ML20127E906
| ML20127E906 | |
| Person / Time | |
|---|---|
| Site: | Limerick, 05000000, 05000447, Atlantic Nuclear Power Plant |
| Issue date: | 08/25/1983 |
| From: | Mattson R, Ogeka G BROOKHAVEN NATIONAL LABORATORY, Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML082170592 | List:
|
| References | |
| CON-FIN-A-3711, FOIA-84-243 20-83-631, NUDOCS 8505200251 | |
| Download: ML20127E906 (10) | |
Text
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NRC F:nu 173 u.s.Mucteam nEtutarcav commissioM caran NuMaisa
-20183-631 8-*
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STANDARD ORDER FOR DOE WORK -
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AUG 2 51983 ISUED TO: (OOE Offleel ISUED SY: INRC Office)
ACCOUNTING CITATION.
Brookhaven Area Office Office of Nuclear Reactor
^**ao*a'arion swoot Regulation, DSI 31X0200.203 S&RNUMSER 20-19-40-41-3 PExpORMeNo ORoANsZAnON ANO LOCAnON Brcokhaven National Laboratory.
FIN NUMBER Upton, New York See Attached
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WORK PERIOD.TMis ORDER
. PlXED E ESTIMATED O FIN TITLE a
FROM:
TO:
See Attached:
See Attached OSLIGATION AVAILABILITY PROVIDED BY:
S A. THIS ORDER 0
[fs'DdRYw "N"Is"E "a'i'eRor llilDNYS' SOS $'AN E78R 0%"R l 5 OF THE d
1a NUMs CsTED asOVE.
E;an1*nat C. TOTAL ORDERS TO DATE (TOTAL A & B) g g,4g1 0dS
- 0. AMOUNT INCLUDED IN "C" APPLICASLE TO THE " PIN NUMSER" CITED IN THIS ORDER.
S Ron attar hed FINANCI AL PLEXISILITY:
O FUNDS WILL NOT SE REPROGRAMMED SETWEEN FINS. LINE D CONSTITUTES A LIMITATION ON OBLIGATIONS
. AUTHORIZED.
PUNOS MAY BE REPROGRAMMED NOT TO 1 XCEED 210% OF FIN LEVEL UP TO SSOK.* LINE C CONSTITUTES A LIMITATION
@ ON COLIGATIONS AUTHORIZEO.1/ SE E BELOW STANDARD TEHMS AND CONDITIONS PROVIDEO 008 ARE CONSIDERED PART OF THIS ORDER UNLESS OTHERWiSE NOTEo.
ATTACHMENTS:
THE FOLLCWING ATTACHMENTS ARE HEREOY SECURITY:
MADE A PART OF THIS ORDER:
@ WORK ON THIS ORDER is NOT CLASSIFIED.
O STATEMENTOF WORK O WORK ON THIS ORDER INVOLVES CLASSIFIED D ADOITIONALTERMS AND CONDITIONg INFORMATION. NRC FORM 187 IS ATTACHEO.
O OTHER CEMARIts (Mehrence the progesel by number and date, and indieste if the ettsched statensent el work modifies the DOLtprogeset:
This order deobligates FY 83 funds in the amount of $60,000 from A3346 and obligates
$60,000'to A3711 as delineated in the attachment.
After acceptance, please send to the NRC Office of Resource Management, ATTN: D. Dandois and provide a copy to the Office of Nuclear Reattor Regulation, ATTN:
C. Paugh.
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ISSUING AUTHORITY ACCEPTING ORGANIZATION k )ll Yoger NattsOn. Director h
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(_) MREGdh J. OGEKA, CHIlf verts Division of Systems Intearation 20, mmuMTnATIVE BRANCH
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hanges on U$s withi 1/ Reprograminkumber and the Y//Y/ &3 CONTRACTING OFFICER NRc FO n Is-7 limited to iN the same B&R this Office must be ame Appreoriation Symbol. hat an apprOpria':e E1",ocat:
Form N to bi effectivecan se issued and counter-signeo to
-In order for thss otified within 5 days so t
- omplete the action prior to receipt of any bills.
8505200251 840920 PDR FOIA BHOLLYS4-243 PDR
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BROOKHAVEN NATIONAL LABORATORY
- ASSOCIATED UNIVERSITIES, INC.
Upton, Long Island, New York 11973 (516)282x 3317
= Office of the Director FTS 666' September 16, 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: GESSAR-FDA, Limerick-OL, FNP-ML," FIN A-3711,. being submitted for your review and approval. The pro-
, posal.is being submitted in response to a request from NRC dated August 8, 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 copies 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 total cost of this program is $1,280,000.
The funds obligated to date are $600,000.
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'Ihis proposal has,been prepared in accordance with the modification of 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.
Sincerel yours,
& ^ V_
l H. C. Grahn Assistant Director for Financial Planning Enclosure B.L.Grenier/
S. Boyd (2) cc:
J. Maher (2)
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U.S.NUCLEAtt REGULATOAY COMMi$$lON GATE CF PMCFoSAL tuRCFLOM 189 2
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Saptembar 12, 1983 PROJECT AND BUDGET PROPOSAL FOR NRC WORK w.
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'cestc7 TITLE Safety Evaluation of Core-Melt Accidents: GESSAR-FDA' A-3711 Limerick-OL, FNP-ML unc ean uvueen 20-19f40-41-3
%'4C CFFICE Nuclear Reactor Regulation CONT R ACT OR ACCOUNT
- ,ctconTRAcTOR Associated Universities, InC.
uvusEn 04231 Brookhaven National laboratory oossaauvueea O'TE UDron. New York 11973 PERICOOF PERFORMANCE COGNIZANT PERSONNEL ORG ANIZ ATION l FT5 PHONE NUMBER
$ TARTING DATE
%RC PROJECT M AN AGER l
J. Meyer REC /RSB 492-4754 01/14/83 COMPLETION DATE OTHE;4 NRC TECHNICAL STAFF 01/15/85 FIX BrOOkhaven
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OCE PROJECT M AN AGER
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i David SChveller Area of f1C e 666-3424
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h 5 2 666-2815 ONTRAcTOR-PROJECT MAN AGER H. J. KOuts BNL/DNE yj c. py-;/( -]-
W. Y. Kato 666-2444
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STAFP YEARS OF EF FORT sAound to acensar renr4 of s. vee *i lFY 1983 IFY 1984 IFY ]gg$
(FY IW 3 rect Seentific/Teenstel Otw Direct IGradedi f
TOTAL DIRECT STAFF YEARS COST PROPOSAL 08,9Cl Seierset unternes and services tE nesuding ADP)
ADP $wooort l
5.apmontreets Treat Essenses
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Griorel and Adretnistratrve TOTAL OPERATING Cost CAPITAL EQUIPMENT Fft CH ARGED:
TOTAL PROJECT COST 1963
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,e Safety Evaluation of Core-Melt Accidents:
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Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 3 PROJECT DESCRIPTION
- 1.. OBJECTIVE OF PROPOSED WORK a.
Background
x Consideration of severe accidents beyond the traditional design basis, including 5
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 _
.' H in generic rulemaking proceedings. Also the consideration of features to mitigate 9
the consequences of core melt accidents for nuclear facilities continues to be a -
major specific licensing activity. It is very important that the large amount of technical information available and being developed by, for example, NRC/RES in this area be appropriately assimilated, codified and evaluated in a way that is directly applicable to licensing needs. These needs are in three major areas.
(
First,'there is a need to'better understand the progression of core melt accident
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sequences up to and including associated core melt related phenomenology and the N
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implementation ~of these~ processes ~(and~their ~un'ceftiiinties) into an ove 611 asiess-ment 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 tera suspended in the containment, the effects on engineered safety features (ESFs) and mitigation features of this source term and finally the-
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release characteristics of-this source term following containment failure.
4 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.
b.
Objective 7
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The objective of the activities described in this proposal is 'to meet the above g
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 devel-
-oped from NRC/RES and other R&D programs. The scope will also include review and i
evaluation of licensee submittals and other pertinent information dealing with,the N,
subjects described below.
,% S-The analyses provided under this contract will form the basis for the licensing de "
cisions required on GESSAR-II FDA review (PRA portion), Limerick - OL review (FRA portion), 'and Floating Nuclear Plant - ML - follow-up PRA review (as per NTCP/ML i
rule) with respect to severe accident consideration.
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'j (See Continuation Sheet)
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Safety Evaluation of Core-Melt Accidents:
' f i...J Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 5 A
3.
WORK TO BE PERFORMED AND EXPECTED RESULTS (Cont.)
Subtask I.B - Data Acquisition: Engineering Programs
~
BNL will coordinate engineering mitigation feature input from FIN No. B-8626. BNL will provide cognizance of engineering 1
studies on containment and mitigation features of NRC/RES, IDCOR, DOE and foreign programs and relate the information 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 six months until the end of the' contract.
i Completion Date:
12/15/84 Subtask I.C. MARCH /MELCOR Code Maintenance and Development s
BNL will closely follow RES's MARCH-2 and MELCOR development programs. BNL will also follow the development of similar accident analysis codes (e.g., INCORE), both foreign and domestic, and in addition, specialty codes such as CORCON and CONTAIN. BNL will maintain current MARCH code capability with modifications as appropriate to the reactor type under
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consideration and the containment modifications-(mitigation r
features) being addressed. - This subtask supports directly the efforts in Subtask I.D.
Starting March 15, 1983, a let-b -
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ter report summarizing subtask status will be provided every six months until the end of contract.
s:
Completion Date:
12/15/84 Subtask I.D - Accident Analysis:
GESS R; Limerick; FNP 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 staff.
Particular attention will be given to those containment failure paraneters that are input to the consequence analysis (CRAC code). BNL will include in the set of accident pro-grassions those new sequences and containment conditions described in the " Severe Accident Risk Analysis" provided to NRC by PECO.
Ccapletion Dates:
Preliminary (letter report): 7/27/83 I.D.1 GESSAR Draft NUREG/CR revised:
12/1/83 I.D.2 CESSAR NUREG/CR report (final): 2/29/84 I.D.3 GESSAR s
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Safety Evaluation of Core-Melt Accidents:
Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 7 hd 3.
WORK TO BE PERFORMED AND EXPECTED RESULTS (Cont.)
Subtask II.A - Data Acquisition:
Source Term BNL will provide cognizance 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 NRR/DSI is responsible for providing state-of-technology data on source terms for use in the CORRAL /
MATADOR codes).
BNL will 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 March 15, 1983, a letter report summarizing sub-task status will be provided every six months until the end of the project. BNL will attend relevant ASTPO meetings i
and work closely with AEB, RSB, and ASTP0 staff in the source-term activity for Limerick, GESSAR and FNP.
Completion Date:
12/15/84-Subtask II.B - Data Acquisition:
Code Development BNL will maintain close contact with RES development of MATADOR, NAUA, CONTAIN and MELCORE. BNL will provide as-sessments of progress to date and recommendations for the course of further development.
BNL will also 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 summarizing subtask status will be provided every six months until the end of the project.
BNL will implement the following codes: CORSOR, SPARC, NAUA, and TRAPMELT.
III.B.1 CORSOR:
8/17/83 -
III.B.2 SPARC:
8/17/83 III.B.3 NAUA:
9/17/83 III.B.4 TRAPMELT:
10/17/83 Completion Date:
12/15/84 m;
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(See Continuation Sheet) a 4
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.l i.l Safety Evaluation of Core-Melt' Accidents:
Project
Title:
CESSAR-FDA, Limerick-OL, FNP-ML
- p. 9 s
3' 3.
WORK TO BE PERFORMED'AND EXPECTED RESULTS (Cont.)
II.D.1 GESSAR
- Review response to Q-1s and develop Q-2s :
5/18/83 II.D.2 GESSAR
- Provide assessment of vendor submittals; aid in preparation of NRC staff presentation:
Ongoing II.D.3 Limerick - Provide Assistance in Staff Pre-paration of Hearing Testimony:
Ongoing II.D.4 Limerick - Provide assessment of SARA report:
1/15/84 II.D.5 FNP -
Initial Review of OPS-PRA (Q-Is):
7/31/84 II.D.6 FNP -
Issue Q-2s:
9/15/84 Task III - Consequence Analysis Estimated Level of Effort in FY83:
7 191 Completion Date:
12/15/84 Estimated Level of Effort in FY84: 7 HM Estimated Imvel of Effort in FY85:
1 MM NOTE: The AEB of NRR/DSI is responsible for all NRR consequences analyses. As such rx Task III will be limited to the following activities related to consequences g
analysis:
(1) CRAC analyses in order to determine the impact on risk of varia-tions in the Task I & II analyses based on phenomenological uncer-tainties, engineering uncertainties and the incorporation of miti-
-gation 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 BNL will keep abreast of the state of technology in the area of consequence analysis 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 c
i the sites used 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 six months until the end of the t
proj ect.
Completion Date:
12/15/84
]
iJ (See Continuation Sheet) r
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-Safety Evaluation of Core-Melt Accidents:
Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 11
( 3 3.
WORK TO BE PERFORMED AND EXPECTED'RESULTS (Cont.)
Subtask IV.B - Integration: Impact on Risk BNL will present results of analyses and assessments in Task I, II'and III in terms of risk values (including CCDFs) and changes in risk values due to changes in con-tainment designs (mitigation features) or changes in damage state probabilities.
Completion Dates:
IV.B.1 GESSAR
- 2/29/84 IV.B.2 Limerick - Draft Report on Mitigation Features (milestones may change due to Indian Point Hearing Schedule):
1/31/84 IV.B.3 Limerick - Mark-II with Mitigation Final Report on Mitigation Features:
4/15/84 IV.B.4 Limerick - Impact of New Source Terms (in particular, RES FIN No. B-6747) on BNL Risk Studies:
9/15/83 r
i Subtask IV.C - Integration: Uncertainty Analysis v
BNL will develop a methodology for translating containment matrix element uncertainties and other uncertainties (e.g.,
in damage states and CRAC analyses) into uncertainties in final risk and risk reduction values making use of the RES and industry programs in this area. Starting March 15, 1983, a letter report summarizing subtask status will be provided every six months until the end of the project.
Completion Dates:
12/15/84 Level of Effort and Period of Performance This modification increases the level of effort by 11 man-months. The overall level of effort is 133 man-months (11.1 PSY) over a two year period.
b.
Meetings and Travel BNL staff will participate in several meetings at the NRC Headquarters (two one-day meeting each quarter in Bethesda to discuss performance and work progress) and at other locations (two one-day meeting each quarter in Bethesda or at licensee /appli-cant headquarters with licensee / applicant and NRC staff is anticipated) to obtain source material for this program. BNL staff will attend hearings (one-week travel status for BNL staff.at the Limerick Hearing is anticipated); also BNL staff may visit other laboratories or institutions and participation at pro'fessional meetings J.
(See Continuation Sheet)
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Safety Evaluation of Core-Melt Accidents:
Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 13 6.
REPORTING REQUIREMENTS (Cont.)
Business Letter Reports A monthly business letter report will be submitted by the 20th of the month to the Project Manager, J. F. Meyer (DSI),.with copies provided to the Director, Division of Systems Integration,' ATTN:
,T. Speis, S. Boyd, 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, and the reporting period and will contain 3 sections as follows:
a.
Project Status Section
- 1) A listing of efforts completed during the period, milestones reached, or if missed, an explanation provided.
- 2) Any problems or delays encountered or anticipated and recommendations for reso_lution. _(NOTE:
If_ the rec.ommended_re. solution _ involves a con-tract modification, i.e., change in work requirements, level of effort (costs), or period of performance, a separate letter will be prepared and submitted to J. F. Meyer.
- 3) A summary of progress to date.
(This may be expressed in terms of percentage completion for each task.)
c
- 4) A brief summary of plans for the next reporting period.
q, b.
Financial Status Section BNL' will provide the total cost (value) of ~ the project as reflected in the proposal (NRC Form 189), the total amount of funds obligated to date, and the balance of funds required to complete the work.
Total Funds Balance of Funds Projected Obligated by Fiscal Year Project Cost to Date FY-FY-FY >
BNL will provide the amount of funds expended (costed) by category during the period and total cumulative year-to-date as follows:
Period Cumulative Direct Salaries Indirect Salaries ADP Support Travel Subcontracts Equipment & Materials Overhead Total
(%)*
O
- Percentage of funds received (year to-date) against funds obligated.
.i (See Continuation Sheet)
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Safety Evaluation of Core-Melt Accidents:
Project Title':
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 15 6.
REPORTING REQUIREMENTS (Cont.)
)
- Common costs will be reported against Docket 50-900. Common costs are for those costs incurred for effort such as preparatory or start-up efforts to interpret and reach agreement on methodology, approach, acceptance criteria, regulatory position, or TER format; efforts associated with the " lead plant" concept that might be in-volved during the first one or two plant reviews as estimated by the contractor; meetings / discussions involving the above efforts to provide orientation, background knowledge, or guidance at the beginning or during performance of work; and any technical effort applied to a category of facilities, e.g.,
some effort on Task IV might.be appropriate coimmon cost. In the case of the latter example, these costs will be prorated equally to only those facilities to which the effort applies.
Development of methodologies, criteria or technical positions are not fee-recoverable and, therefore, will not be categorized as common costs. Management and related support costs chargeable directly to the effort will not be reported as common costs and will, therefore, be charged in proportion _to the other direct costs. associated with those facilities during the reporting period.
NOTE: Common costs will be accrued by BNL on a monthly basis and prorated by NRC equally among the facilities identified under the effort at the end of each fiscal year or at the completion of the effort, whichever occurs first.
7.
SUBCONTRACTOR INFORMATION
-~
BNL does not intend to subcontract any portion of this work. In the event a sub-contract is anticipated, BNL will notify NRC prior to initiating it.
8.
NEW CAPITAL EQUIPMENT REQUIRED
-None.
9.
SPECIAL FACILITIES REQUIRED None.L
- 10. CONFLICT OF INTEREST INFORMATION
.There are neither significant contractual nor organizational relationships of the Department of Energy, BNL and employees, or expected subcontractors or consultants on this proposal, with industries regulated by the NRC and suppliers thereof that give rise to an apparent or actual conflict of interest.
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