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MAC *IC M Igg US. NUCLEAR E.EGULATO.4Y COMMISSION oave ce sww4sn
- ' 84 " A December 3, 1982
( } PROJECT AND BUDGET PROPOSAL FOR NRC WORK gg new O nevisiO~ so KOJECT TITLE *iN Nvwe g a Safety Evaluation of Core-Melt Accidents: Indian Point- A-3712 OR and Zion-OR saceAa~vuesa NEC OF FICE Nuclear Reactor Regulation 20-19-10-11-3 c:a con 7a ACTOa Associated Universities, Inc. GONT R ACTop ACCoyNT nuusEm Brookhaven National Laboratorv New SITE ooteAaNuussa UptOn, New York COGNIZANT PE RSONNE L ORGANIZATION [ FT5 PHONE NUMgER PE RIOD OF PE RFORMANCE NRC PROJECT MAN AGER i STARTING OATE J. Meyer nrc/nsB I
492-4754 12/10/82 OTHER NRC TECHNICAL STAFF COMPLETION DATE 07/31/84 OOE PROJECT M ANAGER Brookhaven C 1. e c . c David Schweller Area Office 666-3424 .h .*/.57
. w 5"i. Y CONTRACTOR-PROJECT MAN AGER H.J.C. KOuts 666-2815 .' .l.jdl2{I.E;'$ J-C W.Y. Kato .
666-2444 :. 2. - . , ; :- .7 PRINCIPA L INV ESTIGA TORl58 * ^- ' P 'Y l
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Other Direct fGreceol I I l I TOTAL DIRECT STAFP YEARS COTTPROPOSAL l t i Direct samries Merecisi and Serv.ces IE acevoing ACPI l 1 i i ACP Swooort
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,, 1983 1 * * " "
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is e" 0505230213 041002 -
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Safety Evaluation of Core-Melt Accidents:
Project
Title:
Indian Point-OR and Zion-OR p. 3 PROJECT DESCRIPTION a.- OBJECTIVE OF PROPOSED WORK
"(1) 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. Also the consideration of features to mitigate the consequences of core melt accidents for nuclear facilities continues to be a major specific licensing activity. It is very important that the large amount of technical information available and being developed by, for example, NRC/RES in this area be appropriately assimilated, codified and evaluated in a way that is directly applicable to licensing needs. These needs are in three major areas.
First, there is a need to better understand the progression of core melt accident '
' sequences up to and including associated core melt related phenomenology-and-the implementation of these processes (and their uncertainties) into an overall assess-ment of containment loading and failure modes. The impact of mitigation strategies on containment loading and fsilure modes must also be factored into the assessment.
Second, based on the containment loading histories, there is a need to determine the radiological source tera suspended in the containment, the effects on engineered safety features (ESFs) and mitigation features of this source term and finally, the release characteristics of this source term following containment failure. -
Third, there is a need for an overall capability to assess the radiological conse-quences as a function of the assumptions regarding accident sequences, pheno nnology and mitigation hardware. These radiological consequences must be further analyzed in a licensing context with a full appreciation of its regulatory implicatio-2s.
(2) Obj ective F
The objective of the activities described in this proposal is to meet the above needs.
The scope of this work will be limited to addressing immediate NRC/NRR licensing con-corns using the state-of-the-art codes and the analyses and experimental data devel-oped from NRC/RES and other It&D programs. The scope will also include review and evaluation of licensing submittals and other pertinent information dealing with the subjects described below.
The analyses provided under this contract will help form the basis for positions taken by the NRC staff as related to questions raised by the Commission, hearing board and intervenors as part of the Indian Point Hearing. Also the analyses will provide input to the NRC staff's review of the Indian Point Probabilistic Safety
, Study (IPPSS) and the Zion Probabilistic Safety Study (ZPSS).
(See Continuation Sheet)
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Safety Evaluation of Core-Melt Accidents:
Project
Title:
Indian Point-OR and Zion-OR p. 5
- c. WORK REOUIREMENTS (Continued) on containment and mitigation features of RES, IDCOR, DOE and foreign programs and relate the information gathered to MARCH predictions. This subtask supports directly the efforts in Sub-task.I.D. Starting December 15, 1982, a letter report summa-rizing subtask status shall be provided every three months until the end of the contract. (Note: Subtask I.B of FIN No. A-3711 provides the overall evaluation in this area; the subtask above is limited to specific Indian Point and/or Zion items. This re-quired letter report input will be combined with the letter re-port required in FIN No. A-3711).
Completion Date: 7/15/84 Subtask I.C - MARCH /MELCOR Code Maintenance and Development
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BNL will closely follow RES's MARCH-2 and MELCOR development pro-grams. BNL will also follow the development of similar accident analysis codes (e.g., INCORE), both foreign and domestic, and in addition, specialty codes such as CORCON and CONTAIN. BNL will maintain current MARCH code capability with modifications as appropriate to the reactor type under consideration and the con-tainment modifications (mitigation features) being addressed.
This subtask supports directly the efforts in Subtask I.D. -
Starting December 15, 1982, a letter report summarizing subtask status shall be provided every three months until the end of con-tract. (Note: Subtask I.C of FIN No. A-3711 provides the over-all evaluation in this area; the subtask above is limited to specific Indian Point and/or Zion items. This* required letter report input will be combined with the letter report required in FIN No. A-3711) .
Completion Date: 7/15/84 Subtask I.D - Accident Analysis: Indian Point / Zion BNL will analyze the accident progressions up to and including containment failure characterizations based on accident sequences and containment modifications (if any) supplied by the NRC staff.
Particular attention will be given to those containment failure parameters that are input to the consequence analysis (CRAC code).
Completion Dates:
I.D.1 Complete analyses of accident progressions for Indian Point by performing analyses of Event V and basemat penetration: 12/15/82 (See Continuation Sheet) u._
3 Safety Evaluation of Core-Melt Accidents:
Project
Title:
Indian Point-OR and Zion-OR p. 7
- c. WORK REOUIREMENTS (Continued)
' project. (Note: . Subtask II.A of FIN No. A-3711 provides the overall evaluation in this area; the subtask above is limited to specific Indian Point and/or Zion items. This required letter report input will be combined with the letter report required in FIN No. A-3711).
Completion Date: 7/15/84 Subtask II.B - Data Acquisition: Code Development BNL will maintain close contact with RES development of MATADOR, NAUA, CONTAIN and MELCOR. BNL will provide assessments of prog-ress to date and recommendations for the course of further de-velopment. ' BNL will also follow EPRI, IDCOR and foreign activi-ties in this area. This subtask supports directly the efforts in Subtask II.C. Starting December 15, 1982, a letter report summarising subtask status will be provided every three months until the end of the project. (Note: Subtask II.B of FIN No.
A-3711 provides the overall evaluation in this area; the subtask above is limited to specific Indian Point and/or Zion items.
This required letter report input will be combined with the let-ter report required in FIN No. A-3711).
Completion Date: 7/15/84 Subtask II.C - Accident Analysis: Indian Point and Zion For each reactor type under consideration, BNL will perfor:s analyses' of the release fractions and other containment failure parameters important in the subsequent consequence analysis.
This effort is closely coupled to Subtask I.D and will be per-formed concurrent with Subtask I.D.
Completion Dates:
II.C.1 Complete analyses of radionuclide taleases for Indian Point by performing analysis of Event V at.d basemat penetratica: 12/15/82 II.C.2 Assess impact of source term modifications (in particu-lar RES FIN No. B-6747) on radionuclide release analyses performed for Indian Point and Zion: 3/15/83 Subtask II.D - Accident Assessment: Indian Point and Zion BNL will review PRA submittals in the areas within the scope of Task II by utilities / vendors. BNL will generate questions
, to the utilities / vendors based on this review. BNL will (See Continuation Sheet)
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Safety Evaluation of Core-Meit Accidents:
Project
Title:
Indian Point-OR and Zion-OR p. 9 l
j c. WORK REOUIREMENTS (Continued)
I
( Subcask III.B - Accident Analysis BNL will perform CRAC analyses consistent with the MARCH / CORRAL analyses performed in Subtask I.D and II.C. BNL will determine changes in risk based on inclusion of aitigation (or preven-tion) features and on variations due to accident progression uncertainties. (Note Milestone in II.C).
Completion Date: 4/15/84 Task IV - Risk Assessment Summary (Integration of Tasks I. II and III) l' Estimated Level of Ef fort in FY83: 3 MM Completion Date 7/15/84 l Estimated Level of Effort in FY84: 3 MM
. SubtaskE.A - Integration _ conemi-ne heriv __. . _ _ _ _ . _ . . . . _
For the reactors being considered in this project, BNL will gen-erste a containment matrix, which shows the relacionship of dam-age states (provided by the NRC staff) to release categories, and defend each element of the matrix based on analyses and as-sessment provided in Task I & II. BNL will determine estimates of uncertainties for each containment matrix element (to be used in Subcask IV.C) and compare this matrix to that developed by -
the utility / vendor, if appropriate.
Completion Dates:
IV.A.1 Zion Preliminary: 4/15/83 IV.A.2 Indian Point Preliminary: 1/15/83 IV.A.3 Zion Final 4/15/84 IV . A . 4 Indian Point Final: 4/15/84 Subtask IV.B - Integration: Impact on Risk BNL will present results of analyses and assessments in Task I, II and III in terms of risk values '(including CCDFs) and changes in risk values due to changes in containment designs (mitigation features) or changes in damage state probabilities.
Completion Dates:
IV.B.1 Letter Report review of IPPSS: 4/15/83 IV . B .2 Letter Report review of ZPSS: 5/15/83 IV.B.3 Indian Point and Zion Final Report (NUREG/CR): 7/15/84 (See Continuation Sheet) w . _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _- . _ _ _ _ _ _ _ _ _ _ _
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W Safety Evaluation of Core-Melt Accidents:
Project Title Indian Point-OR and Zion-OR p. 11 l~ d. REPORTING REOUIREMENTS (Continued)
- The total amount of funda expended (costed) during the period and total cumulative to date smider the following categories: Labor-related costs, l Computer services, Travel.. Subcontracts, Equipment and Total;
- The total snount of funds expended during the period (costed) and cumulative to date for each task, i.e., each plant under each Project.
- e. MEETINGS AND TRAVEL BNL staff will participate in several asetings at the NRC Headquarters (one one-day l
aseting each quarter in Bethesda to discuss perforesace and work progress) and at other locations (one one-day meeting each quarter in Bethesda or at licensee /sppli-cant headquarters with licensee / applicant and NRC staff is anticipated) to obtain source asterial for this program. BNL staff will attend hearings (two-week travel-status for BNL staff at the Indian Point Hearings is anticipated); also BNL staff may visit other laboratories, orptitutions_and_ participation.at_ prof essional_aaet.-
[ ~ - ~" ings' ('attenTance at two topical professional meetings on relevant topics will be l planned and budgeted).
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- 1. f. NRC-FURNISHED MATERIALS The NRC will provide any documentation relevant to the above tasks which is sub-mitted by licensees during the course of this project.
- g. DESCRIPTION OF ANY FOLLOW-ON EFFORTS
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Not Applicable.
,h. RELATIONSHIP TO OTHER PROJECTS This project is related to a number of other NRC projects. Specifically, BNL will
- coordinate (Subtask I.A) phenomenological input from FIN No. B-8634 and provide cognizance of the phenomenological studies of NRC/RES, IDC0K and foreign programs.
BNL will relate the information gathered from these prograns to MARCH code predic-tions. BNL will also coordinate (Subtask I.8) engineering mitigation feature in-put from FIN No. B-8625. BNL will provide cognisance of engineering studies on con-tainment and mitigation features of NRC/RES, IDCOR, DOE and foreign programs and relate the information gathered to potential contaitunent building failure modes.
BNL will also assess the impact of source term modifications (in particular RES FIN No. 5-6747) on radionuclide release analyses performed for Indian Point and l Zion (Subtask II.C). Finally, some of the activities covered under this project, l (namely, FIN No. 3712) although limited specifically to Indian Point and/or Zion
( applications, are also relevant to FIN No. A-3711. In particular, Subtasks I.A, l 1.3, I.C II.A, II.B and III.A have parallel objectives in the two FIN Nos. A-3711 and A-3712 but with application to different reactors. The overall evaluation in these areas will be carried out under FIN No. A-3711 and will be combined with the l work done in these subtasks in FIN No. A-3712.
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'l BROOKHAVEN NATIONAL LABORATORY
.,J,..sa ASSOCIATED UNIVERSITIES. INC.
Upton. Long isfond. New York 11973 (516) 282s Offico of the Director FTS 666' 3317 December 15, 1982 Mr. David Schweller, Manager Brookhaven Area Office U. S. Department of Energy Upton, New York 11973
Dear Mr. Schweller:
Enclosed is one copy of a proposal to the flucicar Regulatory Commission. - - - - - -
entitled, " Safety Evaluation of Core-Melt Accidents: Indian Point-OR and Zion-OR," FIN A-3712, being submitted for your review and approval. The proposal is being submitted in response to a request from NRC dated November 30, 1982. Two copies have been sent to Mr. J. Maher, Department of Energy, one copy has been sent to Mr. B. L. Grenier, Nuclear Regulatory Commission, and two copies have been sent to:
Mrs. Sybil Bo'yd, Program Assistant Division of Systems Integr.1 tion Mail Stop P-1102 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 If there are any questions regarding the docume'nt, please call the prin-cipal investigator or Mr. A. J. Romano, FTS 666-4024,' Department Administrator for the Department of Nucicar Energy.
, Sincerely yours,-
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'. H. C. Grahn Assistant Director for Financial Planning Enclosure v.
cc: S. Boyd (2)
B. L. Cronier J. Maher (2) -
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NRR TECHNICAL ASSISTAfiCE PROGRAM
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