ML19347A927

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LER 80-061/03L-0:on 800825,core Spray Valve Mo 1400-24A Failed & Prevented Valve Mo 1400-25A from Being Tested. Caused by Lack of Lubrication.Valve Lubricated & Returned to Svc.Valve Insp Scheduled During Next Outage
ML19347A927
Person / Time
Site: Pilgrim
Issue date: 09/24/1980
From: Mcloughlin M
BOSTON EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19347A921 List:
References
LER-80-061-03L, LER-80-61-3L, NUDOCS 8009300535
Download: ML19347A927 (2)


Text

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LICENSEE EVENT REPORT CONTROL BLOCK: l 1

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EVENT OESCRIPTION AND PROBA8LE CONSEQUENCES h t o l a l l On August 25, 1980 at approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> surveillance testing of the Core Spray I jog 3; ; System, which was necessary to permit continued reactor operation, was not completed. l Ioi4; 1 The failure of Core Spray Valve MO 1400-24A prevented Core Spray Valve MO 1400-25A l lo I5l l from being tested. An orderly shutdown was initiated and terminated at 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br /> l l o 16 l l the same day a'f te'r the Core Spray Valve M01400-24A was manually placed in the open I l o l 7 l l position. Valve MD 1400-24A was repaired, tested and declared operable at approximate (ly I o la l l 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br /> on August 27, 1980. ]

80 7 8 9 0E CODE S 8C DE COMPONENT CODE SU8 CODE SU E lo191 'lS l Fj@ g@ l Xl@ lV l A lL lV [E lX l@ l Fl@ ]Q 9 12 13 18 19 20 7 8 to 11 SEQUENTIAL OCCURRENCE REPORT 'EVISION EVENT YE AR REPORT NO. CODE TYPE NO.

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33 34 35 36 3/ 40 - 41 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h Iiloil The valve was lubricated and successfully operated. Inspection of this valve will l Iilil i be scheduled for the next refueling outage. I l

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LL.id I I 80 7 8 9 STA  % POWER OTHER STATUS IS O RY DISCOVERY DESCRIPTION I1 l5l W h l1l0l0l@l N.A. l lBl@l Routine Testing l ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE N.A.

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PERSONNEL EXPOSURES NUM8ER TYPE DESCRIPTION N.A. l l 1 l 7 l l 0] 0 l 0l@l Zl@l PERSONN E L INJU IES NUMRER DESCRIPTION N.A. l l1 lR8 I9 l 0l 0l0 l@l12 7 11 80 LOSS OF OR DAMAGE To FACIUTY TYPE DESCRIPTION N.A. l

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BOSTON EDISON COMP /d;Y PILGRIM NUCLEAR POWER STATION DOCKET NO. 50-293 o

Attachment to LEB 80-061/03L-0 Description On August 25, 1980 et approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> surveillance testing, which was initiated because of failure of the HPCI system, determined that the 'A' loop of the Core Spray System was inoperable. During this surveillance testing, Core Spray Valve MD 1400-24A failed in a partially open position. The failure of valve MD 1400-24A prevented station personnel from performing the required testing of Core Spray Valve MO 1400-25A. As an active component of the Core Spray System, Technical Specification 3.5.C.2 requires that valve MO 1400-25A be verified as operable by testing when the HPCI system is inoperable.

An orderly shutdown was immediately initiated as required by Technical Specifi-cation Section 3.5.C.3. The shutdown was terminated at approximately 1440 hrs.

on August 25, 1980 af ter Core Spray valve MD 1400-24A was opened and electrically disabled.

Core Spray Valve MO 1400-24A was repaired, tested and declared operable at approximately 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br /> on August 27, 1980.

Cause & Corrective Action On August 25, 1980 mtintenance and operations personnel inspected Core Spray Valve MD 1490-24A and found it stuck in a partially open position. Attempts to manually open it were difficult therefore it was decided to electrically close it in an effort to release its bound state. This. closing action appeared to eliminate the restriction to valve movement. The valve was opened and electri-cally disabled until maintenance could verify its operation.

On August 27, 1980 maintenance personnel af ter lubricating the valve's stem verifie the electrical operation of the valve. Current readings taken before and after lubrication measured 17 and 9 amperes respectively. The torque switch trip setting of the valve's breaker is 10-12 amperes. The valve was satisfactorily timed, functionally tested, and declared operable at approximately 0955 hcurs the same day.

Maintenance, additionally, has recommended that the valve be scheduled for in-spection during the next refueling outage.

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