAL

EXCEPTIONS (JUL 2016)

H.5 IT SECURITY REQUIREMENTS – NRC AND CONTRACTOR (NON-NRC) FACILITIES

(APR 2014)

H.6 DEFINITION AND HANDLING OF EXPORT CONTROLLED INFORMATION

H.7 ANNUAL AND FINAL CONTRACTOR PERFORMANCE EVALUATIONS

H.8 RULES OF BEHAVIOR FOR AUTHORIZED COMPUTER USE

H.9 FOREIGN OWNERSHIP, CONTROL, OR INFLUENCE OVER CONTRACTOR

H.10 REPORTING FOREIGN TRAVEL (MAY 2018)

H.11 SECURITY REQUIREMENTS FOR ACCESS TO CLASSIFIED MATTER OR

INFORMATION (SEP 2013)

H.12 NRC INFORMATION TECHNOLOGY SECURITY TRAINING (MAY 2016)

H.13 SECURITY REQUIREMENTS RELATING TO THE PRODUCTION OF REPORTS OR

THE PUBLICATION OF RESULTS UNDER CONTRACTS, AGREEMENTS, AND GRANTS

(JUL 2016)

H.14 DRUG FREE WORKPLACE TESTING: UNESCORTED ACCESS TO NUCLEAR

FACILITIES, ACCESS TO CLASSIFIED INFORMATION OR SAFEGUARDS

INFORMATION, OR PERFORMING IN SPECIALLY SENSITIVE POSITIONS (OCT 2014) .58

H.15 USE OF AUTOMATED CLEARING HOUSE (ACH) ELECTRONIC

PAYMENT/REMITTANCE ADDRESS

H.16 AWARD NOTIFICATION AND COMMITMENT OF PUBLIC FUNDS

H.17 CONTRACTOR CONDUCT (DEC 2019)

H.18 COMPLIANCE WITH INTERNET PROTOCOL VERSION 6 (IPV6) IN ACQUIRING

ELECTRONIC AND INFORMATION TECHOLOGY (EIT) (OCT 2012)

H.19 ORDERING PROCEDURES FOR MULTIPLE-AWARD INDEFINITE-

DELIVERY/INDEFINITE-QUANTITY CONTRACTS (MAR 2014)

H.20 SECURITY REQUIREMENTS FOR UNESCORTED ACCESS TO NUCLEAR POWER

PLANTS (SEP 2013)

H.21 2052.204-71 SITE ACCESS BADGE REQUIREMENTS. (JAN 1993)

H.22 2052.209-72 CONTRACTOR ORGANIZATIONAL CONFLICTS OF INTEREST. (JAN

1993)

H.23 2052.215-70 KEY PERSONNEL. (JAN 1993)

H.24 2052.215-71 CONTRACTING OFFICER REPRESENTATIVE AUTHORITY. (OCT 1999)

H.25 2052.242-70 RESOLVING DIFFERING PROFESSIONAL VIEWS. (OCT 1999)

H.26 2052.242-71 PROCEDURES FOR RESOLVING DIFFERING PROFESSIONAL VIEWS.

(OCT 1999)

I - Contract Clauses

I.1 COMPLIANCE WITH SECTION 508 OF THE REHABILITATION ACT OF 1973, AS

AMENDED (SEP 2013)

I.2 2052.222-70 NONDISCRIMINATION BECAUSE OF AGE. (JAN 1993)

I.93 52.203-14 DISPLAY OF HOTLINE POSTER(S). (OCT 2015)

I.94 52.215-23 LIMITATIONS ON PASS-THROUGH CHARGES. (OCT 2009)

I.95 52.216-7 ALLOWABLE COST AND PAYMENT. (AUG 2018)

I.96 52.216-18 ORDERING. (OCT 1995)

I.97 52.219-6 NOTICE OF TOTAL SMALL BUSINESS SET-ASIDE. (NOV 2011)

I.98 52.219-8 UTILIZATION OF SMALL BUSINESS CONCERNS. (OCT 2018)

I.99 52.219-14 LIMITATIONS ON SUBCONTRACTING. (JAN 2017)

I.100 52.227-14 RIGHTS IN DATA-GENERAL. (MAY 2014) - ALTERNATE II (DEC 2007)...90

I.101 52.244-2 SUBCONTRACTS. (OCT 2010)

I.102 52.244-2 SUBCONTRACTS. (OCT 2010) - ALTERNATE I (JUN 2007)

I.103 52.252-2 CLAUSES INCORPORATED BY REFERENCE. (FEB 1998)

J - List of Documents, Exhibits and Other Attachments K - Representations, Certifications, and Other Statements of Bidders

K.1 2052.209-70 CURRENT/FORMER AGENCY EMPLOYEE INVOLVEMENT. (OCT 1999)

K.2 2052.209-71 CONTRACTOR ORGANIZATIONAL CONFLICTS OF INTEREST

(REPRESENTATION). (OCT 1999)

K.5 52.204-16 COMMERCIAL AND GOVERNMENT ENTITY CODE REPORTING. (JUL

2016)

K.6 52.204-19 INCORPORATION BY REFERENCE OF REPRESENTATIONS AND

CERTIFICATIONS. (DEC 2014)

K.7 52.209-7 INFORMATION REGARDING RESPONSIBILITY MATTERS. (OCT 2018) ...105

K.8 52.209-11 REPRESENTATION BY CORPORATIONS REGARDING DELINQUENT TAX

LIABILITY OR A FELONY CONVICTION UNDER ANY FEDERAL LAW. (FEB 2016)

K.9 52.215-6 PLACE OF PERFORMANCE. (OCT 1997)

K.10 52.219-1 SMALL BUSINESS PROGRAM REPRESENTATIONS. (OCT 2014)

K.11 52.222-25 AFFIRMATIVE ACTION COMPLIANCE. (APR 1984)

K.12 52.225-20 PROHIBITION ON CONDUCTING RESTRICTED BUSINESS OPERATIONS

IN SUDAN--CERTIFICATION. (AUG 2009)

L - Instructions,Conditions, and Notices to Bidders

L.1 GREEN PURCHASING (JUL 2016)

L.2 2052.215-73 AWARD NOTIFICATION AND COMMITMENT OF PUBLIC FUNDS (OCT

1999)

L.5 52.204-7 SYSTEM FOR AWARD MANAGEMENT. (OCT 2018)

L.6 52.215-1 INSTRUCTIONS TO OFFERORS - COMPETITIVE ACQUISITION. (JAN 2017)

L.7 52.215-20 REQUIREMENTS FOR CERTIFIED COST OR PRICING DATA AND DATA

OTHER THAN COST OR PRICING DATA. (OCT 2010)

L.8 52.215-22 LIMITATIONS ON PASS-THROUGH CHARGES--IDENTIFICATION OF

SUBCONTRACT EFFORT. (OCT 2009)

L.9 52.216-1 TYPE OF CONTRACT. (APR 1984)

L.10 52.222-24 PREAWARD ON-SITE EQUAL OPPORTUNITY COMPLIANCE

EVALUATION. (FEB 1999)

L.11 52.233-2 SERVICE OF PROTEST. (SEP 2006)

L.12 52.252-1 SOLICITATION PROVISIONS INCORPORATED BY REFERENCE. (FEB

1998)

L.13 INSTRUCTIONS, CONDITIONS & NOTICES

M - Evaluation Factors for Award

M.1 EVALUATION FACTORS

B - Supplies or Services/Prices

B.1 BRIEF DESCRIPTION OF WORK ALTERNATE I

(a) The title of this project is: TECHNICAL ASSISTANCE IN SUPPORT OF NRC NUCLEAR

REGULATORY RESEARCH FOR MATERIALS, WASTE, AND REACTOR PROGRAMS

(b) Summary work description: The NRC activities applicable to this Statement of Work (SOW) for nuclear power reactors and non-commercial non-power production and utilization facilities may include providing support for the following: technical reviews of topical reports for reactor design certifications (DCs); early site permits (ESPs); combined license (COL) applications;

reactor pre-application activities; limited work authorizations (LWAs); construction permits (CPs); operating licenses (OLs); license actions (i.e., amendments, facility operating license renewals, relief requests, and exemptions); supporting development of regulatory guides (RG) and research information letters (RILs); oversight; and staff infrastructure development. Other activities for materials and waste facilities include, but are not limited to, technical support for technical reviews of license applications, license renewals, license amendments, exemption requests, and decommissioning.

(c) Orders will be issued for work in accordance with FAR 52.216-18 – Ordering.

B.2 CONSIDERATION AND OBLIGATION—INDEFINITE-QUANTITY CONTRACT

(a) The estimated total quantity of this contract for the products/services under this contract is ($ to be determined) incorporated into resultant contract.

(b) The Contracting Officer will obligate funds on each task order issued.

(c) The minimum guarantee under this contract is $10,000.00.

(d) The obligated amount for this contract is Obligated under Task Order No. 1.

(e) A total estimated cost and fee, if any, will be negotiated for each task order and will be incorporated as a ceiling in the resultant task order. The Contractor shall comply with the provisions of FAR 52.232-20 - Limitation of Cost for fully-funded task orders and FAR 52.232-22

- Limitation of Funds for incrementally-funded task orders, issued hereunder.

B.3 PRICE/COST SCHEDULE

Period of Performance – Five Years from Effective Date of Contract

CLIN DESCRIPTION OF

SUPPLIES/SERVICES

The cost schedule will be completed at time of award. See Section J for Cost proposal templates and Section L.13 - Part 2 Cost Proposal format.

Total estimated cost shall be $42,000,000.00 which will result in a shared IDIQ Ceiling.

C - Description/Specifications

C.1 STATEMENT OF WORK

C.1 STATEMENT OF WORK

PROJECT TITLE: TECHNICAL ASSISTANCE IN SUPPORT OF NRC NUCLEAR

REGULATORY RESEARCH FOR MATERIALS, WASTE, AND REACTOR PROGRAMS

1.0 BACKGROUND

U. S. Nuclear Regulatory Commission (NRC) regulates the licensing, construction and operation of commercial nuclear power facilities and commercial and non-commercial non-power production and utilization facilities (NPUFs). The Office of Nuclear Reactor Regulation (NRR) with support from the Office of Nuclear Security and Incident Response (NSIR), serves the public interest by enabling the safe, secure, and environmentally responsible use of nuclear power and technology in meeting the nation's energy and research needs. The Office of Nuclear Material Safety and Safeguards (NMSS) is responsible for regulating activities which provide for the safe and secure production of nuclear fuel used in commercial nuclear reactors (uranium recovery, conversion, and enrichment activities; fuel fabrication); and development;

the safe storage, transportation and disposal of high-level radioactive waste and spent nuclear fuel; and the transportation of radioactive materials regulated under the Atomic Energy Act.

NMSS ensures safety and security by implementing a regulatory program involving activities including licensing, inspections, assessments of licensee performance, events analysis, enforcement, and identification and resolution of generic issues. The Office of Nuclear Regulatory Research (RES) furthers the regulatory mission of the NRC by providing technical advice, technical tools, and information for identifying and resolving safety issues, making regulatory decisions, and promulgating regulations and guidance.

The NRC activities applicable to this SOW for nuclear power reactors and NPUFs may include providing support for the following: technical reviews of topical reports for reactor design certifications (DCs); early site permits (ESPs); combined license (COL) applications; reactor pre-application activities; limited work authorizations (LWAs); construction permits (CPs);

operating licenses (OLs); license actions (i.e., amendments, facility operating license renewals, relief requests, and exemptions); supporting development of regulatory guides (RG) and research information letters (RILs); oversight; and staff infrastructure development. RES activities for materials and waste facilities include, but are not limited to, technical support for technical reviews of license applications, license renewals, license amendments, exemption requests, and decommissioning.

NRC anticipates the continued review of COL applications and operating and renewal reactor licensing actions over the next several years as well as a variety of applications for Non-Light Water (non-LWR) reactors. Due to the volume of new and advanced reactor applications as well as licensing actions for operating reactors and NPUFs, commercial contractor resources are needed to augment staff resources. Also, commercial contractor resources are needed to support reactor security reviews including, but not limited to: physical security, cyber security, access authorization, fitness for duty, materials control and accounting security, transportation security, independent spent fuel storage installation security and support in emergency preparedness.

2.0 WORK REQUIREMENTS

2.1 Contractor Technical Assistance

The Contractor shall provide technical assistance and expertise in NRC activities, including, but not limited to, the following:

(a) Revising regulatory documents as assigned, to support application reviews (e.g., NUREG- 0800, 10 CFR Parts 50, 51, 52, 54, 71, 72, 73 and related guidance including regulatory guides and research information letters);

(b) Reviewing, assessing and evaluating submittals (e.g., License Applications, Technical Reports, Safety Analyses, Topical Reports, Amendments, and similar documents for New, Advanced, Operating, Or Renewal License Applications, and Materials and Waste Safety Reviews) and prepare requests for additional information (RAIs);

(c) Preparing input to SERs by utilizing NRC provided templates and instructions;

(d) Preparing for and traveling to NRC Headquarters, Regional offices, or plant sites for the purpose of participating in audits, inspections, as well as attending meetings at other NRC locations, with applicants, potential applicants, licensees, or vendors;

(e) Conducting reviews, assisting in siting issues, any required regulatory development; and

(f) Technical expertise and administrative support in rulemaking activities.

(g) Guidance and technical report development.

2.2 Task Orders

The Task Orders will be awarded by the Contracting Officer (CO). The Contractor shall submit a technical and cost proposal in response to the Task Order Request for Proposal (RFTOP).

The Contractor shall perform each Task Order in accordance with the final project plan approved by the COR.

2.3 Quality Control Plan

The Contractor shall follow a Quality Control Plan which outlines the procedures and system they will use for document version control, technical input tracking, change management, and technical and editorial reviews. The Contractor shall organize, track, and manage changes in a structured, systematic, and transparent manner, throughout the review and production of each deliverable.

3.0 SCOPE OF WORK

The Contractors shall provide technical assistance and expertise in a wide range of technical and scientific disciplines that are more fully-described in the Statement of Work Sections or Parts located below. These technical support services are necessary to accomplish work-related activities aimed at ensuring the overall safety, security and adequacy of nuclear power plant and NPUF design, construction, operations and environmental protection.

3.1 Thermal Hydraulics Research Support

The Contractor shall provide technical assistance for simulations and analyses that include normal operations, anticipated operational occurrences, design basis accidents, and beyond-design basis accidents relevant to all currently operating reactor types, as well as new and advanced reactor designs. Such assistance shall be accomplished using the NRC’s computer code suite designed to perform the respective simulations for the applicable technical disciplines, including thermal-hydraulics, computational fluid dynamics (CFD), neutronics, severe accidents, radiological consequences, and fuel behavior. The thermal-hydraulic code suite for the analysis of nuclear reactor systems and components contains the following NRC computer codes:

• TRAC/RELAP Advanced Computational Engine (TRACE): Reactor Systems Thermal- Hydraulics

• Purdue Advanced Reactor Core Simulator (PARCS)

• Advanced Gas REactor Evaluation (AGREE): Core Thermal-Hydraulics

• Fuel Analysis under Steady-state and Transients (FAST): Thermal-Mechanical Fuel Performance

3.2 Nuclear Fuel and Core Neutronics Support

The Contractor shall update the architecture of the Fuel Analysis under Steady-state and Transients (FAST) code in order for the code to be parallelized, modern and be able to solve the major governing physics (such as heat conduction, diffusion and solid mechanics) on multiple types of geometries. The code shall include finite difference, finite element, and finite volume partial differential equation solvers and shall be written to ensure FAST is utilizing the most modern supported features of Fortran 2018. These code architecture updates are needed to support licensing reviews of advanced non-LWR designs and advanced fuel concepts.

Steady-state and transient nodal diffusion codes such as PARCS are used to predict the fission power and decay heat sources that arise under normal, off-normal, and accident conditions.

Steady-state calculations of spatial core power and burnup distributions over multiple core operating cycles are used in analyzing (a) peak pin powers in relation to fuel thermal limits, (b) reactivity and power control, (c) safe shutdown margins, (d) slow spatial xenon transients and oscillations, and (e) the initial conditions of spatial reactivity feedback characteristics, fission power, stored heat, and decay power. Dynamically coupled transient calculations are especially important in analyzing the spatial kinetics of reactivity insertion transients (e.g., rod bank withdrawal, rod drop, rod ejection) and the core power surges and oscillations associated with transient over-cooling events (e.g., turbine trip), flow and boiling instabilities, and anticipated transients without scram (ATWS).

This predictive ability entails the use of three-dimensional (3-D) reactor physics codes such as PARCS, which has been continuously developed by RES since 1998. PARCS has been dynamically coupled to the system thermal hydraulic (T-H) code TRACE and is available as both an embedded module within TRACE and as a standalone code. TRACE/PARCS is used for the analyses of normal operations and transients in operating reactors (control and power maneuvers), confirmation of licensee’s analyses, and supporting analyses for the certification review of current reactor designs, and advanced reactor designs.

PARCS is a nodal reactor analysis code that calculates the transient and steady state core power (and other safety significant reactor parameters) through the numeric solution to a discretized formulation for the neutron diffusion equation. In standalone-maintained form, it is coupled to PATHS for thermal-hydraulic feedback during semi steady-state calculations for both BWR and PWR cores, and a simple mass energy balance for PWR analysis. The code system includes the main PARCS code, the cross-section processing interface for conversion into the PARCS format from lattice physics data (GenPMAXS). In addition to converting lattice physics-averaged cross sections, GenPMAXS also analytically solves for the flux discontinuity along the fuel reflector interface. In anticipation of license reviews of advanced designs and advanced fuel concepts, the Contractor shall provide technical assistance in the development, maintenance, and applications of the PARCS code.

3.3 Severe Accident and Consequence Analysis Support

The Contractor shall provide technical assistance and regulatory support associated with input model development, severe accident progression simulations, and benchmarking against selected test data for specific reactor technologies. The computer codes used include the integrated system level MELCOR computer code, MELCOR Accident Consequence Code System (MACCS) for consequence analysis, TEXAS code for fuel coolant interaction analysis, and computational fluid dynamics (CFD) codes to support system level codes.

3.4 Component Integrity and Materials Performance

The Contractor shall provide Technical assistance and support for confirmatory research on component integrity and materials performance on both the development of methodologies needed to support regulatory actions and supporting the technical bases for codes and standards development. A common theme in this work is a proactive approach to the management of aging degradation for operation beyond 60 years. The Contractor shall assemble technical information on aging phenomena that can affect materials in nuclear power plants (NPPs) and to develop technical assessment of subsequent license renewal (SLR) applications for the currently operating NPPs. In addition, Contractor shall provide technical support for confirmatory research on advanced light water and non-light water reactors that are expected in near future for regulatory considerations. Major areas of current interest are:

Piping Degradation:

To better understand how the reactor is influenced by the phenomenon of primary water stress corrosion cracking (PWSCC), the contractor shall provide technical assistance on the development of analysis methods and computational tools, and assess the impact of PWSCC on the overall safety of piping systems of the reactor coolant pressure boundary. The Contractor shall also assess impacts of PWSCC on the leak-before-break (LBB) behavior of piping systems.

Reactor Pressure Vessel (RPV) Integrity:

The Contractor shall provide technical assistance and support on maintaining the structural integrity of the reactor pressure vessel (RPV) during normal operations and also during postulated accident scenarios. The Contractor shall provide support for the assessment of RPV structural integrity to; (1) predict the behavior of cracked components under loading, and (2) predict the effects of irradiation embrittlement on the fracture toughness of RPV steels. In addition, the Contractor shall provide assistance on understanding the adequacy of existing approaches and on developing new models and predictive procedures to address the integrity of the RPVs.

Non-Destructive Evaluation (NDE):

The Contractor shall provide technical assistance on determining the effectiveness and reliability of NDE methods, assessment of NDE modeling tools, and evaluation of human factors on NDE performance. The contractor shall provide support for regulatory decisions associated with NDE and in-service inspection (ISI) of safety-related systems. In addition, the contractor shall provide support for review of relief requests and proposed changes to ASME (American Society of Mechanical Engineers) Boiler & Pressure Vessel Code (B&PVC) and code case requirements.

Storage and Transportation of Spent Nuclear Fuel:

The Contractor shall provide technical assistance to develop the technical bases for review of license renewal applications for continued storage and transportation of spent nuclear fuel. In addition, the contractor shall provide support for improved understanding of potential degradation modes that could affect safety significant structures, systems, and components in dry cask storage systems. Potential degradation modes include, but not limited to, chloride-induced stress corrosion cracking of stainless steel canisters.

Technical assistance and support may be needed in the following specific areas of materials performance and component integrity:

• Nuclear reactor pressure vessel and piping systems materials, environmental degradation, and fracture assessment.

• Finite element modeling and simulation including extended finite element method (XFEM) including, but not limited to, Simulia/ABAQUS FEM code.

• Fracture mechanics modeling and experimental validation.

• Weld residual stress modeling and measurement.

• Mechanical testing of structural materials (metals and non-metals) for NPP applications.

• Software maintenance, quality assurance, verification and validation.

• Applications, maintenance, and/or development of probabilistic fracture mechanics (PFM) modeling software such as: (1) eXtremely Low Probability of Rupture (xLPR) software for piping systems containing dissimilar metal welds that are subjected to primary-water stress corrosioncracking (PWSCC) and thermal stress-induced fatigue, (2) Fracture Analysis of Vessels – Oak Ridge (FAVOR) software for RPV assessment, (3) Design Analysis Kit for

Optimization and Terascale Applications (DAKOTA), (4) FES (Flaw Evaluation Software – NRC), (5) LEAPOR (Leak Analysis of Piping – Oak Ridge), and others.

• Statistical analysis (e.g., sensitivity analysis, sampling convergence analysis, uncertainty analysis).

• Application of computational fluid dynamics to assess leakage from cracks to support LBB assessments.

• Application of computer programming including, but not limited to, Fortran programming.

• Technical assistance for evaluation of codes and standards and code cases that are being developed under ASME B&PVC, Section III (nuclear components), Division 5 (high-temperature reactors) for nuclear-grade graphite and metallic materials for use in high-temperature gas-cooled reactors (HTGRs), liquid metal (sodium, lead or lead-bismuth)-cooled fast reactors (LMRs) and molten-salt cooled reactors (MSRs).

• Support on development and assessment of high temperature flaw evaluations methodologies under steady-state and time-dependent loadings and materials’ response such as in creep-fatigue.

• Technical assistance for evaluating the chemical compatibility and testing of molten salt reactor corrosion on structural materials and graphite.

• Technical assistance for assessing ASME B&PVC code cases for allowing piping repairs made with carbon fiber reinforced polymers (CFRP), support relief request allowing repair to safety-related piping (e.g., service water piping) with CFRP materials.

• Support on web-based public-facing application and programing for Radiation Embrittlement Archive Project (REAP) database developed at Oak Ridge National Laboratory for continued operation and maintenance of LWR surveillance testing.

• Support of NDE of advanced materials, human factors for NDE and, on computational modeling and simulation for NDE.

• Support on analyzing, assembling and review information presented at various international technical meetings and published in scientific journals concerning key emerging issues and recent progress related to plant chemistry/corrosion in pressurized water reactors (PWRs), boiling water reactors (BWRs), Russian VVER and CANDU (Canada) reactors.

• Support on technology advancement and regulatory acceptance of advanced manufacturing technology (AMT)-fabricated components, and identify AMTs that are likely to be used in new NPPs or in existing plants.

• Support on computational modeling and simulation of AMTs including, but not limited to, electron beam welding (EBW) and hot isostatic pressing (HIP) for application to fabrication of advanced light water reactor (LWR) and non-LWR primary system components.

• Support on compiling, analyzing and verifying mechanical properties, strength, fracture toughness, and microstructure characterization data for AMT-fabricated and subsequent heat treated test specimens that are representative of full-scale sub-assemblies and components.

• Support on identifying and qualifying NDE techniques to ensure the quality of AMT- fabricated parts.

3.5 Instrumentation and Controls (I&C) and Electrical Systems for NPP and NPUFs

The instrumentation and controls (I&C) area continues to evolve, and the NRC continues to refine its regulatory approach to comport with technological advancements in this area. As operating NPPs and NPUFs upgrade, analog equipment is being replaced with modern digital equipment including, but not limited to, flat screen operator interfaces and soft controls, embedded digital devices in even traditionally electromechanical systems such as relays, and reactor protections systems. In addition the way in which these systems are developed is advancing, such as the shift to systems engineering, the use of model based engineering, and modern hazard analysis methods. The NRC continues to perform research and licensing activities that supports development of licensing criteria to evaluate new digital I&C systems.

The NRC also continues to perform research and licensing activities into the operation of electrical systems. The topical areas for electrical engineering include offsite power sources, onsite electrical power distribution systems, emergency power supplies, electrical equipment qualification, and electrical cable and equipment aging.

The contractor shall provide technical assistance and support on one or more of the following areas:

• Assessment and licensing activities on analog and digital I&C and electrical systems and components.

• Assessment and licensing activities on I&C systems and components modernization and refurbishment.

• Assessment and licensing activities on Equipment qualification (EQ) of I&C systems and electrical system components.

• Assessment and licensing activities on field-programmable gate array (FPGA)-based instrumentation and control systems’ applications in NPPs; design, programming, testing, integration, and verification and validation.

• Assessment and licensing activities on Cyber physical systems (CPS).

• Assessment and licensing activities on embedded digital devices.

• Assessment and licensing activities on Model Based Systems Engineering and associated methods, processes, tools, and their combined use as methodologies.

• Application and licensing activities of modern hazard analysis methodologies (e.g., Systems- Theoretic-Process-Analysis).

• Development and maintenance of databases on operational experience of digital instrumentation and controls in nuclear power plants, or other applications of similar safety significance.

• Assessment and licensing activities on offsite power sources.

• Assessment and licensing activities on onsite electrical power distribution systems.

• Assessment and licensing activities on emergency power supplies.

• Assessment and licensing activitieson electrical equipment qualification.

• Assessment and licensing activities on electrical cable and equipment aging.

3.6 Risk Analysis

The NRC staff performs risk assessments of inspection findings and reactor incidents to determine their significance for appropriate regulatory response. The NRC recognizes that probabilistic risk assessment (PRA) has evolved to the point where it can be used as a tool in risk-informed regulatory decision-making. Consequently, confidence in the information derived from a PRA is an important issue. The accuracy of the technical content must be sufficient to justify the specific results and insights that are used to support the decision under consideration.

The NRC continues to perform research that supports development of methods used for regulatory decision-making.

The contractor shall provide technical assistance and support on one or more of the following areas:

• Technical assistance for in-depth analyses and evaluations of significant operating events and safety issues to determine the root causes of these events, risk insights and lessons-learned.

• Technical assistance for the Risk Assessment Standardization Project (RASP) to establish standard procedures, improve the methods, and enhance risk models that are used in risk assessment in various risk-informed regulatory applications.

• Technical assistance in the development of consistent PRA/Risk-related terminology to ensure accurate communication and transfer of information in support of risk-informed decision-making (related to NUREG-2122).

• Support the development of PRA uncertainty (related to NUREG-1855) to foster an understanding of the uncertainties associated with PRA and their impact on the results of PRA and by providing a pragmatic approach to addressing these uncertainties in the context of the decision-making.

• Support the advancement of Standardized Plant Analysis Risk (SPAR) models used by NRC staff in support of risk-informed activities related to the inspection program, incident investigation program, license amendment reviews, performance indicator verification, accident sequence precursor program, generic safety issues, and special studies.

• Provide insights to support the Systems Analysis Programs for Hands-on Integrated Reliability Evaluation (SAPHIRE) software development program to advance the state of art in performing risk calculations accurately and efficiently in support of risk-informed regulatory activities.

• Technical assistance on the development of new Level 3 PRAs to enhance regulatory decision-making with the focus on issues directly related to the agency's mission to protect public health and safety.

• Support research programs related to human performance, personnel safety and security, and human reliability analysis (HRA) such as: technical support and on-going Part 26 implementation consultation, HRA data repository, HRA-informed tools for medical applications, and updating human factors engineering methods and tools to provide safety perspectives on the impact of human performance on nuclear power plants and other NRC-licensed facilities and their regulated activities.

• Technical assistance in support of fire PRA methodologies to evaluate the impact of fire to safety systems, failures in the fire defense in depth strategy, and safe operation of nuclear power plants (related to NUREG/CR-6850).

• Support the development of methods, data, standards, and modeling tools to assess the magnitude and effect of released radioactive material to the environment outside nuclear facilities.

• Support in experiments to better characterize and quantify fire safety risks and hazards in nuclear power plants.

• Support the development of fire HRA methods in support of fire PRA beyond those currently in NUREG/CR-6850 and to expand existing HRA methods to evaluate the impact of human failures in the fire protection defense-in-depth safety strategy.

• Technical assistance to improve, verify and validate fire modeling in NPPs used to analyze fire scenarios in risk assessments, determine damage to cables and other systems and components important to safety.

• Technical assistance in support of the development of Regulatory Guide and standards development for risk-informed decision-making.

• Support development of advanced risk-informed methods for non-reactor applications (e.g., Dry Cask Storage).

• Support to expand, update, review advanced PRA methods, tools and data used in nuclear regulatory activities to support implementation of risk-informed regulation.

3.7 Code Development and Code Support

Unless otherwise stated, these task areas may apply to any of the following codes: TRACE, PARCS (both standalone and coupled versions), RELAP5, AVScript, and ACAP, AGREE, SNAP, APTPlot, and GENPMAXS. Also included are component integrity and probabilistic fracture mechanics related codes such as FAVOR (Fracture Analysis of Vessels – Oak Ridge), xLPR (extremely Low Probability of Rupture - piping), FES (Flaw Evaluation Software – NRC), LEAPOR (Leak Analysis of Piping – Oak Ridge), and other codes. PARCS-related application and development work necessary to support project objectives, as well as the use of commercially available lattice physics codes like HELIOS or CASMO. In addition, the stated codes may need support and maintenance and may be used for analysis under this contract.

The NRC may, at its discretion, issue task orders for work in any of the following areas:

1. Engineering analyses related to code errors, modeling gaps, or deficiencies and document those analyses and their safety significance.

2. Code and/or model development to add new modeling capabilities or features to the codes.

This may include the integration of changes developed by others into official code update submittals (including all necessary SQA). All development will be performed according to accepted SQA practices.

3. Code and/or model development to change existing modeling capabilities or features in the codes. This may include the integration of changes developed by others into official code update submittals (including all necessary SQA). All development will be performed according to accepted SQA practices.

4. Typical code maintenance activities, such as (but not necessarily limited to) tracking & fixing bugs, version control and configuration management, developing and maintaining installation packages across multiple platforms, and maintaining documentation.

5. Evaluation of new experimental and/or assessment results and make recommendations to the NRC concerning their implementation.

6. Developmental assessment and documentation of (i.e. V&V) the codes against new or existing experimental data. This may involve assessing codes against a wide range of pre-existing test cases in an automated framework and documenting the results in an assessment addendum prior to code release. This may also include reviewing the assessment data base and expanding it with applicable test cases and automated validation frameworks, as appropriate.

7. Have new versions of codes tested or peer reviewed by independent organizations.

8. Maintenance and updates of code documentation, as appropriate. This may include converting documentation to different formats.

9. Specific technical studies and technical support related to the codes as requested by the

NRC.

10. Development of input models to address issues that may arise from the NRC review of new or existing reactor designs and generic or safety issues related to operating reactors.

11. Maintenance and improvement of the NRC Data Bank. This may include (but is not limited

to) such tasks as

• Converting raw data to the NRC PIB binary format and arranging for placement into the NRC’s Agency-wide Documentation and Management System (ADAMS)

• Identifying and acquiring relevant technical reports and reference material for inclusion in the Data Bank

• Reorganizing electronic files already in the Data Bank to new hierarchical structures

• Migration of the Data Bank to a version control system

• Development of a queuing system to allow tracking of the file conversion process

• Changes to the conversion process or storage format

12. CAMP and Domestic User Group program management. Typical activities would include maintaining a current list of approved users/organizations, organizing and participating in bi-annual CAMP conferences, taking meeting minutes, maintaining a user support site, reviewing in-kind contributions, providing telephone and email assistance to code users, developing and distributing bi-annual newsletters, distributing codes to approved users, establishing CAMP licensing agreements with foreign commercial organizations on NRC’s behalf, and handling invoicing and fee collection for domestic and international organizations.

13. Special development projects designed to improve the capabilities or maintenance of electronic tools used to support code users and the CAMP program.

14. Develop and/or conduct training courses for NRC T/H codes as well as general thermal-hydraulics and reactor safety topics (i.e. LBLOCA, SBLOCA, transients, stability analysis, two-phase flow fundamentals, etc.). Training materials may take the form of on-line web-based training videos as opposed to traditional classroom-based learning.

15. The contractor shall provide technical assistance for simulations and analyses that include normal operations, anticipated operational occurrences, design basis accidents, and beyond-design basis accidents relevant to all currently operating reactor types, as well as new and advanced reactor designs. Such assistance shall be accomplished using the principal computer codes designed to perform the respective simulations for the applicable technical disciplines, including thermal-hydraulics, neutronics, computational fluid dynamics (CFD), severe accidents, radiological consequences, and fuel behavior. This work includes the formulation of input models (aka input decks; e.g., the input model for the Browns Ferry Nuclear Plant), calculational notebooks that document formulation of the input models and any other associated documentation.

16. The contractor shall provide technical assistance for creation of constitutive relations and phenomenological models (e.g. a two-phase drag model; droplet models, entrainment models etc.) to support analysis needs of all currently operating reactor types, as well as new and advanced reactor designs. Such assistance shall be accomplished through modifications of the principal computer codes or the coupling methods that link the various codes and models. In addition, the contractor shall provide experimental data (preferably by obtaining the existing data from other facilities, or via experiments produced by building experimental facilities and operating them as part of this contract). Such data will be used in verification and validation activities that are part of this contract. The codes and their correlations must be verified and validated for their intended uses.

17. SNAP Development and Support activities.

• SNAP is written in Java, which itself it updated rather frequently. The contractor shall make sure that SNAP and its components fully function under the current version of Java; this may involve rewriting SNAP components to ensure compliance with the new Java versions.

• SNAP code plug-ins exist for the following NRC-developed analytical codes: TRACE, MELCOR (1.8.6, 2.1, and 2.2), PARCS, RADTRAD, FRAPCON, FRAPTRAN, and FAST.

TRACE is a system-level thermal hydraulic code. MELCOR is a system-level severe accident code. PARCS is a three-dimensional (3D) reactor core simulator which solves the steady-state and time-dependent, multi-group neutron diffusion and transport equations. RADTRAD is a code that predicts dose to populations based on radiological release from various scenarios.

FRAPCON and FRAPTRAN are fuel phenomena codes; FAST replaces the functionality of the “FRAP” codes with a modern architecture and updated models. The contractor shall maintain and extend these existing plug-ins to maintain compatibility with the current versions of these codes.

• SNAP also supports additional features through “feature” plug-ins. Feature plug-ins are also self-contained “jar” files. Feature plug-ins that are currently available for SNAP are: the “AVF” (auto-validation framework) plug-in and the “UQ” (uncertainty) plug-in. The AVF plug-in allows users to define validation and verification suites as well as code-to-code and code-to-data assessment cases. The UQ plug-in provides a framework for interfacing the analytical code plug-ins to the Design Analysis Kit for Optimizing and Terascale Applications (DAKOTA) code.

DAKOTA is a multilevel parallel object-oriented framework for design optimization, parameter estimation, uncertainty quantification, and sensitivity analysis. The contractor shall maintain and extend these existing feature plug-ins to maintain compatibility with the underlying support codes (DAKOTA for UQ plug-in, and the AVScript for the AVF plug-in.

• The contractor shall also support the development of any changes to the existing user interfaces for the SNAP code plug-ins as well as developing bug fixes and providing user support activities including tutorial video development and user manual documents. The contractor may also be asked to modify the source code for analytical codes that support SNAP features.

3.8 Litigation Support

The Contractor shall provide litigation support at hearings (mandatory or contested), and other similar processes. This effort includes, but is not limited to: providing written documentation of work performed during the subject technical reviews; providing expert testimony (written and oral) and reports; reviewing and analyzing expert testimony/reports provided by other parties in the litigation; and participate in evidentiary hearings.

4.0 TASK ORDER PLACEMENT PROCEDURES

Each task order under this IDIQ contract will be awarded on a competitive basis within the technical support service area vendor pool.

Under FAR 19.502-4 "Multiple-Award Contracts and Small business Set-Asides" in accordance with Section 1331 of Public Law 111-240 (15 U.S.C. 644(r)), Contracting Officers may, at their discretion, set aside orders for any of the small business concerns identified in 19.000(a)(3).

When setting aside orders for small business concerns, the specific small business program eligibility requirements identified in Part 19 apply.

5.0 PERSONNEL QUALIFICATIONS

All personnel performing work under this contract shall have pertinent technical experience by discipline and technical area. Experience in these disciplines and technical areas must be related to the design, construction, operation, maintenance, security, inspection and environmental review of nuclear power plants and non-nuclear facilities licensed by the NRC.

Emphasis is placed on experience that is related to safety, security and environmental impact where judgments are made as to whether applicable codes and federal regulations are being, or have been, implemented and/or followed. It is the responsibility of the Contractor to propose technical staff, employees, subcontractors or specialists who have the required educational background, experience, security clearance and/or access authorization or combination thereof, to meet both the technical and regulatory objectives of the work specified in the task order statement of work (SOW). The number of personnel required will vary during the course of the contract. The availability of qualified Contractor personnel who shall possess the minimum experience, educational background, and combination thereof, will be negotiated on each task order.

5.1 CONTRACTOR PROJECT MANAGER QUALIFICATIONS

The Contractor shall provide a responsible Project Manager who shall possess, at a minimum, a Bachelor's Degree in Engineering or Science and ten (10) years of direct project management experience in professional commercial nuclear support services. The Project Manager shall have experience that is related to safety, and/or security, and/or environmental impact where judgments are made as to whether applicable codes and federal regulations are being, or have been, implemented and/or followed. The Project Manager will have demonstrated capabilities to address highly complex issues. This individual shall also be considered as key personnel under the contract and serve as primary contact.

5.2 TECHNICAL DISCIPLINES AND SPECIALIZED TECHNICAL AREAS

The staffing plan of the technical personnel must at a minimum possess the education, qualifications and project experience for each technical support service area listed below:

The NRC encourages, offerors to include education, qualifications and project experience on Artificial Intelligence and Data Science as an emerging future skill needed as the paradigm of the NRC is being a modern risk informed regulator.

The minimum number of years listed below applies to the individual and not collective of individuals. The required experience is a collection of individuals and will be proposed in the staffing plan format found in Section L.

3.1 Thermal Hydraulics Research Support

Educational Requirements Required Experience Minimum Number of Years of Experience

B.S. in Computer Science or Engineering

Experience in Fortran and C/C++ 15 years

Experience in the latest (2018) Fortran code development practice, including Object-Oriented Programming, Parallel programming and MPI

15 years

Experience with TRACE, SNAP, and PARCS 3 years

3.2 Nuclear Fuel and Core Neutronics Support

Educational Requirements Required Experience Minimum…