ML20082P687

Revised Part 21 Rept Re Failure of Crosby Spring Relief Valves During Testing.Valve Prematurely Lifted During Sixth & Seventh Refueling Outages Due to Use of Stainless Instead of Carbon Steel.Springs,W/New Matl,Installed at Facility

ML20082P687
Person / Time
Site:	Beaver Valley
Issue date:	09/04/1991
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-PT21-91 ND3MNO:3182, NUDOCS 9109110010
Download: ML20082P687 (4)

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l P O O<a 4 wn.uan ai a n,mww September 4, 1991 ND3MNO:3182 Beaver Valley Power Station, Unit No. 1 Docket llo. CO-334, Licence No. OPR-66 Special Renqrt United States Nuclear Regulatory Commission Document Control Dehk WashJ.ngton, DC 20555 Gentlemen: .

The following notification report is a revision of Beaver Valley letter ND3MNO: 316*/ previously submitted under 3 0 CPR Part

21. This issue concerns Crosby spring relief valve failures experienced during testing at Beaver Valley Unit 1. This revision in being submitted to correct a typographic mistake in the fifth paragraph. The original submission should have stated that there were no other affected valves.

l The Boron Injection Tank Relief Valve (BVPS Mark No.

RV-SI-857) provides overpressure relief capability for the Boron Injection Tank. Information on the Relief Valve is an follows:

Mfg: Crosby Valve & Gage Co.

Model No: 50913MC Style: JMAK-SPEC Mfg. Code: C710 Crosby Type: Globe Size: 3/4 inch The subject valve failed when the valve prematurely lifted on two (2) separate occasions during testing, both due to spring failures as a result of the spring material. The first failure occurred during the sixth refueling outage (6R) and the second failure occurred during the seventh refueling outage (7R). In correspondence with the vendor, it was learned that the recommended spring material for this valve was changed from the original carbon steel to stainless stool, and then to the present alloy steel ASTM-A638 grade 660.

9109110010 910904 PDR ADOCK 05000334 ,,ZMA 2 S PDR

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' - September 4, 1991 ND3MHO:3182 l Page two An evaluation was conducted to determine if a substantial cafety hazard could exist at DVPS Unit 1. In the event of a safety injection (SI) and the relief valve lifted prematurely (at a pressure lower than the 2735 poig setpoint), the high head safety injection flow that potentially would be lost via the relief valve could result in degraded safety injection flow conditionc. However, it was demonstrated during two actual SI events (LERs88-007 nnd 89-007) that the relief valvo performed natisfactorily (i.e., . did not lift prematurely). These events occurred during the time frame between the first and second test failuren of RV-SI-857 (6R and 7R testing periods). After the second test failure of the relief valve, the spring was changed to the presently installed ASTM-A638 grade 660 and no additional failures have been experienced.

An investigation was made to determine if thin application affected other valves at the site and the resulta indicated there were none.

The problem of the spring material has been corrected at Deaver Valley A cpring of material type ASTM-A638 grade 660 was installed during 7R. The station operated for the eighth fuel cycle with this opring installed. During the recent eighth refueling outage (8R), the valve was tested and operated satisfactorily. This notice is being provided pursuant to the requirements of 10 CFR Part 21 (b). This information la also being provided to the inductry via the INPO Nuclear Network system.

If there are any questions regarding this matter, please contact John Maracek, (412)-393-5232.

Very truly yours, WJ A T. P. Noonan General Manager Nuclear Operations DC/sl Attachment

, Septembnr 4, 1991 NO3MHO!3182 Page three cc: Mr. T. T. Martin, Regional Administrator United States Nuclear Regulatory Commission Region 1 475 Allendale Road King.of Prussia, PA 19406 C. A. Rotock, Ohio Edison 76 S. Main Street Akron, OH 44308 Mr. A. DeAgazio, BVPS Licensing Project Manager United States Nuclear Regulatory Commission Washington, DC 20555 J. Beall, Nuclear Regulatory Commission, BVPS Senior Resident Inspector Larry Beck Centerior Energy 6200 Oak Tree Blvd.

Independence, Ohio 44101-4661 INPO Records Center Suite 1500 1100 Circle 75 Parkway Atlanta, GA 30339 G. E. Muckle, Factory Mutual Engineering 680 Anderson Drive #BLD10 Pittsburgh, PA 15220-2773 Mr. Richard Janati Department of Environmental Resources P. O.-Box 20f'.

16th Floor, Fulton Building Harrisburg, PA 17120 Director, Safety Evaluation & Control j Virginia Electric & Power Co.

P . O '. Box 26666 One James River Plaza Richmond, VA 23261 W. Hartley Virginia Power Company 5000 Dominion Blvd.

2SW Glenn Allen, VA 23060

, J. M. Riddle NUS Operating Service Corporation

! Park West II Cliff Mine Road Pittsburgh, PA 15275 I

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Sepgember 4, 1991 l ND3MNO 3182 i Pago four Bill Wegner, consultant  !

23 Woodlawn Terrace Fredricksburg, VA 22404 i

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