05000333/LER-1999-008-01, :on 990910,HPCI Sys Was Declared Inoperable Due to Apparent Failure of Master Trip Unit (MTU) within HPCI Sys Automatice Isolation Logic.Subject MTU Was Replaced & HPCI Sys Was Returned to Operable Status.With1999-10-12012 October 1999
- on 990910,HPCI Sys Was Declared Inoperable Due to Apparent Failure of Master Trip Unit (MTU) within HPCI Sys Automatice Isolation Logic.Subject MTU Was Replaced & HPCI Sys Was Returned to Operable Status.With
ML20217A9931999-09-30030 September 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data
JAFP-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
ML20212E9761999-09-21021 September 1999
Safety Evaluation Supporting Amend 255 to License DPR-59
ML20212A7971999-09-13013 September 1999
Safety Evaluation Supporting Amend 254 to License DPR-59
05000333/LER-1998-015, :on 981211,identified Logic Sys Functional Test Inadequacies.Caused by Personnel error.Re-review of Surveillance Testing for EDG Sys to Ensure TS Surveillance Tests Adequate,Scheduled to Be Completed by Jan 15, 20001999-09-0808 September 1999
- on 981211,identified Logic Sys Functional Test Inadequacies.Caused by Personnel error.Re-review of Surveillance Testing for EDG Sys to Ensure TS Surveillance Tests Adequate,Scheduled to Be Completed by Jan 15, 2000
05000333/LER-1999-007-01, :on 990809,both a & B Division of CS Pump Start Interlock Relays Exceeded Values Required by Ts.Caused by Inappropriate as-left Calibr Tolerance for Time Delay Relays.Relays Were Immediately Recalibr.With1999-09-0808 September 1999
- on 990809,both a & B Division of CS Pump Start Interlock Relays Exceeded Values Required by Ts.Caused by Inappropriate as-left Calibr Tolerance for Time Delay Relays.Relays Were Immediately Recalibr.With
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
ML20210J0061999-07-30030 July 1999
Safety Evaluation Supporting Amend 253 to License DPR-59
ML20216D9541999-07-28028 July 1999
Safety Evaluation Authorizing Proposed Alternatives for Second 10-year Interval Pursuant to 10CFR50.55a(a)(3)(ii)
05000333/LER-1999-006-01, :on 990609,LCPI Mode of RHR Sys Was Inoperable. Caused by Loss of Automatic Startup Capability of RHR Pumps. Repaired Defective Fuse Contact & Conducted Equipment Failure Evaluation.With1999-07-0808 July 1999
- on 990609,LCPI Mode of RHR Sys Was Inoperable. Caused by Loss of Automatic Startup Capability of RHR Pumps. Repaired Defective Fuse Contact & Conducted Equipment Failure Evaluation.With
05000333/LER-1999-005-01, :on 990506,missed Surveillance Test Was Noted. Caused by Inoperable Containment Hydrogen/Oxygen Analyzer. Counseled Personnel Involved & Revised Procedures.With1999-07-0707 July 1999
- on 990506,missed Surveillance Test Was Noted. Caused by Inoperable Containment Hydrogen/Oxygen Analyzer. Counseled Personnel Involved & Revised Procedures.With
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
ML20196H8621999-06-30030 June 1999
NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept
05000333/LER-1999-004-01, :on 990403,two Electrical Leads in 09-30 Panel in Relay Room Were Found Unlanded.Caused by Inattention to Detail & Inadequate Process to Ensure Complete Protective Tag.Performed Extent of Condition Walkdowns.With1999-06-17017 June 1999
- on 990403,two Electrical Leads in 09-30 Panel in Relay Room Were Found Unlanded.Caused by Inattention to Detail & Inadequate Process to Ensure Complete Protective Tag.Performed Extent of Condition Walkdowns.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
05000333/LER-1999-002, :on 990113,discovered That Suppression Chamber RB Vacuum Breaker Isolation Valve Differential Pressure Switches Were Out of Tolerance Due to Incorrect Assumption in Calculation.Calibr Pressure Switches.With1999-05-13013 May 1999
- on 990113,discovered That Suppression Chamber RB Vacuum Breaker Isolation Valve Differential Pressure Switches Were Out of Tolerance Due to Incorrect Assumption in Calculation.Calibr Pressure Switches.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
ML20205N4041999-04-12012 April 1999
Safety Evaluation Supporting Amend 252 to License DPR-59
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
05000333/LER-1998-015, :on 981211,logic Sys Functional Test Inadequacies Were Noted.Caused by Personnel Error.Revised ST-9P, Functional Test of Breakers 10514 & 10516 EDG Logic Auxiliary Stationary Contact. with1999-03-0808 March 1999
- on 981211,logic Sys Functional Test Inadequacies Were Noted.Caused by Personnel Error.Revised ST-9P, Functional Test of Breakers 10514 & 10516 EDG Logic Auxiliary Stationary Contact. 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
ML20206U4851999-02-0808 February 1999
Safety Evaluation Supporting Amend 251 to License DPR-59
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
ML20199G9041999-01-12012 January 1999
Safety Evaluation Supporting Amend 250 to License DPR-59
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
ML20198R0241998-12-28028 December 1998
Safety Evaluation Supporting Amend 249 to License DPR-59
05000333/LER-1998-013, :on 981117,containment Leakage Rate Exceeds Authorized Limits,Was Determined.Caused by Valve Sealing Failure.Failed Valves Repaired & Retested Satisfactorily Prior to Plant Startup1998-12-17017 December 1998
- on 981117,containment Leakage Rate Exceeds Authorized Limits,Was Determined.Caused by Valve Sealing Failure.Failed Valves Repaired & Retested Satisfactorily Prior to Plant Startup
05000333/LER-1998-014, :on 981117,trip of RPS Power Supply & ESF Actuation Occurred.Caused by Relay Failure.Relay Was Replaced & Motor Was Restarted Satisfactorily.With1998-12-15015 December 1998
- on 981117,trip of RPS Power Supply & ESF Actuation Occurred.Caused by Relay Failure.Relay Was Replaced & Motor Was Restarted Satisfactorily.With
ML20198B5171998-12-11011 December 1998
Safety Evaluation Supporting Amend 248 to License DPR-59
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
05000333/LER-1998-012, :on 981104,failure to Meet Primary Containment Leakage Rate Testing Program Requirements Was Noted.Caused by Deficient Test Procedures.Leak Rate Test Procedures Were Revised & Testing Was Completed.With1998-12-0404 December 1998
- on 981104,failure to Meet Primary Containment Leakage Rate Testing Program Requirements Was Noted.Caused by Deficient Test Procedures.Leak Rate Test Procedures Were Revised & Testing Was Completed.With
ML20196J6201998-12-0101 December 1998
Safety Evaluation Supporting Amend 247 to License DPR-59
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
ML20196G0181998-11-25025 November 1998
Safety Evaluation Supporting Amend 246 to License DPR-59
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
05000333/LER-1998-011, :on 980929,failure to Meet Drywell Continuous Atmosphere Monitoring Sys TS Surveillance Test Requirements Were Noted.Caused by Deficient Tp.Declared Both Channels of CAM Sys Inoperable.With1998-10-27027 October 1998
- on 980929,failure to Meet Drywell Continuous Atmosphere Monitoring Sys TS Surveillance Test Requirements Were Noted.Caused by Deficient Tp.Declared Both Channels of CAM Sys Inoperable.With