ML20054M015
| ML20054M015 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/01/1982 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20054M016 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM GL-81-36, TAC-44562, NUDOCS 8207090154 | |
| Download: ML20054M015 (2) | |
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Telephone (412) 45s4000 Nuclear DiviMon P.O. Box 4 Shipp6ngport, PA 1507N)o04 July 1, 1982 Pirector of Nuclear Reactor Regulation United States Nuclear Regulatory Commission Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Washington, EC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 NUREG-0737, item II.D.1; Plant Specific Report Gentlemen:
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 plant specific submittal addressing the pe rf o rma nce testing of pressurized water reactor relief and safety valves.
Our submittal of March 29, 1982 documented our preliminary review of the Electric Power Research Institute (EPRI) generic valve test program and identified the Westinghouse Electric Corporation as being contracted to evaluate the specific Beaver Valley Power Station, Unit No. 1, safety and relief valve system, including downstream piping.
Included as attachments to this submittal are the reports prepared by Westinghouse which are intended to satisfy the NUREG-0737 documentation requirements.
The plant-specific report for safety and relief valve qualification is included as Attachment A, "PWR Safety and Relief Valve Adequacy Report for Duquesne Light Company, Beaver Valley Unit 1".
The plant-specific submittal for piping and support evaluations is included as Attachment B,
" Pressurizer Safety and Relief Line Piping and Support Evaluation, Interim Report, Duquesne Light Company, Beaver Valley Unit 1".
As documented in Attachment B, based on the results of the EPRI Safety and Relief Valve Test Program, additional thermal hydraulic analyses are required to adequately define the loads on the piping system due to valve actuation, thus this is considered an interin. report. This report contains a description of the work effort including a plan for a future course of action and represents the current status.
If the evaluation indicates pertinent stress intensities within the allowabie limits, we will provide supporting documentation by December 31, 1982, or if system modifications are required, we will provide an implementation schedule at that time..
The plant-specific submittal for block valve qualification is repre-sented by several reports.
Mr. R. C. Youngdahl of Consumers Power Company transmitted the following, "EPRI PWR Safety and Relief Valve Test Program, PORV Block Valve Information Package" to Mr. Ilarold Denton of the NRC on B207090154 820701 DR ADOCK 05000334 i
PDR J
y Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 NUREG-0737, item II.D.1; Plant Specific Report July 1, 1982 Page 2 June 1, 1982. This package contains a description of block valves in PWR plant service including valve types, installation arrangements and listing by PWR plants.
It also includes two reports:
1.
"EPRI/ Marshall Electric Motor Operated Valve (Block Valve), Interim Test Data Report", May 31, 1982.
2.
"EPRI Summary Report: Westinghouse Gate Valve Closure 1
Testing Program", March 31, 1982.
Mr. David Hoffman of Consumers Power Company had previously submitted in support of the April 1,1982 submittal schedule, the EPRI " Test Condition Justification Report" and the " Westinghouse Plant Condition Justification Report" which documented the basis and justification of the valve test conditions for all participating PWR plants. This was previously documented in our submittal of March 29, 1982. We have reviewed the above reports and have determined that the Beaver Valley Power Station, Unit No.1, is repre-sented by these reports. The block valve tested at the Marshall facility, Model B10-3045B-13MS, represents the block valves installed in our plant.
This submittal is consistent with statements contained in our response to Generic Letter No. 82-10 addressed to Mr. Darrell Eisenhut of.the NRC on June 8,1982 with regard to the block valve test program as agreed upon by the NRC and Mr. Youngdahl on July 17, 1981.
If you have any questions concerning this submittal, please contact my office.
Very t uly yours,
. Carey Vice President, Nuclear cc:
Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077
- b. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 y
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