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| RAl-1 The NRC staff notes that the licensee adopted Option B of 10 CFR 50, Appendix J following the September 4, 2002 issuance of Amendment No. 207 to Facility Operating License No. NPF-9 and Amendment No. 188 to Facility Operating License NPF-17 for MNS, Units 1 and 2. Per the guidance of Nuclear Energy Institute (NEI) 94-01, "Industry Guideline for Implementing Performance-Based Option of 1 O CFR Part 50, Appendix J," Revision O (Reference 2), Section 10.2.3.2 and subject to the four provisions identified in Regulatory Position "C" of Regulatory Guide (RG) 1.163, "Performance-Based Containment Leak-Test Program," both MNS, Unit 1 and Unit 2 are currently allowed to extend the test intervals for Type C CIVs up to 60 months. :1 RG 1.63 Regulatory Position C.2 reads, in part: . . . . . | | RAl-1 The NRC staff notes that the licensee adopted Option B of 10 CFR 50, Appendix J following the September 4, 2002 issuance of Amendment No. 207 to Facility Operating License No. NPF-9 and Amendment No. 188 to Facility Operating License NPF-17 for MNS, Units 1 and 2. Per the guidance of Nuclear Energy Institute (NEI) 94-01, "Industry Guideline for Implementing Performance-Based Option of 1 O CFR Part 50, Appendix J," Revision O (Reference 2), Section 10.2.3.2 and subject to the four provisions identified in Regulatory Position "C" of Regulatory Guide (RG) 1.163, "Performance-Based Containment Leak-Test Program," both MNS, Unit 1 and Unit 2 are currently allowed to extend the test intervals for Type C CIVs up to 60 months. :1 RG 1.63 Regulatory Position C.2 reads, in part: . . . . . |
| Further, the interval for Type C tests for main steam and feedwater isolation valves in BWRs, and containment purge and vent valves in PWRs and BWRs, should be limited to 30 months as specified in Section 3.3.4 of ANSl/ANS-56.8-1994, with consideration given to operati,ng experience and safety significance. | | Further, the interval for Type C tests for main steam and feedwater isolation valves in BWRs, and containment purge and vent valves in PWRs and BWRs, should be limited to 30 months as specified in Section 3.3.4 of ANSl/ANS-56.8-1994, with consideration given to operati,ng experience and safety significance. |
| Section 10.2.3.2 of NEI 94-01 of both Revision 0 and Revision 3-A (Reference | | Section 10.2.3.2 of NEI 94-01 of both Revision 0 and Revision 3-A (Reference |
| : 3) reads, in part: Test intervals for Type C valves may be increased based upon completion of two consecutive periodic As-found Type C tests where the result of each test is within a licensee's allowable administrative limits ..... As conveyed in LAR Section 3.3 "Containment Leakage Rate Testing Program, Type B and Type C Testing," the NRC staff notes that currently less than half of the population of both Unit's CIVs are on extended frequencies of 60 months. The NRC staff's review of LAR Table 3.3-3 "MNS Type Band C LLRT Program Implementation Review As-Found Failures of Components on Extended Intervals (emphasis added)" fails to adequately explain "Why a greater percentage of the CIVs are not qualifying for extended frequencies"? | | : 3) reads, in part: Test intervals for Type C valves may be increased based upon completion of two consecutive periodic As-found Type C tests where the result of each test is within a licensee's allowable administrative limits ..... As conveyed in LAR Section 3.3 "Containment Leakage Rate Testing Program, Type B and Type C Testing," the NRC staff notes that currently less than half of the population of both Unit's CIVs are on extended frequencies of 60 months. The NRC staff's review of LAR Table 3.3-3 "MNS Type Band C LLRT Program Implementation Review As-Found Failures of Components on Extended Intervals (emphasis added)" fails to adequately explain "Why a greater percentage of the CIVs are not qualifying for extended frequencies"? |
| The NRC staff requests that the licensee provide additional information about LAR Section 3.3 and Table 3.3-3. In particular, about: A. All (i.e. not just those on extended frequencies) | | The NRC staff requests that the licensee provide additional information about LAR Section 3.3 and Table 3.3-3. In particular, about: A. All (i.e. not just those on extended frequencies) |
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| May 25, 2017 Serial No. MNS-17-023 Response to RAl-1 A Enclosure Page 2 of 8 The two most recent MNS Unit 1 refueling outages were 1 EOC23 (September 2014) and 1EOC24 (March 2016). The two most recent MNS Unit 2 refueling outages were 2EOC23 (September 2015) and 2EOC24 (March 2017). Tables 1 -4 contain Type C LLRT administrative failures for the requested outages. All leakage rates are reported in standard cubic centimeters perminute (seem) and include instrument uncertainty. | | May 25, 2017 Serial No. MNS-17-023 Response to RAl-1 A Enclosure Page 2 of 8 The two most recent MNS Unit 1 refueling outages were 1 EOC23 (September 2014) and 1EOC24 (March 2016). The two most recent MNS Unit 2 refueling outages were 2EOC23 (September 2015) and 2EOC24 (March 2017). Tables 1 -4 contain Type C LLRT administrative failures for the requested outages. All leakage rates are reported in standard cubic centimeters perminute (seem) and include instrument uncertainty. |
| As-found penetration minimum pathway leakage rates (MNPLR) are provided in parentheses to demonstrate penetration integrity. | | As-found penetration minimum pathway leakage rates (MNPLR) are provided in parentheses to demonstrate penetration integrity. |
| Table 1: 1 EOC23 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed Observed Valve As-Found Leak As-Left Leak Administrative Rate (MNPLR) Rate Failure Limit 1M-309 1NM-423' off scale ( 17) 1 2:: 110 1M-374 1WL-64A" 2,100 (2,100) 1 2:: 590 1M-221 1WL-385" 190 (1.44) 190 2:: 147.5 Table 1 Footnotes: | | Table 1: 1 EOC23 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed Observed Valve As-Found Leak As-Left Leak Administrative Rate (MNPLR) Rate Failure Limit 1M-309 1NM-423' off scale ( 17) 1 2:: 110 1M-374 1WL-64A" 2,100 (2,100) 1 2:: 590 1M-221 1WL-385" 190 (1.44) 190 2:: 147.5 Table 1 Footnotes: |
| : 1. 1 NM-423 disassembly noted excessive wear on valve disc and body seat. Internal valve parts were replaced and the seat mating surface was verified to have 100% contact. 2. 1WL-64A inspection revealed a limit switch setup issue that prevented full seating load on the diaphragm valve. Limit switches were adjusted to restore seating load. 3. 1WL-385 leakage was accepted by engineering. | | : 1. 1 NM-423 disassembly noted excessive wear on valve disc and body seat. Internal valve parts were replaced and the seat mating surface was verified to have 100% contact. 2. 1WL-64A inspection revealed a limit switch setup issue that prevented full seating load on the diaphragm valve. Limit switches were adjusted to restore seating load. 3. 1WL-385 leakage was accepted by engineering. |
| Repairs were completed the following outage, 1 EOC24 as shown in Table 2. Table 2: 1 EOC24 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed As-Observed As-Administrative Found Leak Left Leak Failure Limit Rate (MNPLR) Rate 1 M-317 1Vl-124 1 1 ,300 (7.2) 2.4 2:: 295 1 M-221 1WL-385" 568 (3) 9.1 2:: 147.5 1 M-342 1NV-1002'' | | Repairs were completed the following outage, 1 EOC24 as shown in Table 2. Table 2: 1 EOC24 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed As-Observed As-Administrative Found Leak Left Leak Failure Limit Rate (MNPLR) Rate 1 M-317 1Vl-124 1 1 ,300 (7.2) 2.4 2:: 295 1 M-221 1WL-385" 568 (3) 9.1 2:: 147.5 1 M-342 1NV-1002'' |
| off scale (3.41) 1 2:: 295 1 M-309 1NM-22AC" off scale (2.6) 4 2:: 147.5 1 M-327 1KC-340" off scale (2) 47 2:: 1, 180 1 M-320 1KC-424Bl'.l off scale (19) 970 2:: 1, 180 Table 2 Footnotes: | | off scale (3.41) 1 2:: 295 1 M-309 1NM-22AC" off scale (2.6) 4 2:: 147.5 1 M-327 1KC-340" off scale (2) 47 2:: 1, 180 1 M-320 1KC-424Bl'.l off scale (19) 970 2:: 1, 180 Table 2 Footnotes: |
| : 1. 1Vl-124 disassembly noted an impression on the b'ody seat that required lapping to restore proper sealing surfaces. | | : 1. 1Vl-124 disassembly noted an impression on the b'ody seat that required lapping to restore proper sealing surfaces. |
| Lapping was performed until 100% contact was achieved. | | Lapping was performed until 100% contact was achieved. |
| : 2. 1WL-385 disassembly noted a small particle of foreign material on the valve seat. Refer to RAl-1 B response for more details associated with 1WL-385. 3. 1NV-1002 disassembly noted the valve disc soft seat to be deteriorated and in need of replacement. | | : 2. 1WL-385 disassembly noted a small particle of foreign material on the valve seat. Refer to RAl-1 B response for more details associated with 1WL-385. 3. 1NV-1002 disassembly noted the valve disc soft seat to be deteriorated and in need of replacement. |
| Internal valve parts were replaced. | | Internal valve parts were replaced. |
| : 4. 1 NM-22AC disassembly noted a bent valve stem at the disc to stem connection. | | : 4. 1 NM-22AC disassembly noted a bent valve stem at the disc to stem connection. |
| The valve was repaired with new parts. 5. 1 KC-340 disassembly noted residue present on the valve seat. The valve seat was repaired and disc verified to cycle freely. Refer to RAl-1 B response for more details associated with 1 KC-340. | | The valve was repaired with new parts. 5. 1 KC-340 disassembly noted residue present on the valve seat. The valve seat was repaired and disc verified to cycle freely. Refer to RAl-1 B response for more details associated with 1 KC-340. |
| May 25, 2017 Serial No. MNS-17-023 Enclosure Page 3 of 8 6. 1 KC-4248 torque setting was found out of tolerance. | | May 25, 2017 Serial No. MNS-17-023 Enclosure Page 3 of 8 6. 1 KC-4248 torque setting was found out of tolerance. |
| Torque setting adjustments were made to decrease leakage. Table 3: 2EOC23 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed As-Observed Administrative Found Leak As-Left Leak Failure Limit Rate (MNPLR) Rate 2M-309 2NM-421 1 588 (1.07) 588 ;::: 110.6 Table 3 Footnotes: | | Torque setting adjustments were made to decrease leakage. Table 3: 2EOC23 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed As-Observed Administrative Found Leak As-Left Leak Failure Limit Rate (MNPLR) Rate 2M-309 2NM-421 1 588 (1.07) 588 ;::: 110.6 Table 3 Footnotes: |
| : 1. 2NM-421 leakage was accepted by engineering. | | : 1. 2NM-421 leakage was accepted by engineering. |
| 2NM-421 leakage reduced to 85 seem in 2EOC24. Table 4: 2EOC24 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed As-Observed Administrative Found Leak As-Left Leak Failure Limit Rate (MNPLR) Rate 2M-221 2WL-385' 189 (53.6) 189 147.5 Table 4 Footnotes: | | 2NM-421 leakage reduced to 85 seem in 2EOC24. Table 4: 2EOC24 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed As-Observed Administrative Found Leak As-Left Leak Failure Limit Rate (MNPLR) Rate 2M-221 2WL-385' 189 (53.6) 189 147.5 Table 4 Footnotes: |
| : 1. 2WL-385 leakage was accepted by engineering. | | : 1. 2WL-385 leakage was accepted by engineering. |
| B. Whether there have been repetitive failures of "Administrative Limits" for any LLRTs associated with the MNS, Unit 1 or Unit 2 Type C tests (i.e. CIVs) since the last ILRTs of 2008. If so, please provide a minimum of three examples that details the corrective actions performed to prevent reoccurrence. | | B. Whether there have been repetitive failures of "Administrative Limits" for any LLRTs associated with the MNS, Unit 1 or Unit 2 Type C tests (i.e. CIVs) since the last ILRTs of 2008. If so, please provide a minimum of three examples that details the corrective actions performed to prevent reoccurrence. |
Letter Sequence Response to RAI |
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CAC:MF9020, Implement 10 CFR 50, Appendix J, Option B (Approved, Closed) |
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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
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24110A0382024-04-30030 April 2024 – Correction to Issuance of Amendment Nos. 330 and 309, Regarding Implementation of Technical Specifications Task Force (TSTF) Traveler TSTF 505, Revision 2, “Provide Risk-Informed Extended Completion Times - Ritstf RA-23-0279, Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power2023-11-0202 November 2023 Supplement to Application to Adopt Risk-Informed Completion Times TSTF-505, Revision 2 and Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power RA-18-0090, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-02-17017 February 2023 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors RA-18-0190, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-02-16016 February 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-21-0320, License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits2021-12-20020 December 2021 License Amendment Request (LAR) to Revise the Applicability Term for Pressure and Temperature Limit Curves of Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility2021-12-14014 December 2021 William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility RA-19-0043, Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-06-0909 June 2021 Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-18-001, McGuire Nuclear Station, Units 1 and 2 - Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating.2018-07-10010 July 2018 McGuire Nuclear Station, Units 1 and 2 - Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating. RA-18-0015, Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating.2018-07-10010 July 2018 Supplement to License Amendment Request Proposing Changes to Catawba and McGuire Technical Specification 3.8.1, AC Sources - Operating. 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 ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications 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-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 RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing 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 RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.2017-07-20020 July 2017 Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. RA-17-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules2017-07-18018 July 2017 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules 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 ML17122A1162017-05-0202 May 2017 Catawba and McGuire - License Amendment Request Proposing Changes to Technical Specification 3.8.1, AC Sources - Operating. RA-17-0003, Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-01-11011 January 2017 Application to Revise Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers 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. ML16305A1412016-10-20020 October 2016 Document Transmittal Regarding Issue MNS FOL U-2, Rev. 3 RA-16-0019, Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Proces2016-09-27027 September 2016 Duke Energy Progress - Application to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process 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-16-039, 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-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. MNS-16-015, License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval2016-02-18018 February 2016 License Amendment Request (LAR) for One-Time Extension of Appendix J Type a Integrated Leakage Rate Test Interval MNS-15-099, Submittal Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program2016-01-14014 January 2016 Submittal Regarding License Amendment Request to Implement a Risk-Informed Performance-Based Fire Protection Program MNS-16-002, Proposed Technical Specifications (TS) Amendment TS 3.7.10, Control Room Area Chilled Water System (Mns), and TS 3.7.11, Control Room Area Chilled Water System (CNS)2016-01-0707 January 2016 Proposed Technical Specifications (TS) Amendment TS 3.7.10, Control Room Area Chilled Water System (Mns), and TS 3.7.11, Control Room Area Chilled Water System (CNS) ML15258A0582015-09-0909 September 2015 Amendment 280 ML15258A0592015-09-0909 September 2015 Renewed Facility Operating License ML15258A0552015-09-0808 September 2015 Renewed Facility Operating License ML15258A0572015-09-0808 September 2015 Mcgurie Nuclear Station - MNS-TS-1.1 Amendment 280/260 Distribution MNS-15-069, Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Unit 1 - License Amendment Request for One-Time Change to Technical Specification 3.5.2, Emergency Core Cooling Systems (ECCS) - Operating.2015-08-28028 August 2015 Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Unit 1 - License Amendment Request for One-Time Change to Technical Specification 3.5.2, Emergency Core Cooling Systems (ECCS) - Operating. RA-15-0020, License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding2015-08-20020 August 2015 License Amendment Request and 10 CFR 50.12 Exemption Request for Use of Optimized Zirlo Fuel Rod Cladding RA-15-001, Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Foot2015-07-15015 July 2015 Catawba, McGuire, and Oconee - License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footn RA-15-0013, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112015-07-15015 July 2015 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 MNS-15-025, License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation2015-07-0909 July 2015 License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation MNS-15-026, License Amendment Request for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System Degraded Condition - Drawing MCFD-2574-03.01, Rev. 11, Flow Diagram of Nuclear Service.2015-06-30030 June 2015 License Amendment Request for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System Degraded Condition - Drawing MCFD-2574-03.01, Rev. 11, Flow Diagram of Nuclear Service. ML15191A0252015-06-30030 June 2015 License Amendment Request for Temporary Changes to Technical Specifications for Correction of an 'A' Train Nuclear Service Water System (Nsws) Degraded Condition ML15175A4482015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 6 of 6 ML15175A4472015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 5 of 6 ML15175A4452015-06-24024 June 2015 Application to Revise Technical Specifications to Adopt TSTF-523, Revision 2, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process. Part 4 of 6 2024-04-30
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0142, Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require2023-07-0707 July 2023 Mcguire, Units 1 and 2, Oconee, Units 1, 2, and 3, H. B. Robinson, Unit 2, Response to Request for Additional Information Regarding the License Amendment Request to Revise Restrictive Technical Specification Surveillance Require RA-23-0076, Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report2023-03-16016 March 2023 Supplement to Response to Request for Additional Information (RAI) Regarding McGuire Nuclear Station Unit 1 Spring, 2022 Outage Steam Generator Tube Inspection Report RA-23-0024, Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds2023-02-28028 February 2023 Response to Request for Additional Information (RAI) for Relief Request for RPV Reactor Coolant System Welds RA-23-0025, End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI)2023-02-15015 February 2023 End of Cycle 28 (M1R28) Steam Generator Tube Inspection Report Response to Request for Additional Information (RAI) RA-22-0147, Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility2022-05-13013 May 2022 Duke Energy Carolinas, LLC, and Duke Energy Progress, LLC, Response to Request for Additional Information (RAI) Regarding License Amendment Request for Relocating the Duke Energy Emergency Operations Facility RA-22-0102, Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology2022-04-0707 April 2022 Response to Request for Additional Information (RAI) Regarding Revision 1 of DPC-NE-1007-P, Conditional Exemption of the EOC Mtc Measurement Methodology RA-22-0003, Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative2022-01-31031 January 2022 Response to Requests for Additional Information for Reactor Vessel Closure Stud Exam Extension Alternative RA-21-0259, Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-10-0404 October 2021 Response to Request for Additional Information for Request to Use Provisions of a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/ Replacement Activities in Accordance with 10 CFR 50.55a(g)(4 RA-21-0063, 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan2021-03-11011 March 2021 1, 2; Catawba Nuclear Station 1, 2; H. B. Robinson Steam Electric Plant 2; Mcgguire Nuclear Station 1, 2; Oconee Nuclear Station 1, 2, 3; Shearon Harris Nuclear Power Plant 1 - Response to RAI Re Amend for Emergency Plan RA-21-0032, Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(42021-02-11011 February 2021 Duke Energy - Response to Requests for Additional Info for Request to Use a Provision of Later Edition & Addenda of the ASME Boiler & Pressure Vessel Code, Section XI for Repair/Replacement Activities in Accordance with 10 CFR 50.55a(g)(4)( RA-21-0017, Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage2021-01-29029 January 2021 Response to Request for Additional Information Re License Amendment Request to Revise Tech Spec 3.8.1 to Reduce Emergency Diesel Generator Maximum Steady State Voltage RA-20-0087, Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period2020-04-0202 April 2020 Response to Request for Additional Information Regarding Request for Alternative in Accordance with 10CFR 50.55a(z)(1) to Delay the Update of the ASME Code of Record for the First Inspection Period RA-19-0189, Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.12019-04-0808 April 2019 Supplement to Response for Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 RA-19-0004, Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 22019-03-0707 March 2019 Response to NRC for Additional Information (RAI) Regarding License Amendment Request Proposing Changes to the Technical Specifications 3.8.1 for Catawba Nuclear Station, Units 1 and 2 RA-19-0026, Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001)2019-02-11011 February 2019 Response to Request for Additional Information (RAI) Regarding Proposed Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 and 10 (18-GO-001) RA-19-0005, Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A2019-01-30030 January 2019 Response to NRC Request for Additional Information Regarding Review Request of the Aging Management Program and Inspection Plan for the Reactor Vessel Internals to Implement MRP-227-A RA-18-0229, Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.12018-12-0303 December 2018 Response to NRC Request for Additional Information Regarding License Amendment Request Proposing Changes to the Technical Specification 3.8.1 RA-18-0213, Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles2018-11-0101 November 2018 Response to the Second Request for Additional Information Regarding the License Amendment Request to Revise the Licensing Bases for Protection from Tornado-Generated Missiles ML18191A5642018-07-10010 July 2018 Attachment 3 - Response to NRC Request for Additional Information 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 ML20052D9362018-07-0303 July 2018 Response to Nrg Request for Additional Information (RAI) Regarding NAC Magnastor Cask Loaded to Incorrect Helium Backfill Density 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 ML17349A1572017-12-12012 December 2017 Response to Request for Additional Information Regarding License Amendment Request for Temporary Changes to Technical Specifications to Address the 'A' Train Nuclear Service Water System Non-Conforming Condition RA-17-0039, Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001)2017-08-0909 August 2017 Response to Request for Additional Information (RAI) Regarding 10 CFR 50.55a(z)(1)Proposed Alternative to ASME Section XI Threads in Flange Examination (17-GO-001) RA-17-0035, Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating.2017-07-20020 July 2017 Supplement to License Amendment Request Proposing Changes to Technical Specification 3.5.1, AC Sources - Operating. 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 RA-17-0030, Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers2017-06-0808 June 2017 Response to Request for Additional Information Regarding Application to Reverse Technical Specifications to Adopt Multiple Technical Specification Task Force Travelers 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 CNS-16-066, Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task..2016-10-20020 October 2016 Stations - Supplemental Information Regarding Reevaluated Seismic Hazard Screening and Prioritization Results - Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task.. ML16294A2542016-10-13013 October 2016 Response to Request for Additional Information Regarding Relief Request 16-MN-002, Alternative to Defect Removal Prior to Performing Repair Activities on Nuclear Service Water System Piping RA-16-0035, Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation2016-10-0303 October 2016 Response to Request for Additional Information (RAI) Regarding Application for Emergency Operations Facility (EOF) Consolidation ML16244A0602016-08-18018 August 2016 Response to Request for Addition Information to RR 16-MN-003 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 ML16230A0062016-08-11011 August 2016 Response to Request for Additional Information Regarding License Amendment Request to Technical Specification 3.6.13, Ice Condenser Doors RA-16-0027, Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations2016-07-14014 July 2016 Response to NRC Regulatory Issue Summary 2016-09 Preparation and Scheduling of Operator Licensing Examinations 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-16-023, Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications2016-03-16016 March 2016 Response to Request for Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request for Control Room Chilled Water System Technical Specifications ML16056A2422016-02-18018 February 2016 Response to Request for Additional Information Regarding the License Amendment Request (LAR) to Change the Emergency Plan to Upgrade Emergency Action Levels Based on NEI 99-01, Revision 6 MNS-16-005, Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension2016-02-10010 February 2016 Response to Request for Additional Information (RAI) During January 12, 2016, NRC Teleconference Pertaining to License Amendment Request for Nuclear Service Water System Allowed Outage Time Extension MNS-16-008, Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2016-02-0404 February 2016 Expedited Seismic Evaluation Process (ESEP) Closeout, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. MNS-16-009, Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c)2016-02-0404 February 2016 Response to NRC Letter Dated December 9, 2015, Request for Additional Information Regarding Request for Exemption from Title 10 of the Code of Federal Regulations (10 CFR) Part 74.19(c) RA-16-0006, Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions2016-02-0101 February 2016 Response to NRC Request for Additional Information (RAI) Regarding Application to Use Alternate Fission Gas Gap Release Fractions MNS-16-003, Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation2016-01-0707 January 2016 Response to Request for Additional Information (RAI) Regarding License Amendment Request to Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation ML15343A0122015-12-0707 December 2015 Response to NRC Letter Dated 10/26/2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension. MNS-15-093, Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System2015-11-13013 November 2015 Response to Request for Additional Information Regarding License Amendment Request Regarding Residual Heat Removal System MNS-15-078, Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension2015-10-0808 October 2015 Response to NRC Letter Dated September 14, 2015, Request for Additional Information Regarding License Amendment Request, Nuclear Service Water System Allowed Outage Time Extension MNS-15-077, Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..2015-10-0808 October 2015 Expedited Seismic Evaluation Process (ESEP) Report (CEUS Sites), Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.. 2023-07-07
[Table view] |
Text
(111tte.DUKE Serial No: MNS-17-023 May 25, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy) McGuire Nuclear Station, Units 1 and 2 Docket Nos. 50-369 and 50-370 License Amendment Request Steven D. Capps 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 Steven. Ca pps@d u ke-energy.com 10 CFR 50.90 Permanent Extension of Type A and Type C Leak Rate Test Frequencies Response to Request For Additional Information By letter dated December 19, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16363A349), Duke Energy submitted the subject license amendment request to the U.S. Nuclear Regulatory Commission (NRC) for approval.
By electronic mail dated April 28, 2016 (ADAMS No. ML 17121A005), the NRC requested additional information.
The enclosed document provides the requested information.
This submittal contains no regulatory commitments.
If you have any questions or require additional*
information, please contact P.T. Vu of Regulatory Affairs at (980) 875-4302.
I declare under penalty of perjury that the foregoing is true and correct. Executed on May 25, 2017. Sincerely, Steven D. Capps Enclosure www.duke-energy.com U.S. Nuclear Regulatory Commission May 25, 2017 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 M. Mahoney, 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 W. L. Cox, Ill, Section Chief North Carolina Department of Health and Human Services Radiation Protection Section 1645 Mail Service Center Raleigh, NC 27699-1645 License Amendment Request Request for Additional Information ENCLOSURE May 25, 2017 Enclosure Page 1of8 Serial No. MNS-17-023 By letter dated December 19, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16363A349), Duke Energy, (the licensee), requested changes to the Technical Specifications (TSs) for McGuire Nuclear Station (MNS), Units 1 and 2. The proposed change (LAR) would permit the existing Containment 10 CFR 50 Appendix J Type A Integrated Leakage Rate Test (ILRT) intervals to be extended from 1 O years to 15 years and the Type C test (LLRT) intervals for qualifying containment isolation valves (CIVs) to be extended from 60 months up to 75 months on a permanent basis. In order to complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests the following additional information.
Please provide your response to the following request for additional information within 30 days of the date of this correspondence.
RAl-1 The NRC staff notes that the licensee adopted Option B of 10 CFR 50, Appendix J following the September 4, 2002 issuance of Amendment No. 207 to Facility Operating License No. NPF-9 and Amendment No. 188 to Facility Operating License NPF-17 for MNS, Units 1 and 2. Per the guidance of Nuclear Energy Institute (NEI) 94-01, "Industry Guideline for Implementing Performance-Based Option of 1 O CFR Part 50, Appendix J," Revision O (Reference 2), Section 10.2.3.2 and subject to the four provisions identified in Regulatory Position "C" of Regulatory Guide (RG) 1.163, "Performance-Based Containment Leak-Test Program," both MNS, Unit 1 and Unit 2 are currently allowed to extend the test intervals for Type C CIVs up to 60 months. :1 RG 1.63 Regulatory Position C.2 reads, in part: . . . . .
Further, the interval for Type C tests for main steam and feedwater isolation valves in BWRs, and containment purge and vent valves in PWRs and BWRs, should be limited to 30 months as specified in Section 3.3.4 of ANSl/ANS-56.8-1994, with consideration given to operati,ng experience and safety significance.
Section 10.2.3.2 of NEI 94-01 of both Revision 0 and Revision 3-A (Reference
- 3) reads, in part: Test intervals for Type C valves may be increased based upon completion of two consecutive periodic As-found Type C tests where the result of each test is within a licensee's allowable administrative limits ..... As conveyed in LAR Section 3.3 "Containment Leakage Rate Testing Program, Type B and Type C Testing," the NRC staff notes that currently less than half of the population of both Unit's CIVs are on extended frequencies of 60 months. The NRC staff's review of LAR Table 3.3-3 "MNS Type Band C LLRT Program Implementation Review As-Found Failures of Components on Extended Intervals (emphasis added)" fails to adequately explain "Why a greater percentage of the CIVs are not qualifying for extended frequencies"?
The NRC staff requests that the licensee provide additional information about LAR Section 3.3 and Table 3.3-3. In particular, about: A. All (i.e. not just those on extended frequencies)
CIVs that failed "Administrative Limits" during the last two MNS, Unit 1 and Unit 2 refueling outages.
May 25, 2017 Serial No. MNS-17-023 Response to RAl-1 A Enclosure Page 2 of 8 The two most recent MNS Unit 1 refueling outages were 1 EOC23 (September 2014) and 1EOC24 (March 2016). The two most recent MNS Unit 2 refueling outages were 2EOC23 (September 2015) and 2EOC24 (March 2017). Tables 1 -4 contain Type C LLRT administrative failures for the requested outages. All leakage rates are reported in standard cubic centimeters perminute (seem) and include instrument uncertainty.
As-found penetration minimum pathway leakage rates (MNPLR) are provided in parentheses to demonstrate penetration integrity.
Table 1: 1 EOC23 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed Observed Valve As-Found Leak As-Left Leak Administrative Rate (MNPLR) Rate Failure Limit 1M-309 1NM-423' off scale ( 17) 1 2:: 110 1M-374 1WL-64A" 2,100 (2,100) 1 2:: 590 1M-221 1WL-385" 190 (1.44) 190 2:: 147.5 Table 1 Footnotes:
- 1. 1 NM-423 disassembly noted excessive wear on valve disc and body seat. Internal valve parts were replaced and the seat mating surface was verified to have 100% contact. 2. 1WL-64A inspection revealed a limit switch setup issue that prevented full seating load on the diaphragm valve. Limit switches were adjusted to restore seating load. 3. 1WL-385 leakage was accepted by engineering.
Repairs were completed the following outage, 1 EOC24 as shown in Table 2. Table 2: 1 EOC24 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed As-Observed As-Administrative Found Leak Left Leak Failure Limit Rate (MNPLR) Rate 1 M-317 1Vl-124 1 1 ,300 (7.2) 2.4 2:: 295 1 M-221 1WL-385" 568 (3) 9.1 2:: 147.5 1 M-342 1NV-1002
off scale (3.41) 1 2:: 295 1 M-309 1NM-22AC" off scale (2.6) 4 2:: 147.5 1 M-327 1KC-340" off scale (2) 47 2:: 1, 180 1 M-320 1KC-424Bl'.l off scale (19) 970 2:: 1, 180 Table 2 Footnotes:
- 1. 1Vl-124 disassembly noted an impression on the b'ody seat that required lapping to restore proper sealing surfaces.
Lapping was performed until 100% contact was achieved.
- 2. 1WL-385 disassembly noted a small particle of foreign material on the valve seat. Refer to RAl-1 B response for more details associated with 1WL-385. 3. 1NV-1002 disassembly noted the valve disc soft seat to be deteriorated and in need of replacement.
Internal valve parts were replaced.
- 4. 1 NM-22AC disassembly noted a bent valve stem at the disc to stem connection.
The valve was repaired with new parts. 5. 1 KC-340 disassembly noted residue present on the valve seat. The valve seat was repaired and disc verified to cycle freely. Refer to RAl-1 B response for more details associated with 1 KC-340.
May 25, 2017 Serial No. MNS-17-023 Enclosure Page 3 of 8 6. 1 KC-4248 torque setting was found out of tolerance.
Torque setting adjustments were made to decrease leakage. Table 3: 2EOC23 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed As-Observed Administrative Found Leak As-Left Leak Failure Limit Rate (MNPLR) Rate 2M-309 2NM-421 1 588 (1.07) 588 ;::: 110.6 Table 3 Footnotes:
- 1. 2NM-421 leakage was accepted by engineering.
2NM-421 leakage reduced to 85 seem in 2EOC24. Table 4: 2EOC24 CIVs Exceeding LLRT Administrative Failure Limits Penetration CIV Observed As-Observed Administrative Found Leak As-Left Leak Failure Limit Rate (MNPLR) Rate 2M-221 2WL-385' 189 (53.6) 189 147.5 Table 4 Footnotes:
- 1. 2WL-385 leakage was accepted by engineering.
B. Whether there have been repetitive failures of "Administrative Limits" for any LLRTs associated with the MNS, Unit 1 or Unit 2 Type C tests (i.e. CIVs) since the last ILRTs of 2008. If so, please provide a minimum of three examples that details the corrective actions performed to prevent reoccurrence.
The examples presented should be with respect to the worst performing CIVs. Response to RAl-1 B A review of Type C leak rate test failures since the last ILRTs of 2008 for both units was conducted.
For Unit 1, eight valves were noted as having more than one administrative failure. For Unit 2, one valve was noted as having more than one administrative failure. Valve 1WL-385 (Penetration 1M-221) During 1 EOC21 (September 2011 ), Valve 1WL-385, Unit 1 Ventilation Unit Condensate Drain Tank (VUCDT) Inlet Penetration Check Valve, failed to meet its administrative test acceptance criterion of< 147.5 seem when tested at 15 psig. The observed leakage was 474 seem. The testing was being conducted in accordance with a normally scheduled Appendix J program surveillance under Option B. 1WL-385 is a one-inch soft seat "Y" pattern Kerotest check valve with spring assist to close. The valve functions as a CIV in the closed direction and to provide thermal overpressure relief of the associated penetration piping in the open direction.
1WL-385 is tested in parallel with Motor Operated Valve (MOV) 1WL-321A (Unit 1 VUCDT Containment Inside Isolation Valve). 1 NM-321A has an administrative test acceptance criterion of< 885 seem at 15 psig. Since the system configuration limits the ability to determine which valve is contributing the leakage or ratio of leakage, the penetration test was considered a failure to meet the individual valve administrative leak rate criterion, specifically that of 1WL-385. As a result of 1WL-385 administrative failure, penetration 1 M-221 was removed from Option B May 25, 2017 Serial No. MNS-17-023 Enclosure Page 4 of 8 extended interval testing and placed on base interval.
Prior to Unit 1 restart,474 seem was evaluated and determined to be acceptable when compared to the total allowable bypass leakage limit of 0.07La (9,820 seem) and the total combined Type B and C allowable limit of 0.6La (84,200 seem). No further work was required to address 1WL-385 leakage during 1 EOC21. Work Order (WO) 02013330 was initiated for 1WL-385 disassembly and inspection during refueling outage 1 EOC22. During 1EOC22 (March 2013), 1WL-385 failed to meet its administrative test acceptance criterion of< 147.5 seem when tested at 15 psig. The observed leakage was 1, 782 seem. The testing was being conducted prior to WO 02013330 valve disassembly and was considered an as-found failure. Given that 1WL-385 experienced elevated as-left leakage during 1 EOC21, the 1 EOC22 as-found failure was* not unexpected, although test data confirmed an adverse change in performance.
1WL-385 was disassembled and the disc assembly rubber seat was discovered worn and required replacement.
The valve seat was lapped to ensure proper contact between mating surfaces and the disc was verified to cycle freely. The valve internal spring and body gaskets were replaced with new parts. Inspection of 1WL-385 revealed the cause of leakage to be a deteriorated valve disc soft seat that prevented a proper seal between the disc and valve body seat. Following 1WL-385 repairs during 1 EOC22, as-left testing was performed.
1WL-385 failed to meet its administrative test acceptance criterion of< 147.5 seem when tested at 15 The observed leakage was 485 seem. Prior to Unit 1 restart, the leakage was evaluated and determined to be acceptable when compared to the total allowable bypass leakage limit of 0.07La (9,820 seem) and the total combined Type B and C allowable limit of 0.6La (84,200 seem). No additional work was pursued to*address 1WL-385 leakage during 1 EOC22, and penetration 1 M-221 remained on base interval testing frequency.
WO 02171306 was initiated for 1WL-385 disassembly and inspection during refueling outage 1EOC23. . During 1 EOC23, 1WL-385 failed to meet its administrative test acceptance criterion of< 147.5 seem when tested at 15 psig. The observed leakage was 190 seem. Based on a reduction in leak rate from 1 EOC22, 1WL-385 was not disassembled for inspection in 1 EOC23 and WO 02171306 was rescheduled for 1 EOC24. During 1 EOC24, 1WL-385 failed to meet its administrative test acceptance criterion of< 147.5 seem when tested at 15 psig. The observed leakage was 568 seem. 1WL-385 was disassembled and a small particle of debris was discovered on the seat. The foreign material prevented a proper seal between the disc and valve body seat. The valve was reassembled with all new parts. As-left leak rate testing was conducted with a final value of 9.1 seem. The 1WL-385 valve LLRT failures represent an adverse trend because this valve failed multiple times from 2011 to 2016. The two maintenance inspections during 1 EOC22 and 1 EOC24 yielded two separate failure modes. Prior to 2011, penetration 1 M-221 had favorable LLRT results. The discussion below classifies each failure mode witnessed and actions taken (if any) to prevent recurrence.
1WL-385 soft seat degradation 1 EOC22: As a result of the potential for 1WL-385 soft seat degradation, a preventative maintenance (PM) task was created to rebuild the valve; replacing the soft seat, spring, gaskets and to perform lapping to ensure proper contact of mating sealing surfaces.
For 1WL-385, maintenance history shows the elastomers were replaced during 1 EOC8 (May 1993) and in 1 EOC22 (March May 25, 2017 Serial No. MNS-17-023 Enclosure Page 5 of 8 2013). Based on the expected service life, the PM interval was set at 15 refueling outages, or approximately 22.5 years. MNS will continue to monitor valve performance by testing in accordance with the 10 CFR 50 Appendix J program and make adjustments in PM frequency as necessary based on inspection results. 1WL-385 foreign material 1 EOC24: Penetration 1 M-221 is used as a part of the Unit 1 upper and lower containment ventilation unit
- condensate drain system. Condensate for each air-handling unit is transported through six-inch MOV 1WL-321A (inside CIV) and 1WL-322B (outside CIV) to the VUCDT located outside of containment.
The penetration piping and associated CIVs are protected from thermal pressurization by a one-inch spring check valve, 1WL-385. This portion of the liquid waste system operates under low pressure since the ventilation unit drains are open to containment atmosphere.
Since the system inlet is open to the environmental effects of the ventilation units, the system is vulnerable to particulate and other small system generated foreign material, especially in sections of small bore piping with low flows. 1WL-385 is located outside the normal flow path, parallel to 1WL-321A and would not experience forward or reverse flow during normal operation.
- Per MNS 4th interval In-service Testing (IST) submittal dated February 27, 2013 (ADAMS ML 13078A009), 1WL-385 was re-categorized from ASME OM code category A to category A&C. Per 2004 ASME OM Code 2004 Edition through 2006 Addenda, Table ISTC-3500-1 requires category A&C check valves to undergo leakage testing and bi-directional exercise testing. As a part of MNS 4th IST interval update, LLRT procedure changes were implemented to include forward flow exercise testing of 1WL-385 as a part of performing LLRT on the valve. The procedure sequence directs forward flow testing of the valve before performing LLRT in the reverse (accident) direction.
With respect to ISTC-5221 "Check Valves," paragraph (a.1) states that "check valves that have a safety function in both directions shall be exercised by initiating flow and observing that the obturator has traveled to either the full open position or to the position required to perform its intended function(s), and verify that on cessation or reversal of flow, the obturator has traveled to the Per this section of the code, forward flow exercise testing is required before closure verification testing. MNS utilizes LLRT for 1WL-385 to ensure the valve obturator has returned to the seat following forward flow verification testing. Although 1WL-385 leakage values have exceeded the program administrative limit, pressurization to 15 psig with an adequate vent path ensures the valve is not experiencing gross leakage and that the valve obturator returned to the seated position.
MNS is aware of the potential for introducin'g foreign material to the valve seat by performing forward flow verification testing before leak rate testing and concluded this testing sequence to be the most conservative with respect to the known as-left condition of the valve. Penetration 1 M-221 LLRT remains on base interval subject to the rules of 1 O CFR 50 Option B. Associated valves will continue to be monitored each refueling outage until the conditions of NEI 94-01, Revision 0, Section 10.2.3 are met. 1 KC-340 (Penetration 1 M-327) During 1EOC19 (September 2008), 1 KC-340 failed to meet its administrative test acceptance criterion of< 1180 seem when tested at 15 psig. The observed leakage was 2,006 seem. The test was being conducted in accordance with 10 CFR 50 Appendix J Option B. As a result of the as-found failure, penetration 1 rvI-327 was removed from extended interval testing and May 25, 2017 Serial No. MNS-17-023 Enclosure Page 6 of 8 returned to based interval.
1 KC-340 is an eight-inch wafer style check valve with soft seat. A torsion spring provides light seating pressure.
To address 1 KC-340 as-found leakage, WO 1833494 was generated to inspect the valve. Upon inspection a brownish residue was found on the valve seat and could be hand removed using a light abrasive pad. After re-assembly, a light check was performed and visible light could be seen past the disc 0-ring. After additional cleaning, no light was visible past the disc 0-ring. It is not clear why the additional cleaning of the valve would have any effect on the 0-ring contact with the seating surface. The valve was noted to open easily with light finger pressure.
The seat leakage is believed to be caused by the brown residue on the seating surface and secondarily, by insufficient closing force applied by the torsional spring to create continuous and sufficient pressure on the 0-ring seal. The brown residue is likely caused by system corrosion inhibitor Sodium Molybdate used in the KC system since 2004. Following inspection, 1 KC-340 passed as-left testing with a leak rate of 247 seem at 15 psig test pressure.
1 KC-340 passed as-found testing .in both 1 EOC20 and 1 EOC21 at 1 seem and 1.39 seem, respectively.
Based on two successful as-found tests, penetration 1 M-327 was placed back on extended interval testing per NEI 94-01, Revision 0, Section 10.0. LLRT of penetration 1 M-327 was next due 1 EOC24. During 1 EOC24 (March 2016), 1 KC-340 failed to meet its administrative test acceptance criterion of< 1180 seem when tested at 15 psig. The observed leakage was off scale and the valve would not pressurize to 15 psig test pressure.
WO 20068356 was generated for 1 KC-340 inspection during 1 EOC24. Minor residue on the valve seating surface was noted by field technicians; however, the valve appeared to be in good condition.
Valve installation configuration matched design drawings and the hinge allowed proper movement of the disc assembly.
1 KC-340 successfully passed as-left testing at 47 seem. The likely cause was again determined to be a brownish residue acting as an obstruction preventing a proper seal between the disc 0-ring and the valve seat. As a result of this as-found failure, Penetration 1 M-327 was removed from extended interval testing and returned to base interval LLRT subject to the rules of 10 CFR 50 Option B. Valves associated with penetration 1 M-327 will continue to be monitored each refueling outage until the conditions of NEI 94-01, Revision 0, Section 10.0 are met. 1NF-1464 (Penetration 1M-372) During 1 EOC20 (March 2010), ice co'ndenser refrigeration system valve 1 NF-1464 failed to meet its test acceptance criterion of< 73.8 seem when tested at 15 psig using air. Actual observed leakage was 184. 7 seem. As a result of this failure, penetration 1 M-372 was removed from Option B extended interval testing and returned to base interval.
184. 7 seem was evaluated and determined to be insignificant compared to the overall containment leakage summation; therefore, no additional work was performed during 1 EOC20. WO 1926097 was generated to disassemble and inspect 1 NF-1464 during 1 EOC21. During 1 EOC21 (September 2011 ), 1 NF-1464 failed as-found leak rate testing with an observed leakage rate of 157 seem at 15 psig. The test was being conducted as an as-found test prior to valve disassembly per WO 1926097. The as-found testing was being conducted in a "wet" condition using the normal system glycol-water mixture. Per Technical Specification Surveillance Requirement (TSSR) 3.6.1.1 Note 3, Type C tests on penetrations M372 and M373 may be performed without draining the glycol-water mixture from the seats of their diaphragm valves if meeting a zero indicated leakage rate (not including instrument error). Since the May 25, 2017 Serial No. MNS-17-023 Enclosure Page 7 of 8 observed leakage of 157 seem exceeded TSSR 3.6.1.1 requirement of zero indicated leakage, this was considered the second consecutive 1 M-372 penetration failure. Following as-found testing, 1 NF-1464 was removed from the system and bench testing was conducted using air in the accident direction (checked direction).
Bench testing included supplying pressurized air in the accident direction and submerging the opposite side of the valve in water. Bubbles were present at 1 psig and continued to worsen as air pressure was increased.
For troubleshooting purposes, bench test pressure was increased to 40 psig when the bubbles began to decrease.
This additional data suggested that small debris was likely on the valve soft seats and that the additional test pressure aided the valve's ability to seal. Upon valve disassembly, foreign material was found on the valve body seat. Per engineering inspection, the foreign material was described as resembling grinding dust and normal system corrosion flakes from carbon steel piping. The valve was cleaned and soft seats replaced.
After valve assembly, another bench test was conducted in the same manner as the as-found bench test. No bubbles were observed while slowly increasing pressure from 1 psig to 20 psig. The valve was also bench tested in the forward flow direction with satisfactory results. 1 NF-1464 was reinstalled into the system and post maintenance leak rate testing was performed.
The observed as-left leakage for 1 NF-1464 was 1 seem. Since 1 EOC21, Penetration 1 M-372 has successfully passed its LLRT three times. 1 EOC22, 1 EOC23 and 1 EOC24 observed as-found leakages were 1, 1.3 and 1 seem, respectively.
The penetration is currently on Option B t?Xtended interval testing with the next Type C LLRT due in 1EOC27. C. Of the total number of 86 Unit 1 Type C penetration tests, how many are not eligible for an extended frequency of 60 months per the requirements of RG 1.163 Regulatory Position C.2 and NEI 94-01, Revision O? Response to RAl-1 C Of 86 Unit 1 Type C penetration tests, 18 are associated with the containment purge (VP) system and kept on 30 month interval per requirements of RG 1.163 Regulatory Position C.2. Seven penetrations are considered service penetrations and are utilized during refueling outages to support maintenance activities.
Since these penetrations are manipulated each outage, testing is conducted in accordance with NEI 94-01, Revision 0, Section 10.2.3.3 "Repairs or Adjustments".
McGuire also has five Unit 1 penetrations that contain Rotork motor operated diaphragm valves. Vulnerability has been identified with this valve type associated with inadvertently re-setting the closed limit switch by manually operating these valves. Therefore, these five penetrations are programmatically restricted from Option B extended interval testing. The 30 penetration tests listed above are coded "SR" in MNS work management system, meaning a work order is automatically generated for conducting LLRT each outage. These 30 penetration tests are not eligible for an extended frequency of 60 months per the requirements of RG 1.163 Regulatory Position C.2 and NEI 94-01, Revision 0. Based on the restrictions above, 56 Type C penetration tests are eligible for Option B testing. Of those 56, there are currently 39 Type C penetration tests on Option B extended interval testing representing 69.6% of the eligible population.
May 25, 2017 Serial No. MNS-17-023 Enclosure Page 8 of 8 D. Of the total number of 88 Unit 2 Type C penetration tests, how many are not eligible for an extended frequency of 60 months per the requirements of RG 1.163 Regulatory Position C.2 and NEI 94-01, Revision O? Response to RAl-1 D Of 88 Unit 2 Type C penetration tests, 18 are associated with the VP system and kept on 30 month interval per requirements of RG 1.163 Regulatory Position C.2. Eight penetrations are considered service penetrations and are utilized during refueling outages to support maintenance activities.
Since these penetrations are manipulated each outage, testing is conducted in accordance with NEI 94-01, Revision 0, Section 10.2.3.3 "Repairs or Adjustments".
McGuire also has six Unit 2 penetrations that contain Rotork motor operated diaphragm valves. Vulnerability has been identified with this valve type associated with inadvertently re-setting the closed limit switch by manually operating these valves. Therefore, these six penetrations are programmatically restricted from Option B extended interval testing. The 32 penetration tests listed above are coded "SR" in MNS work management system, meaning a work order is automatically generated for conducting LLRT each outage. These 32 penetration tests are not eligible for an extended frequency of 60 months per the requirements of RG 1.163 Regulatory Position C.2 and NEI 94-01, Revision 0. Based on restrictions above, 56 Type C penetration tests are eligible for Option B testing. Of those 56, there are currently 40 Type C penetration tests on Option B extended interval testing representing 71.4% of the eligible population.