ML20070H767

Advises That Final Evaluation Re EPRI Relief & Safety Valve Testing Per NUREG-0737,Item II.D.1, Reliability Engineering, Will Not Be Submitted Until 830131.Summary of Evaluation Submitted

ML20070H767
Person / Time
Site:	Davis Besse
Issue date:	12/17/1982
From:	Crouse R TOLEDO EDISON CO.
To:	Stolz J Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.1, TASK-TM 44572, 886, TAC-44572, NUDOCS 8212270205
Download: ML20070H767 (2)

Text

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4 TOLEDO

%mm EDISON Docket No. 50-346 ),[l(([;"""'

nam-License No. NPI-3 * *' *58-58 '

Serial No. 886 December 17, 1982 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz Operating Reactor Branch No. 4 Division of Operating Reactors United States Naclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Stolz:

In our letter dated July 1, 1982, (Serial No. 834) Toledo Edison proposed to supply the NUREG-0737 requestEi information on EPRI relief and safety vs ve testing per Item II.D.1.2 and II.D.1.3 by December 31, 1982. Due to unanticipated delays, we must now propose to submit the final detail evaluation by January 31, 1983. However, we will summarize in thin letter the essential conclusions of the esaluation on Davis-Besse Nuclear Power Station Unit No. 1.

The Toledo Edison evaluation of the pressurizer safety / relief and block valves, discharge piping and supports have been completed to a degree necesriry to summarize the results. As mentioned in the July 1, 1982 submittal, the two pressurizer safety relief valves were removed and relocated to the pressurizer nozzles without reconnecting the discharge lines. Based on our present evaltation, we have uncovered no concern with the relief valve performance expectations (based on EPRI and Crosby valve testing), no piping related probelms, nor any piping support related problems. Our detail information will follow in the January 31, 1983 submittal.

In our evaluation on the PORV, block valve, and piping no problems have been identified with valve performance (PORV or Block valve) and no areas of concern on the pipir; analysis. However, several supports were analyzed to have higher loadings than previously designed to be maintained. The evaluation to ensure that overstressing does not oteur has not been completed. This will be reported in our January 31, 1983 cubmittal along with any required actions as a result of the conclusions.

l THE TOLEDO EDISON COMPANY EDISON PLAZA 300 AADISON AVENUE lOLEDO, OHIO 43S52 8212270205 821217 ..I PDR ADC0K 05000346 i

.~P PDR.

,F ' D:ckst Ns. 'i0-346 Licznca No. NPF-3 Serial No. 886 December 17, 1932 Page 2 In summary, the PORV valve and the blocking valve in the original position in the valve room will function properly for all expected operating and accident conditions. The PORV meets the standard of

, NUREG-0737 Item II.D.1. The safety relief valves (2) in.the new location mounted on the pressurizer with no discharge piping to the quench tank, meet the standards of NUREG-0737 Item.II.D.l. The valves-will function properly under all expected operating and accident conditions. The PORV piping requires further evaluation to' ensure the standard of NUREG-0737 Item II.D.1 is met.

Very truly yours,

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RPC:LDY:lah cc: DB-1 NRC Resident Inspector J

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