ML20028D560
| ML20028D560 | |
| Person / Time | |
|---|---|
| Issue date: | 09/30/1982 |
| From: | Mattson R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20027A678 | List:
|
| References | |
| CON-FIN-A-7275-2, FOIA-82-543 20-82-710, NUDOCS 8301190279 | |
| Download: ML20028D560 (6) | |
Text
J NRC a omu 173 u s.Nucttan stGutATOmv cowusssioN omot a Nuust a 20-82-710 g STANDARD ORDER FOR DOE WORK vEr-3 0 582 c.
ISSUED TO: (DOE Office)
ISSUE D BY INRC Of ficol ACCOUNTING CITATION Office of Nuclear Reactor APPROPRIAT1oN SYMSOL Albuquerque Operations Office Regulation, DSI 31X0200.202 s&R NUMScA PERFORMING ORGANIZATION AND LOCATION 20-19-50-51-3 Los Alamos National Laboratory Fluuuu.cn p
Los Alamos, New Mexico A7275-2 fk WORK PERIOD THIS ORDER FIN TITLE Thermal-Hydraulic Analyses of Reactor Coolant Systems F'xED o ESTiuATEikg in a Feed and Bleed Mode 09$82 b9/30/83 OBLIGATION AVAIL' ABILITY PROVIDED BY:
A. THIS ORDER S 5,000 I;NDER THE"SME "li^rEOSl512ESr'OSyr"/80SU E71RS OU3 $ I S
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AP F
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i 8&R NUMBER" CITED ABOVE 2,480,000 C. TOTAL ORDERS TO DATE (TOTAL A & 81 5 2,485,000 l
D. AMOUNT INCLUDED IN "C" APPLICABLE TO THE " FIN NUMBER" CITED IN THIS ORDER.
S 5,000 FINANCIAL FLEX 181LITY; O FUNDS WILL NOT BE REPROGRAMMED BETWEEN FINS. LINE D CONSTITUTES A LIMITATION CN 08 LIGATIONS AUTHORIZED.
@ FUNDS MAY BE REPROGR AMMED NOT TO EXCEED 110% OF FIN LEVEL UP TO $50K. LINE C CONSTITUTES A LIMITATION, ON OBLIGATIONS AUTHORIZED. If SEE BELOW STANDARD TEYMS AND CONDITIONS PROVIDED DOE ARE CONSIDERED PART OF THIS ORDER UNLESS OTHERWISE NOTED.
ATTACHVE NTS THE FOLLOWING ATTACHMENTS ARE HERE8Y SECURITY:
MADE A PART OF THIS ORDER:
U WORK ON THIS ORDER IS NOT CLASSIFIED.
d STATEMENT OF WOR K O WORK ON THIS CBDER INVOLVES CLAS$1FIED
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O ADDITION AL TERMS AND CONDITIONS INFORMATION. NRC FORM 187 IS ATTACHED.
O OTHER REM AR KS (Reference the proposal by number and date, and endocate if the attached statement of work modifies the doe proposeq:
This order provides incremental funds for initiation of work in accordance with the attached Statement of Work.and requests that a proposal be submitted within 30 days.
Please submit a copy of the proposal to B. L. Grenier, NRR.
After acceptance, please send to the NRC Office of Resou-e Management, ATTN: D. Dandois,
and provide a copy to the Office of Nuclear Reactor Reg @.cion, ATTN: D. Corley.
ISSUING AUTHORITY ACCEPTING ORGANIZATION g
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Roger J. Mattson, Director f
Division of Systems Integration
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NRCFO 73 15-79),1/ Reprogrammin limited.to
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ame Appropriation Symbol.
In order for this r l effective this ff
[otified within 5 days so that an appropriate NN locati Form IN to bbe issued alid counkerice mubt be can signe to complete the action prior to receipt of any bills.
I 9301190279 821122 PDR FOIA SHOLLY82-543 PDR
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ENCLCSURE 2 STATEMENT OF WORK
Title:
Themal-Hydraulic Analyses of Reactor Coolant Systems in a Feed and Bleed Mode FIN No.:
A7275 B&R No.:
20-19-50-51-3 Technical Monitor:
Chu-Yu Liang (FTS492-9401)
Project Manager:
Ledyard Marsh (FTS 492-7626)
BACKGROUND In NRC unresolved safety issue A-45 Task Action Plan (TAP), dated June 2,1982, several potential alternative means for removal of shutdown d6 cay heat hav6 been~id6ntified that ir6 gener511y considbr6d is being technically feasible, but have not yet been formally approved by NRC.
l Some of these alternatives have the a_dvantage that they could provide means of~ removing decay heat without major modification to the existing l
plant system design and minimize additional cost to the plants.
Thermal-hydraulic analyses of reactor systems is necessary to determine l
whether it is practicable to make use of one or more of the alternative means of decay heat removal described in TAP A-45.
Analyses are needed to evaluate system performance and to determine majdFparameters of the plant systems and to identify any test work required to substantiate system performance.
Additionally, the relevance and applicability of the various LOFT and semiscale l
experiments to the feed and bleed calculations should be assessed, and l
factored in to an overall judgement whether~ feed and bleed is alviable technique for decay heat removal, and, under what circumstances-(transient and accident conditions)it may noi. be relied on.
In addition, the staff review of Emergency Response Guidelines (ERGS) for plant operating procedure under emergency conditions requires thermal hydraulic analysis to provide their bases of acceptance.
OBJECTIVE The objective of this technical support program is to provide thermal hydraulic analyses of reactor systems in feed and bleed mode of decay hedt renoval for Westinghouse designed PWRs to (1) support USI Task Action Plan A-45 in determining which transient and accident conditions that are feasible to use feed and bleed as an alternative method of decay heat removal, and (2) support staff review of operator guidelines for plant operating procedures under emergency conditions.
WORK REQUIREMENTS The following tasks are essentially the work extended from NUREG/CR-2656
~
" Loss-of-Feedwater Transient for the Zion-1 Pressurized Water Reactor."
Task 1 - Thermal-hydraulic Analyses for Feed and Bleed-System Considerations
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w Estim ted Level of Effort:
0.2 staff-years Estinated Computer Cost:
$15,000 Estimated Completion 'Date:
January 31, 1983 Investigate the viability of the feed and bleed method of decay heat removal during transient and accident scenarios other than the loss-of-feedwater event which was used in NUREG/CR-2656 " Loss of Feedwater Transient for the Zion-1 PWR".
Specifically consider: (a) multiple steam generator tube rupture event in wnich all SGs are affected, and decay heat removal is via means other than the SGs, (b) steam line break followed by a failure of all feedwater, (c) feedline break in a location that results in a loss of steam generator inventory from one SG and a loss of all feed flow from the main feed or auxiliary feed system out the break.
These calculations should involve sufficient sensitivity studies to assess the affects of (1) delay in RCS blowdown (i.e., bleed), (2) reduced safety injection flow and/or charging flow (i.e., feed) and (3) failures that may aggravate the situation.
The contractor may use or extend the sensitivity studies performed under chapters VII and VIII of NUREG/CR-2656 to satisfy these requirements.
Task 2 - Thennal-Hydraulic Analyses for Feed and Bleed-0perational Considerations Estimated Level of Effort:
0.1 staff-years Estimated Computer Cost:
$10,000
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Estimated Completion Date:
flarch 31, 1983
-t Perform thermal hydraulic analyses to assess the viability of energency response guidelines using feed and bleed to. remove decay heat during the following accidents: (1) loss of all feedwater, (2) multiple SGTRs, (3)
MSLB combined with loss of all feedwater, and (4) MFLB combined with loss of all feedwater, using most recent Westinghouse Emergency Response Guidelines (ERGS).
Sensitivity studies should be performed to determine the effects of (1) delayed operator action, (2) out of sequence operator action, (3) omitted operator actions. Again, as in Task 1, the sensitivity studies previously performed (in NUREG/CR-2656, or in Task 1) may be used to satisfy this requirement.
In any case, a description of the operator errors and the effects should be included in the results.
A maximum of three sensitivity studies will be performed to detemine operator error and effects.
LEVEL 0F EFFORT AND PERIOD OF PERFCRMANCE:
The level of effort is estimated at 0.30 staff-yrars over a 12 month period.
REPORTING REQUIREMENTS:
1)
Upon completion of Task 1, provide the technical monitor with 6 copies of a report which includes a description of the calculations x
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and their basis, assumptions made, a summary of the computer output and other results, a discussion of the results, and a discussion of any anomalies or areas of potential misinterpretation of the data.
2)
Upon completion of Task 2, provide the technical monitor with 6 copies of a report which includes a description of the calculations performed and their bases, assumptions made, a summary of the results, a discussion of the results, and a discussion of any anomalies or areas of potential misinterpretation of the data.
BUSINESS LETTER REPORT A monthly business letter report will be submitted by the 15th of the month to the Project Manager L. Marsh with copies provided to the Directe, Division of Systems Integration, ATTN: _Sybil Boyd, 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 2 sections as follows:
PROJECT STATUS SECTION 1.
A listing of the 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.
EMP-3.
A summary of progress to date (this may be expressed in terms of percentage completion for the project).
4.
Plans for the next reporting period..
FINANCIAL STATUS SECTION 1.
Provide the total cost (value') of the project as reflected in the-proposal and the total amount of funds obligated to date.
2.
Provide the total amount of funds expended (costed) during 1he period and total cumulative to date as follows:
Period Cumulative a.
Labor-related costs b.
Computer services c.
Travel d.
Subcontracts e.
Equipment Total
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IEETIfiGS Ar.'D TRAVEL Two visits to ??RC in Bethesda, Md. should be planned:
- 1) after completion of Task 1;
- 2) after completion of Task 2; itRC FURfilSHED MATERIALS:
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DOE SOURCE SELECTION JUSTIFICATION A7275 YhcNai-HydraulicAnalysesofReactorCoolant Systems in a Feed and Bleed Mode Los Alamos National Laboratory (LANL) w on,nzArcNron.a.3 ~ n.naa,.nen, Office of Nuclear Reactor Regulations, Division of Systems Integration, Reactor Systems Branch LONATURE-PROJECT M AN AGER ggyg 7
l TYPED N AME-PROJECT M ANAGER I L. B. Marsh, (P-1114C, X27626) 9/
/82 w AseoR sEtEc,oN co..c~ m.1.c,on,>...a ao su,w m u.s. ror..,.cr.on.... e.s u. ua,.,,
r l LANL is recognized for its expertise in nuclear reactor technology, research and engineering.
They have been initimately involved in thermal-hydraulic, heat transfer, and safety reviews.
LANL previously completed a study of Loss-of-Feedwater Transients for thc Zion-1 PWR (NUREG/
i CR-2656).
They are therefore, uniquely familiar with the phenomena of concern for this work.
Not only are they highly competent analytically, but they also exhibit excellent engineering i judgement and excellent managerial expertise. This background and expertise makes LANL the most appropriate source for thermal-hydraulic analyses of reactor coolant systems in a feed
! and bleed mode study, as documented in the subject FIN plan.
In addition:
- LANL has a large computer facility with complex thermal-hydraulic computer programs which are required for this subject TA contract.
- LANL has noconflict of interest problems.
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Ledyard B. Marsh / Brian W. Sheron / Themis P. Speis 9/e 7 /82
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