ML17251A169

Special Rept:On 880516,turbine Driven Auxiliary Feedwater Sys Inoperable During Period from 880516-25.Valve V-3504B Operated W/Notable Resistance.Procedure A-52.4 Revised to Incorporate Check Valve

ML17251A169
Person / Time
Site:	Ginna
Issue date:	07/07/1988
From:	Snow B ROCHESTER GAS & ELECTRIC CORP.
To:	Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8807190156
Download: ML17251A169 (4)

Text

A,C CEIZRATED DlK'REBUTlON DEMONSTRX'EON SYSTEM REGULA-' ZNFORFD ZON DZSTRZEUTZOtZSTEN (RZDS)

/ACCESSION NBR: 8807190156 DOC.DATE: 88/07/07 NOTARIZED: NO DOCKET 4 FACZL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH. NAME AUTHOR AFFILIATION SNOW,B.A. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION RUSSELL,W.T. Region 1, Ofc oi the Director

SUBJECT:

Special rept:on 880516.turbine driven auxiliary pump inoperab'lity.Rept required to be submitted by 880622. R DISTRIBUTZON CODE: IE22D COPIES RECEIVED:LTR / ENCL + SIZE:

. I TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

D NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244

=8 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR EN CL ID CODE/NAME LTTR ENCL PD1-3 LA 1 PD1-3 PD h STAHLE,C 1

'INTERNAL: ACRS MICHELSON ACRS MOELLER 2 AEOD/DOA AEOD/DSP/NAS 1 AEOD/DSP/ROAB AEOD/DSP/TPAB 1 ARM/DCTS/DAB DEDRO 1 NRR/DEST/ADS 7E NRR/DEST/CEB 8H- 1 NRR/DEST/ESB 8D NRR/DEST/ICSB 7 1 NRR/DEST/MEB 9H NRR/DEST/MTB 9H 1 NRR/DEST/PSB 8D NRR/DEST/RSB 8E 1 NRR/DEST/SGB 8D NRR/DLPQ/HFB 10 1 NRR/DLPQ/QAB 10 NRR/DOEA/EAB 11 1 NRR/DREP/RAB 10 NRR/DREP/RPB 10 2 NRR DgZS B 9A NUDOCS-ABSTRACT l.

REG FI E 02 RES TELFORD,J 1 RES DE/EIB RES/DRPS DEPY 1 RGN1 FILE 01 EXTERNAL'GGG WILLIAMSI S FORD BLDG HOYFA H ST LOBBY WARD LPDR NRC PDR NSIC HARRISF J NS 1C MAYS I G h

TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL I

July 7, 1988 Mr. William T. Russell, Regional Administrator U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406

Subject:

Thirty (30) Day Special Report Turbine Driven Auxiliary Pump Inoperability R.E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Russell:

Ginna Technical Specification Section 3.4.2.b requires that a thirty (30) day Special Report be submitted.

auxiliary feedwater pump if one or flow path is inoperable for more than 7 days. The Turbine Driven Auxiliary Feedwater system (1 of 5 100% capacity systems) was inoperable during the period from May 16, 1988 to May 25, 1988. Procedure A-52.4, "Control of Limiting Conditions for Operating Equipment" for the Turbine Driven Auxiliary Feedwater system had been initiated at 0700 on May 16, 1988 to permit installation of a replacement service water bypass solenoid valve for the pump.

The solenoid. valve was installed, tested and determined operable on May 18, 1988. However, during this time, NRC Inspection 88-10 regarding Ginna's Pump and Valve Program identified the need for including the Turbine Driven Auxiliary Feedwater Pump Steam Admission check valves (V-3504B and V-3505B) in the test program. An external inspection of the subject valves was immediately conducted to determine if the required testing criteria could be satisfied using a visual indicator on the existing counter weight swing arm. During this inspection, operated with a notable resistance it was noted that V-3504B as compared. to the opposite train V-3505B. As a result, the existing A-52.4 was amended to incorporate the inoperable check valve on May 17, 1988. Corrective'ctions were immediately taken as addressed below..

A Maintenance Work Request and Trouble Report (MWRTR)

.was initiated on May 17, 1988 for V-3504B which identified difficulty in open and close movement and requested repairs as necessary to correct the condition. Maintenance personnel examined the check valve externally, adjusted the packing gland, tightened the swing arm (counter weight) and 8807l90156 880707 PDR ADOCK 05000244 8 PNU

externally actuated the shaft assembly. to permit moving the disc. However, resistance was still noted. This activity resulted in Maintenance personnel initiating a second MWRTR to disassemble and repack the valve shaft on May 19, 1988.

Check valve 3504B was disassembled, all parts were cleaned and the valve reassembled with new packing installed in the .packing gland. This action, again, did not substantially improve the valve operating characteristics. A surveillance test was subsequently performed which determined that the valve opening satisfactorily met pump performance requirements. However, full valve closure was not evident (Note: Since a backflow motive force could not be obtained due 'o system configuration constraints, the only motive force for closure during this test is the counter weight assembly) . The A-52.4 remained in effect for further valve diagnosis and repair.

On Monday, May 23, 1988 a third MWRTR was initiated, and a detailed inspection plan was developed, resulting in machining .0125" off the valve disc shaft as per vendor recommendations and locating and removing a 1/32" casting high spot on the hinge which was determined to be binding against the internal valve body. The valve was reassembled and the disc was found to be moving freely in both the open and close direction.

Plant Results and Test Department personnel performed an operational test on May 25, 1988. The check valve functioned properly and the Turbine Driven Auxiliary Feedwater system was declared operable.

To assure continued operability of V-3504B and V-3505B, the performance testing procedure PT-16 has been changed to incorporate these valves into the monthly testing program.

Additional information concerning actions to improve our inservice testing program will be addressed in our response to Inspection 88-10.

You will note that this report was required to be submitted by June 22, 1988. Although it was prepared to meet that date, an administrative error resulted in it not being sent. The error was identified during follow up and closeout of this item. We regret the error.

Very truly yours, Bruce A. Snow Superintendent-Nuclear Production

zc: U.S. Nuclear Regulatory Commission (original)

Document Control Desk Washington, DC 20555 xc: Ginna Senior Resident Inspector