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EPID:L-2018-LLR-0005, Relief Request MC-SRV-NS-02, Containment Narrow Range Pressure Inside Isolation Valve 2NSSV5550 (Open) |
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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
Thomas D. Ray, P.E.
Site Vice President McGuire Nuclear Station Duke Energy MGOl VP I 12700 Hagers Ferry Road Huntersville, NC 28078 O: 980.875.4805 f: 980.875.4809 Tom.Ray@duke-energy.com Serial No: MNS-18-015 February 21, 2018 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-NS-02 Containment Narrow Range Pressure Inside Isolation Valve 2NSSV5550 Pursuant to 10 CFR 50.55a(z)(2), Duke Energy hereby requests U.S. Nuclear Regulatory Commission (NRC)'s approval for an alternative to performing inservice testing on Containment Narrow Range Pressure Inside Isolation Valve 2NSSV5550. Duke Energy is requesting to delay quarterly valve stroke time and two year position verification testing until after repair of the valve's position indication during the next Unit 2 refueling outage in the fall of 2018. Repair of the valve's position indication now would create a hardship due to personnel safety and ALARA considerations.
The late date for the next quarterly test is March 11, 2018. Duke Energy requests NRC's approval of this relief request by March 5, 2018.
If you have any questions or require addit_ional information, please contact P.T. Vu of Regulatory Affairs at (980) 875-4302.
Sincerely, st,~
Thomas D.. Ray, P.E.
Attachment www.duke-energy.com
U.S. Nuclear Regulatory Commission February 21, 2018 Page 2 xc:
Catherine Haney, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 Michael Mahoney, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8G9A Rockville, MD 20852-2738 Andy Hutto NRC Senior Resident Inspector McGuire Nuclear Station
Attachment File: MC-1234.01 McGuire Nuclear Station Unit 2 - Specific Valve Relief Request MC-SRV-NS-02 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:
Unit 2 Containment Narrow Range Pressure Inside Isolation Valve 2NSSV5550.
- 2. Component Function:
2NSSV5550 is a normally open fast acting solenoid valve located on the impulse line for the narrow range containment pressure transmitter. The valve serves as the inside containment isolation valve for containment penetration 2M402A and closes on a containment isolation signal. 2NSSV5550 is located in the 20 cold leg accumulator room inside the Unit 2 reactor building.
3. Applicable Code Edition and Addenda
ASME OM Code 2004 through 2006 Addenda.
- 4. Applicable Code Requirements:
Quarterly valve stroke time (VST) testing in closed direction [ASME OMb-2006, section ISTC-5150]; Two year position verification testing [ASME OMb-2006, section ISTC-3700].
Note that the quarterly exercise testing [ASME OMb-2006, section ISTC-351 O] is applicable but not included as a part of this relief request.
5. Reason for Request
Nuclear Condition Report (NCR) 02184928 was initiated by Operations on February 15, 2018. The NCR identifies an issue with not being able to obtain a valid VST for 2NSSV5550 during normal quarterly surveillance test on February 15, 2018. The VST procedure utilizes the plant Operator Aid Computer (OAC) for indication signal timing from open to closed. It was determined that the OAC indication shows the valve position to be intermediate when the main control board indication shows correct valve position.
Erratic OAC indication began in October 2015 following 2NSSV5550 coil replacement with periods of correct indication. Repair of 2NSSV5550 OAC indication was attempted on February 6, 2018, per Work Order 20025829. Technicians were able to obtain correct OAC indication momentarily by making adjustments to the solenoid valve reed switches; however, proper OAC indication could not be sustained as the solenoid valve cover was reinstalled and torqued. Due to the component location, technicians were allotted a one hour stay time due to heat stress (with ice vest) and ALARA considerations. Technicians exited the building without making repeated adjustments to fine tune the solenoid valve reed switches.
Repair of 2NSSV5550 OAC indication would require an extended amount of time at the solenoid valve to make required reed switch adjustments. Due to hardship created by Page 1 of 3
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Attachment File: MC-1234.01 personnel safety and ALARA considerations, McGuire proposes repair during the next Unit 2 refueling outage M2R25 scheduled to begin on September 15, 2018.
Control room valve position indication is available on the main control board. Control room indication was observed to be consistent with actual valve position when technicians were present at the solenoid valve on February 6, 2018. Consideration was given to performing VST testing using main control board indication and a calibrated stopwatch. Given the fast acting nature of the solenoid valve, operator uncertainty would likely be in excess of the expected valve stroke time, resulting in inconsistent data. For this reason, McGuire does not intend to use this alternate testing method.
2NSSV5550 has a history of excellent VST performance. Table 1 summarizes VST data for the previous two years. The VST acceptance criteria for 2NSSV5550 is < 2 seconds per ISTC-5152( c), which applies to fast acting solenoid valves.
Table 1: 2NSSV5550 VST results VST Surveillance Date Results (sec) Percent of Allowable (%)
2/15/16 0.4 20 5/19/16 0.2 10 8/18/16 0.1 5 11/10/16 0.3 15 2/16/17 0.1 5 4/15/17 0.1 5 5/18/17 0.2 10 8/18/17 0.1 5 11/16/17 0.1 5 Penetration 2M402A outside containment isolation valve 2NSSV5551 will continue to be tested in accordance with all ASME OM code requirements. Historic results for 2NSSV5551 are consistent with 2NSSV5550 and range between 0.1 and 0.3 seconds. Both solenoid valves are subject to 10 CFR 50 Appendix J Containment Leak Rate Testing. For valves 2NSSV5550 and 2NSSV5551, the most recent Type C local leak rate test occurred on April 16, 2017, with results of 5 seem and 6.4 seem respectively compared to an administrative leakage test limit of 73 seem. Prior Appendix J testing results have been excellent with both valves demonstrating significant margin to allowable leakage limits.
2NSSV5550 visual verification requirements are satisfied by visually checking OAC position against main control board indication. Since OAC indication is currently unreliable, McGuire proposes relief from ISTC-3700 requirements for the duration discussed in Section 7. Valve remote position verification is satisfied by performing Type C local leak rate testing, which was last performed on April 16, 2017, as previously discussed.
- 6. Proposed Alternative and Basis for Use:
As an alternative to performing 2NSSV5550 quarterly VST testing [ISTC-5150] and two year position indication verification testing [ISTC-3700], McGuire is requesting to suspend VST and position indication testing until M2R25 repairs are complete as discussed in Section 7.
2NSSV5550 can still be exercise tested quarterly in accordance with ISTC-3510. In the Page 2 of 3
Attachment File: MC-1234.01 event of a containment isolation signal, reasonable assurance of valve closure and containment isolation is demonstrated through previous testing (VST and Appendix J) and local observation of valve position as indicated on the control room main control board.
Based on available data, McGuire considers deferral of the proposed testing for the requested duration to be low risk without compromising quality or safety.
- 7. Duration of Proposed Alternative:
This relief request is only intended to permit McGuire Unit 2 operation for a limited period of time, not to exceed restart from the next Unit 2 refueling outage M2R25. Work Order 20025829 will complete necessary OAC indication repairs during M2R25, which is scheduled to begin on September 15, 2018. Following the refueling outage, McGuire will resume inservice testing of 2NSSV5550 per applicable ASME OM 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 2004.
c) NUREG-1482, Revision 2, "Guidelines for lnservice Testing at Nuclear Power Plants,"
published October 2013.
d) Duke Energy fleet procedure AD-EG-ALL-1720, Revision 02, "lnservice Testing (1ST)
Program Implementation," dated February 7, 2017.
e) NCR 02183451, Team 319 week 06 unable to complete schedule.
f) NCR 02184928, Unable to complete VST Quarterly due to bad OAC indication.
g) WO 20025829, 2NSSV5550 Intermediate on OAC but closed on MCB.
h) AR 02184102, add 2NSSV5550 to outage (M2R25) scope.
i) McGuire Flow Diagram MCFD-2563-01.00, Revision 19, Containment Spray (NS)
System.
j) MCTC-1563-NS.V008-01, Testing and Acceptance Criteria Solenoid Valves 1/2NSSV5550 and 1/2NSSV5551.
k) MCS-1563.NS-00-0001, Revision 34, Design Basis Specification for the NS System.
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