ML20127E418
| ML20127E418 | |
| Person / Time | |
|---|---|
| Site: | Limerick, 05000000, 05000447, Atlantic Nuclear Power Plant |
| Issue date: | 12/10/1982 |
| From: | Harold Denton Office of Nuclear Reactor Regulation |
| To: | Beckwith C NRC |
| Shared Package | |
| ML082170592 | List:
|
| References | |
| CON-FIN-A-3711, FOIA-84-243 NUDOCS 8505200069 | |
| Download: ML20127E418 (9) | |
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DISTRIBUTION December 10, 1982 Ep%HIXKIIH 6fficial Contract File ECase TSB R/F HDenton DCorley GrMiiU JCarter JFunches HEMORANDUM FOR:
Charles Beckwith, Secretary Senior Contract Review Board FROM:
Harold R. Denton, Director Office of Nuclear Reactor Regulation
SUBJECT:
REQUEST FOR SENIOR CONTRACT REVIEW BOARD APPROVAL OF AN NRR TECHNICAL ASSISTANCE PROJECT - " SAFETY EVALUATION OF CORE-MELT ACCIDENTS: CASEWORK REVIEllS FOR LIMERICK, GESSAR, FNP" (FINA3711)
Enclosed for SCRB approval are the Project Descriptive Summary, the draft Statement of Work, and the Interoffice concurrences from RES, NMSS, I&E, AE00, and Region IV for the subject project. Concurrences from the other regional offices are assumed since the request for reply within the 10-day response period has elapsed.
If you need further information, please contact B. L. Grenier.
Please inform him of the date, time and location of the SCRB meeting to review this project so that we may have the appropriate NRR people in attendance to answer any questions the SRCS may have.
Original Signed by Jesse Funches k'
Harold R. Denton, Director Office of Nuclear Reactor Regulation
Enclosure:
As stated I
cc:
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ENCLOSURE l' STATEMENT OF WORK q
' Titl e:
Safety Evaluation of C' ore-Melt Accidents:
GESSAR-FDA, Limerick-OL, FNP-ML l
(FIN s:-
A-3711 B&R #:
20-19-40-41-3
.i Project Manager:
J.Meyer,-(FTS'492-4754) 1 Technical Mo'nitor:
J. Meyer, (FTS 492-4754)
Backcround and Objective Consideration of severe accidents' beyond the traditional design bas.is,fincluding full core melt accidents, is.an important part of NRC's overall safety. assessment and therefore is becoming an important ingredierit 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 1:entinues i
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, 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 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 as a function of the assumptions regarding accident sequences, phenomenology l
and ~ mitigation hardware.
These radiological consequences must be further analyzed in a licens'ing context with a full appreciation of its regulatory implications.
The-objective of the activities described in this Statement o'f Work is to meet '
the above needs.
The scope of this work will be limited to addressing,immediate NRR licensing concerns using the state-of-the-art codes and the analyses and experimental data developed from NRC/RES'and other R&D programs.
The scope will also include i
review and, evaluation of licensee submittais and other pertinent information dealing with' the subjects ' described below.
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- lThe analyses provided_ under this contract will form the basis for the licensing
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. decisions required'on GESSAR-II FDA review (PRA portion)
Limerick --0L review (PRA portion, and Floating. Nuclear Plant - ML - followup _ PRA review (as per NTCP/ML rule with respect to severe accident consjderation.
Inis-contract replaces contract FIN No. A-3399.
Although much of the work in this request for proposal (RFP) is a continuation of the activities in A-3399 it was decided'to initiate a-new contract for the following reasons:
- (1)
The tasks'are restructured from being project oriented (Task-I: Grand Gulf; Task-II:
FNP; Task-III:
GESSAR) to being functional oriented (Task-I:
Containment Loading and Failure Analysis; Task-II:
Radio-nuclide Releases; Task-III:
Consequence Assessment; Task-IV:
Risk Assessment Sumary).
This has been done to facilitate technical assistance management'and. contractor accountability.
(2)' The Limerick BWR study has replaced the Grand Gulf BWR study because of_a shift in regulatory / licensing needs.
The Limerick PRA study now has higher priority.
(3). The period of performance has been considerably extended over that in LA-3399 due to delays in the issuing of the manufacturing license (ML) for the FNP (a PRA is to' be completed by OPS within two years of their ML..
The extensive analysis and assessment performed, code capability developed and' experience gained under A-3399 has been taken into account in developing this RFP.
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Work Requirements The Work Requirements are:
Task I. - Severe-Accident Progression Analysis:
Reactor Systems / Containment Systems Loading and Failure Modes.
Estimated Level of Effort in FY83: 24 MM Completion Date: 12/15/84 Estimated Level of Effort in FY84:
29 MM Estimated Level of Effort in FY85:
2 MM Subtask I.' A - Data Acquisition: Phenomenology Programs Coordinate'phenomenological input from FIN No. B-8635.
Provide cognizance of and foreign programs. phenomenological studies of RES, IDCOR, Relate the informa. tion gathered to MARCH predictions. 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 the contract.
......... Completion Date: 12/15/84 Subtask I.B - Data Acquisition:
Engineering Programs Coordinate engineering mitigation feature input from FIN No. B-8626.
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 suppor.ts directly the
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efforts in subtask "I.D.." _ Starting December 15, 1982, a 3
letter report summarizing subtask-status shall be provided every three months.until the end of the contract.
......... Completion Date: 12/15/84
' Subtask I.C - MARCH /MELCOR Code Maintenance and Development:
Participate in RES's MARCH-2 and MELCOR develooment program Follow the development of similar accident 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 the-reactor type under considerationandthecontainmentmodifications(mitigation features) being addressed. This subtask supports directly the efforts in subtask "I.D" Starting December 15, 1982, a letter report summarizing -subt.ask status -shall be provided every three months until the end of contract.
......... Completion Date: 12/15/84.
t Subtask I.D - Accident Analysis:
GESSAR; Limerick; FNP For'each_ reactor type under consideration, analyze the accident' progressions up to and including con _ tai._nment fafTUre 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 GESSAR-preliminary.... March 1,1983 I.D.2 GESSAR-revis ed........ August 1, 1983 -
,I.D.'3 GESSAR-HUREG/CR Report.. November 15, 1983 I.D.4 Limerick-final analysis with Mitigation Features.. December. 31, 1982 I.D. 5 FNP-preliminary....... August 31, 1984 I.D.,6 TiiF-revised........... November 1, 1984 Subtask I;E - Accident Assessment: GESSAR, Limerick', FNP Review PRA submittals for these reactors within the ' scope 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 of Task I for inclusion in staff assessments......... Completion Dates:
I.E.1 GESSAR-review response to Q.1's and develop Q.2's... April 1,1983 1.E.2 GESSAR-provide assessment of vendor submittal; aid in preparation of staff presentations.... Ongoing I.E.3 Limerick-provide assistance in staff preparation of hearing testimony.
... 0ngoing I.E.4 FNP-initial review of OPS-TRA.(Q1's)
..... July 31, 1984 I.E.5 FNP-issue "Q2s"....'.. September 15, 1984 1
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Task-II.- Radionuclide-Release Assessment
. Estimated Level of Effort in FY83:
12 MM Completion Date:
12/15/84 Estimated Level of Effort in FY84:
14 MM Estimated Level of Effort-in FY85:
1 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 1
.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 (e.g., suppression pool temperatures and particle. sizes-for determination of decontamination factors for BWRs).
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.
......... Compl etion Date :
12/15/84 Subtask II.B --Data-Acquisition:
Code Development Maintain close contact with RES development of MATADOR, NAUA CONTAIN AgD MELCORE.
Provide assessments of progress 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 provided every three months until the end of the project.
......... Compl etion Date:
12/15/34 Subtask II.C;- Accident analysis:
GESSAR; Limerick; FNP For each reactor type under consideration, perform analyses of the release fractions and other containment failure parameters important in the subsequent consequence l
- analysis.
This effort is closely coupled to Subtask I.D and should be performed concurrent with Subtask I.D.
.......... Completion Dates:
II.C.1 GESSAR-preliminary. March 1,1983 II.C.2 GESSAR-revised..... August 1, 1983 II.C.3 GESSAR-NUREG/CR report
... November 15,1983 II.C.4 Limerick-Final analysis with Mitigation Features..... December 31, 1983 II.C.5 FNP-preliminary.... August 31, 1984
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II.C.6 ThP-revised
... November l', 1984 f
Subtask II.D - Accident Assessment:
GESSAR; L'imerick; FNP i
- Review PRA sumittals in the areas within the scope of
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Task II by utilities / vendors.
Generate questions to the utilities / vendors based on this review.
Participate in e
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Provide write ups of-reldvant areas within the. scope of Task II-scheduled for inclusion in staff assessments.
And conform to scheduled provided by. staff below:
..... Completion Dates:
-II.D.1 GESSAR-re~ view response to Q.I's and develop Q'2s.. April l' 1983' II.D.2 GESSAR-provide assessment of vendor submittals; aid in preparation of staff ~ presentation..... Ongoing II.D.3 Limerick-provide assistance in in staff preparation of hearing testimony
..... Ongoing II'D.4 FNP-initial review of OPS-PRA'- (Q1s)
.... July 31.-1984
.II.D.5 FHP-issue "Q2s"
...... Sept 15, 1984
- Task III - Consequence Analysis Estimated Level of Effort in FY83: 6 MM Completion Date: December 15, 1984 Estimated Level of Effort in FY84: 7 MM Estimated Level of Effort in FY85: l'MM-
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.(Note: -The-AEB of NRR/DSI is* responsible for all NRR consequences analyses.
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As such Task III will ~ be limited to the following ~ activities related g
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 uncertainties and the incorporation of mitigation features
-(2) -CRAC analyses' determining risk values at the request of AEB through RSS (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 anlaysis including working knowledge 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
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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.
....... Completion Date: 12/15/84.
Subtask III.B - Accident Analysis Perform CRA' analyses consistent with the MARCH / CORRAL C
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 Milestone in II.C)-
........ Completion Date: 12/15/84
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TasR IV - Risk Assessment Summary (Inteoration of Tasks I, II and III)
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Estimated-Level of Effort in FYS3:
12 MM Completion Date:
12/15/84 Estimated Level of Effort in FY84:
12 MM-Estimated Level of Effort in FY85:
2 MM
- Subtask IV.A - Integration
Containment Matri.x 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 GESSAR-IV.A.2 LT5 TAT preliminary... March 1, 1983' revi sed....... August 1, 1983
.IV.A.3 GE55AR-NUREG/CR Report.. November 15, 1983 IV.A.4 Limerick-final analysis with Mitigation Features Qecember_31._1983 IVT5 FNP-preliminary August 31, 1984 IV.'A.6 TIF-revised.
November 1, 1984
, Subtask IV.B -- 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 glues due to changes in containment designs-(Mitigation features) or changes in damage state p'robabilities.
..... Completion Dates :
GESSAR.......... August 1, 1983 Limeric k........ December 31,.1982 Subtask IV.C - Integra' tion:
Uncertainty. Analysis Develop a methodology fo.r 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 Level of Effort and Period of Perfomance The level.of-effort is estimated at 122 man-months over a 25 month period.
Technical Reporting Requirements:
All products which art required from this contract (including Q1s, Q2s.,
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 Requirements 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".
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Business Letter Report
- AL monthly business letter report will be submitted by the 15th of the month to the Project Manager with copies provided to the Director, Division of Systems Integration,-ATTN:. S. Boyd, T. Speis, B. Sheron, DSI, and Mr. B. L. Grenier, NRR.
These reports will identify-the title of the project, the FIN, the Principal Investigator, the period of performance, a'nd the reporting period will contain 2 sections as follows:
Project Status Section For'each 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 of delays encountered or anticipated and recomendation for resolution.
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3.
A~ summary of progress to date (this may be expressed in terms.of percentage completion for each task).
4.
Plans for the next repor. ting period.
Financial Status Section 1.
Provide the total cost (value) of the project as reflected in,the proposal and the total amount of funds obligated to date.
2.
Provide the total amount of funds expended (costed) during the period and total: cumulative to date as follows:
3 Period Cumulative a.
Labor-related costs b.
Computer services c..
Travel d.
Subcontracts e.
Equipment
-Total
(%)2]
3.
Provide the total amount of funds expended-during.the period (costed) and cumulative to date for each plant by docket number.
GESSAR-II - 05000447, Limerick - 05000352, FNP - 05000437. y y If the recommended resolution involves a contract modification. -1.e., changes in work requirements, level of effort (costs), or period of performance, a separate letter should be prepared and, submitted to the Director, Division of Systems
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Integration, ATTN: S. Boyd, E. Marinos, DSI and copy provided to the Project Manager and B. L. Grenier, NRR.
2f Provide percentage against total funds oblicated to date.
- 3/ Cost of licensing nuclear power 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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Meeting and Travel 1
-1.
Two one-day meetings each quarter in Bethesda.to discuss performance and work j
progress should be planned and budgeted.
2..
Five topical professional meetings on relevant topics should be planned and budgeted (one attendee).
3.
-Two one-day meetings each quarter in Bethesda or at licensee / applicant head-quarters with licensee / applicant and NRC staff.
4.
One-week travel status for two contractor staff at Limerick hearing.
NRC Furnished Materials The NRC will provide any documentation relevant to the above tasks including that which ois submitted by licensees /appli. cants during the course of this project.
NRC will furnish copies of the latest relevant codes together with appropriate Users Iianauals and description of subroutines.
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