ML20050B571
| ML20050B571 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/29/1982 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM GL-81-36, TAC-44562, NUDOCS 8204060075 | |
| Download: ML20050B571 (2) | |
Text
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M12H564000 March 29, 1982
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R Director of Nuclear Reactor Regulation j3 United States Nuclear Regulatory Commission S
(V s Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 g}
HENI Division of Licensing 3
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Washington, DC 20555
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Reference:
Beaver Valley Power Station, Unit No.1
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Docket No. 50-334, License W. DPR-66 g
NUREG 0737, item II.D.1.2.a; Safety and Relief Valv T'dstin$
Centlemen:
In accordance with the requirements of NUREG 0737, item II.D.1, and the revised schedule as documented in Generic Letter 81-36 dated September 29, 1981, this letter represents our submittal to confirm the adequacy of safety and relief valves based on our preliminary review of the generic test program results. The Duquesne Light Company has actively pursued resolution of this issue through direct participation in the Electric Power Research Institute (EPRI) valve test program.
The primary objective of the test program was to provide full-scale test data confirming the functional capability of primary system power operated relief valves and safety valves for expected operating and accident conditions. The second objective was to obtain sufficient piping thermal hydraulic load data -
to permit confirmation of models which may be utilized for plant unique analy-sis of safety and relief valve discharge piping systems. The relief and safety valve tests were completed in August and December 1981, respectively.
The following EPRI reports, which have been transmitted to you by David Hof fman of Consumers Power Company, were reviewed and it has been concluded that the valves tested adequately represent the safety and relief valve designs and the conditions for Beaver Valley Power Station, Unit No. 1.
(a) " Valve Selection / Justification Report" documenting that the selected valves represent all participating PWR plant safety and relief valves.
(b)
" Test Condition Justification Report" and the " Westinghouse Plant Condition Justification Report" documenting the basis and justifi-cation of the val.ve test conditions for all participating PWR plants.
(c)
" Safety and Relief Valve Test Report" which provide evidence demon-strating the functional capability of the selected test valves under the selected test conditions for all participating PWR plants.
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E Beaver' Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 NUREG 0737, item II.D.1.2.a; Safety and Relief Valve Testing.
Page 2 (d) " Application of RELAP 5/ MOD 1 for Calculation of Safety and Relief Vaive Discharge Piping Hydrodynamic Loads" which presents an analytical modei benchmarked against test data that may be used for plant unique analysis of safety and. relief valve discharge piping systems.
These reports will be used to perform the final plant specific evaluation which is presently scheduled for submittal by July 1,1982.
Certain areas of system performance are att11 undergoing review, specifically addressing the inlet piping, outlet piping and the valves. The Duquesne Light Company is actively involved with the Westinghouse Owners Croup program and has additionally contracted Westinghouse to evaluate the specific BVPS Unit No.1 safety and relief valve system, including downstream piping. Reference (b) above identified BVPS Unit No. I as not being included for Cold Overpressurization Events. We have reviewed the test data for valve operation for the Cold Overpressure Protection System and have determined that our system operates within this test envelope and is therefore represented by the referenced reports.
The September 29, 1981 NRC letter requested that plant specific final evaluations be submitted by July 1,1982.
In order to meet that date, eval-untions have been initiated.
Depending on the outcome of the evaluations, it may be necessary to continue the evaluation beyond the required submittal r
-date.
If a longer evaluation period is required, you will be notified on or before July 1,1982.
Very truly yours, J. J. Carey Vice President, Nuclear cc:
Mr. D. A. Beckman, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555
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