ML18131A262

Task Order No. 31310018F0009 to Interagency Agreement No. NRC-HQ-25-14-D-0005

ML18131A262
Person / Time
Issue date:	05/11/2018
From:	Jeffrey Mitchell Acquisition Management Division
To:	Whitley C Sandia
References
NRC-HQ-25-14-D-0005
Download: ML18131A262 (12)

Text

INTERAGENCY AGREEMENT

1. IAA NO.

PAGE OF

2. ORDER NO.

3. REQUISITION NO.

4. SOLICITATION NO.

5. EFFECTIVE DATE

6. AWARD DATE

7. PERIOD OF PERFORMANCE 31310018F0009 RES-18-0077 04/23/2018 04/23/2018 04/23/2018 TO 05/01/2019 3

1

8. SERVICING AGENCY

9. DELIVER TO POC TELEPHONE NO.

Christine Whitley 505-844-3811 ALBUQUERQUESANDIA NATL LAB DOENNSASFO CONTRACTING OFFICER PO BOX 5400 ALBUQUERQUE NM 87185-5400 MARK FUHRMANN US NUCLEAR REGULATORY COMMISSION 11555 ROCKVILLE PIKE ROCKVILLE MD 20852 ALC:

DUNS: 155505027 +4:

10. REQUESTING AGENCY POC TELEPHONE NO.

11. INVOICE OFFICE Jeffrey R. Mitchell ACQUISITION MANAGEMENT DIVISION US NUCLEAR REGULATORY COMMISSION ONE WHITE FLINT NORTH 11555 ROCKVILLE PIKE ROCKVILLE MD 20852-2738 US NUCLEAR REGULATORY COMMISSION ONE WHITE FLINT NORTH 11555 ROCKVILLE PIKE MAILSTOP O3-E17A ROCKVILLE MD 20852-2738 301-415-5074 ALC: 31000001 DUNS: 040535809 +4:

13. LEGISLATIVE AUTHORITY

12. ISSUING OFFICE

14. PROJECT ID

15. PROJECT TITLE US NRC - HQ ACQUISITION MANAGEMENT DIVISION MAIL STOP TWFN-8E06M WASHINGTON DC 20555-0001 Energy Reorganization Act of 1974 MELCOR MODELING OF ACCIDENT BASED RELEASES FROM A EWA

16. ACCOUNTING DATA 2018-X0200-REIM-60-60D002-60B207-1304-38-R-838-253D-DOE-GNEPTIE-31-38-R-838-1304 17.

ITEM NO.

22.

AMOUNT 21.

UNIT PRICE 20.

UNIT 19.

QUANTITY 18.

SUPPLIES/SERVICES The NRC and the DOE Sandia National Laboratory (SNL) hereby enter into this Task Order 31310018F0009 under Agreement, NRC-HQ-25-14-D-0005 for the project entitled, "MELCOR Modeling of Accident Based Releases from a Nuclear Fuel Reprocessing Facility".

The performance period for this agreement shall commence on April 23, 2018 and will expire on May 1, 2019.

Consideration and Obligations:

Continued...

23. PAYMENT PROVISIONS

24. TOTAL AMOUNT 26a. SIGNATURE OF GOVERNMENT REPRESENTATIVE (REQUESTING) 26b. CONTRACTING OFFICER 26c. DATE 25a. SIGNATURE OF GOVERNMENT REPRESENTATIVE (SERVICING) 25b. NAME AND TITLE 25c. DATE JEFFREY R. MITCHELL

$120,000.00 05/11/18

3 IAA NO PAGE OF 3

ORDER NO 31310018F0009 ALC: 31000001 DUNS: 040535809 TAS: 31X0200.320 The total amount of award: $207,686.00. The obligation for this award is shown in box 24.

1 STATEMENT OF WORK (SOW)

NRC Agreement Number NRC Agreement Modification Number NRC Task Order Number (If Applicable)

NRC Task Order Modification Number (If Applicable)

NRC-HQ-25-14-D-0005 31310018F0009 Project Title MELCOR Modeling of Accident Based Releases from a Nuclear Fuel Reprocessing Facility Job Code Number B&R Number Servicing Agency Sandia National Laboratories NRC Requisitioning Office Period of Performance RES April 23, 2018 to May 1, 2019 NRC Form 187, Contract Security and Classification Requirements Applicable Not Applicable Involves Proprietary Information Involves Sensitive Unclassified Non Fee-Recoverable Fee-Recoverable (If checked, complete all applicable sections below)

Docket Number (If Fee-Recoverable/Applicable)

Inspection Report Number (If Fee Recoverable/Applicable)

Technical Assignment Control Number (If Fee-Recoverable/Applicable)

Technical Assignment Control Number Description (If Fee-Recoverable/Applicable)

3 STATEMENT OF WORK (SOW)

Contents 1.0

Background

2.0 Objective 3.0 Scope of Work/Tasks 4.0 List of Deliverables 5.0 Estimated Labor Categories, Key Personnel and Levels of Effort 5.1 Labor Categories, Requirements and Key Personnel 5.2 Level-of-Effort (in hours) 6.0 Certification and License Requirements 7.0 Meetings and Travel 8.0 Reporting Requirements 8.1 Monthly Letter Status Report (MLSR) 8.2 Reports 9.0 Required Materials, Facilities, Hardware/Software 10.0 Applicable Publications (Current Editions) 11.0 Data Rights

4 DESCRIPTION/SPECIFICATIONS/WORK STATEMENT

1.0 BACKGROUND

In earlier work, the construction of a MELCOR model of a nuclear fuel reprocessing plant was performed by Clinton Shaffer for Sandia National Laboratories (SNL) under sponsorship by the U.S. Nuclear Regulatory Commission (NRC). The results of this project were contained in the draft report entitled Demonstration of MELCOR Analyses of a Nuclear Fuel Reprocessing Plant (Shaffer, 2016). The project demonstrated analytical techniques needed to apply the MELCOR code in safety assessments of any future, spent nuclear fuel reprocessing facility built in the United States.

Reprocessing plants contain both chemical and nuclear processes each with their own hazards and in many processes a combination of these hazards. Analyzing these hazards requires the simulation of operational and accident-driven airflows throughout the facility and to track the transport of contaminants from their point of release to their final deposition or release from the facility into the environment. This type of facility is designed with pressure zones so that the air flows from the least radioactive (or non-radioactive) areas to the most radioactive areas and then through a filtration process to clean the air before it is reintroduced into the environment via a tall stack. The NRC established a previous agreement with Sandia National Laboratory (SNL) to create a MELCOR code, which contains the necessary physics and engineering models to simulate airflow and fission product transport and deposition, including filtration of the airflows.

The construction of a MELCOR model of a nuclear fuel reprocessing plant was initially performed by Clinton Shaffer for SNL, and the results of this project were contained in the draft report entitled: Demonstration of MELCOR Analyses of a Nuclear Fuel Reprocessing Plant (Shaffer, 2016). The project demonstrated analytical techniques needed to apply the MELCOR code in safety assessments of any future, spent nuclear fuel reprocessing facility built in the United States.

For the basis of the facility design, the Barnwell Nuclear Fuel Plant (BNFP) was chosen for this study. The Barnwell plant was constructed in the early 1970s to process spent nuclear fuel from commercial power reactors, but the now decommissioned plant was never used for that purpose.

5 For these analyses, MELCOR 2.1 Version RL_NL_8152 was used. A key challenge for using the Barnwell plant in the MELCOR code setting was the development of the control volumes needed to model the airflows and pressures to match the Barnwell facility design and/or operational flow and pressure data for the specific facility. Once this was done, example explosion and fire accidents were simulated to demonstrate the models responses to these types of accident source terms.

Due to a large degree of uncertainty in the accident source terms, fission product releases from processing tanks and piping were simply sourced into the MELCOR calculations in trace amounts to estimate conservative leak path factors (LPF). This task order with SNL would allow more realistic source terms to be modelled with a variety of source terms, accident energies and accident sequences.

2.0 OBJECTIVE The objective of this project is to assess the impact of accidents at spent nuclear fuel reprocessing facilities due to explosions and/or fires related directly to nuclear fuel reprocessing.

This includes an evaluation of the applicability of MELCOR for assessing accident consequences at nuclear fuel reprocessing facilities. This project also includes an evaluation of various leak pathways and the LPF for various scenarios.

3.0 SCOPE OF WORK/TASKS SNL shall provide all resources necessary to accomplish the tasks and deliverables described in this Statement of Work (SOW). The laboratory shall provide a final report that describes the modelling approach and results for a set of accident scenarios. The report shall include a summary, discussion and evaluation of calculated LPFs, as well as an evaluation of applicability of MELCOR to reprocessing facilities.

SNL shall perform MELCOR modelling using the model parameters, flow rates, and room volumes developed in an earlier task order (see Demonstration MELCOR Analyses of a Nuclear Fuel Reprocessing Plant, C. Shaffer, 2016) for a spent nuclear fuel reprocessing facility. The model parameters may be refined and expanded by SNL, however, SNL shall clearly cite the adjusted parameters in the final report.

Task 1-Develop Accident Scenarios SNL shall develop a set of accidents (i.e., scenarios) to include a realistic range of energies, realistic masses of chemicals and radionuclides (source terms), and vapor properties. These

6 scenarios shall be described in a letter report. It is anticipated that a set of three energies for each of three mass/activity source terms will be used (plus a fire/explosion combination); for a total of 10 scenarios. These accidents shall include the following:

Chemical explosions (especially red-oil explosions) that involve radionuclides Fires that involve radionuclides A combination of explosion and fire Task 2-Perform Accident and Release Modelling Using the previously developed MELCOR model of the Barnwell reprocessing facility, task 2 shall focus on a set of accidents that result in damage to the facility and on the potential release of radionuclides to the environment. SNL shall model each type of event, using realistic chemical and radionuclide source terms as described in task 1. These events may be obtained from NUREG/CR-7168 and NUREG/CR-7232 which is available on the NRCs public website at:

https://www.nrc.gov/reading-rm/doc-collections/nuregs/contract/. It also may be possible to obtain information from existing European reprocessing facilities. For the explosion scenarios, SNL shall model a variety of energies associated with the explosions that fall within estimated ranges of actual events (e.g. 50 to 700 MJ), which have taken place in reprocessing facilities.

When mutually agreed upon with the COR Modelling of aerosols generated during the events shall include distributions of particle sizes such as those presented by Gelband et al, (SAND2013-9268C) and shall include a combined explosion/fire scenario. The use of other literature based on basic principle approaches to generating parameters for input to the models is strongly encouraged.

While task 2 shall focus on explosions and fires, SNL shall discuss other types of accidents at reprocessing facilities such as criticality events, leaks, earthquake impacts as appropriate in the context of potential off-site releases. SNL shall submit a Draft Report and then a Final Report, incorporating NRC comments. The report shall contain the following:

a description of each of the 10 accident scenario a description of model results and facility impacts from each scenario estimates of the degree of damage to and contamination of the facility an discussion of the pathways of contaminant transport quantities of radionuclides released from the facility a discussion of the Leak Path Factor (LPF)

7 SNL shall use the best MELCOR modelling practices as discussed in Louie and Humphries, 2017 (SAND2017-3200). A comparison of LPF from modelling to that of the DOE Handbook (DOE-HDBK-3010-94) shall be made.

The Final Report shall also reference selection, modeling, and results of the analysis of releases from reprocessing accidents. Results and descriptions from earlier work (i.e., Shaffer, 2016) shall be integrated into the report. SNL shall use NRCs Word template for NUREG/CR reports in submitting the Final Report. The COR will provide the NRC Word template to SNL subsequent to award.

4.0 LIST OF DELIVERABLES SNL shall submit all deliverables referenced in the table below electronically to the COR.

Unless otherwise directed by the COR or the CO, SNL must provide all deliverables except the Monthly Letter Status Report (MLSR) as draft products. The COR will review all draft deliverables and provide comments back to SNL. SNL shall revise the draft deliverable based on the comments provided by the COR, and then resubmit the final version of the deliverable to the COR. More than one round of drafts may be needed if SNL does not successfully incorporate the CORs comments on the previous draft. When mutually agreed upon between SNL and the COR, SNL may submit preliminary or partial drafts to the COR for the purpose of helping the COR to gauge SNLs understanding of the particular work requirement.

Task Number Deliverable Deliverable Format Due Date 1

Accident Scenario Letter Report Microsoft Word No Later Than (NLT) 60 calendar days from to task order award 2

Draft Report Microsoft Word NLT 9 months from to task order award 2

Final Report Microsoft Word or Adobe PDF NLT 30 calendar days from receipt of NRC comments on the Draft Report All Monthly Letter Status Report (MLSR)

Microsoft Word or Adobe PDF NLT than the 20th of the following month

8 5.0 ESTIMATED LABOR CATEGORIES, KEY PERSONNEL AND LEVELS OF EFFORT 5.1 Labor Categories, Requirements and Key Personnel. Personnel working under this agreement/order shall meet the minimum requirements for experience and education, as follows:

Labor Category Position Minimum Requirements Key Personnel Key Staff Ph. D., Nuclear Engineering or similar Key Staff Ph. D., Nuclear Engineering or similar 6.0 CERTIFICATION AND LICENSE REQUIREMENTS Not Applicable 7.0 MEETINGS AND TRAVEL Not Applicable 8.0 REPORTING REQUIREMENT SNL is responsible for structuring the deliverables to current NRC standards. SNL shall submit deliverables free of spelling and grammatical errors and shall conform to the requirements stated in this SOW.

8.1 Monthly Letter Status Report (MLSR)

SNL shall provide a MLSR which consists of a technical progress report and financial status report. This report will be used by the sponsoring agency to assess the adequacy of the resources utilized by the servicing agency to accomplish the work contained in this SOW and to provide status of the servicing agency progress in achieving tasks and producing deliverables.

The report shall include agreement/order summary information, work completed during the specified period, milestone schedule information, problem identification and resolution, and staff hour summary. Copies must be sent to the COR and AMD at ContractsPOT.Resource@nrc.gov.

The MLSR shall include the following: agreement number; task order number; title of the project; project period of performance; task order period of performance; CORs name, telephone

9 number, and e-mail address; full name and address of the performing organization; principal investigator's name, telephone number, and e-mail address; and reporting period.

8.2 Reports See Section 4.0, List of Deliverables.

Acceptance Criteria for Task 2 Draft Report: SNL shall clearly describe the accident scenarios modeled, the modeling process, and results and interpretation. SNL shall submit the report in a Microsoft Word format.

Acceptance Criteria for Task 2 Final Report: SNL shall address all NRC comments and shall follow the format, content, and schedule described in this SOW.

9.0 REQUIRED MATERIALS, FACILITIES, HARDWARE/SOFTWARE SNL shall use the latest and most appropriate version of the MELCOR code to perform the modeling described in this SOW.

10.0 APPLICABLE PUBLICATIONS (CURRENT EDITIONS)

SNL shall comply with NRCs NUREG report template, which the COR will provide to SNL subsequent to award.

11.0 DATA RIGHTS The NRC shall have unlimited rights to and ownership of all deliverables provided under this agreement/order, including reports, recommendations, briefings, work plans and all other deliverables. All documents and materials, to include the source codes of any software, produced under this agreement/order are the property of the NRC with all rights and privileges of ownership/copyright belonging exclusively to the NRC. These documents and materials may not be used or sold by the servicing agency without prior written authorization from the CO. All materials supplied to the NRC shall be the sole property of the NRC and may not be used for any other purpose. This right does not abrogate any other Government rights.