05000266/LER-1981-003, Forwards LER 81-003/01T-0

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Forwards LER 81-003/01T-0
ML20009A860
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 06/04/1981
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20009A855 List:
References
NUDOCS 8107140368
Download: ML20009A860 (1)
v • d • e


LER-1981-003, Forwards LER 81-003/01T-0
Event date:
Report date:
2661981003R00 - NRC Website
v • d • e

text

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Wisconsin Electnc eom couem 231 W. MICHIGAN, P.O. BOX 2046. MILWAUKEE, WI 53201 June 4, 1981 Mr. James G. Keppler, Regional Director Office of Inspection and Enforcement, Region III U.

S. NUCLEAR REGULATORY COMMISSION 799 Roosevelt Road Glen Ellyn, Illinois 60137

Dear Mr. Keppler:

DOCKET NO. 50-301 POINT BEACH NUCLEAR PLANT, UNIT 2 LICENSEE EVENT REPORT NO. 81-003/0lT-0 Enclosed is Licensee Event Report No. 81-003/0lT-0 (a 14-day followup report) and an attachment which provides a description of an event reportable in accordance with Technical Specification 15.6.9.2.A.2, " Operation of the unit or affected systems when any parameter or operation subject to a limiting condition for operation is less conservative than the least conservative aspect of the limiting condition for operation established in the Technical Specification."

Very truly yours, bADJ

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C. W. Fay, Director Nuclear Power Department Enclosure Copy to NRC Resident Inspector 3107140368 810702 PDR ADOCK 05000266 S

PDR JUL.

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8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h lDuring normal operations at 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br />, on May 26, 1981, attempts to l

O 2 i o l3 l l cycle 2A steam generator blowdown sample isolation valve, 2CV-2 0 8 3, we re l iol4ll unsuccessful.

Failure of 2CV-2083 to close when actuated is a technicall l violation of containment integrity as defined in T.

S.

15.1.d.

This l

o 3 i o is ; l occurrence is reportable in accordance with T. S.

15.6.9.2.A.2 as l

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33 34 35 36 Ji 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS i O l Failure of 2CV-2083 to close upon actuation was due to excessive stem tol li ii ; l packing friction resulting from dried (

pa ck in g.

Followina discoverv I lof the prob'lem the packing gland was g y ed and the valve stem was I

i,l3; l lubricated.

The valve was tested satis f t2s vrily and returned to I

i, i, i loperation at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on May 26, 1981.

At no time was the public l

safe ty endangered.

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DISCOVERY DESCRIPTION

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Fay PHONE:

NAME OF PREPARER

P ATTACHPENT TO LICENSEE EVENT REPORT NO. 81-003/OlT-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 2 Docket No. 50-301 At 1250 hours0.0145 days <br />0.347 hours <br />0.00207 weeks <br />4.75625e-4 months <br /> on May 26, 1981, during normal power operation, Unit 2, "A" steam generator blowdown sample.

valve, 2CV-2083, failed to close upon a manual remote signal from the control operator.

The attempt to close 2CV-2083 was at the request of Chemistry Group personnel to stroke the valve.

Valve 2CV-2083 is an air-operated containment isolation valve which is required to close automatically upon actuation of containment isolation.

Inoperability of 2CV-20 83 is a technical violation of containment integrity as defined in Technical Specification 15.1.d.

This occurrence is reportable in accordance with Technical Specification 15.6.9.2. A.2 as operating in a less conservative manner than the limiting condition of operation specified in Technical Specification

15. 3. 6. A. a.

After an immediate investigation it was found that 2CV-2083 failed to close due to excessive stem to packing friction resulting from dried out packing.

The packing was adjusted and the valve stem lubricated.

Followirg a satis-factory operational test on 2CV-2083, it was. returned to an operable status at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br /> on May 26, 1981.

The automatic containment isolation function of 2CV-20 83 was installed, in accordance with NUREG-0578, during the Unit 2 refueling outage ending on May 22, 1981.

The last operability test of 2CV-2083 was conducted on May 13, 19 81, with satisfactory results.

If containment isolation was initiated while 2CV-2083 was inoperable, isolation could be provided via accessible mar.ual valves downstream of 2CV-208 3.

At no time was the public safety endange red.

The nameplate data for 2CV-2083 is as follows:

Manufacturer:

Copes Vulcan Body Size:

3/4" Pressure Rating:

600 psig Type:

D-100-60 9

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