ML20097H841

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Interim Deficiency Rept DER 84-58 Re Auxiliary Feedwater (AFW) Sys Solenoid Valve Failure to Open in Response to AFW Actuating Sys Signal.Initially Reported on 840808.Next Rept Will Be Submitted by 841019
ML20097H841
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 09/06/1984
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Bishop T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
ANPP-30449-TDS, DER-84-58, NUDOCS 8409210012
Download: ML20097H841 (3)


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Arizona Public Service Company September 6, 1984 ANPP-30449-TDS/TRB U. S. Nuclear Regulatory Commission Region V Creekside Oaka Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368

. Attention: Mr. T. W. Bishop, Director Division of Resident Reactor Projecta and Engineering Programa

Subject:

Interin Report - DER 84-58 A 50.55(e) Potentially Reportable Deficiency Relating to Auxiliary Feedwater System Soleroid Valve Failed To Open In Response To AFAS Signal.

F1.le: 84-019-026; D.4.33.2 Referen:e: Telephone Conversation betwe<m J. Ball and T. Bradish on August 8, 1984

Dear Sir:

The. NRC was notified of a potentic11y reportable deficiency in the referenced telephone convernation. At that time it was estimated that a determination of reportability would be made within thirty (30) days.

Due to the extensive investigation and evaluation required, an Interim Report in attached. It is now expacted that thin information will ha finalized by October 19, 1984, at which time a complete report will be submitted.

Very truly yours, I

h E. E. Van Brunt, Jr.

APS Vice President Nuclear Production ANPP Project Director EEVB/TRB/nj DPk$hhd20 ohkh8 Atta heent cc: See Page Two PDR

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Mr. T. W. Bishop DER 84-58 Page Two-cc:

Richard DeYoung, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Comminaion Wanhington, D. C. 20555 T. G. Woods, Jr.

D. B. Karner

' W. E. Id e D. B. Fasnacht A. C. Rogern L. A. Souza D. E. Fowler T. D. Shriver C. N. Ruano-J. Voreen J. R. Bynum J. M. Allen J. A. Brand D. Canady-A. C. Gehr W. J. Stubblefield W. G. Bingham R. L. Patterson R. W. Welcher H. D. Foater 4

D. R. Harkinnon L. E. Vorlerbrueggen.

R. P. Zimvrean S. R. Frost L. Clyde M. Wooda T. J. Bloom Records Center Inntitute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339 d

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r INTERIM REPORT - DER 84-58 POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COMPANY (APS)

PVNGS UNIT 1 I.

Potential Problem Per the final safety analysis report, section 7.3.1.1.10.7, the seismic category I portion of the auxiliary feedwater system is provided to automatically initiate residual heat removal capability during emergency conditions such as a steam line rupture, loss of normal feedwater, or loss of offsite and normal onsite power.

During the performance of preoperational testir.g, the steam supply bypass solenoid valve (UV-138A, used in the slow starting of the auxiliary feedwater turbine) to the auxiliary pump (AFA-P01) failed to open in response to an AFAS signal as required by design. This condition would result in the tripping of the auxiliary feedwater turbine (AFA-K01) due to overspeed; consequently, the turbine driven pump (AFA-P01) would not he available to initiate residual heat removal during emergency conditions. Investigation of the valve indicated that the valve was mechanically stuck in the closed position. Af ter disassembly of the valve by the vendor's field service representative (Target Rock Corp.) the following were found: 1) Powdery rust on the plunger and inside the bonnet assembly; 2) Parts of the soft seat were missing around the edges; and 3) Some very minor galling on the upper edge of the plunger which holds the seal ring.

II.

Approach To and Status Of* Proposed Resolution The specific areas of concern resulting from these deficiencies are as follows:

1. To positively identify the powdery rust found in the valves' internals as being t egnetite and evaluate its presence in this system.
2. Target Rock's evaluation of the problem after receipt and inspection of the valvea in their factory.

Bachtel Engineering is currently reviewing this problem with Target Rock to determine reportability and technical justification for corrective action.

III.

Proiected Completion of Corrective Action and Submittal of the Final Report Evaluation of this condition and submittal of the Final Report is forecast to be completed by October 19, 1984.

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