ML20127E379
| ML20127E379 | |
| Person / Time | |
|---|---|
| Site: | Limerick, 05000000, 05000447, Atlantic Nuclear Power Plant |
| Issue date: | 12/10/1982 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Beckwith C NRC |
| Shared Package | |
| ML082170592 | List:
|
| References | |
| CON-FIN-A-3711, FOIA-84-243 NUDOCS 8505200057 | |
| Download: ML20127E379 (6) | |
Text
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-DISTRIBUTION December 10, 1982 HMXHIXXIIHg qw
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JCarter JFunches ME!;0RA!!DUM FOR: Charles Beckwith, Secretary Senior Contract Review Board FROM:
Harold R. Denton, Director Office of Nuclear Reactor Regulation
SUBJECT:
REQUEST FOR SENIOR CONTRACT REVIEW BOARD APPROVAL OF AflflRR TECHNICAL ASSISTANCE PROJECT - " SAFETY EVALUATION OF CORE-MELT ACCIDENTS: CASEUORK REVIEllS FOR LI!!ERICK, GESSAR, RIP" (FIN A3711)
Enclosed for SCRB approval are the Project Descriptive Summary, the draft Statement of Work, and the Interoffice concurrences from RES, HMSS, I&E, AE00, and Region IV for the subject project.
Concurrences from the other regional offices are assumed since the request for reply within the 10-day response period has elapsed.
If you need further information, please contact B. L. Grenier.
Please
-inform him of the date, time and location of the SCRB meeting to review this project so that we may have the appropriate !!RR people in attendance to answer any questions the SRCS may have.
Original signed by Jesse Pbnehes Harold R. Denton, Director Office of Nuclear Reactor Regulation
Enclosure:
As stated I
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PROJECT DESCRIPTIVE
SUMMARY
OFFICE: Office of Nuclear Reactor Regulation, DSI PROJECT TITLE: Safety Evaluation of Core-Melt Accidents:
Casework Reviews for Limerick, GESSAR, FNP 9
PROJECT MANAGER: James F. Meyer 492-4754 TYPE 0F CONTRACT: DOE Work Order CONTRACTOR: ~ D0E/Brookhaven National Laboratory Upton, NY (No suocontractors)
FIN N0: A-3711 FY Budget (K):
FY 82 FY 83 FY 84 FY 85 PRIOR:
-0*
OPERATING:
450 FOLLOW-0N:
520 50 SCOPE OF WORK:
Background
Consideration of severe accidents beyond the traditional design basis, including ' full core melt accidents, is an important part of NRC's overall safety assessment and therefore is becoming an important ingredient in specific licensing actions and in generic rulemaking proceedings such as that proposed in SECY-82-18.
The analyses provided under this contract will form the basis for the licensing decisions required on GESSAR-II FDA review (PRA portion), Limerick -
_ OL review (PRA portion), and Floating Nuclear Plant - ML - followup PRA review (as per NTOP/ML rule) with respect to severe accident consideration.
Work Requirements The work is organized into four major areas:
Task I - Severe-Accident Progression Analysis:
Reactor Systems / Containment Systems Loading and Failure Modes Task II - Radionuclide Release Assessment Task III - Consequence Analysis Task IV - Risk Assessment Summary
- See discussion under Prior Projects
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, BENEFIT:
This project, complemented by the other NRR related projects, assimilates all relevant. data 'being developed in RES and other programs (e.g. IDCOR, U.S. A. and foreign) and applies -the data to specific licensing actions. Contractor input and assistance will aid the DSI staff in the preparation of SERs and hearing testimony. Without this contractor assistance, the staff would be unable sto meet the review schedules and complete these licensing reviews in a time-frame compatible with the overall severe accident rulemaking.
USER NEED:
In addition to completing the specific licensing actions involved (Limerick, FNP and.GESSAR-II) analyses done under this contract provide generic information on three different containment designs which will provide the bases for the staff's
- positions for the severe accident rulemaking and the CP/ML rule " Licensing Requirements for Pending Applications for Construction Permits and Manufacturing License Applications."
PRIOR AND CURRENT RELATED PROJECTS:
Within NRR, work related to these licensing actions is divided between DST and DSI with DST responsible for the " front end" of the PRA review, i.e.
1 determination of the core melt probabilities (accident sequences and frequencies) and.DSI responsible for the 1) Containment Analysis and failure modes, 2) site Consequence Analysis (affect on source term) and 3) calculation of risk and risk reduction through various mitigation features. -
.The other related NRR projects (under separate FIN numbers) 'for these activities are listed in the attachment.
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. RES has a number of projects that provide results and experimental data in 1) phenomenological research on fuel and fission product behavior 2) behavior of existing systems and components in the severe accident environ-ment, 3) probability risk assessment methodology and other areas involving core damage which are assimilated into the analysis required under this project.
RES is also responsible for code development, including the MARCH-2, MATADOR, CRAC-II, C0RCON and CONTAIN codes, which in the long-term (by 1985) will be integrated into the MELCOR code, and which are being used in conducting these analyses.
INTERAGENCY COORDINATION AND INTEREST There are no other U. S. government programs (specfically DOE) that we are aware of. Work related to core melt accidents in LWRs is being perfomed in a number of European countries with advanced nuclear programs.
In some countries this work has progressed sufficiently (e.g., France and Gemany) so that it is becoming beneficial. for both the NRC and the French _and German authorities to-exchange-infomaton which is used to either confirm each other's findings or in some areas te complement them.
These exchanges are taking place via NRC's participatior, in the NEA/CSNI activities or through bilateral exchanges.
For example,-the analyses done by the French to evaluate the containment response of their PWRs to core melt accidents using their own developed code PARE 0 have been used to compare the analysis using the MARCH Code described in this contract.
JUSTIFICATION FOR SOURCE SELECTED AND DISCUSSION OF ALTERNATIVES 1.
Continuity and unique background BNL can provide us with the required technical support because they have been intimately involved with severe accident (degraded core / melt) analysis and assessment for a large variety of nuclear power plants for the past eight (8) years. This involvement has led to a unique level of expertise in the areas of severe accident phenomenology and accident progressions through the reactor and containment systems.
This backgrour.d makes BNL the most appropriate source for these services.
BNL also has expertise in other areas supportive of this effort e.g.,
(1) Probabilistic Risk Assessment, (2) Structual Analysis, and (3) RES -
research programs.
(2) Conflict of Interest Since this project involves review of applicant submittals, which are being compiled by the limited number of commercials firms expert in this area, DOE /BNL, can perform this work without a conflict of interest.
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. No suitable alternatives exist for this particular project, although the overall NRR program has been structured such that other DOE labs and commercial firms
.and universities are used'for those projects of a more generic nature which are not directly related to the review of applicant submittals.
Since the codes and PRA methodology are developed at SNL, using BNL to conduct the analyses provides an additional independent assessment of the SNL program.
SUGGESTED NRC 0FFICES FOR COORDINATION:
This project has been coordinated with RES, I&E, NMSS and the regional offices.
Concurrence, for non-duplication of effort, has been received from all affected
. offices.
E.
o, ATTACHMENT DIVISION OF SYSTEMS INTEGRATION o A-3712 BNL Safety Evaluation of Core-Melt Accidents:
Indian Point -
0.R., and Zion - 0.R. (New replaces A-3392 of FY 82) o A-3705 BNL Safety Evaluation of Core-Melt Accidents: CESSAR - F.D. A.,
W Standard Plant - F.D.A.(New) o A-3706 BNL Safety Evaluation of Core-Melt Accidents: MARK-I Containments (New)
-B-8634 RFPA Severe Accident Core / Vessel / Containment Interactions o B-8635 83-093 (New)
B-8625 RFPA Severe Accident Consequences Mitigation 0: B-8626 83-092 (New)
B-6836 Energetic Thermal Interactions and Coolant Flow Phenomena PURDUE associated with Nuclear Reactor Concepts (Ends 1/22/83) o B-8619 o-B-6823 ASAI Core Melt Materials Interations Evaluations (Ends 4/16/83) o A-3389 BNL Design Basis for Hydrogen Control ' Systems (Ends 12/31/82)
Division of Safety Technology o A-3366 BNL ReviewofGESSAR-IIPRAReview(Ends 6/11/84) o A-3393 BNL Limerick Risk Study Reviews (Ends 8/31/83) o A-1125 Sandia Review of Detailed Reliability Analysis for Zion Units 1 and 2 and Indian Point Units 2 and 3 (Ends 2/31/83)