ML20101C732
| ML20101C732 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000470, 05000601 |
| Issue date: | 02/28/1983 |
| From: | Kato W, Kouts H, Schweller D BROOKHAVEN NATIONAL LABORATORY, ENERGY, DEPT. OF |
| To: | Meyer J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20101C698 | List: |
| References | |
| CON-FIN-A-3705, FOIA-84-335 NUDOCS 8412210174 | |
| Download: ML20101C732 (19) | |
Text
.
NRC'F Cpv 189 U.S NLC.E AR R EGULATCA Y CO.tMISSION O AT E G 8 8 88 08 0 5 A *.
(3 8 " '
i February 28, 1983
) PROJECT AND BUDGET PROPOSAL FOR NRC WORK g.NEw i
C REvtSiON NC sa0JE0*TLE
, sin w vgge Safety Evaluation of Core-Melt Accidents:
CESSAR-FDA, A-3705 Westinghouse Standard Plant-FDA i N AC S&a NUVBf 4 NRC OFFICE Nuclear Reactor Regulation j20-19-40-41-3 coE ceNTaActea Associated Universities, InC.
CONTR ACTOR ACCOUNT suusER Brookhaven National Laboratorv New SITE OCE S&R NVY8E9 Upton, New York COGNIZANT PERSONNEL l
O R G ANIZ ATI ON f
FTS PHONE NUMPER PE RICO O F PE R FORMA NCE NRC PQ0aECT M AN AGER STARTING DATE J. Meyer DSI/RSB 492-4752 04/01/83 GTH ER NRC TECHNIC AL STAFF i
COMPLETION DATE l
08/31/85 Est.
CCE PROJECT M AN AGER l
Brookhaven j
',5fy.yv +0E i ~ JI.3 IN~3Nf i
Area Office i
666-3424 David Schweller 7, @hly["gaWaW CONTR ACTOR-PR OJECT M AN AGER H. J. C. Kouts 666-2615 W. Yc Kato 666-2444
-$Mdl.$?$
PRINC:P A L INV ESTIGATOR(S) j EMN k*iW[g, %Ns@f~,i I
W. T. Pratt i
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ST A F F Y E AR S O F E F F O R T r Roun.f ra ncJrest tente ora 3eart IFY j Qgg FY }qg4
!FY 1985 IFY
!FY Direct Scier tific:Technicat l
l 1.0 2.3 i
2.0 l
l Other Direct iGr oed!
I l
0.2 0.4 I 0.3 TOTAL DIRECT STAFF YEARS 1.2 2.7 2.3 f
COST PROPOSAL l
l l
j Detect Saiaries i
58 137 131 i
Materrai and Serv.ces.E ncNcs *g ACP)
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8 7
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ACP Swooort 1
2 1
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i Swocontracts 0
0 0
F ore'on 0
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O T,avet Empenses Oomestic 5
10 1
12 i
Incirect Laoor Co5t5 (Departmental Acministration) 7 15 14 Orwer tscec.tv/
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I i
1 l
2 l
2 General and Administrative (
44 % of modified direct cost) l l
33 76 73 4
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250 240 CAPITAL EOU6PVENT B412210174 840621 I
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TOTAL PROJECT COST l 110 250 240 i v o.3
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Safety Evaluation,of Core-Me'lt Accidents:
. Project
Title:
CESSAR-FDA, Westinghouse Standard Plant-FDA
- p. 3 PROJECT DESCRIPTION a '. OBJECTIVE OF PROPOSED WORK (1)
Eackground
. 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 or 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 conteinment loading and failure modes must also be factored into the assessment.
Second, based on the containment loading histories, there is a need to determine the radiological source term suspended in the containment, the effects on engineered safety features (E.S.Fs) 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, phenomenology and mitigation hardware. These radiological consequences must be further analyzed in a licensing context with a full appreciation of its regulatory implications.
(2) Objective 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-cerns using the state-of-the-art codes and the analyses and experimental data de-veloped from NRC/RES and other R&D programs. The scope also includes review and evaluation of licensee submittals and other pertinent information dealing with the subjects described below.
The analyses provided under this contract will form the basis for the licensing de-cisions required on CESSAR-System 80 FDA review (PRA portion), and the Westinghouse Standard Plant, FDA (PRA portion) with respect to severe accident considerations.
The extensive analysis and assessment to be performed, code capability to be de-veloped and experience to be gained under FIN A-3711 has been taken into account when developing this proposal.
(See Continuation Sheet)
Safety Evaluation of Core-Melt Accidents:.
. Project
Title:
CESSAR-FDA, Westinghouse Standard Plant-FDA
- p. 5.
c.
WORK REQUIREMENTS (Continue.d)
Subtask I.C - MARCH /MELCOR Code Maintenance and Development BNL will closely follow RES's MARCH-2 and MELCOR development programs. BNL will follow the development of similar accident analysis codes, e.g., INCORE, foreign and domestic and specialty codes, e.g., CORCON, CONTAIN.
BNL will maintain current MARCH code capability with modifications as appropriate to the reactor type under consideration and the containment modifications (mit-igation features) being addressed.
This subtask supports di-rectly the efforts in Subtask I.D.
Starting March 15, 1983,-a letter report summarizing subtask status will be provided every three months until the end of the project.
(Note:
Subtask I.C.
of FIN No. A-3711 provides the overall evaluation in this area; the subtask above is limited to specific W and/or CESSAR items.
This required letter report input will be combined with the letter report required in FIN No. A-3711).
Completion Date:
8/31/85 Subtask I.D - Accident Analysis: W/CESSAR For each reactor type under consideration, 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.
Particular atten-tion will be given to those containment failure parameters which are input to consequence analysis (CRAC code).
Completion Dates:
I.D.1 CESSAR Preliminary 8/31/84 I.D.2 CESSAR Final 8/31/85 I.D.3 W Preliminary 7/31/84 1.D.4 II Final 7/31/85 Subtask I.E - Accident Assessment:
W/CESSAR' BNL will review PkA submittals for those reactors within the scope of Task I as prepared by utilities / vendors. BNL will gen-erate questions to the utilities / vendors as needed. 3NL will provide write-ups of relevant areas within the scope of Task I for inclusion in NRC assessments and testimony.
Completion Dates:
1.E.1 CESSAR Q-l's 2/29/84 I.E.2 CESSAR Q-2's 9/30/84 I.E.3 W Q-l's 8/31/83 I.E.4 {Q-2's 8/31/84 (See Continuation Sheet) w
',~
Safety Evaluation of Core-Melt Accidents:
. Proj'ect
Title:
CESSAR-FDA, Westinghouse Standard Plant-FDA
- p. 7 c.
WORK REOUIREMENTS (Continued)
Subtask II.C - Accident Analysis: }[ and CESSAR For each reactor type under consideration, BNL will perform 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 should be per-formed concurrent with Subtask I.D.
Completion Dates :
II.C.1 CESSAR Preliminary 8/31/84 II.C.2 CESSAR Final 8/31/85 II.C.3 }[ Preliminary 7/31/84 II.C.4 W Final 7/31/85 Subtask II.D - Accident Assessment: }{and CESSAR 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 partici-pate in meeting with the utilities / vendors as updated.
BNL will provide write-ups of relevant areas within the scope of Task II scheduled for inclusion in NRC assessments and testimony, and will conform to schedules provided by NRC staff below:
Completion Dates:
II.D.1 CESSAR Q-l's 2/29/84 II.D.2 CESSAR Q-2's 9/30/84 II.D.3 W Q-l's 8/31/83 II.D.4 EQ-2's 8/31/84 Task III - Consequence Analysis Estimated Level of Effort in FY83:
1 MM Estimated Level of Effort in FY84:
3 MM Estimated Level of Effort in FY85:
2 MM (Note:
The AEB of NRR/DSI is responsible for all NRR consequence analyses. As such, Task III will be limited to the following activities related to consequence analyses:
(1)
CRAC analyses in order to determine the impact on risk of variations in the Tasks I & II analyses based on phenomenological uncertain-ties, engineering uncertainties and the incorporation of mitigation features.
(2) CRAC analyses determining risk values at the request of AEB through RSB (as a supplement to AEB's own analyses).
(See Continuation Sheet)
Safety Evaluat on of Core-Melt Accidents:
Profect
Title:
CESSAR-FDA, Westinghouse Standard Plant-FDA
- p. 9 c.
WORK REQUIRESENTS (Continued)
Completion Dates:
IV.A.1 Preliminary:
CESSAR 8/31/84 IV.A.2 Preliminary: W 7/31/84
~
IV.A.3 Fina!. :
CESSAR 8/31/85 IV.A.4 Final: W 7/31/85 Subtask IV.B - Integration:
Impact on Risk BNL will present results of analyses and assessment in Tasks I, II and III in terms or risk values (including CCDFs) and changes in risk values due to changes in containment designs (mitigation features) or changes in damage state probabilities.
1 Completion Dates:
IV.B.1 CESSAR:
Letter Report Review of IPPSS 9/30/84 IV.B.2 W:
Letter Report i
Review of Zion 8/31/84 IVlB.3 CESSAR Final Report (NUREG/CR) 8/31/85 IV.B.4 W Final Report l
(NUREG/CR) 7/31/85 Subtask IV.C - Integration:
Uncertainty Analysis BNL will develop a methodology for translating containment matrix element uncertainties and other uncertainties (e.g., in damage states and CRAC analyses) into final uncertainties in final risk and risk reduction values making use of the NRC/RES and industry programs in this area.
Completion Dates:
Quarterly Reports d.
REPORTING REQUIREMENTS 1.
All producta which are required from this proposal (including NUREG/CR reports, and miscellaneous letter reports for input to SERs as well as input.to hearing testimony) have been identified specifically under each subtask in the WORK REOUIRESENTS Section.
BNL will submit six copies of draft NUREG/CR reports to the NRC Project Manager for staff review and approval. For NUREG/CR reports, within sixty days of receipt of the staff's comments on these reports, BNL will submit one (1) reproducible and six (6) reproduced copies of the final reports in accordance with NRC Manual Chapter 3202, " Publication of Unclassified Regulatory and Technical Reports Prepared by NRC Contractors."
(See Continuation Sheet)
j i
Safety Evaluation of Core-Melt Accidents:
P ro'j e ct
Title:
CESSAR-FDA, Westinghouse Standard Plant-FDA p.
11 l
l d.
RI;)RTING RIOUIREMENTS (Continued)
Task II: -Radionuclide Release Assessment Facility Docket F Period Cumulative CESSAR-80 50-470 Westinghouse 50-668 Advanced Design Task III:
Consequence Analysis Facility Docket #
Period Cumulative CESSAR-80 50-470 Westinghouse 50-668 Advanced Design Task IV:
Risk Assessment Summary Facility Docket F Period Cumulative CESSAR-80 50-470 Westinghouse 50-668 Advanced Design e.
MEETINGS AND TRAVEL BNL staff will participate in several meetings at the NRC Headquarters (one one-day meeting each quarter in Betbesda to discuss performance and work progress) and at other locations (one one-day meeting in Bethesda or at licensee / applicant headquar-ters with licensee / applicant and NRC staff is anticipated) to obtain source material for this program.
BNL staff may visit other laborataries or institutions and parti-cipate in professional meetings (attendance at two topical professional meetings on relevant topics vill be planned and budgeted).
f.
NRC-FURNISHED MATERIALS The NRC will provide any documentation relevant to the above tasks that are sub-mitted by licensees during the course of this project.
g.
DESCRIPTION OF ANY FOLLOW-ON EFFORTS Not Applicable.
t (Sta Continuation Sheet)
p BROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES, INC.
Upton. Long Istond. New York 11973 (516) 282s 3317 FTS 666' Oftce of tne Director Ma rc h.7, 1983 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 Nuclear Regulatory Commission entitled, " Safety Evaluation of Core-Melt Accidents:
CESSAR-FDA, Westing-house Standard Plant-FDA," FIN A-3705, being submitted for your review and approval.
The proposal is being submitted in response to a request from NRC dated January 4, 1983.
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 copics have been sent to:
Mrs. Sybil Boyd, Program Assistant Division of Systems Integration Mail Stop P-1102 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 The proposal has been prepared in accordance with the statement of work attached to the aforementioned letter.
If there are any questions regarding the document, please call the principal investigator or Mr. A. J. Romano, FTS 666-4024, Department Administrator for the Department of Nuclear Energy.
Sincerely yours, H. C. Grahn Assistant Director for Financial Planning Enclosure
/
cc: 6 S. Boyd (2)
B. L. Grenier J. Maher (2) 3
NRCpo w iss U.S. NUCLE AR G EGv. ATOR Y COMMISSION ATE :s sucresA.
[,,.
Feb urrv 28. 1983
,,g PROJECT AND' BUDGET PROPOSAL FOR NRC WORK g NE.
O R EVISION NC.
rw c.E CT TITLE a F'N NUVS E
- Safety Evaluation of Core-Melt Accidents:
CESSAR-FDA, Westinghouse S:andard Plant-FDA A-a 5
s i Nac esa NuvsEm t nC OFFICE Nuclear Reactor Regulation 20-19-40-41-3
- E ConTm ACTom Associated Universities, Inc.
CONT R ACTCn ACCovNT Nvusta Brookhaven National Laberatorv x,,,, [*,"
SITE Upton, New York COGNIZANT PERSONNEL l
OR G ANIZ ATION t FTS PHONE NUMBE R Pai RIOD OF PE R F O R MA NCE NAC PROJECT M AN AGER STARTING C ATE J. Meyer DSI/RSB 492-4752 04/01/83 OTnEM N'RC TECHNICAL STAFF COMPLETION CATE 08/31/85 Est.
OC E iMOJECT M AN AG ER Brookhaven W " 9-hd
.3F.cggg MD.Td David Schweller Area Office 666-3424 CONTR ACTOR.-PROJECT M AN AGER H. J. C. Kouts e66-2615 MMi e W.
Y/ Kato 666-20E4
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.- T4 gJ STAF F YE ARS OF EFFORT (Rounc to nearest renth of a Jears IFY 3opg lFY ]gg4 lFY 1Q85 IFY
}FY Dir2:: Scentific/ Technical 1.0 2.3 2.0 Oth;r Direct (Graced) 0.2 0.4 l
0.3 TOTAL OIRECT STAFF YEARS 1.2
- 2. 7 '
2.3 COST PROPOSAL l
l l
l l
Ce ec 3sla ies r
58 137 131 l
l'
- r. :einiea: Serv.ces (E nciocing AOpi 5
8 7
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- Tat =t=ATins :::7 C_, :A. u..F.. s. T i
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tCTAL PROJECT COST {
110 1
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,3*311 A-05 PROJECT AND BUDGET PROPOSAL FOR NRC WORK
,o...
7eoruary 28, 1983 eacsse: 1i t.e Safety Evaluation of Core-Melt Accidents:
CESSAR-FDA, k'estinghouse Standard Plant-FDA
=cs me esiso omo Asiz ATicN Associatec Universities, Inc.
Brookhaven National Laboratory FORECAST MILESTONE CHART: Sc%eculec te Start - M
-Completec /Shown an Qudtfor Yerr/
PROVIDE ESTIMATEC OoLLAR COST FOR EACM TASK FoA E ACH FISCAL YEAR FY IC83 iFY IC84 IFY
)Q85 6FY ipv TASK 1st l2nc l 3rd { 4tn l 1st l 2nc l3rc j 4tml 1st l2ncl 3rcl 4tn.) 1st l 2nc l 3relain i tr: l 2r cl 3ecl 4tn Task 1-Severe AeCident SCHEDULE Progression Anal.: Reactor d
A Svs./ Containment Sys l
pedingandFailurebodes COST 100K 46K 102K T
I I
l
' ask II-Radionuclide SCHEOULE g
i I
Release Assessment COST 28K 46K 50K Task III-Consequence SCHEDULE d
f Analysis COST 9K 28K 20K sCH EDULE d
Task IV-Risk a, ssessment l
l A
$u :3ary COST 27K 74K 70K SCHEDULE COST TOTAL ESTIMATED PROJECT COST 110K 250K 240K raC;ECT C E$Caneinon. torovoar narrature cescractices of tne foncmng tccocs on the orce'tostre. Attaen on coorn oncer to this NRC form 129. If an stem os ect a::,b:o: e, s: s:s te.)
- 1. C E;ECTIV E 05 P AOPOSED WC AK
- 2.
SUMMARY
OF PAIOR EFFORTS
- 3. WOAK TO EL PERFORMED AND EXPECTED RESULTS
- 4. DESCAl' TION OF ANY FOLLOWCN EFFORTS E. A ELATION $ dip TO OTHER PROJECTS
- 6. E EPORTl".G SCH EDULE
- 7. SUECONTR ACTOR INFOAMATION
!. L : S T *. E.'. C A * :TAL EOwFYENT AEOUIREO
- 9. CEECPIE E SPECI AL F ACILITIES REOulRED l
l t C. CON s Lt0T CF INTE AEST IN FORY ATION l
SEE NRC VANUAL CH APTER 1102 FOm A00l?tCN AL INFORMATION A ** m o v A L A.,,T. c a.;~ -sio N A Tv a t g;A g
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fr [1 1
l L
Snfety Evaluatien,cf Cort-Me'1: Accidents:
' Project
Title:
CESSAR-FDA, Westinghouse Standard-Plant-FDA
- p. 3 PROJECT DESCRIPTION a..
OBJECTIVE OF PROPOSED WORK i
(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 citigate
}
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.
I First, there is'a need to better understand the progression or 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 j
on contaf,ument loading and failure modes must also be factored into the assessment.
Second, based on the containment loading histories, there is a need to determine the radiological source term suspended in the containment, the effects on engineered I
safety features (E.S.Fs)~and mitigation features of this source term and finally the release characteristics of this sourc'e 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, phenomenology and mitigation hardware. These radiological consequences must be further analyzed in a licensing context with a full appreciation of its regulatory implications.
(2)
Objective 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-cerns using the state-of-the-art codes and the analyses and experimental data de-veloped from NRC/RES and other R&D programs. The scope also includes review and evaluation of licensee submittals and other pertinent infcrmation dealing with the subjects described below.
I The analyses provided under this contract will form the basis for the licensing de-i cisions required on CESSAR-System 80 FDA review (PRA portion), and the Westinghouse Standard Plant, FDA (FRA portion) with respect to severe accident considerations.
i The extensive analysis and 5 isessment to be performed, code capability to be de-veloped and experience to be gained under FIN A-3711 has been taken into account i
when developing this proposa..
\\
(See Continuation Shect)
Project
Title:
. Safsty Evclustion of Cora-M21t Accidents:
CESSAR-FDA, Wastinghouse Standard Plant-FDA
- p. 4 b.
SLM1ARY OF PRIOR EFFORTS Not Applicable,
c.,
WORK REQUIREMENTS
~*
As directed by the technical monitor J. Meyer, 3NL will perform the reviews, analy-sos and' assessments, as listed in the Tasks below.
Tcsk I:
~ Severe-Accident Progression Analysis:
Reactor
}
Systems / Containment Systems Loading and Failure i
Modes Estimated Level of Effort in FY83:
5 MM Estimated Level of Effort in FY84:
11 MH Estimated Level of Effort in FY85:
10 MM Subtask I.A - Data Acquisition:
Phenomenology Programs BNL will coordinate phenomenological input from FIN No. B-8634.
BNL vill provide cognizance of phenomenological studies of NRC/
RES, IDCOR, and foreign programs.
BNL will relate the informa-tion gathered to MARCH predictions.
This subtask supports di-rectly the efforts in Subtask I.D.
Starting March 15, 1983, a letter report summarizing subtask status will be provided every three months until the end of the project.
(Note:
Subtask I.A i
of FIN No. A-3711 provides the overall evaluation in this area; i
the subtask above is limited to specific }[ and/or CESSAR items.
This required letter report input vill be combined with the let-ter report required in FIN No. A-3711).
Completion Date:
8/31/85 Subtask I.B - Data Acquisition:
Engineering Programs i
l BNL vill coordinate engineering mitigation feature input from FIN No. B-8625.
BNL will provide cognizance of engineering studies on containment and mitigation features of NRC/RES, IDCOR, DOE and foreign programs. BNL vill relate the information gathered to MARCH predictions.
This subcask supports directly the efforts in Subtask 1.D.
Starting March 15, 1983, a letter-report su=mariz-i ing subtask status will be provided every three months until the 4
end of the project.
(Note:
Subtask I.B of FIN No. A-3711 pro-vides the orerall evaluation in this area; the subtask above is l
11=ited to specific }[ and/or CESSAR ite=s.
This required letter report input will be combined *vith :he letter report required in FIN No. A-3711).
Completion Date:
8/31/85 4
(See Continuation Sheet)
.n
Snfaty Evalustien of Cors-Melt Accidsnts:.
' Project Titla:
CESSAR-FDA, Westinghouse Standard Plant-FDA
- p. 5 c.
WORK PIOUIRIMENTS (Continued)
Subtask I.C - MARCE/MILCOR Code Maintenance and Development BNL Tdll closely follow RIS's MARCH-2 and MELCOR development programs.
BNL will follow the development of similar accident analysis codes, e.g., INCORE, foreign and domestic and specialty codes, e.g., CORCON, CONTAIN. BNL will maintain current MARCH code capability with modifications as appro*priate to the reactor type under consideration and the containment modifications (mit-igation features) being addressed.
This subtask supports di-rectly the efforts in Subtask I.D.
Starting March 15, 1983, a letter report summarizing subtask status will be provided every three months until the end of the project.
(Note:
Subtask I.C.
of FIN No. A-3711 provides the overall evaluation in this ' area; the subtask above is limited to specific W and/or CESSAR items.
~
This required letter report input will be combined with the letter report required in FIN No. A-3711).
Completion Date:
8/31/85 Subtask I.D - Accident Analysis: ~W/CESSAR For each reactor type under consideration, 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.
Particular atten-tion will be given to those containment failure parameters which are input to consequence analysis (CRAC code).
Completion Dates:
I.D.1 CESSAR Preliminary 8/31/84 I.D.2 CESSAR Final 8/31/85 I.D.3 W Preliminary 7/31/84 I.D.4 { Final 7/31/85 Subtask I.E - Accident Assessment:
W/CESSAR' BNL will review P'RA sub=ittals for those reactors within the scope of Task I as prepared by utilities / vendors.
BNL will gen-erate questions to the utilities / vendors as needed. BNL will provide write-ups of relevant areas within the scope of Task I for inclusion in NRC assess:ents and testimony.
Co=pletion Dates:
I.E.1 CESSAR Q-l's 2/29/84 I.E.2 CESSAR Q-2's.
9/30/84 4
I.E.3 W Q-l's 8/31/83 I.E.4
$Q-2's 8/31/84 (See Continuation Sheet)
Safety Evaluttion of Core-Malt Accidents:
Project
Title:
CESSAR-FDA, Westinghouse Standard Plant-FDA
- p. 6 c.
WORK F.EOUIREMENTS.(Continued),
Task II - Radionuclide Release Assessment Estimated Level of Effort in FY83:
3 MM I
Estimated Level of Effort in FY84:
5 MM j
Estimated. Level of Effort in FY85:
5 MM Subtask II.A - Data Acquisition:
Source Term e
BNL will provide cognizance of this activity and proper coupling with CORRAL / MATADOR so that NRC/AED positions on source terms are properly translated into the CORRAL / MATADOR analyses of re-leases at containment failure.
(The AEB branch of NRR/DSI is responsible for providi.ng state-of-technology data on source terms for use in the CORRAL / MATADOR codes).
BNL will provide _ physical processes data to AEB in trder to aid them in their source term eval'uation (particle densities and particle sizes for determination of agglomeration rates in con-i tainment volumes).
i This subtask supports directly the efforts in Subtask II.C.
Starting March 15, 1983, a letter report summarizing subtask status will be provided every three months until the end of the I
proj ect.- (Note:
Subtask II.A of FIN No. A-3711 provides the overall evaluation in this area; the~ subtask above is limited to specific }[ and/or CESSAR items. This required letter report in-put will be combined with the letter report required in FIN No.
A-3711).
Completion Date:
8/31/85 Subtask II.B - Data Acquisition:
Code Development I
BNL will maintain close contact with NRC/RES development of MATADOR, NAUA CONTAIN an~d MELCOR.
BNL will provide assessments of progress to date and recommendations for the course of fur-ther development and follow EPRI, IDCOR and foreign activities,
l in this area.
This subtask supports directly the efforts in Subtask II.C.
Starting March 15, 1983, a letter report su=-
marizing 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 }[ and/or CESSAR items.
This re-quired letter report input will be combined with the letter re-i port required for FIN No. A-3711).
1 Completion Date:
8/31/85 (See Continuation Sheet) u
y Snfety-Evaluation of Core-Melt Accidsnts:
Project
Title:
CESSAR-FDA, Westinghouse Standard Plant-FDA
- p. 7 3.RK REOUIREMENTS (Continued) c.
Subtask II.C - Accident Analysis:
W and CESSAR For each reactor type under consideration, BNL will perform 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 should be per-formed concurrent with Subtask I.D.
Completion Dates:
II.C.1 CESSAR Preliminary 8/31/84 II.C.2 CESSAR Final 8/31/85 7/31/84 II.C.3 W Preliminary II.C.4 W Final 7/31/85 Subtask II.D - Accident Assessment:
L*and CESSAR BNL will review PRA subuittals in the areas within the scop'e of Task II by utilities / vendors.
BNL will generate questions to the utilities / vendors based on this review.
BNL will partici-pate in meeting with the utilities / vendors as updated.
BNL will provide write-ups of relevant areas within the scope of Task II scheduled for inclusion in NRC assessments and testimony, and will conform to schedules provided by NRC staff below:
Completion Dates:
II.D.1 CESSAR Q-l's 2/29/84 II.D.2 CESSAR Q-2's 9/30/84 II.D.3 W Q-l's 8/31/83 II.D.4 {Q-2's 8/31/84 Task III - Consecuence Analysis Estimated Level of Effort in FY83:
1 MM Estimated Level of Effort in FY84:
3 MM Estimated Level of Effort in FY85:
2 MM (Note:
The AEB of NRR/DSI is responsible for all NRR consequence analyses.
As such, Task III will be limited to the following activities related to consequence analyses:
(1)
CRAC analyses in order to determine the impact on risk of variations in the Tasks I & II analyses based on phenomenological uncertain-ties, engineering uncertainties and the incorporation of citigation features.
(2)
CRAC analyses determining risk values at the request of AEB through RSB (as a supplement to AEB's own analyses).
(See Continuation Sheet)
Safaty-Evaluation of Core-Melt Accidents:
Projact
Title:
'CESSAR-FDA, Westinghouse-Standard Plant-FDA
- p. 8 e.
WORK REOUIREMENTS (. Continued),
Subtask 'III.A - Data Acquisition:
CRAC Code BNL will keep abreast of the state-of-technology in the area of consequence analyses including working knowledge of CRAC-II and other related codes (e.g., CRAC-IT).
BNL will maintain a CRAC code capability and data files for the sites psed in this study.
This subtask supports directly the efforts in Subtask III.B.
Starting March 15, 1983, a letter report summarizing subtask status will be provided every three months until the end of the project.
(Note:
Subtask III.A of FIN No. A-3711 provides the overall evaluation in this area; the subtash above is limited to specific W and/or CESSAR items.
This required letter report input will be. combined with the letter report required in FIN No. A-3711).
Completion Date:
8/31/85 i
Subtask 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 mitigation (or preven-tion) features and on variations due to accident progression uncertainties.
(Note Milestone in II.C)
Completion Date:
8/31/85 Task IV - Risk Assessment Sum =ary (Integration of Tasks I, II, and III)
Estimated Level of Effort in FY83:
3 MM Es timated Level of Ef fort in FY84:
8 MM Estimated Level of Effort in FY85:
7 MM i
Subtasks IV.A - Integration:
Containment Matrix 1
For the reactor being considered in this project, BNL will gen-erate a containment matrix which shows the relationship of dam-age states (provided by the staff) to release categories, and defend each elecent of the matrix based on analyses and assess-ment provided in Tasks I.&II.
BNL will determine estimates of uncertainties for each containment matrix element (to be used in Subtask IV.C).
BNL will compare this matrix to that de-veloped by the utility / vendor, if appropriata.
l l
(See Continuation Sheet)
S;fo'ty ' Evaluation' of Core-Malt Accidents :
Project
Title:
CESSAR-FDA, Westinghouse Standard Plant-FDA
- p. 9 c.
WORK REOUIRIMENTS (Continued)
Completion Dates:
IV.A.1 Preliminary:
CESSAR 8/31/84 IV.A.2 Preliminary:
W 7/31/84
~
IV.A.3 Final:
CESSAR 8/31/85 IV.A.4 Final: W 7/31/85 Subtask IV.B - Integration:
Impact on Risk BNL will present results of analyses and assessment in Tasks I, II and III in terns or 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 CESSAR:
Letter Report Review of IPPSS 9~/30/84 IV.B.2 W:
Letter Report Review of Zion 8/31/84 IV.'B.3 CESSAR Final Report (NUREG/CR) 8/31/85 IV.B.4 W Final Report (NUREG/CR) 7/31/85
- ~ ~
Subtask IV.C - Integration:
Uncertainty Analysis ENL will develop a cethodology for translating containment matrix element uncertainties and other uncertainties (e.g., in da= age states and CRAC analyses) into final uncertainties in final risk and risk reduction values making use of the NRC/RIS and industry progra=s in this area.
Completion Dates:
Quarterly Reports d.
REPORTING REQUIREMENTS 1.
All products which are required fro = this proposal (including NUREG/CR reports, and miscellaneous letter reports for input to SERs as well as input to hearing testimony) have been identified specifically under each subtask in the WORK l
REOUIRIMENTS Section.
BNL will submit six copies of draf t NUREG/CR reports to l
the NRC Project Manager for staff review and approval.
For NUREG/CR reports, within sixty days of receipt of the staff's co==ents on these reports, BNL vill sub=it one (1) reproducible and six (6) reproduced copies of the final reports in accordance with NRC Manual Chapter 3202, " Publication of Unclassified l
Regulatory and Technical Reports Prepared by FRC Contractors."
(See Continuation Sheet)
Stfaty Evaluation of Cors-Malt Accidents:
Project
Title:
CESSAR-FDA. Westinghouse Standard Plant-FDA p.
10
.d.
REPORTING REQUIREMENTS (Continued) 2.
A conthly' business letter report will be sub=itted by the 20th of the conth to the Project Manager, J. F. Meyer (DSI) with copies provided to the Director,
' Division of Systems Integration, ATTN:
W. Houston, S. Boyd, B. Sheron, DSI, and
~ Mr. 3. L. Grenier, NRR.
These reports will identify the title of the project, the FIN, the Principal Investigator, the period of performance, and the report-ing period and will contain 3 sections as follows:
A Project Status Section, which will contain:
- A listing of the efforts co=pleted during the period; milestones reached, or if missed, an explanation provided;
- Any problems or delays encountered or anticipated and reco=mendations for resolution;
- A surrary 'of progress to date;.
- Plans for the next reporting period.
A Financial Status section, which will contain:
- The total cost (value) of the project as reflected in the proposal and the total amount of funds obligated to date;
- The total amount of funds expended (costed) during the period and total cumulative to date undar the following categories:
Labor-related costs, Computer services, Travel, Subcontracts, Equipment and Total;
- The total amount of funds expended during the period (costed) and cumulative to date for each task, f.e., each plant under each Project.
A Fes Recovery Cost Status Section, which will contain the total amount of funds expended (costed) during the period and cumulative to date for each task in the following format:
FIN:
A-3705 TITLE:
Safety Evaluation of Core-Melt Accidents:
CESSAR-FDA; Westinghouse Standard Plant-FDA Period:
Task I:
SevIre-Accident Progression Analysis:
Reactor Systems / Containment Syste=s Load'ngs and Failure Modes Facility Docket F Period Cumulative
(
CESSAR-80 50-470 Westinghouse 50-668 Advance'd Design 3
i (See Continuation Sheet) m.-
Safety Evaluction of Core-Malt Accidents:
Project
Title:
CESSAR-FDA, Westinghouse Standard Plant-FDA p.
11
'd.
REPORTING REQUIREMENTS (Continued)
~
Task II:
Radionuclide Release Assessment Facility Docket F Period Cumulative CESSAR-80 50-470
~
I Westinghouse 50-668 Advanced Design Task III:
Consequence Analysis Facility Docket #
Period Cumulative CESSAR-80 50-470 Westinghouse 50-668 Advanced Design 4
Task IV:
Risk Assessment Summary Facility Docket F Period Cumulative CESSAR-80 50-470 Westinghouse 50-668 Advanced Design e.
MEETINGS AND TRAVEL BNL staff vill participate in several meetings at the NRC Headquarters (one one-day meeting each quarter in Bethesda to discuss perfor=ance and work progress) and at
{
other locations (one one-day meeting in Bethesda or at licensee / applicant headquar-ters with licensee / applicant and NRC staff is anticipated) to obtain source material for this program.
BNL staff may visit other laboratories or institutions and parti-cipate in professional meetings (attendance at two topical professional meetings on relevant topics will be planned and budgeted).
f.
NRC-FURNISH 5D MATERIALS The NRC wil'1 provide any docu=entation relevant to the above tasks that are sub-nitted by licensees during the course of ' this project.
g.
DESCRIPTION OF ANY FOLLOW-ON EFFORTS
)
Not Applicable.
(See Continuation Sheet)
Safety Evaluation of Core-Mel: Accidents:
Projact
Title:
CESSAR-FDA, Westinghouse Standard Plant-FDA p. 12 h.
RELATIONSHIP TO OTEER PROJECTS.
This project is related to a number of other NRC projects.
Specifically, BNL vill coordinate (Subtask I.A) phenomenological input fro = FIN No. B-8634 and provide cog'nizance of the phenomenological studies of NRC/RES, IDCOR and foreign programs.
BNL will relate the infor=ation gathered from these programs to MARCH code predic-tions.
BNL will also coordinate (Subtask I.B.) engineering citigation feature input from FIN No. B-8625.
BNL will provide cognizance of engineering studies on contain-otnt and mitigation features of NRC/RES, IDCOR, DOE and foreign programs and relate the inf or=ation gathered to potential containment building f ailure modes.
BNL will also assess the impact of source ter= codifications (in particular, RES FIN No.
B-6747) on radionuclide release analyses performed for W and CESSAR (Subtask II.C).
Finally, some of the activities covered under this project, (namely, FIN No. A-3705) although limited specifically to Indian Point and/or Zion applications, are also relevant to FIN No. A-3711.
In particular, Subtasks I.A, I.B I.C, II.A, II.B and III. A have paralle.1 objectives in the two FIN Nos. A-3711 and A-3705 but with appli-cation to different reactors.
The overall evaluation in these areas will be carried out under FIN No. A-3711 and will be combined with the work done in these subtasks in FIN No. A-3705.
1.
SUBCONTRACTOR INFORMATION BNL does not intend to subcontract any portion of this work.
In the event a subcontract is anticipated, BNL will notify NRC prior to initiating it.
j.
NEW CAPITAL EQUIP.ENT REQUIPID None.
k.
SPECIAL FACILITIES REQUIPID None.
1.
CONFLICT OF INTEREST There are no significant contractual or organization relationships of the Depart =ent of Energy, BNL and e=ployees, or expected subcontractors or consultants on this pro-posal, with industries regulated by the NRC and suppliers thereof that give rise to an apparent or actual conflict of interest.
_ _