ML20127F024
| ML20127F024 | |
| Person / Time | |
|---|---|
| Site: | Limerick, 05000000, 05000447, Atlantic Nuclear Power Plant |
| Issue date: | 11/16/1983 |
| From: | Mattson R, Ogeka G BROOKHAVEN NATIONAL LABORATORY, Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML082170592 | List:
|
| References | |
| CON-FIN-A-3711-4, FOIA-84-243 20-84-010, 20-84-10, NUDOCS 8505200296 | |
| Download: ML20127F024 (13) | |
Text
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,5 '~ NpC FonM 173 u.s. Nuctsan nacutarcR v couusssioN cats n NUM5E R 20-84-010
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STANDARD ORDER FOR DOE WORK g ig ISUED TO: l DOE Offleel ISSUED SY: (NRC Office)
ACCOUNnNG CITATION.
Brookhaven-Area Office Office of Nuclear Reactor Aao'a'*T'o" S**
Regulation, DSI 31 X0200.204 gen NuMcEn PERpORMINo ORoANizAnON ANo LOCAnON 20-19-40-41-3 f
Brookhaven National Laboratory Upton, New York A3711-4 i
WOR K etRico.Yms ORDER Fue TITLE FIXED Q
' ESTIMATED O l
Safety Evaluation of. Core-Melt Accidents: GESSAR-FDA, FROM:
TO:
j Limerick-OL. FNP-ML 01/14/83 01/15/85 08 LIGATION AVAILABILITY PROVIDED BY:
- 4. THIS ORDER S 400,000
EDENNEME "IPP Of SYW80
" " ^" "
F I AN E FlR OUR S OF THE S
1&R NUMBER" CITED A80VE.
614.000 C. TOTAL ORDERS TO DATE
'(TOTAL A & BI g 1.014.000 O. AMOUNT INCLUDED IN "C" APPLICASLE TO THE " FIN NUMBE R" CITED IN THIS OR DER.
S FINANCIAL FLEXISILITY:
3 FuNos WILL NOT BE REPROGRAMMED BETWEEN FtNS. LINE D CONSTITUTES A LIMITATION ON OSLIGATIONS
' AUTHORIZED.
Q FUNDS MAY BE REPROGRAMMED NOT TO EXCEED 210% OF FIN LEVEL UP TO 850K. LINE C CONSTITUTES A LIMITATIO ON OSLIGATIONS AUTHOpl2ED.
STANDARD TERh5 AND CONDITIONS PROVIDED DOE ARE CONSIDERED PART OF THIS ORDER UNLESS OTHERWISE NOTED.
ATTACHMENTS:
THE FOLLOWING ATTACHMENTS ARE HERE8Y SECURITY:
MADE A PART OF THIS ORDER:
$ WORK ON THIS ORDER IS NOT CLAS$1FIED.
- % STATEMENT OF WORKO ADDITIONALTERMS AND(CONDITIONSModifiCation)
O WORK ON THl3 ORDER INVOLVES CLASSIFIED INFORMATION. NRC FORM 187 IS ATTACHED.
O OTHER REMARKS (Rektence the proposal by number and date. and indicate if the ottsched statement of work modifies the DOE proposeq:
This order (1) provides a modification to the.BNL proposal dated December 10, 1982 and the NRC DOE Work Order 20-83-602-dated August 8,1983,(2) provides incremental funds for continuation of work in accordance with the BNL proposal (Revision 1) j dated September.12,1983, (3) changes the Project Manager from J. Meyer to J. Carter, and (4) reqeusts that BNL submit a revised proposal in the format of the
)
)ro xisg1 C NftW aYc$gntengRg{,g{y. send to the NRC Office of Resource Managem tete, p D. Dandois and provide,a copy to the Office of Nuclear Reactor Regulation, ATTN:
C. Paugh.
O A pihtG AUTMPRLTY ACCEPTING QRGANIZATION SogYrJ.
a n
Division of Systems Integration
.ORNR[J. OGEKA, CHIEF m....
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DATE
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N "unif3 MI5YE DKANGM NIC FORu 17s as-m jf /j 4,/g-f0NTRACTING OFFICER B5052g296040920 hLLYO 243 PDR
- 9 BROOKHAVEN NATIONAL LABORATORY ASSOCIATED UNIVERSITIES, INC.
.m Upton. Long Island. New York 11973 (516) 282s 3317 Office of the Director FTS 666' November 18, 1983 Mr. David Schweller, Manager Brookhaven Area Office U. S. Department of Energy Upton, New York 11973
Dear Mr. Schweller:
Enclosed is one cop _y of_a_ proposal _without _ attachments _.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 proposal is being submitted in response to a request from NRC dated November 1, 1983.
Two copies have been sent to Mr. J. Maher, Depart-ment of Energy one copy has been sent to Mr.
B. L. Grenier, Nuclear Regula-tory 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 $1,110,000.
The funds obligated to date are $1,000,000.
This 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.
Sincerely yours, H. C. Grahn Assistant Director for Financial Planning Enclosure cc:
S. Boyd (2)
B. L. Grenier J. Maher (2)
tRC PEIM.189 U.S. NUCLEAR REGULATORY COMMA &SION OATE Of P5do*CsAL M"
7 Saptember 12, 1983 I
PROJECT AND BUDGET PROPOSAL FOR NRC WORK usw (K) mevisio~ wo 1
- 8J' CT T8 Safety Evaluation of Core-Helt Accidents: GESSAR-FDA, A-3711 Limerick-OL, FNP-HL Nmc B&R Nuungm vzC crriCE 20-19-40-41-3 Nuclear Reactor Regulation CONT R ACTom acCovNT sesConTRACToR Associated Universities, Inc.
suusan Brookhaven National laboratory 04231 u Ta oots&msuusta Upton, New York 11973 COGNIZANT PERSONNE L O RG ANIZ ATION FT5 PHONE NUMBER PE RIODOF PE RFORMANCE
%RC PROJECT M AN AGER STARTING OATE J. Mever REG /RSB 492-4754 01/14/83 OTHER NRC TECHNICAL STAFF COMPLETION DATE 01/15/85 FIX
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TOTAL DIRECT STAFF YEARS COST PROPOSAL l
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PROJECT AND BUDGET PROPOSAL FOR NRC WORK Novanbar 10, 1983 u new aavisio = =o
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einnuMeta Safety Evaluation of Core-Melt Accidents: GESSAR-FDA, Limerick-OL, FNP-ML A-3711 mmCsaa=vuesa N!:C OFFICE Nuclear Reactor Regulation 20-19-40-41-3 sca Co=TR ACTom Associated Universities, Inc.
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TOTAL DIRECT STAFF YEARS COST PROPOSAL l
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ADP Support Sutwortreets Treal Emoonse l
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TOTAL OPE R ATING COST l
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., t; Safety Evaluation of Core-Melt Accidents:
Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 3 PROJECT DESCRIPTION 1.
OBJECTIVE OF PROPOSED WORK s.
Background-Consideration of severe accidents beyond the traditional design basis, including full core melt accidents, is an important part of NRC's overall safety assessment and.therefore is becoming an important ingredient in specific licensing actions and in generic rulemaking proceedings. Also the consideration of features to mitigate the consequences of core melt accidents for nuclear facilities continues to be a major specific licensing activity.
It is very important that the large amount of
~
i 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 sequences _up_to.and including associated core melt related phenomenology and the implementation of these processes (and their uncertainties) into an overall assess-ment of containment loading and failure modes. The impact of mitigation strategies on 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 C
safety features (ESFs) and mitigation features of this source term and finally the
(,
release characteristics of this source term following containment failure.
i 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 The objective of the activities described in this proposal.is to meet the above needs.
The scope of this work will be limited to addressing immediate NRC/NRR licensing con-cerns using the state-of-the-art codes and the analyses and experimental data devel-oped from NRC/RES and other R&D programs.
The scope will also include review and
. evaluation ~of licenses submittals and other pertinent information dealing with the subjects described below.
The analyses provided under this contract will form the basis for the licensing de-cisions required on GESSAR-II FDA review (PRA portion), Limerick - OL review (PRA portion), and Floating Nuclear Plant - ML - follow-up PRA review (as per NICP/ML rule) with respect to severe accident consideration.
r%
)
w (See Continuation Sheet)
.-._.---...-__..-_.____,__._--._,-..-_-_-_____,__._.,.L.-_-.-..-_
Safety Evaluation of Core-Melt Accidents:
S Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 5 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 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.
Completion Date:
12/15/84 Subtask I.C - MARCH /MELCOR Code Maintenance and Development 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 consideration and the containment modifications (mitigation
~
features) being addressed. This subtask supports directly the efforts in Subtask I.D.
Starting March 15, 1983, a let-ter report summarizing subtask status will be provided every six months until the end of contract.
Completion Date: _
12/15/84 Subtask I.D - Accident Analysis: GESSAR; 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 parameters that are input to the consequence analysis (CRAC code). BNL will include in the set of accident pro-gressions those new sequences and containment conditions described in the " Severe Accident Risk Analysis" provided to NRC by PECO.
Completion Dates:
Preliminary (letter report): 7/27/83 I.D.1 GESSAR I.D.2 GESSAR Draft NUREG/CR revised:
12/1/83 NUREG/CR report (final)<
2/29/84 I.D.3 GESSAR S_/
(See Continuation Sheet)
T Safety Evaluation of Core-Malt Accidents:
Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 7 3.
WORK TO BE PERFORMED AND EXPECTED RESULTS (Cont.) _
l 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 provida 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).
i 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 ASTP0 meetings and work closely with AEB, RSB, and ASTP0 staff in the source-term activity for Limerick, GESSAR and FNP.
h 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, c
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 proj ect.
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
I m
(See Continuation Sheet)
2 Safety Evaluation of Core-Melt Accidents:
Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 9 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 MM Completion Date:
12/15/84 Estimated Level of Effort in FY84:
7 MM Estimated Level of Effort in FY85:
1 MM
. NOTE: The AEB of NRR/DSI is responsible for all NRR consequences analyses. As such O
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 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 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 project.
Completion Date:
12/13/84
..)
(See Continuation Sheet)
e
,j Safety Evaluation of-Core-Malt Accidents:
- f 7 Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 11 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.
t Completion Dates:
i IV.B.1 GESSAR
- 2/29/84 IV.B.2 Limerick - Draf t Report on Hitigation Features (milestones may change due to Indian Point Hearing Schedule): 1/31/84 1
IV.B.3 Limerick - Mark-II with Hitigation 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 W.,
Subtask IV.C - Integration: Uncertainty Analysis w.:
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 i
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 headquar'ters 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 professional meetings s
j (See Continuation Sheet)
Safety Evaluation of Core-Melt Accidents:
({'
Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 13 L
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 r.eports 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 resolution.__(NOTE:_ If_the_ recommended.lesolution 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. Heyer.
- 3) A sussary of progress to date.
(This may be expressed in terms of percentage completion for each task.)
p
- 4) A brief summary of plans for the next reporting period.
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.
l 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:
l Period Cumulative l
Direct Salaries Indirect Salaries i
I ADP Support Travel Subcontracts Equipment & Materials i
Overhead Total
(%)*
- Percentage of funds received (year to date) against funds obligated.
gr l
t j
(See Continuation Sheet) l l
1
.,, ~
s Safety Evaluation of Core-Malt Accidents:
/N.
Project
Title:
GESSAR-FDA, Limerick-OL, FNP-ML
- p. 15
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6.
REPORTING REQUIREMENTS (Cont.)
- Common costs _will be reported against Docket 50-900. Common costs are for those s;
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 common 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.
p 7.
SUBCONTRACTOR INFORMATION L ~
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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20-84-164 DATE STANDARD ORDER FOR DOE WORK g 1 61904 MUED TO: (DOE Offleel ISSUED BY: (NRC Officol ~
ACCOUNTING CITATION.
.Brookhaven Area' Office.
Office of Nuclear Reactor
- ^**ao'al*T'oa mmoi-Regulation, DSI 31X0200.204.
esR NumeER PERFORMtNG ORGANIZATION AND LOCATION 20-19-40-41-3 Brookhaven National Laboratory FIN NuMeER Upton, New York.
A3711-4 WORK PERIOD THIS ORDER FIN TITLE FlXED Q ESTIMATED O Safety Evaluation of _ Core-Melt Accidents:
GESSAR-FDA, FROM:
TO:
Limerick. OL. FNP-ML 01/14/83 01/15/85 08 LIGATION AVAILABILITY PROVIDED BY:
A. THIS ORDER S 40,000 S. TOTAL OF ORDERS PLACED PRIOR TO THIS DATE WITH THE PERFORMING ORGANIZATION "Ed"NEN^"ENEI" SOS'ATI N SMOL" AND NE FIRST FOUR DIGITS OF ME S
E 3.342.000 L
c.-.sOTALORoERs-TO DA ::
(TOTAL A a el S 3,382,000 D. AMOUNT INCLUDED IN "C" APPLICA8LE TO THE " FIN NUMBER" CITED IN THIS OR DER.
S g
FINANCIAL PLEXISILITY:
- @ FUNDS WILL NOT BE REPROGRAMMED SETWEEN FINS. LINE D CONSTITUTES A LIMITATION ON OSLlGATIONS
' AUTHORIZED.
- Q FUNOS MAY BE REPROGRAMMED NOT TO EXCEED 210% OF FIN LEVEL UP TO $50K. LINE C CONSTITUTES A LIMITATION ON OSLIGATIONS AUTHORIZED.
STANDARD TERMS AND CONDITIONS PROVIDED DOE ARE CONSIDERED PART OF THIS ORDER UNLESS OTHERWISE NOTED, ATTACHMENTS:
~ THE FOLLOWING ATTACHMENTS ARE HEREBY SECURITY:
MADE A PART OF THIS GROER:
@ WORK ON THIS ORDER IS NOT Ci ASSIFIED.
a O STATEMENT OFWORK O WORK ON THIS ORDER INVOLVES CLAS$1FIED O ADDITIONALTERMS AND CONDITIONS INFORMATION. NRC FORM 187 IS ATTACHED.
O OTHER REMARKS. (Mekvence the proposal by number and date, and indicate if the ettsched statement of work modifies the DOE propose 0:
-This order provides 1.ncremental funds for continuation of work on this project in accordance with the-BNL proposal dated November 18, 1983.
t
'After acceptance [please/ send to the NRC Office of Resource Management, ATTN: D. Dandois and provide a copy to the Office of Nuclear Reactor Regulatione ATTN:
C. Paugh.
ISSUING AUTHORITY ACEPTINGARfsANIZATION og r J. Mattson.' Directorb! ah, 4
i ision of Systems Integration 16 /p h&(SchweIler 7 oAre
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ywg gg wgewg,w--,+=,w=.w gwvW-w.-e weW*mr' m e-ewr wme+-w-4-eesw ee-w-wmes-- M-e*
sew---v-ee=ra**wewwwm-v wa.-e-mi.,+er.-wT-t