ML18152B156

LER 88-012-00:on 880418,Tech Spec 1.0.H.5 Violated.Caused by Discovery of Valve 1-RS-11 Held in Open Position by Counter Weight Due to Personnel Error.Valves Inspected & Verified to Be in Closed Position & 1-RS-11 disassembled.W/880517 Ltr

ML18152B156
Person / Time
Site:	Surry
Issue date:	05/17/1988
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-020, 88-20, LER-88-012-01, LER-88-12-1, NUDOCS 8805310041
Download: ML18152B156 (4)

Text

NRC l'orm 366 (9~83) e

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• . ' '*:*w * *. LICENSEE EVENT REPORT (LER) e .. -.*. -:-.,_.: POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3160-0104 EXPIRES: 8/31/88 FACILITY NAME (11 'DOCKET NUMBER 121 I PAGE (31 Surry Power Station, Unit 1 o I s I o I o I o 1 2 I 8 10 1 I oF n I 1 TITLE (41 Inoperable Containment Isolation Valve Due To Pel'.'sonnel Error EVENT DATE (51 LER NUMBER 161 REPORT DATE (71 OTHER FACILITIES INVOLVED 181 MONTH DAY YEAR YEAR tt ft MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI.

o I 4 1 J a a a a I a -ol 1 I 2 -o I o o I s 1 b s Is THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Ch6Ck ona or more of tho fol/o-.ying}

1111 OPERATING MODE 191 N 20.402lbl t----.......,....--'--+--1 POWER I 20.4051*1111111

-20.405lcl 50,7311112llivl 73.71lbl -,__ 50.3lllcll1 l 50.73lill2lM 73.71 lcl LEVEL --..__ ..__ 1101 n I n I n zo.4051111111111 50.361cll2) 50.731111211vill 0TH ER (Spaclfy in Abstract ..__ Inlow and In Taxt, NRC Form --tall=:::::::::::

x.. 60.73111121111 60.73(11121(vlllllAI 366A} -50.7311112lliil 50.7311l12llv111IIB)

--50.731111211illl 60.7311112llxl LICENSEE CONTACT FOR THIS LER 1121 NAME TELEPHONE NUMBER AREA CODE D. L. Benson, Station Manager COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 1131 CAUSE SYSTEM COMPONENT TURER R~~o~~:giE i!i!::ii!i!iii!:!i!i!i!i!i!i!i!:!i!:ii!iii!i!i!i!i!:

CAUSE SYSTEM COMPONENT MANUFAC. TURER I I I I I I I I I I I I I I I I I I I I I I I I I I I I SUPPLEMENTAL REPORT EXPECTED 1141 MONTH DAY YEAR . I YES /If yes, complata EXPECTED SUBMISSION OATE} NO EXPECTED SUBMISSION DATE 1161 I I I ABSTRACT /Limit to 1400 spacas, I.a., approximeta/y';fiftaan ,ingla-spaca rypawrlttan

/in**/ 1181 NRC Form 388 ,a.e,, On April 18, 1988 at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />, with Unit 1 at cold shutdown, the "As Found" leakage test (PT 16.4) revealed that 1-RS-11 {EIIS-BE-ISV}

was held in the open position by its counter weight. As it could not be determined when this condition originated, it is being reported as contrary to Technical Specification 1.0.H.5 which requires that all automatic containment isolation valves are operable or are locked closed under administrative control. An inspection of 1-RS-11 revealed that the valve external counterweight was lifted to past 90 degrees from the horizontal which held the check valve open. The counterweight was able to pass the vertical position because there was movement between the lever arm and hinge pin connection.

The other three (3) valves of similar design in the Unit 1 containment were inspected and verified to be in the closed position.

Similar valves in the Unit 2 containment were visually verified to be closed as required.

1-RS-11 was disassembled.

No internal damage was.observed which could have caused the valve to open or remain open. Eight (8) valves of this design in the Unit 1 and 2 containments will be modified to reduce the counterweight arm angle to zero degrees from the horizontal with the valve closed to prevent the valve from being capable of remaining in the open position.

ri{_. c 7 t? 8805310041 880517 ,,-I-~----PDR ADOCK 05000280 'f ! S PDR NRC Form 3811A (9-831 FACILITY NAME (11 . . .,'-"* ... *:.* . * ., .. --t..*., * .. ** . . **~ ...... ':".: .. .. , ....... e e LICENSEE EVENT REPORT (LERI TEXT CONTINUATION DOCKET NUMBER (21 POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88 LER NUMBER (61 PAGE (31 Surry Power Station, Unit 1 o I 5 Io Io Io I 2 Is 1* o sl 8 -o I 1 I 2 -n In n b OF n h TEXT /If --* ,equlted, u. eddltioMI NRC Fonn .-.i '1J 1171 NRC FORM 388A (9-831 1.0 Description of the Event On April 18, 1988 at 1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />, with Unit 1 at cold shutdown, the "As Found" leakage test (PT 16.4) revealed that 1-RS-11 (a weighted check valve in the "B 1 outside recirculation spray pump discharge)

{EIIS-BE-ISV}

was held in the open position by its counter weight. As it could not be determined when this condition originated, it is being reported as contrary to Technical Specification 1.0.H.5 which requires that all automatic containment isolation valves are operable or are locked closed under administrative control. 2.0 Safety Consequences and Implications The Outside Recirculation Spray (ORS) discharge check valves provide a passive, inside containment, isolation function.

The ORS pump discharge_motor operated valves outside of containment are normally open. The piping between the ORS pump discharge and suction valves, which includes*the ORS pump, was air tested for leakage. The result was less than the allowable Appendix J type B & c leakage. During normal operation, the containment operates in a atmospheric condition and any leakage through the check valve would be into containment.

During a Loss Of Coolant Accident (LOCA), the containment spray pumps automat1cally start at a containment pressure of 8.3 psig to reduce the containment pressure t6 atmospheric.

The ORS pumps start five minutes later to assist in the depressurization and at this time the ORS system is filled with pressurized water. 3.0 Cause An inspection of 1-RS-11 revealed that the.valve external counterweight was lifted past 90 degrees from the horizontal which heid the check valve open. The counterweight was able to pass the vertical position because there was movement between the lever arm and hinge pin connection.

The weight was originally positioned 30 degrees above the horizontal when the valve was closed and 85 degrees above the horizontal when the valve was open. The aforementioned movement permitted the weight to move past 90 degrees above the horizontal.

An engineering evaluation determined that it would be an extremely remote probability for the

• U.S.GPO: 1986*0-824-538/455

'* NRC Farm 31111A 19-831 FACILITY NAME 111 --: e e LICENSEE EVENT REPORT (LERI TEXT CONTINUATION DOCKET NUMBER 121 VEAR --. . ._* *, :.~-*.: :/ .; ' .. :' :* ~.:* ** .. POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMS NO. 3150-0104 EXPIRES: 8/31 /88 LER NUMBER 161 PAGE (31 Surrv Power Station. Unit 1 o 1s Io Io Io I 2 IR I n A R -n I 1 I 1 -n In n h OF n I '.l TEXT,,, __ a __ . u* -NRC Fonn.11111A'*I 1171 NRC FORM 388A 19-831 valve to have been opened by flow through the system. Although it was not possible to co~firm, it was surmised that the valve was opened by a worker in the area during an outage while performing maintenance in the vicinity.

This could have occurred during the current outage. 4.0 Immediate Corrective Action(s)

The other three (3)"valves of similar design in the Unit 1 containment were inspected .and verified to be in the closed position.

5.0 Adcitional Corrective Action(s)

Similar valves in the Unit 2 containment recirculation spray and containment spray systems were visually verified to be closed as required.

1-RS-11 was disassembled.

No internal damage was observed which could have caused the valve to open or remain open. 6.0 Action(s)

Taken to Prevent Recurrence Eight (8) valves of this design in the Unit 1 and 2 containment spray and recirculation spray systems will be modified to reduce the counterweight arm angle to zero degrees from the horizontal with the valve closed to prevent the valve from being capable of remaining in the open position.

With the valve open, the counterweight will be at an angle of 55 degrees from the horizontal.

7.0 Similar Events None. 8.0 Manufacturer/Model Number (1-RS-11)

Schutte & Koerting/828

• U.S.GPO: 1988'.0-824*538/455

.. e May 17, 1988 U.S. Nuclear Regulatory Commission Docmnent Control Desk 016 Phillips Building Washington, D.C. 20555 Gentlemen::

e VIRGINIA ELECTRIC ANO POWER COMPANY Surry Power Station P. 0. lox 315 Surry, Virginia 23883 Serial No.: Docket No.: Licensee No.: 88-020 50-280 DPR-32 Pursuant to Surry Power Station Technical Specifications, Virginia Electric and Power Company hereby subaits the following Licensee Event Report for Surry Unit 1. REPORT NUMBER 88-012-00 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