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Category:Letter
MONTHYEARML24268A3382024-10-16016 October 2024 Issuance of Amendment No. 253 Regarding the Modification of TS Surveillance Requirement 4.3.6.a Related to Adoption of TSTF-425, Revision 3 RS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP2L2890, Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6)2024-10-0404 October 2024 Submittal of Revision 26 to the USAR and Reference Figures, 10 CFR 50.59 Evaluation Summary Report, TS Bases, TRM Requirements Manual Changes, and 10 CFR 54.37(b) Aging Management Review (Excludes Attachment 6) ML24275A2442024-10-0303 October 2024 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief, Division of Operating Reactor Licensing IR 05000220/20243022024-10-0303 October 2024 Initial Operator Licensing Examination Report 05000220/2024302 ML24190A0012024-09-26026 September 2024 Issuance of Amendment Nos. 252 and 197 Regarding the Revision to Technical Specification Design Features Section to Remove Nine Mile Point Unit 3 Project Designation NMP1L3608, Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-09-20020 September 2024 Supplemental Information Letter No. 3 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000220/20240052024-08-29029 August 2024 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2024005 and 05000410/2024005) IR 05000220/20240102024-08-22022 August 2024 Age-Related Degradation Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3603, Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan2024-08-20020 August 2024 Submittal of Preliminary Decommissioning Cost Estimate and Irradiated Fuel Management Plan ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000220/20240022024-08-0505 August 2024 Integrated Inspection Report 05000220/2024002 and 05000410/2024002 ML24215A3002024-08-0202 August 2024 Operator Licensing Examination Approval NMP1L3601, Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-07-31031 July 2024 Supplemental Information Letter No. 2 - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML24213A1412024-07-31031 July 2024 Requalification Program Inspection NMP2L2883, Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations2024-07-24024 July 2024 Fourth Inservice Inspection Interval, Second Inservice Inspection Period 2024 Owner’S Activity Report for RFO-19 Inservice Examinations ML24198A0852024-07-16016 July 2024 Senior Reactor and Reactor Operator Initial License Examinations RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3584, License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2024-06-13013 June 2024 License Amendment Request to Revise Technical Specifications to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000220/20244012024-05-30030 May 2024 Security Baseline Inspection Report 05000220/2024401 and 05000410/2024401(Cover Letter Only) ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 NMP1L3591, Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request2024-05-18018 May 2024 Response to Ny State Pollutant Discharge Elimination System (SPDES) Permit Request for Information & Modification Request NMP1L3589, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-05-16016 May 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report NMP1L3582, 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 22024-05-15015 May 2024 2023 Annual Radioactive Environmental Operating Report for Nine Mile Point Units 1 and 2 IR 05000220/20240012024-05-10010 May 2024 Integrated Inspection Report 05000220/2024001 and 05000410/2024001 RS-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds 05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report2024-04-30030 April 2024 Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report NMP2L2877, 2023 Annual Environmental Operating Report2024-04-19019 April 2024 2023 Annual Environmental Operating Report NMP2L2878, Core Operating Limits Report2024-04-16016 April 2024 Core Operating Limits Report ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 ML24074A2812024-03-14014 March 2024 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000220/2024010 and 05000410/2024010 NMP1L3577, Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable2024-03-13013 March 2024 Special Report: Containment High Range Radiation Monitor Instrumentation Channel 12 Inoperable IR 05000220/20230062024-02-28028 February 2024 Annual Assessment Letter for Nine Mile Point Nuclear Station, Units 1 and 2, (Reports 05000220/2023006 and 05000410/2023006) IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 NMP1L3570, Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2024-02-0101 February 2024 Supplemental Information Letter - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024 CFR 50.46 Annual Report ML24004A2122024-01-0808 January 2024 Senior Reactor and Reactor Operator Initial License Examinations ML23354A0012024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0059 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023 Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 NMP1L3566, Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station2023-12-14014 December 2023 Radiological Emergency Plan Document Revision. Includes EP-AA-1013, Revision 10, Radiological Emergency Plan Annex for Nine Mile Point Station 2024-09-04
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000410/LER-2024-001, Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum2024-05-0101 May 2024 Automatic Reactor Scram on Turbine Trip Due to Low Condenser Vacuum 05000410/LER-2023-001, Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater2024-01-30030 January 2024 Supplement to LER 2023-001-00, Automatic Reactor Scram on Low Level Due to Partial Loss of Feedwater 05000220/LER-2023-002, Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 122023-12-15015 December 2023 Average Power Range Monitors Declared Inoperable Due to Trip of Reactor Recirculation Pump 12 05000220/LER-2023-001-01, Supplement to NMP1 Indication on the N2E Dissimilar Metal Weld Exceeding ASME Acceptance Criteria2023-08-11011 August 2023 Supplement to NMP1 Indication on the N2E Dissimilar Metal Weld Exceeding ASME Acceptance Criteria 05000220/LER-2023-001, Indication on the N2E Dissimilar Metal Weld Exceeding ASME Acceptance Criteria2023-05-12012 May 2023 Indication on the N2E Dissimilar Metal Weld Exceeding ASME Acceptance Criteria 05000410/LER-2022-002-01, Reactor Protection System Actuation While Shutdown2022-12-20020 December 2022 Reactor Protection System Actuation While Shutdown 05000410/LER-2022-002, Reactor Protection System Actuation While Shutdown2022-11-0303 November 2022 Reactor Protection System Actuation While Shutdown 05000410/LER-2022-001, Regarding Automatic Reactor Scram Due to Low Reactor Water Level During Maintenance2022-06-0303 June 2022 Regarding Automatic Reactor Scram Due to Low Reactor Water Level During Maintenance 05000220/LER-2021-002, Isolation of Both Emergency Condensers Due to Loss of UPS 162A2021-11-19019 November 2021 Isolation of Both Emergency Condensers Due to Loss of UPS 162A ML18018B1122018-01-18018 January 2018 Scram Summary 91-01 Relating to an Event on August 13, 1991 Concerning a Turbine Trip and Automatic Reactor Scram When the Main Transformer Phase B Developed an Internal Fault ML18018B1152018-01-18018 January 2018 Scram Summary 91-01 Relating to a Turbine Trip and Automatic Reactor Scram When the Main Transformer Phase B Developed an Internal Fault on August 13, 1991 05000410/LER-2017-0022017-11-28028 November 2017 Secondary Containment Inoperable Due to Wind Conditions, LER 17-002-00 for Nine Mile Point Nuclear Station, Unit 2 Regarding Secondary Containment Inoperable Due to Wind Conditions 05000220/LER-2017-0032017-11-0202 November 2017 Automatic Reactor Scram due to Reactor Vessel Low Water Level, LER 17-003-00 for Nine Mile Point, Unit 1, Regarding Automatic Reactor Scram due to Reactor Vessel Low Water Level 05000410/LER-2017-0012017-10-0404 October 2017 1 OF 5, LER 17-001-00 for Nine Mile Point Nuclear Station, Unit 2, Regarding Automatic Reactor Scram due to High Reactor Pressure 05000220/LER-2017-0022017-05-18018 May 2017 Manual Reactor Scram Due to Pressure Oscillations, LER 17-002-00 for Nine Mile Point Nuclear Station, Unit 1 Regarding Manual Reactor Scram Due to Pressure Oscillations 05000220/LER-2017-0012017-02-0808 February 2017 Manual Reactor Scram Due to Hiah Turbine Vibration, LER 17-01-00 for Nine Mile Point Unit 1 RE: Manual Reactor Scram Due to High Turbine Vibration NMP1L3129, LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration2017-02-0808 February 2017 LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration 05000220/LER-2016-0022016-09-26026 September 2016 Isolation of both Emergency Condensers due to loss of UPS 162B, LER 16-002-00 for Nine Mile Point, Unit 1, Regarding Isolation of Both Emergency Condensers due to Loss of UPS 1628 05000220/LER-2016-0012016-07-12012 July 2016 Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors, LER 16-001-00 for Nine Mile Point Nuclear Station Unit 1 Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors 05000410/LER-2016-0012016-06-0606 June 2016 Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors, LER 16-001-00 for Nine Mile Point, Unit 2, Regarding Secondary Containment Inoperable Due to Simultaneous Opening of Airlock Doors 05000410/LER-2015-0032016-03-31031 March 2016 Primary Containment Isolation Function for some valves not maintained during Surveillance Testing, LER 15-003-01 for Nine Mile Point, Unit 2, Regarding Primary Containment Isolation Function For Some Valves Not Maintained During Surveillance Testing ML1005504842010-02-15015 February 2010 Special Report: Inoperable Suppression Chamber Water Level Instrumentation ML0903605172009-01-21021 January 2009 Special Report: Inoperable Channel of Suppression Chamber Water Level Instrumentation ML0534802052005-12-0202 December 2005 Special Report for Nine Mile Point Unit 1 Re Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0515400362005-05-24024 May 2005 Special Report, Channel #11 of the Containment Hydrogen Monitoring Inoperable for Scheduled Preventive Maintenance ML0509602522004-12-17017 December 2004 Final Precursor Analysis - NMP-2 Grid Loop ML0509602422004-12-17017 December 2004 Final Precursor Analysis - NMP-1 Grid Loop ML0434304492004-11-22022 November 2004 Special Report for Nine Mile Point, Unit 1 Regarding Channel #12 of the Containment Hydrogen Monitoring System Removed from Service for Planned Maintenance ML0425300732004-08-27027 August 2004 Special Report for Nine Mile Point Unit 1 Re Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Preventive Maintenance ML0418105152004-06-18018 June 2004 Revised Special Report for Nine Mile Point, Unit 1 Re Channel #12 of the Containment Hydrogen Monitoring System Inoperable ML0413204992004-05-0404 May 2004 Special Report for Nine Mile Point Unit 1 Regarding Inoperability of Channel #12 of the Containment Hydrogen Monitoring System ML0410603992004-04-0707 April 2004 Special Report, Channel #11 of the Containment Hydrogen Monitoring System Inoperable for Scheduled Corrective Maintenance ML0336404932003-12-19019 December 2003 Special Report Regarding Channel #11 Containment Hydrogen Monitoring System Being Inoperable for Scheduled Preventive Maintenance ML0221303572002-07-23023 July 2002 Special Report for Nine Mile Point Unit 2 Re Noble Gas Activity Monitoring Instrumentation Inoperable for Greater than 72 Hours ML18018B1112000-03-0707 March 2000 LER 99-019-01 Supplement 1, for Nine Mile Point, Unit 2, Regarding Two Standby Liquid Control Valves Not Tested as Required by Technical Specification 4.0.5 and LER 99-010-01, Supplement 1, Unit 2 Reactor Trip Due to a Feedwater Master .. ML18018B0771997-12-29029 December 1997 Letter Replying to Notice of Violation as Contained in NRC Inspection Report 50-220/97-07 and 50-410/97-07 ML18018B1171991-09-0404 September 1991 NRC UPS Meeting ML18018B2511978-09-29029 September 1978 LER 78-034-00 for Nine Mile Point, Unit 2, Regarding an Environmental Contractor Obtaining 22 Hourly Fish Impingement Samples, and One Two-Hour Sample, Which Is Contrary to the Technical Specification Requiring 24 Hourly Samples ML18018B2521978-08-24024 August 1978 LER 78-030-00, 78-031-00, and 78-032-00 for Nine Mile Point Unit 1 Regarding, Respectively, Unavailability of Feedwater Pump 29-03 While Its Pump Seals Were Replaced, Unavailability of Liquid Poison Pump NP02A While a Frozen Valve .. ML18018B2531978-07-28028 July 1978 LER 78-029-00 for Nine Mile Point, Unit 2, Regarding Discovery of High Drywell Pressure Switches RE04A, RE04B, and RE04C with Setpoints Less Conservative than the Technical Specifications ML18018B2541978-07-25025 July 1978 LER 78-028-00 for Nine Mile Point Unit 1 Regarding Discovery of the Allowable Test Interval of TS 4.1.4c for the Core Spray Power-Operated Valves Had Been Exceeded ML18018B2551978-07-13013 July 1978 LERs 78-025-00, 78-026-00, and 78-027-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery of RE04D with a Setpoint of 3.70 PSIG, Discovery of Numerous Small Leaks in Small Sample and Instrument Pipes, and Discovery of RE22D wit ML18018B2561978-06-21021 June 1978 LER 78-024-00 for Nine Mile Point Unit 1 Regarding Discovery That Test N1-St-Q2,4,5,7,8,9, and 10 Had Not Been Performed During a Review of Quarterly Surveillance Test Results ML18018B2571978-06-12012 June 1978 LERs 78-020-00, 78-021-00, 78-022-00, and 78-023-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery of RE18A with a Setpoint of 135 Inches Wc, Discovery of RE04A and RE04B with a Setpoint of 3.65 PSIG, Discovery of Turbine ... ML18018B2591978-06-0101 June 1978 LER 78-019-00 for Nine Mile Point Unit 1 Regarding Discovery That Hydraulic Snubber 31-HS-1 Had Failed and Was Empty of Hydraulic Fluid and Disconnected from Its Anchor at the Feedwater Pipe ML18018B2581978-05-26026 May 1978 LER 78-009-01 for Nine Mile Point Unit 1 Regarding Replacement of Explosive Charges in the TIP Shear Valves with New Charges and the Resulting Unsatisfactory Ohmmeter Continuity Test for Acceptable Electric Contact ML18018B2601978-04-24024 April 1978 LER 78-018-00 for Nine Mile Point Unit 1 Regarding Discovery of Main Steam High Flow Switch with a Setpoint of 106.2 PSI, Which Is Above the Technical Specification ML18018B2611978-04-0707 April 1978 LERs 78-014,00, 78-016-00, and 78-016-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery That the Fuel Transfer Pump on 102 D/G Would Not Fill the Day Tank, Discovery of RE18C with a Setpoint of 129 Inches Wc, and RE04B .. ML18018B2621978-03-28028 March 1978 LER 78-014-00 and LER 78-015-00 for Nine Mile Point Unit 1 Regarding, Respectively, Discovery That the Fuel Transfer Pump in 102 D/G Would Not Fill the Day Tank and Discovery That #12 Control Room Air Treatment Fan Would Not Run ML18018B2631978-03-16016 March 1978 LER 78-011-00, LER 78-012-00 and LER 78-013-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Section 3.6.2 2024-05-01
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM <RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC'RIER B H ORG: SCHNEIDER R R DOCDATE: 02/24/78 NRC NIAGARA MOHAWK PWR DATE RCVD: 03/07/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 0 ENCL 1 LICENSEE EVENT REPT <RO 50-220/78-06) ON 01/27/78 CONCERNING PERFORMANCE OF SURVEILLANCE TEST IC-75 FOUND A TRIP SETPOINT OF
- 22. 5 INCHES WATER ON ONE VACUUM SWITCH IN THE VACUUM RELIEF SYSTEM FROM THE PRESSURE SUPPRESSION CHAMBER TO THE RX BLDG (68-12B>.
PLANT NAME: NINE MILE PT UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR. INITIAL:gQ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS INCIDENT REPORTS
<DISTRIBUTION CODE A002)
FOR ACTION: /4 ENCL INTERNAL: EG ILE~~~~W/ENCL NRC PDR44W/ENCL I 8. E%~% MIPC++W/3 ENCL SCHROEDER/I PPOL I T044 W/ENCL HOUSTON4+W/ENCL NOVAK/CHECK++W/ENCL GR IMES++W/ENCL KNIGHT++W/ENCL BUTLER++W/ENCL HANAUER+4W/ENCL TEDESCO++W/ENCL E I SENHUT++W/ENCL BAER44W/ENCL SHAO++W/ENCL VOLLMER/BUNCH>~W/ENCL KREGER/J. COLLINS44W/ENCL ROSA++W/ENCL K SEYFRIT/IE++W/ENCL EXTERNAL: LPDR'S OSWEGO'Y++W/ENCL TIC++W/ENCL I
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~o 7 safet im lications. A redundant switch was available to initiate
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~QEE 43 44 47 QEE CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o The cause of the failure was instrument drift in a mercoid model CP4122 vacuum switch. Trip setpoint was reset to 6.8 inches water. Current surveillance testing schedules are adequate to ensure early detection of future instrument drifts.
7 8 9 80 Q
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AMOUNT OF ACTIVITY nA Q LOCATION OF RELEASE Q Q33 ~ZQ34 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7
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EVEITIT DESCRIPTION ANO PROBABI.E CONSEQUENCES 10
~oz Burin stead state o eration erformance of surveillance test IC-75
~o 2 found a trip setpoint of 22.5 inches water on one vacuum switch in the
~o R vacuum relief s stem from the ressure su ression chamber to the Rx
~o s Buildin (68-128 . T.S. 3.3.6.F requires a setpoint less than or equ'al
~o 8 to 0.5 si 13.85 inches ivater . This condition resulted in minimal
~o T safet im Iications. A redundant switch was available to initiate
~o 8 o aration of the vacuum relief valve.
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~SA Q ~EQ ~EQ 9 10 11 12 13 I N S T R 0 18 Q ~SQ ~2cl 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Qir LEREPRO REPQRT ACTION, FUTURE EVENT YEAR
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~NQ22 41 FORM SUB,
~TOTE SUPPLIER
~NQzs MANUFACTURER N 2 3 5 Q28 42 43 44 47 CAUSF DESCRIPTION AND CORRECTIVE ACTIONS '27 o The cause of the failure was instrument drift in a mercoid model CP4122 vacuum switch. Trip setpoint was reset to 6.8 inches water. Current surveillance testing schedules are adequate to ensure early detection of future instrument drifts.
4
~O 7 8 9 80 FACILITY ~ I,IETHQD OF STATUS <<8 POWER OTHER STATUS DISCOVERY DISCOVERY OESCRIPTIQi'4 Q3 CO LJOS E 28 0 9 6 29 NA ~BQSI 45 46 Surveillance Testing 80 ACTIVITY CONTENT REI.EASED OF RELEASE AMOUNT OF ACTIVITY Q LOCATION OF RELEASE QB 8 ~2 Qzz ~2QEE NA NA 7 8 9 10 11 44 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~I7 ~00 0 QTT ~L Q28 NA 7 8 9 11 12 13 80 PERSOiNiNEL INJURIES NUMBER O'ESCRIPTIONQ 8
~00 9
0 Qio 12 NA 7 11 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 2 Q42 NA 7 8 9 10 80 ISSUED~
PUBLICITY
- 6) E~EE DESCRIPTION IEA
~ I I NRC IJSE ONLY I I I I .I .I..I. I I I "",
NAME OF PREPARER Dennis t 1acVi ttie PHONE:
315-343-2110 ext. 1558
To: PIB -39~)~) ',
Y<i'(lil~~.riG l'w:;b~:r rooN .3fa -gQ 2 lg~
lel ephonc lou::il~ci or<TL/To r TO: Frooi: Hiirgara lTol:a';cl; Po.jcr Corporation Director of Pco>>lat<<ry Operation bine hilt. Point, Duel cdr Station OSl;lK l. -.:ir,n I U>>lt fiT 63l Pari: l:;en c P 0. Bor. i<32 l:in@ nf Pros'ia, Ph. 19406 Lp'colllin9, hcl'I York 13093 SUPiilECT: PP.Ol',1'T Rl.PO.,TN)].!! OCD).J)El'CE DOC):l'.T ASSJ(islED LER HO. '8-09 l'0. "0-220 LICLl!SE l!0. DPR-G3 CYGNET DATE: 78022E REPORT Df<TE: 78022I EVErlT DFSCRIPTTnrl:
SEE ATTACHED.
CO:(POlKliTS Il 'OL"ED: TIP machine shear va'1ve squfb devices
, CAUSE l(t!D RKr':ENf(L ACTIDIL Institution of modiffcation in squib circuit per GE revisi'on
~
FE(CILITV STATUS= S; TllEt:Wnt. bi( 1840 c) Routine Startop Slwit<foi~o d) Routln~ Sll:: dc"n refuel lng e) stea<ry s:.iie opLl- Other f) Load Cl'.-.age l(ot lippj'IcBI>IL IL i'riticn follow-up rcport will be sent v;itbin i<io v.'ccl:s.
vr..roon ro 35 7 H:i ll.
- 6. roo~ rV: P.~~a" llMH.
owL a 2.i
ATTACHMENT TO LER 78-09 Event
Description:
During routine station operation with the TIP detectors. withdrawn, repTacement explosive charges in the TIP system shear valves were replcaed with new charges. Following replacement, it was found that the ohmneter contlnuity test for acceptable eTectric contact was unsatisfactory.
The normal TIP tube tsoTaticm system was. operabTe at this time.
I It was found thart the. actual etectricaV connections to the. explosive The shear charges were net as-described -4n the maStenance-procedure. - .
valves would not have operated to 5solate the TIP guide. tuba witlr the TIp inserted Dectrical connections vill be checked described in the and tested to assure.
that the explosive.va7.ves wAl operate as operatic procedures."..Station records; including. the au6ntenance.-.procedures,-wfTT =
be corrected to reflect the correct. wiriny connections An end-ta-end demonstration-at'he. explosive shear va7ves=will be performed'ith the explosive charge removed. from..the, system.. 'orrective action wfll be compTeted before the TIP system is again used r
The explosive operated TIP shear tsolation valves are a back-up system to be used for isa'Eatioe of the TIP tubes in the event detectnr the it is i.soTation not possible. te wfthdrwr the. se normaT automat%a.
system may function