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| | document report number = LER-81-059-03X, LER-81-59-3X, NUDOCS 8206110137 | | | document report number = LER-81-059-03X, LER-81-59-3X, NUDOCS 8206110137 |
| | package number = ML20054E363 | | | package number = ML20054E363 |
| | document type = LICENSEE EVENT REPORT (SEE ALSO AO,RO), TEXT-SAFETY REPORT | | | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT |
| | page count = 1 | | | page count = 1 |
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Revision as of 15:39, 15 March 2020
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000333/LER-1993-0171993-08-30030 August 1993 LER 93-017-00:on 930729,declared APRM Downscale,Companion IRM Upscale Inoperable Due to Misinterpretation of Sr. Initiated Plant Shutdown & Declared Unusual Event Until Trip Was corrected.W/930830 Ltr 05000333/LER-1993-0161993-08-23023 August 1993 LER 93-016-00:on 930722,missed Source Check of Radwaste Discharge Monitor Prior to Discharge of Waste Sample Tank a Due to Failure to Follow Procedures.Performed Source Check & Counseled Involved indiviuals.W/930823 Ltr 05000333/LER-1991-0321993-05-0101 May 1993 LER 91-032-01:on 911226,determined That During Postulated CR Fire,Existing Design of Circulating Water Sys Intake Structure Deicing Heaters Outside Design Basis.Caused by Omission of Heaters in Analyses.Fsar revised.W/930501 Ltr 05000333/LER-1983-060, Updated LER 83-060/03X-1:on 831130,incorrect Motor Actuator Installed on RHR Suppression Pool Outboard Isolation Valve During Maint Activities.Cause Not Stated.Replacement Actuator Installed on 840119.W/840203 Ltr1984-02-0303 February 1984 Updated LER 83-060/03X-1:on 831130,incorrect Motor Actuator Installed on RHR Suppression Pool Outboard Isolation Valve During Maint Activities.Cause Not Stated.Replacement Actuator Installed on 840119.W/840203 Ltr ML20071G2541978-12-20020 December 1978 /03L-0 on 781122:during Shutdown & Surveillance Test,A Number of Battery Cells Were Found W/Specific Gravity &/Or Individual Cell Voltage Variations(High or Low) Greater than Allowed by Test Acceptance Criteria ML20071G1391978-12-18018 December 1978 /04X-1 on 781006:3rd Quarter Release of Halogens & Particulates Greater than Tech Specs.Caused by Steam Leaks & Fuel Pin Clad Performance ML20071F9161978-11-28028 November 1978 /03L-0 on 781101:during Refueling & Maint Shutdown It Was Found That Surveillance Test Had Not Been Performed for Combustion Ionization Products Smoke Detectors Installed in Diesel Fire Pump Room on 780310,due to Oversight ML20071F8651978-11-17017 November 1978 /04L-0 on 781024:excess Solute Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel Detected.Caused by Unsound Sampling & Method of Determining Concentrations & Dissolved Solids ML20148F2461978-11-0101 November 1978 /04T-0 on 781018:Environ Radiological Monitoring Sample of Periphyton Samples Pci/Gm(Wet)Does Not Meet Subj Facil Tech Spec Append B,Paragraph 5.6.2.6 ML20071F4241978-10-0303 October 1978 /04L-0 on 780914:An Apparent Excessive Solute Release from Makeup Water Treatment Waste Neutralizer Tanks to Circulating Water Discharge Tunnel Was Detected While Performing Aug 78 24-hour Complete Sample Analysis 1993-08-30
[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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NEC FORM 366 U. S. NUCLE AR REGULATORY COMMIS32CN 17 77) "
LICENSEE EVENT REPORT CONTROL block: l l l l l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 l o lij l Nl Yl Jl Al Fl 1lgl 0 l 0 l -l 0 l 0 l 0 l 0 l - [ 0 l 0 l 025lgl 4 l 1 l 1 l 1 l 1 lglS 3 cAl T Sdlg 7 8 9 LICENSEE CCDE 14 15 LICENSE NUMSER 26 LICENSE TYPE JO CON'T lol,l gog [ L lgl 0 ; 5 l 0 l 0 l 0 l 3 l 3 l 3 gl 69 0 l 7 [ 3 l1 l 8 l1 l@l0 [6 l0 l1 l8 l2 75 80 lg i 8 60 61 COCK ET NUMB ER 68 EVENT OATE F4 REPORT QATE EVENT DESCRIPTION AND PACBABLE CCNSEQUENCES h t o l2l l During normal operation, while plant personnel were troubleshooting a problem with l 1 o 131 I the HPCI System primary containment isolation circuits, the Resident Inspector noted ;
[o i.; I that some administrative controls associated with control of maintenance activities l i o i 9, I were not being followed. The event is . considered reportable under TS 6.9. A.4.2.c, i lo Is l I inadequate implementation of approved administrative procedures for safety related ;
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JJ 36 40 44 47 CAUSE DESCRIPTION AND CCARECTIVE ACTICNS h li io l l Personnel error Was the cause. The maintenance activities were immediately terminated ii ii il and the isolation circuits restored to normal. Work was not resumed until applicable;
,, ,,, l administrative controls were applied as required. Formal training concerning the l i,i3i l control of safety related work was conducted to prevent recurrence. l I1 14 Il .,j
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