ML20050A450
| ML20050A450 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/23/1982 |
| From: | Parker W DUKE POWER CO. |
| To: | Harold Denton, Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, TASK-1.D.1, TASK-TM NUDOCS 8204010302 | |
| Download: ML20050A450 (2) | |
Text
4 DUKE POWER COMPANY Powzu Dun.onwo 422 Sourn Cnuncu Srazer, CnAHLoTTE, N. C. 28242 WI L LI AM O. PA R M E R, J R.
WCr PRESicfMT TELCPMONE; AREA 704 ser. Peooven "
March 23, 1982 snI b
a Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation
'l b8CggD U. S. Nuclear Regulatory Commission Washington, D. C. 20555 2
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Attention:
Mr. J. F. Stolz, Chief Operating Reactors Branch No. 4 p
Re: Oconee Nuclear Station g
b Docket Nos. 50-269, -270, -287 O
Dear Sir:
In accordance with NUREG-0737, Item 11.D.1 as revised on September 29, 1981 a preliminary evaluation supported by test results which demonstrates the capability of relief and safety valves to operate under expected operating and accident conditions was required by April 1, 1982. The following pre-liminary assessment for Oconce Nuclear Station is pursuant to this require-ment.
Duke Power Company is a participant in the Generic PWR Safety and Relief Valve Test Program implemented by the Elcetric Power Research Institute (EPRI) at the request of participating utilities. The primary objective of the Test Program was to provide full scale test data confirming the ability of primary system power operated relief valves (PORV) and safety valves to function for expected operating and accident conditions. The second objective of the program was to obtain sufficient piping thermal hydraulic load data to permit confirmation of models which may be utilized for plant specific analysis of safety and relief valve discharge piping systems.
The PORV tests were completed in August 1981 and the safety valve tests were completed in December 1981. The reports provided by EPRI documenting the Test Program results are as follow: Valve Selection Justification Report, Test Condition Justification Report, B&W Plant Condition Justification Report, Safety and Relief Valve Test Report, and Discharge Piping Load Model Report.
These reports have been transmitted to you by David Hoffman of Consumers Power Company on behalf of the participating PWR utilities as part of our preliminary assessment submittal.
Preliminary analysis by Duke Power Company indicates that the test results demonstrate generally favorable performance for the Dresser 31533 VX-30 PORV and the Dresser 31739 A safety valves utilized at Oconee Nuclear Station.
The PORV tests were conducted at Marshall Steam Electric Station and the Wylie/Norco facility utilizing generally bounding conditions for Oconee l O 8204010302 820323 PDR ADOCK 05000269 P
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Mr. Ilarold R. Denton, Director March 23, 1982 Page 2 Nuclear Station operations. Preliminary analysis of the test results indicatts that the Dresser 31533 VX-30 PORV can be expected to perform adequately under all expected conditions.
Analysis of the Dresser 31739 A safety valve tests conducted at Combustion Engineering is very preliminary at this time due to the late completion of the tests (December 1981). Preliminary analysis of the EPR1 test conditions found them to be conservatively bounding of the expected operating and accident conditions at Oconee Nuclear Station. Preliminary analysis of test results shows favorable performance on all tests.
Preliminary analyses of the EPRI test results relative to specific expected operating and accident conditions at Oconee Nuc1 car Station have indicated that the Relief and Safety Valves will perform adequately. Analysis is continuing to provide a detailed report on July 1, 1982.
If a longer evaluation period is required you will be notified on or before July 1, 1982.
Very truly yours, Ww O.
William O. Parker, J.
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