ML20127M177
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Mr. Gregory J. Ogeka, Chief NOV 2 91902 Administrative Branch Brookhaven Area Office U. S. Department of Energy Upton, New York 11973
Dear Mr. Ogeka:
SUBJECT:
Bill TECHflICAL ASSISTA!!CE TO THE DIVISk0il 0F SYSTEMS INTEGRATION, NRR, NRC, " SAFETY EVALUATION OF CORE-MELT ACCIDEliTS: IriDIAN POINT-0.R. AllD ZION-0.R. (FIN A-3712)
The purpose of this letter is to request a proposal from BNL to provide technical assistance to the Division of Systems Integration,ilRC through FY-84. The enclosed Statement of Work (Enclosure 1) details the required work and should be used as the basis for preparing a proposal for submittal to this office.
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Standard Tems and conditions for NRC work, as provided in the DOE /NRC Memorandum of Understanding of February 24, 1978, and described in NRC Manual Chapter 1102, should be used as the basis for preparing a proposal.
If a portion of this work is to be subcontracted, it is required that BNL have a professional assigned to the contract who is qualified to defend the results. Also, prior approval by me in writing is required before initiation of any subcontractor effort. Please submit a proposal contain-ing, as a minimum, the infomation set forth in Enclosure 2, Proposal Content, in the fomat of the Statement of Work within 60 days to:
Mrs. Sybil M. Boyd, Program Assistant Division of Systems Integration P-1102 U. S. Nuclear Regulatory Comission Washington, D.C. 20555 8505230202 841002 PDR FOIA -
SHOLLYB4-243 PDR
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OFFICIAL RECORD COPY
, Mr. Gregory J. Og:ka Some work under this task is anticipated to be proprietary. "TJ 29 $gy If you have any questions about this authorization, please contact Ms. S. M.
Boyd on FTS 492-7685. Thank you for your assistance.
Sincerely, 9Fisinal 31sned by:
3eser J. Mattson Roger J. Mattson, Director Division of Systens Integration Office of Nuclear Reactor Regulation
Enclosures:
- 1. S0W (FIN A-3712)
W. T. Pratt, BNL -~
H.'Grahn, BNL-
.R. Bauer, DOE-CH R. Barber, DCE-QH
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Rfuttson SBoyd TSpeis EMarinos BSheron NLauben JMayer PTing Rasztac;f h m h.4, - A VZeoli DDandois DCorley RSB S/F: TA JMeyer
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EliCLOSURE 1 1
STATEMENT OF WORK , ,
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Title:
." Safety Evalua-ion of Core-Melt Accidents:
Indian Point-OR.and Zio R FIN 4:
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M, A-3712 B&R i:
20-19-10-11-3 7
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project Manager: J. Meyer, (FT5 492-4754) -
sechnical Monitor:
J. Meyer, (FT5 492-4754)
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1Backcround and Objective ,
'- Cons'ideration of severe accidents beyond the traditional design basis, including full core melt accidents. is an imp **mt part of fiRC's overall safety assessment
" -and-.therefore 'is becoming an important ingredient in specific licensing.ac: ions aro in generic rulemaking proceedings. _ Also. the consideration of features to mitigate the conse:;uences of core meit acci:ents for nuclear facili-ies continues te be a major: specific licensing activity. It is very important that the large- ,
amount of techn.ical information available and _being developed by, for example, 3.ES in this area be appropriately assimilated, codified and evaluated in a way that is directly applicable to licensing nes:s. These needs are in'three major areas. First, there is a need to better understand the progression or core melt- -
accioent. sequences up to and including associated core melt related phenomenology and the implementation of these processes '(and their uncertainties) into an overall assessment of containment loading _and failure modes. The impact of mitigation strategies on containment loading and failure medes must also be factored inte 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 engi-neered 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 Jand as a function mitigation of the assumptions regarding accident sequences, phenomenology hardware._ These radiological consequences must be further analyzed in'. a licensing context with a full appreciation of its regulatory implications.
The. objective of the activities described in this Statement of Work is to meet -
the above needs. -
The scope of this work will be' limited to.acdressing immediate NRR licensing concerns using the state-of-the-art codes and the analyses and ex$erimental data developed from NRC/RES and other R&D prograts. The scope will also include review and evaluation of licensee submittals and other pertinent information *
- dealing with the subjects described below.
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'. o Tne' analyses previded under this contract will help form the basis for positions-taken by the staff as related to questions raised by the Commission, hearing board and intervenors as.part of the Indian Point Hearing. Also the analyses will orovide and the Zion Probacilistic Safety Study (IPSS). input to the staff's This contract replaces contract FIN No. A-3392. Although much of the work in this recuest for proposal (RFP) is a continuation of the activities in A-3392 it was decided to initiate a new contract for the following reasons: ,
(1)
The Pointtasks are restructured Accident Analysis: from beine project oriented (Task-I: Zion / Indian (Task-I: Task-II: On-call services) to functional oriented Relea'ses; Task-III: Containment Loading and Failure Analysis;Radionuclide Task-II:
Summary). Consequence Assessment; Task-IV:
Risk Assessment This has been done to facilitate technical assistance ,
management and contractor accountability. ,
(2)
The period of performance has been considerably extended ov'er trat in A-3392 assessment duerequirements.
to delays in the Indian Point Hearing schedule and.tc additional -
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The extensive analysis and assessment perfcrmed, ccde capability develc:ed a-exgeriencs-t u s n.-P . gained uncer 'A-3392 has been taken into account in developing
';crk Pecuirements The Work Requirements are: _
Task I. - Severe-Accident Procression Analysis: Reactor Systems / Containment Systems Loacina and Failure Moces.
Estimated Level of Effort in FYE3: 4 MM Completien Date:
Estimatec Level of Effort in FY8a: 7/31/54 a MM
-Subtask I.A - Data Acquisition: Phencaenology Programt Coordinate phenomenological input from FIN No. 5-8634.
' Provide cognizance of phenomenological studies of RES, IDCDR, and foreign MARCH programs. -Relate the information gathered to predictions.
efforts in subtask "I.D."This subtask supports directly the Starting December 15, 1982, a letter report summarizing subtask status shall be provided every three months until the end of the contract. (Ncte:
Subtask I.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 -
can be combined with the letter report required in FIN No. A-3711)
......... Completion Cate: 7/15/84 Subtask I.B - Data Acquisition: Engineering Programs I Coordinate engineering mitigation feature input from FIN No. B-8625. Provide cognizance of engineering studies .
on containment and mitigation features of RES, IDCOR, DOE and foreign programs. Relate the information gathered to '
MARCH predictions.
This subtask supports directly the
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, efforts' in subtask ".I .D. " StErting'~ December IE, 1952, a
' letter report summarizing subtask stads shall be provided every three months until tne end of the contract. -(Note:
Subtask I.B of FII: No. A-3711 prov.. ides ;he overall evaluation in tni.i u ca; the subtask above is lim,ited to specific Indian Point ard/c- Zier Me s. TMs-required letter report input canTe' combined with the letter repore reouired in F:N No. A-3711)
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........ffompietionDate: 7/15/84 gs Suotas'k I.C - MARCH' /MELCOR Code Mainten2nce and Dd2*.fopment; Participate in RES's MARCH-2 and MELCOR development program Follow the developnent of similar accident analysis code e.g. , INCORE, foreign and domestic anc specialty codes, e.g.,
CORCON, CONTAIN. Maintain current MARCH code capability - -
with modifications as appropriate to the reactor type under consideration and the containment mod,ifications (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 contract. '(Note:
Subtask I.C of FIN No. A-3711 provides the overall evaluation in this area; the subtask above is limited to scecific Indian Point and/or Zion ite- s. This required letter report input can be ccm::ined with the iet er report recuired in FIN No. A-3711)
.........Cocpletion Date: 7/15/84.
c Subtask I.D ' : Accident Analysis: Indian Pcint/ Zion For each reactor type uncer consideration, analyze the _
accident progressions up to and including containment failure characterizations based on ' accident sequences and containment modifications (if any) supplied by the staff (Pay particular attention to those containment failure parameters which are input to consecuence analysis (CRAC code).) ....... Completion Dates:
I.D.1 Complete contractor analyses of accicent progressions for Indian Point by perform-ing analyses of Event V and basemat penetration ........ 12/15/82 1.D.2 Assess impact of code modifications (in particular MARCH-2) on accident progression analyses performed for Indian Point and Zion. ......... 3/15/83 I.D.3 Develop "best. and final" ~ set of accident progressions for input to NUREG/CR
......... 3/15/84
- Subtask I.E - Accident Assessment: Indian Point / Zion "
Review PRA submittals for these reactors within the scope L
of Task I as prepared by utilities / vendors. Generate questions to the utilities / vendors as needed. Provide write-ups of relevant areas within the scope oY Task I for L
inclusion in staff assessments and testimony. .
......... Completion Datesr i.
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I.E.1 Review ZPSS Utility submittal of 09/02/82 and prepare letter report
....... 3/15/83 I.E.2 Continue assisting in preparing testimony for the Indian Point hearing
....... 1/15/83 I .E.3 Participate in hearing. ...(Hearing dura-tion estimated to be from 1/15/82 tc 7/15/83 with 4 weeks of participation by contractor staff) ....... 7/15/83 Task II - Radionuclide Release-Assessment Estimated Level of Effort in FY83: 2 MM Comoletion Date: 7/15/84 Estimateo Level of Effort in FY84: 2 MM Subtask II.A - Data Acquisition: Source Term .
Provide congnizance of this activity and proper coupling with CORRAL / MATADOR so that AEB positions on source terms are properly translated into the CORRAL / MATADOR analyses of releases at containment failure. (The AEB branch of
!;RR/DSI is responsible for providing state-of-technology data on source terms for use in the CORRAL / MATADOR coces.)
Provide physical processes data to AEB in order t6 aid them in their source term evaluation (particle dens-ities and particle sizes for cetermination of aggicmeration rates in containment volumes). -
This subtask supports directly the efforts in subtask "II.C." Starting December 15, 1982, a letter report summarizing subtask status shall be provided every three months until the end of the project. (Note: Su: task 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 can be combined with the letter report required in FIN No. A-3711)
......... Completion Date: 7/15/84 Subtask II.B - Data Acquisition: Code Development Maintain close contact with RES development of MATADOR, NAUA C0!!TAIN AllD MELCORE. Provide assessments of pregress to date and recommendations for the course of further development.
And follow EPRI, IDCOR and foreign activities in this area.
This subtask supports directly the efforts in subtask "II.C." Starting December 15, 1982, a letter report summarizing subtask status shall be provid,ed 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 specifiq Indian Point and/or Zion items. This required letter report input can be combined with the letter report required in FIN No. A-3711) .
. . . . . . . . . Compl etion Da te: 7/15/84 Subtask II.C - Accident analysis: Indi n Point and Zion For each reactor type under consideration, perform analyses of the release fractions and other containment failu're r , .- - . - - - -
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- parameters important in the s0bsequent consequence analysis. This effort is closely cou) led to Subtask I.D and should be performed concurrent with Subtask I.D.
s . ., . A n . . Compi eti on Da tes :
II.C.1 Ccmplete contradter analyses of
f redtUnaclide releases _for Indian Pcint by performing: analysis of agmatpenetration Event:Vand{4..........12/15/82 f
.II.C.2~ Assess-impact v source term modi-fications (in partaicular RES FIN flo.
- ' S5747) on radionuclide release : .alyses
~ performed for-Indian Point and ' Zion.
.......... 3/15/8'3
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Subtask. II.D - Accident Assessment: Indian Point and Zion-Review PRA sumittals in the areas within the scope of-Task II by ~ utilities / vendors. Generate questions to 'the '
utilities / vendors based on this review. Participate in meeting with the utilities / vendors _as. updated. . P.r_ ovide _ __ _ __ _ _
write-ups^of"relevarit areas wit'h'in the scope of Task II~~
. scheduled for inclusion in staff assessments and. testimony.
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And conform to scheduled :rovided by staff below:
..... Completion Dates:
II.D.1 Continue assisting.in preparing testimony'for the Indian. Point hearing ......... . 3/15/83 II.D.2 Participate in hearing --
g (Duration: See Subtask I.E.3)
........... 7/15/83
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Task III - Ccnsecuence Analysis Estimated Level of Effort in FY83: 1 MM Completion Date: 7/15/84 Estimateo Level of Effort in FYS4: l'MM (tiote: The AES of NRR/DSI is responsible fer all NRR consequences analyses.
As such, Task III will be limited to the following activities related to consequences analysis:
(1) CRAC analyses in order to determine the impact on risk of variations in the Task I & II analges based on phenomenological uncertainties, engineering uncertainties and-the incorporation of mitigation features (2) CRAC analyses det'ermining risk values at the request of AEB ,
t through RSB (as a' supplement to AEB's own analyset).) - -
, Subtask III. A - Data Acquisition: CRAC Code Keep abreast of the state of technology in the area of consequence analyses including working knowlddge of CRAC-II and other related codes (e.g., CRAC - IT).
Maintain in a CRAC code capability and data files for -
- the sites used in this study. This subtask supports directly the efforts in subtask "III.B." Starting December 15, 1982, a letter report summarizing subtask status shall be provided every three months under end of contract. .(Note: Subtask III.A of FIN No. A-3711 ;
provides the overall evalos H nn in thie a-a=- +~k
)
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' task above is limited to specific Indian Point and/or Zion items. This required letter report input can be combined with the letter report required in FIN No. A-3711)
................ 7/15/84 Subtask III.B - Accident Analysis Perform CRAC analyses consistent with 'the MARCH / CORRAL M analyses performed in Subtask _ID and IIC. Determine enanges in _ risk based on inclusion of mitication (or_ pre-vention) features and 'on variations due to accident pro-gression uncertainties. (Note Mileston in II.C)
. . . . . . . . . . . . . . . . . 4/15/ 84
' Task IV - Risk Assessment Summary (Inteoration of ~ Tasks I, II and III)
Estimated level of E' fort in FY83: 3 MM Completion Date: 7/15/84 Estimateo Level of Effort in FY84: 3 MM Subtask IV. A'- Integration: Containment Matr1x_
For the. reactor being considered in this project, generate a containment matrix wnich shows the relationship of dama::e
-states (provided by the staff) to release categories, ani defend each element Of the matrix based on analyses and assessment provided in Task I &iII. Determine estimates of uncertainties for each containment matrix element (to be used in. Subtask IVC). Compare this-matrix to that developed by the utility / vendor, if appropriate. . . . .Cempletion Date:
IV.A.1 Preliminary: Zion.......... 4/15/83 '
IV.A.2 Preliminary: Indian Point.. 1/15/83 IV.A.3 Final: Zion................ 4/15/84 IV.A.4 Final: Indian Point. . . . . . . . 4/15/84 Subtask IV.5 - Integration: Impact on Risk Present results of analyses and assessments in Task I, II and III in terms of risk values-(incl. 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 Indian Point: Letter Report i
review of IPPSS...... 4/15/83 IV.B.2 Zion: Letter Report c review of Zicn....... 5/15/83 IV.B.3 Indian ' Point and Zion Final Report (NUREG/CR)'.... 7/15/84 .
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. S'ubtask IV.C _ - Integration: Uncertainty Analysis ..
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 RES and industry programs in this area. . .
....Cempletion Dates: Quarterly Reports ,
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Level of Effort and Period of-performance ? -
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' The level of eT'ont i; =ti...ecet 20 maTFMonths~cEr~a,2'0-month period.
Technical Reoorting RecciN Eents: --
- k. All products which are required from this coni;ract (,in.c)uding NUREG/CR reports, and miscellaneous letter reports for input to SERs as Wil, as input to nearing testimony) have been identified specifically under eacn subtask 'in the Work Recuirements Section. BNL shall submit six copies of draft NUREG/CR reports
! to :ne NRC Project Manager, for staff review and. approval. For NUREG/CR reports,
' witnin sixty cays of receipt of the staff's comments on these. reports, the - .
contractor ,shall 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" Business-Letter Recort A monthly business letter report will be sub.4tteo-by-the-lhof-the-month-te the Project Manager with copies provided t the Director, Division'of Systems Integration, ATTN: S. Boyd, T. Speis, B. Sheren DSI, and Mr. B. L. Grenier, NRR. Tnese reports will icentify the title of the project, the FIN,. tne Principal Investigator, the period of perfcrmance, and the reporting period will
-contain 2 sections as follows:
i project Status Section -
For each task under this program, provide the following information:
i 1. A list of the efforts completed during the period; milestones reached, or if missed, an explanation provided.
'2. Any problems of delays encountered or anticipated and' recommendation for resolution. 1_/
- 3. A summary of progress to date (this may be expressed in terms of percentage completion for each task).
- 4. Plans.for the next reporting period.
Financial Status Section
- 1. Provide the total cost (value) of the project as reflected
- in the proposal -
and ' the total amount of funcs obligated to date. *
- 2. Provide the total amounf. of funds expended (costed) during the period and total cumulative to date as follows: I 1/ If the reccmmenced resolution involves a contract modification, i.e., changes in work requirements, level of effort (costs), or period of performance, a seoarate letter should be prepared and submitted to the Director, Division of Systems r
Integration, ATTN: S. Bovd E. Marin,os, DSI, and cc:y provided to the Project
' Manager and B. L. Grenier, NRR. .
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Period Cumulative
'a . Labor-related costs
- b. : Computer services
- c. Travel ~
- d. -Subcontracts -
'e. Equipment
-Total
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- 13. Provide the total amount of funds expended during the period (costed) and cumulative to date .for each plant by TAC ' number. ' Zion - TAC No. 41044 Incian. point TAC No. 48055. 3/ . .
Meeting and Travel .
- 1. 'One one-day meeting each quarter in Bethesda to discuss performance and work progress should be planned and budgeted.
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- 2. Two topical professional meetings on relevant topics should be planned and
. budgeted (one attendee).
- 3. One one-day meeting each quarter in Bethesda or at licensee / applicant head-quarters with licensee / applicant and NRC staff. .
- 4. . Two-week travel status for two contractor staff at Indian Point hearing. _
NRC Furnished Materials '
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The NRC will provide any documentation relevant to the above tasks including,that which is subnitted.by licensees / app.licants during the course of this project. NRC will furnish copies of the latest relevant codes together with appropriate Users Manuals" and description of subro'utines. -
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Z/ Provide percentage against total funds obligated to date. '
3/ Cost of licensing nuclear power must be kept by NRC under the Licensing Fee
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Program for the purpose of billing the utility for processing the application. "
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' STATEMENT OF WORK ,
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Ti-le: .. # Safety Evaluation of Core-Melt Accidents:
IndianPoin-OR.andZiong
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FIN'#: A-3712 B&R-#:: 20-19-10-11-3 I Project Manager: J. Meyer, (FTS 492-4758) .
Technical Monitor:
J. Meyer, '(FTS 492-4754)
\
Background and Objective .
' ' Consideration of severe accidents beyond the traditional design ba1!is, 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 c ardlin generic rulemaking proceedings. .Also the consideration of features te ci-igate the conse:;uences of core mel . accidents fcr 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,
.RES in this area be appropriately assimilated, cocified 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 _
acciden_t sequences up to and including associated core melt related phenomenology and the implementation of. these processes (and their uncertainties) into an overall Lassessment of containment loading and failure modes. The impact of mitigation strategies -~on containment 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.engi-neered 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 and as a function mitigation of the assumptions regarding accident sequences, phenomenology hardware. These radiological consecuences must be further analy::ed in a licensing context with a full appreciation of its regulatory implications.
The objective of the activitics described in this Statement of Work is to meet - I the above needs. -
l- The scope of this work will be' limited to addressing immediate NRR licensing concerns using the state-of-tne-art codes and the analyses and ex$erimental data .
l developed from NRC/RES and other R&D programs. The scope will also include review and evaluation of licensee submittals and other pertinent information
- j. . dealing with the subjects described below.
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Tne: analyses orovided under?this contract will anc intervenors as part of the Indian Point Hearing. .
and the Zion Probabilistic' Safety Study (IPSS). input to the Tnis' contract replaces contract FIN No. A-3392.
ithis request Lfor proposal'(RFP) is a continuation of the activities in A 3 it was decided to initiate a new contract for the following reasons: -
(1)'
' Point Accident Analysis:The Task-II:
tasks.are restructured from Zion /being Indian projec (Tas k-I:
. Releases; Task-III:Containme'2t Loading and Failure Analysis; Tas Radionuclide -
' Sumary) . Consequence Assessment; -Task-IV:
management This has been and contractor done to facilitate accountability. technical assistanceRisk , .
(2)
The period of performance has been considerably extended o'ver that in A-3392 assessment due to delays in the Indian Point Hearing schedule and to ad recuireants. - - _ , _
ahe this RFP.extensive analysis and assessment performe Work Recuirements The Work Requirements are: -
Task I. - Severe-Accident Procression Analysis:
Systems Loaoina and Failure Moces. Reactor Systems / Containment Estimated Level of Effort in FY83: 4. MM Estimateo Level of Effort in FY84: 4 MM Comoletion Date: 7/31/84 Subtask I.A - Data Acquisition:
Phencmenology Program's Coordinate phenomenological Provide cognizance of input from FIN No. B-8634..
and foreign programs. phenomenological studies of RES, IDCOR, MARCH predictions. Relate the information gathered to efforts in subtask "I.D."This subtask supports directly the Startirig December 15, 1982, a letter report summarizing sub+ask status shall be.provided every three months until the end of the contract. (Note:
Subtask I.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 -
can be combined with the letter report required in FIN No. A-37
......... Completion Date: 7/I5/84 Subtask I.B - Data Acquisition:
Engineering Programs ! -
Coordinate engineering nitigation feature input from .
FIN No. B-3625. .
on containment and miProvide cognizance of engineering studies and foreign programs.tigation features of RES,10COR, DOE MARCH predictions. Relate the information gathered to ",
This subtask supports directly the
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efforts in subtask "I.D. " Starting Cecember lh,1952, a letter report summarizing subtask status shall be provided every three months until the end of the contract. (Note:
Subtack I .B of FIfLuc._A-3711' provides tne overall evaluation in in;s area; the subtcp abcve is lirrited to specific Indian Point can Teand/c, Zim. . w.a . This required 19: er r purs incut combined with the letter recort required in FIN No. A-Nil)
......<.>Com 7/15/E4 Subtask I.C - MARCH'/MELCOR_;.1' .
Code opment:
Maintenance and Participate in RES's MARCH-2 and MELCOR development program Follow the developnent of similar accfdent analysis code e.g. , INCORE, foreign and domestic and specialty codes, e.g. ,
CORCON, CONTAIN. Maintain current MARCH code capability - -
with modifications as appropriate to th t rear, tor type under consideration and the containment modif cations (mitigation features) being addressed. This subtasx supports directly the efforts in subtask "I.D'.' Starting D':cember 15, 1982, a letter report summarizing subtask status shall be provided m-every three months until the end of contract. *(Note:
Subtast-ITC of~ FIN NO. A-Hil ;WoWdes t'he overaT1 evaluation in this area; the subtask above is limited to s;iecific Indian Point and/or Zion items. This required letter report input can 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 For each reactor type under consideration, analyze the -
accident progressions up to and including contaircent failure characterizations based on accident sequences and containment modifications (if any) supplied by the staff (Pay particular attention to those containment failure parameters which are input to consequence analysis (CRAC code) .) . . . . . . . Completion Dates:
1.D.1 Complete contractor analyses of accident progressions for Indian Point by perform-ing analyses of Event V and basemat penetration ........ 12/15/82 I.D.2 Assess impact of code modifications (in particular MARCH-2) on accident progression analyses performed for Indian Point and Zion. ......... 3/15/83 I.D.3 Develop "best. and final" ' set of accident progressions for input to NUREG/CR
......... 3/15/84 Subtask I.E - Accident Assessment: Indian Point / Zion "
Review PRA submittals for these reactors within the scope of Task I as prepared by'ut1 hties/ vendors. Generate Provide
. questions write-ups oftorelevant the utilities areas/ vendors within theas needed.
scope o Y Task I for inclusion in staff assessments and testimony. ,
......... Completion Dates:-
3 o-I.E.1 Review ZPSS Utility subinit al of 09/02/82 and prepare letter report h ....... 3/15/83 I.E.2 Continue assisting in precaring-
, testimony for the Indian Point hearing
....... 1/15/83 I .E.3 Participate in hearing. .'. .(Hearing dura-tion estimated to be from 1/15/83 to 7/15/83 with 4 weeks of participation by contractor-staff) ....... 7/15/83
, . Task II - Radionuclide Release Assessment
. Estimated Level of Effort in FY83: 2 MM Comoletion Date: 7/15/84 Estimateo Level of Effort in FY84: 2 MM Subtask II. A - Data Acquisition: Source Term - '
Provide congnizance of this activity and proper coupling with CORRAL / MATADOR so that AEB positions 6n source terms are properly translated into the CORRAL / MATADOR-analyses of releases at containment failure. (The AES branch of
, NRR/DSI is responsible for providing state-of-technology dat'a on source terms for use in the CORRAL / MATADOR codes.)
Provide physical processes data to AEB in order to aid them in their source term evaluation (particle densities and particle sizes for determination of agglomeration rates in containment volumes). .
This subtask supports directly the efforts in subtask "II.C." Starting December 15, 1982, a letter report summarizing subtask status shall be provided every three months until the end of the project. (Note: Subtask II.A of FIft :10. A-3711 provides the overall_ evaluation in this area; the subtask above is limited to ssecific Indian Point and/or Zion items. This required lette'r report input can be combined with the letter report required in FIrl flo. A-3711)
......... Completion Date: 7/15/84 Subtask II.B - Data Acquisition: Code Development Maintain close contact with RES development of MATADOR, NAUA C0flTAIN AND MELCORE. Provide assessments of progress to date and recommendations for the course of further development.
And follow EPRI, IDCDR and foreign activities in this area.
This subtask supports directly the efforts in subtask "II.C." Starting December 15, 1982, a letter report ,
summarizing subtask status shall be provid,ed every three months until the end of the projact. (flote: Subtask II.B of FIrl No. A-3711 provides the overall evaluation in this area; the subtask above is limited to specifiq Indian Point and/or Zion items. This required letter report inppt can be combined with the letter report required in FIf1 !!o. A-3711) 1 l ......... Completion Date: 7/15/84 Subtask II.C - Accident analysis: Indian Point and Zion For each reactor type under consideration, perform analyses of the release fractions and other containment failure .
9
_ _ . . _ - _ . . _ _ _ _______t._ _ _ _ _ _ _ _ _ _ . _ - _ . . _ _ _ _ _ _
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s: .' '
parameters important in the subsequent consequence analysis. This effort is closely co6 pled to Subtask I.D and should be performed concurrent with Subtask I.D.
m -
. . . . .-l . . . . Compl etion Da tes :
II.C.1 Complete contractor analyses of.
,y radionuclide releases for Indian Point by performing. analysis of Even't V and tiattmat penetration i . 3' 12/15/82 II.C.2AssessimpactcY........... source term modi-fications (in phrtaicular RES FIfl fio.
S5747) on radioriuclide release cr.alyses performed f6r Indian Point ~and Zion.
.......... 3/15/8'3 Subtask II.D - Accident Assessment: Indian Point and Zion-Review PRA sumittals in the areas within the scope of Task 11 by utilities / vendors. Generate questions to'the
- utilities / vendors based on this rev.iew. Participate in meeting with the utilities / vendors as updated. Provide wHte-ups, o~f relevant areas within the scope of Task II scheduled. for inclusion in staff assessments anc testime y.
And conform to scheduled provided by staff below:
..... Completion Dates:
II.D.1 Continue assisting in preparing -
testimony for the Indian. Point hearing ......... . 3/15/83 II.D 2 Participate in hearing -
(Duration:- See Subtask I.E.3)
........... 7/15/83
' Task III - Consecuence Analysis Estimated Level of Effort in FY83: 1 MM Comoletien Date: 7/15/84 Estimated Level of Effort in FYS4: 1 MM
'(liote: The AEB of liRR/DSI is responsible for all fiRR consequer.ces analyses.
As such, Task III will be limited to the following activities related to consequences analysis:
(1) CRAC analyses in order to determine the impact an risk of variations in the Task I & II analy.ses based c.) phenomenological uncertainties, engineering uncertainties and the incorporation of mitigation features (2) CRAC analyses defermining risk values at the request of AES ,-
through RSS (as a supplement to AEB's own analyset).) -
Subtask III.A - Data Acquisition: CRAC Code Keep abreast of the state of technology in the area of consequence analyses including working knowlddge of CRAC-II'and other related codes (e.g.,'CRAC - IT).
Maintain in a CRAC code capability and data files for -
the sites used in this study. This subtask supports directly the efforts in subtask "III.B." Starting December 15, 1982, a letter report summarizing subtask j status shall be provided every three months under end l of contract. (Note: Subtask III.A of FIN ilo. A-3711 '
provides the overall evaluation in thic araa: the ee . _ -
3 .
- m. . ,,-
task above is limited to specific Indian Point and/or Zion items. This required letter report input can be combined with the letter report required in FIN. No. A-3711)
................ 7/15/84 Subtask III.B Accident Analysis .
Perform CRAC analyses consistent with the MARCH / CORRAL .
analyses performed in Subtask ID and IIC. Determine changes in risk based on inclusion of mitigation (or pre-vention) features and on variations due to accident pro-gression uncertainties.
- (Note Mileston in II.C)
................. 4/15/84
~
Task IV - Ris'k Assessment Sumary (Integration of Tasks I, II arid III) '
Estimated Level of Effort in FY83: 3 MM Completion Date: ,7/15/84 Estimated Level of Effort in FY84: 3 MM -
Subtask IV. A - Integration: Containment Matrix '
For the reactor being considered in this project, generate
,- s containment matrix wnich shows the relationship of damage states (provided by the staff) to release categories, and defend each element of tne matrix based on analyses and assessment provided in Task I & II. Determine estimates of uncertainties for each containment matrix element (to be used in Subtask IVC). Compare this matrix to that develcped by the utility / vendor, if appropriate. .... Completion Date:
IV. A.1 Preliminary: Zion.......... 4/15/83
~
IV.A.2 Preliminary: Indian Point.. 1/15/83 IV.A.3 Final: Zion................. 4/15/84 IV.A.4 Final: Indian Point........ 4/15/84 Subtask IV.3 - Integration: Impact on Risk Present results of analyses and assessments in Task I, II and III in terms of risk values (incl. 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 Indian Point: Letter Report .
review of IPPSS...... 4/15/83 IV.B.2 Zion: Letter Report review of Zion....... 5/15/83 IV.B.3 Indian Point and Zion Final Report (NUREG/CR)..... 7/15/84 Subtask IV.C - Integration: Uncertainty Analysis .. J 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 RES and industry programs in this area. '
.... Completion Dates: Quarterly Reports .
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n ; ,
pki- .m' .
ec ,
a .
Level of Effort and Period of Performance .
The level of--e##crt'is-estimated L at.20 man-mon hc ever e EG-month per<ca Technical iReecrtino Rid 51rements:
All products wnich are required from this contraci (including NUREG/CR reports, and miscellaneous letter-reports for input to SERs as well as input to nearing testimony) have been identified specifically under ea'ch subtask in the Work Reouirements Section. BNL shall submit six copies of draft NUREG/CR reports 4to tne. lac Project Manager,' for . staff review and approval. For NUREG/CR reports, within. sixty days of-receipt of the staff's ccaments on these. reports,.the -
contractor,shall' 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" Business Letter Report A monthly business letter report will be submitted by the 15th of the month.tc-- ._
-the Project Manager with copies provided to the Director, Division'cf Systems Integration, ATTN: S. Boyd, T. Speis, E. Sheron, DSI, and Mr. S.-L. Grenier,
' t;RR. These reports will identify the t' le of the project, the FI!;, the Principal Investigator, the period of performance, and the reporting period will contain 2-sections as follows:
Project Status Section -
For each task under this- program, provide the following information:
L 1. . A' list of the efforts co$pleted during the period; milestones reached, or if missed, an explanation provided.
2.' Any problems of delays encountered or anticipated and recommendation for resolution. 1/.
- 3. A summary of progress to date (this may be expressed in terms of percentage completion for each task).
- 4. Plans for the next reporting period.
Financial Status Section
- 1. Provide the total cnst (value) of the project as reflected
- in the proposal -
and the total amount of' funds obligated to date. -
- 2. provide the total am'ount of funds expended (costed) during the period and total cumulative to date as follows: I 1/ If.tne recc=menceo resolution involves a contract modification, i.e., changes in work requirements, level of effort (costs), or period of performance, a secarate letter:should be prepared and submitted to the Director, Division of Systems Integration, ATTit: S.-Boyd, E. Marinos, DSI,and copy provided to the project Manacer and B. L. Grenier, NRR.
Period Cumulative
- a. Labor-related -::~-2
- b. Computer services
- c. Travel .
- d. Subcontracts -
- e. Equipment Total
( 5) 2/
- 3. Provide the total amount of funds expended during the ceriod (costed) and cumulative to date for each plant by TAC number. Zicn - TAC Nc. 41044 Incian. Point 2 - TAC No. 48055. 3/ - -
Meetino and Travel ,
- 1. One one-day meeting each quarter in Bethesda to discuss performance and work progress should be planned and budgeted.
- 2. Two topical professional meetings on relevant topics should be planned and budgeted (cne attendee).
- 3. One one-day meeting each quarter in Eethesda or at licensee / applicant head-quarters with licensee / applicant and NRC staff.
4 Two-week travel status for two contractor staff at Indian point hearing.
NRC Furnished Materials The NRC will provice any documentation relevant to the above tasks including that which is subnitted.by licensees /apolicants during the course of this project. NRC will furnish copies of the latest relevant codes together with appropriate Users Manuals and description of subroutines.
- I 2j Previce percentage against total funcs atlicated to date.
3/ Cost of licensing nuclear p'ower must be kept by NRC under the Licensing Fee .
Program for the purpose of billing the utility for processing the application.
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