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Category:Letter
MONTHYEARNMP1L3608, 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 ML24213A1412024-07-31031 July 2024 Requalification Program Inspection 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 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 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 ML24158A2052024-05-15015 May 2024 Annual Radioactive Environmental Operating Report 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 NMP2L2880, 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 ML24092A3352024-04-0101 April 2024 NRC Office of Investigations Case No. 1-2023-002 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 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) 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 IR 05000220/20230042024-02-0101 February 2024 Integrated Inspection Report 05000220/2023004 and 05000410/2023004 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)) IR 05000410/20243012023-12-14014 December 2023 Initial Operator Licensing Examination Report 05000410/2024301 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 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) 2024-09-04
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-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 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 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 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 . NMP1L3519, Submittal of Emergency 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)2023-03-30030 March 2023 Submittal of Emergency 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) NMP1L3516, Submittal of Emergency 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)2023-03-29029 March 2023 Submittal of Emergency 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) NMP1L3478, Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps2022-08-0505 August 2022 Response to Request for Additional Information - Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs NMP2L2794, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 02022-01-11011 January 2022 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2789, Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-12-16016 December 2021 Response to Request for Additional Information by the Office of Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 NMP2L2787, Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves2021-11-15015 November 2021 Response to Request for Additional Information - Relief Request Associated with Excess Flow Check Valves JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments NMP2L2773, Company - Response to Request for Additional Information2021-06-30030 June 2021 Company - Response to Request for Additional Information JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments NMP1L3402, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 02021-06-0404 June 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-582, Revision 0 JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting NMP1L3376, Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 22021-01-27027 January 2021 Supplemental Information to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Adopt TSTF-334, Revision 2 NMP1L3373, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 22021-01-22022 January 2021 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of License Amendment Request to Adopt TSTF-334, Revision 2 NMP2L2754, Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22021-01-0707 January 2021 Responses to Request for Additional Information Questions 27 and 28 to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 NMP2L2749, Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 22020-10-22022 October 2020 Responses to Request for Additional Information Questions 17 and 26 for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Rev. 2 NMP2L2745, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-10-0202 October 2020 Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 NMP2L2742, Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components2020-08-28028 August 2020 Response to Request for Additional Information by NRR to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request Re Risk Informed Categorization & Structures, Systems and Components ML20188A2642020-07-0606 July 2020 Clinton Power Station, R.E. Ginna Station, Limerick Station, Nine Mile Point Station & Peach Bottom Station - Proposed Alternative to Utilize Code Case OMN-26 - Response to Request for Additional Information NMP2L2713, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates2019-11-21021 November 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Increase Allowable MSIV Leakage Rates NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants NMP1L3264, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Contain2019-02-25025 February 2019 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Revise Technical Specifications 3.3.1 for Primary Containm JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP2L2695, Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The.2018-12-0707 December 2018 Supplement Information and Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of an Emergency License Amendment Request for One Time Extension to The. NMP1L3248, Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pre2018-11-0202 November 2018 Supplement to the Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, Revision 2, Reactor Pres NMP1L3238, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ...2018-10-0101 October 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, License Amendment Request to Apply TSTF-542, ... NMP1L3233, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039)2018-08-17017 August 2018 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 1, Removal of Boraflex Credit License Amendment Request (L-2018-LLA-0039) NMP1L3221, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes.2018-05-10010 May 2018 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 & 2, R. E. Ginna - Response to Request for Additional Information License Amendment Request to Adopt Emergency Action Level Schemes. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) ML18025A7992018-01-25025 January 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP2L2662, Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 22017-12-27027 December 2017 Supplemental Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 NMP2L2658, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water2017-11-0303 November 2017 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation to Support Review of Nine Mile Point Nuclear Station, Unit 2, License Amendment Request to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water NMP1L3180, Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702)2017-09-18018 September 2017 Submittal of Relief Request NMP-RR-001 Concerning Nozzle-to-Vessel Weld and Inner Radii Examinations (Use of Code Case N-702) RS-17-053, Response to Request for Additional Information Regarding Generic Letter 2016-012017-04-27027 April 2017 Response to Request for Additional Information Regarding Generic Letter 2016-01 NMP1L3146, Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J2017-04-0606 April 2017 Response to Request for Additional Information to Relief to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR 50, Appendix J RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-17-027, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-03-10010 March 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal ML17037A2652017-02-0606 February 2017 Response to Request for Information Concerning Regional Meteorological Conditions Characterizing Atmospheric Transport Processes within 50 Miles of the Plant RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure ML16131A6542016-05-0404 May 2016 Response to a Question Raised During the Audit ML16131A6552016-05-0404 May 2016 White Paper Prepared in Response to a Question Raised During the Audit NMP2L2616, Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual2016-03-21021 March 2016 Supplemental Response to Request for Additional Information by NRR to Support Review of Relocation of Secondary Containment Bypass Leakage Paths Table from Technical Specifications to the Technical Requirements Manual 2024-09-12
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'e 5 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>DISTRIBUTION FOR INCOMING MATERIAL 50-410 r REC: CASE E G NRC ORG: RHODE G K NIAGARA MOHAWK PWR DOCD ATE: 04/18/78 DATE RCVD:"<)4/26/78 ,DOCTYPE: LETTER NOTARIZED:
NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 0 RESPONSE TO ORAL REQUESTS MADE BY NRC...FURNISHING INFO CONCERNING SUB JECT FACILITY'UNIT 2)COOLING TOWER.PLANT NAME: NINE MILE POINT-UNIT 2 ENVIRONMENTAL COMMENTS (DISTRIBUTION CODE C002>REVIEWER INITIAL: X JM DISTRIBUTOR INITIAL:~DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 4++++<<+<<<+<+~<++
FOR ACTION: FOR INFO: FOR INFO: INTERNAL: EXTERNAL: ASST DIR MOORE++LTR ONLY(i>PROJ MGR NORRIS+4LTR ONLY(i)VASSALLO+4LTR ONLY(1)KANE++LTR ONLY(EG FILE+%LTR ONLY(i.~N HANAUER++LTR ONLY(1)ERNST+%LTR ONLY<i)YOUNGBLOOD>+LTR ONLY(i>VOLLMER44LTR ONLY<i)J.COLLINS++LTR ONLY(i>LPDR S OSWEGO'Y++LTR ONLY<i)NATL LAB ANL4+LTR ONLY(6)NS I C++LTR ONLY<1)TIC++LTR ONLY(i>ACRS CAT B4+LTR ONLY<0)BR CHIEF REGAN>>LTR ONLY(i>LIC ASST DUNCAN+<LTR ONLY<i)VARGA44LTR ONLY<1)SERVICE4+LTR ONLY(1)NRC PDR++LTR ONLY(i>OELD+<LTR ONLY<i)DENTON/MULLER++LTR ONLY(1)BALLARD++LTR ONLY<1)GAMMILL4+LTR ONLY(2)BUNCH++LTR ONLY<1)-KREGER++LTR ONLY(i>DISTRIBUTION:
LTR 34 ENCL 0 SI ZE: 3P CONTROL NBR: 781160153 t" I l 0 I l(P j(ji Ighfh I~t It 4 II h ,"~~I, h>>~,<<j'I~.p h It I)'ll'*f I It 4~jg W w I I'I P<<r (Wr~
(i\(j jj'<P P'IAGARA MOHAWK POWER CORPORATION NIAGARA l'OHAWK 300 ERIE BOULEVARD, WEST SYRACUSE, N.Y.13202 April 18, 1978 Mr.Edson G.Case, Acting Director Office of Nuclear Reactor Regulation U.S, Nuclear Regulatory Commission Washington, D.C.20555
Dear Mr.Case:
1 I Nine Mile Point Unit 2~Docket No.50-410 CP 1 A Ca CAW~~C/7 C)P7 S ITI CO I'h a 11 The following information responds to oral requests made by your staff regarding the Nine Mile Point Unit 2 cooling tower.Section 8.4.1.3.11 of the Environmental Report-Construction Permit Stage and Figure 14 of the"Report on Circulating Water Cooling System Employing a Natural Draft Cooling Tower," July 1976, do not agree with respect to the predicted area affected by plant noise.The data contained in the latter report are more recent and accurate.These values should be used for plant noise evaluation.
The major reasons for the differences in the predictions are as follows: 1)The Ellis Method used to evaluate noise for the Environmental Report was the best method available at that time.This method was developed fox small cooling towers.The Ellis Method overpredicts noise for large cooling towers.The predictions in the July 1976 report~13 were made using a new method based upon field measurements of a number of large cooling towers.2)The 1976 noise calculations include the effect of atmospheric adsorption for transformer noise.The Environmental Report predictions did not and are therefore louder.78li60],g3 Qo Sy ,(0 p I Mr.Edson Case U.S.Nuclear Regulatory Commission April 18, 1978 Page Two=The discharge hT calculated from the heat addition to the lake value (0.-74 x 109 Btu/hr)on Page 6 of the"Report on Circulating Water Cooling System Employing a Natural Draft Cooling Tower,," July, 1976, does not agree with the value in Response 14 of our September 30, 1977 submittal.
The 19F hT indicated in this latter report is the correct-value and incorporates specific cooling tower vendor predictions.
The discharge,hT of 19F is an annual average based on.a discharge flow of 25,000 gallons per minute.The earlier calculations were not based, upon a specific tower since the vendor had not been selected at that time.The worst case lake surface temperature increase is about 2.7F.This corresponds to a combined plant discharge hT of 30.6F and a flow of 18,.020 gallons per minute.These calculations are based upon conservative worst case conditions of 32F lake.temperature and a wet bulb air temperature of 57F at 45 percent relative humidity.Air temperature was selected from Rochester weather data for the period 1933 to 1972, and lake temperature was based upon 1972 weather conditions.
Very truly yours, NIAGARA MOHAWK POWER CORPORATION Geral K.Rh de, Vice President System Project Management NLR/szd
)P Mr.Edson Case U.S..Nuclear Regulatory Commission April 18, 1978 Page Three REFERENCES 1 R.M.Ellis, Coolin Tower Noise Generation and Radiation Journal of.San an Vibration, Vo ume 1 , Pages 17-1 2, 1971.2 Capano, G.A.;Bradley, W.E.,"Radiation of Noise From Large Natural Draft and Mechanical Draft Cooling Towers" ASME Paper No.74-WA-HT-55.
3 Capano, G.A.;Bradley,-W.E.,"Noise Predicting Techniques for Siting Large.Mechanical Draft Cooling Towers" presented at the 38th Annual Meeting of American Power Conference, April, 1976.
J~~
DIS-ocket fi Local PDR SVarga~LP[1: HService LWR-4 Attorney OEL'D
'I UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.20666 Docket No.50-410 APR 311978 Niagara Mohawk Power Corporation ATTN: Mr.Gerald K.Rhode, Vice President Systems Project Management 300 Erie Boulevard West Syracuse, New York 13202 Gentlemen:
SUBJECT:
REVISED INTRUSION DETION SYSTEMS HANDBOOK-Nine Mile Point 2 Transmitted under separate cover is a revision of the Intrusion Detection Handbook, SAND 76-0554, which may have been sent to you in 51ay 1977.This handbook revision was prepared by the Facilities Protection Department, Sandia Laboratories, Albuquerque, New Mexico under contract with the Division of Safeguards and Security, Department of Energy (DOE)and is made available for your information as a reference source for use.in the design, installation, and operation of intrusion detection systems.The attached revision supersedes the previous version.In addition, we are also including two other reports in the same series: "Nuclear Safeguards Technology Handbook" dated December 1977, which outlines current safeguards technology development programs, and"Entry Control System Handbook" dated September 1977, which describes systems used to'ontrol access to and egress from controlled areas.These documents are marked"Official Use Only." In releasing them to you, we request that distribution of the documents be controlled so that sub-sequent revisions may be sent to all recipients.
Feedback from recipients of these handbooks should be addressed to Dr.Samuel C.T.McDowell, Assistant Director for Research and Development, Office of Safeguards and Security, Department of Energy, Washington, D.C.20545.Sincerely,
Enclosures:
(3)Under separate cove~D.B.Vassallo, Assistant Director for Light Water Reactors Division of Project Management cc w/o enclosures:
See next page
Niagara fdohawk Power Corporation V'(ccs: Arvin E.Upton, Esq.LeBoeuf, Lamb, Leiby 5 MacRae ,,1757 N Street, N.M.Mashi'ngton, O.C.20036 Anthony Z.Roisman, Esq.Natural Resources Defense Council 917 15th Street, N.M.Mashington, O.C.20005 ter.Richard Goldsmith Syracuse Universi ty College of Law E.I.Mhite Hall Campus Syracuse, New York 13210.T.K.DeBoer, Director Technological Development Programs New York State Energy Office Swan Street Building Core 1-2nd Floor Empire State Plaza Albany, New York 12223
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I).>/a s~..i I I~Stol z V,.Voipl 0.I)a I'r S.V(1vq<1 I..C>n~I:ri I).4 s, I.cl!i'.l I.Ilil I ic~'-, I?.t la I.l.'ski>>II.I)<>)I p~~I).I'pl I er Pro jpr I Rttnir>>y, l.l I>HY I t'OI1 IL ("3)RC~S (IC)L..1)rnllr.;r Iff1C I'ai<i~i>>~l",: S.Bulipoc I,p;i
/7
~pR Rf 0y 0.-r W~++*++UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C.205SS APR 1 8 1978 Docket Nos: 50-358 50-387 50-352/353 50-367 50-373/374 50-388 AO-410 50-322'PPLICANTS:
Members of Mark II Owner's Group
SUBJECT:
MEETING WITH MARK II OWNER'S GROUP AND GENERAL ELECTRIC COMPANY TO DISCUSS THE MARK II CONTAINHENT POOL DYNAMICS LOAD PROGRAM-APRIL 6, 1978-SAN JOSE~kd: The staff's Hark II Containment Task Group (Task Action Plan No.A-8)met in Livermore, California and San Jose, California on April'th and April 6th respectively to discuss the Livermore Fluid Structure Interaction Program and Submerged Structure Drag Loads Program and the Owner's Group Monticello SRV, Fluid Structure Interaction Studies, the staff's Pool Temperature Limits review, the 4T Fluid Structures Interaction Studies and other matter's related to Hark II Containment Pool-'ynamics.
These meetings will be reported later when information becomes available from the Task Group.The DPM Hark II coordinator attended the San Jose meeting only.~Summar: 4 General Electric made a presentation'n the effort underway to show that 4T impulse loads at the wall result in responses that will be bounded by the preveously defined bounding loads.GE will informally write up what it is doing in this effort and provide the information to the staff.Another meeting will be held in Bethesda in about three weeks to present the results.GE made a presentation on the FSI-SRV work using the Montecello bench work study to show that flexibility in the pool wall does not introduce lack of conservatism in comparison with the Livermore work.The staff reported its preliminary conclusio8 that data are not adequate to support the pool temperature limit of 150 F for the ramshead.A position paper on this matter is being reviewed by management within the NRC.
APR 18 1978 The discussion on impact loads was deferred until the end of April at which time GE will address this problem.All Nark II owners who originally planned to use the ramshead device have not made the decision to switch to quencher devices.The Cincinnati Gas and Electric Company (Zimmer)has decided to switch.It intends to continue plant analyses and modification on the basis of its own definition of'ramshead bounding loads in anticipation that the quencher will provide additional margin.The staff cautioned CG8E that the DFFR loads are not necessarily acceptable to the staff and that the burden is on the applicant to'establish that quencher loads are less than whatever bounding loads are'sed by the applic'ant.
At this time the Hark II owners plan to address SRV second actuation problems on an individual plant basis.I.Peltier, Project Manager Light Water Reactors Branch No.1 , Division of Project Management cc: See Following Pages 0
Niagra Mohawk Power Corporation ATTN: Mr.Jerald K.Rhode Vice President Engineering 300 Erie Boulavard West Syracuse New York 13202 Eugene B.Thomas, Jr.LeBoeuf, Lamb, Leiby&MacRae 1757 N Street, N.W.Washington, D.C.20036 Anthony Z.Roisman, Esq.Roisman, Kessler&Cashdan 1025 15th Street, N.W.Washington, D.C.20036 Mr.Richard Goldsmith Syra'cuse University College of Law E.I.White Hall Campus Syracuse, Nevi York 13210 T.K.DeBoer, Director Technological Development Programs New York State Energy Office Swan Street Building Core 1-2nd Floor Etapire State Plaza, Albany, New York 12223 APR 18 1978-1 Washington Public Power Supply System ATTN: Mr.Kneil 0.Strand Managing Director 3000 George Washington Way Richland Washington 99352 Joseph B.Knotts, Jr., Esq.Debevoise 5 Liberman 700 Shoreham Building 806 Fifteenth Street, N.W.Washington, D.C.20005 Richard g.guigley, Esq.Washington Public Power Supply System P.0.Box 968 Richland, Washington 99352 PAP.R 78 1978 0
Pennsylvania Power and Light Company ATTN: Mr.Norman W.Curtis Vice President,-
Engineering and Construction 2 North Ninth Street Allentown, Pennsylvania 18101 Mr.Earle M, Mead Project Manager Pennsylvania Power&Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Gerald Charnoff, Esq.Shaw, Pi.ttman, Potts, Trowbridge
&Madden 1800 M Street, N, W.'ashington, D.C.20036 Mr.William E.Barberich Licensing Engineer Pennsylvania Power&Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Mr.Robert J.Shovlin, Project Manager Susquehanna Pennsylvania Power&Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Hubert Barnes, Esq.Pennsylvania Power&Light Company 901 Hamilton Street Allentown, Pennsylvania 18101 Edward M.Nagel, Esquire Genera'I Counsel and Secretary Pennsylvania Pov(er'&Light Company'North Ninth Street Allentown, Pennsylvania 18101 APR>8 1978
Commonwealth Edison Company ATTN: Nr.Byron Lee, Jr.Vice President P.0.Box 767 Chicago, Illinois 60690 Richard E.Powell, Esq.Isham, Lincoln&Beale One First National Plaza 2400 Chicago, Illinois 60670 APR 18 1978
Northern Indiana Pub 1 i c Service Company ATTN: Mr.H.P.Lyle, Vice President Electric Production 8 Engineering 5265 Holman Ave.Hammond, Indiana 46325 Meredith Hemphill, Jr.Esq.Assistant General Counsel Bethlehem Steel Corporation Martin Tower Bethlehem, Pennsylvania 18016 William H.Eichhorn, Esq.Eichhorn, Morrow 8 Eichhorn 5243 Hohman Avenue Hammond, Indiana 46320 Edward W.Osann, Jr., Esq.Wolfe, Hubbard, Leydid, Voit 8 Osann, Ltd.Suite 4600 One IBM Plaza Chicago, Illinois 60611 Marvin N.Berm, Esq.Special Assistant Attorney General 134 North LaSalle Street Suite 2222 Chicago, Illinois 60602 Robert J.Vol)en, Esq.109 North
Dearborn Street Chicago,
Illinois 60602 APR 78 1978
~e The Cincinnati Gas 5 Electric Company ATTN: Mr.Earl A.Borgmann Vice President-Engineering P.0.Box 960 Cincinnati, Ohio 45201 Mr.William J.Moran General Counsel The Cincinnati Gas 8 Electric Co.P.0.Box 960 Cincinnati, Ohio 45201 Hr.William G.Porter,'Jr.Porter, Stanley, Arthur, 8 Platt 37 West Broad Street Columbus, Ohio 43215 Mr.Robert Killen, Chairman of the Board 8 Chief Executive Officer The Dayton Power 5 Light Company P.0.Box 1034 Dayton, Ohio 45401 Mr.J.Robert Newlin, Counsel The Dayton Power 8 Light Company P.0.Box 1034 Dayton, Ohio 45401 Mr.Stephen Schumacher Hiani Valley Power'roject P.0, Box 252 Dayton, Ohio 45401 David B.Fankhauser, PhD 3569 Nine Mile Road Cincinnati, Ohio 45230 Thomas A.Luebbers, Esq.Cincinnati City Solicitor Room 214-City Hall Cincinnati, Ohio 45202 Troy B.Conner, Esq.Conner, Moore 8 Cober 1747 Pennsylvania Ave.N.W.Washington, D.C.20006 Hs.Augusta Price 601 Stanley Avenue Cincinnati, Ohio 45226 Mr.James D.Flynn Manager, Licensing 8 Environmental.
Affaii s The Cincinnati Gas 8 Electri.c Company P.0.Box 960 Cincinnati, Ohio 45201 Hr.J.P.Fenstermaker Senior Vice President-Operations Columbus&Southern Ohio Electric Co.215 North Fr.it Street Columbus, Ohio 43215
'I~)'V APR 18]97)Philadelphi Electric Company ATTN: Mr.Edward G.Bauer, Jr.Vice President and General Counsel 2301 Market Street Philadelphia, Pensylvania
.19101 Troy B.Conner, Jr.Ewq.Conner, Moore 5 Corber 1747 Pennsylvania Avenue, N.W;Washington, D.C.20006 W.William Anderson, Esq.Deputy Attorney General*Room 512, Main Capitol Building Harrisburg, Pennsylvania 17120 Frank R.Clokey, Esq.Special Assistant Attorney General Room 218, Towne House Apartments P.0.Box 2063 Harrisburg, Pensylvania 17105 Honorable Lawrence Coughlin House of Representatives Congress of the United States Washington, D.C.20515 Roger B.Reynolds, Jr., Esq.324 Swede Street Norristown, Pennsylvania 19401 Willard C.Hetzel, Esq.312 main Street East Greenville, Pennsylvania 18041 Lawrence Sager, Esq.Sager&Sager Associates 45 High Street Pottstown, Pennsylvania 19464 Joseph A.Smyth Assistant County Solicitor County of Montgomery Courthouse Norristown, Pennsylvania 19404 Eugene J.Bradley Philadelphia Electric Company Associate General Counsel 2301 Market Street Philad'elphia, Pennsylvania 19101 T~~
Long Island Lighting Company ATTN: Mr.Andrew W: Wofford Vice President 175 East Old Country Road Hicksville, New York 11801 Edward M.Barrett, Esq.General Counsel Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 Edward J.Walsh.Esq.General Attorney Long Island Lighting Company 250 Old Country Road Mineola, New York 11501 Mr.Thomas Burke Project Manager Shoreham Nuclear Power Station P.0.Box 618 Wading River, New York 11792 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plazq Albany, New York 12223 Haward L.Blau Blau and Cohn, P.C.380 North Broadway jericho, New York 11753 Irving Like,,Esq.
Reilly, Like and Schnieder 200 West Main Street Babylon, New York 11702 MUB Technical Associates 366 California Avenue Suite 6 Palo Alto, California 94306 APR 18 1978
F~JR RSGIJ('fp+0 Cy~O++*+4'ocket No.50-410 t UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 April 14, 1978 Niagara Mohawk Power Corporation ATTN: Mr.G.K.Rhode Vice President System Project Management 300 Erie Boulevard, West Syracuse, NY 13202 Gentlemen:
Enclosed is IE Bulletin No.78-05 which requires action by you with regard to your power reactor facility(ies) having an operating license or a construction permit.Should you have questions regarding this Bulletin or the actions required, please contact this office.Sincerely, Boyce H.Grier Director
Enclosures:
l.IE Bulletin No.78-05 2.List of IE Bulletins, Issued in 1978 cc w/encls: Eugene B.Thomas, Jr., Esquire 1 M-h UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.20555 IE Bulletin No.78-05 Date: April 14, 1978 Page 1 of 2 MALFUNCTIONING OF CIRCUIT BREAKER AUXILIARY CONTACT MECHANISM-GENERAL ELECTRIC MODEL CR105X Description of Circumstances:
The Sacramento Municipal Utility District recently reported a problem encountered with the operation of the GE Model CR105X auxiliary contact mechanism installed in a 480 volt circuit breaker.Investigation into the cause for the inability to shutdown a booster supply fan (SF-A-7)in the control room emergency air conditioning system revealed that an auxiliary contact (GE Model CR105X)had failed in the closed position, preventing the fan's power supply circuit breaker from opening.The specific cause for failure was binding of the plunger arm due to burrs and nicks on its surface.An investigation was conducted by the licensee to determine the extent of usage of this type auxiliary contact in other circuits throughout the reactor power plant.Approximately fifty (50)positions in the nuclear service motor control centers were identified as having a similar type auxiliary contact mechanism.
It was also determined that many of the affected systems which require contact operation similar to that described above, either permit or provide a safety feature function during emer-gency conditions.
An example of this type application is auxiliary , contacts that must open to permit closing of certain safety related valves from 480 volt motor control centers.The attached GE Service Advice Letter and associated instruction/drawing sheet were sent to all nuclear power reactor facilities by GE Field Service Offices.The letter, together with the instruction/drawing sheet identifies the problem and provides the recommended corrective action.
~y IE Bulletin No.78-05 Date: April 14, 1978 Page 2 of 2 Action To Be Taken By Licensees and Permit Holders: for all power reactor facilities with an operating license or construc-tion permit: l.If you have received the enclosed General Electric letter and instruction/drawing sheet addressing the auxiliary contact mech-anism problem, and if you have these devices in use at your facility, it is requested that you describe what corrective action you have taken.2.If you have not received the enclosed GE documents before, it is requested that you describe what action you plan to take if the GE CR105X auxiliary contact mechanism is in use or planned for use in safety systems at your facility(ies).
3.Facilities having an operating license should report in writing, within 45 days, and facilities with construction permits within 60 days, the results of action taken or planned with regard to Items 1 and 2 above.Your written reply should also include the date when such actions were or will be completed.
Reports should be sub-mitted to the Director of the appropriate NRC Regional office and a copy should be forwarded to the U.S.Nuclear Regulatory Commission, Office of Inspection and Enforcement, Division of Reactor Operations Inspection, Office of Inspection and Enforcement, Washington, D.C.20555.Approved by GAO, 8180225 (R0072);clearance expires 7/31/80.Approval was given under a blanket clearance specifically for identified generic problems.Attachments:
1.GE Letter 2.GE Control and Instruction Sheet h~
ConttOI IN STRU CTlONS 1QSX AUXf LtARY CONTACT (CHANGt=GUT OF Pt UNGEFt ARM AND lNSULRTlON) for nema size 0 8 5 magnetic starters and contractors REMOVING OVERLOAD RELAY BRACKET (SE Fi" 1)1, Rcmove all otcctricat power fram device.2.Oisassembte device by pressing an the coil while pulling out ca the coil retainers.
Move retainers back and away from coiL 3.Grasp movable~ion of magnet and pull out.remeving magnet assembly.coil, molded cover and movable arm in ane motion.(NGTK: On revorsers ar multispoed starters, this magnet assembly is linked ta the mechanicat interlock arm between cantactars and should be t I p pod toward iaterlack alm to tacitnate easy removaL)4.Remove overload relay bracket by sliding tt out ef the keyed sets m the molded base.(NOTE: lf any wires are tao short to aticw easy renwvaL temporarily disconnect these.)5.Remove overload relay fram bracket by loosening screw on bottom of overload bracket:%4 QV EALQAO RBJLY S4CXArrlttO BRACKET-'i rf I~CCNi.RETAiNCRS'~'NOVA8LK SiAGttKT ASS gtrutLY 7 ttKyED , SLciT8., CHANGING PLUNGER ARM 4 INSULATION (SKK FtG.2)Slide plunger assembty out ot auxiGary contact block.by lifting up and out.2.Select the new plunger arm that is bent the someway as the ene installed.
3.Lcason screw aa plunger ta release metal arm but OO ttOT RKhlOVK SCREW FROM PHKNOUC PLUtf GER (OR PLLtN GERS).4.Mauat nrw plunger arm on plunger.Fasten arm to plunger with screw (or plunger pc t if installing double aux.blacks).5.Apply thin coat at aeroshett grease along plunget'uides.
6.Reinstall plunger assembty in contact black.7.Peassemble overload to mounting bracket.Remove overload~insulation and install new.(NOTE;Overload insulation must be removed and replaced with new insulatiaa supplied with kit)tL Romaunt complete assembly cn cantactor base.I ct.Reconnect any wires previously removed.10.Reassemble magnet assematy to contact base-(on revorsers or multtspeeds be sure ta interlock this assembly with mechancat interlock arm.Check for tree movement ef armature assemblies and mechanics',interlocks).
11.Observe that auxiliary cancxct ptungcr aamnbties are operating pf cperfyo 4'>>r 4 r I~r<<Ot>>Q',.'z]i A'i,.F)GVRE 1 RKMOVtNG OVKRLOAO RELAY MOV rtTt NQ BRACKET 4>>r r 4 r fr 4r rr 4 Oorr rr I4rr%>>4t~44'rr'l&TV>lClL DOVILX 4USll.laltJEl4VWLV lgrrr arw7l FIGURE 2 GKNKRAl.ELECTRIC COMPANY GENERAL FrJRPOSK CONTROL GKPARTLlKtfT g K N E R A L We,~<~, E L E tl T R I
It has been brought to our attention that a potential binding problem may exist with the 100 Line CR105X...auxiliary inter locks mounted on HEMA size 00, 0 and 1 contactors, starters, or reversers used in control equipment manufactured by General Electric Co.(including 7700 Line motor control centers)and other control equipment manufacturers.
The interlocks involved are used on the following devices.CR105A,-B.,-C,-H,-J,-K,-R,-S with additional suffix letters and numbers (contactors}
CR106A,-B,-C,-H,-0,-K,-R,-S with additional suffix'1et ers.and numbers (starters)
CP109A,-B,-C.-H,-0, K,-R,-S with additional suffix letters and numbers (t eversing starters)If any of these devices are currently used in your installations, you should obtain replacement parts to correct this condition by forwarding the following information to my attention:
1.Complete catalog (CR)numbers on device nameplate.
2.guantity of each device catalog number.3.Are the auxiliary interlocks mounted on the left side, right side, or both sides of the device?How many are there at each location?Since the General Purpose Control Department of the General Electric Co.does not know all applications of these interlocks,'t is assumed that some may be in"critical" applications and should be changed out as soon as possible, while those in non-critical applications may be changed out at some routine maintenance period.Since these interlocks are on devices which have been in service for over one (1)year and are out of our normal warranty period, we feel a fair and equitable solution would require that the necessary parts and instructions for the'uggested changeout be provided by GE at no expense to the user.At your ear liest convenience, please provide me with the information requested in paragraph 2 of this letter so that the necessary parts may be provided.This information should be forwarded to: General ElecWic Company P, 0.Box 2913 Bloomington, Illinois 61701 Attention: (Oial Com: Hr, John E.Corbitt Product Service 8~325-4416, or 4294)Attachment 1 Page 1 of 1
ENCLOSURE 2 LISTING OF IE BULLETINS ISSUED IN 1978 IE Bulletin No.78-05 April 14, 1978 Bulletin Subject No.Date Issued Issued To 78-01 78-02 78-03 78-04 Flammable Contact-'rm Retainers in G.E.CR120A Relays Terminal Block qualification Potential Explosive Gas Mixture Accumula-tions Associated with BWR Offgas System Operations Environmental guali-fication of Certain Stem Mounted Limit Switches Inside Reactor Containment I/16/78 1/30/78 2/8/78 2/21/78 All Power Reactor Facilities with an Operating License (OL)or Construc-tion Permit (CP)All Power Reactor Facilities with an Operating License (OL)or Construc--tion Permit (CP)All BWR Power Reactor Facilities with an Operating License (OL)All Power Reactor Facilities with an Operating License (OL)or Construc-tion Permit (CP)Page 1 of 1 I