ML19347F597
| ML19347F597 | |
| Person / Time | |
|---|---|
| Issue date: | 03/23/1981 |
| From: | Bernard Grenier Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19347F596 | List: |
| References | |
| CON-FIN-A-3381-1 20-81-211, NUDOCS 8105220025 | |
| Download: ML19347F597 (7) | |
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NRC Fonu 173 u s NucLEam mEGULAfomy couuission omoE a Nuust n (2-78) 20-81-211 OATE STANDARD ORDER FOR DOE WORK March 23, 1981 ISSUED TO. (DOE Off.ce)
ISSUED BY: (NRC Of f ee)
ACCOUNTING CITATION APPROPRIATION sYMSOL Brookhaven Area Office Office of Nuclear Reactor
., }uu, ;201 31 0200 Regulation / DST PERFORMING ORGANIZATION AND LOCATION 20-19-05-34 FIN NUMBER Brookhaven National Laboratory A-3381 -1 Upton, New York WORK FERioD. THis ORDER FIN TITLE FIXED O
' ESTIMATED D Decay Heat Removal System Evaluations - (A-45)
FROu; TO.
05/01/81 12/30/81 Of LIGATION AVAILABILITY PROVIDED BY:
S 50,000 A.
THIG ORDER 8 TOTAL OF ORDERS PLACED PRIOR TO THis DATE WITH THE PERFORMING ORGANIZATION 5 2,525,000 U,N,gRyE,g,yg,;gPP,RgRi ATION SYMBOL" AND THE FIRST FOUR DIG 4TS OF THE g
g C. TOTAL ORDERS TO DATE (TOTAL A & 81 S
2,575,00C D AMOUNT INCLUDED IN "C" APPLICABLE TO THE " FIN NUMBER" CITED IN THIS ORDER.
S 50,000 FINANCIAL FLEXIBILITY:
h FUNDS WILL NOT BE REPROGRAMMED BETWEEN FINS. LINE D CONSTITUTES A LIMITATION ON OBLIGATIONS AUTHORIZED.
O FUNDS MAY BE REPROGRAMMED NOT TO EXCEED 210% OF FIN LEVEL UP TO S50K. LINE C CONSTITUTES A LIMITATION ON OBLIGATIONS AUTHORIZED.
STANDARD TERMS 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:
M%VORK ON THIS ORDER IS NOT CLASSIFIED.
ESTATEMENT OF WOR K O WORK ON THIS ORDER INVOLVES CLASSIFIED O ADDITION AL TERMS AND CONDITIONS INFORMATION. NRC FORM 187 IS ATTACHED.
O OTHER REMARKS:
This order provides initiation of f6nding for this project, provides work requirements, and requests a proposal based on the attached Statement of Work. The proposal should l
contain a breakdown of tasks into subtasks along with projected milestone completion l
dates. Cost estimates must be separate for each task.
After acceptance please send to the NRC Office of the Controller, ATTN:
D. Dandois, and provide a copy to the Office of Nuclear Reactor Regulation, ATTN:
D. Corley.
ACCEPTING ORGANIZATION 4
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1,S$ ilNG AUTHORITY m
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sIG N AT um E Bernard L. Gren1er TITLE TITLE l
Technical Assistance Program Manager DATE NRCFORM 173(2 78) i I
8105220D)6
STATEMENT OF WORK TITLE:
" Decay Heat Removal System Evaluations - (A-45)"
FIN NO.: A-3381 B&R NUMBER: 20-19-05-34 TECHNICAL MONITOR: Andrew R. Marchese (492-8230)
COGNIZANT BRANCH CHIEF:
Karl Kniel (492-7141)
BACKGROUND In NUREG-0705 entitled, " Identification of New Unresolved Safety Issues Relating to Nuclear Power Plants, Special Report to Congress," dated March 1981, the Comission identified " Shutdown Decay Heat Removal Requirements," Task A-45 as one of four new Unresolved Safety Issues (USIs). Appendix A of NUREG-0705 provides an expanded discussion of each new USI including issue definition, a preliminary discussion of the action plan for resolution and a basis for continued plant operation and licensing.
Although many improvements to the steam generator auxiliary feedwater system were required of the reactor manufacturers by the NRC following the TMI-2 accident, the staff feels that providing an alternative means of decay heat removal could substantially increase the plants' capability to deal with a broader spectrum of transients and accidents and potentially could, therefore, significantly reduce the overall risk to the public.
Consequently, Task A-45 will investigate alternative means of decay heat removal in PWR plants, including but not limited to using existing equipment where possible.
This Unresolved %fety Issue will also investigate the need and possible design requb ements for improving reliability of decay heat removal systems in boiling water reactors (BWRs).
The staff's Task Action Plan for resolution of this USI will include consideration of the following elements. At the outset it will start l
off with the development of acceptance criteria upon which the adequacy of current shutdown decay heat removal requirements will be judged, including the extent to which current operating LWRs satisfy current requirements. Before consideration is given to alternate decay heat removal system concepts, it is important to understand how well current systems cope with dominant accident sequences which can jeopardize plant safety.
If the present criteria are found to be unacceptable, design criteria for both existing and alternate decay heat removal systems as appropriate will be developed. Design criteria will need to consider
. both frequent events (e.g., loss of offsite power, loss of feedwater, small LOCAs) and special emergencies (e.g., seismic events, sabotage, airplane crash).
Because of the broad spectrum of types of LWRs currently operating and the wide variation in the year they were pnt into service, a considerable number of existing plants will need to be analyzed.
OBJECTIVES The objectives of this technical assistance program are as follows:
(1) Obtain an assessment of the cor.tribution to risk and/or core melt probability from decay heat removal system (DHRS)* failures for six specific plants analyzed in the Reactor Safety Study (WASH-1400) and in the Reactor Safety Study Methodology Application Program (RSSMAP).
(2) For the specific plants analyzed in WASH-1400 and RSSMAP, the contractor shall make a determination whether it is feasible to separate all other currently operating U. S. commercial LWRs into groups based on whether they have similar DHRS design characteristics to the six plants covered in item (1) above.
WORK REQUIREMENTS Estimated Tasks Projected Completion Date Level of Effort TASK 1 - DHRS Contribution October 1981 to Risk for Soecific Plants Assess the impact of the overall decay heat removal function in terms of its contribution to con-sequences of accident sequences not initiated by medium or large LOCAs using as a measure the core melt probability and/or overall risk, depending upon the avail-ability of existing information.
The information used in this assessment will be based on con-clusions drawn in NRC-sponsored orobabilistic risk studies. The assessments will be performed for the following reactors and on the basis of the following source doc-unentation.
- See page 4, Definition of DHRS
. Reactor Source Documentation Projected Completion Date*
Surry WASH-1400 05/31/81 Peach Bottom WASH-1400 06/30/81 Sequoyah RSSMAP 07/31/ 81 Grand Gulf RSSMAP 08/31/81 Oconee RSSMAP 09/30/81 Calvert Cliffs RSSMAP 10/31/81 Estimated Tasks Projected Completion Date Level of Effort TASK 2 - Grouping of Plants for DHRS Evaluation December 1981 Based on the specific design features of systems which per-form the decay heat removal function for the plants noted in Task 1, determine whether it is feasible to divide the opera-ting U.S. commercial plants into grouos. Define the groups such that evaluations (based partly on Task 1) and subsequent recommendations with regard to the decay heat removal function would apply (with perhaps minor modifications within a grouo) to all plants within the group.
Identify those olants which may be expected to have similar design characteristics to the six plants noted in Task 1 and provide an initial determination of the extent to which grouping of plants for the purposes of the overall Task A-45 program is possible.
LEVEL OF EFFORT AND PERIOD OF PERFORMANCE The level of effort for this program is estimated at 1 man-year over a period of 8 months.
REPORTING RE0VIREMENTS 1.
Letter reports will be provided documenting the progress upon completion of each task on the date shown in the program schedule.
Ten copies of the letter reports are to be submitted to the technical monitor.
- See page 4, NRC Furnished Material.
.- 2.
A monthly business letter will be submitted by the 15th of the month to the cognizant NRR manager with a copy to the Director, Division of Safety Technology, ATTN:
J. Rakowski; F. Schroeder, DST; and to B. L. Grenier, NRR. The reports shall contain:
- A list of any efforts completed during the period; milestones reached, or if missed, an explanation provided.
- The amount of funds expended for manpower and computer services during the period and cumulative to date for each task;
- Any problems or delays encountered or anticioated;
- Plans for the next reporting period.
MEETINGS AND TRAVEL Approximately four trips to Bethesda, Maryland to meet with the NRC are expected for two Brookhaven personnel. The dates will be determined by program needs and the Technical Monitor. Approximately six plant or facility visits are planned for one or two Brookhaven personnel and an NRC representative. Dates and times will be determined according to the needs of the program.
NRC FURNISHED MATERIALS The NRC will furnish the RSSMAP reports for Sequoyah, Grand Gulf, Oconee and Calvert Cliffs as soon as they are available. For those reports to be furnished by NRC, the estimated completion dates will be one ranth after receipt of the report by the contractor (this assumes that the report will not be critiqued but that information will be extracted and cast into a form suitable for use in this task effort).
DEFINITION OF DHRS DHRS in this context is defined as those components and systems reauired to maintain primary only or primary and secondary coolant inventory control and to transfer heat from the reactor coolant system and containment buildino to an ultimate heat sink following shutdown of the reactor for normal events, off-normal transient events (e.g., loss of off-site power, loss of main feedwater) and small LOCAs (i.e.,1/2" to approximately 2").
DHRS does not encompass those emergency core cooling systems reouired only to maintain coolant inventory and dissipate heat during the first ten minutes following medium or large LOCAs.
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o PROPOSAL CONTENT The minimum items required in all proposals are:
1.
Performing organization's name and location.
2.
FIN Title, FIN Number, and B&R Number (NRC's) (as on Statement of Work).
3.
Performing organization's key personnel, program manager, or principal investigator, their resumes and FTS phone number.
4.
Background (definition of' the problem including the objective (s) to be attained).
5.
Work to be performed (provide a concise description of tasks to be performed and expected results for the period of performance. Note technical data requirements, potential problems, and other technical information needed to fully explain the effort.
Highlight changes from prior authorized 50W's, if any, identify changes in performance, schedule, or costs).
6.
Identify major subcontracts, including consultants.
7.
Costs estimated to be incurred by 00E contractors, subcontractors, and consultants. List by fiscal year to completion:
a.
Marfears of Technical Support (MTS) b.
Costs:
(1) Direct Salaries (Labor) for MTS (2) Material and Services (excluding ADP)
(3)
Total ADP Support (4)
Subcontracts (5)
Capital Equipment (6)
Direct Travel Expense (foreign travel must be shown separately)
(7) General and Administrative Expense (include indirect labor cost) c.
Total Estimated Cost 6
8.
Forecasts:
l a.
Milestone chart for accomplishing the work.
P00RORBlKAL
2_
b.
Planned monthly rate of costs by fiscal year. This may be provided with the first report of an authorized program if not knswn at time of proposal submittal. At the beginning of' each subsequent year, reports should include the planned monthly rate of costs for the ensuing year.
9.
Conflict of Interest:
In order to assist the Commission in its evaluation, the DOE Contracting Officer shall describe any significant contractual and organizational relationships of the TOE, its contractor, their employees, or expected subcontractors or corsultants on this proposal, with industries regulated by the NRC (e.g. ut111 ties, etc.) and suppliers thereof (e.g. architect engineers and reactor manufacturers, etc.) that might give rise to an apparent or actual conflict of interest.
- 10. Reporting Requirements (as on Statement of Work).
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