ML18152A775

LER 88-002-00:on 880202,containment Isolation Valves Declared Inoperable Due to Leakage in Excess of Spec Value. Cause Not Determined.Valves Will Be Replaced/Repaired Based Upon Failure Analysis results.W/880303 Ltr

ML18152A775
Person / Time
Site:	Surry
Issue date:	03/03/1988
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-004, 88-4, LER-88-002-02, LER-88-2-2, NUDOCS 8803090302
Download: ML18152A775 (4)

Text

POW 28-06-01-01 NRC For~ 366 U.S. NUCLEAR REGULATORY COMMISSION (9-83)

APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER)

FACILITY NAME (1) OOCKET NUMBER (2) PAGE 131 TITLE (4)

Surry-*Power *station, .Unit 2 Io 1s I o-io*pi'12(8 (l 1 loi= oI 3 Inoperable Containment Isolation Valves Due To Excessive Leakage EVENT'DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR tit SE~~~~~~AI. t) ~G~~~~ MONTH DAY YEAR FACI I.ITV NAMES DOCKET NUMBER(S)

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• 2 o 12. 8 .8 a Ia - o I o I 2 - oI o oI3 oI 3 s I s o* 1 s10 ,o 1 0 1* 1 1 THIS REPORT IS SUBMITTED* PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check one or more of the folloV(ing/ (11)

OPERATING .

MODE (9)

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- 73.71(bl POWER Lf~TL 20.406(*1(1)(11 60.36(cl(1)

- 50.73(al(21(v) 73.71(c) 20.406(al(11(11) 50.38(cl(2) 60.73(al(21(vli) OTHER (Specify in Abstract

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• LICENSEE CONTACT FOR THIS LER (121 NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager 8 I OI 4 31 5 I 7 I -13 11 I 814 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 MANUFAC- MANUFAC-CAUSE SYSTEM COMPONENT TURER TURER X J I r11l I IS IV I VI O 13 10 y I I I I I I I 1

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SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION

""x1 YES (If ves, comp/et* EXPECTED SUBMISSION DATE/

DATE (151 1 1 11 1s a1a ABSTRACT /Limit to 1400 spacos, i.e., epproximotelv fifteon sing/e-spac* rypowritton lines/ (161 On February 2, 1988, Unit 2 was at 100% power. At 1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br />, it was determined that the individual valve leakage through the reactor coolant cold leg sample isolation valves {EIIS-JM ISV}

(TV-SS-202A and TV-SS-202B) was greater than the ASME Section XI specification. They were then declared inoperable. Technical Specifications require administrative control for inoperable automatic containment isolation valves.

The valves were maintained closed and placed under administrative control at 2244 hours0.026 days <br />0.623 hours <br />0.00371 weeks <br />8.53842e-4 months <br /> by lifting a lead on both solenoid valves.

The cause of the leakage has not been determined. A failure analysis will be performed during the next refueling outage.

The valves will be repaired or replaced as necessary based upon the results of the failure analysis.

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NRC Form 386

• POW 28-06-01-01 NRC Form 31141A e U.S. NUCLEAR REGULATORY COMMISSION (9-831 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /BB FACILITY NAME .(1 I D~KET NUMBER (21 LER NUMBER (61 PAGE (31

_ Surry Power Station, Unit_2 o 1s1010101.21.a11 818 - 01012 010 012 OF ol3 TEXT /If mot9 -  ;. , . , , . - . u* -iriaM/ NRC Fann lliliA'*J (17) 1.0. Description of the Event On February 2, 1988,* Unit 2 was at 100% power. At

.1715 hours0.0198 days <br />0.476 hours <br />0.00284 weeks <br />6.525575e-4 months <br />,. it was determined.that the individual valve leakage through the reactor c6olant cold leg sample isolation valves {EIIS-JM ISV} (TV-SS-202A and TV-SS-202B) was greater than the ASME Section XI specification. They were the~ declared ino~erable.

Technical Specifications require administrative control.

for inoperable automatic containment isolation valves.

The valves were maintained closed and placed under administrative control at 2244 hours0.026 days <br />0.623 hours <br />0.00371 weeks <br />8.53842e-4 months <br /> by lifting. a lead on both solenoid valves.

2.0 Safety Consequences and Implications The cold leg sample system trip valves provide containment isolation in the event of a loss of coolant accident. Although the leakage through the trip valves exceeded the ASME Section XI specification, the leak~ge was well within the. total allowable leakage for containment integrity. Therefore,. the health and

. safety of the public were not affected.

3.0 Cause The cause of the leakage has not been determined.

A failure analysis will be performed during the next refueling outage.

4.0 Immediate Corrective Action(s)

The electricians lifted a lead on both solenoid valves. Operators verified that the trip valves could not be opened.

5.0 Additional Corrective Action(s)

The valves will be repaired or replaced as necessary based upon the results of the failure analysis.

NRC FOAM 366A 19-831

• U.S.GPO: 1986*0*624-536/455

POW 28-06-01-01 NRC Form 368A (9-83) e u.s.- NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED 0MB NO. 3150-0104

\ EXPIRES: 8131/811 FACILITY* NAME. (1 J DOCKET NUMBER (2)- LER NUMBER (61 PAGE (3)

• YEAR ::'.:::::::: SEQUENTIAL ::::::::::: REVISION

NUMBER '.*'.*

*:*:* NUMBER Surry Power Station, Unit 2 0 1s IO IO I O I 218 I 1 81 8 - 0 IO I 2 - 0 IO OI 3 OF OI 3 TEXT / l f - - i a required, u*--NRC Form366A'*I 1171 6.0 Action(s) Taken to Prevent Recurrence None 7.0 Similar Events LER 88-001 8.0 Manufacturer/Model Number TV-SS-202A, B Valcor/V526-5683-19 NRC FOAM 366A 19-831

• U.S.GPO: 1986*0*824*538/455

VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P. 0. Box 316 Surry, Virginia 23883 March 3, 1988 U.S. Nuclear Regulatory Commission Serial No.: 88-004 Document Control Desk Docket No.: 50-281 016 Phillips Building Licensee No;.: DPR-37 Washington, D.C. 20555 Gentlemen:

Pursuant to Surry Power Station Technical Specifications,*Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Unit 2.

REPORT NUMBER 88-002-00 This report has been reviewed by the Station Nuclear Safety and Operating Committee and will be reviewed by Safety. Evaluation and Control.

Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administrator Suite 2900 101 Marietta Street, NW Atlanta, Georgia 30323

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