ML20011D254

LER 89-022-00:on 891128,plant Operated in Condition Prohibited by Tech Specs When Emergency Diesel Generator a Inoperable More than 24 H.Caused by Personnel Error.Ltr Issued to All Shift supervisors.W/891220 Ltr

ML20011D254
Person / Time
Site:	Waterford
Issue date:	12/20/1989
From:	Mcgaha J, Starkey R LOUISIANA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-022, LER-89-22, W3A89-0212, W3A89-212, NUDOCS 8912260075
Download: ML20011D254 (4)

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( +/" ,. E - Ref: 10CFR50.73(a)(2)(i)-  :

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D'ecember 120, 1989 .

Wr4 '_U.S.LNuclear Regulatory Commission

}j@ ATTENTION ; Document Control Desk j Washington, D.C. :20555 ,

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Subject:

_ Waterford 3 SES' m . Docket No. 50-382 '

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License-No. NPF-38 Reporting of Licensee Event Report Jf '

io ' Gentlemen:

,( - Attached is, Licensee-Event Report Number LER-89-022-00 for Waterford

_ Steam Electric Station Unit 3. This Licensee Event Report _is submitted

.. pursuant to 10CFR50.73(a)(2)(1).

Very.truly yours,- ,

. l q JlR.'McGaha Plant Manager Nuclear '

' JRM/KTW/rk (w/ Attachment) -

f-cci Messrs. R.D.~ Martin

< J.T. Wheelock INPO Records Center

'E.L. Blake

, , , W.M. Stevenson D.L. Wigginton~ ,

NRC Resident Inspectors Office  :

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-2 Perm att U.S. NUCLEIA 4 E$ ULATORY COMMIE 810N

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[- F ACILITY NAAIE til DOCEET NUh00ER (2) PAGE G Waterford Steam Electric Station Unit 3 0 l 510 l 0 l 01318 12 1 lOFl 0 3 TITLEtot .

" Failure to Perform Emergency Diesel  !'

Generator Surveillance due to Technical Specification Misinterpretation"-

EVENT DATE (6) LER NUMBER ($1 REPORT DATE 171 OTHER f ACILITIES INVOLVED (bl MONTH DAY YEAR YEAR ,

SE O AL m MONTH DAY YEAR F ACILITv N AMES OOCKET NUMBER 151 g

N/A 0l5l0l0;0l l l 1 1l 1 2l 2 8 9 8 l9 0 b l2 0 l0 1l 2 2l 0 8l 9 N/A 0[5l0l0g0g l l OPERATING THIS REPORT IS SUOMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5 <Caece one or mor of fa. 8enewmal Ull

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NAME TELEPHONE NVMBER ARE A CODE R.S. Starkey, Operations Superirtendent s 1 0 14 41614 1-1 111131 4 COMPLETE ONE LINE FOR EACH COMPONENT F AILLsRE DE1CRl5ED IN THIS REPORT H31 MAN AC- R A CAUsE system COMPONENT POR,TA8 o E CAU$E sysTE M COMPONENT MANNPAC- POn,T^8h' R

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$UPPLEMENTAL REPORT EXPECTED H46 MONTH DAY YEAR

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On November 22, 1989, Waterford Steam Electric Station Unit 3 was operating at 64% power with the ' A' Emergency Diesel Generator (EDC) inoperable. The ' A' EDG had been declared inoperable because Essential Services Chiller 'A' had been declared inoperable at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on November 21, 1989. Technical Specificat1on (TS) 3.8.1.1 action requirement b specifies that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of declaring one EDG_inoperabic, the other EDG will be demonstrated operable by

-performing a test start surveillance. The 'B' EDG test start was performed 2' hours and 36 minutes after the 'A' EDG was declared inoperable. Therefore, the plant operated in a condition prohibited by TSs.

The root cause of this event is personnel error. TS 3.8.1.1 action requirement  ;

b was improperly interpreted by the Shift Supervisor (SS) resulting in the I failure to run the 'B' EDG within the prescribed time limit. To prevent i recurrence, a letter.has been issued to all SSs which reinforces the current  !

guidance regarding cascading TSs, particularly with respect to EDG surveillance  ;

requirements. Because the 'B' EDG was subsequently tested satisfactorily and demonstrated operable, this event did not threaten the health and safety of the i general public or plant personnel.  !

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S' NNC Perm,30P h U.S NUCLELP. LEIULiTORY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION cPPaovio ous No. 3tio-oio4 e?

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LER NUMBER (4) Pact (3)

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0 l0 0 12 0F 0 13 text a -ac r asse siin On November 22, 1989 Waterford Steam Electric Station Unit 3 was operating at 64% power with the 'A' Emergency Diesel Generator-(EDG) (E1IS Identifier EK-DG) inoperable. The 'A' EDG was declared inoperable at 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on November 21, 1989, due to Essential Services Chiller 'A' (EIIS Identifier KM) being declared inoperable. Because the Essential Chillers are the source of ,

cooling water to the Component Cooling Water Pump (CCW) (EIIS Identifier CC-P) room coolers (EIIS Identifier VF-CLR), and the CCW pumps supply EDG cooling water, it was necessary to declare the 'A' EDG inoperable.

Technical Specification (TS) 3.8.1.1 action requirement b specifies that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of declaring one EDG inoperable, the remaining EDG will be demonstrated operable by performing a test start surveillance. The 'B' EDG was not tested until 2036 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.74698e-4 months <br /> on November 22, 1985, contrary to TS 3.8.1.1 requirements.

The root cause of this event is personnel error. The Shift Supervisor (SS) misinterpreted the action requirements of TS 3.8.1.1, resulting in a failure to perform the required surveillance. The decision to not run the EDG evolved i

from a discussion with the Assistant Operations Superintendent during which TS applicability was questioned because TS 3.8.1.1 was entered by cascading from a support system TS (3.7.12). The surveillance was deemed to be not required, until the on-shift SS reevaluated the situation and performed the test-start surveillance several hours later. The delay was a result of a misunderstanding as to the intent of recent regulatory guidance with respect to EDG limiting condition for operation (LCO) requirements when cascading from

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corrective maintenance versus preventative maintenance on support systems.

As an action to prevent recurrence, letter W3089-0120 has been issued to all SSs which reinforces the guidance provided in Plant Management Directive Number 34 regarding cascading TSs. This guidance dictates that when a component support system is declared inoperable, the component served by that support system shall also be considered inoperable and the TS LCO shall be entered for that component.  ?

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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION e.PP:ovio ous No. moe  !

EXPIAES: 8'31/EB . J i PAcILITV haa8E (Il DOCr.ET NUGASER (2) LEM NUMSER (Si PAGE (3)

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TEXT W mee ausse As menest ses asWeenet NAC /enn 24'st (17)

Because'the..'B' EDG was successfully tested and demonstrated operable, this

,. event did not threaten the health and safety of the general public or plant

. personnel..

SIMILAR' EVENTS ,

LER 89-005 reported a similar event in that TS interpretation was questioned iin light of-the cascading TS issue. Since LER 89-005 was submitted, Waterford 3

' has issued' Plant M?nagement Directive Number 34 to clarify TS interpretation.

PLANT CONTACT R.S. Starkey, Operations Superintendent, 504/464-3134 i

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i NRC FORM 366A *U.S. CFO 19FS-520 %89 00d M  !

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