ML20044D218

LER 93-002-00:on 930403,containment Isolation Valve Which Controls Reactor Makeup Water to Containment Exceeded Max Time for Closure.On 930413,lockwire & Safety Tag Removed. Caused by Communication Errors.Safety Tag Process Reviewed

ML20044D218
Person / Time
Site:	Prairie Island
Issue date:	05/13/1993
From:	Hunstad A NORTHERN STATES POWER CO.
To:
Shared Package
ML20044D217	List: ML20044D215 ML20044D218
References
LER-93-002-02, LER-93-2-2, NUDOCS 9305180346
Download: ML20044D218 (6)

Text

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Prairie Island Nuclear Generating Plant Unit 2 05000 306 FAGE 1 OF (3) 5  :

TfTLE W LOSS of AdniniStrative Control ol an Inoperable I

Containment Isolation Valve Due to Personnel Error

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AB T ACT (Limit to 1400 spat.es, i e., approximately 15 single-spaced typewrrt en knes) (16)

On April 3, 1993, control room operators performed surveillance procedure ,

SP2272, Quarterly Cycling of Pressurizer Relief Tank Reactor Makeup k'ater and Nitrogen Control Valves. One containment isolation valve, which controls _

reactor makeup water to Unit 2 containment, exceeded its maximum time for (

closure (an ASME Section X1 requirement), and was declared inoperable. The redundant containment isolation check valve was operable. To comply with .

Technical Specifications, the control valve was closed and its air supply was i lockwired closed. Later, to improve control over the penetration, the ,

upstream manual isolation valve was closed.  !

Later, when the System Engineer requested the control room to stroke the f inoperable control valve for troubleshooting purposes, an operator was sent to restore the air supply to the control valve. lie performed that action, but had misunderstood the instructions and mistakenly opened the manual isolation valve. Later, another operator making rounds discovered the manual valve open  ;

when it should have been shut. The situation was corrected. Administrative }

control of the penetnion had been lost for about 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. The redundant [

containment isolation check valve was operable throughout the period. t

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NAC rs ed FORM 366A ' U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 EXPlRES 5/31/95 ESWA*ED BJADEN PER RESPONSE TO COMPLY W:TH TH:S LICENSEE EVENT REPORT (LER) $$TESSEffd5ERis$UJ!?OOwS$2 TEXT CONTINUATION AC M R S MAMGEMN BMNOWBB WW S NMR MGULATORY COMM:S$rON. W ASHW370% DO 20$5$4001, AND TO THE PAPERWVDR*C REDJOT)ON PR:1!ECT pincioan DFFCE oF MAM3EMENT AND BJ33ET, WASMW3 ton. DO 7J503 F ACIUTV hAME (1) DOCAET NUMBER (2) LER NUMBER (S) FAGE(3) y LiusENLA. 6tf. V4bCA NJMBER #dJUBER Prairie Island Unit 2 05000 306 -

> OF 5 93 002 CO rExT w we ,c.c. . w..a m emw. m. , a wc re,,, :wy v n EVENT DESCRIPTION On April 3, 1993, control room operators performed surveillance procedure SP2272, Quarterly Cycling of Pressurizer Relief Tank Reactor Makeup Water and Nitrogen Control Valves. One containment isolation valve, CV-31342, which controls reactor makeup water to Unit 2 containment, exceeded its maximum time for closure (an ASME Section XI requirement), and was declared inoperable.

See Figure 1. The redundant containment isolation check valve, 2RC-3-1, was operable. To comply with Technical Specification 3.6.C.3.c, CV-31342 was closed and its air supply was lockwired closed. A safety tag was also applied to the air supply and to the control room control switch for CV-31342.

(Safety tags are used to administrative 1y control equipment status.) Later, to improve control over the penetration, the upstream isolation valve 2RM-8-4 was closed, vent valve 2RC-9-4 was verified closed, and both valve positions were secured with safety tags. (Vent valve 2RC-9-4 was closed and capped throughout the event, and check valve 2RC-3-1 was operable throughout the event.)

Later, the System Engineer requested the control room to stroke the inoperable control valve for troubleshooting purposes. To do this, he and the Shift Supervisor determined that valves 2RM-8-4 and 2RC-9-4 should remain closed and be lockwired in that position to maintain compliance with Technical Specification 3.6.C.3.c. Valve 2RM-8-4 was lockwired closed, but valve 2RC 4 could not be lockwired because there was no hole in the handwheel through which to pass a lockwire. Maintenance was contacted to drill a hole in the handwheel of valve 2RC-9-4, and on April 13 that was completed. An outplant operator was then sent to lockwire valve 2RC-9-4, and to remove the lockwire and safety tag from the air supply for CV-31342 and open the air supply so the valve could be stroked. At about 1100 on April 13, he performed those actions, but had misunderstood the instructions and, assuming he was making a routine system restoration after maintenance, also removed the lockwire and safety tag from valve 2RM-8-4 and opened it. The outplant operator informed the control room operator that he had completed his tasks. The control room operator removed the safety tag from the control switch for CV-31342.

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NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 m e23 EXPIRES 5/31/95 ES'IMA'ED BURDEN PER RESPONSE TO cOMat.Y W:TH TH;S INEORMATON COLLECTON REQJEST: 50 0 hrs F ORW ARD LICENSEE EVENT REPORT (LER) COMMecS REcARams BsRnEN EST,Mi E TO mE ,N.ORuuoN TEXT CONTINUATION ANO REO R S MANAGEMW' BriANOH (MNBB maw S NJOLEAR REGULATORY COMM'SSON W ASHrN3 TON. DC 205SS-DD01. AND TO TME FAPERWORK REDUCTCN PROJECT Q1SD-0104n DFSCE OF M ANAGEMENT AND BJDGET. WASMfNGTON. DC 20503 f ACILITY hAME (1) DOCKET NUMBER (2) LER NUMBER (8) PAGE (3) blQvENT.A RLWhCN NUuBER NUMBER 05000 306 3 OF 5 l Prairie Island Ur.it 2 93 002 00 l TLxT pr mt , syste as re:pura. use saa trone copes or k% term 3%A; (17) 1 Valve status now was: ,

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- CV-31342 closed and its air supply available I

- 2RM-8-4 open

- 2RC-9-4 closed and lockwired

- 2RC-3-1 operable But the control room operators, the Shift Supervisor and the System Engineer believed 2RM-8-4 was still closed and lockwired.

CV-31342 was stroked for troubleshooting, and when that was completed, CV-31342 was left in the open position. At about 1700, in preparation for shift turnover, the control room operator realized that he had not received instructions on final disposition of CV-31342, and after discussion with the j Shift Supervisor the decision was made to close it. Shift turnover occurred at 1800. At about 0030 on April 14, a control roti operator was making outplant rounds and decided to check the status of the penetration. He found the control valve closed, its air supply open, 2RM-8-4 open and 2RC-9-4 lockwired closed. He called the Shift Supervisor to report his findings. The Shift Supervisor instructed the operator to close and lockwire valve 2RM-8-4.

At this point the Technical Specifications were again satisfied.

l CAUSE OF THE FVENT The event had several causes.

Errors were made in communication of verbal instructions.

Safety tags can be issued by the Shift Supervisor without a Work Request. Use of safety tags in this event caused confusion concerning status of the penetration. Isolation and restoration instructions provided by the Shift Supervisor did not contain specific conditions for removing the isolations, and did not indicate that the purpose of the valve manipulations was to maintain containment integrity.

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ANALYSIS OF THE EVENT This event is reportable purs_ 10CFR50.73(a)(2)(1)(B) since plant operation was in violation of 14.- onical Specification 3.6.C.3.c for about 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br />. Health and safety of the public were unaffected since containment integrity existed at all times; check valve 2RC-3-1 was operable throughout the event. [

[ CORRECTIVE ACTION ,

The process for use of safety tags is being reviewed and revisions will be F made where needed.

) Operators will review the event report. Operators will also review the [

administrative requirements for oral communications and for use of safety tags. ,

FAILED COMPONENT IDENTIFICATION  ;

None.  !

i PREVIOUS SIMIIAR EVENTS  !

There have been 4 previous events involving loss of administrative control of 1 containment penetrations. Containment integrity remained intact in all of the j 4 events. The events are AO 75-27 and RO's 76-03, 76-41 and 76-42.  ;

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, sw a e.c sEosoN NUMBER NUuSER 05000 306 5 OF 5 Prairic Island Unit 2 002 00 93 TEXT fu more nece a rema ss sae ecottsons' copoes or NRC +:m xw p n OUTSIDE CONTAINMENT INSIDE CONTAINMENT f

A 2RM-8-4 CV-31342 N

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