Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045C5031993-06-14014 June 1993 Special Rept 93-005:on 921215,periodic Testing of Heat & Smoke Detection Sys Inappropriately Suspended Based on Belief That Sys Declared Inoperable on 920819 & Appropriate Compensatory Measures in Place.Smoke Detectors Tested ML20044G4901993-05-25025 May 1993 Special Rept 93-004:on 930422,fire Barrier Penetration Seal Between Turbine Bldg 272-ft Elevation & West Cable Tunnel Opened for More than 7 Days.On 930429,penetration Did Not Meet Fill Criteria.Penetration Reworked & Sealed ML20042H0441990-05-11011 May 1990 Ro:On 900412,fire Protection Sys 2 Multiplexer Trouble Alarm Received in Control Room & Would Not Clear,Resulting in Inoperability of Sys for More than 14 Days.Hourly Fire Patrol Established & Power Supply for Multiplexer Replaced ML20012F3541990-04-0202 April 1990 Special Rept:On 900302,diesel engine-driven Fire Pump 76P-1 Out of Svc for Approx 7 Days & 14 H Due to Failure & Replacement of Starter Motor.On 900315,fire Pump Failed to Start.Starting Sys Battery Replaced ML19331C7951980-08-14014 August 1980 RO 80-163:on 800814 Following Plant Startup,Both Trains of Standby Gas Treatment Found Inoperable.Caused by Water Accumulation in Discharge Line as Result of 2-inch Drain Line from 24-inch to Radwaste Sys Being Blocked ML19309H8801980-05-14014 May 1980 Ro:On 800513,instantaneous Release Rate of Halogens & Particulates w/half-lives Greater than 8 Days Exceeded Ets. Caused by Evolution of Radioactive Iodine from Water in Reactor Head Cavity,Following Filling for Refueling ML19270H7611979-12-0606 December 1979 RO-79-217:on 791205,during Reanalysis of Pipe Support, Support Found to Be Inoperative Per Criteria of 790814 Ltr. Addl Analysis Showed Associated Piping to Be Inoperative. Caused by Thermal Growth.Mods to Be Completed ML19322A5811979-11-0202 November 1979 RO-79-197:on 791102,A/E Informed Util That Support H11-8 in Standby Liquid Control Sys,Support H66-33 in Containment Vent & Purge Sys & Support H76-61 in Fire Protection Sys, Found Inoperative During Pipe Stress Reanalysis ML19322A5721979-10-29029 October 1979 RO 79-190:on 791029,A/E Indicated That Three Piping Supports Associated W/Rhr Sys B & One on RHR Svc Water Sys B Were Inoperative.Supports Upgraded & Acceptable.Support N10-145 Being Upgraded ML19322A5801979-10-26026 October 1979 RO-79-187:on 791025,pipe Stress Reanalysis Indicated That Five Supports on Emergency Svc Water Return Piping & One Support on Standby Gas Treatment Sys Were Inoperative. Supports Upgraded to Accept Increased Loads ML19322B8881979-10-24024 October 1979 Ro:On 791024,A/E Informed Util That Pipe Stress Reanalysis Indicated Pipe Support to Be Inoperative Per NRC Guidelines. Support Will Be Upgraded to Accept Increased Loads from SHOCK-III Analysis ML19262A1411979-10-10010 October 1979 RO-79-079:on 791010,pipe Support H15-7 Determined to Be Inoperable,Rendering Sys Inoperable.Support Upgraded ML19254E1401979-10-0505 October 1979 RO 79-164:on 791004,pipe Stress Reanalysis Showed One Piping Run Inoperable.Pipe Support on Return Piping from Cross Tie Into Reactor Bldg Closed Loop Cooling Sys & Has No Safety Significance.Hanger Will Be Repaired in Seven Days ML19322A3721979-09-28028 September 1979 RO 79-159:on 790927,hangers on Discharge of Core Spray Pump B & Reactor Bldg Closed Hoop Heat Exchanger Found Inoperable,Causing Sys to Be Inoperable Under Earthquake Conditions.Hangers Will Be Repaired within seven-day Period ML19322A4751979-09-28028 September 1979 RO 79-159:on 790927,hangers on Discharge of Core Spray Pump B & Reactor Bldg Closed Loop Heat Exchangers Found Inoperable Under Earthquake Condition.Cause Not Stated. Hangers Will Be Repaired ML19322A3691979-09-26026 September 1979 RO-79-158:on 790926,informed by A/E That Addl HPCI & Automatic Depressurization Sys Cabling Affecting Control of HPCI Inboard Steam Supply Isolation Valve Did Not Have Required Separation Criteria,Creating Potential Fire Hazard ML19253A9781979-08-30030 August 1979 RO 79-046:on 790830,noted That Routing of HPCI Sys Steam Isolation Valve Control Cable & Thermocouple Temp Detector Cable for HPCI Sys Not Sufficiently Separate from Control Cables of Depressurization Sys ML19208B2351979-08-30030 August 1979 RO 79-118:on 790830,no Separation Existed Between HPCI Sys Steam Isolation Valve Control Cable & Thermocouple Detector Cabling & Control Cables.Caused by Vague Design Requirements.Presently Rerouting Cable ML19259B9491978-01-0505 January 1978 RO 78-01 on 780105:inlet Piping to Safety Relief Valves Was 6-inch Double Extra Strong,Causing Inside Diameter to Be Slightly Smaller than Throat Diameter of Valve.Vendor Evaluation Rept Due in Feb 1993-06-14
[Table view] Category:LER)
MONTHYEARML20045C5031993-06-14014 June 1993 Special Rept 93-005:on 921215,periodic Testing of Heat & Smoke Detection Sys Inappropriately Suspended Based on Belief That Sys Declared Inoperable on 920819 & Appropriate Compensatory Measures in Place.Smoke Detectors Tested ML20044G4901993-05-25025 May 1993 Special Rept 93-004:on 930422,fire Barrier Penetration Seal Between Turbine Bldg 272-ft Elevation & West Cable Tunnel Opened for More than 7 Days.On 930429,penetration Did Not Meet Fill Criteria.Penetration Reworked & Sealed ML20042H0441990-05-11011 May 1990 Ro:On 900412,fire Protection Sys 2 Multiplexer Trouble Alarm Received in Control Room & Would Not Clear,Resulting in Inoperability of Sys for More than 14 Days.Hourly Fire Patrol Established & Power Supply for Multiplexer Replaced ML20012F3541990-04-0202 April 1990 Special Rept:On 900302,diesel engine-driven Fire Pump 76P-1 Out of Svc for Approx 7 Days & 14 H Due to Failure & Replacement of Starter Motor.On 900315,fire Pump Failed to Start.Starting Sys Battery Replaced ML19331C7951980-08-14014 August 1980 RO 80-163:on 800814 Following Plant Startup,Both Trains of Standby Gas Treatment Found Inoperable.Caused by Water Accumulation in Discharge Line as Result of 2-inch Drain Line from 24-inch to Radwaste Sys Being Blocked ML19309H8801980-05-14014 May 1980 Ro:On 800513,instantaneous Release Rate of Halogens & Particulates w/half-lives Greater than 8 Days Exceeded Ets. Caused by Evolution of Radioactive Iodine from Water in Reactor Head Cavity,Following Filling for Refueling ML19270H7611979-12-0606 December 1979 RO-79-217:on 791205,during Reanalysis of Pipe Support, Support Found to Be Inoperative Per Criteria of 790814 Ltr. Addl Analysis Showed Associated Piping to Be Inoperative. Caused by Thermal Growth.Mods to Be Completed ML19322A5811979-11-0202 November 1979 RO-79-197:on 791102,A/E Informed Util That Support H11-8 in Standby Liquid Control Sys,Support H66-33 in Containment Vent & Purge Sys & Support H76-61 in Fire Protection Sys, Found Inoperative During Pipe Stress Reanalysis ML19322A5721979-10-29029 October 1979 RO 79-190:on 791029,A/E Indicated That Three Piping Supports Associated W/Rhr Sys B & One on RHR Svc Water Sys B Were Inoperative.Supports Upgraded & Acceptable.Support N10-145 Being Upgraded ML19322A5801979-10-26026 October 1979 RO-79-187:on 791025,pipe Stress Reanalysis Indicated That Five Supports on Emergency Svc Water Return Piping & One Support on Standby Gas Treatment Sys Were Inoperative. Supports Upgraded to Accept Increased Loads ML19322B8881979-10-24024 October 1979 Ro:On 791024,A/E Informed Util That Pipe Stress Reanalysis Indicated Pipe Support to Be Inoperative Per NRC Guidelines. Support Will Be Upgraded to Accept Increased Loads from SHOCK-III Analysis ML19262A1411979-10-10010 October 1979 RO-79-079:on 791010,pipe Support H15-7 Determined to Be Inoperable,Rendering Sys Inoperable.Support Upgraded ML19254E1401979-10-0505 October 1979 RO 79-164:on 791004,pipe Stress Reanalysis Showed One Piping Run Inoperable.Pipe Support on Return Piping from Cross Tie Into Reactor Bldg Closed Loop Cooling Sys & Has No Safety Significance.Hanger Will Be Repaired in Seven Days ML19322A3721979-09-28028 September 1979 RO 79-159:on 790927,hangers on Discharge of Core Spray Pump B & Reactor Bldg Closed Hoop Heat Exchanger Found Inoperable,Causing Sys to Be Inoperable Under Earthquake Conditions.Hangers Will Be Repaired within seven-day Period ML19322A4751979-09-28028 September 1979 RO 79-159:on 790927,hangers on Discharge of Core Spray Pump B & Reactor Bldg Closed Loop Heat Exchangers Found Inoperable Under Earthquake Condition.Cause Not Stated. Hangers Will Be Repaired ML19322A3691979-09-26026 September 1979 RO-79-158:on 790926,informed by A/E That Addl HPCI & Automatic Depressurization Sys Cabling Affecting Control of HPCI Inboard Steam Supply Isolation Valve Did Not Have Required Separation Criteria,Creating Potential Fire Hazard ML19253A9781979-08-30030 August 1979 RO 79-046:on 790830,noted That Routing of HPCI Sys Steam Isolation Valve Control Cable & Thermocouple Temp Detector Cable for HPCI Sys Not Sufficiently Separate from Control Cables of Depressurization Sys ML19208B2351979-08-30030 August 1979 RO 79-118:on 790830,no Separation Existed Between HPCI Sys Steam Isolation Valve Control Cable & Thermocouple Detector Cabling & Control Cables.Caused by Vague Design Requirements.Presently Rerouting Cable ML19259B9491978-01-0505 January 1978 RO 78-01 on 780105:inlet Piping to Safety Relief Valves Was 6-inch Double Extra Strong,Causing Inside Diameter to Be Slightly Smaller than Throat Diameter of Valve.Vendor Evaluation Rept Due in Feb 1993-06-14
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARJAFP-99-0277, Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 Fpr Ja FitzPatrick Nuclear Power Plant.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data JAFP-99-0261, Monthly Operating Rept for Aug 1999 for Jafnpp.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Jafnpp.With JAFP-99-0236, Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Ja FitzPatrick Npp. with ML20216D9541999-07-28028 July 1999 Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii) ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept JAFP-99-0211, Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0175, Annual Summary of Changes,Tests & Experiments for 1997/1998. with1999-06-0202 June 1999 Annual Summary of Changes,Tests & Experiments for 1997/1998. with JAFP-99-0181, Monthly Operating Rept for May 1999 for Jafnpp.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Jafnpp.With JAFP-99-0166, Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Ja FitzPatrick Nuclear Plant.With JAFP-99-0142, Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Ja FitzPatrick Nuclear Power Plant.With JAFP-99-0092, Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Ja FitzPatrick Nuclear Power Plant.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20202J0891999-02-0303 February 1999 Safety Evaluation Accepting Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc JAFP-99-0011, Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20198F9991998-12-0404 December 1998 Assessment of Licensing Basis for Use of Containment Overpressure Credit for Net Positive Suction Head Analyses Power Authority of State of New York,James a Fitzpatrick Nuclear Power Plant ML20196J3501998-12-0404 December 1998 SER Accepting License Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves JAFP-98-0396, Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Ja FitzPatrick Npp. with ML20196F9251998-11-25025 November 1998 Safety Evaluation Re Thrid 10-year Interval Inservice Insp Program Relief Requests for Plant ML20195J7521998-11-18018 November 1998 Rev 7 to Jaf Colr ML20195K4211998-11-17017 November 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request VRR-05 Per 10CFR50.55a(a)(3)(i) & PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04 Per 10CFR50.55a(a)(3)(ii) ML20195E1051998-11-13013 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves, Issued 950817 ML20197G6221998-11-0606 November 1998 Non-proprietary Rev 7 to HI-971661, Licensing Rept for Reracking of Ja FitzPatrick Sfp ML20155H5321998-11-0303 November 1998 Safety Evaluation Authorizing Alternative to ASME Code Requirements for CRD Bolting ML20155H5801998-11-0303 November 1998 Safety Evaluation Authorizing Postponement of Beginning of Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) Re ASME Code,Section XI JAFP-98-0360, Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Ja FitzPatrick Nuclear Power Plant.With ML20155C2821998-10-30030 October 1998 Non-proprietary Rev 0 to GENE-187-30-1598 Np, CRD Bolting Flaw Evaluation for Ja FitzPatrick Nuclear Power Plant ML20154L6591998-10-14014 October 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Snubber Visual Inservice Exam Intervals & Sampling Rates Requirements Contained in ASME Code,Section Xi,Subsection Iwf,Article IWF-5000 JAFP-98-0322, Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Ja Fitzpatrick Nuclear Power Plant.With ML20153D2591998-09-21021 September 1998 SER Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement ML20153B5611998-09-0101 September 1998 Rev 1 to JAF-SE-98-013, RHR & Core Spray Suppression Pool Suction Strainer Replacement ML20151X6891998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Ja FitzPatrick Nuclear Power Plant ML20237E8361998-08-25025 August 1998 Rev 6 to Colr ML20237E9471998-08-0808 August 1998 Rev 6 to Colr JAFP-98-0264, Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Ja FitzPatrick Nuclear Plant ML20236X5881998-07-29029 July 1998 Safety Evaluation Supporting Amend 245 to License DPR-59 ML20236V8181998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief from Implementation of Requirements of 10CFR50.55a Related to Containment Repair & Replacement Activities for James a FitzPatrick Nuclear Power Plant ML20153B5781998-07-28028 July 1998 Rev 0 to JAF-SE-98-025, HPCI & RCIC Suppression Pool Suction Strainer Replacement ML20236X3831998-07-14014 July 1998 Rev 2 to JAF-RPT-MULTI-02671, Summary of Detailed Evaluation for NRC Generic Ltr 96-06 ML20154L9201998-07-10010 July 1998 SER Accepting Rev to Reactor Vessel Surveillance Capsule Withdrawal Schedule for James a Fitzpatrick Nuclear Power Plant JAFP-98-0222, Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0193, Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant1998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Ja FitzPatrick Nuclear Plant ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted JAFP-98-0168, Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant1998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Ja FitzPatrick Nuclear Power Plant JAFP-98-0128, Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Ja FitzPatrick Nuclear Power Plant ML20217A4631998-03-23023 March 1998 Safety Evaluation Accepting Use of Three Heats/Lots of Hot Rolled XM-19 Matl in Core Shroud Repair Assemblies Re Licenses DPR-16 & DPR-59,respectively JAFP-98-0091, Monthly Operating Rept for Feb 1998 for JAFNPP1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for JAFNPP ML20202G9081998-02-0606 February 1998 Safety Evaluation Re Amend to License DPR-59 to Revise TS Tables 3.2-2 & 4.2-2 JAFP-98-0058, Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Ja FitzPatrick Nuclear Power Plant 1999-09-30
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