ML20029B254

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LER 91-005-00:on 910131,steam Leakage in Auxiliary Feedwater Pumproom Caused ESF Actuation.Caused by Personnel Error. Control Room Operator Closed Steam Supply Isolation Valve to Stop Steam Leaking & Event Will Be reviewed.W/910304 Ltr
ML20029B254
Person / Time
Site: Beaver Valley
Issue date: 03/04/1991
From: Noonan T
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-91-005, LER-91-5, ND3MNO:3110, NUDOCS 9103060311
Download: ML20029B254 (6)


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March 4, 1991 ND3MNO:3110-Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License _No. DPR-66 LER 91-005-00 United-States: Nuclear Regulatory Commission-Document control' Desk Washingtoni._DC_ 20565

Gentlemen 1 In - accordance with Appendix A, Beaver Valley Technical Specifications, the following Licensee -Event Report 'is

-submitted:

LER 91-005, 10 CFR 50.73.a.2.1v, "ESF Actuation-Steam Generator Blowdown Isolation".-

Very truly yours,

[. [. @ 6

-T. P. Noonan General Manager Nuclear-_ Operations JGT/sl

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March 4,.1991' '

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acc: Mr.-T. T.-Martin,nRegional Administrator :l t United ~ States-Nuclear Regulatory Commission-

-Region-1 m 475LAllendale Road- 1 King of Prussia, PA::19406 C. A. Rcteck,10hio Edison 76.S.-. Main Street

' Akron,10H 44308-Mr. A. .DeAgazio,: BVPS Licensing Project Manager United States Nuclear Regulatory Commission

> ._ W ashington,;DC 20555 -j i

J. Beall,1 Nuclear Regulatory Commission,  !

BVPS Senior-Resident-Inspector LarrylBeck _.

Cleveland Electric 6200 Oak Tr( e Blvd.

Independence,. Ohio. 44101 L INPO Records Center. -1 Suite:1500 i 1100 Circle 75 Parkway. 1

-: Atlanta, GA 30339-G.-E.-Muckle, Factory 1 Mutual Engineering 1680 Anderson Drive #BLD10-Pittsburgh,1PA 15220-2773 '

Mr./ Richard Janati ,

Department of. Environmental Resources

'P.=0. Box 2063' 16th Floor, Fulton Building =

g -- Harrisburg ,1 PA 17120 4 l Director,--Safety Eval'uation & Control-

,VirginiaEElectric &. Power Co._ <

iP.O.-Box 26666 =

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. Management Analysis Company

, ;112671 High' Bluff' Drive '

San Diego, CA 92130-2025'

-: J . ' M . Riddle

_NUS Operating-Service-Corporation Park' West.II:

Cliff Mine' Road-Pittsburgh, PA 15275

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P ACitlTY hAMt Hi Doca ti huMetR (21 FAGE G Beavor Valley Power Station Unit 1 o 15 l 0 I o l o 131 3 l 4 1 lor l 0 l 4 vita iA, ESF Actuation - Steam Generator Blowdown isolation  !

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~~~} vis 1:< m a.w. asecreo svenssion os re "i] No l l l uetRACT m ,ue m .. .,. .~, , u .,.,,. <, -,- . e n e i On 1/31/91 at 0303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br />, blowdown from all steam generators isolated when blowdown containment isolation valves TV-BD-100A,B,'C and blowdown sampling- containment isolation valves. TV-SS-117A,B,C- closed. Steam, leaking past the seat of the normally closed steam supply trip valve, TV-MS-105A, to the steam-driven auxiliary feedwater pump caused the pump to develop a discharge pressure sufficient to cause automatic blowdown isolation. Steam supply to the pump was isolated by closing the upstream steam supply isolation valve (MOV-MS-105). The, diaphragm of- TV-MS-105A was rerlaced by Instrument & Control (I&C) technicians. The cause 4 this event was personnel error. The air supply to TV-MS-105A was set at 30 psi versus the required 50 psi. TV-MS-105A had insufficient air pressure to completely close'against full secondary steam-pressure. I&C personnel increased the air pressure to maintain the valve closed. This event will be reviewed by all I&C supervisors and technicians. There were no safety implications to the public as a result of this event. TV-BD-100A,B,C and TV-SS-117A,B,C are containment isolation valves which actuated to their required safety related positions.

NZ Form 364 (649)

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'On 1/30/91, Unit 1 was in Hot Standby (Operational Mode 3),

preparing _ for station startup. At 1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />, the primary auxiliary building- operator reported a steam leak in the auxiliary feedwater pump room. Steam was observed leaking from

.the actuator of TV-MS-105A, one of two normally closed trip valves which supply steam to the steam-driven auxiliary feedwater pump (FW-P-2). Steam was also leaking past the seat of TV-MS-105A causing FW-P-2 to rotate slowly. Steam supply to

-_FW-P-2 was isolated when a control room operator closed the steam supply isolation valve (MOV-MS-105). Steam isolation requires into Technical Specification 3.7.1.2, which requires FW-P-2 entry ~ to be returned to Operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Maintenance was requested to replace the diaphragm of TV-MS-105A._ Diaphragm replacement was completed on 1/31/91.

=The I&C s'upervisor noted that only 9 psi was required to stroke the valve' _ closed yet the air regulator was set at 65 psi. The I&C supervisor felt that this was excessive and may have contributed to the failure of this diaphragm since it had been replaced just one week earlier. The I&C supervisor instructed the_ technicians .to set the air. pressure at 30 psi. The valve stroked . full open and full closed properly. Operations prepared to perform the post-maintenance valve stroke-test.

As MOV-MS-105 was opened, the local operator obscrved'the FW-P-2 turbine rolling. . At - 0303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br />, blowdown from all steam

_ generators isolated when blowdown isclation' valves TV-BD-100A,B,C and blowdown sampling isointion valves TV-SS-117A,B,C closed. This automatic- actuation to maintain steam- generator inventory occurs by design whenever the discharge -pressure of any of the three auxiliary feedwater pumps

-reaches 500 ;psig . When the operating crew realized that TV-MS-105A was leaking by, even though it displayed a closed-indication, _ MOV-MS-105 was closed . to stop the leak.

Subsequently, I&C technicians increased the air pressure to 55

-psi and TV-MS-105A remained completely closed against steam pressure when MOV-MS-105 was opened. A satisfactory valve stroko ' test was .then performed on TV-MS-105A as part of post-maintenance testing.

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O lo 0l 3 0F 0 14 rm y .. w wet uw nn CAUSE OF EVENT The- cause of the event was personnel error. While processing the- Maintenance Work Request (MWR) written to replace the diaphragm of TV-MS-105A, I&C supervisors did not find this particular valve in the specifications table of the Corrective

-Maintenance Procedure used for a large number of air-operated

-valves. . The--I&C supervisor reviewing the MWR instructe- (on the

-MWR) the technicians- - to set the regulator air pressure to the value found prior to-maintenance.

The I&C work party supervisor suspected that too high of an air set pressure 'on TV-MS-105A may have been responsible for premature- failure of the diaphragm that- had recently been replaced. He instructed the technicians to set the air pressure i.

at 30 ' psi. He did not _ refer to- the correct table in the Corrective _ Maintenance Procedure (CMP) which listed the air set

. pressure.for this valve at 50 psi.

i' When- MOV-MS-105 was opened, TV-MS-105A had insufficient air pressure to remain completely closed against full secondary steam- pressure. Steam leaked past-the seat of TV-MS-105A to the turbine of the steam-driven auxiliary feedwater pump causing it to . develop a discharge-pressure sufficient to trigger automatic closing of! blowdown isolation valves TV-BD-100A,B,C and blowdown

-sample line containment isolation valves TV-SS-117A,B,C.

CORRECTIVE ACTIONS The -following corrective actions have been or'will be taken as a result of this event:

1. The control room operator closed steam' supply isolation valve MOV-MS-105 to stop steam leaking past TV-MS-105A.
2. I&C personnel -increased the air regulator pressure setting of TV-MS-105A (to approximately 55 psi) to maintain the

' valve closed against steam pressure.

3.- This event will. be reviewed by all I&C supervisors and technicians,

4. Instrument and Control supervision is performing an
. evaluation to determine the cause for the personnel error and any additional corrective actions. ,

NIC Form 384A (6A9)

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_This event was reported to the Nuclear Regulatory Commission at 0438 hours0.00507 days <br />0.122 hours <br />7.242063e-4 weeks <br />1.66659e-4 months <br /> in accordance with-10 CFR 50.72.b.2.ii. This written report is being submitted in accordance with 10CFR50.73.a.2.iv, as an' event. involving an Engineered Safety Features Actuation.

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, PREVIOUS OCCURRENCES.

Two-previous similar events were identified:

-LER 88-014-00 Steam- driven auxiliary feedwater pump-actuation due to diaphragm failure.

LER 90-014 A failed pressure switch caused . the automatic- start of the steam drivon' auxiliary feedwater pump and steam generator  :

blowdown isolation.

JAFETY IMPLICATIONS There were no safety implications to the-public as a result.of this-- event. Blowdown ~ isolation valves TV-ED-100A,B,C and sampling isolation .;-valves TV-SS-117A,B,C are containment-isolation. valves which actuated to their_ required safety related

_(closed); _ positions. Blowdown. from-all_.three steam generators had. been _ isolated prior to -this = event by trip valves:at the blowdown flash'tankLinlet.

' NIC Poem 3eSA 4 49) .

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