05000029/LER-1986-011, Forwards LER 86-011-00

Forwards LER 86-011-00

ML20214J042
Person / Time
Site:	Yankee Rowe
Issue date:	10/31/1986
From:	St Laurent N YANKEE ATOMIC ELECTRIC CO.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8612010128
Download: ML20214J042 (1)

LER-2086-011, Forwards LER 86-011-00

Event date:
Report date:
0292086011R00 - NRC Website

text

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-f YANKEE ATOMIC ELECTRIC COMPANY r.i.vu on.<<,s><2<.s2e, Star Route, Rowe, Massachusetts 01367

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October 31, 1986 U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: Dr. Thomas E. Murley, Regional Administrator

Subject:

Licensee Event Report 50-29/86-11 Containment Isolation Valves Missed Surveillance

Dear Sir:

In accordance with 10 CFR 50.73(a)(2)(i), the attached Licensee Event Report is hereby submitted.

Very truly yours, hl& dd/d/4 Normand N. St. Laurent Plant Superintendent RLB/nm Enclosure cc: [3] NSARC Chairman (YAEC)

[1] Institute of Nuclear Power Operations (INPO) 8612010128 861031 PDR ADOCK 05000029 S PDR 2 g . )) I \

• A U S. NUCLE AM LEGULATORY COMMISSION NaC perse 338 "3 I APPRIVEO OMS NO 3150-4104 LICENSEE EVENT REPORT (LERI

1. AGE 438 DOCKET NUMSER (21 FACILITY NAME til Yankee Nuclear Power Station 01s10 010101 219 1 loFl 012 TITLE 448 Containment Isolation Valves Missed Surveillance EVENT DATE (Si LER NUMSER ISI REPORT DATE 171 OTHER F ACILITIES INVOLVED 181 iA6 DAY YEAR F ACiLITV N Awes DOCnf T NUM8ERi$1 MONTM OAV YEAR YEAR st u n me

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1l 0 0l 386 8l6 0 l1 l1 0l0 1l0 3l 1 8] 6 oisio,o,o,  ; ,

Twis mEPORT is susMiTTEo PURSUANT TO THE REOuiREulNTs 0,10 Cr A t iCaece eae er . e es c*e serie.,ans siti MODE m ) 20.402(b) 20.406tel 60.73 fall 2Hevi 73 71461 20 40GleH1H4 63.38 feH1) 50.73iell2Het 73.71(si 20 405teH1Hnl 14 341:1121 50 73teH211.I OH ($aec se A8 tract (103 l l 20 408tell1Hed 50.73te H2HJ 60.7 31al(2He.nH A) J66Al to 406teH1Havl 50.73(al(2Het 60.731eH2Husultel 20 40Gisil1Hol 50 73teH25 tad 50.73 rah 2Hal LICENSEE CONTACT FOR TMit LER 1111 NAME TELEPMONE NUMSER

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R. L. Boutwell,. Senior Plant Engineer j 3 4,2,4, ,5,2,6,1 COMPLETE ONE LINE FOR E ACH COMPONENT F AILURE CESCRISED IN TMis REPORT (13)

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• CAUSE SYSTEM COMPONENT 'g ' O' " y#gORT ppgA8 E CAUSE SY ST E M COMPONENT 'ON "eR l I I I I I I I I I I I I I I I I I i 1 1 I l ! ! I I I

$UPPLEMENTAL REPORT EXPECTED (141 MONTM DAY YEAR YE5 III res, esmotete EJrPECTED Sugst155'Ont DA TEI NO l l l ABSTR ACT (L,mer te 7400 speces s e . eaaroseete>y Mtesa snat e spece tyneer,trene #.aess (16l On October 3, 1986, during normal steady state Mode 1 operation, at 100 percent power and during a revision to OP-4637, " Containment Isolation System Valves Operability Check," it was discovered that contrary to Technical Specifications (TS) 4.6.2.1.a, the surveillance requirement for the Containment Isolation Valves, HV-SOV-39 and HV-SOV-42 had not been performed.

The root cause of this occurrence was a failure to properly incorporate this requirement into a procedure.

On October 7, 1986, the surveillance was satisfactorily completed using a temporarily changed procedure. A full review of the surveillances required by TS 4.6.2.1.a was conducted and no further' discrepancies were found. The surveillance requirement will be permanently incorporated into a surveillance procedure. Additionally, a review of surveillance procedures against TS is in progress. These actions are expected to be completed by December 1, 1986.

These valves are in a normally closed position by design, therefore, there was no affect on the public health and safety.

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'NRC Fww* A

• U.S. NUCLEA2 OE!ULK.T@2Y COMMISSION

- LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ArenovEo oui No siso-oio.

EXPIRE 5. 8/3i /05 FACILITY MAME H) DOCKET NUMBER (23 LER NUMSER (6) PAGE 13)

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Yankee Nuclear Power Station o[s10]olol0l2l9 8l6 -

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0 l0 0l2 or 0p iEXT IM more space e requwed, use anwnonalNRC Form 366Ksl Ui)

On October 3, 1986, during normal steady state Mode 1 operation, at 100 percent power, it was discovered that a required surveillance had not been properly incorporated into plant procedures and that the failure to perform the surveillance requirement for the Containment Isolation Valves, HV-SOV-39 and HV-SOV-42 was a violation of TS 4.6.2.1.a. The quarterly surveillances required by Amendment 86 to the TS that requires the valves to be cycled quarterly had not been performed since its issuance on November 8, 1985. A review of the surveil'tance and operational requirements disclosed that the valves, although not cycled, were already in the design position (i.e., closed) for Containment Isolation. .

The root cause of this item was a failure to incorporate the surveillance requirement into a procedure. The surveillance requirement was temporarily incorporated into OP-2658, " Operation of the Post Accident Vapor Containment Hydrogen Control Monitoring System and Sampling System" and the surveillance was satisfactorily completed on October 7, 1986. A full review of the surveillances required by TS 4.6.2.1.a was conducted by the departments assigned responsibility for incorporating surveillance changes issued under Amendment 86.

The results disclosed that all other required surveillances had been inccrporated into appropriate procedures. The missed surveillance requirement will be incorporated permanently into the surveillance procedure, OP-4216,

" Testing of the Containment Hydrogen Venting and Recirculation System."

Additionally, all departments have been assigned responsibility to review their surveillance procedures against TS to ensure appropriate surveillance requirements have been addressed and incorporated into procedures, as appropriate. An independent review will also be conducted. As this is considered an isolated case, these actions are considered adequate and are expected to be completed by December 1, 1986. There have been no similar reportable events.

Since these valves are in their intended closed position by design, there was no effect on the public health and safety.

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NIC FORM 366%

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