ML20024D477

Rev 1 to Final Deficiency Rept DER 80-30 Re Failure of Borg-Warner Motor Operated Gate Valve to Close.Condition Reevaluated as Not Reportable.Part 21 Rept Filed on 800216. Valves Will Be Tested Under Differential Pressures

ML20024D477
Person / Time
Site:	Palo Verde
Issue date:	07/25/1983
From:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Sternberg D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
10CFR-050.55E, 10CFR-50.55E, ANPP-27369-BSK, DER-80-30, NUDOCS 8308050080
Download: ML20024D477 (3)

Text

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R yg Arizona Public Service Company U3 P.O. BOX 21666 . PHOENIX, ARtZONA 85036  ?'; .,j [s([ {.

July 25,1983 lOll P 'g g ANPP-27369-BSK/RQT U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. D. M. Sternberg, Chie f Reactor Projects Branch 1

Subject:

Final Report - Revision 1 - DER 80-30 A 50.55(e) Report Relating To Borg-Warner Motor Operated Gate Valve Failure To Close Under Operating Conditions.

File: 83-019-026; D.4.33.2

Reference:

A) Telephone Conversation between J. Eckhardt and B. Kaplan on October 1, 1980 B) ANPP-16653 dated October 31,1980 (Final Report)

Dear Sir:

Enclosed is Revision 1 of the subject Deficiency Evaluation Report under the requirements of 10CFR50.55(e). This revision provides changes in the

" Analysis of Safety Implications" and " Corrective Action" sections.

Very truly ours

. s --

. CLLL n LR E. E. Van Brunt, Jr.

l APS Vice President, Nuclear Projects Management i ANPP Project Director EEVBJr./RQT:rb Enc losure cc: See Attached Page 2 I

8308050080 830825 PDR ADOCK 05000528 S PDR Tf-)7

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f U. S. Nuclear Regulatory Commission Page 2.

cc: Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 T. G. Woods, Jr.

G. C. Andognini J. A. Roedel i D. B. Fasnacht A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees J. R. Bynum P. P. Klute/D. D. Green A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen G. A. Fiorelli S. R. Frost J. Self Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway - Suite 1500 Atlanta, Georgia 30339

p FINAL REPORT - REVISION 1 - DER 80-30 DEFICIENCY EVALUATION 50.55(e)

ARIZONA PUBLIC SERVICE' COMPANY (APS)

PVNGS UNITS 1&2 I. DESCRIPTION OF CONDITION During testing in November, 1979 at Duke Power, a Borg Warner 3" 1500 # motor operated gate valve failed to completely close when actuated under operating conditions of 2485 psi at 650 degrees F.

with a flow rate of 220,000 lbs. per hour of steam. Testing by Duke Power in conjunction with Borg Warner, Nuclear Valve Division, determined the potential failure to be-inadequate' guiding of the valve gate.

II. ANALYSIS OF SAFETY IMPLICATIONS This condition has been re-evaluated as not reportable. The subject deficiency would not have resulted in a' safety significant condition if left undetected and uncorrected.

The Borg-Warner valve model in question is utilized as an isolation valve in the safety injection long-term recirculation lines at Palo

~

-Verde. The safety function of this valve is to open against differential pressure should plant conditions require the operator to initiate simultaneous cold leg and hot leg injection. At such time as plant conditions would allow the operator to terminate simultaneous cold leg and hot leg injection, the operator would then close the valves from the control room. The condition of the plant at the time an operator would take this action is such that should the valve fail to close, the. plant cool down capability is not affected and no safety significant condition would exist.

III. CORRECTIVE ACTION Borg Warner filed a 10CFR Part 21 Notification Report with the NRC on February 16, 1980 covering this condition. Supplemental testing

, was performed by Borg Warner, in response to the corresponding NRC I&E Bulletin 81-02, to demonstrate the valves operability under the l

valve specification design requirements of 2500 psi differential pressure and 600 gpm flow rate. The results of the test demonstrated that the valve assembly as delivered to Palo Verde successfully passed the operability test; opening and closing fully

, against 2500 psi differential pressure and 600 gpm.

The operability of the subject valves will also be verified during i the pre-operational tests at all three Palo Verde units under differential pressure conditions greater than that which would be present during actual plant operation.

NCR PA-1643 has been dispositioned use-as-is.

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