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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
(~DUKE Steven D. Capps
~
Vice President ENERGY McGuire Nuclear Station Duke Energy MGOlVP I 12700 Hagers Ferry Road Huntersville, NC 28078 O: 980.875.4805
- f: 980.875.4809 Steven.Capps@duke-energy.com Serial No: MNS-16-079 September 29, 2016 10 CFR 50.55a U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
McGuire Nuclear Station, Unit 2 Docket No. 50-370 Relief Request MC-SRV-NC-01 Pressurizer Power Operated Relief Valve (PORV) Block Valve lnservice Testing Pursuant to 10 CFR 50.55a(z)(2), Duke Energy hereby requests U.S. Nucle.ar Regulatory Commission's approval of alternative testing for two PORV Block Valves, 2NC-33A and 2NC-35B. These valves have packing leakage, and stroking them quarterly creates a hardship without a compensating increase in quality and safety as described in the attached relief request.
- The next quarterly testing for 2NC-35B is due*October 31, 2016. Duke Energy requests NRC's approval of this relief request prior to this due date.
If you have any questions or require additional information, please contact P.T. Vu of Regulatory Affairs at (980) 875-4302.
Sincerely, Steven D. Capps Attachment www.duke-energy.com
U.S. Nuclear Regulatory Commission September 29, 2016 Page 2 xc:
C. Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 V. Sreenivas, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD _20852-2738 A.Hutto NRC Senior Resident Inspector McGuire Nuclear Station
ATTACHMENT Attachment File: MC-1234.01 McGuire Nuclear Station Unit 2 - Specific Valve Relief Request MC-SRV-NC-01 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2)
-- Hardship without a compensating increase in quality and safety --
- 1. ASME Code Component(s) Affected:
Pressurizer Power Operated Relief Valve (PORV) Block Valves 2NC-33A, 2NC-35B.
- 2. Component Function:
The pressurizer PORV Block Valves are normally open motor-operated gate valves located on the pressurizer steam space. To perform their design safety functions, the subject valves must provide isolation in the case of a leaking or stuck open PORV and must open to vent the pressurizer during a steam generator tube rupture event. Manual operator action is credited for valve actuation in both the closed and open directions. These valves do not receive an automatic actuation signal. These valves are interlocked to prevent more than one valve being closed at a time.
3. Applicable Code Edition and Addenda
ASME OM Code 2004 through 2006 Addenda.
4. Applicable Code Requirement
Quarterly exercise testing [ASME OMb-2006, section ISTC-351 O]; Quarterly valve stroke time testing open and closed directions [ASME OMb-2006, section ISTC-5113]. Two year position verification testing [ASME OMb-2006, section ISTC-3700]. Note the two year position indication verification testing does not apply to this relief request.
5. Reason for Request
Nuclear Condition Report (NCR) 02043441 was initiated by systems engineering due to an increase in identified reactor coolant system (RCS) leakage during performance of RCS system leakage calculation on July 4, 2016. Subsequent calculations yielded repeatable results at or near 0.148 GPM, a significant change from previous results of approximately 0.038 GPM. Technical Specification (TS) 3.4.13 limits RCS identified leakage to a maximum of 10 GPM. Initial troubleshooting identified 2NC-33A packing leakage as the source of RCS leakage. Following additional troubleshooting of all Unit 2 pressurizer PORV block valves, NCR 02048025 identified ~
2NC-35B as a source of RCS identified leakage due to high temperatures observed on the valve packing leak off line.
Stroking the valves can create a hardship as further packing degradation may result, reducing operational RCS leakage margin. Current RCS leakage values are stable with 2NC-33A administratively open on backseat and 2NC-35B administratively closed. Both valves remain operable with emergency power available. Based on current plant conditions and as described in the proposed alternative basis, the licensee is requesting relief from ASME Code quarterly valve surveillances to prevent quarterly valve cycles until valve repair can be made during the next Unit 2 refueling outage (2EOC24).
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Attachment File: MC-1234.01 Repair of 2NC-33A and 2NC-358 would require entry into containment and RCS depressurization for isolation purposes. Personnel safety and ALARA practices are maximized during a scheduled refueling outage. Additionally, maneuvering the reactor to a mode outside of TS applicability and depressurizing the RCS involves inherent risk and increases nuclear safety risk due to cycling plant equipment.
- 6. Proposed Alternative and Basis for Use:
As an alternative to performing quarterly surveillance testing on 2NC-33A and 2NC-35B, the licensee is requesting to perform exercise and valve stroke timing testing during cold shutdown. In the event of PORV block valve packing leakage, stroking the respective valve creates a hardship because of the increased potential for packing leakage. Increased leakage reduces the margin for acceptable reactor coolant system identified leakage (Reference TS 3.4.13, Operational Leakage).
If RCS identified leakage exceeds its allowable limit, the required action is plant shutdown. For non-leaking PORV block valves, the valves will continue to be stroked quarterly per applicable ASME code requirements.
As stated in Section 5, to control stem packing leakage on 2NC-33A, the licensee manually positioned the valve open on backseat with power available. Operational valve stroke timing testing was conducted from the open backseat configuration and re-opened the valve with satisfactory results. This testing demonstrates the valve is fully operational ready in the current configuration.
Continued stroking of 2NC-33A represents a hardship with respect to manually positioning the valve on backseat following each quarterly exercise and valve stroke timing test.
When the valves are closed due to valve packing leakage, the valve is administratively maintained closed with power available. If required to be opened to perform its intended safety function, the valve is opened by the control room operator. Opening the valve with a packing leak during normal plant operation may cause further stem packing damage, resulting in increased RCS leakage.
When the valves are open due to valve packing leakage, the valve is administratively maintained open with the valve stem on backseat with power available. If required to be closed to perform its intended safety function, the valve is closed by the control room operator. Closing the valve with a packing Jeak during normal plant operation may cause further stem packing damage, resulting in increased RCS leakage.
The subject valves have established preventative maintenance activities. The valves have maintained consistent performance with no adverse trends or abnormalities noted during Motor Operated Valve diagnostic testing. The valve actuator general and lubrication condition is of sufficient quality to support continued reliability with the relief of quarterly exercise and stroke timing activities until scheduled repairs in 2EOC24.
IST performance history of McGuire Unit 2 PORV block valves has been excellent with no valve stroke timing or position indication testing failures from reviewed data January 1, 2009 to present.
2NC-33A and 2NC-35B valve stroke timing performance (open and closed directions) has been consistently between 5.5 and 6.5 seconds, demonstrating acceptable margin to the maximum limit of 1O seconds.
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I ' ' "
Attachment File: MC-1234.01
- 7. Duration of Proposed Alternative:
This condition is only intended to permit McGuire Unit 2 operation for a limited period of time not to exceed restart from the next refueling outage. 2NC-33A and 2NC-35B repair is planned for the next McGuire Unit 2 refueling outage 2EOC24 scheduled to begin on March 30, 2017. Following the refueling outage, the licensee will resume quarterly testing of 2NC-33A and 2NC-35B per applicable ASME Code requirements.
- 8.
References:
a) Duke Energy, McGuire Nuclear Station ASME lnservice Testing Program Revision 28, dated March 1, 2013 b) NEI white paper "Standard Format for Requests from Commercial Reactor Licensees Pursuant to 10 CFR 50.55a" Revision 1 dated June 7, 2004.
c) Duke Energy fleet procedure AD-EG-ALL-1720 "lnservice Testing (IST) Program Implementation" Revision 01 dated April 20, 2016.
d) Technical Specification Surveillance Requirement 3.4.11.1 e) Technical Specification 3.4.13 RCS Operational LEAKAGE f) NCR 02043441 Elevated Unit 2 Identified Leakage g) NCR 02048025 2NC-35B identified as likely source of Unit 2 ID Leakage h) McGuire Flow Diagram MCFD-2553-2.0 Revision 9 NC (Reactor Coolant) System i) MCTC-1553-NC.V002-01 Revision 01 Test Acceptance Criteria for Pressurizer PORV Block Valves 1/2NC-31 B, -33A and -358.
j) MCS-1553.NC-00-0001 Revision 32 Design Basis Specification for the NC System k) WO 20097096: 2NC-33A Repack Valve I) WO 20099545: 2NC 35B Investigate/Repair Packing Page 3 of 3