ML20004E744

Updated LER 81-013/03L-1:on 810415,determined Containment Isolation Valves Not Tested in Required Manner.Seven of Eight Valves Functioning as Designed.Eighth Valve Tested & Shown Operable.Test Undergoing Revision

ML20004E744
Person / Time
Site:	Robinson
Issue date:	06/09/1981
From:	Gilman F CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20004E741	List: ML20004E740 ML20004E744
References
LER-81-013-03L, LER-81-13-3L, NUDOCS 8106150151
Download: ML20004E744 (2)

Text

, .. x s. - - - . .: . ..x U.S. NUCLEAR REGULATORY COMMISSION NBC FORM 36G Update Report - Previous Report Date 5/15/81

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• LICENSEE EVENT REPORT.

CONTROL DLOCK: l l l l } l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo l1l l Sl Cl 11l Bl Rl 2l@l0 l0 l- l0 l0 l0 l0 l0 l - l 0 l 2b 0 l@l 2ti 4 l LICENSE 1 l T)PE1 l JD 1 l l

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$n$!Il@l0l5l0l0 l0 l2 l6 l 1 }@[ 014 l 1 l 5 l 8 l 1 l@l 0 l 6 l 0 l 9 l 8 l 1 CO Gl DOCKET NUMBE H 68 63 EVENT D/sTE 74 7b HEPORT DATE 80 EVENT DESCRIPTION AND PDOBABLE CONSEQUENCES h

! 10121lon April 15. 1981. durinn a review of Periodic Test (PT) nrocedures_ ft unn datorminod.l I

lo13]lthat six containment isolation valves were not beinn tested in a manner which l o l41 ] fully satisfies Technical Specification 4.4.2.a. On itav 10,_1_981. two additicnal l

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l I lol5) [ valves were identified . Procedures developed to satisfy these requirements l

o o [ precluded the verification of operation of one contact in eacjLvalve control 1

Q QJ l circuit. This event is reportable purnuar.t to Technical Specification 6.9.2.b.3.

I Lo I s I I 7 8 9 COMPONENT CODE SB DE SU E C DE CODE $ BCO E ITTol I si Fj@ yh l Z j@ lV l A lL lV lE lX lh lX lh lXlh 12 13 18 '9 20 7 8 9 10 11. HEVISION SEGUENTIAL oCCUHRENCE REPORT CODE TYPE NO.

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i o lRecent operating experience has verified that seven of the eight valves were func-In order to I i i ltioning as designed. The eighth valve was tested and shown operable.

ji,7, l prevent recurrence, a PT is being revised to include provisions for fully testing l t

I g , g 3 g l the valves. This revision will be completed prior to the next scheduled performance

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i114I Iof this PT (refueling outage). 80 7 8 9 DISCO H DISCOVEHY DESCRIPTION STA S  % POWER oTHER STATUS NA l W @l Review of Periodic Tests l l1 l s] l El@ l 0 l 9 l 5 l@l ACTIVITY CO TENT LOCATION OF RELEASE RELCASED OF RELE Af E AMOUNT OF ACTIVITY NA l l1 lGl 7 8 9 d h W@l to 11 NA 44 l l 45 80 PEntONNEL E XPOSURES NUMDFR TYPE DESCRIPTION l

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J h] NA PERSONNEL INJUHIES NUMaE n oESCRIP e TON @ l W l0l0l0l@l 7 8 9 11 12 NA 80 LOSS of Ott DAMAGE TO FACILITY TYPE DE SCHIPilON NA l 7

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SUPPLEMENTAL 7NFORMATION

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FOR LICENSEE EVENT REPORT 81-013, REV. 1

1. Cause Description and Analysis On April 15, 1981, during a review of the H. B. Robinson isolation Periodic Test (PY) procedures, it was determined that six containment valves were not being tested in a manner which fully satisfied Tech-nical Specification 4.4.2.a. OnRMS-1, May 10, 1981, two additional valves were id entified . 'lhese valves are: These RMS-2, valves RMS-3, RMS-4, CVC-204A, are tested for opcrability CVC-?94B, PCV-1716 and SI-855.

under the ISI Program. The containment isolation function is verified by a number of periodic tests; however, these test procedures do not As a require the above valves to be open prior to conducting the tests.

result a contact in each valve control circuit which is required to open to initiate the auto closure upon an isolation signal is not tested by these procedures. Recent operating events have serified that each of these valves will close on the isolation signal, except SI-855 which was closed during the events. SI-855 is the containment isolation valve for the nitrogen supply to the SI accumulators. This valve which is operated from the control room is normally closed. In addition, there is one remotely operated valve downstream of SI-855 in each accumulator leg and manual valves upstream of the SI-855 valve which are also normally closed.

These valves are manually operated as necessary to add nitrogen to the SI Accumulators. These valves are only opened for very short time periods Additionally, (2-5 minutes per week) and under direct operator control.

the safeguard position for SI-855 as well as the other seven containment isolation valves above is procedurally verified by a control room status Therefore, there has been no undue risk panel following initiation of SI.This event is reportable pursuant to to the public from this event.

Technical Specification 6.9.2.b.3.

2.. Corrective Action these Recent plant conditions and operating events have required that "A" isola tion signal I containment isolation valves respond to the Phase which has verified the operability of all the valves except SI-855 (normally closed). SI-855 was tested on June 5,1981, and verified operable. Therefore, no additional immediate actions are necessary.

3. Corrective Action To Prevent Recurrence A periodic test (PT-2.6) is being revised to include the above valves in the pretest valve lineup to insure ' full compliance with the surveil-lance requirements. This revision will be completed prior to the next refueling outage when the test is scheduled to be performed again.

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