ML20050D576

Forwards Preliminary Evaluation of PWR Safety & Relief Valve Test Program Results,Point Beach Nuclear Plant, in Response to NUREG-0737,Item II.D.1

ML20050D576
Person / Time
Site:	Point Beach
Issue date:	04/08/1982
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20050D577	List: ML20050D576 ML20050D592
References
RTR-NUREG-0578, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-737, TASK-2.D.1, TASK-TM NUDOCS 8204120335
Download: ML20050D576 (3)

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l%SC0nSin Electnc powra couesur 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 April 8, 1982 Mr. H. R. Denton, Director B-Office of Nuclear Reactor Regulation 8 U. S. NUCLEAR REGULATORY COMMISSION 20555 g g Washington, D. C. p

Dear Mr. Denton:

p} 4 0 q@ p DOCKET NOS. 50-266 AND 50-301 FURTHER RESPONSE TO NUREG-0737, ITEM II.

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POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2

/bg W>Q ' 3-In accordance with the initial recommendation of NUREG-0578, Section 2.1.2, as clarified by NUREG-0737, Item II.D.1, and the NRC's letter of September 29, 1981, each pressurized water reactor (PWR) licensee is to submit by April 1, 1982 a preliminary evaluation, supported by test results, of the functionability of existing safety and relief valves for expected NSSS operating and accident con-ditions. This is our response to the April 1 NRC submittal request.

Wisconsin Electric is a participant in the Generic PWR Safety and Relief Valve Test Program implemented by the Electric Power Research Institute (EPRI) at the request of participating PWR utilities in response to the NRC recommenda-tions for safety and relief valve testing. The test program's primary objective was to provide full-scale test data confirming the functionability of primary system safety and power-operated relief valves for expected operating and accident conditions.

A further objective was to obtain piping thermal hydraulic load data to confirm the adequacy of models which may be utilized for plant-specific analysis of safety and relief valve discharge piping systems.

All safety and relief valve performance testing was completed by the end of December 1981. By an April 1, 1982 letter to you, Mr. David Hoffman on behalf of the participating PWR utilities transmitted the following program reports:

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8204120335 820408 PDR ADOCK 05000266 p PDR

Mr. H. R. Denton ,

April 8, 1982

1. Safety and Relief Valve Test Report This report provides the test evidence demonstrating the functionability of the selected test valves under the selected test conditions for all participating PWR plants. While there are some items in the tables of data to be furnished later, most of the test infor-mation is contained in this report.

2. Valve Selection / Justification Report This report verifies that the selected test valves represent all participating PWR plant safety and relief valves.

3. Test Condition Justification Report and the NSSS Vendor Plant Condition Justification Reports (3)

Of the NSSS vendor reports, the Westinghouse report is applicable to Point Beach Nuclear Plant. These reports define the basis of and justification for the valve test conditions for all participating PWR plants.

4. Application of RELAP 5/ MOD 1 for Calculation of Safety and Relief Valve Discharge Piping Hydrodynamic Loads This report documents the acceptability of using the RELAP 5/ MOD 1 computer code for the calculation of the pipe loadings resulting from safety valve discharges. Actual test data are compared to analytical results.

Wisconsin Electric has retained EDS Nuclear, Incorporated for assistance on the specific evaluations required for the Point r Beach Nuclear Plant. We have both completed a preliminary review of j the test program results and based upon this review, which is described in the attachment hereto, we have concluded the following:

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1. That the valves do perform their basic function of opening, relieving pressure, and closing.

2. That the valves tested are sufficiently representative of the Point Beach Nuclear Plant valves.

3. That the conditions for which the valves were tested effectively envelop the range of expected operating and accident conditions for the Point Beach Nuclear Plant.

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Mr. H. R.,Denton ,

April 8, 1982 1

4. That the reports provide the test evidence required a

by NUREG-0737, Item II.D.l.a, to support the final plant-specific evaluations for Point Beach Nuclear Plant.

j The September 29 NRC letter requested that plant-specific final evaluations be submitted by July 1, 1982. These evaluations are being pursued presently. If a longer evaluation period is required, we will notify you on or before that date.

Very truly yours, ll C/ t Assistant Vice President C. W. Fay

'l Attachment Copy to NRC Resident Inspector I

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