Forwards Corrected LER 94-008,changing Date to 940720 on Page 5 of 6,paragraph 5.0,line Four
Person / Time
ML18153B087
Site:	Surry
Issue date:	10/05/1994
From:	Christian D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153B088	List: 05000280/LER-1994-008, Forwards Corrected LER 94-008,changing Date to 940720 on Page 5 of 6,paragraph 5.0,line Four 05000280/LER-1994-008-07, Corrected LER 94-0087-00,reflecting That Filter 3A Replaced & Returned to Service on 940720 Following Testing in Accordance W/Ts 4.12
References
94-527A, NUDOCS 9410130172
Download: ML18153B087 (1)
v • d • e

LER-1994-008, Forwards Corrected LER 94-008,changing Date to 940720 on Page 5 of 6,paragraph 5.0,line Four

Event date:
Report date:
2801994008R00 - NRC Website
v • d • e

text

October 5, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Dear Sirs:

10CFR50.73 Vn-ginia Electric and Power Company Surry Power Station P.O.Box:315 Surry, Virginia 23883 Serial No.:

94-527 A SPS:VAS Docket Nos.: 50-280 50-281 License Nos.: DPR-32 DPR-37 A review of Licensee Event Report 50/280, 50/281/94-008 indicated that the subject report, dated September 6, 1994 (Serial No.94-527), contained incorrect data. On page 5 of 6, paragraph 5.0, line four, the date has been changed to July 20, 1994.

Attached is a corrected copy of this Licensee Event Report. Please replace the previously submitted version with the corrected copy. We regret any inconvenience resulting from this error.

Very truly yours, D. A. Christian Station Manager Attachment cc:

Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 M. W. Branch NRC Senior Resident Inspector Surry Power Station 120033 9410130172 941005 PDR ADOCK 05000280 S

PDR

Licensee Event Report

Surry

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000281/LER-1994-001-01, :on 940124,both Auxiliary Exhaust Filter Trains Declared Inoperable Due to Excessive flow.Six-h Action Statement to Hot Shutdown of Facility Entered Until Normal 1J Bus Alignment Restored	on 940124,both Auxiliary Exhaust Filter Trains Declared Inoperable Due to Excessive flow.Six-h Action Statement to Hot Shutdown of Facility Entered Until Normal 1J Bus Alignment Restored	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii)
05000280/LER-1994-001-03, :on 940203,while Unit 1 Was at Cold Shutdown in Refueling Outage,Tack Weld Was Being Performed & Water Squirted from Opening in RCS Piping.Caused by H Gas in Pressurizer Being Ignited by Welding Arc	on 940203,while Unit 1 Was at Cold Shutdown in Refueling Outage,Tack Weld Was Being Performed & Water Squirted from Opening in RCS Piping.Caused by H Gas in Pressurizer Being Ignited by Welding Arc	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000281/LER-1994-002-01, :on 940307,filtered Exhaust Fan 1-VS-F-58B Tripped,Rendering Ventilation Filtered Exhaust Train Inoperable.Caused by Damper from Filter Was Found Halfway Shut.Filter Fully Opened & Device Tightened	on 940307,filtered Exhaust Fan 1-VS-F-58B Tripped,Rendering Ventilation Filtered Exhaust Train Inoperable.Caused by Damper from Filter Was Found Halfway Shut.Filter Fully Opened & Device Tightened	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A)
05000280/LER-1994-002-03, :on 940204,main Steam Safety Valves Found Out of Tolerance.Caused by Minor Setpoint Drift.Valves Inspected & Overhauled	on 940204,main Steam Safety Valves Found Out of Tolerance.Caused by Minor Setpoint Drift.Valves Inspected & Overhauled	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)
05000280/LER-1994-003-01, :on 940204,hole in Recirculating Spray HX Svc Water Outlet Piping Identified.Caused by Failure of Coal Tar Epoxy Coating.Piping Inspected & Will Be Pressure Tested Per Station Procedures	on 940204,hole in Recirculating Spray HX Svc Water Outlet Piping Identified.Caused by Failure of Coal Tar Epoxy Coating.Piping Inspected & Will Be Pressure Tested Per Station Procedures	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000281/LER-1994-003-03, :on 940617,primary Grade Water Supply Manual Isolation Valve 2-CH-212 Found in Open Position During Cold Shutdown Condition Due to Personnel Error.Valve 2-CH-212 Immediately Isolated & Secured	on 940617,primary Grade Water Supply Manual Isolation Valve 2-CH-212 Found in Open Position During Cold Shutdown Condition Due to Personnel Error.Valve 2-CH-212 Immediately Isolated & Secured	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B)
05000281/LER-1994-004-03, :on 941007,inoperable Condition Noted During Performance of Corrective Maint on Station Battery 2A.Caused by Inadequate post-maint Testing & Cognitive Personnel Error by Util Engineer.Process Changed	on 941007,inoperable Condition Noted During Performance of Corrective Maint on Station Battery 2A.Caused by Inadequate post-maint Testing & Cognitive Personnel Error by Util Engineer.Process Changed	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000280/LER-1994-004, :on 940301,reactor Coolant Sys Loops Drained & Isolated.Caused by Personnel Error.Operations Dept Personnel Involved Counseled	on 940301,reactor Coolant Sys Loops Drained & Isolated.Caused by Personnel Error.Operations Dept Personnel Involved Counseled	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000280/LER-1994-005, :on 940330,steady State Reactor Power Exceeded Operating License Limit.Caused by Inadequate Instrumentation Change Control Process.Instrumentation Change Control Process Modified	on 940330,steady State Reactor Power Exceeded Operating License Limit.Caused by Inadequate Instrumentation Change Control Process.Instrumentation Change Control Process Modified	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)
05000280/LER-1994-006, :on 940511,manual Reactor Trip Occurred During Safeguards Actuation Logic Testing.Caused by Inadvertent Actuation of Relay in Safety Injection Actuation Circuitry. Reactor Placed in Safe,Hot Shutdown Condition	on 940511,manual Reactor Trip Occurred During Safeguards Actuation Logic Testing.Caused by Inadvertent Actuation of Relay in Safety Injection Actuation Circuitry. Reactor Placed in Safe,Hot Shutdown Condition	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B)
05000280/LER-1994-007, :on 940614,Kaman Process Vent Radiation Monitors Were Declared Inoperable.Caused by Moisture Entrapment in System.Annunciator Response Procedure 0-RM-A-C-4 Was Performed	on 940614,Kaman Process Vent Radiation Monitors Were Declared Inoperable.Caused by Moisture Entrapment in System.Annunciator Response Procedure 0-RM-A-C-4 Was Performed	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A)
05000280/LER-1994-008, Forwards Corrected LER 94-008,changing Date to 940720 on Page 5 of 6,paragraph 5.0,line Four	Forwards Corrected LER 94-008,changing Date to 940720 on Page 5 of 6,paragraph 5.0,line Four
05000280/LER-1994-008-07, Corrected LER 94-0087-00,reflecting That Filter 3A Replaced & Returned to Service on 940720 Following Testing in Accordance W/Ts 4.12	Corrected LER 94-0087-00,reflecting That Filter 3A Replaced & Returned to Service on 940720 Following Testing in Accordance W/Ts 4.12	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A)
05000280/LER-1994-010, :on 940927,procedure 0-EPT-0109-03,weekly Emergency Diesel Generator Battery Pilot Cell & Bus Voltage Checks Had Not Been Performed.Caused by Personnel Error. Individuals Were Counseled	on 940927,procedure 0-EPT-0109-03,weekly Emergency Diesel Generator Battery Pilot Cell & Bus Voltage Checks Had Not Been Performed.Caused by Personnel Error. Individuals Were Counseled	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B)

05000280/LER-1994-008, Forwards Corrected LER 94-008,changing Date to 940720 on Page 5 of 6,paragraph 5.0,line Four

text

Dear Sirs:

Navigation menu

Search