Similar Documents at Hatch |
---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARHL-5657, Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures1998-07-30030 July 1998 Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures HL-5278, Special Rept:On 961203,30 Days Elapsed Since Position Indication Light for MSIV 1B21-F022D Declared Inoperable. Caused by Limit Switch Out of Proper Adjustment for Power Conditions.Light Will Be Restored During Next Outage1996-12-11011 December 1996 Special Rept:On 961203,30 Days Elapsed Since Position Indication Light for MSIV 1B21-F022D Declared Inoperable. Caused by Limit Switch Out of Proper Adjustment for Power Conditions.Light Will Be Restored During Next Outage HL-5212, Special Rept:On 960721,flood-up Range Reactor Vessel Water Level Instrument 1B21-R605 Out of Svc for Greater than 30 Days.Caused by Packing Leak on Equalizing Valve.Packing Leak on Equalizing Valve Repaired1996-07-30030 July 1996 Special Rept:On 960721,flood-up Range Reactor Vessel Water Level Instrument 1B21-R605 Out of Svc for Greater than 30 Days.Caused by Packing Leak on Equalizing Valve.Packing Leak on Equalizing Valve Repaired HL-5096, Special Rept 1-95-004:on 951215,emergency Light 1R42-E125 Declared Inoperable for More than 14 Days.Caused by Result of Broken Battery Terminal Discovered During Routine Surveillance Testing.Battery Replaced1996-01-0909 January 1996 Special Rept 1-95-004:on 951215,emergency Light 1R42-E125 Declared Inoperable for More than 14 Days.Caused by Result of Broken Battery Terminal Discovered During Routine Surveillance Testing.Battery Replaced HL-5082, Special Rept I-95-003:on 951117,fire Door 1L-48-1C50 Remained Inoperable for Longer than 14 Days.Caused by Component Failure Resulting from High Usage.Appropriate Fire Detectors Verified1995-12-0707 December 1995 Special Rept I-95-003:on 951117,fire Door 1L-48-1C50 Remained Inoperable for Longer than 14 Days.Caused by Component Failure Resulting from High Usage.Appropriate Fire Detectors Verified HL-5073, Special Rept 2-95-003:on 951029,fire Door 2L48-2R23 Had Remained Inoperable for More than 14 Days to Support Scheduled Refueling Outage Work.Fire Door 2L48-2R23 Restored to Operable Status on 9510311995-11-28028 November 1995 Special Rept 2-95-003:on 951029,fire Door 2L48-2R23 Had Remained Inoperable for More than 14 Days to Support Scheduled Refueling Outage Work.Fire Door 2L48-2R23 Restored to Operable Status on 951031 HL-4876, Special Rept:On 950516,fire Doors Blocked Open in Controlled Manner to Provide Addl Cooling for Plant RPS motor-generator Set Rooms.Cause Due to Controlled Actions of Appropriate Personnel.Doors Restored to Operable Status1995-06-21021 June 1995 Special Rept:On 950516,fire Doors Blocked Open in Controlled Manner to Provide Addl Cooling for Plant RPS motor-generator Set Rooms.Cause Due to Controlled Actions of Appropriate Personnel.Doors Restored to Operable Status HL-4773, Special Rept:On 950113,monitor Displayed Microcomputer Error Code Indicating Inoperability of Flow Transducer in Sampling Sys.Caused by Component Failure.Several Components Replaced or Adjusted in Accordance W/Mfg Recommendations1995-01-27027 January 1995 Special Rept:On 950113,monitor Displayed Microcomputer Error Code Indicating Inoperability of Flow Transducer in Sampling Sys.Caused by Component Failure.Several Components Replaced or Adjusted in Accordance W/Mfg Recommendations HL-0476, Special Rept 2-95-01:on 950110 Unit 2 Drywell High Range Radiation Inoperable Longer than 7 Days.Caused by Exceeding Procedural Limits of 34SV-SUV-019-2S.Technicians Checked High Voltage Power Supply Which Powers Radiation Detectors1995-01-17017 January 1995 Special Rept 2-95-01:on 950110 Unit 2 Drywell High Range Radiation Inoperable Longer than 7 Days.Caused by Exceeding Procedural Limits of 34SV-SUV-019-2S.Technicians Checked High Voltage Power Supply Which Powers Radiation Detectors HL-4727, Special Rept:On 941007,discovered That Required Hourly Fire Watch Patrol Initiated for Fire Area 0040 on 920629 Inappropriately Terminated Due to Personnel Error.Hourly Fire Watch Patrol for Affected Area re-established1994-10-31031 October 1994 Special Rept:On 941007,discovered That Required Hourly Fire Watch Patrol Initiated for Fire Area 0040 on 920629 Inappropriately Terminated Due to Personnel Error.Hourly Fire Watch Patrol for Affected Area re-established HL-4693, Special Rept 1-94-001:on 940911,seven Days Elapsed Since Main Stack post-accident Effluent Monitoring Sys Declared Inoperable Due to Damage to Sys Electronics by Lightning. Sys Expected to Be Returned to Svc by 9409211994-09-15015 September 1994 Special Rept 1-94-001:on 940911,seven Days Elapsed Since Main Stack post-accident Effluent Monitoring Sys Declared Inoperable Due to Damage to Sys Electronics by Lightning. Sys Expected to Be Returned to Svc by 940921 HL-4590, Special Rept 2-94-001:on 940517,fire Rated Assembly Was Inoperable for Longer than 14 Days as Result of Planned Activities.Caused by Affected Assemblies & Sealed Devices1994-05-17017 May 1994 Special Rept 2-94-001:on 940517,fire Rated Assembly Was Inoperable for Longer than 14 Days as Result of Planned Activities.Caused by Affected Assemblies & Sealed Devices HL-3434, Special Rept 1-93-004:on 930512,discovered That Cable Trays TFQ5-01 & TFR3-01 Were Not Enclosed in Thermo-Lag 330-1 Fire Barrier Matl,Per Safe Shutdown Analysis Rept.Caused by Inadequate Design.Appropriate Fire Detectors Verified1993-08-30030 August 1993 Special Rept 1-93-004:on 930512,discovered That Cable Trays TFQ5-01 & TFR3-01 Were Not Enclosed in Thermo-Lag 330-1 Fire Barrier Matl,Per Safe Shutdown Analysis Rept.Caused by Inadequate Design.Appropriate Fire Detectors Verified HL-3054, Special Rept 2-92-005:on 921102,battery-powered Emergency Lighting Unit Inoperable for More than 72 H.Caused by Failure of Lighting Unit to Pass Regularly Scheduled Maint. Lighting Unit Replaced & Verified Operable1992-12-0202 December 1992 Special Rept 2-92-005:on 921102,battery-powered Emergency Lighting Unit Inoperable for More than 72 H.Caused by Failure of Lighting Unit to Pass Regularly Scheduled Maint. Lighting Unit Replaced & Verified Operable HL-2937, Special Rept 1-92-002:on 920911,fire Barrier Assembly Inoperable for Longer than 14 Days Due to Cavity in 3 H Fire Rated Wall.Cause of Cavity Unknown.Cavity in Wall Repaired Under Mwo 1-92-4244 on 9209181992-10-0707 October 1992 Special Rept 1-92-002:on 920911,fire Barrier Assembly Inoperable for Longer than 14 Days Due to Cavity in 3 H Fire Rated Wall.Cause of Cavity Unknown.Cavity in Wall Repaired Under Mwo 1-92-4244 on 920918 HL-2380, Special Rept 1-92-001:on 920804,during Monthly Operability Test on Lighting Unit 1R42-E130,light Failed to Illuminate. Caused by Failure of battery-powered Emergency Lighting Unit to Pass Scheduled Surveillance.Subj Unit Replaced1992-08-28028 August 1992 Special Rept 1-92-001:on 920804,during Monthly Operability Test on Lighting Unit 1R42-E130,light Failed to Illuminate. Caused by Failure of battery-powered Emergency Lighting Unit to Pass Scheduled Surveillance.Subj Unit Replaced HL-2341, Special Rept 2-92-004:on 920630,battery Powered Emergency Lighting Units Inoperable for Period Greater than 72 H.Event Had No Adverse Impact on Nuclear Safety.Battery Discharge Test Performed1992-07-30030 July 1992 Special Rept 2-92-004:on 920630,battery Powered Emergency Lighting Units Inoperable for Period Greater than 72 H.Event Had No Adverse Impact on Nuclear Safety.Battery Discharge Test Performed HL-2247, Special Rept:On 920506,discovered That Annual 8 H Battery Discharge Test on Lighting Unit 2R242-E104 Had Not Been Performed in 1991.Caused by Personnel error.Battery-powered Emergency Lighting Demonstrated Operable1992-06-0505 June 1992 Special Rept:On 920506,discovered That Annual 8 H Battery Discharge Test on Lighting Unit 2R242-E104 Had Not Been Performed in 1991.Caused by Personnel error.Battery-powered Emergency Lighting Demonstrated Operable HL-2203, Special Rept 2-92-002:on 920407,signal from Triaxial Time History Accelerometer Contained Excessive Amount of Noise & Instrument Declared Inoperable for More than 30 Days.Cause Not Determined.Root Cause Analysis Underway1992-05-11011 May 1992 Special Rept 2-92-002:on 920407,signal from Triaxial Time History Accelerometer Contained Excessive Amount of Noise & Instrument Declared Inoperable for More than 30 Days.Cause Not Determined.Root Cause Analysis Underway HL-1967, Special Rept 1-91-010:on 911121,discovered That Blue Pen of post-accident Effluent Monitoring Sys Recorder 1D11-R631 Spiking Upscale at Regular Interval.Caused by Failed Flow Transducer.Flow Transducer Replaced1991-12-0505 December 1991 Special Rept 1-91-010:on 911121,discovered That Blue Pen of post-accident Effluent Monitoring Sys Recorder 1D11-R631 Spiking Upscale at Regular Interval.Caused by Failed Flow Transducer.Flow Transducer Replaced HL-1941, Special Rept 1-91-009:from 910929-1029,all Fuel Removed from Reactor Vessel & Fire Barriers Inoperable for More than 14 Days.Caused by Need to Install Support Plates,Platforms & Conduits.Structural Beams Restored to Operable Status1991-11-22022 November 1991 Special Rept 1-91-009:from 910929-1029,all Fuel Removed from Reactor Vessel & Fire Barriers Inoperable for More than 14 Days.Caused by Need to Install Support Plates,Platforms & Conduits.Structural Beams Restored to Operable Status HL-1916, Special Rept 1-91-008:on 911014,four Suppression Sys Flooding Valves in Fixed Water Suppression Sys Not Surveilled Once Per 18 Months.Caused by Less than Adequate Procedure.Valves Tested & Inspected Per Revised Procedures1991-11-0808 November 1991 Special Rept 1-91-008:on 911014,four Suppression Sys Flooding Valves in Fixed Water Suppression Sys Not Surveilled Once Per 18 Months.Caused by Less than Adequate Procedure.Valves Tested & Inspected Per Revised Procedures HL-1891, Special Rept 2-91-003:on 911003,during Performance of Battery Discharge Test,Two Emergency Lighting Units Failed to Illuminate for 8 H & Could Not Be Restored within 72 H. Lighting Units Repaired & Discharge Test Performed1991-10-31031 October 1991 Special Rept 2-91-003:on 911003,during Performance of Battery Discharge Test,Two Emergency Lighting Units Failed to Illuminate for 8 H & Could Not Be Restored within 72 H. Lighting Units Repaired & Discharge Test Performed HL-1682, Rev 2 to Special Rept 1-91-005:on 910515,discovered That Cable Penetration Seal Assembly Not Installed Per Mfg Instructions & Barrier Inoperable for More than 14 Days. Hourly Fire Watch Established & Thermolag Barrier Installed1991-10-0909 October 1991 Rev 2 to Special Rept 1-91-005:on 910515,discovered That Cable Penetration Seal Assembly Not Installed Per Mfg Instructions & Barrier Inoperable for More than 14 Days. Hourly Fire Watch Established & Thermolag Barrier Installed HL-1861, Special Rept 1-91-007:on 910909 & 16,fire Barrier Assemblies Inoperable for More than 14 Days When Unsealed Drilled Hole & Unsealed Penetration Discovered.Caused by Personnel Error.Hole Repaired & Penetration Sealed1991-10-0808 October 1991 Special Rept 1-91-007:on 910909 & 16,fire Barrier Assemblies Inoperable for More than 14 Days When Unsealed Drilled Hole & Unsealed Penetration Discovered.Caused by Personnel Error.Hole Repaired & Penetration Sealed ML20082B7301991-07-0909 July 1991 Special Rept:On 910515 & 0613,cable Penetration Seals Discovered Inoperable & Left in Untested Configuration. Caused by Personnel Error.Hourly Fire Watch Initiated & Penetrations Covered W/Thermolag Fire Barrier Matl HL-1691, Special Rept:On 910526,fixed Water Spray Nozzles Inoperable for Longer than 14 Days Identified During Insp of Fire Sprinkler Sys.Cause Indeterminate.Conduits Routed Away from Vicinity of Spray Nozzles1991-06-21021 June 1991 Special Rept:On 910526,fixed Water Spray Nozzles Inoperable for Longer than 14 Days Identified During Insp of Fire Sprinkler Sys.Cause Indeterminate.Conduits Routed Away from Vicinity of Spray Nozzles ML20079B9181991-06-14014 June 1991 Special Rept 1-91-005:on 910515,fire Barrier Assemblies Inoperable for Longer than 14 Days.Caused by Personnel Error.Penetration Declared Inoperable & Required Hourly Fire Watch Established HL-1674, Special Rept 2-91-001:on 910320 & 0401,fire-rated Assemblies Inoperable for More than 14 Days Due to Reloading of Reactor Core & Planned Maint Activity,Respectively.Hourly Fire Watch Initiated & Set Room Walls Reinstalled1991-06-0707 June 1991 Special Rept 2-91-001:on 910320 & 0401,fire-rated Assemblies Inoperable for More than 14 Days Due to Reloading of Reactor Core & Planned Maint Activity,Respectively.Hourly Fire Watch Initiated & Set Room Walls Reinstalled HL-1667, Special Rept 1-91-004:on 910502 & 06,listed battery-powered Emergency Lighting Units Inoperable for More than 72 H. Affected battery-powered Emergency Lighting Units Verified Operable by Performing Monthly Insp1991-06-0606 June 1991 Special Rept 1-91-004:on 910502 & 06,listed battery-powered Emergency Lighting Units Inoperable for More than 72 H. Affected battery-powered Emergency Lighting Units Verified Operable by Performing Monthly Insp HL-1649, Special Rept:On 910420,fire Barrier Assemblies Inoperable for Period Longer than 14 Days Discovered During Insp.Caused by Personnel Error.Penetrations 2Z43-H66OC & 2Z43-HO27C Resealed & Partially Drilled Hole Repaired1991-05-21021 May 1991 Special Rept:On 910420,fire Barrier Assemblies Inoperable for Period Longer than 14 Days Discovered During Insp.Caused by Personnel Error.Penetrations 2Z43-H66OC & 2Z43-HO27C Resealed & Partially Drilled Hole Repaired HL-1547, Special Rept 1-91-003:on 910318,during Monthly Insp of Fire Door 1L48-1C22,discovered That Door Inoperable for More than 14 Days Due to Worn Hinges,Plates & Shins.Caused by Normal Wear.Fire Watch Established & New Door Ordered1991-04-0202 April 1991 Special Rept 1-91-003:on 910318,during Monthly Insp of Fire Door 1L48-1C22,discovered That Door Inoperable for More than 14 Days Due to Worn Hinges,Plates & Shins.Caused by Normal Wear.Fire Watch Established & New Door Ordered HL-1542, Special Rept:On 910301,battery-powered Emergency Lighting Units Inoperable for Period Greater than 72 H.Caused by Personnel Error.Units Restored to Operable Status on 910302 & Surveillance Procedure 42SV-FPX-003-0S Revised1991-03-25025 March 1991 Special Rept:On 910301,battery-powered Emergency Lighting Units Inoperable for Period Greater than 72 H.Caused by Personnel Error.Units Restored to Operable Status on 910302 & Surveillance Procedure 42SV-FPX-003-0S Revised HL-1492, Ro:On 910214,potential Malfunction of SRVs Suspected. Caused by Turbine Trip & Reactor Scram Valve Testing. Investigation of Malfunction Planned1991-02-15015 February 1991 Ro:On 910214,potential Malfunction of SRVs Suspected. Caused by Turbine Trip & Reactor Scram Valve Testing. Investigation of Malfunction Planned HL-1470, Special Rept:On 901119,discrepancy Noted in Number of SRM & IRM Detectors During Inventory.Caused by Inadequate Recordkeeping Controls.Responsibility for Control & Accountability of Detectors Returned to Reactor Engineering1991-02-14014 February 1991 Special Rept:On 901119,discrepancy Noted in Number of SRM & IRM Detectors During Inventory.Caused by Inadequate Recordkeeping Controls.Responsibility for Control & Accountability of Detectors Returned to Reactor Engineering HL-1488, Ro:On 910212,potential Malfunction of SRVs Suspected.Caused by Turbine Trip & Re Actor Scram.Investigation of Malfunction Planned1991-02-13013 February 1991 Ro:On 910212,potential Malfunction of SRVs Suspected.Caused by Turbine Trip & Re Actor Scram.Investigation of Malfunction Planned ML20062G3641990-11-16016 November 1990 Special Rept:On 901108,reactor Bldg Ventilation Accident Range Radiation Monitor Inoperable for More than Seven Days. Caused by Component Failure.Reactor Bldg Accident Range Radiation Monitor Declared Inoperable HL-1353, Special Rept 2-90-003 Re fire-rated Assemblies Inoperable W/O Hourly Fire Watch Maintained.Caused by Personnel Error. License Condition 2-90-332 Initiated1990-11-15015 November 1990 Special Rept 2-90-003 Re fire-rated Assemblies Inoperable W/O Hourly Fire Watch Maintained.Caused by Personnel Error. License Condition 2-90-332 Initiated ML20059G3131990-09-0404 September 1990 Special Rept 90-004:on 900810,fire-rated Assembly Inoperable for Longer than 14 Days.Caused by Component Failure.Hourly Fire Watch Maintained & Fire Damper Replaced HL-1259, Special Rept 90-001:on 900730,fire-rated Assembly Declared Inoperable for More than 14 Days.Caused by Personnel Error. Hourly Fire Watch Initiated1990-08-29029 August 1990 Special Rept 90-001:on 900730,fire-rated Assembly Declared Inoperable for More than 14 Days.Caused by Personnel Error. Hourly Fire Watch Initiated ML20246J2841989-08-28028 August 1989 Special Rept 1-89-002:on 890803,power Cables to Battery Powered Emergency Lighting Units Disconnected.Caused by Plant Mod Activity Which Resulted in Inoperability of Several Battery Powered Emergency Lighting Units for 72 H ML20246F7541989-07-0505 July 1989 Special Rept 89-004:on 890525,sealing Devices for Penetrations in 3 H fire-rated East Wall Breached in Excess of 14 Days.Breach Necessitated by Scheduled Work Activities. Penetrations Sealed,Inspected & Declared Operable on 890608 ML20244B8061989-06-0808 June 1989 Special Rept 89-003:on 890509,smoke Detectors Left Inoperable W/O Compensatory Measures Being Taken.Caused by Failure to Reset Alarm at Slave Panel.Smoke Detectors in Battery Rooms Replaced W/Heat Detectors ML20247K4121989-05-24024 May 1989 Special Rept 89-002:on 890414,signal from Triaxial Time History Accelerograph Located Inside Drywell Determined to Contain Excessive Amount of Noise & Declared Inoperable for More than 30 Days.Cause of Event Not Determined ML20236B5071989-03-14014 March 1989 Special Rept 89-001:on 890216,fire Door Not Restored to Operable Status within 14 Days.Caused by Use of Structural Grouting Procedure Instead of Cosmetic Grouting Procedure. Grouting Placed Underneath Door & Individuals Counseled ML20235U8201989-02-28028 February 1989 Special Rept 89-001:on 890120,fire-rated Assemblies Inoperable for More than 14 Days.Caused by Inadequate Design.Limiting Condition for Operation Established for Each Identified Deficiencies ML20196F0181988-12-0707 December 1988 Special Rept 88-008:on 881101,fire Watch Not Established & Fire Rated Assembly Not Restored to Operable Condition within 14 Days as Required.Event Had No Adverse Impact on Plant Safety.Personnel Counseled & Cable Tray Encl Modified ML20196E4721988-12-0202 December 1988 Special Rept 88-005:on 881105,emergency Light Inoperable for Longer than 24 H Period.Caused by Depleted/Dead Battery. Maint Personnel Replaced Dead Battery Under MWO-2-88-4353 ML20151F0081988-07-21021 July 1988 Special Rept 88-005:on 880505,fire Wrap Not Installed on Cable Raceways.Caused by Inadequate Guidance Re Application of App R Requirements.Limiting Condition for Operation Established for Each Individual Raceways ML20196C2871988-06-22022 June 1988 Special Rept 88-004:on 880523,determined That Fire Doors W/ Automatic hold-open & Release Mechanisms Were Not Being Verified to Be Free of Obstructions at Least Once Per 24 H as Required.Caused by Inadequate Administrative Controls 1998-07-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D3061999-10-13013 October 1999 SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation HL-5845, Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program HL-5836, Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With ML20210J9631999-08-0202 August 1999 SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9271999-08-0202 August 1999 SER Finds That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant,Susceptible to Pressure Locking or Thermal Binding HL-5818, Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5805, Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20207E7631999-06-0303 June 1999 Safety Evaluation Concluding That Licensee Proposed Alternative to Use Code Case N-509 Contained in RR-4 Provides Acceptable Level of Quality & Safety.Considers Rev 2 to RR-4 & RR-6 Acceptable HL-5795, Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Ehnp Units 1 & 2. with ML20206G1691999-05-0404 May 1999 SER Approving Requirements of Istb 4.6.2(b) Pursuant to 10CFR50.55a(a)(3)(ii) HL-5784, Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5766, Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20207M1891999-03-11011 March 1999 SER Accepting Relief Request for Authorization of Alternative Reactor Pressure Vessel Exam for Circumferential Weld HL-5755, Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20206P6981999-01-0707 January 1999 Ehnp Intake Structure Licensing Rept HL-5726, Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20196J4931998-12-0707 December 1998 Safety Evaluation Accepting Proposed Alternatives in Relief Requests RR-V-12,RR-V-15,RR-P-15,RR-V-7,RR-V-12,RR-V-14 & RR-V-15 HL-5714, Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With HL-5706, Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Hatch Nuclear Plant Units 1 & 2.With ML20155B6121998-10-28028 October 1998 Safety Evaluation of TR SNCH-9501, BWR Steady State & Transient Analysis Methods Benchmarking Topical Rept. Rept Acceptable HL-5691, Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Ei Hatch Nuclear Plant,Units 1 & 2.With ML20153G2481998-09-24024 September 1998 SE Concluding That Licensee Implementation Program to Resolve USI A-46 at Plant Adequately Addressed Purpose of 10CFR50.54(f) Request ML20239A2531998-09-0303 September 1998 SER Accepting Licensee Request for Relief Numbers RR-17 & RR-18 for Edwin I Hatch Nuclear Plant,Units 1 & 2.Technical Ltr Rept on Third 10-year Interval ISI Request for Reliefs for Plant,Units 1 & 2 Encl HL-5675, Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20238F7131998-08-31031 August 1998 9,change 2 to QAP 1.0, Organization HL-5667, Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5657, Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures1998-07-30030 July 1998 Ro:On 980626,noted That Pami Channels Had Been Inoperable for More than Thirty Days.Cause Indeterminate.Licensee Will Replace Automatic Function W/Five Other Qualified Pamis of Like Kind in Drywell & Revised Procedures ML20236W3441998-07-30030 July 1998 Safety Evaluation Accepting Relief Requests for Second 10-yr ISI for Plant,Units 1 & 2 ML20236V5191998-07-28028 July 1998 Safety Evaluation Accepting Proposed License Amend Power Uprate Review ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20236L1821998-07-0707 July 1998 Safety Evaluation Accepting 980428 Proposed Alternative to ASME Boiler & Pressure Vessel Code,Section Xi,Repair & Replacement Requirements Under 10CFR50.55a(a)(3) HL-5653, Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5640, Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20248B8651998-05-15015 May 1998 Quadrennial Simulator Certification Rept HL-5628, Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant1998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Ei Hatch Nuclear Plant HL-5604, Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20216B2711998-02-28028 February 1998 Extended Power Uprate Safety Analysis Rept for Ei Hatch Plant,Units 1 & 2 HL-5585, Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5571, Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 11998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Edwin I Hatch Nuclear Plant,Unit 1 HL-5551, Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Ei Hatch Nuclear Plant,Units 1 & 2 ML20199B0561997-12-31031 December 1997 Rev 0 GE-NE-B13-01869-122, Jet Pump Riser Weld Flaw Evaluation Handbook for Hatch Unit 1 HL-5581, Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 21997-12-31031 December 1997 Annual Operating Rept for 1997, for Ei Hatch Nuclear Plant Units 1 & 2 HL-5533, Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 21997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Ei Hatch Nuclear Plant,Units 1 & 2 HL-5514, Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 21997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20212A1981997-10-16016 October 1997 Safety Evaluation Denying Licensee Request for Relief from Implementation of 10CFR50.55a Requirements Re Use of 1992 Edition of ASME Code Section XI for ISI of Containments ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H5311997-10-0101 October 1997 Rev 2 to Unit 1,Cycle 17 Colr ML20211H5251997-10-0101 October 1997 Rev 3 to Unit 1,Cycle 17 Colr 1999-09-30
[Table view] |
Text
cwga Nw cre; any 40 lrN0f fWSS Ci'"tOf PMh'VW/
! n,st ow su u>n o . Batmr r.;*em. Nahyrue 3'; et i
1.,pi.,# cm m m9 m
a u a m..m Georgia Power vo rmsew Nam , , , , ,
Hatn Pacgt '
HL-1967 002648 December 5, 1991 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C. 2t.,555
, PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE DPR-57 SPECIAL REPORT 1-91-010 MAIN STACK POST-ACCIDENT RANGE MONITORING SYSTEM TN0PERABLE FOR A PERIOD GREATER THAN 7 D M Gentlemen:
In accordance with Plant i;atch Unit 1 Technical Specifications Table 3.2-11 and Unit 2 Technical SP ecificat uns Table 3.3.6.4-1, Georgia Power Company is submitting the enclused Spe:iai Report concerning tt, main stack post accident effluent monitoring syste... '. hich was inoperable for a period greater than 7 days.
Sincerely,
[
g'fd. T. Beckham, Jr, OCV/cr
Enclosure:
Special Report 1-91-010 cc: .0fornia Power Compa_y Mr. H. L. Sumner, General Manager - Nuclear Plant NORMS U.S. Nuclear Reaulatcry Commission. Washinator. D.C.
Mr. K. Jabbour, licensing Project Manager - Hatch ll.S. Nuclear Regulatory Commission. Realon II I . S. D Ebneter, Regional Administrator Mr. L. D. Wert, Senior Resident Inspector - Hatch 9112100247 911205 / 2.
ges Anoct oscop,y1 I
- g. -
/ .
i L. l
.. l ENCLOSURE PLANT HATCH - UNIT 1 NRC DOCKET 50-321 OPERATING LICENSE OPR-57 SPECIAL REPORT l-91-010 MAIN STACK POST-ACCIDENT RANGE MONITORING SYSTEM IN0PERABLE FOR GREATER THAN 7 DAYS A. REQUIREMENT FOR REPORI This_ report is required ner Unit 1 Technical Specifications Table 3.2-11,
-Footnote (g) and Unit 2 Technical Specifications Table 3.3.6.4-1, footnote (b). Specifically, the noted specifications require that in the event the Main Stack Post-Accident Effluent Monitoring System is inoperable for greater than seven days a Special Report is required to be submitted within 14 days of the_ event. In this event, the Main Stack Post-Accident Effluent Monitoring System wes inoperable for greater than seven days, thus, this Special Report is required.
B. UNIT STATUS Al TIME =OF EVENT On 11/21/91, at_2215 CST, Unit I was in Cold Shutdown and Unit 2 was in the
_Run mde at 2436 CHWT (100 percent of rated thermal power).
C. DESCRIPTION OF EVENT On 11/21/91, at 2215 CST, during a _ surveillance of Main Control Regn instrument panels, a licensed operator noted _that the blue pen of Post-Accident Effluent Monitoring System recorder 1Dll-R631 was spiking upscale ' at a _ regular interval. The blue pen provides - indication and recording capability for the Main Stack radioactive gaseous effluents. The Main - Stack itself_ provides an elevated release path for both Unit 1 and Unit 2 radioactive gaseous effluents.
-The Main' Stack Post-Accident Effluent Monitoring System was subsequently declared inoperabic. The aforementioned Unit 1 and Unit 2 Technical Specifications foo_tnotes require that the ystem'be returned to_ service within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the pre-planned alternate method for monio:. ring the Main Stack post-accident gaseous effluents be initiated end that a Srecial Report be submitted to the NRC if the system is out of service for greater than seven days. Limiting Cor.ditions for Operation (LCO) 1-91-783 and 2-91-762
- were init:ated to ensure compliance with the specifications.
Instrument _ and Controls (l&C) technicians investigated the condition and found two problems': 1) a failed flow transducer which monitors sample flow to the system detectors and alarms on a low flow condition, and 2) the system computer being unresponsive to keyboard input. The computer was shutdown and then restarted. Several of the alarms cleared and within a i.
002648 HL-1967 E-1
s ENCLOSURE (Continued)
SPECIAL REPORT 1-91-010 MAIN STACK POST-ACCIDENT RANGE MONITORING SYSTEM IN0PERABLE FOR GREATER THAN 7 DAYS short period of time the computer anomaly cleared itself and responded to keyboard input. The computer was subsequently reprogrammed and returned to service on.11/23/91. The spiking phenomena did not recur when the syrtem was placed into service. The system was still considered inoperable because s repair of the flow transducer was awaiting replacement parts. Consequently, it was decided to observe the system over the next several days to ensure the spiking phenomena did not recur.
Seventy-two hours into the event, the system had not been returned to operable status. Consequently, the pre-planned alternate method for ,
monitoring the Main Stack effluents was initiated. The pre-planned alternato method for monitoring gaseous releases via the Main Stack consists of using the Main Stack Normal Range Monitoring System in conjunction with performing grab samples. Specifically, the normal range monitoring system is used until it indicates offscale at which time periodic grab samples are to be taken and analyzed for activity. Thus, at 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> into the event, the normal range monitoring system had been verified as being operable.
A replacement flow transducer was not readily available since the particular model in use was no longer being manufactured. A spare transducer was located at anather utility and provisions were made to send it overnight to the site via a commerciel shipping company. Unfortunately, the part was lost in shipment and, thus, a second transducer had to be obtained ftom the same utility. The part arrived on site the morning of 11/28/91. The transducer was replaced and satisfactorily furctionally tested per procedure 57SV-Dil-O'8 OS, "Kaman Accident Range Monitor FT&c." The system was then returned to operable status at 2205 . CST, on 11/28/91 - ten minutes before '
the_seven day LC0 expired. The LCOs were subsequently terminated. Since it was apparent that the system had not been inoperable for greater than seven days, a Special Report was not required.
Approximately three hours after the system was returned to operable status, however, the recorder began spiking again. The system again was removed from service and declared inoperable. Two new LCOs (LCOs 1-91-797 and 2-914-762) were initiated. Since the spiking problem which initially occurred on 11/21/91 apparently had not been repaired, the LCOs were bacedated to 11/21/91 which meant the system had been inoperable for greater than seven days, requiring the issuance of a Special Report.
I&C technicians again investigated the cor.dition and'found a bad computer central processing-unit _(CPU) board. The CPU board was replaced and the system was returned to service. A functional test was satisfactorily
, completed at which time the system was declared operable. The LCOs were subsequently terminated at 1600 CST, on 11/30/91.
002648 HL-1957 E-2
.t-ENCLOSURE (Continued)
SPECIAL REPORT 1-91-010 MAIN STACK POST-ACCIDENT RANGE MONITORING SYSTEM IMfERABLE FOR GREATER THAN 7 DAYS D. CAUSE OF EVENT The cause of the event was failed components. Specifically, the system flow transducer -and the system computer CPU board failed. The flow transducer failure resulted in the system low flow alarm being inoperable. The CPU board failure was intermittent resulting in the spiking condition randomly appearing and disappearing. As a consequence of this failure made, plant personnel were led to believe that the system was functioning properly since the condition did not recur between 11/23/91 and 11/28/91. However, after the system was declared operable, on 11/29/91, the condition reappeared.
E. ANALYSIS OF EVENT The Main Stack Post-Accident Effluent Monitoring Sy:. tem provides information regarding radioactive gaseous release rates via the plant Main Stack in a post-accident Otuation, The system consists of two Geiger-Mueller detectors: one for measuring mid-range noble gas activity and one for measuring high range noble gas activity. The system is normally on standby and is automatically initiated when a prescribed gaseous radioactivity limit is exceeded as measured by the Main Stack Normal Range Monitoring System.
Upon- initiation, a- sample pump- starts and a continuous sample of Main Stack effluent . is routed to the post-accident system detectors. The gaseous radioactivity, as measured by the detectors, is then displayed on recorder IDll-R631 in the Main Control Room. The pre-pianned alternate method for monitoring gaseous release via the Main Stack consists of using the normal range system in conjunction with performing grab samples. Specifically, the normal range monitoring system is used until-it indicates offscale at which time periodic grab samples are to be taken and samples-analyzed for activity.
In this event, the Main Stack Post-Accident Effluent Monitoring System was
-inoperable for nine days. During this time, the Main Stack Normal Range Mnnitoring System was operable -and showed no unusual radioactive gaseous releases via the Main Stack. Had a Design Basis Event occurred and resulted in radioactive gaseous releases exceeding the range of the Main Stack Normal Range Monitoring System, grab sampling and analysis in accordance with procedure 64CH-SAM-005-0S, " Gaseous Ef fluents: Sampling," would have been initiated providing Main Control Room personnel with the necessary information regarding radioactive gaseous releases.
002648 HL-1567 E-3
ENCLOSURE (Continued)
SPECIAL REPORT l-91-010 MAIN STACK POST-ACCIDENT RANGE MONITORING SYSTEM INOPERABLE LOR GREATER THAN 7 DAYS Based on this information, it is concluded that this event had no adverse impact on nucleir safety. This analysis applies to all operating conditions, F. CORRECTIVE ACTIONS The pre-planned alternate method for monitoring the Main Stack ef fluent releases was initiated within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> of the monitoring system becoming inoperable.
The computer CPU board and the flow transducer were replaced.
lhe system was satisfactorily functionally tested per procedure 575V-Dil-018-0S and returned to operable status by 1600 CST, on 11/30/91.
I h
002648 HL-1967 E-4 ,
_ - - - - - - _ _ - - _