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-!!r. Gregory J..Ogeka, Chief '
Administrative Branch Brookhaven Area Office U. S. Department of Energy Upton, New York 11973
Dear Mr. Ogeka:
SUBJECT:
BNL TECHNICAL ASSISTANCE TO THE DIVISION OF SYSTEMS INTEGRATI0li, NRR, NRC, " SAFETY EVALUATIO!I 0F CORE-MELT ACCIDENTS: CESSAR-FDA; UESTIllGHOUSE STAllDARD PLANT-FDA" (FINA3705)~
The purpose of this letter is to request a proposal from Bf!L to provide technical assistance to the Division of Systems Integration, HRC through ~
FY-85. 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.
-Standard Terns and conditions for liRC work, as provided in the DOE /f!RC
-Ilemorandum of Understanding of February 24, 1978, and described in URC Hanual 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 Bill 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.containing, as a minimum, the information set forth in
' Enclosure 2, Proposal Content, in the femat of the Statenant of Work xithin 60 days to:
Mrs. Sybil !!. Boyd, Program Assistant Division of Systems Integration P-1102 U. S. Nuclear Regulatory Comission Washington, D. C. 20555 kson 30 \% xk
...a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ... .. . . . . . . . . . . . . . . . . . . . . -- .-
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Soma trork under this task is anticip=ted to be proprietary.
If you have env questions about this authorization, please contact l'rs.
S. !!. Scyd on FTS 492-7685. Thank you for your assistance.
Sinceralv, Or!arar signee g.
RcrJ.Ma : son Roger J. liattson, Director Division of Systens Integration Office of Nuclear Reactor Pegulation
Enclosures:
- 1. 50W(FINA-3705)
- 2. Proposal Content cc: P,. Bari, BfL T. Roman _o_, Bt:L _ _ _ _ , , _ _ _ _
W. Kato, Bill H. T. Pratt, BNL DISTRIBUTION H. Grahn, BUL NRR Project File (BGrenier)
R. Sauer, DOE-CH RSB S/F: TA R. Barber, DOE-HQ JMeyer R/F RMattson TSpeis BSheron RSB R/F EMarinos NLauben SBoyd JMeyer DDandois O ZRosztoczy VZeoli gA 4
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ENCLOSURE 1 STATEMENT OF WORK 9
Title:
Safety Evaluation of Core-Melt Accidents:
CESSAR-FDA, Westinghouse Standard Plant-FDA FIN NO.: . A-3705 B&R NO.: 20-19-40-41-3 Project Manager: 'J. Heyer (FTS 492-4752)
Technical Monitor: J. Meyer (FTS 492-4752)
Background and Objective 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 end in-generic-rulemakiag 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 th large amount of technical information available and being developed b.ey, for example, 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 assessment 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 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 . consequences 'as a function of the assumption: 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.
The objective of the activities described in this Statement of Work is l ,
to meet the above needs.
~ The scope of this work will be limited to addressing immediate NRR licensing concerns using the sta'te-of-the-art codes and the analyses and
~ experimental data developed from NRC/RES and other R&D prograns. The scope also includes review and evaluation of licensee submittals and other pertinent information dealing with the subjects described below.
~
3 . 2 The analyses provided under this' contract will form the basis for the
-licensing decisions required on CESSAR-System 80 FDA review (PRA portion),andtheWestinghouseStandardPlant,FDA(PRAportion)with respect to severe accident considerations.
- The extensive analysis and assessment to be performed, code capability to be developed and experience to be gained under A-3711 has been taken
.into, account.in developing the RFP.
Work Requirements The Woric Requirements Are:
Task I: Severe-Accident Progression Analysis: Reactor Systems / Containment Systems Loading and Failure Modes.'
Estimated Level of Effort in FY83: 7 MM Completion Date: 8/31/85 9 MM Estimated Estimated Level-of Level Effort of Effort in FY85: in FY84_:_ 10 MM Subtask 1.A - Data Acquisition: Phenomenology Programs '
Coordinate phenomenological input from FIN No.B8634.
Provide cognizance of phenomenological studies of RES, IDCOR, and foreign programs. . Relate the '
information gathered to MARCH predictions. This subtask supports directly the efforts in Subtask "I.D." Starting March 15, 1983, a letter report summarizing subtask status shall be provided every three months'until the end nf the contract. (Note:
Subtask 1.A of FIN No.A3711 provides the overal.1 evaluation in this area; the subtask above is limited to specific W and/or CESSAR items. This
, .reouired letter report input can be combined with the letter report required in FIN No.A3711.) .
... Completion Date: 8/31/85 Subtask I.B - Data Acquisition: Engineering Programs
! Coordinate engineering mitigation feature input from n FIN No.B8625. 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 efforts in subtask "I.D." Starting March 15, 1983, a letter report summarizing subtask status-shall be provided every three months until the end of the contract. (Note:
Subtask I.B of FIN No.A3711 provides the ov~erall evaluation in this area; the subtask above is limited to specific W and/or CESSAR items. This
> required letter report input can.be combined with the letter report required in FIN No.A3711)
... Completion Date: 8/31/85 D.
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- 1 Subtask I.C - MARCH /llELCOR Code Maintenance and Development
Closely follow RES's MARCH-2 and MELCOR development
-program. Follow the development of similar accident analysis codes e.g., INCORE, foreign and domestic and speciality codes, e.g., CORCON, CONTAIN.
. Maintain current 11APCH code capability with modifications as appropriate to the reactor type under consideration and the containment modifications (mitigation features) being addressed.
This subtask supports directly the efforts in subtask "I.D". Starting March 15, 1983, a letter report summarizing subtask status shall be provided every three months'until the end of contract.
(Note: Subtask I.C of FIN No.A3711.provides the overall evaluation in this area; the subtask above is limited to specific W and/or CESSAR items. This required letter report Tnput can be combined with
, , the letter report required in FIN No.A3711).
... Completion Date: 8/31/85 Subtask I.D - Accident Analysis: W/CESSAR For each reactor type under 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 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 E Final............. 7/31/85 Subtask I.E - Accident Assessment: W/CESSAP, -
Review PRA submittals Tor-these reactors within the scope of Task I as prepared by utilities / vendors.
Generate ouestions to the utilities / vendors as needed. Provide write-ups of relevant areas within the scope of Task I for inclusion in staff assessments and testicony.
... Completion Dates:
I.E.1 CESSAR Q1's.. 9/30/83-I.E.2 CESSAR Q2's.. 9/30/84 I.E.3 W Q1's....... 8/31/83 I.E.4 E 02's....... 8/31/84 Task II - Radionuclide Release Assessment .
Estimated Level of Effort in FY83: 4 MM Completion Date: 8/31/85 Estimated Level of Effort in FYS4: 4 MM Estimated Level of Etfort in FY85: 5 Mit .
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. Subtask II.A - Data Acquisition: Source Term n Provide cognizance of this activity and proper coupling with CORRAL / MATADOR. so that AED positions on source terms are properly translated into the CORRAL / MATADOR analyses of releases at containment failure. (The AEB branch of NRR/DSI is responsible for providing state-of-technology data 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 March 15, 1983, a letter report summarizing subtask status shall be provided every three months until the end of the project.
(Note: Subtask.II.A of FIN No.A3711 provides the averall evaluatina in tMs area; the subtask above is limited to specific W and/or CESSAR items. This required letter report Tnput can be combined with the letter report required in FIN No.A3711).
... Completion Date: 8/31/85 Subtask II.B - Data Acquisition: Code Development Maintain close contact with RES development of MATADOR, NAUA CONTAIN and MELCOR. -Provide ,
assessments of progress to date and recomendations 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 March 15, 1983, a letter report sumarizing subtask status shall be pro.vided every three months until the end of.the project.
(Note: Subtask II.B of FIN No.A3711 provides the o overall evaluation in this area; the subtask.above l is limited to specific W and/or CESSAR items. This
! required letter report Tnput can be combined with the letter report required in FIN No.A3711).
... Completion Date: 8/31/85 Subtask II.C - Accident Analysis: W and CESSAR For each reactor type under consideration, perfom analyses of the release fractions and other l containment failure parameters important in the l subsequent consequence analysis. This effort is l: closely coupled to Subtask-I.D ar.d should be
! performed 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 W preliminary....... 7/31/84 II.C.4 7 final............. 7/31/85 E
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. Subtask II.D - Accident Assessment: W and CESSAR -
Review PRA submittals 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. Provide write-ups of relevant area within the scope of Task II scheduled for inclusion in staff assessments and testimony, and confom to schedules provided by staff below:
... Completion Dates:
II.D.1 CESSAR Q1's... 9/30/83 II.D.2 CESSAR Q2's... 9/30/84 II.D.3 W Q1's........ 8/31/83 II.D 4 E Q2's........ 8/31/84 Task III - Consequence Analysis Estimated Level of Effort in FY83: 2 MM Completion Date: 8/31/85 Estimated Level of Effort in FY8Ti 2 MM -
Estimated Level of Effort in FY85: 2 MM (Note:. The AEB of NRR/DSI is responsible for all NRR consequences 4 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 analyses based on phenomenological uncertainties, engineering unceri.ainties 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).)
Subtask III.A- Data Acquisition: CRAC Code 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). Maintain a CRAC code capability and data files for the sites used in this study. This suhtask l supports directly the efforts in subtask "III.B."
l Starting March 15, 1983, a letter report sumarizing L -
subtask status shall be provided every three rionths l until end of contract. (Note: Subtask III.A of FIN No.A3711 provides the overall evaluation in this area; the subtask above is limited to specific W j, and/or CESSAR items. This required letter report input can be combined with the letter report requiredinFINNo.A3711).
... Completion Date: 8/31/85 Subtask III.B- Accident Analysis Perform CRAC analyses consistent with the MARCH / CORRAL analyses perfomed in Subtask ID and IIC. Determine changes in risk based on inclusion of mitigation (or prevention) features and on i
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- , uncertainties. (NoteMilestoneinII.C)
... Comp 1.etion Date: 8/31/85 Task IV - Risk Assessment Sumary (Integration of Tasks I, II, and III)
Estimated Level of Effort in FY83: 5 MM Completion Date: 8/31/85 Estimated Level of Effort in FY84: 6 MM Estimated Level of Effort in FY85: 7 MM Subtask IV.A - Integration: Containment Matrix For the reactor being considered in this project, generate a containment matrix which shows the relationship of damage states (provided by the staff) to release categories and defend each
. element of the 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 developed by the utility / vendor, if appropriate. ... Completion Date:
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 .
- Present results of analyses and assessment 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.
IV.B.1 CESSAR: Letter Report .
review of. IPPSS.. ... 9/31/84 IV.B.2 W: Letter Report review of Zion... ... 8/31/84 IV.B.3 CESSAR Final Report (NUREG/CR)... 8/31/85
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IV.B.4 W Final Report .
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INUREG/CR)... ...... 7/31/85 Subtask 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.
... Completion Dates: . Quarterly Reports
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4 - Level of Effort and Period of Performance The level of effort is estimated at 63 man-conths over a 33-month period.
Technical' Reporting Requirements:
All products which are required from this contract (including NUREG/CR reports, and miscellaneous letter reports for input to SERs) have been identified specifically under each subtask in the Work Recuirements Section. BNL shall 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, .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".
'i Business Letter Reports A monthly business letter report will be submitted by the 15 th of the month to the Project Manager with copies provided.to the Director, DivTsion of Systems Integration, ATTN: S. Boyd, T. Speis, B. Sheron, i DSI, and Mr. B. L. Grenier, NRR. These reports will identify the title of the project, the FIN, the Principal Investigator, the period of 4
performance, and the reporting period will contain 2 sections as follows: -
Project Status Section ,
For cach task under this program, provide the following information:
- 1. A list of the efforts completed during the period; milestones reached, or if missed, an explanation provided.
- 2. Any problems or delays encountered,or anticipated and recoerendationforresolution.If
- 3. A sumary of progress to date (this r:ay be expressed in terms of percentage completion for each task).
- 4. - Plens. gor the next reporting period.
l Financial Status Section L 1. Provide the total cost (value) of the project as reflected in the l- proposal and the total amount of funds obligated to date.
JJ If the recomended resolution involves a contract modification, i.e ,
changes work requirements, level o*f effort (costs), or period of performance, a separate letter should be prepared and submitted to the Director, Division of Systems Integration, ATTN: S. Boyd, E.
Marinos, DSI, and a copy provided to the Project Manager and B. L.
i- Grenier, NRR.
1 -
. 2. Provide the total amount of funds expended (costed) during the period and total cumulative to date as follows:
Period - Cumulative
- a. Laber-related costs b .~ Computer services
- c. Travel
- d. Subcontracts
- e. Equipment
' Total
( %) 2/
- 3. See attached format Meeting 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 profes.sional_ meetings _on_ relevant topics _should be planned and budgeted (one attendee).
- 3. - One one-day meeting each quarter in Bethesda or at licensee / applicant headquarters with licensee / applicant and NRC staff. -
NRC Furnished Materials The NRC will provide any documentation relevant to the above tasks including that which is submitted by licensees / applicants during the course of this project. NRC Will furnish copies of the letest relevant codes together with appropriate Users Manuals and description of subroutines.
2/ Provide percentage against total funds obligated to date.
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, 3. Fee Recovery Cost Status Section Pursuant to the provisions of HRC Regulations,10 CFR 170, provide the total amount of funds expended (costed) during the period and cumulative to date for each task in,the following format:
FIN: 83705 TITLE: Safety Evaluation of Core-Melt Accidents: CESSAR-FDA; Westinghouse Standard Plant-FDA Period: .
Task I: Severe-Accident Progression Analysis: Reactor Systems / Containment Systems Loadings and Failure Modes Facility Docket # Period Cumulative
. CESSAR-80 50-470 Westinghouse 50-668 Advanced Design .
Task II: Radionuclide Release Assessment Facility Docket # Period Cumulative CESSAR-80 50-470 Westinghouse 50-668
, Advanced Design Task III: Consequence Analysis a
Facility _ Docket # Period Cumulative CESSAR-80 50-470 Westinghouse 50-668 Advanced Design Task IV: Risk Assessment Sumary facility Docket # Period Cumelative CESSAR-80 50-470 Westinghouse 50-668 Advanced Design Note: If there is any effort under any of these tasks that is generic in nature such that the effort is required in order to perform the evaluation of any submittal, the cost for the generic effort should be prorated to each facility to which it applies. ,
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hh /0 3 OFFICE OF NUCLEAR REACTOR REGULATION
, PROJECT IDENTIFICATION
SUMMARY
(PIDS) ll W d' 1 1 t o 0 02 u.gA-.-
-TITLE: -
3 u on nj IN: A3705 CONTRACT' NUMB"ER(Non-DOE): B&R NUMBER:# ~ I NRR OPERATING PLAN 20-19-40-41-3 INDEX NO.:
DIVISION: DSI BRANCH:RSB PROJECT MANAGER: J. Meyer CONTRACTOR: BNL CONTRACT METHOD: DOE Work Order CITY, STATE (Non-DOE): SMALL BUSINESS / MINORITY CONTRACT (Non-DOE):
SUB-CONTRACTOR (S): YES / / N0 / / AMOUNT $
PROJECTED PERIOD OF PERFORMANCE START: iii/6) (est) END: 9/30/85 7/ d. V3 PROJECTED FINANCIAL DATA (000's)
PROJECT FY 1983 TOTAL TOTAL TOTAL CARRY FY 83 FY 84 FY 85 VALUE OBLIG COSTED OVER BUDG BUDG BUDG 525 M --W 200 100 225 APPLICATION (RELATE THE PROJECT TO A SPECIFIC PLANNED ACCOMPLISHMENT)
Review of PRA studies for:
- 1. CESSAR System 80 FDA review l 2. Westinghouse Standard Plant FDA review l
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WORK-REQUIREMENTS (DESCRIBE WHAT IS TO BE PERFORMED)
The following analyses and assessments will be performed by this project: core-melt accident progressions with emphasis on containment loadings (pressure and temperature) and containment failure characteristic; evolution and release of radiological source term during core-melt accidents from fuel, primary system, and containment system; radiological consequences to the public from cere-melt accidents; and safety benefit from features to mitigate the consequences of core melt accidents. To support these analyses, the contractor will be required to maintain and modify the MARCH, CORRAL, MATADOR'and CRAC Codes as required in light of the current RES MARCH-2 and MELCOR development assimilate results of phenomenological studies (RES, ID00R, foreign, and DOE) andprogram and engineering research programs. In addition, an overall integrated assessment which considers all of these factors will be prepared for design. Products: miscellaneous letter reports for input to SERs, input to hearing testimony, if required.
. Major Product: (2) NUREG/CRs - FY 1985.
MODIFICATIONS (DESCRIBE MAJOR CHANGES TO THE PROJECT) i 4
i COMPLETE AS APPLICABLE -
Recemmended: Endorsed: Endorsed: Endorsed: Approved:
PROJECT MANAGER SECTION LDR BRANC!l CHF ASST DIR. DIV. DIR 1
(Initials)
(Cate)
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' OFFICE OF NUCLEAR REACTOR REu 5 TION
, PROJECT IDENTIFICATION
SUMMARY
(PIDS)'
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TITLE: Evaluation of MARK-I a $ SDob$Eud FIN: New i A 17nM CONTRACTNUMBER(Non-DOE): B&R NUMBER: ,NRR OPERATING PLAN 20-19-50-53-3 INDEX NO.:
DIVISION: DSI BRANCH: RSB PROJECT MANAGER: J. Meyer CONTRACTOR: BNL CONTRACT METHOD: DOE Work Order CITY, STATE (Non-DOE): - SMALLBUSINESS/MINORITYCONTRACT(Non-DOE):
SUB-CONTRACTOR (S): YES /' / NO ' / / AMOUNT $'
PROJECTED PERIOD OF PERFORMANCE ART * " > ~ - a -- --
?ns.:.W..il?%
END:'Af4'E$-
d, PROJECTED FINANCIAL DATA (000's) .
PROJECT FY 1983 -
TOTAL TOTAL TOTAL CARRY FY 83 '
FY 84 FY 85 VAUJE OBLIG COSTED OVER BUDG, BUDV BUDG
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APPLICATION (RELATE THE PROJECT TO A SPECIFIC PLANNED ACCOMPLISHMENT) -
Analyses of MARK-I BWR's '(Multi-plant category) for severe accidents as per SECY 82-1A requirements.
- Containment Analyses as part of NREP implementation program required assessments as per SECY-82-1A.
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WORK REQUIREMENTS (DESCRIBE WHAT IS TO BE PERFORMED)
The following analyses and assessments will be performed by this project: core-melt accident progressions with emphasis on containment loadings (pressure and temperature) and containment failure characteristic; evoluation and release of radiological source term during core-melt accidents from fuel, primary system, and containment system; radiological consequences to the public from core-melt accidents . End products include reports d:cumenting analyses; reviews licensee submittals; input to staff licensing actions related to degraded and/or molten- accidents; preparation of input for anticipated hearing.
Products: NUREG 1 CR .
NUREG 1 CR FY1983l FY 1984
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MODIFICATIONS (DESCRIBEMAJORCHANGESTOTHEPROJECT) -
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l COMPLETE AS APPLICABLE -
Recommended: Endorsed: Endorsed: Endorsed: Approved:
PROJECT MAfiAGER SECTION LDR BRANCll CHF ASST DIR. DIV. DIR (Initials)
(Date)
. h Bre:khev;n N ticnol Leb:;ratcry'
- Nuclear Regulatory Commission Analyses of Programs 90% Expended as of February 28, 1983 NRC Anticipated Account Action NRC FIN Expiration No. Requested No. of Funds Se f. G wff 3/'J. u b.
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Safety & Safeguards 04636 (1) A-3164 02/28/83 04637 (1) A-3168 03/15/83 04633 (1) A-3159 01/31/83 04638 (1) A-3167 02/04/83 l Nuclear Regulatory 05074 (1) A-3016 01/14/83 Research 05073 (2) A-3256 -
- t 04656 (1) A-3230 12/31/82
- 04293 (1) A-3231 02/14/83
. 04322 (2) A-3248 -
l (1) Increase funding level. -
(2) Request for de-obligation sent to DOE.
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BROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES. INC.
Upton. Long Island. New York 11973 (516)282N 3317 FTS 666' Office of the Director March 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 senc 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 Boyd, Program Assistant Division of Systems Integration Mail Stop F-1.IO2 U. S. Nuclear Reguistory Commission Washington, D. C. 20555 .
The proposal has been prepared in accordance vii.h the statement of work attached to the aforementioned letter. If there are any yiestions 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, l
H. C. Grahn
> Assistant Director for Financial Planning Enclosure ec: S. Boyd (2)
/B. L. Grenier J. Maher (2)
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'NRR TECHNICAL ASSISTANCE PROGRAM -
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SHEET DATE RECEIVED BY PPAS: f!d3 FIN (S): f)370[ d'
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