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Category:Letter type:MNS
MONTHYEARMNS-18-044, Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments2018-07-26026 July 2018
Independent Spent Fuel Storage Installation (Isfsi), Submittal of 10 CFR 72.48 Summary Report from September 15, 2016 to July 26, 2018, No Changes, Tests, or Experiments
MNS-18-036, Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles2018-07-0303 July 2018
Redacted Response to the Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado Generated Missiles
MNS-18-042, Independent Spent Fuel Storage Installation (ISFSI)2018-06-28028 June 2018
Independent Spent Fuel Storage Installation (ISFSI)
MNS-18-040, Submittal of Information Related to Pressurizer Surge and Spray Nozzle Thermal Sleeves Attachment Welds for License Renewal2018-06-26026 June 2018
Submittal of Information Related to Pressurizer Surge and Spray Nozzle Thermal Sleeves Attachment Welds for License Renewal
MNS-18-039, Independent Spent Fuel Storage Installation (ISFSI)2018-06-19019 June 2018
Independent Spent Fuel Storage Installation (ISFSI)
MNS-18-001, Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable2018-05-31031 May 2018
Application to Revise Technical Specifications to Adopt TSTF-234-A Revision 1, Add Action for More than One Dpri Inoperable
MNS-18-030, 2017 Annual Radiological Environmental Operating Report2018-05-15015 May 2018
2017 Annual Radiological Environmental Operating Report
MNS-18-029, Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A2018-05-0909 May 2018
Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A
MNS-18-029, McGuire Nuclear Station, Units 1 and 2 - Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-2018-05-0909 May 2018
McGuire Nuclear Station, Units 1 and 2 - Resolution of Commitments Related to Review Request for the Aging Management Program and Inspection Plan for the McGuire Nuclear Station Units 1 and 2 Reactor Vessel Internals to Implement MRP-227-A
MNS-18-028, Annual Radioactive Effluent Release Report2018-04-25025 April 2018
Annual Radioactive Effluent Release Report
MNS-18-017, Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs2018-02-26026 February 2018
Non-Voluntary License Amendment Request (LAR) to Correct Non-Conservative Technical Specification 3.4.11 - PORVs
MNS-18-018, McGuire, Units 1 & 2, Submittal of Emergency Plan Implementing Procedure Changes2018-02-22022 February 2018
McGuire, Units 1 & 2, Submittal of Emergency Plan Implementing Procedure Changes
MNS-18-009, McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 18-12018-01-31031 January 2018
McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1
MNS-18-003, End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports2018-01-11011 January 2018
End of Cycle 25 In-service and Steam Generator In-service Inspection Summary Reports
MNS-17-050, Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2017-12-13013 December 2017
Review Request for the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A
MNS-17-048, Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-12-12012 December 2017
Response to Request for Additional Information License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies
MNS-17-026, Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles2017-12-0808 December 2017
Submittal of License Amendment Request Proposing to Revise the Bases for Protection from Tornado-Generated Missiles
MNS-17-042, McGuire Nuclear Station, Unit 1, Submittal of Cycle 26, Revision 0, Core Operating Limits Report2017-10-0909 October 2017
McGuire Nuclear Station, Unit 1, Submittal of Cycle 26, Revision 0, Core Operating Limits Report
MNS-17-040, (Mns), Units 1 and 2 - Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force ..2017-09-27027 September 2017
(Mns), Units 1 and 2 - Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force ..
MNS-17-038, Startup Ascension Summary Report Measurement Uncertainty Recapture Power Uprate2017-09-25025 September 2017
Startup Ascension Summary Report Measurement Uncertainty Recapture Power Uprate
MNS-17-039, McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 17-12017-09-19019 September 2017
McGuire Nuclear Station, Units 1 and 2, Submittal of Emergency Plan, Revision 17-1
MNS-17-031, License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition2017-09-14014 September 2017
License Amendment Request for Temporary Changes to Technical Specifications to Address an 'A' Train Nuclear Service Water System (Nsws) Non-Conforming Condition
MNS-17-037, Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 20172017-08-10010 August 2017
Submittal of Summary Report of Evaluations Performed Pursuant to 10 CFR 50.59 Changes, Tests, and Experiments During the Period from January 1, 2016 to March 31, 2017
MNS-17-033, Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval2017-08-0202 August 2017
Snubber Program Plan for the Fourth Ten-Year Lnservice Testing (IST) Interval
MNS-17-034, 16C4435-RPT-002, Rev. 1, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for McGuire Nuclear Station.2017-07-24024 July 2017
16C4435-RPT-002, Rev. 1, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation for McGuire Nuclear Station.
MNS-17-030, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-06-28028 June 2017
Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal
MNS-17-023, Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies2017-05-25025 May 2017
Response to Request for Additional Information to License Amendment Request Permanent Extension of Type a and Type C Leak Rate Test Frequencies
MNS-17-016, Nuclear Regulatory Commission (NRC) Annual Commitment Change Report2017-05-18018 May 2017
Nuclear Regulatory Commission (NRC) Annual Commitment Change Report
MNS-17-020, Transmittal of McGuire, Units 1 and 2, 2016 Annual Radiological Environmental Operating Report2017-05-0505 May 2017
Transmittal of McGuire, Units 1 and 2, 2016 Annual Radiological Environmental Operating Report
MNS-17-019, McGuire Nuclear Station, Units 1 and 2 - Submittal of Annual Radioactive Effluent Release Report2017-04-28028 April 2017
McGuire Nuclear Station, Units 1 and 2 - Submittal of Annual Radioactive Effluent Release Report
MNS-17-008, Letter of Intent to Submit Plant-Specific Reactor Vessel Internals Inspection Plans2017-02-23023 February 2017
Letter of Intent to Submit Plant-Specific Reactor Vessel Internals Inspection Plans
MNS-16-092, License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-12-19019 December 2016
License Amendment Request to Revise Technical Specifications Section 5.5.2, Containment Leakage Rate Testing Program for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
MNS-16-091, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity.2016-12-0808 December 2016
License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity.
MNS-16-086, Emergency Plan, Revision 16-42016-12-0707 December 2016
Emergency Plan, Revision 16-4
MNS-16-078, Written Notification Joslyn Clark Overload Heater Element Part No. 24552016-10-19019 October 2016
Written Notification Joslyn Clark Overload Heater Element Part No. 2455
MNS-16-077, Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program2016-09-29029 September 2016
Responding to Request for Additional Information Related to License Amendment Request to Implement a Risk-informed Performance-Based Fire Protection Program
MNS-16-070, Response to Request for Additional Information to Relief Request 16-MN-0032016-08-18018 August 2016
Response to Request for Additional Information to Relief Request 16-MN-003
MNS-16-060, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-18018 August 2016
Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
MNS-16-062, Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping2016-08-10010 August 2016
Relief Request 16-MN-003 Alternative to Defect Removal Prior to Performing Temporary Repair Activities on Three-Inch-Diameter Nuclear Service Water System Piping
MNS-16-046, License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity2016-06-30030 June 2016
License Amendment Request for Technical Specification 3.6.14, Divider Barrier Integrity
MNS-16-056, License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information2016-06-30030 June 2016
License Amendment Request, One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval, Response to Request for Additional Information
MNS-16-053, Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping2016-06-23023 June 2016
Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping
MNS-16-052, Supplement to License Amendment Request for the Removal of Superseded Technical Specification Requirements, Dated May 5, 2016, TAC Nos. MF7682 and MF76832016-06-16016 June 2016
Supplement to License Amendment Request for the Removal of Superseded Technical Specification Requirements, Dated May 5, 2016, TAC Nos. MF7682 and MF7683
MNS-16-042, Withdrawal of Relief Request Serial No. 15-MN-0022016-05-17017 May 2016
Withdrawal of Relief Request Serial No. 15-MN-002
MNS-16-020, License Amendment Request Removal of Superseded Technical Specification Requirements2016-05-0505 May 2016
License Amendment Request Removal of Superseded Technical Specification Requirements
MNS-16-041, Supplement to Final Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051..2016-05-0505 May 2016
Supplement to Final Notification of Full Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events and with Order EA-12-051..
MNS-16-036, Relief Request 16-MN-001, Limited Weld Examinations2016-04-28028 April 2016
Relief Request 16-MN-001, Limited Weld Examinations
MNS-16-039, Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program2016-04-26026 April 2016
Submittal Revising Attachment s of License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program
MNS-16-026, Transmittal of Updated Final Safety Analysis Report, Revision 192016-04-0505 April 2016
Transmittal of Updated Final Safety Analysis Report, Revision 19
MNS-15-068, License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors.2016-03-24024 March 2016
License Amendment Request to Technical Specification (TS) 3.6.13, Ice Condenser Doors.
2018-07-03
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Text
Steven D. Capps DUKE Vice President E ER . McGuire Nuclear Station ENERGYG Duke Energy MG01VP 112700 Hagers Ferry Road Huntersville, NC 28078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com Serial: MNS-14-102 December 16, 2014 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555 Duke Energy Carolinas, LLC (Duke Energy)
McGuire Nuclear Station (MNS), Unit 1 Docket Numbers 50-369 Renewed License Number NPF-9
Subject:
Emergency Response Data System Changes By letter dated May 16, 2013, the NRC staff issued approved License Amendment No. 269 to Renewed Facility Operating License NPF-9 and Amendment No. 249 to Renewed Facility Operating License NPF-1 7 for McGuire Nuclear Station (MNS) Units 1 and 2 respectively. The license amendments were approved to support the implementation of a measurement uncertainty recapture (MUR) power uprate on MNS Units 1 and 2.
Subsequent to the implementation of the MUR power uprate on MNS Unit 1, MUR related Data Point Library (DPL) changes were completed on the Emergency Response Data System (ERDS) on November 23, 2014. Pursuant to the requirements of 10CFR50 Appendix E, Section VI.3.a, Enclosure 1 provides these ERDS DPL changes. The NRC DPL information for MNS Unit 1 should be revised per the four sheets in Enclosure 1. The DPL changes associated with implementation of MUR on MNS Unit 2 were provided by letter dated January 9, 2014.
All ERDS communication protocols, messages, quality codes, and formats are unaffected by the MUR power uprate on MNS Unit 1 or the ERDS changes provided in the Enclosure to this letter.
Therefore, there is no requirement for prior notification per 10CFR50 Appendix E, Section VI.3.b.
Questions regarding this submittal should be directed to Jeff Robertson, McGuire Regulatory Affairs at (980) 875-4499.
Steven D. Capps Enclosure $ D2-(V
United States Nuclear Regulatory Commission December 16, 2014 Page 2 xc:
V.M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 G. E. Miller, Project Manager (MNS and CNS)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 G9A Rockville, MD 20852-2738 J. Zeiler NRC Senior Resident Inspector McGuire Nuclear Station W. L. Cox Ill, Section Chief North Carolina Department of Health and Human Services Division of Health Service Regulation Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645
Enclosure 1 MUR Related MNS Unit 1 ERDS DPL Changes
r McGuire Nuclear Station Emergency Response Data System (ERDS) Implementation PWR DATA POINT REFERENCE FILE DATE: 11/19/2014 REACTOR UNIT: MCI DATA FEEDER: Ul OAC NRC ERDS PARAMETER: MN FD FL 1A POINT ID: M1P1412 PLANT SPEC POINT DESC: 1A STEAM GENERATOR TOTAL FEEDWATER FLOW 1 GENERIC/COND DESC: STM GEN A MAIN FEEDWATER FLOW ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: MLB/HR ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: 0 MAXIMUM INSTR RANGE: 5.15 ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES: N/A PROC OR SENS: P NUMBER OF SENSORS: 3 HOW PROCESSED: Dir. from flow (DP), Temp and Pressure SENSOR LOCATIONS: ASME nozzle Current Prodac ALARM/TRIP Hi: - Lo: -
SETPOINTS:
NI DETECTOR POWER SUPPLY CUT- N/A OFF POWER LEVEL:
NI DETECTOR POWER SUPPLY N/A TURNON POWER LEVEL:
INSTRUMENT FAILURE MODE: LOW TEMPERATURE COMPENSATION FOR DP: Y REF_ LEG: N/A UNIQUE SYSTEM DESC: Performance point calculated feedwater flow using delta P across ASME nozzle, temperature, and pressure of feedwater. 1 or 2 channel performance points. Minimum instr. range = 0" of minimum range =>
minimum forced flow reading of 0 MLB/HR.
point xref: 10.1
p McGuire Nuclear Station Emergency Response Data System (ERDS) Implementation PWR DATA POINT REFERENCE FILE DATE: 11/19/2014 REACTOR UNIT: MC1 DATA FEEDER: U10 AC NRC ERDS PARAMETER: MN FD FL 2B POINT ID: M1P1414 PLANT SPEC POINT DESC: 1 B STEAM GENERATOR TOTAL FEEDWATER FLOW 1 GENERIC/COND DESC: STM GEN B MAIN FEEDWATER FLOW ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: MLB/HR ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: 0 MAXIMUM INSTR RANGE: 5.15 ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES: N/A PROC OR SENS: P NUMBER OF SENSORS: 3 HOW PROCESSED: Dir. from flow (DP), Temp and Pressure SENSOR LOCATIONS: ASME nozzle Current Prodac ALARM/TRIP Hi: - Lo: -
SETPOINTS:
NI DETECTOR POWER SUPPLY CUT- N/A OFF POWER LEVEL:
NI DETECTOR POWER SUPPLY N/A TURNON POWER LEVEL:
INSTRUMENT FAILURE MODE: LOW TEMPERATURE COMPENSATION FOR DP: Y REF_ LEG: N/A UNIQUE SYSTEM DESC: Performance point calculated feedwater flow using delta P across ASME nozzle, temperature, and pressure of feedwater. 1 or 2 channel performance points. Minimum instr. range = 0" of minimum range =>
minimum forced flow reading of 0 MLB/HR.
point xref: 10.1
McGuire Nuclear Station Emergency Response Data System (ERDS) Implementation PWR DATA POINT REFERENCE FILE DATE: 11/19/2014 REACTOR UNIT: MC1 DATA FEEDER: UlOAC NRC ERDS PARAMETER: MN FD FL 3C POINT ID: M1P1416 PLANT SPEC POINT DESC: 1C STEAM GENERATOR TOTAL FEEDWATER FLOW 1 GENERIC/COND DESC: STM GEN C MAIN FEEDWATER FLOW ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: MLB/HR ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: 0 MAXIMUM INSTR RANGE: 5.15 ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES: N/A PROC OR SENS: P NUMBER OF SENSORS: 3 HOW PROCESSED: Dir. from flow (DP), Temp and Pressure SENSOR LOCATIONS: ASME nozzle Current Prodac ALARM/TRIP Hi: - Lo:-
SETPOINTS:
NI DETECTOR POWER SUPPLY CUT- N/A OFF POWER LEVEL:
NI DETECTOR POWER SUPPLY N/A TURNON POWER LEVEL:
INSTRUMENT FAILURE MODE: LOW TEMPERATURE COMPENSATION FOR DP: Y REF_ LEG: N/A UNIQUE SYSTEM DESC: Performance point calculated feedwater flow using delta P across ASME nozzle, temperature, and pressure of feedwater. 1 or 2 channel performance points. Minimum instr. range = 0" of minimum range =>
minimum forced flow readinq of 0 MLB/HR.
point xref: 10.1
McGuire Nuclear Station Emergency Response Data System (ERDS) Implementation PWR DATA POINT REFERENCE FILE DATE: 11/19/2014 REACTOR UNIT: MC1 DATA FEEDER: UL1OAC NRC ERDS PARAMETER: MN FD FL 4D POINT ID: M1P1418 PLANT SPEC POINT DESC: 1D STEAM GENERATOR TOTAL FEEDWATER FLOW 1 GENERIC/COND DESC: STM GEN D MAIN FEEDWATER FLOW ANALOG/DIGITAL: A ENGR UNITS/DIG STATES: MLB/HR ENGR UNITS CONVERSION: N/A MINIMUM INSTR RANGE: 0 MAXIMUM INSTR RANGE: 5.15 ZERO POINT
REFERENCE:
N/A REFERENCE POINT NOTES: N/A PROC OR SENS: P NUMBER OF SENSORS: 3 HOW PROCESSED: Dir. from flow (DP), Temp and Pressure SENSOR LOCATIONS: ASME nozzle Current Prodac ALARM/TRIP Hi: - Lo: -
SETPOINTS:
NI DETECTOR POWER SUPPLY CUT- N/A OFF POWER LEVEL:
NI DETECTOR POWER SUPPLY N/A TURNON POWER LEVEL:
INSTRUMENT FAILURE MODE: LOW TEMPERATURE COMPENSATION FOR DP: Y REF_ LEG: N/A UNIQUE SYSTEM DESC: Performance point calculated feedwater flow using delta P across ASME nozzle, temperature, and pressure of feedwater. 1 or 2 channel performance points. Minimum instr. range = 0" of minimum range =>
minimum forced flow reading of 0 MLB/HR.
point xref: 10.1
