ML20024D553

LER 83-044/01T-0:on 830711,2-inch Manual Isolation Valve Opened to Provide Svc Air to Support Work in Containment. Caused by Personnel Ignorance of Tech Specs.Personnel disciplined.W/830727 Ltr

ML20024D553
Person / Time
Site:	San Onofre
Issue date:	07/27/1983
From:	Ray H SOUTHERN CALIFORNIA EDISON CO.
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
LER-83-044-01T-01, LER-83-44-1T-1, NUDOCS 8308050233
Download: ML20024D553 (4)

Text

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EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l o l2 l lWith Unit 3 in Mode 4. at 2200 MU-055. a 2" manual isolation valve. was opened I o l3 j lto supply service air to support work inside containment, contrary to the [

lo p l l requirement of Table 3.6-1 of the Technical Specifications. The error was [

lo ls l[ recognized at 1710 on 7/12/83 during routine surveillance of containment l lo le l lisolation valve position indication in the Control Room. Within 45 minutes I lo l 7 l lMU-055 was returned to its closed and locked position. Public health and I lo l8 l lsafetv wara nnt affected hv this event. I

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l9 l9 l 9lu u u .. n .. .. u CAUSE DESCRIPTION AND CORF'cCTIVE ACTIONS h lilo llInvestigation of the event has determined that direction was given to open l lilillMU-055 without recognition that the provision in Table 3.6-1 of the Technical l lil2 l l Specifications, which allows opening certain designated containment isolation [

t 3 Ivalves on an intermittent basis, does not include this valve. Station l

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ATTACHMENT TO LER 83-044 SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT NO. 3, DOCKET NO. 50-362 SUPPLEMENTAL INFORMATION FOR CAUSE DESCRIPTION AND CORRECTIVE ACTION:

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As corrective action, the two licensed control room operators involved were disciplined for failure to follow established administrative controls for abnormal valve lineups and positioning of locked valves. Other operations personnel who were involved with shift reliefs during this 19-hour period have been warned about failure to properly identify the abnormal position of this containment isolation valve. Also, each station operating crew has been briefed in detail on the importance of verbatim compliance with Station procedures and

> administrative controls which exist to preclude incidents of this nature.

In addition, commencement of an upgrading of both classroom and on-the-job training in administrative controls, will be implemented. Items such as compliance with procedures, abnormal valve alignments, control of containment valves, and Control Room command structure will be addressed to increase the effectiveness of administrative controls.

Administrative controls are under evaluation for locked valves in non-safety-related systems, such as service air, which include valves that perform a safety-related function (e.g.,

containment isolation). If the need for procedure revision is identified as a result of this evaluation, these revisions will

( be made, j

l Lastly, a revision of the Technical Specifications to permit intermittent opening of MU-055 under administrative control is currently being developed. These actions are considered adequate to prevent recurrence of this event.

- --- . - - - . _ _ ~ . . . . . .

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. . ( P rT(Po Southern California Edison Company A!!' , WE S AN ONOFRE NUCLE AR GENER ATING ST ATION  ! .'

• 3 P.O. e O x t a s f, s AN C LEMENT E. C ALIFORNI A 92672 /

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f U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region V 1450 Maria Lane, Suite 210

Walnut Creek, California 94596-5368

- Attention: Mr. J. B. Martin, Regional Administrator i

Dear Sir:

i

Subject:

Docket No. 50-362 14-Day Follow-Up Report l Licensee Event Report No.83-044 l

San Onofre Nuclear Generating Station, Unit 3 i

Reference:

Letter, H.B. Ray (SCE) to J.B. Martin (NRC),

dated July 13, 1983 l

The referenced letter provided you with confirnation of our prompt notification, pursuant to Section 6.9.1.12.b of Appendix A, Technical Spacifications to Facility Operating License NPF-15 for San Onofre Unit 3, of a reportable occurrence involving the Containment Isolation System.

l Pursuant to Section 6.9.1.12.b, this submittal provides the required 14-day follow-up report and a copy of Licensee Event Report (LER) No.83-044 to address this event.

If there are any questions regarding this event, please contact me.

S i ncer ely, i

Enclosure:

LER 83-044 i

f I. (

l IEMA

r; Mr. J.B. Martin cc: A.E. Chaffee (USNRC Resident Inspector, Units 2 and 3)

J.P. Stewart (USNRC Resident Inspector, Units 2 and 3)

U.S. Nuclear Regulatory Commission 7

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Division of Technical Information and Document Control Institute of Nuclear Power Operations (INPO) r I

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