ML19325C782

LER 89-023-00:on 890911,discovered That Remote Indication to Valve RHR-20 Not Available from 890320-0912,when Supply Breaker Replaced.Caused by Lack of Personnel Recognition. Breaker Replaced & Indication restored.W/891011 Ltr

ML19325C782
Person / Time
Site:	Vermont Yankee
Issue date:	10/11/1989
From:	Pelletier J, Wanczyk R VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-023, LER-89-23, VYV-89-195, NUDOCS 8910170266
Download: ML19325C782 (4)

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ERMONT YANKEE NUCLEAR POWER CORPORATION P. O. BOX 157 q l -.

ilh , ' GOVERNOR HUNT ROAD :

. VERNON, VERMONT 05354 c g.;

October 11, 1989l y , -VYV 89-195 oq x.: _U.S. Nuclear RegulatoryrCommission

Document Control Desk:

Washingtoni;D.C. 20555

REFERENCE:

Dperating' License DPR-28 l Docket.No.'50-271 ffy l Reportable Occurrence No. LER 89-23

,: 4 Dear-Sirs -

7 Ai defined by 10CrR50.73; we;are reporting the attached Reportable

' Occurrence as LER 89-23.

Very truly yours, VERMONT-YANKEE NUCLEAR POWER CORPORATION rt J. Wanc Acting Plant Manager cc: Regional Administrator ,

s. USNRC -)

Region I i 475 Allendale Road ,  ;

King of Prussia, PA 19406 I

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NRC Form 384 U.S. NUCLEAR REGULATORY COMMISSION F

f9-83)*

APPROVED OMS NO.3150-0104 J

LICENSEE EVENT REPORT (LER) EXPIRES 8/31/96 FACILITY.NAME (5) DOCKET NO. *) PAGE (a)

VERMONT' YANKEE NUCLEAR POWER STATION- 0 l 5 l 0 l 0 l(0 l 2 l 70l110Fl0l3 l1 ,

TITLE (*) Failure to perform daily instrument checks on the Low Pressure Coolant Injection System Crosstie Monitor due to interpretation of Tech. Spec, Requirements.

EVENT DATE (5) LER NUMBER (8) REPORT DATE (') OTHER FACILITIES INVOLVED (*)

MONTH DAY YEAR YEAR SEO. # REV# MONTH DAY YEAR FACILITY NAMES DOCKET NO.(S) 0 5 0 0 0 0l9 1ll' 8l9 8l9 -

0l2l3 -

0l0 1l0 1l1 8l9 0 5 0 0 0 OPERATINO THIS REPORT IS SUBMITTED PURSUANT TO RE0'MTS OF 10CFR 6: ( ONE OR MORE (SS)

MODE (') N l20.402(b) __ 20.405(c) __ 50.73(a)(2)(iv) __ 73.71(b)

POWER _l20.405(a)(1)(I) __ 50.36(c)(1) __ 50.73(a)(2)(v) __ 73.71(c)

' LEVEL ( *) Il d 0 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)(II) __ 50.73(a)(2)(viii)(B)

............... 20.405(a)(1)(v) 50.73(a)(2)(III) 50.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER ( a)

NAME TELEPHONE NO.

AREA CODE JAMES P. PELLETIER, PLANT MANAGER dd2 d d M -l d d 'Il 1 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (58)

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

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

l N/A- l ll l l l l ..... N/A l l l l ll l ......

N/A- l lll lll ..... N/A l lll lll ......

SUPPLEMENTAL REPORT EXPECTED ( *) EXPECTED l MO DA YR SUBMISSION lYES (If ves, complete EXPECTED SUBMISSION DATE) xlNO DATE (15) l l l ABSTRACT (Limit.to 1400 spaces, i.e., approx. fifteen single-space typewritten lines) (15)

Vermont Yankee Technical Specification 4.2.A, Table 4.2.1, requires that an instrument check of the indication for the Residual Heat Removal (RHR) (EIIS = BO) system crosstie

valve, RHR-20,.be completed once per day. Contrary to this requirement, it was disco-vared, on 9/11/89, that the remote indication to the-valve had not been available from 3/20/89, when the power supply breaker to the indication was removed, to 9/12/89, when the breaker was replaced.

1' l The root cause of this event is that Operations personnel did not recognize that the RHR-20 breaker was needed to maintain continuity for the LPCI crosstie monitoring circuit which is required by Tech Specs. 4.2.A.

On 9/12/89 at 1455, the breaker was replaced and indication was restored to the valve (RHR-20). A change was made to OP 0150 " Responsibilities and Authorities of Operations Department Personnel" to include a specific reference to the RHR-20 valve indication.

Long term corrective actions are currently being processed.

NRC Form 384 (9-83)

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APPROVED OMS NO.3150-0104' q

1. .; ' LICENSEE EVENT REPORT (LER) TEXT CONTINUATION EXPIRES 8-31-96.

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UTILITY,NAME ('). DOCKET NO. (*)

YEAR LER NUMBER (*)

SEQ. # REV#

PAGE (8) I VERMONT YANKEE' NUCLEAR POWER STATION 0l5l0l0l0l2l7l1 8l9 -

0l2l3 -

0l0 0l 2 0F 0l 3 TEXT (If more space is required, use additional NRC Form 384A) (")-

DESCRIPTION OF EVENT w

Vermont Yankee -Technical Specification 4.2. A, Table '4.2.1, requires that an instru -

mentJcheck of the indication for the residual heat removal-(RHR)' system crosstie valve, r O RHR-20, be completed once per day. Contrary to this requirement, it was discovered, on l

9/11/89, that the. indication to the valve had not been available from 3/20/89, when the power supply breaker to the indication was removed, to 9/12/89, when the breaker was i replaced.

In 1974/19' 5, Tech. Spec. 4.2.A was revised to reflect the removal of the RHR-LPCI loop selection-logic. The loop selection logic was designed to determine which recire loop i

.was breached during a LOCA and utilized the LPCI crosstie valve to direct cooling water to '

'the selected loop. The change to Tech. Specs, that removed the loop selection logic 1 , ' required-that the RHR crosstie valve, RHR-20 be locked closed and the_ power leads discon-nected. .

On 5/21/75, Vermont Yankee received a change to the Technical Specifications that

' required an instrument check of the RHR-20 valve position indication. This check had been e -included:on the' Control Room Operator's Log and continued tc be there until 7/11/80 when

-it was removed by a revision to the procedure since another procedure, AP 0152, " Shift' Turnover" included the RHR-20 valve indication. AP 0152 was revised on 10/12/81 to include a check-off for "other RHR, RHRSW valves." This has been a check-off in that pro-cedure and currently remains there.

- During the 1989 shutdown, on 3/20/89, it became necessary to provide a breaker for cnother system valve. -Due to the recent work performed related to Info. Notice 89-045, the only available breaker was the breaker that supplied the RHR-20 valve. As that valve j? is chained and locked closed with the power-leads disconnected personnel interpreted the i breaker out of service. The breaker was removed with a subsequent loss of indication.

On 9/11/89, the Maintenance Department required the use of the breaker cubical, that previously had been used for the RHR-20 valve, as a safety class power supply was needed l L ,

L for another job. At that time it was realized that the breaker cubical in question was

-needed for the RHR-20 valve indication. On 9/12/89, the breaker was replaced for the >

RHR-20 valve and indication was restored to the valve.

-CAUSE OF EVENT The root cause of this event is that Operations personnel did not recognize that the RHR-20 breaker was needed to maintain continuity for the LPCI crosstie monitoring cir-cuit which is required by Tech Specs. 4.2.A.

Personnel were aware of the importance of maintaining the RHR-20 valve shut. They believe that Tech. Specs were met because:

NRC Form 384A (9-83)

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. . _ , .M LICENSEE = EVENT REPORT.(LER)? TEXT CONTINUATION APPROVED OMS NO.3150-0104

EXPIRES 8-31 -

k;p: UTILITY NAME (!)i DOCKET NO. (*). LER NUM8ER (*) PAGE (:}:

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YEAR SEO.' # REV#

st -VERMONT-YANKEENUCLEARPOWERSTATION 0l5l'01010l217l1 8l9 -

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0l0 0l 3 0F 0l 3 N TEXT 7;(If more spacetis required,- use additional NRC Form-384A) (") l

, L' ' RHRi 20 is chained arid _' locked shut

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4 ' *i RHR-20 motor.1eads are disconnected'

'* fThe RlR-20-keylock; switch is-defeated

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cndsthusithere is'no way that the valve can be: opened. c

'N ANALYSIS OF EVENT A <

LAlthough the indication.for this valve was not available for a: period of time,.the

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valve

has been chained and locked close with the motor leads disconnected since the inclu-: ;t icion of Tech. Spec.~ change 25 in 1975. With this arrangement, confidence that the valve l ,

would notsbe inadvertently opened is assured.. q qca, , . .

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Therefore, during the events of_.'this report,'there is reasonable ~ assurance that there.

d..were no; adverse safety implications to plant equipment,; personnel, or to the public. --

! CORRECTIVE ACTIONS JThe following corrective actions have.been completed.

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m :1)1JT'hhl breaker was replaced and indication restored to RHR-20 I onL9/12/89.:

i2)L<APl0150?" Responsibilities and Authorities of Operations Department' Personnel" was revised to-include a specific check of the RHR-20 valve" indication.

rhe following corrective' actions will be completed.

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l 1) :A:copyLof this LER will.be sent to all licensed operators for their review and 7- ' signature to' emphasize the importance of this requirement.

C 'l2) !A' change to Tech. Specs. to eliminate this surveillance will be submitted for NRC' d

' review and approval. 1 E

o. . . , g IADDITIONAL'INFORMATION Similar: events have been reported to the commission in the last five years as LER 87-04, and'89-20.

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NRC Form 384A

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