ML18152A847

LER 88-001-01:on 880127,containment Isolation Valves TV-SS-201A & TV-SS-201B Inoperable Due to Leakage.Cause of Leakage Not Determined.Failure Analysis Will Be Performed During Next Refueling Outage.Leads lifted.W/880304 Ltr

ML18152A847
Person / Time
Site:	Surry
Issue date:	03/04/1988
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-001A, 88-1A, LER-88-001, LER-88-1, NUDOCS 8803140319
Download: ML18152A847 (4)

Text

Updated Report-~vious Report Dated 2/26/8~ POW 28-06-01-01

• NRC Form 366 U.S. NUCLEAR REGULATORY COMMISSION 19-831 APPROVED 0MB NO. 3150-0104 LICENSEE EVENT REPORT (LER) EXPIRES: 8/31 /88 FACILITY NAME 111 DOCKET NUMBER 121 I PAGE (31 Surry Power Station. Unit 2 o Is Io Io Io I 21 R I 1 1 loF ol :

TITLE (41 Improper Administrative Control of Containment Isolation Valves Due to Personnel Error '

EVENT DATE 151 LER NUMBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED 181 MONTH DAV YEAR VEAR It? SE~~~~~~AL ti~~~~~ MONTH DAV VEAR FACILITY NAMES DOCKET NUMBERISI oI1 2 I1 a a a la - o I o I ,

OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check on* or mor* of the follol'(ing} 111 I MODE (9)

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..K 20.4061*111 l(lv) 150.73lall2lliil 60.73lal(2l(vllll(BI 20.4051*111 IM 60.731a11Zlliiil 60.73la11Zllxl LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager RI n Ill l I r:; I 71 -1 ~ I 1 I i::i l 11 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 113)

CAUSE SYSTEM COMPONENT MANUFAC- MANUFAC-TURER TURER X 11 M I Jc:; I VI TI 1 17 In y I I I I I I I X JIM I IS I VI A.16 I o 19 y I I I I I I I SUPPLEMENTAL REPORT EXPECTED 114) MONTH DAY YEAR EXPECTED SUBMISSION DATE 1151 MYES (If v*s, compl*t* EXPECTED SUBMISSION DATE/

1 I1 1 I c; i:l I i:l' ABSTRACT (Limit to 1400 spscBS, i.B., approKimatBly fiftBen single-spec* typawrittBn lin*si 1161 On January 27, 1988, with Unit 2 at 100% power, it was determined at 1944 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.39692e-4 months <br /> that leakage through containment isolation valves*

TV-SS-201A and TV-SS-201B (pressurizer vapor space sample)

{EIIS-JM ISV} was greater than the ASME Section XI specification.

The valves were declared inoperable at that time-.- The valves were maintained closed and placed under administrative control at 2241 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.527005e-4 months <br /> by lifting a lead on TV-SS-201A (a solenoid operated valve) and by lifting a lead and isolating instrument air to Tv-ss*-201B (an air operated valve). However, on February 2, 1988 at 2225 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.466125e-4 months <br />, it was discovered that the wrong leads had been lifted for the trip valves, and that TV-SS-201A had not been. properly administratively controlled. The correct leads were lifted at 2324 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.84282e-4 months <br />, and the trip valves were verified to be properly controlled. Electricians have been instructed as to which are the proper leads to lift to disable these 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.

8803140319 880304 PDR ADOCK 05000281 S DCD NRC Form 366

Updated ReporiiPrevious Report Dated 2/2w8 POW 28-06-01-01 NRC Form 31111A U.S. NUCLEAR REGULATORY COMMISSION (9-83)

,) LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED 0MB NO. 3150-0104

. EXPIRES: 8/31 /88 FACILITY NAME 11 J DOCKET NUMBER (21 LER NUMBER (61 PAGE 131 Surry Power Station, Unit 2 o Is I o I o I o I 21 81 1 81 8 - 0 IO I 1 - 0 i1 0 I2 OF OI 3 TEXT /If,_. - * ,.,,,..,, ,_ <<ldlrJoMI NRC Fomr 3S4'1/ 1171 1.0 Description of the Event On January 27, 1988, with Unit 2 at 100% power, it was determined at 1944 hours0.0225 days <br />0.54 hours <br />0.00321 weeks <br />7.39692e-4 months <br /> that leakage through containment isolation valves TV-SS-201A and TV-SS-201B (pressurizer vapor space sample) {EIIS-JM ISV} was greater than the ASME Section XI specification. The valves were declared inoperabl~at that time.

Technical Specifications require administrative control of inoperable automatic containment isolation valves.

The valves were maintained closed and placed under administrative control at 2241 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.527005e-4 months <br /> by lifting a lead on TV-SS-201A (a solenoid operated valve) and by lifting a lead and isolating instrument air to TV-SS-201B (an air operated valve). Also, the manual isolation valve downstream of the penetration, 1-SS-113, was closed under administrative control.

However, on February 2, 1988 at 2225 hours0.0258 days <br />0.618 hours <br />0.00368 weeks <br />8.466125e-4 months <br />, it was discovered that the wrong leads had been lifted for the trip valves, and that TV-SS-201A had not been properly administratively controlled. (Since air was isolated to TV-SS-201B, it was effectively administratively controlled. The correct leads were lifted at 2324 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.84282e-4 months <br />, and the trip valves were verified to be properly controlled.

2.0 Safety Consequences and Implications The pressurizer vapor space 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 allowable leakage for operable containment isolation valves, the leakage was well within the total allowable leakage for containment integrity. Therefore, the health and safety of the public were not affected.

3.0 Cause Electrical maintenance personnel misinterpreted the electrical sketches and lifted the wrong leads when attempting to disable the trip valves.

The cause of the leakage has not been determined.

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

NAC FORM 386A (9-83)

• U.S.GPO: 1986*0*624*536/455

Updated Repo.Previous Report Dated 2/2-88 POW 28-06-01-01 NAC form 3MA U.S. NUCLEAR REGULATORY COMMISSION 19-831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION ' APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88 FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 PAGE (31 Surry Power Station, Unit 2 0 15 IO IO IO I 21 a I 1 81 8 - 0 IO I 1 - 011 0I 3 OF OI 3 TEXT (II mote - I,,.,,,-, u* <<ltHtioMI NRC Fann :m.4'111171 4.0 Immediate Corrective Action(s)

When it was discovered that the wrong leads had been lifted, the electricians lifted the proper leads and reconnected the leads that had been lifted incorrectly. Operations then 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.

6.0 Action(s) Taken to Prevent Recurrence Electricians have been instructed as to which are the proper leads to lift to disable these valves.

7.0 Similar Events None.

8.0 Manufacturer/Model Number TV-SS-201A Rock/86V-001 TV-SS-201B Asco/Kx2063803RF NRC FORM 366'"

(9-831

• U.S.GPO: 1988*0*824-538/455

e e VIRGINIA ELECTRIC AND POWER COMPANY Surry Power Station P. 0. Box 316 Surry, Virginia 23883 Karch 4, 1988 U.S. Nuclear Regulatory Commission Serial No.: 88-00lA 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 updated Licensee Event Report for Surry Unit 2.

REPORT NUMBER 88-001-01 This repo~t 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