ML20012E930

LER 90-002-00:on 900302,identified That Key Sprinkler Isolation Valve Not Adequately Surveilled.Caused by Personnel Error.Valve Verified as Sealed & Surveillances for Fire Protection Valves revised.W/900322 Ltr

ML20012E930
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	03/22/1990
From:	Pelletier J VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
90-081, 90-81, LER-90-002, LER-90-2, NUDOCS 9004090102
Download: ML20012E930 (4)

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\7 ERMONT Y ANKicic NUCLEAR POWElf CORPOR ATION P. O. DOX 157 GOVDtNOR !!UNT ROAD VEftNON, VEitMONT 05354 March 22, 1990 VYV# 90-001 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

REFERENCE:

Operating License DPR-26 Docket No. 50-271 Reportable Occurrence No. LER 90-02

Dear Sirs:

As defined by 10CFR50.73, we are reporting the attached Reportable Occurrence as LER 90-02.

Very truly yours, VERMONT YANKEE NUCLEAR POWER CORPORATION s f(<hV7Mt 1,)

[7 M es P. Pel d{ier Plant Manager cc: Regional Administrator USNRC Region I.

475 Allendale Road King of Prussia, PA 19400 9004090102 900322 7 - eeeg j ,

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pur, NhC Form 366_ U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.2160-0104 (6-89) . EXPIRES 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:

50.0 HRS. FORWARD COMMENTS REGARDING LICENSEE EVENT REPORT (LER) BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P-530), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20$$5.- AND TO THE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON. DC 20603.

FACILITY NAME (') pang (a)

VERMONT YANiiE NUC_LfAR POWER STATION DOCKETNO.(e)l2l7l1 Ol510l010 01110Fl0l3 TITLE (*) M'2 SED SURVEILLANCE OF A KEY FIRE PROTECTION VALVE DUE TO A PROCEDURAL DEFICIENCY EVENT DATE_{5) ,_ LER__ NUMBER (*) REPORT DATE_(L) OT_HER F ACILITIES INVOLVED (*)

MONTH DAY YEAR YEAR SEO. # REV# MONTH' DAY YEAR FACILITY NAMES DOCKET NO.(S)

N/A 0 5 0 0 0 0l3 0l2 9l0 9l0 -

0l0l2 -OLIO Ol3 2l2 9l0 N/A 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT TO REQ'MTS OF 10CFR 6:_ _

/ ONE OR MORE (5t)

MODf (') N 20.402(b) __ 20.405(c) . . _ 50.73(a)(2)(iv) __ 73.71(b)

POWER _ 20.405(a)(1)(1) __ 50.36(c)(1) _ 50.73(a)(2)(v) __ 73.71(c)

LEVEL (5*) 11010 20.405(a)(1)(II) __ 50.36(c)(2) _ 50.73(a)(2)(vii) __

OTHER:

............... .__ 20.405(a)(1)(III) _X 50.73(a)(2)(I) __ 50.73(a)(2)(viii)(A)

....'........... __ 20.405(a)(1)(iv) __ 50.73(a)(2)(!!) ._ 50.73(a)(2)(viii)(B)

............... 20.4Q5(a)(1)(v) 50.73(a)(2)(!!!) 50.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER (ie)

NAME TELEPHON[ NO.

AREA CODE JAMES P. PELLEY!ER. PL ANT MANAGER ( d 2 Pl N 7l -l 7] 71111 CDMPLETE ONE (JNE FOR EACH COMPONENT FAILURE _DESCR[BJD IN THIS REPORT (58)

CAUSE SYST COMPNT MFR REPORTABLE ..... CAUSE SYST COMPNT MFR REPORTABLE ......

TO NPRDS ..... TO NPRDS ......

N/A -------------------------------- ..... N/A -------------------------------- ......

l l l ..... l l l ......

N/A- -------------------------------- ..... N/A --------------------------------

SUPPLEMENTAL REPORT EXPECTED ('*) EXPECTED MO DA YR

~

SUBMISSION

~~l YES (If ves, complete EXPECTED SUBMISSION DATE) Xl NO DATE (55) l l l ABST?ACI (Limit to 1400 spaces, i.e., approx. fifteen single-space typewritten lines) (5')

On March 2, 1990 with the plant operating normally at 100% power, it was identified that a key sprinkler isolation valve (EIIS identifier ISV) was not adequately surveilled.

Thia was the result of a procedural deficiency identified during the resolution of 1990

, Tri:nnial Fire Protection Audit report findings. It was identified that the Technical Specification required surveillance of the isolation valve for the Diesel Fire Pump sprinkler had not been completed. FP-6, the isolation valve for the fire pump sprinkler, was not included in the monthly or annual surveillances of key fire system valves.

Valve FP-6 was verified as sealed in the open position on March 2, 1990. On March 13,

'1990 the valve was cycled and resealed in the open position. The monthly and annual sur-veillance procedures were revised to include this inspection and cycling of the valve.

.The cause of the missed surveillances was a personnel error in not adequately updating surveillance procedures.

i NRC Form 366 (6-89) u

f O

l NRC Form 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS NO.3150-0104 L* '(6,09) CXPIRES 4/30/92 0 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST:

50.0 HRS. FORWARD COMMENTS REGARDING LICENSEE EVENT REPORT (LER) BURDEN ESTIMATE TO THE RECORDS AND REPORTS TEXT CONTINUATION MANAGEMENT BRANCH (P-530), U.S. NUCLEAR

, REGULATORY COMMISSION, WASHINGTON, DC I 20555, AND TO THE PAPERWORK REDUCTION l PROJECT (3160-0104), OFFICE OF MANAGEMENT AND BUDGET. WASHINGTON. DC 70603.

UTILITY NAME (S) DOCKET NO. (*) LER NUMBER (*) PAGE (8) l YEAR SEQ. # REV#

VERMONT YANKEE NUCLEAR POWER STATION 01 fl ( 0( Ol ?l 7l 1 9l0 -

0l0l? - 0l0 Ol? 0F 0l 3 TEXT (If more space is required, use additional NRC Form 366A) ($')

OESCRIPTION OF EVENT L on March 2, 1990 with the plant operating normally at 100% power, a procedural defi-f ciency was identified. This was identified during the resolution of the 1990 Triennial Fire Protection Audit report findings. It was identified that the Technical Specification

!. required surveillance of the isolation valve for the Diesel Fire Pump sprinkler was not per-f;rmed. FP-6, the isolation valve for the fire pump sprinkler was not included in the

. monthly or annual surveillances of fire system valves.

I Subsequent evaluation of the audit finding by Vermont Yankee perconnel determined that the surveillance had not been completed as specified by Technical Specification sections

! 4.13.b.1.b & d.

l The valve in question, FP-6, provides isolation for the sprinkler which protects the dtsel fire pump. This sprinkler is identified in Technical Specifications Table 3.13.F.1-as-a vital sprinkler.

Water for this sprinkler is supplied by the fire protection main, with isolation pro-vided by the FP-6 valve. The valve is normally open, and sealed in that position.

{

r CAUSE OF EVENT Root Cause.

[ Personnel Error The procedural omission is attributed to personnel error in the development, revision, 1 Cnd subsequent reviews of the surveillance procedure following installation of the sprinkler system in 1977.

l ANALYSIS OF EVENT

! Technical Specifications Section 4.13.D.1.b requires a monthly inspection of key fire

prCtection valves. The purpose of this inspection is to verify the proper position of the l valve, and ensure that the valve is sealed in the open position.

Valve FP-6 provides isolation for the diesel fire pump single head sprinkler system.

.LThis sprinkler is defined as a vital sprinkler by Technical Specification Table 3.13.F.1.

This designation as a vital sprinkler infers that the associated isolation valve is con-sidered as a " key" fire protection valve. Therefore, the valve is required by Technical Specifications to be inspected on a monthly basis, t

NRC Form 366A (6-89) e

'NRC Fore 366A U.S. NUCLLAR REGULATORY COMMISSION APPROVED OMS NO.3160-0104 (6s09), . EXPIRES 4/30/92-a ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST 50.0 HRS. FORWARD COMMENTS REGARDING LICENSEE EVENT REPORT (LER) BURDEN ESTIMATE TO THE RECORDS AND REPORTS TEXT CONTINUATION MANAGEMENT BRANCH (P-510), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20$55, AND TO THE PAPERWORK REDUCTION PROJECT (3160-0104), OFFICE OF MANAGEMENT AND DVDGET._ WASHINGTON._DC 20603.

UTILITY NAME ('). DOCKET NO. (a) LER NUMBER (*) PAGE (*)-

YEAR __ .jy[Q. 8 REV8 VERMONT YANKEE NUCLEAR POWER STATION d F4 d d d ?! 7l 1 910 -

010l2 -

0l0 d3 0F d3 TEXT (If more space is required, use additional NRC Form 366A) (")

In addition, Technical Specification Section 4.13.B.1.d requires an annual cycling of fire protection valves. The purpose of this surveillance is to ensure the operability of

-fire protection system valves.

Isolation valve FP-6 does not provide an active function for the operation of the diesel fire pump sprinkler. The activation of the diesel fire pump aprinkler is only depen-dent on the proper position of the FP-6 valve.

CORRECTIVE ACTIONS

-!mmediate Corrective Actions The FP-6 valve was verified as being sealed in the open position on March 2, 1990.

This verification fulfilled the requirement for Technical Specification Section 4.13.B.1.b.

Cycling of the valve was completed on March 13, 1990. Section 4.13.B.1.d of Technical Specifications was satisfied by this action.

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Each of these actions served to demonstrate the continued operability of the diesel fire pump sprinkler. In each case, the surveillances were completed with no discrepancies.

Subsequent Corrective Actions A revision to the Monshly and Annual surveillances for fire protection valves was completed on March 13, 1990. This revision added the FP-6 valve to the respective sur-veillances for verification and cycling.

The surveillance procedures for all other vital fire protection water systems were reviewed to ensure that no additional key valves were overlooked. No additional discrepancies were identified. This review was completed on March 21, 1990.

ADDITIONAL INFORMATION Previous similar events have been reported to the Commission, in the last five years as, LER 89-24, LER 89-20, and LER 87-04.

l

. NRC Form 366A (6-89)

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