ML19305E122

Revised LER 79-098/03L-1:on 791004,during Performance of Component Cooling Water Monthly Test,Decay Heat Cooler 1 Component Cooling Outlet Valve CC1467 Would Not Operate. Caused by Valve Linkage Slippage.Linkage Realigned

ML19305E122
Person / Time
Site:	Davis Besse
Issue date:	10/30/1979
From:	Deakyne K TOLEDO EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19305E119	List: ML19305E118 ML19305E122
References
LER-79-098-03L, LER-79-98-3L, NUDOCS 8004220772
Download: ML19305E122 (2)

Text

NRC FORM 36G U. S. NUCLEAR REGULATORY COMMISSION 4 77)

. LICENSEE EVENT REPORT CONTROL BLOCK: l 1

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EVENT DESCRIPTION AND PHOBABLE CONSEQUENCES h 8 lOn October 4 1979 at 1007 hours0.0117 days <br />0.28 hours <br />0.00167 weeks <br />3.831635e-4 months <br /> during the performance of Component Cooling Water l o 3 l Monthly Test, ST 5074.01, the Decay Heat Cooler 1 Component Cooling Outlet Valve I t o l4 l l CC1467 would not operate. This rendered Decay Heat and Low Pressure Injection Train l I'oT o 1 11 inoperable placing the station in the action statement of Technical Specification I oe 13.5.2. This required the inoperable train be made operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. There 1 o 7 I was no danger to the health and safety of the public or station personnel. Redundant I i o Is I l Train 2 was available. (NP-33-79-114) 1 7 8 9 80 E CODE SUBC E COMPONENT CODE SUSC DE S E 1[@3 8 9l Sl Fl@ {@ Q@ l Vl Al Ll Vl 0l Pl@ W@ W @

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41 l y [@ lA l g lH l0 l3 l5 l g 40 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l1 l 0 l l The inoperability of CC1467 was due to slippage of the valve linkage. The slippage l LLL1_J l was due to a design deficiency which allows vibrations to loosen the bolt that retains l l

y I the two linkage arms. The linkage was realigned, calibrated and successfully tested 1[E l under ST 5074.01 on 10/4/79. On 12/10/79 the design deficiency was corrected via l

[E l the implementation of Facility Change Request 79-347. l 8 9 80 ST S  % POWE R OTHER STATUS IS O RY DISCOVERY DESCRIPTION

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o ISSUSELNA81 i 111111-lll11111 8 9 to 69 60 E DVR 79-145 Kenneth Deakyne NAME OF PREPARER 8 004220 7((h 68419-259-5000, E'xt. 231g

TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-79-114 DATE OF EVENT: October 4, 1979 FACILITY: Daivs-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Decay Heat Cooler 1 Component Cooling Outlet Valve CC1467 would not operate Conditions Prior to occurrence: The unit was in Mode 1, with Power (MWT) = 2770, and Load (Gross MWE) = 920.

Description of Occurrence: On October 4,1979 at 1007 hours0.0117 days <br />0.28 hours <br />0.00167 weeks <br />3.831635e-4 months <br /> during the performance of ST 5074.01, Component Cooling Water Monthly, CC1467 would not move. Component Cooling Pump 1 was shut off. Additional attempts to mov e the valve were unsuccessful.

The operator suspended the test and CC1467 was declared inoperable which rendered Decay Heat and Low Pressure Injection Train 1 inoperable. This placed the unit in the Action Statement of Technical Specification 3.5.2 which requires the inoperable train be made operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Designation of Apparent Cause of 0:currence: The improper operation of valve CC1467 was attributed to slippage of the valve linkage. This was caused by a design defi-ciency which allowed vibrations to loosen the bolt that retains the two linkage arms together.

Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. An inspection of the Decay Heat / Low Pressure Injection Train 2 was performed to assure its availability.

Corrective Action: Under Maintenance Work Order IC-455-79, the valve linkage was realigned and calibrated. The applicable portions of ST 5074.01, Component Cooling Water Monthly Surveillance Test and ST 5074.02, Component Cooling Water Syr. tem Refuel-ing Test were performed to verify operability. The valve and train 1 were declared 3 operabic at 1415 hourn on October 4, 1979.

Facility Change Request 79-347 was implemented on December 10, 1979 to prevent vibra-tions from loosening the retaining bolts on CC1467 and CC1469. This Facility Change Rtquest is identical to Facility Change Request 79-151 which resolved the vibration problems on Service Water Valves SW1429,1434 and 142.4.

Failure Data: There have been three previously reported occurrences with valves of this type of actuators. They were reported in Licensee Event Reports NP-33-78-120, NP-33-78-147 and NP-33-79-74.

l l LER #79-098 -

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