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| {{#Wiki_filter:NRC l'orm 366 (9~83) e | | {{#Wiki_filter:* _,_:..,,'* *. ' '*:*w * *. ..-.*. -:-.,_.: |
| * _,_:..,,'* | | NRC l'orm 366 e e POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSION (9~83) |
| *. ' '*:*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. | | APPROVED 0MB NO. 3160-0104 EXPIRES: 8/31/88 LICENSEE EVENT REPORT (LER) |
| 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}
| | FACILITY NAME (11 DOCKET NUMBER 121 I PAGE (31 Surry Power Station, Unit 1 o I s I o I o I o 12 I 8 10 I 1 oF nI 1 TITLE (41 Inoperable Containment Isolation Valve Due To Pel'.'sonnel ' |
| 1111 OPERATING MODE 191 N 20.402lbl t----.......,....--'--+--1 POWER I 20.4051*1111111 | | Error EVENT DATE (51 LER NUMBER 161 REPORT DATE (71 OTHER FACILITIES INVOLVED 181 MONTH DAY YEAR YEAR tt SE~~~~~~AL ft ~E~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI. |
| -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=::::::::::: | | oI4 1J a a a a Ia - ol 1 I 2 - o I o o I s 1 b s Is OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Ch6Ck ona or more of tho fol/o-.ying} 1111 MODE 191 N In t----.......,....--'--+--1 20.402lbl |
| x.. 60.73111121111 60.73(11121(vlllllAI 366A} -50.7311112lliil 50.7311l12llv111IIB)
| | - 20.405lcl |
| --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!: | | - 50,7311112llivl |
| 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 | | ,__ 73.71lbl POWER LEVEL - |
| /in**/ 1181 NRC Form 388 ,a.e,, On April 18, 1988 at 1145 hours, with Unit 1 at cold shutdown, the "As Found" leakage test (PT 16.4) revealed that 1-RS-11 {EIIS-BE-ISV} | | 20.4051*1111111 |
| 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. | | - 50.3lllcll1 l ..__ 50.73lill2lM ..__ 73.71 lcl 1101 In In zo.4051111111111 |
| The other three (3) valves of similar design in the Unit 1 containment were inspected and verified to be in the closed position. | | -x.. 50.361cll2) |
| Similar valves in the Unit 2 containment were visually verified to be closed as required. | | - 50.731111211vill ..__ 0TH ER (Spaclfy in Abstract tall=::::::::::: |
| 1-RS-11 was disassembled. | | Inlow and In Taxt, NRC Form 60.73111121111 |
| 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. | | - 60.73(11121(vlllllAI 366A} |
| 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 hours, 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) | | - 50.7311112lliil 50.731111211illl |
| {EIIS-BE-ISV} | | - 50.7311l12llv111IIB) 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 MANUFAC- MANUFAC. |
| 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. | | CAUSE SYSTEM COMPONENT TURER 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 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 EXPECTED |
| 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. | | SUBMISSION |
| 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. | | .I YES /If yes, complata EXPECTED SUBMISSION OATE} NO DATE 1161 I I I ABSTRACT /Limit to 1400 spacas, I.a., approximeta/y';fiftaan ,ingla-spaca rypawrlttan /in**/ 1181 On April 18, 1988 at 1145 hours, with Unit 1 at cold shutdown, the "As Found" leakage test (PT 16.4) revealed that 1-RS-11 |
| 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. | | {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? |
| An engineering evaluation determined that it would be an extremely remote probability for the | | 8805310041 880517 ,,-I- ~---- |
| * U.S.GPO: 1986*0-824-538/455 | | PDR ADOCK 05000280 'f ! |
| '* 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.
| | NRC Form 388 S PDR |
| This could have occurred during the current outage. 4.0 Immediate Corrective Action(s) | | |
| | . . .,'-"* ... *:.* . * ., . . --t..*., *.. **. .**~..... .':".: .. .. ....... |
| | ~ , ~ |
| | e e POW 28-06-01 NRC Form 3811A U.S. NUCLEAR REGULATORY COMMISSION (9-831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88 FACILITY NAME (11 DOCKET NUMBER (21 LER NUMBER (61 PAGE (31 Surry Power Station, Unit 1 o I5 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 1.0 Description of the Event On April 18, 1988 at 1145 hours, 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 sub-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 sub-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 NRC FORM 388A (9-831 |
| | * U.S.GPO: 1986*0-824-538/455 |
| | |
| | --: |
| | -- . . ._* *, :.~- *.: :/ .; ' .. :' :* ~.:* **.. |
| | e e POW 28-06-01 NRC Farm 31111A U.S. NUCLEAR REGULATORY COMMISSION 19-831 |
| | '* LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED OMS NO. 3150-0104 EXPIRES: 8/31 /88 FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 PAGE (31 VEAR Surrv Power Station. Unit 1 o 1s Io Io Io I 2 IR I n A R - n I 1 I1 - n In n h OF n I '.l TEXT,,, _ _ a _ _. u* - N R C Fonn.11111A'*I 1171 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. | | 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) | | 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. | | 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. |
| 1-RS-11 was disassembled. | | 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. |
| No internal damage was observed which could have caused the valve to open or remain open. 6.0 Action(s) | | 7.0 Similar Events None. |
| 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. | | 8.0 Manufacturer/Model Number (1-RS-11) Schutte & Koerting/828 NRC FORM 388A 19-831 |
| With the valve open, the counterweight will be at an angle of 55 degrees from the horizontal. | | * U.S.GPO: 1988'.0-824*538/455 |
| 7.0 Similar Events None. 8.0 Manufacturer/Model Number (1-RS-11) | | |
| Schutte & Koerting/828 | | e e |
| * 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::
| | VIRGINIA ELECTRIC ANO POWER COMPANY Surry Power Station P. 0. lox 315 Surry, Virginia 23883 May 17, 1988 U.S. Nuclear Regulatory Commission Serial No.: 88-020 Docmnent Control Desk Docket No.: 50-280 016 Phillips Building Licensee No.: DPR-32 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}}
| | 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}} |
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LER 97-003-00:on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified open.W/970319 Ltr
ML18153A1131997-02-20020 February 1997
LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr
ML18153A1101997-02-13013 February 1997
LER 97-002-00:on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116.W/970214 Ltr
ML18153A0951997-01-0202 January 1997
LER 97-002-00:on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown
ML18153A0931996-12-12012 December 1996
LER 96-008-00:on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers replaced.W/961212 Ltr
ML18153A0691996-09-19019 September 1996
LER 96-007-00:on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch training.W/960920 Ltr
ML18153A0481996-08-26026 August 1996
LER 96-005-00:on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other tubing.W/960826 Ltr
ML18153A0521996-08-20020 August 1996
LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr
ML18153A0321996-07-30030 July 1996
LER 96-006-01:on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to batteries.W/960730 Ltr
ML18153A0281996-07-17017 July 1996
LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr
ML18153A0141996-07-0202 July 1996
LER 96-004-00:on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status trees.W/960702 Ltr
1999-08-27
[Table view]
Category:RO)
MONTHYEARML18152B4411999-08-27027 August 1999
LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18152B4421999-08-27027 August 1999
LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr
ML18152B3771999-08-13013 August 1999
LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18152B4181999-05-18018 May 1999
LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr
ML18152B4111999-04-28028 April 1999
LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr
ML18153A2741999-03-29029 March 1999
LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
ML18153A2681999-03-19019 March 1999
LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML18152B7261999-01-21021 January 1999
LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B5811998-12-16016 December 1998
LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5781998-12-16016 December 1998
LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B7121998-12-0404 December 1998
LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened
ML18152B7041998-12-0101 December 1998
LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr
ML18152B6161998-11-0606 November 1998
LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable
ML18152B6081998-10-23023 October 1998
LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely
ML18152B7811998-07-31031 July 1998
LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
ML18153A2581998-06-0303 June 1998
LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
ML18152B8241998-05-22022 May 1998
LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
ML18152B7951998-04-29029 April 1998
LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
ML18153A2521998-04-22022 April 1998
LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
ML18153A2511998-04-22022 April 1998
LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
ML18153A2391998-03-13013 March 1998
LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued
ML18153A2341998-03-0909 March 1998
LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
ML18153A2301998-03-0606 March 1998
LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
ML18153A2251998-03-0404 March 1998
LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
ML18153A2201998-02-0606 February 1998
LER 98-001-00:on 980108,deficient Test Due to Faulty Test Equipment Resulted in TS Violation.Caused by Faulty Vibration Analyzer Cable or Loose Connection.Station Deviation Rept Was submitted.W/980206 Ltr
ML18153A2071998-01-13013 January 1998
LER 97-012-01:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Two Breakers in Security Distribution Panel.Reset Affected Breakers Which Restored Power to Security Systems & Affected Doors
ML18153A2101998-01-13013 January 1998
LER 97-009-01:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Caused by Inadequate Maint of Intake Canal Level Probes.Subject Probes Were Cleaned, Tested Satisfactorily & Returned to Operable Status
ML18153A1911997-11-26026 November 1997
LER 97-011-00:on 971030,determined That Periodic Test Procedures for Testing Reactor Trip Bypass Breakers Did Not Test Manual Undervoltage Trip.Caused by mis-interpretation of Term in-service. Procedures Revised
ML18153A1971997-11-26026 November 1997
LER 97-012-00:on 971028,loss of Power to Latching Mechanism on Several Doors Occurred.Caused by Tripping of Breaker in Security Distribution Panel in Central Alarm Station (CAS) Panel.Breakers in Affected CAS Panel Reset
ML18153A1921997-11-25025 November 1997
LER 97-010-00:on 971028,discovered Missed Fire Protection Surveillance Pt.Caused by Personnel Error.Satisfactorily Completed PT Procedure 0-OPT-FP-009 & Diesel Driven Fire Pump 1-FP-P-2 Declared operable.W/971125 Ltr
ML18153A1831997-11-12012 November 1997
LER 97-009-00:on 971014,declared Intake Canal Level Probes Inoperable Due to Marine Growth.Cause Indeterminate.Divers Inspected,Cleaned & Returned Probes to Operable Status & Initiated Interdepartmental Team to Investigate Cause
ML18153A1791997-11-0707 November 1997
LER 97-008-00:on 971011,invalid Actuation of ESF Occurred. Caused by Personnel Errors.Main CR Bottled Air Sys Isolated & Containment Hydrogen Analyzer Heat Tracing Actuation Signal Reset
ML18153A1721997-10-30030 October 1997
LER 97-007-00:on 970930,determined That Plant Was Outside App R Design Basis Due to Vital Bus Isolation Issue.Caused by Personnel Error.Installed Circuit Protective Device During Oct 1997 Refueling Outage
ML18153A1421997-06-10010 June 1997
LER 97-001-01:on 970123,shutdown Occurred Due to Drain Line Weld Leak.Inspected & Tested Turbine Trip Actuation circuitry.W/970610 Ltr
ML18153A1391997-05-28028 May 1997
LER 97-005-00:on 970502,Unit 1 Power Range Nuclear Instrumentation Was Inoperable Due to Personnel Error.Sro & STA That Were Involved in Event Were Counseled
ML18153A1291997-04-18018 April 1997
LER 97-006-00:on 970320,loss of Refueling Integrity Due to Inadequate Containment Closure Process & Verification.Fuel Movement Stopped IAW Action Statement Requirements of TS 3.10.B.W/970418 Ltr
ML18153A1281997-04-15015 April 1997
LER 97-004-00:on 970317,main Steam Safety Valve Was Outside as Found Setpoint Tolerance.Specific Cause Unknown,However, Minor Setpoint Drift Can Be Expected.No Immediate Corrective Actions performed.W/970415 Ltr
ML18153A1241997-04-0808 April 1997
LER 97-002-01:on 970116,one Train of Auxiliary Ventilation Sys Was Inoperable Outside of Ts.Caused by Personnel Error. Submitted Deviation Rept Re Reverse Rotation of Fan & Work Request to Adjust linkage.W/970408 Ltr
ML18153A1191997-03-19019 March 1997
LER 97-001-00:on 970218,manual Reactor Trip & ESF Actuation Occurred Due to Loss of EHC Control Power.Caused by Momentary Short.Relay Card Was replaced.W/970319 Ltr
ML18153A1201997-03-19019 March 1997
LER 97-003-00:on 970219,loss of Pressurizer Heaters Resulted in Manual U1 Trip & U2 ESF Actuation.Caused by Loss of Group C Pressurizer Proportional Heaters.Reactor Trip Breakers Were Verified open.W/970319 Ltr
ML18153A1131997-02-20020 February 1997
LER 97-001-00:on 970123,shutdown Occurred Due to Steam Drain Line Weld Leak.Management Was Notified & Shift Supervisor Invoked Requirements of TS 4.15.C.1.W/undtd Ltr
ML18153A1101997-02-13013 February 1997
LER 97-002-00:on 970116,one Train of Auxiliary Ventilation Sys Declared Inoperable.Caused by Personnel Error.Properly Adjusted Damper 1-VS-MOD-58B & Exited Seven Day LCO on 970116.W/970214 Ltr
ML18153A0951997-01-0202 January 1997
LER 97-002-00:on 961213,automatic Reactor Trip Occurred During Planned Shutdown.Caused by Steam Flow/Feedwater Flow Mismatch.Rps Functioned as Designed & Plant Placed in Hot Shutdown
ML18153A0931996-12-12012 December 1996
LER 96-008-00:on 961112,water Gas Decay Tank Oxygen Analyzer Pressure Sensors Inoperable Due to Vendor Supplied Equipment Not Meeting Procurement specifications.Post-implementation Procedures Revised & Transducers replaced.W/961212 Ltr
ML18153A0691996-09-19019 September 1996
LER 96-007-00:on 960821,failed to Complete Fire Detection Zone Inspections within Required Time Period.Caused by Personnel Error.Counseled Personnel Re Fire Detection Zone Inspections & Revised Fire Watch training.W/960920 Ltr
ML18153A0481996-08-26026 August 1996
LER 96-005-00:on 960803,manual Reactor Trip.Caused by Loss of Electro Hydraulic Control Pressure.Repaired Two Compression Fitting Union Connections on Leaking Fitting & Performed Evaluations on Other tubing.W/960826 Ltr
ML18153A0521996-08-20020 August 1996
LER 96-004-01:on 960510,discovered Hydrogen Analyzers Inoperable.Caused by Procedural Deficiencies.Implemented Permanent Changes to Hydrogen Analyzer Instrument Calibr Procedures.W/960820 Ltr
ML18153A0321996-07-30030 July 1996
LER 96-006-01:on 960618,anti-corrosion Coating Had Not Been Reapplied to Station Battery 2B.Caused by Procedural Error in That Verbatim TS Compliance Not Reflected in Procedures. Coating Was Applied to batteries.W/960730 Ltr
ML18153A0281996-07-17017 July 1996
LER 96-006-00:on 960618,failed to Apply anti-corrosion Coating to Station Battery 2B.Caused by Procedural Error. Applied anti-corrosion Coating to Batteries & Revised TS 4.6.C.1.f Re Battery Coating requirements.W/960717 Ltr
ML18153A0141996-07-0202 July 1996
LER 96-004-00:on 960606,turbine/reactor Trip Occurred.Caused by High Level in Steam Generator B.Placed Plant in Hot Shutdown Condition,Calculated Shutdown Margin & Monitored Critical Safety Function Status trees.W/960702 Ltr
1999-08-27
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML18152A2811999-10-12012 October 1999
Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619.
ML18152B3531999-09-30030 September 1999
Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr
ML18152B6651999-08-31031 August 1999
Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr
ML18152B4421999-08-27027 August 1999
LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr
ML18152B4411999-08-27027 August 1999
LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed
ML18151A3981999-08-13013 August 1999
SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage.
ML18152B3771999-08-13013 August 1999
LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms
ML18152B3791999-07-31031 July 1999
Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr
ML18152B3911999-06-30030 June 1999
Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr
ML18152B4341999-05-31031 May 1999
Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr
ML20195E2401999-05-31031 May 1999
Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag
ML18152B4181999-05-18018 May 1999
LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr
ML18152B4161999-04-30030 April 1999
Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr
ML18152B4111999-04-28028 April 1999
LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr
ML18152B6511999-03-31031 March 1999
Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2
ML18153A2741999-03-29029 March 1999
LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212
ML18153A2681999-03-19019 March 1999
LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr
ML18152B7331999-02-28028 February 1999
Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr
ML18152B5421999-01-31031 January 1999
Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr
ML18151A3031999-01-29029 January 1999
ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements.
ML18152B7261999-01-21021 January 1999
LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable
ML18152B6011998-12-31031 December 1998
Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr
ML18152B5781998-12-16016 December 1998
LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B5811998-12-16016 December 1998
LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition
ML18152B7121998-12-0404 December 1998
LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened
ML18152B7041998-12-0101 December 1998
LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr
ML18152B7081998-11-30030 November 1998
Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un.
ML18152B5721998-11-30030 November 1998
Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr
ML18152B6161998-11-0606 November 1998
LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable
ML18152B6241998-10-31031 October 1998
Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr
ML18152B6081998-10-23023 October 1998
LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely
ML18152B6881998-09-30030 September 1998
Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr
ML18153A3271998-08-31031 August 1998
Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2
ML18152B7811998-07-31031 July 1998
LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status
ML18153A3161998-07-31031 July 1998
Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr
ML18152B7621998-06-30030 June 1998
Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr
ML18153A2581998-06-0303 June 1998
LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed
ML20248F7441998-05-31031 May 1998
Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity
ML18153A3141998-05-31031 May 1998
Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610
ML18152B8241998-05-22022 May 1998
LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed
ML18152B8161998-04-30030 April 1998
Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr
ML18152B7951998-04-29029 April 1998
LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6
ML18153A2511998-04-22022 April 1998
LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced
ML18153A2521998-04-22022 April 1998
LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame
ML20217P9941998-04-0707 April 1998
Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024
ML18153A2951998-03-31031 March 1998
Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr
ML18153A2391998-03-13013 March 1998
LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued
ML18153A2341998-03-0909 March 1998
LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition
ML18153A2301998-03-0606 March 1998
LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs
ML18153A2251998-03-0404 March 1998
LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket
1999-09-30
[Table view] |
Text
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Error EVENT DATE (51 LER NUMBER 161 REPORT DATE (71 OTHER FACILITIES INVOLVED 181 MONTH DAY YEAR YEAR tt SE~~~~~~AL ft ~E~~~~ MONTH DAY YEAR FACILITY NAMES DOCKET NUMBER(SI.
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- 50.7311l12llv111IIB) 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 MANUFAC- MANUFAC.
CAUSE SYSTEM COMPONENT TURER 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 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 EXPECTED
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SUBMISSION
.I YES /If yes, complata EXPECTED SUBMISSION OATE} NO DATE 1161 I I I ABSTRACT /Limit to 1400 spacas, I.a., approximeta/y';fiftaan ,ingla-spaca rypawrlttan /in**/ 1181 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 !
NRC Form 388 S PDR
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e e POW 28-06-01 NRC Form 3811A U.S. NUCLEAR REGULATORY COMMISSION (9-831 LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED 0MB NO. 3150-0104 EXPIRES: 8/31 /88 FACILITY NAME (11 DOCKET NUMBER (21 LER NUMBER (61 PAGE (31 Surry Power Station, Unit 1 o I5 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 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 sub-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 sub-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 NRC FORM 388A (9-831
- U.S.GPO: 1986*0-824-538/455
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e e POW 28-06-01 NRC Farm 31111A U.S. NUCLEAR REGULATORY COMMISSION 19-831
'* LICENSEE EVENT REPORT (LERI TEXT CONTINUATION APPROVED OMS NO. 3150-0104 EXPIRES: 8/31 /88 FACILITY NAME 111 DOCKET NUMBER 121 LER NUMBER 161 PAGE (31 VEAR Surrv Power Station. Unit 1 o 1s Io Io Io I 2 IR I n A R - n I 1 I1 - n In n h OF n I '.l TEXT,,, _ _ a _ _. u* - N R C Fonn.11111A'*I 1171 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 NRC FORM 388A 19-831
- U.S.GPO: 1988'.0-824*538/455
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VIRGINIA ELECTRIC ANO POWER COMPANY Surry Power Station P. 0. lox 315 Surry, Virginia 23883 May 17, 1988 U.S. Nuclear Regulatory Commission Serial No.: 88-020 Docmnent Control Desk Docket No.: 50-280 016 Phillips Building Licensee No.: DPR-32 Washington, D.C. 20555 Gentlemen::
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
