LER-1980-055, /01T-0:on 800626,review of FSAR Safety Analyses for Boron Dilution Accidents Determined That Nonconservative RCS Vols Were Used for Cold Shutdown Condition.Cause Undetermined.Solution Pending Further Evaluation |
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Q" U.S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK / / / / / / / (1)
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
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DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)
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During a review'of the FSAR safety analyse.s for boron dilution accidents, it
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was determined ; hat nonconservative RCS volumes were used for the Cold Shut-
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down conditiori..Since the FSAR analysis assumes a full RCS and the RCS may
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be drained to the centerline of the RCS hotlegs, the volumes used in the
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analysis are nonconservative. This event is reportable pursuant to T.S.
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Since neither Unit 1 or 2 are in the cold shutdown condition, the /
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public health and safety are not affected.
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SEQUENTIAL OCCURRENCE REPORT REVISION LER/R0 EVENT YEAR REPORT NO.
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ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
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The cause of the discrepancy is not known. A minimum of two shutdown banks
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will be fully withdrawn and available for trip during shutdown conditions.
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withdrawn banks, the operator will 'nitiate boration immediately. This
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solution will be used pending further evaluation.
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FACILITY METHOD OF DISCO W J DESC M ON (32)
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80 0.715 0 M NAME ~ OF PREPARER -
W. R. CARTWRIGHT PHONE (703) 894-5151
4.
I Virginia Electric and Power Company North Anna Power Station, Unit 1 Attachment: Page 1 of 2 l
Docket No. 50-338 Report No. LER 80-055/01T-0
Description of Event
During a review of the FSAR safety analyses for boron dilution accidents, it was determined that nonconcervative RCS volumes were used for the Cold Shutdown condition. FSAR section 15.2.4.3 states that in the Cold Shutdown condition with a boron concentration of 1500 ppm, all RCC assemblies in, and a dilution flow rate of 300 gpm, the reactor could go critical in 15.5 minutes. This result may not be conservative because the RCS was assumed to be full.
In the Cold Shutdown condition the RCS may be drained to the centerline of the RCS hotlegs for main-tenance. This event applies to both Unit 1 and 2 and is reportable pursuant to T.S. 6.9.1.8.h.
At the time the event was determined to be reportable Unit I was in Mode 1 (Power Operation) and Unit 2 was in Mode 3 (Hot Standby).
Probable Consequences of Occurrence Since in Modes 3, 4, 5 and 6, the PG valves to the blend system are locked closed within 15 minutes after a planned dilution or makeup activity pursuant to T.S. 3.1.1.3.2 and neither unit is in cold shutdown, there are no immediate consequences which will affect the public health and safety. Westinghouse is performing a review of the safety signifi-cance of an inadvertant boron dilution at shutdown conditions and has identified the following potential concerns:
1)
There may be insufficient indication of an inadvertant dilution event to assure timely action by the operator prior to a
' return to critical.
2)
Without positive operator action, the potential exists for system overpressurization and limited fuel damage.
Both Vepco and Westinghouse are continuing investigations of the safety significance of inadvertant boron dilution at shutdown conditions.
Cause of Event
The cause of the discrepancy in FSAR analyses for boron dilution accidents is not known.
Immediate Corrective Action
In order to increase the safety margin for boron dilution accidents the following interim actions have been implemented:
1)
During shutdown conditions and while on the residual heat removal system, a minimum of two shutdown banks will be avail-able for trip (fully withdrawn) whenever dilution /bocation capability exists.
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Following either a source range high flux at shutdown alarm or trip of the withdrawn bank, the operator will terminate the dilution and f attiate boration immediately.
3)
The source range detectors and high flux at shutdown alarm will be verified as operable during shutdown.
The above interim action will continue until investigation results indicate other actions to be appropriate.
Scheduled Corrective Actions Corrective actions other than the actions listed above are pending the results of investigations of the safety significance of inadvertant boron dilution at shutdown conditions.
Actions to Prevent Recurrance No actions to prevent recurrance are required.
Generic Implications Westinghouse is conducting an investigation of the safety signifi-cance of inadvertant boron dilution at shutdown conditions for generic implications.
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| 05000338/LER-1980-001-01, /01T-0:on 800118,during Review for IE Bulletin 79-14,letdown Lines 3/4-CH-275-1502Q1 & 3/4-CH-123-1502-Q2 Reported Overstressed.Caused by Incorrect Valve Weights Used in Pipe Stress Calculations | /01T-0:on 800118,during Review for IE Bulletin 79-14,letdown Lines 3/4-CH-275-1502Q1 & 3/4-CH-123-1502-Q2 Reported Overstressed.Caused by Incorrect Valve Weights Used in Pipe Stress Calculations | | | 05000338/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000339/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000339/LER-1980-001-03, /03L-0:on 800423,w/unit in Mode 6 Following Fuel Loading,Rhr Sys Inlet Valve MOV-2700 Ran Closed,Causing Loss of Operable RHR Loop.Caused by Blown Signal Comparator Card Power Supply Fuse in Process Control Sys.Card Replaced | /03L-0:on 800423,w/unit in Mode 6 Following Fuel Loading,Rhr Sys Inlet Valve MOV-2700 Ran Closed,Causing Loss of Operable RHR Loop.Caused by Blown Signal Comparator Card Power Supply Fuse in Process Control Sys.Card Replaced | | | 05000338/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000338/LER-1980-002-01, /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations | /01T-0:on 800107,S&W Informed Util That Stress on Vertical Supports RH-R-19 & WS-R-316 & Snubbers SI-HSS-101B,101C & 107A Exceeded Allowable Design Values. Caused by Wrong Valve Weights Used in Design Calculations | | | 05000339/LER-1980-002-01, /01T-0:on 800429,during Structural Review for IE Bulletin 79-14,S&W Discovered Overstressed Pipe Hangers in Svc Bldg.Caused by Error in Stress Analysis Used to Design Pipe Hanger Supports.Mods Will Be Implemented | /01T-0:on 800429,during Structural Review for IE Bulletin 79-14,S&W Discovered Overstressed Pipe Hangers in Svc Bldg.Caused by Error in Stress Analysis Used to Design Pipe Hanger Supports.Mods Will Be Implemented | | | 05000339/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000339/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000339/LER-1980-003-03, /03L-0:on 800528,2H Diesel Generator Frequency & Voltage Response Was Not Verified Every 8-h,contrary to Tech Spec.Caused by Faulty Lead on Monitoring Instrumentation. Offsite Power Sources Verified & Found Acceptable | /03L-0:on 800528,2H Diesel Generator Frequency & Voltage Response Was Not Verified Every 8-h,contrary to Tech Spec.Caused by Faulty Lead on Monitoring Instrumentation. Offsite Power Sources Verified & Found Acceptable | | | 05000338/LER-1980-003-03, /03L-0:on 800121,nuclear Instrumentation Sys Power Range Channel 4 Declared Inoperable Due to Erratic Power Bistable Operation.Caused by Failed Ion Chamber Detector.Ion Chamber Detector Replaced | /03L-0:on 800121,nuclear Instrumentation Sys Power Range Channel 4 Declared Inoperable Due to Erratic Power Bistable Operation.Caused by Failed Ion Chamber Detector.Ion Chamber Detector Replaced | | | 05000338/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000339/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000339/LER-1980-004-03, /03L-0:on 800519,during Mode 3 Operation,Steam Generator Level Channel LT-2475 Indicated Level 9% Lower than Two Redundant Channels.Caused by Voltage Drift.Channel Was Placed in Trip Mode | /03L-0:on 800519,during Mode 3 Operation,Steam Generator Level Channel LT-2475 Indicated Level 9% Lower than Two Redundant Channels.Caused by Voltage Drift.Channel Was Placed in Trip Mode | | | 05000338/LER-1980-004-03, /03L-0:on 800109,during Test of Equipment Hatch Emergency Escape Lock,Inner Door Seal Found Leaking When Door Opened & Lock Found to Be Under Slight Vacuum.Caused by Frequent Door Operation.Seals Replaced | /03L-0:on 800109,during Test of Equipment Hatch Emergency Escape Lock,Inner Door Seal Found Leaking When Door Opened & Lock Found to Be Under Slight Vacuum.Caused by Frequent Door Operation.Seals Replaced | | | 05000338/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000338/LER-1980-005-03, /03L-0:on 800110,w/unit in Mode 4,main Steam Isolation Trip Valve TV-MS101C Would Not Close Using Train a Push Button.Caused by Open Auxiliary Relay in Circuit. Relay Replaced from Stock & Tested Satisfactorily | /03L-0:on 800110,w/unit in Mode 4,main Steam Isolation Trip Valve TV-MS101C Would Not Close Using Train a Push Button.Caused by Open Auxiliary Relay in Circuit. Relay Replaced from Stock & Tested Satisfactorily | | | 05000338/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000339/LER-1980-005-03, /03L-0:on 800517,2J Emergency Diesel Generator Tripped After Starting & Operability of 2H Diesel Generator Was Not Verified within 1-h.Caused by Existing Procedures Not Specifying Test Connections Required to Test Diesel | /03L-0:on 800517,2J Emergency Diesel Generator Tripped After Starting & Operability of 2H Diesel Generator Was Not Verified within 1-h.Caused by Existing Procedures Not Specifying Test Connections Required to Test Diesel | | | 05000339/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000339/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000339/LER-1980-006-03, /03L-0:on 800520,during Startup Testing in Mode 3, B Steam Generator Narrow Range Level Channel III Was Observed Reading Below Redundant Level Channels & Drifting Low.Caused by Air Pocket in Steam Generator Sensing Line | /03L-0:on 800520,during Startup Testing in Mode 3, B Steam Generator Narrow Range Level Channel III Was Observed Reading Below Redundant Level Channels & Drifting Low.Caused by Air Pocket in Steam Generator Sensing Line | | | 05000338/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000338/LER-1980-006-03, /03L-01:on 800111,w/unit in Mode 3,casing Coolant Pump Discharge Valve MOV-RS-100A Was Discovered to Be Inoperable.Caused by Removal of Casing Cooling Tank Level Transmitter LT-RS103A During Execution of Design Change | /03L-01:on 800111,w/unit in Mode 3,casing Coolant Pump Discharge Valve MOV-RS-100A Was Discovered to Be Inoperable.Caused by Removal of Casing Cooling Tank Level Transmitter LT-RS103A During Execution of Design Change | | | 05000338/LER-1980-007-03, /03L-0:on 800111,during Mode 3 Reactor Heating Containment Average Temp Decreased to 85 F,Less than Tech Specs.Caused by Insufficient Procedural Precautions. Removed Chiller from Svc.Monitored Temp | /03L-0:on 800111,during Mode 3 Reactor Heating Containment Average Temp Decreased to 85 F,Less than Tech Specs.Caused by Insufficient Procedural Precautions. Removed Chiller from Svc.Monitored Temp | | | 05000339/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000339/LER-1980-007-03, /03L-0:on 800521,during Mode 3 Operation,Channel in Tave Protection Loop 2 Failed in High Direction.Cause Is Unknown.Failed Channel Was Removed from Svc & Replaced by Spare | /03L-0:on 800521,during Mode 3 Operation,Channel in Tave Protection Loop 2 Failed in High Direction.Cause Is Unknown.Failed Channel Was Removed from Svc & Replaced by Spare | | | 05000339/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000338/LER-1980-008-01, /01T-0:on 800111,during Review for IE Circular 78-08,S&W Found Control Room Air Conditioning Chiller Units Control Panel Not Qualified to Seismic Category I Requirements.Cause Unknown.Vendor Reviewing Components | /01T-0:on 800111,during Review for IE Circular 78-08,S&W Found Control Room Air Conditioning Chiller Units Control Panel Not Qualified to Seismic Category I Requirements.Cause Unknown.Vendor Reviewing Components | | | 05000339/LER-1980-008-03, /03L-0:on 800521,during Mode 3 Operation,Redundant Channel Protection Was Lost.Caused by Personnel Not Placing Tave Protection Loop Failed Channel in Trip Mode within Required Time.Failed Channel Placed in Trip Mode | /03L-0:on 800521,during Mode 3 Operation,Redundant Channel Protection Was Lost.Caused by Personnel Not Placing Tave Protection Loop Failed Channel in Trip Mode within Required Time.Failed Channel Placed in Trip Mode | | | 05000338/LER-1980-009-03, /03L-0:on 800111,while Performing Periodic Test on Main Steam Safety Valves,Found Valves SV-MS-101-A & C, SV-MS-102-A & B & SV-MS-105-A & C Did Not Lift at Pressure Setpoints Per Tech Specs.Caused by Setpoint Drift | /03L-0:on 800111,while Performing Periodic Test on Main Steam Safety Valves,Found Valves SV-MS-101-A & C, SV-MS-102-A & B & SV-MS-105-A & C Did Not Lift at Pressure Setpoints Per Tech Specs.Caused by Setpoint Drift | | | 05000339/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000339/LER-1980-009-03, /03L-0:on 800522,power Supply for Main Steam Pressure Protection Channel III Failed High,Causing Steam Line Pressure Mismatch.Caused by Failed Card in Power Supply.Card Was Replaced & Calibr | /03L-0:on 800522,power Supply for Main Steam Pressure Protection Channel III Failed High,Causing Steam Line Pressure Mismatch.Caused by Failed Card in Power Supply.Card Was Replaced & Calibr | | | 05000338/LER-1980-010-01, /01T-0:on 800111,during Review for IE Bulletin 79-14,S&W Found Stress on Vertical Rod Hangers SW-H-162A & SW-H-160A to Be Over Design Allowable.Caused by Incorrect Valve Weights Used in Pipe Support Design Calculations | /01T-0:on 800111,during Review for IE Bulletin 79-14,S&W Found Stress on Vertical Rod Hangers SW-H-162A & SW-H-160A to Be Over Design Allowable.Caused by Incorrect Valve Weights Used in Pipe Support Design Calculations | | | 05000339/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000339/LER-1980-010-01, /01T-0:on 800523,during Review of ECCS Piping for Fluid Temp Below 70 F,Determined That Loadings on Both Low Head Safety Injection Pump Nozzles Exceeded Design Stress Allowables.Caused by Deficiency in Sys Stress Analysis | /01T-0:on 800523,during Review of ECCS Piping for Fluid Temp Below 70 F,Determined That Loadings on Both Low Head Safety Injection Pump Nozzles Exceeded Design Stress Allowables.Caused by Deficiency in Sys Stress Analysis | | | 05000339/LER-1980-011-03, /03L-0:on 800520,personnel Air Lock Doors Would Not Seal Completely,Causing Air Leakage While Performing Surveillance Test 2-PT-62.4.Caused by Leakage Past Seals on Inner & Outer Doors.New Seals Were Installed | /03L-0:on 800520,personnel Air Lock Doors Would Not Seal Completely,Causing Air Leakage While Performing Surveillance Test 2-PT-62.4.Caused by Leakage Past Seals on Inner & Outer Doors.New Seals Were Installed | | | 05000339/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000338/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000338/LER-1980-011-03, /03L-0:on 800115,when Sys Sample Monitoring Pumps Were Removed from Svc,Ventilation Vent Stack B Particulate & Gas Radiation Monitors RM-VG112 & 113 Were Rendered Inoperable.Design Changes Will Add High Range Monitor | /03L-0:on 800115,when Sys Sample Monitoring Pumps Were Removed from Svc,Ventilation Vent Stack B Particulate & Gas Radiation Monitors RM-VG112 & 113 Were Rendered Inoperable.Design Changes Will Add High Range Monitor | | | 05000339/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000339/LER-1980-012-03, /03L-0:on 800618 While in Mode 2,control Rod Demand Position Indication Noted 19 Steps Higher than Associated Rod Position Indication.Caused by Drift of Rod Position Indicator Channel.Channel Recalibr | /03L-0:on 800618 While in Mode 2,control Rod Demand Position Indication Noted 19 Steps Higher than Associated Rod Position Indication.Caused by Drift of Rod Position Indicator Channel.Channel Recalibr | | | 05000338/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000338/LER-1980-012-03, /03L-0:on 800111,during Testing in Mode 3 to Verify Main Steam Trip Valve Closure Time,Trip Valve Failed to Close Fully within Required Five Seconds.Cause Unknown. Valve Was Retested.Closure Time within Acceptable Limits | /03L-0:on 800111,during Testing in Mode 3 to Verify Main Steam Trip Valve Closure Time,Trip Valve Failed to Close Fully within Required Five Seconds.Cause Unknown. Valve Was Retested.Closure Time within Acceptable Limits | | | 05000338/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000338/LER-1980-013-03, /03L-0:on 800114,while Using Steam Driven Feedwater Pump 1-FW-P-2 to Add Feedwater to Steam Generator A,Water Leaked from Pump Oil Cooler Gasket.Caused by Blown Gasket.Gasket Replaced | /03L-0:on 800114,while Using Steam Driven Feedwater Pump 1-FW-P-2 to Add Feedwater to Steam Generator A,Water Leaked from Pump Oil Cooler Gasket.Caused by Blown Gasket.Gasket Replaced | | | 05000339/LER-1980-013-03, /03L-0:on 800520 & 27,w/unit in Hot Standby, Samples of Boron Injection Tank & C Boric Acid Storage Found to Contain Less than 20,000 Ppm Boron.Caused by Leaks Past Inlet Valves MOV-2867 a & B.Switch Settings Increased | /03L-0:on 800520 & 27,w/unit in Hot Standby, Samples of Boron Injection Tank & C Boric Acid Storage Found to Contain Less than 20,000 Ppm Boron.Caused by Leaks Past Inlet Valves MOV-2867 a & B.Switch Settings Increased | | | 05000339/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000338/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000338/LER-1980-014-03, /03L-0:on 800113,during Insp of Auxiliary Feedwater Pump 1-FW-P-2 Outboard Bearing,Discovered Inboard Side of Thrust Bearing Had Been Wiped.Caused by Lack of Oil. Bearing Replaced & Pump Returned to Svc | /03L-0:on 800113,during Insp of Auxiliary Feedwater Pump 1-FW-P-2 Outboard Bearing,Discovered Inboard Side of Thrust Bearing Had Been Wiped.Caused by Lack of Oil. Bearing Replaced & Pump Returned to Svc | |
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