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 ...ML18018B257 |
Person / Time |
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Site: |
Nine Mile Point ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
06/12/1978 |
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From: |
Schneider R Niagara Mohawk Power Corp |
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To: |
Grier B NRC Region 1 |
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References |
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LER 78-020-00, LER 78-021-00, LER 78-022-00, LER 78-023-00 |
Download: ML18018B257 (12) |
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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
REGULATORY INFORMATION DISTRIBUTION SYSTEM < RIDS)
DISTRIBUTION FOR INCOI"IING MATERIAL 50-220 REC: GRIER B ORG: SCHNEIDER R R DOCDATE: 06/12/78 NIAGARA MOI-IAIJK PIJR DATE RCVD: 06/16/78 H'RC DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING LICENSEE EVENT REPT <RO 50-220/78-020) ON 05/26/78 CONCERNING DURING ROUTINE STARTUP OPERATIONS'ERFORMANCE OF SURVEILLANCE TEST Ni-1SP-RE18 FOUND RE18A WITH A SETPOINT OF 135 WC... IJ/ATT LERS78-021 78-022)73-023. d PLANT NAME: NINE MILE PT UNIT 1 REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:
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~01 7 8 9 N Y N LICENSEE CODE M P 1 14 Q20 i5 0 0 0 0 0 LICENSE NUMBER 0 0 0Qo 25 26 4 1 1 LICENSE TYPE 1 1 30 Qs~Qs 57 CAT 58 CON'T
~01 7 8 soURcE LiJQB 60 61 0 5 0 0 DOCKET NUiVIOER GB 0 G9 EVENT DATE 7 8Qs0 74 75 6 1 REPORT DATE 2 7 8 Qo EVENT DESCRIPTION AND PROBABLE CONSEQUENCES Q10 During routine startup operations, performance of surveillance test Nl-ISP-RE18, found RE18A with a setpoint of 135 inches wc. Required setpoint of Rx Lo-Lo-Lo water 1 evel i s (/= 1 27. 1 inches wc +/- 2. 6 5 inches wc . Thi s condi ti on resul ted in minimal sa fety imp 1 i cati ons ~
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~03 28 ATTACHMENT CODE 29 NPRDR TYPE
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36 37
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~NQ2, 43 44 MANUFACTURER B 0 8 0 47 Q2B CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o The change in setpoint ex erienced on the Barton Model 288 level indicating switch was due to instrument drift. It was reset to 126.0 inches wc. Current surveillance testing schedules are ade uate to 3 i nsure early detecti on of future instrument dri fts ~
~Q 7 8 9 80 FACILITY STATUS
~
'4 POIVER OmenSTATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 CO 5 C Q
28 0 4 5 2o NA ~BQ31 45 nG Sur vei 1 1 ance Testing 80 ACTIVITY CONTENT
~B RELEASED OF RELEASE
~Z Q3. Z NA AMOUNTOF ACTIVITY Q NA LOCATION OF RELEASE Q Q34 7 8 9 10 11 4n 45 80 PERSONNEL EXPOSURES NUMBER TYPC DESCRIPTION Q3O
~l7 ~0000 00Q or Z Q os NA 7 8 9 11 12 13 80 PERSONNE. L INJURIES
~O""'O""O '"'"NA"'"
Qso 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43
~IB Z Q4. NA 7 8 9 10 80 PUBLICITY NRC USE ONLY 8 9 10 68 69 '80 o D.K. MacVi ttie 315-343-2110 xl 558 NAME OF PREPARER PHONE:
(
NQC FORM 3GG U. S. NUCLEAR REGULAFORY COfs1hIISSION (7-77) ii4 LICENSEE EVENT REPOR CONTROL BLOCK:
I ,Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
~01 7 8 9 N Y N LICENSEE CODE M P 1Q20 14 I5 0 0 0 0 LICENSE NUMBER 0 0 - 0 0 25 Q34 26 1 1 1 LICENSE TYPE 1
30 Qs~Qs 57 CAT 58 CON'T
~01 ,"", ~LQs 0 5 0 0 0 2 2 0 Qi 0 5 2 7 7 8 Qs~06 I 2 7 8 Qg 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO Durin routine startu o erations, erformance of surveillance test Nl-ISP-RE04, found RE04A and RE048 with a setpoint of 3.65 PSIG.. The required setpoint of these drywel 1 high ressure switches is 3. 50 PSIG
+/- 0. 053 PSIG. Thi s condi ti on resul ted in minimal safety impl i cations.
~DG
~O7
~08 80 7 8 9 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 7 8
~IB 9 10 Qii 11 E ~EQis 12 13 I N S T R 0 18 Q ~SQis 19
~ZQis 20 SEQUENTIAL OCCURRENCE REPORT REVISION Ql7 LERIAO REPORT ACTION . FUTURE EVENT YEAR
~78 21 22 EFFECT
+
23 SHUTDOWN
~02 24 REPORT NO.
1 26 Q~
27
~03 28 ATTACHMENT CODE 29 NPADQ TYPE
+L 30 31 PRIhIE COMP.
NO.
+0 32 CONIPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FOBh'I SUB. SUPPLIER h'IANUFACTURER 33 Qis ~ZQis 34
~ZQss 35
~ZQ 36 37 0 0 0 40
~NQss 41
~YQss 42
~NQss 43 44 8 0 8 0 Qs 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o These changes in setpoints experienced on Barton Model 289 pr essure indicating switches were due to instrument drift. RE04A was reset at 3.52 PSIG, and RE048 was reset at 3.50 PSIG. Current surveillance testing schedules are adequate to insure early detection of future instrument drifts, 8 9 80
~
7 FACILITY METHOD OF STATUS '4 POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32 5 0 Qss ~06 0 Qss NA
~Q31 Surveil lance Testing 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT G
RELEASED OF RELEASE
~~ Q33 Z NA AMOUNT OF ACTIVITY Q NA LOCATION OF RELEASE QG Q34 7 8 9 10 45 80 PERSONNEL EXPOSURES NUhIBEA TYPE DESCRIPTION Q39
~l7 ~00 0 Qss Z Qss NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCAIPTIONQ4 s ~00 0 Qs NA 7 8 9 11 12 80 LOSS OF OA DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q42 NA 7 8 9 10 80 PUBLICITY O
ISSUED
~NQ44 DESCRIPTION NA Q NRC USE ONLY ss o
I 7 8 9 10 68 69 80 o NAME oF PREPARER D. K. MacVi ttie PHONEI 315 343 21 0
\6
1 0
NQC FORM 360 U. S. NUCLEAR 11EGULA IOIIY CLIIEINEIlb'LE14 (7 77) 0 LICENSEE EVENT REPOR CONTROL BLOCK:
I ,Q {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 7 8 9 N Y N H LICENSEE CODE P 1 14;5 2 0 0 - 0 0 0 0 LICENSE NUMBER 0 0 0 25 Q 3 26 4 1 1 LICENSE TYPE 1 1 30 Q4~0557 CAT 58 CON'T 7 8 cE ~LQB 60 61 0 5 0 0 0 DOCKET NUMBER 2 2 0 Q o 7 EVENT DATE 7
74 Q 6 1 REPORT DATE 80 QB EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO Durin routine startu o erations erformance of surveil nc 3 ISI'-02-13 t'ound turbine antici ator tri b ass reactor scram 521itcb
~04 02-13A Yrith a set oint of 367 PSIG. This exceeds the 355 + - 5 PSIG
~0 s specified by procedure. This condition resulted in minimal safet
~0 B im lications. Redundant instrumentation was available in the channel.
~os 80 7 8 9 SYSTEh1 CAUSE CAUSE Coh1P. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE 0" 2 0'2 ~2 0>> I N S T R 0 Q14 ~6015 ~Z 015.
7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Qll LE ATRO REPoRT ACTION . FUTURE EVENT YEAR
~ra 21 22 EFFECT
~
23 SHUTDOWN
~02 24 REPORT NO.
2 26 Q~
27
~02 28 ATTACHMENT CODE 29 NPRD<
TYPE Lil 30 31 PRlh'IE CohIP.
LJ NO.
32 COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER L~JQLJQ MQ20 L~JQ 0 0 ~ L~JO MQ24 L~JQ25 B 0 7 0 Q
33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 0 The change in tri p setpoint on the Bar ksdal e Hodel 2T-A1SS ressure switch was due to instrument drift. It was reset to 357 PSIG. Current surveillance testing schedules are adequate to insure early detection 3 of future i nstrument dri fts ~
4 8 9 80
~
7 F AC I LI T Y ~30 h1ETHOO OF STATUS % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Q32
~ls 0 Q25 [0060J025 NA 44
~BQ31 Survei 1 lance Tes tin 7 8 9 10 12 13 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITYQ3 LOCATION OF RELEASE QB
~IB ~Z Q33 Z Q3. NA NA 7 8 9 10 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 1 ~00 0 Qsl Z Qss NA 7 8 9 11 12 13 80 PERSONNEL INJURIES 7 8 9 11 12 80 LOSS OF OA DAMAGE TO FACILITY TYPE DESCRIPTION Q43 7 8 9 zQ 10 NA 80 PUBLICITY NRC USE ONLY ISSUED DESCRIPTION Q45 PE O L~JQ44 NA 2'0 7 8 9 10 68 69 ER D.K. HacVittie 315-343-2110 x1558 0 NAME OF PREPARER PHONE:
NBC FUBM 3IIB (7w77'I w
CONTROL BLOCK:
I t LICENSEE E'IJ'ENT REPO 6
Q U. S. ITIUCLLAIIHEQULA I OHY COR2IiuilSSIVid (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
~o1 7 8 9 N Y N H LICENSEE CODE P 1 14 Q20 15 0
LICENSE NUMBER 25 Q34 26 1 1 LICENSE TYPE 1 1 30 OR~OR 57 CAT 58 CON'T Q70 5 2 6 7 8 QB 0 6 1 2 7 8 80 QB 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO
~o 2 During routine startup operations, LPRN res onse was monitored duri
~33 control rod withdraws1s. This testing found two LPRN detections AFiB in LPRN string 28-33 cross connected to APRHS ll and 15. This resul-ed in APRN 1 1 having one LPRM detector input from Level 8,. and APRH 1 5 having one input from Level A. This condition resulted in minimal safety impl i cations . T. S. 3. 6. 2a ( 10) al 1 ows an APRH to be o erati onal B wi th al 1 A and 8 1 evel LPRN detector in uts b assed.
7 8 9 80 SYSTENI CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE CORIPONENT CODE SUBCODE 'UBCODE
[oO~)
8
~IA 9 10 Q11 11 A Q12 ~CQ13 12 13 I N 5 T R U 18 04 ~EQ15 19 20 Z O16 SEQUENTIAL OCCURRENCE REPORT REVISION Q17 LEBERO REPoRT ACTION . FUTURE EVENT YEAR
~78 21 22 EFF ECT
+
23 SHUTDOWN
~02 24 REPORT NO.
3 26
+W 27
~03 28 ATI'ACHMENT CODE 29 NPRO 4 TYPE 30 PRIME COhIP.
31 NO.
32 COMPONEiNT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER
~EOEE ~ZQEO ~ZQEO ~ZO27 0 0 0 0 ~NO23 ~NQ24 8 0 8 0 Qss 33 34 35 36 37 40 41 42
~NOTE 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 0 Thi s GE-NA-1 00 LPRH S/N 661 0724 was repl aced duri ng the 1 ast schedul ed
.unit outage. During replacement, the two detectors covered b this report were connected to the wrong APRHS. These were reconnected to 3 the proper APRHS, and a special instrument maintenance procedure was generated to cover verification of cable connections.
7 8 9 80 FACILITY STATUS 38 POWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32 s ~COTE ~05 4 Qs NA ~C Q31 Monitored LPRN responses 7 8 9 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY Q LOCATION OF RELEASE Q 7 8
~zQ33 9 10 z
Q 44 NA 80 PEASONNEL EXPOSURES 7 8 9 11 12 13 80 PERSONNEL INJURIES NUhiBEA DESCRIPTION 41 3 ~00 0 Q4o 7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Q43 Z Q42 7 8 9 10 80 PUBLICITY DESCRIPTION ~4 NRC USE ONLY ISSUED
~NQ4 NA 8 9 10 D.K. NacVittie 315 343 2110 x1558 0 NAME OF PREPARFR PHONE
t ~