ML19351A457

LER 89-014-00:from 891115-16,Tech Spec 3.0.3 Entered Voluntarily to Repair Leaking Containment Purge Isolation Dampers.Caused by Need to Repair Dampers.Dampers Closed & Automatic Isolation Feature restored.W/891212 Ltr

ML19351A457
Person / Time
Site:	Farley
Issue date:	12/12/1989
From:	Hairston W, Dennis Morey ALABAMA POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-014, LER-89-14, NUDOCS 8912180033
Download: ML19351A457 (4)

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Alabama Power C:mpany '

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,f .IJ - Post Office Box 1295-Birmingham. Alabame 35201 Telephono 205 868 5581. -l W. G. Hairston, til ' s Senior Vice President Nuclear Operations gghgg3 g the soutwn electrc system ,

v 10CFR50.73 L December 12, 1989 Docket No. 50-364

.U. S. Nuclear Regulatory Commission ATTN: Document Control Desk

-Washington, D.C. 20555 Dear Sir

~ Joseph M. Farley Nuclear Plant - Unit 2 Licensee Event Report No. LER 89-014-00 Joseph M. Farley Nuclear Plant, Unit 2 Licensee' Event Report No. LER 89-014-00 is being submitted in accordance with 10CFR50.73.

If you have any questions, please advise.

Respectfully submitted, l.

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. G. He.irston, III VGH,III/JARamd 8.60 l ' Enclosure l cci Mr. S. D. Ebneter

! Mr. G. F. Haxwell 1

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Joseph M. Farley - Unit 2 o is l 0 l 0 1 o l 31 6l4 __1lorl 013 TITLt t4l Technical Specification 3.0.3 Entered To Repair Containment Purge Dampers IVENT DAf t ill L;R NueeBER tal REPORT DATE (M OTH&R f ACILITit4 INVOLVED (Si MONTH DAY YEAR YlAR 'Q '"L

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NAME TELEPHONE NUM0f R ARE A COQt D. N. Morey, General Manager-Nuclear Plant 2 05 N OOJ ti 1 'il 6 COMPLETE ONE LIN4 POR ( ACH COMPONEWT PAILURE DESCRitED IN THl3 REPORT (13)

CAUSE SYST E M COMPONtNT "h)$'g AC R O iA t '

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$V8M153 ION i Yt$ (It ven cornotete 4xPLCTtO $Ugeets;isON OA Til NO l l l AesmCT a,-,, w un soeceu e . mn. ee ureenno,e are on,n.,, s so oes Over the period of time from 1443 on 11-15-89 to 1411 on 11-16-89, Technical Specification 3.0.3 vas entered voluntarily a total of six times for short periods of time in order to repair leaking containment purge isolation dampers.

Technical Specification 3.0.3 vas in effect because the automatic isclation capability of a containment purge damper had been deactivated and the damper was subsequently opened in order to effect the repair of the leaking containment purge dampers. Technical Specification 3.0.3 was in effect for a total of 38 minutes during the two days.

The dampers were closed immediately after each opening. The automatic isolation feature which had been made inoperable to allow repairs was restored after repairs were completed. The containment purge dampers vill be tested for leakage at an increased frequency until as-found leakage rates between tests remain relatively c.onstant.

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Plant and System Identification Westinghouse - Pressurized Vater Reactor Energy Industry Identification System codes are identified in the text as [XX].

Summary of Event f Over the period of time from 1443 on 11-15-89 to 1411 on 11-16-89, Technical i Specification 3.0.3 was entered voluntarily a total of six times for short periods of time in order to repair leaking containment purge isolation dampers [NH].

Technical Specification 3.0.3 was in effect because the automatic isolation capability of a containment purge damper had been deactivated and the damper was subsequently opened in order to effect the repair of the leaking containment purge dampers. Technical Specification 3.0.3 was in effect for a total of 38 minutes during the two days. ,

Description of Event On 11-15-89, the unit was operating at approximately 100 percent power and testing ,

of.the containment purge supply isolation dampers was being conducted per L FNP-2-STP-627.2 (Leak Testing of The Containment Purge System). Each containment purge line has two dampers in series. Testing is done by pressurizing between the dampers.

At 0904, the containment purge supply isolation dampers were found to have leakage i rates that could potentially be in excess of Technical Specification limits. The action statement for Technical Specification 3.6.1.7 requires that within twelve I hours the-leakage be reduced within limits or the penetration isolated on at least one side of the containment boundary.

Repair of the containment purge supply isolation dampers required opening the 48-inch damper outside containment (02P13V281) to allow personnel access for damper adjustments. Personnel safety concerns required deactivation of this damper's l

l automatic isolation function. The dt.mper inside containment remained closed with its automatic isolation capability operable throughout this event.

In order to eliminate the excessive leakage as soon as possible, it was decided to make the required adjustments to the damper seats at current plant conditions rather than vait for the plant to be placed in a condition where the automatic actuation logic for purge and exhaust isolation was not required (Mode 5 - Cold Shutdown). It would have required 15-20 hours to place the unit in Mode 5.

With the automatic isolation capability of 02P13V281 deactivated, Technical Specification 3.3.2 was entered. Action Statement 17 associated with Table 3.3-3 of Technical Specification 3.3.2 requires that the inoperable containment purge damper (s) be maintained closed. During the time the damper was opened to allow access for repairs, the action statement for Technical Specification 3.3.2 was not met and Technical Specification 3.0.3 was entered.

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• ua "==. O'#,'N Farley Nuclear Plant - Unit 2 o ls ;o jo jo l 3l q 4 8;9 0,1l 4 J ;0 0 [3 or ftXT W snese ausse 4 tovuseel use ashamsvia/ M,C Fame ms (th 0 l3 02P13V281 was opened and Technical Specification 3.0.3 was entered voluntarily four separate times on 11-15-89 for a total of 22 minutes. The longest period Technical Specification 3.0.3 was in effect at any one time was 11 minutes.

These periods were 1443 - 1454, 1502 - 1505, 1628 - 1633, and 1646 - 1649.

Leakage testing performed subsequent to adjustment of 02P13V281 proved that the actual leakage through any purge supply isolation damper was not in excess of the Technical Specification 3.6.1.7 limits.

The containment purge exhaust dampers were tested on 11-16-89. Although the ceasured leakage was less than the Technical Specification limit, it was considerably higher than the leakage measured during the previous test which was performed three months earlier. A decision was made to reduce the leakage even though the Technical Specification limit was not exceeded. The exhaust dampers were adjusted during operation in a manner similar to the supply dampers. Technical Specification 3.0.3 was in effect twice for a total of 16 minutes on 11-16-89. The periods were 1340 - 1351 and 1406 - 1411.

Cause of Event Technical Specification 3.0.3 was entered voluntarily to allow access to the damper seats so that the leaking containment purge dampers could be repaired.

Reportability Analysis and Safety Assessment The event is reportable because Technical Specification 3.0.3 was entered. However,

'lechnical Specification 3.0.3 was in effeet for no more than eleven minutes at a time end for a-total of only 38 minutes over a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period. The Technical Specification 3.6.1.7 nction statement requirements for the purge supply and exhaust dampers were met at all times. One of the two dampers in each line remained closed with its automatic isolation capability operable throughout the event. No adverse condition resulted and there was no effect on plant operation. The health and safety of the public vere not affected by this event.

Corrective Action The dampers were closed immediately after each opening. The automatic l isolation feature which had been made inoperable to allow repairs was restored l- ofter repairs were completed. The containment purge dampers vill be tested l for leakage at an increased frequency until as-found leakage rates between L tests remain relatively constant.

1 Additional Information No similar LER'S have been submitted by FNP.

The dampers are NR1A containment purge isolation dampers made by Henry Pratt Co.

This event would not have been more severe if it had occurred under different operating conditions.

E'MC Form 355A (689)