LER 77-029-00, 77-030-00, 77-031-00, 77-034-00, & 77-035-00 for Nine Mile Point Unit 1 Low-Low-Low Level Set Point Out of Specs on RE-18A, Vacuum Switch Trip & Reset Point on Torus Relief Valves Out of Specs, Weld Leak in Emergency CondenseML18018B142 |
Person / Time |
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Site: |
Nine Mile Point |
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Issue date: |
07/14/1977 |
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From: |
Schneider R Niagara Mohawk Power Corp |
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To: |
O'Reilly J NRC Region 1 |
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References |
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LER 77-029-00, LER 77-030-00, LER 77-031-00, LER 77-034-00, LER 77-035-00, LER 77-036-00 |
Download: ML18018B142 (14) |
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Category:Letter
MONTHYEARNMP1L3570, 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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 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)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines 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 IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 ML23305A1402023-12-13013 December 2023 Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580 NMP1L3564, Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request - Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements ML23291A4642023-12-0707 December 2023 Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants ML23289A0122023-12-0606 December 2023 Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NMP1L3563, Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-12-0404 December 2023 Submittal of Relief Request I5R-12, Revision 0, Concerning the Installation of a Full Structural Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) IR 05000220/20234022023-11-28028 November 2023 Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402 NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000220/20234202023-11-0101 November 2023 Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420 ML23305A0052023-11-0101 November 2023 Operator Licensing Examination Approval IR 05000220/20230032023-10-25025 October 2023 Integrated Inspection Report 05000220/2023003 and 05000410/2023003 IR 05000220/20235012023-10-17017 October 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501 IR 05000220/20230112023-10-16016 October 2023 Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023 Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C IR 05000220/20233032023-09-20020 September 2023 Retake Operator Licensing Examination Report 05000220/2023303 ML23250A0822023-09-19019 September 2023 Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69 ML23257A1732023-09-14014 September 2023 Requalification Program Inspection IR 05000220/20230052023-08-31031 August 2023 Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005) RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023 Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations ML23151A3472023-08-21021 August 2023 Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023 License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation ML23220A0262023-08-0808 August 2023 Licensed Operator Positive Fitness-for-Duty Test IR 05000220/20234012023-08-0808 August 2023 Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only) NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023 Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems . RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor IR 05000220/20230022023-08-0101 August 2023 Integrated Inspection Report 05000220/2023002 and 05000410/2023002 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023 Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations ML23186A1642023-07-0606 July 2023 Operator Licensing Retake Examination Approval NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023 Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications ML23192A0622023-06-30030 June 2023 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0 IR 05000220/20230102023-06-29029 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010 ML23131A4242023-06-23023 June 2023 Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568 RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023 Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling IR 05000410/20233022023-05-15015 May 2023 Initial Operator Licensing Examination Report 05000410/2023302 2024-02-01
[Table view] Category:Licensee Event Report (LER)
MONTHYEARML18018B1152018-01-18018 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 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 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 ML0509602422004-12-17017 December 2004 Final Precursor Analysis - NMP-1 Grid Loop ML0509602522004-12-17017 December 2004 Final Precursor Analysis - NMP-2 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 ML18018B2641978-03-0101 March 1978 LER 78-007-00, LER 78-008-00, LER 78-009-00 and LER 78-010-00 for Nine Mile Point, Unit 1 Re Technical Specification Violations of Listed Sections ML18018B2651978-02-24024 February 1978 LER 78-006-00 for Nine Mile Point, Unit 1 Re During Steady State Operation, 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 Cha ML18018B2661978-02-0707 February 1978 LER 78-004-00 and LER 78-005-00 for Nine Mile Point, Unit 1 Re During Unit Shutdown, Reserve Power Breaker on Power Board II Failed to Close in After Loss of Normal Power and During Plant Outage While Marking Up Outside MSIV 01-03 Discovere ML18094A0301978-01-31031 January 1978 LER 1978-003-03 for Nine Mile Point Unit 1 Re Surveillance Test Found Main Steam High Flow Switch with Setpoint of 107.5 PSI ML18018B1221978-01-31031 January 1978 LER 78-002-00 for Nine Mile Point 1 Regarding Drywell High Pressure Switch RE04A Setpoint Drift and LER 78-003-00 ML18018B2701978-01-13013 January 1978 Submittal of Licensee Event Report LER 78-01 Concerning Delta Temperature of the Discharge Water Exceeded Environmental Tech. Spec ML18094A0291978-01-13013 January 1978 LER 1978-001-00 for Nine Mile Point Station Unit 1 Re Delta Temperature of Discharge Water Exceeded Specification 2.1.5 of Environmental Tech Specs ML18018B1361977-07-21021 July 1977 LER 77-032-00 for Nine Mile Point Unit 1 Regarding a Water Phase Material Sample in the Reactor Vessel Inspection Lapse During Refueling ML18018B1421977-07-14014 July 1977 LER 77-029-00, 77-030-00, 77-031-00, 77-034-00, & 77-035-00 for Nine Mile Point Unit 1 Low-Low-Low Level Set Point Out of Specs on RE-18A, Vacuum Switch Trip & Reset Point on Torus Relief Valves Out of Specs, Weld Leak in Emergency Condense 2018-01-18
[Table view] |
Text
U.So NUCI.EAR REGULATORY C SSION DOCKET NUMBER NRC FDRM 195 (2-76),' ~ ~
FILE NUMBER NRC 6ISTRIBUTION FOR PART 60 DOCKET MATER(AL, 'NCIDENT REPORT TO: FROM: DATE OF DOCUMENT James P 0,'Reilly Niagara Mohawk Power Corp. 7/14/77 Syracuse,NY DATE RECEIVED R. R. Schneider 7/20/77 LETTER QNOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED CI ORIGINAL 0 UN C LASS IF I ED OPY DES C R I P T I 0 N ENCLOSURE Licensee Event Reports (50-220/77-29, 77-30, 77-31, 77-34, and 77-35)
KgyVIZM~@: on 6/16, 6/16, 6/18, 7/3, and 7/5/77 concerning low-low-low level set point out of specs on'RE-18A, vacuum switch trip and reset point on torus relief valves out of specs, weld leak in go goi REMOVE emergency condenser valves, and failure PLANT NAME- Nine Mile Point 'Nucleax Station of RTD to maintain required accuracy.
Unit No. 1 1p+5p RBT 7/21/77 NOTE: IP PERSONNEL. EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS FOR CT /I NF0 RM AT I ON BRANCH CHIEP:
W 3 CYS POR ACTION W CYS ACRS CYS INTERNAL D ISTR I BUTION REG F NR PDR I &E 2 MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/CHECK GRIMES BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER BUHGH KREGER/J COLLINS EXTERNAL DISTRIBUTION CO OL NUMBER LPDR:
TIC:
N ~ 72020321 NRC FORM 195 (2 78)
~ I, ATTACHMENT TO LER 77-36 for NMP k'1 EVENT DESCRIPTION During routine unit startup, 811 Emergency Cooling System was discovered to be inoperable. Ultra-sonic testing of system ll's condensate return inlet valve (39-01) indicated that the valve stem was separated from the disc. The normally open valve was run to closed position and a surveillance test was run on the redundant Emergency Cooling System (812) in accordance with Technical Specification 4.1.3.4 No problems were encountered. A Technical Specification change was requested to allow normal operation with one Emergency Cooling System inoperable, beyond the seven days currently allowed. In addition, it was requested that the increased surveillance for operation with an inoperable emergency cooling system be performed on a weekly rather than a daily basis.
At the conclusion of Cycle 5, maintenance will be performed on the inoperable emergency cooling system to place it back in service.
CAUSE DESCRIPTION A Crane Company 10 inch list 900 W.E.O.S. Gate Valve failed to open or close automatically or open manually. It is suspected that the valve stem has separated from the disc or has sheared at some point along its length. The actual cause cannot be determined until the valve is disassembled.
J 1
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CONTROL BLOCK: fPLEASE PAINT ALL REQUIRED IN&OAIVIATION) 1 LICENSEE LICENSE EVENT NAME LICENSE NUMOER TYPE TYPE gg89 N 7
Y N NP I 14 15 25 26 4 1 1 I I 30
~0 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMOER EVENT DATE REPORT DATE Q~gccwv~ L L 05 0 0 2 2 0 0 7 I 2 7 7 07 2 0 7i 7 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION QP2 SEE ATTACHMENT FOR DESCRIPTION 7 8 9 ~ 80 7 89 80
~04 7 8 9 80
[ops 8 9 80
{oat LER 77-36 7 8 9 PRIMAE 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPLIER MANUFACTURER . VOLATION
~CP ~E V A L V E X C 6 6 5 ~N 7 8 9 10 11 1P 17 43 44 47 48 CAUSE DESCRIPTION Qo 8 SEE ATTACHMENT 7 8 9 80 QOg 7 8 9 80
[isa]
7 89 METHOD OF 80 FACILITY STATUS POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q~g 7 8 9 c ~00 4 NA 44 45 46 80 10 12 13 FORM OF AMOUNT OF ACTIVITY LOCATION OF RELEASE NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES 7
~13 8 9
~00 NUMOER 11 TYPE
~Z 12 13 DESCRIPTION NA 80 PERSONNEL INJURIES NUMOER DESCRIPTION Qg ~oo o NA 7 89 11 12 80 dggljtIxl, YCONSEQUENCES PROBABLE Qsj NA 7 8 9 80 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Q~g Z NA 7 89 10 80 PueLICITY NA 7 89 80 ADDITIONAL FACTORS 7 89 80 7 89 NAME'HONE: CP0,44'I ~
80 467
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LICEttSEE LICENSE EVENT NAME (oO] N 7 N N P 1 4 1 1.1 1 ~p~g 7 89 25 26 30 31 32 RL'PORT REPORT CATEGORY TYPE SOUfICE OOCKET'4UMOER EVEttT 0 TE REPORT OATS
[oO~]cove~ 7 ~L 0 5 0 0 2 2 0 0 6 T 6 7 7 0 7 1 3 7 7 7" 0,57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION at' Jog Durin routine surveillance testing, found reactor low-low-low level setpoint 89 80
@~3 140" on RE-18A. Should have been 125'+ 2.0-2.5". Reset to 126". Inspected 7 89 80 tooj4 friction and mechanical defects, found none. Redundant instrumentation operable.
LER 77-29
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[0DB] Instrument setpoint dri ft.
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Surveillance Test 80 10 4G FORM OF AMOUNT OF ACTIVITY LOCATION OF RELEASE NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE OESCRIPTION Qsg ~00 0 2 . NA 7 8 9 11 12 " 13 80 PERSONNEL INJURIES NUMBER OESCRIPTION
~~~ ~00 0 NA 7 89 11 12 80 ANNAL cowssousscss pROBABLE Q~g 7 89 60 LOSS OR DAMAGE TO FACILITY 7
Q~g 89
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TYPE 10 OESCRIPTION NA 80 PUBLICITY NA 7 89 ADDITIONAL FACTORS
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MOHAWK 300 ERIE DOUI.EVARD, WEST SYRACUSE. N. Y. l3202 JuLy 14,
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~EYO6 lib. Jam~ P NJLe&ok Used S~e6 NueLeat Regulato<IJ Con ncb6<on Region I 631 Parch Avenue Kmg o$ P~6kx, PA. 19406 RE: Sock& No. 50-220 geaPI, h(PI.. O'Reify:
In accordance ~k N~e hKCe Po~ NucL~
TecluucaL Spew.gc~on6, toe hereby 6ubnkt Licen6ee
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LER 77-29, 77-30, 77-31, 77-34 and 77-35.
The6e rcepo~ uIePIe compL&ed ~n Che $ o~at de6~gnat'ed Licen6ee Eveet RepoM In6Wu~on BookLM 00E-SS-.001, ~ed.
~ She 0&obn 1974, JI.ev~ed Gecembec 8, 1975.
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ORIGINAL SIGNED BY R.R. SCHNEIDER R.R. SclumufeA Vzce PJce6&eet-ELe~c Pcodu~on h(AS/mmmm kttachm~
xc: Vme&oe, ISE (40 cop~e6)
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LICENSEE EVENT REPO+ 'I CONTROL 8LOCK: (PLEASE PRINT ALL REQUIRED INFoRMATIoN3 1 6 UCENSEE NAME LICENSE NUMOER LICENSE TYPE
'VENT TYPE 4 1 1 1 1 ~03 7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE 'SOURCE DOCKET NUIliOER EVENT DATE REPORT DATE
[ca~Ice@'T~ L ~L 0 5 0 0 22 0 0 6 1 8 ? ? 0 ? 1 3 7 7 7 8 57 58 59 60 61 68 69 74 75 FVENT DESCRIPTION Jog During routine surveillance test, found vacuum switch trip and res'et point on 7 8 9 80 toD3] reactor building to torus relief valves (68-12A) set 8" and <0". Should have 89 80 tQ been < 7" and > 2". Reset at'6;5" and 2.3". Redundant sensors operable.
7 8 9
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QOg 7 8 9 80 l LER 77-31 Jog 7 8 9 PR?hE 80 SYSTEM CAUSc COMPONENT COMPONENT' CODE CODE COMPONENT CODE SUPPUdl MANUFACTURER VIOLATION
[cO'] ~SA ~E I N S TR. U N N 2 3 5 IN 7 8 9 10 11 12 17 43 . 44 47 48 CAUSE DESCRIPTION 7
gg8 9 rn Jog 7 89 80 7 89 METHD9 OF FACIUTY STATUS POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Qg8 ~8 [oaooJ12 ~B 'urveillance Test 7 9 10 13 44 45 46 80 FORM OF ACTIVITY COATENT 7
Q~g 8
~ ~
RELEASEO 9
OF RELEASE 10 1'I NA AMDUNT OF ACTIVITY 44 45 LOCATION OF RELEASE 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
[iisj ~00 0 2 .NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION
~>4 ~00 0 NA 7 89 11 12 80 X5ggfg CONSEOUENCES PROBABLE NA 7 8 9 LOSS OR DAMAGE TO FACILITY TYPE DESCRIPTION Z NA 7 89 10 PueLICITY Q~~]
7 0 9 Q NA AODITIONAI. FACTORS Q~g 7 89
+1q 7 89 00 NAME: PHONE:
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LICENSEE EVENT REPOR CONTROL BLOCK: fPLEASE PRINT ALL REQUIRrD IMFQRflATIOIYI) 1 I.ICENSEE UCENSE EVENT h NAME LICENSE NUMBER
~Oh N Y N 14 P I 4 1 I 1 I ~03
~
7 09 15 25 26 30 31 32 TIEPOAT AEPOAT CATEGORY TYPE SOURCE DOCKET NUMOEA EVENT DATE ACPOAT DATE
'061]coN'T T ~L 0 6 0 0 2 2 0 0 6 1 6 7 7 0 7 1 3 7 7 7 8 57 58 59 60 61 68 69 74 75 80 EVENT DESCRIPTION Qpg Dur ing routine surveillance testing, found reactor low-low-low level setpoint at 7 0 9 II Qo 3 127',"II on RE-18B. Should have been 125 + 2.0-.2.5". II Reset to 125". Inspected 7 09 00
~04 for friction and mechanical defects, found none. Redundant instrumentation operable.
80 LER 77-30
.7 89 00
'Jog 7 8 9 PAhhIE
[aO~I 7 8 9 10 SYSTEM CODE
~IB CAUSE CODE
~E 11
'IN 12 COMPONENT CODE 3 T II 0 17 COMPONENT SUPPLKA
~A 43
~80~80 COMPONENT IAWUFACTURER 48 CAUSE DESCRIPTION
[oO~j Instrument setpoint drift.
7 89 00
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7 0 9 80
~10 7 89 METMOO OF 00 FACILITY STATUS 36 POWER OTMEA STATUS OISCOVEAY OLSCOVERY DESCRIPTION EO" 7 8 9 0
10
~00 0 12 13 NA 44 45 46
'Surveillance Test 00 FORM OF ACTIVITY COATENT AEI.EASCD OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q~g Z Z NA NA h 7 0 9 10 11 . 44 45 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION
~hh ~00 O ~Z NA 7 09 12 13 00 PERSONNEL INJURIES NUMQEA DESCRIPTION
~00 0 NA 7 89 11 12 00 5%8%< CONsEoUENCES PROBABLE NA Qqg 7 09 80 LOSS OR DAMAGE TO FACILITY TYPE DCSCAIPTION
~Z NA 7 09 10 PUOLICITY h h
NA 7 09 ADDITIONAl. FACTORS Q~g NA 7 09 00 Qg 7 09 00 PHONE:
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LICENSEE EVENT REPO- s CONTROL BLOCK: (PLCAOE PRINT ALL REQUIRED INFORMATION) 1 6 s UCENSf E LICfNSE EVENT s NAME UCENSC NUMUEA TYPE TYPE
[oaj N I N N P 1 1 1 1 1 ~04
~
7 09 14 15 30 , 31 32 AEPOAT AEPOAT CATEOOAY TYPC SOUACC DOCKET NUMBCfI EVENT DATE AEPOAT DATE
~os coen T ~L 0 5 0 0 22 0 0 7 0 5 7 7 0 7 13 7 7 7,' 57 59 59 80 61 68 69 74 75 80 EVENT DESCRIPTION Qg8 RTD in condenser dischar e failed to maintain re uired acuracy of +3; F.'TD in 7 9 80 denser inlet north water box failed o en. In both cases redundant RTD's were 7 89 80 tooj4 0 erable. Inaccurate instrument recalibrated and returned to service.
- 7. 89
~os 7 8 9 LER 77-35 7 8 9 PAL%!E 80 SYSTEM CAUSE COMPONENT COMPONENT
~
CODE CODE COMPONENT CODE SUPPLEA MANUFACTUAEA VIOLATION
[onsI ~HE E N 5 T R 0 L c .5 1 5 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION
~o e Instrument drift caused inaccuracy of about I', P in condenser discharge RT0 8 9 *" 80 Q~ 8 Failed instrument wi 11 be replaced and/or repaired.
7 8 9 80 7 89 METHOD OF 80 FACILITY STA'IUS 55 POWEA OTHER STATUS DISCOVEAY OISCOVEAY DESCAIPTION Q'g N ~00 0 NA Surveillance Test - Calibration 7 8 9 10 12 13 44 45 46 80 FOAM OF ACTIVITY COATENT ACLEASEO OF AELEASE 'MOUNT OF ACTIVITY LOCATION OF AELEASE Q~g Z Z NA 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBEA TYPE DESCAIPTION 0 Z NA 7 89 11 12 - 13 80 PERSONNEL INJURIES NUMBEA OESCAIPTION 00 0 NA 7 8 9 11 12 80
>QXRIXK cONSEoUENCES PROBABLE Q1g NA 7 89 80 LOSS OR DAMAGE TO FACILITY TYPE OESCAIPTION NA Q~g Z 89 10 80 PUQLICITY NA 1.6(
7 8 9 6y >
ADDITIONAL FACTORS Q~g NA 9HiSS~~O" 7 0 9 gaHAJ 80 7 09 NAME: PHONE:
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LICENSEE EVENT REPOR CONTROL BLOCK: (PLEASE PRINT AU. RL'QUIRED IIIIFOAMATION)
UCENSEE UCENSE EVENT NAME LICENSE NUMBER TYPE TYPE Jog N Y II II P 1 41 1 1 1 ~01 7 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE REPORT DATE Ioa~jcoov~ T I. 0 5 0 0 2 2 0 0 7 0 37 7 0 71 3 7 7 7 8 57 58 59 60 61 68 69 74 75 80 EVENT OESCRIPTION >>
toa~] During hydrostatic test found leak at weld between emergency condenser valves 39-01 7 89 80
[oaf and 39-03. Weld was ground out and repaired. Both PT and Radiographic examinations 7 89 80 were made durin and followin re airs.
7.89 80 Qog 7 8 9 80 Jog LER 77-34 7 8 9 PRME 80 SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SUPPUER MANUFACTUAER Ice~l~05 5 P I P 5 'xx A K 05 5 ~N 7 8 9 10 11 12 17 43 44 47 48 CAUSE DESCRIPTION toom Defect was in ori inal weld to valve body. Cause being investigated.
7 8 9
~os 7 8 9
~10 7 89 FACILITY METHOD OF 80 STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION E38 7 9 H ~00 10 0
12 13 NA 44 45 46 Hydrostatic Test 80 FORM OF ACTIVITY COATENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Q1g Z ~Z NA NA 7 8 9 10 45 80 PERSONNEL EXPOSURES 7 89 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION
~<< ~oo o NA 7 89 11 12 80 XIQNM( GQNBEQUENGEs PROBABLE
~15 NA 7 8 9 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION Q~g Z NA 7 09 10 PUBLICITY NA I>> >>> g,>> ~ >>
7 I39 '~ ~"'i ll qoj 80 AOOITIONAL FACTORS 7 89 80 PHONE:
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To- z~FR(N:- ~<'3 43 6ATE/TD'E 1 Tc.3c:ll)l'.n~= tlu"hc.r 'e)@phone limier j ~' (
Ja)m" P. O'Heilly From: Reagan mohawk Pow.r Corpora,%
- 0) rectot of PcguTOCGry Qpcrailon Nine bile Point fluclear Station USllK P.=-":icn Z Bait II'I 637 P;rP. f::enuc P.O.'or. $ 32 Qng 0 Prussia. PA. 19@06 tycceain9, Has York l3093 R;B~ ECT: PPG'.l'7 REPOliTWLE CCCURRENCE MCrET n0. 50-220 LXCBfSE M. DPR-63 A55KG'<EO LEP. NO. 7T- 34 EVDiT DATE: 7 3 77 7/5/TT H'ENT DiSCPIPl ION:
Leak in reactor coolant pressure boundary weld found during hydrostatic test. The we>d is a valve to valve mid fn the Emergency Condenser-Condensate return 1ine.
CO.PO.,<<;;T5 I -OL. ~ Emergency Condenser Valves SV-39-0l, 39-03 CMSE. Nlo ~="!. DEAL ACTION
~ne cause $ s unlcnown cut and repaired.
it the present t$ me The ~'ld mal. be ground PCIUTV STD US:- i TH~mtijou fQ c) Routire Smitup g) Shut:dms cl) Rou ir~ 5'" dc~a h) Refuel ir@
<) Steady 5".3te Oper 0) Other
~ ) k.cad Cl:.=nge y) Rot Applicable P
A r ri-:c~,@33. -up rel>6rt will be sent within be ~ks taL COPY l0 .! 7-
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'TO: i.rate e)%if Java P. O'Rei'l)y Free: Riagaf'il ho[ lDNR'oli'f Corpora/i pn Director. of PcgulatorJJ Operation hive tRi7c Point. huc7ear Station VSlfRC Pi~icn X 633 Part fi.enuc Uoit P.O.
fl Gor. f32 King of Prus ia. PA. 19406 lyccming. Hns York 13093 SUI .'ECE: PR'R:r'T REPORTABLE CCCORREHf:E 60CVET RQ. M-220 LICHISE )IO. DPR-63 ASSESLCD LD'S. 11-c.s'E'le DATE: 7/5/77 RDOaT WTE= 716//TT EVE4T DESCRIPTlAN='=,D in condenser discharge fa4'fed. to maintain +qu=.red ac+racy f ~ oF.
RWi in condenser inlet. orth mter box Vaiied open Kn both cases redundant RTO's ~re operabTe.
CO:lPO:iCllTS D,"iQLV-"0: Resistance Tanperature Oe7ectors (RTD) in condenser in)et and discharge filiD R=~:iGIAL ACTION"
U5E Instant driest caused inaccuracy of'pproximate'Ey f4oF in condenser cfischarge Fii) testkent seas recaiibrated and returned to service Cause of fa47ure to condenser 4n'let RTU's ainkncneo inlet temp.
is being recorded using a redundant RTD.
0 c) Routine S artup 9) Shvtdpwn d) Bpv inc Sh"tdim e> Stairway St>te Oper 0) Other f3 Road Ch...~ge J) Rot App13cQlpl8 g< l:ritter iÃ3p -up report mls be sent lecithin tm scabs 7" "-CO> Y TO FRY ~iz NIL'iL 4i c. NTE ~!
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