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Category:Code Relief or Alternative
MONTHYEARML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RA-22-0257, Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-02-17017 February 2023 Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22213A2532022-08-31031 August 2022 Authorization and Safety Evaluation for Alternative Request RA-21-0144 to Use Reactor Vessel Head Penetration Embedded Flaw Repair Method ML22007A3452022-01-11011 January 2022 Proposed Alternative to Use the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-885 ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI 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-18-0180, Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 22018-11-12012 November 2018 Supplement to Relief Request for an Alternative to the Depth Sizing Qualification Requirement of Appendix Viii, Supplements 2 ML18016A1782018-01-24024 January 2018 Request for Relief No. 17-CN-001, Regarding Category B-J Pressure Retaining Welds for the Third 10-Year Inservice Testing Interval (CAC Nos. MF9807 and MF9808; EPID L-2017-LLA-0032) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads ML17104A1102017-04-26026 April 2017 Relief Request CN Grr 01, Alternative to the Testing Frequencies in the American Society of Mechanical Engineers Operation and Maintenance Code, by Adoption of Code Case OMN-20, Inservice Test Frequencies (CAC Nos. MF9595-6) CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017 Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing ML15301A5442015-11-10010 November 2015 Proposed Relief Request 15-CN-001, Alternative Repair of a Main Steam System Braided Flex-Hose CNS-15-062, Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2)2015-07-16016 July 2015 Relief Request Serial Number 15-CN-001, Proposed Alternative Repair for Main Steam System Braided Flex-Hose - Submitted Pursuant to 10 CFR 50.55a(z)(2) ML15161A3762015-06-19019 June 2015 Proposed Relief Request 14-CN-002, Alternative to American Society of Mechanical Engineers (ASME) Section XI Requirements for Class 3 Buried Piping ML15124A6992015-05-0808 May 2015 (Catawba 1 and 2) - Request to Use a Later Edition of the ASME Boiler and Pressure Vessel Code, Section X1, for Inservice Inspection Activities ML14295A5322014-10-30030 October 2014 Proposed Relief Request 14-CN-001, American Society of Mechanical Engineers (ASME) Section IX Volumetric Examination Requirements ML14079A5462014-03-26026 March 2014 Proposed Relief Request 13-CN-003, Request for Alternative to the Requirement of IWB-2500, Table IWB-2500-1, Category B-A and Category B-D for Reactor Pressure Vessel Welds ML11187A0012011-07-14014 July 2011 Relief 10-CN-001, Alternative Requirements for Temporary Acceptance of a Through-Wall Flaw in Boric Acid Tank Nozzle Weld ML1012501702010-05-0303 May 2010 Withdrawal of Request for Relief Number 09-CN-001, Limited Weld Examinations During the End-of-Cycle 17 Refueling Outage ML0912401562009-05-27027 May 2009 Relief 06-CN-003 for Use of Polyethylene Material in Buried Service Water Piping ML0902301722009-01-16016 January 2009 Response to NRC Requests for Additional Information and Request for Relief (Alternative) Number 08-CN-002 - Reactor Vessel Hot Leg Nozzle-to-Safe End Weld Full Structural Weld Overlays ML0831506302008-11-0606 November 2008 Transmittal of Request for Relief Number 08-CN-002, Reactor Vessel Hot Leg Nozzle-to-Safe End Weld Full Structural Weld Overlays (Fswols) ML0822403862008-09-12012 September 2008 Relief 06-CN-003, Use of Polyethylene Material in Nuclear Safety-Related Piping Applications ML0815607342008-07-0707 July 2008 Request for Relief 07-CN-001, Limited Weld Examinations During End-Of -Cycle 14 Refueling Outage ML0816000032008-07-0101 July 2008 Request for Relief 07-CN-002, Limited Weld Examinations During End-of-Cycle 14 Refueling Outage ML0731804472007-08-27027 August 2007 Request for Relief Number 07-CN-004 Limited Weld Examinations During the End-of-Cycle 16 Refueling Outage ML0706504172007-02-26026 February 2007 Submittal of Request for Relief Number 07-CN-003, Request for Relief to Allow Use of Alternate Requirements for Snubber Inspection & Testing ML0636000142007-01-0909 January 2007 Relief, Request to Use a Portion of a Letter Edition of ASME Code ML0632801882006-11-16016 November 2006 Revision to Relief Request 06-GO-001 ML0623900202006-09-25025 September 2006 Request for Relief 05-CN-004, Limited Weld Examinations During End-of-Cycle 15 Refueling Outage, MC8337, MC9171, MC9172, MC9173, MC9174, MC9175, MC9176, MC9177, MC9178, and MC9179) ML0626202612006-09-11011 September 2006 Relief Request 06-GO-001 Request for Additional Information ML0622304212006-09-0707 September 2006 Relief, Request for Relief for Snubber Visual Examination and Functional Testing Related to the Third 10-year Interval Inservice Inspection Program ML0634903992006-07-27027 July 2006 Relief Request 06-GO-001 ML0616603262006-07-20020 July 2006 Request for Use of Later Edition and Addenda of the ASME Code ML0616800102006-07-19019 July 2006 Regarding Request for Relief 05-CN-001, Limited Weld Examinations During End-of-Cycle 14 Refueling Outage ML0535503702006-04-0303 April 2006 Relief, O5-CN-003 Limited Weld Examination Coverage ML0517801882005-07-25025 July 2005 RR 04-CN-001, Volumetric Weld Inspection Requirements ML0519403672005-07-13013 July 2005 Relief Request MC3057, 04-CN-002, Limited Weld Examinations During End-of-Cycle 12 Refueling Outage ML0518901432005-06-28028 June 2005 Submittal of Third Ten-Year Interval Inservice Inspection Plan for Steam Generator Tubing ML0517801642005-06-23023 June 2005 RR 04-CN-004, Class 1 ISI Pressure Test Boundaries Requirement (Tac No. MC3276, MC3277) ML0510203642005-03-31031 March 2005 Relief, Request to Use a Later Edition and Addenda of the ASME Boiler and Pressure Vessel Code, Section XI for Repair/Replacement Activities at Catawba Nuclear Station, Unit 2 in Accordance with 10 CFR 50.55a(g) (4) (IV) ML0504105322005-03-17017 March 2005 RR, Alternative Code of Prv Nozzle Welds for Volumetic Examination RR-04-GO-001 ML0504904622005-02-17017 February 2005 Relief, RR No. 03-001, 10 CFR Section 50.55a (a)(3)(ii) for Second ISI Intervals ML0428106012004-10-20020 October 2004 Relief Request, Alternate to the American Society of Mechanical Engineers Section XI for Reactor Vessel Examinations RR-04-GO-001 ML0427400272004-09-30030 September 2004 Relief, Amended Relief Request 03-GO-010 Requesting Use of Subsequent Edition and Addenda of the ASME Code for Class Mc and CC Components (MC9674-MC9680) ML0427302912004-09-29029 September 2004 Request for Relief, 04-GO-006, for Use of an Alternate Code Case to Use Ultrasonic Techniques Equipment ML0420403942004-07-20020 July 2004 Request for Relief 03-004, Minimum Percentage Requirements for Second Period of the Second Inservice Inspection Interval 2023-09-25
[Table view] Category:Letter type:CNS
MONTHYEARCNS-18-008, License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing2018-07-19019 July 2018 License Amendment Request to Remove the Containment Valve Injection Water System Supply from Specified Containment Isolation Valves and to Exempt These CIVs from Type-C Local Leak Rate Testing CNS-18-032, Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report2018-07-12012 July 2018 Refueling Outage 22 (C2R22) Inservice Inspection Report Summary Report CNS-18-031, Notice of Enforcement Discretion (NOED) Request2018-06-18018 June 2018 Notice of Enforcement Discretion (NOED) Request CNS-18-028, 2017 Annual Radiological Environmental Operating Report2018-05-14014 May 2018 2017 Annual Radiological Environmental Operating Report CNS-18-026, Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report2018-05-10010 May 2018 Transmittal of 2017/2018 10 CFR 50.59 Evaluation Summary Report CNS-18-023, (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System2018-05-0808 May 2018 (Cns), Units 1 and 2 - Response to NRC Requests for Additional Information (Rais) License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System CNS-18-025, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-30030 April 2018 Submittal of 2017 Annual Radioactive Effluent Release Report CNS-18-022, Submittal of Emergency Plan Implementing Procedure2018-04-12012 April 2018 Submittal of Emergency Plan Implementing Procedure CNS-18-017, Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-22018-03-24024 March 2018 Catawba, Units 1 and 2, Submittal of Emergency Plan, Revision 18-1 and 18-2 CNS-18-015, Commitment Change Evaluation Report for 20172018-03-22022 March 2018 Commitment Change Evaluation Report for 2017 CNS-18-005, Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes2018-02-0808 February 2018 Technical Specification Bases Changes and Ufsar/Selected Licensee Commitment Changes CNS-18-006, Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days2018-01-23023 January 2018 Submittal of Special Report 2018-01 for the Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-058, Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukus2017-12-28028 December 2017 Supplement to the High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushi CNS-17-061, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information2017-12-21021 December 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations Response to NRC Requests for Additional Information CNS-17-056, Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-22017-11-0101 November 2017 Catawba Nuclear Station Units 1 and 2, Resubmittal of Emergency Plan, Revision 17-2 CNS-17-056, Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-22017-10-23023 October 2017 Catawba Nuclear Station Units 1 and 2, Submittal of Emergency Plan, Revision 17-2 CNS-17-053, Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement2017-10-12012 October 2017 Transmittal of 2016 Annual Radioactive Effluent Release Report - Supplement CNS-17-048, Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-1222017-09-29029 September 2017 Supplemental Response to Preliminary White Finding, Apparent Violations, and NRC Inspection Report 05000414/2017012; Enforcement Action 17-122 CNS-17-049, Submittal of Ufsar/Selected Licensee Commitment Changes Manual2017-09-28028 September 2017 Submittal of Ufsar/Selected Licensee Commitment Changes Manual CNS-17-051, Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask2017-09-28028 September 2017 Independent Spent Fuel Storage Installation (ISFSI) Registration of Spent Fuel Storage Cask CNS-17-014, License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time2017-09-14014 September 2017 License Amendment Request to Revise Technical Specification Section 3.7.8, Nuclear Service Water System, to Add a New Condition to Allow Single Pond Return Header Operation of the Nsws with a 30-Day Completion Time CNS-17-050, ISFSI - Registration of Spent Fuel Storage Cask2017-09-12012 September 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-047, Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding2017-08-29029 August 2017 Response to NRC Inspection Report 05000414/2017012 and Preliminary White Finding CNS-17-041, ISFSI - Registration of Spent Fuel Storage Cask2017-08-15015 August 2017 ISFSI - Registration of Spent Fuel Storage Cask CNS-17-040, Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump2017-08-14014 August 2017 Withdrawal of Inservice Testing Relief Request 17-CN-002 Regarding an Alternative Method to Establish New Reference Values for Testing Chemical and Volume Control Pump CNS-17-039, Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump2017-07-27027 July 2017 Relief Request 17-CN-002, Request for Alternative Method to Establish New Inservice Testing Values for a Chemical and Volume Control Pump CNS-17-036, Mid-Cycle Power Uprate Ascension Startup Report2017-06-29029 June 2017 Mid-Cycle Power Uprate Ascension Startup Report CNS-17-033, Technical Specification Bases Changes2017-06-27027 June 2017 Technical Specification Bases Changes CNS-17-029, Flood Hazard Mitigating Strategies Assessment Report Submittal2017-06-20020 June 2017 Flood Hazard Mitigating Strategies Assessment Report Submittal CNS-17-030, Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core2017-06-20020 June 2017 Catawba, Unit 1, Submittal of Core Operating Limits Report (Colr) for Cycle 24 Reload Core CNS-17-024, Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations2017-05-25025 May 2017 Third Ten-Year Inservice Inspection Plan, Limited Volumetric Examinations CNS-17-031, Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report2017-05-24024 May 2017 Response to NRC Requests for Additional Information End of Cycle 21 Refueling Outage Inservice Inspection Report and Steam Generator Inservice Inspection Summary Report CNS-17-027, Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report2017-05-10010 May 2017 Submittal of 2015/2016 10 CFR 50.59 Evaluation Summary Report CNS-17-015, Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report2017-04-27027 April 2017 Catawba Nuclear Station, Units 1 and 2 - Submittal of 2016 Annual Radioactive Effluent Release Report CNS-17-021, Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days2017-04-20020 April 2017 Special Report 2017-01 for the Units 1 and 2 Loose Parts Monitoring System Non-Functional for Greater than 30 Days CNS-17-020, Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing2017-04-11011 April 2017 Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve Inservice Testing CNS-17-008, Commitment Change Evaluation Report for 20162017-03-16016 March 2017 Commitment Change Evaluation Report for 2016 CNS-17-004, Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants.2017-01-26026 January 2017 Response to NRC Request for Additional Information on License Amendment Request to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants. CNS-17-002, End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report2017-01-0606 January 2017 End of Cycle 21 Refueling Outage, Lnservice Inspection Report and Steam Generator Lnservice Inspection Summary Report CNS-16-080, Submittal of Emergency Plan Implementing Procedure2016-12-20020 December 2016 Submittal of Emergency Plan Implementing Procedure CNS-16-077, Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-12-0808 December 2016 Expedited Seismic Evaluation Process Closeout, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendations 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident 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.. CNS-16-069, Submittal of Emergency Plan, Revision 16-22016-10-10010 October 2016 Submittal of Emergency Plan, Revision 16-2 CNS-16-068, Submittal of Emergency Plan Implementing Procedure Revisions2016-10-10010 October 2016 Submittal of Emergency Plan Implementing Procedure Revisions CNS-16-064, License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 242016-09-0707 September 2016 License Amendment Request to Adopt National Fire Protection and Revised Response to Probabilistic Risk Assessment Request for Additional Information 24 CNS-16-061, Submittal of Design Basis Specification for the Plant Fire Protection Revision 252016-08-12012 August 2016 Submittal of Design Basis Specification for the Plant Fire Protection Revision 25 CNS-16-051, License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) an2016-08-0202 August 2016 License Amendment Request (LAR) to Adopt National Fire Protection Association (NFPA) 805 Performance-Based Standard for Fire Protection for Light-Water Reactor Generating Plants, Response to NRC Request for Additional Information (RAI) and CNS-16-049, ISFSI Registration of Spent Fuel Storage Cask2016-07-14014 July 2016 ISFSI Registration of Spent Fuel Storage Cask CNS-16-056, Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/00682016-07-13013 July 2016 Transmittal of Emergency Plan Implementing Procedures, Including Revision 034 to RP/0/A/5000/006A and Revision 038 to RP/0/A/5000/0068 CNS-16-050, Unit 2 - Ufsar/Selected Licensee Commitment Changes2016-07-12012 July 2016 Unit 2 - Ufsar/Selected Licensee Commitment Changes 2018-07-19
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Text
el'_~DUKE Tom Simril
~ ENERG~ Vice President Catawba Nuclear Station Duke Energy
- CN01VP 14800 Concord Road York, SC 29745 o: 803.701.3340 f: 803.701.3221 CNS-17-020 10 CFR 50.55a April 11, 2017 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Catawba Nuclear Station, Units 1 and 2 Docket Nos.50-413 and 50-414 Renewed License Nos.NPF-35 and NPF-52
Subject:
Application to Adopt ASME Code Case OMN-20 (CN-GRR-01) for Pump and Valve lnservice Testing Pursuant to Title 10 of the Code of Federal Regulations ( 10 CFR) 50.55a(z)(2), Duke Energy Carolinas, LLC, collectively referred to henceforth as "Duke Energy," requests an alternative to the testing frequencies in the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code, by adoption of approved Code Case OMN-20, "lnservice Test Frequency," for the current ten-year lnservice Testing (IST) interval for the Catawba Nuclear Stations (CNS) Units 1 and 2. Section IST of Division 1 of the OM Code, which is incorporated by reference in 10 CFR 50.55(a), specifies component test frequencies based either on elapsed time periods (e.g., quarterly, two years) or on the occurrence of a plant condition or event (e.g.,
cold shutdown, refueling outage).
ASME OM committee has approved ASME Code Case OMN-20 as an alternative to the test .
frequencies for pumps and valves specified in ASME OM Division 1, Section IST 2009 Edition through OMa-2011 Addenda and all earlier editions and addenda of ASME OM Code. The latest revision of Regulatory Guide (RG) 1.192 (August 2014) does not reference Code Case OMN-20 as an acceptable OM Code Case to comply with 10 CFR 50.55a(f) requirements as allowed by 10 CFR 50.55a(b)(6). The proposed alternative is to use Code Case OMN-20 to extend or reduce the IST frequency requirements for the current fourth ten-year IST interval or until Code Case OMN-20 is incorporated into the next revision of RG 1.192.
To support routine scheduling of pump and valve testing, without reliance on Technical Specification section 5.5.8, "lnservice Testing Program," provisions that permit similar scheduling flexibility, and upcoming Unit 1 refueling outage, Duke Energy requests approval of the relief request prior to April 21 2017.
There are no regulatory commitments contained in this letter.
www.duke-energy.com
U.S. Nuclear Regulatory Commission CNS-17-020 April 11, 2017 Page2 If you have any questions regarding this submittal, please contact Tolani E. Owusu at (803) 701-5385.
Sincerely, Tom Simril Vice President, Catawba Nuclear Station
Enclosure:
Generic Relief Request CN-GRR-01
U.S. Nuclear Regulatory Commission CNS-17-020 April 11, 2017 Page3 cc: (Enclosure)
C. Haney, Regional Administrator U.S. Nuclear Regulatory Commission - Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, GA 30303-1257 J. D. Austin, Senior Resident Inspector U.S., Nuclear Regulatory Commission Catawba Nuclear Station M. Mahoney, NRG Project Manager (Catawba)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mailstop 0-8H4A Rockville, MD 20852-2738 S. E. Jenkins Manager Radioactive & Infectious Waste Management Division of Waste Management South Carolina Department of Health and Environmental Control 260 Bull St.
Columbia, SC 29201
Enclosure U.S. Nuclear Regulatory Commission CNS-17-020 April 11, 2017 Enclosure Catawba Nuclear Station, Units 1and2 Generic Relief Request CN-GRR-01 Alternative Due To Hardship Without a Compensating Increase in Quality and Safety in Accordance with 10 CFR 50.55a(z)(2)
1.0 DESCRIPTION
The request is to adopt a proposed alternative to the American Society of Mechanical Engineers (ASME) Operation and Maintenance (OM) Code by adoption of approved Code Case OMN-20, "lnservice Test Frequency."
2.0 ASSESSMENT Technical Evaluation of the Proposed Alternative to the OM Code Section IST of Division 1 of the OM Code, which is incorporated by reference in 10 CFR 50.55a(a), specifies component test frequencies based either on elapsed time periods (e.g., quarterly, 2 years) or* on the occurrence of a plant condition or event (e.g., cold shutdown, refueling outage).
ASME Code Case OMN-20, "lnservice Test Frequency," has been approved for use by the ASME OM committee as an alternative to the test frequencies for pumps and valves specified in ASME OM Division, 1 Section IST 2009 *Edition through OMa-2011 Addenda, and all earlier editions and addenda of ASME OM Code.
Code Case OMN-20 is nof referenced in the latest revision of Regulatory Guide 1.192 (August 2014) as an acceptable OM Code Case to comply with 10 CFR 50.55a(f) requirements as allowed by 10 CFR 50.55a(b)(6). The proposed alternative is to use Code Case OMN-20 to extend or reduce the IST frequency requirements for the fourth ten-year IST interval or until OMN-20 is incorporated into the next revision of Regulatory Guide 1.192.
ASME Code Components Affected The Code Case applies to pumps and valves specified in ASME OM Division 1, Section IST 2009 Edition through OMa-2011 Addenda and all earlier editions and addenda of ASME OM Code. Frequency extensions may also be applied to accelerated test frequencies (e.g., pumps in Alert Range) as specified in OMN-20.
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Enclosure U.S. Nuclear Regulatory Commission CNS-17-020 April 11, 2017 For pumps and valves with test periods of two years of less, the test frequency allowed by OMN-20 and the current TS lnservice Testing Program [as modified by TS Surveillance Requirement (SR) 3.0.2 and Enforcement Guidance Memorandum (EGM) 2012-001] are the same. For pumps and valves with test frequencies greater than two years, OMN-20 allows the test frequency to be extended by six months. The current TS lnservice Testing Program does not allow extension of inservice testing intervals that are greater than two years. *
Applicable Code Edition and Addenda
ASME Code Case OMN-20 applies to ASME OM Division, 1 Section IST 2009 Edition through OMa-2011 Addenda and all earlier editions and addenda of ASME OM Code.
The CNS Units 1 and 2, Code Edition and Addenda that are applicable to the program interval are ASME OM Code 2004 Edition with 2006 Addenda. The CNS Units 1 and 2 current interval ends August 19, 2025.
Applicable Code Requirement
This request is made in accordance with 10 CFR 50.55a(z)(2), and proposes an alternative to the requirements of 10 CFR 50.55a(f), which requires pumps and valves to meet the test requirements set forth in specific documents incorporated by reference in 10 CFR 50.55a(a).
ASME Code Case OMN-20 applies to Division 1, Section IST of the ASME OM Code and associated addenda incorporated by reference in 10 CFR 50.55a(a).
Reason for Request
The IST Program controls specified in Section 5.5 of TS provide: a) a table specifying certain IST frequencies; b) an allowance to apply SR 3.0.2 to inservice tests required by the OM Code and with frequencies of two years or less; c) an allowance to apply SR 3.0.3 to inservice tests required by the OM Code; and d) a statement that, "Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS." In Regulatory Issue Summary (RIS) 2012-10, "NRC Staff Position on Applying Surveillance Requirement 3.0.2 and 3.0.3 to Administrative Controls Program Tests," and EGM 2012-001, "Dispositioning Noncompliance with Administrative Controls Technical Specifications Programmatic Requirements that Extend Test Frequencies and Allow Performance of Missed Tests," the NRC stated that items b, c, and d of the TS IST Program were inappropriately added to the TS and may not be applied (although the EGM allows licensees to continue to apply those paragraphs pending a generic resolution of the. issue).
In RIS 2012-10 and EGM 2012-001, the NRC stated that the current TS allowance to apply SR 3.0.2 and SR 3.0.3 to the lnservice Testing Program would no longer be permitted. In response, OMN-20, which provides allowances similar to SR 3.0.2, was approved and is proposed to be used as an alternative to the test periods specified in the OM code. The proposed alternative substitutes an approved Code Case for the existing TS requirements that the NRC has determined are not legally acceptable as a TS allowance. This proposed alternative provides an equivalent level of safety as the existing TS allowance, while maintaining consistency with 10 CFR 50.55a and the ASME OM Code.
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Enclosure U.S. Nuclear Regulatory Commission CNS-17-020 April 11, 2017 Proposed Alternative and Basis for Use The proposed alternative is OMN-20, "lnservice Test Frequency," which addresses testing periods for pumps and valves specified in ASME OM Division 1, Section IST, 2009 Edition through OMa-2011 Addenda and all earlier editions and addenda of ASME OM Code.
This request is being made in accordance with 10 CFR 50.55a(z)(2), in that the existing requirements are considered a hardship without a compensating increase in quality and safety for the following reasons:
- 1) For IST testing periods up to and including two years, Code Case OMN-20 provides an allowance to extend the IST testing periods by up to 25%. The period extension is to facilitate test scheduling and considers plant operating conditions that may not be suitable for performance of the required testing (e.g., performance of the test would cause an unacceptable increase in the plant risk profile due to transient conditions or other ongoing surveillance, test or maintenance activities). Period extensions are not intended to be used repeatedly merely as an operational convenience to extend test intervals beyond those specified. The test period extension and the statements regarding the appropriate use of the period extension are equivalent to the existing TS SR 3.0.2 allowance and the statements regarding its use in the SR 3.0.2 Bases. Use of the SR 3.0.2 period extension has been a practice in the nuclear industry for many decades and elimination of this allowance would place a hardship on CNS when there is no evidence that the period extensions affect component reliability.
- 2) For IST testing periods of greater than 2 years, OMN-20 allows an extension of up to six months. The ASME OM Committee determined that such an extension is appropriate.
The six-month extension will have a minimal impact on component reliability considering that the most probable result of performing any inservice test is satisfactory verification of the test acceptance criteria. As such, pumps and valves will continue to be adequately assessed for operational readiness when tested in accordance with the requirements specified in 10 CFR 50.55a(f) with the frequency extensions allowed by Code Case OMN-20.
- 3) As stated in EGM 2012-001, if an lnservice Test is not performed within its frequency, SR 3:0.3 will not be applied. The effect of a missed lnservice Test on the Operability of TS equipment will be assessed under the licensee's Operability Determination Program. ,
Duration of Proposed Alternative The proposed alternative is requested for the current 10 year IST interval or until Code Case OMN-20 is incorporated into a future revision of Regulatory Guide 1.192, referenced by a future revision of 10 CFR 50.55a, whichever occurs first.
Precedents
- The NRC approved the use of OMN-20 for North Anna on March 27, 2014 (NRC ADAMS Accession Number ML14084A407).
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Enclosure U.S. Nuclear Regulatory Commission CNS-17-020 April 11, 2017
- The NRG approved the use of OMN-20 for Duane Arnold on June 9, 2014 (NRG ADAMS Accession Number ML14144A002).
- The NRG approved the use of OMN-20 for Oconee Nuclear Station on March 1, 2016 (NRG ADAMS Accession Number ML16053A501).
- The NRG approved the use of OMN-20 for Point Beach, Seabrook, St. Lucie, and Turkey Point on December 15, 2016 (NRG ADAMS Accession Number ML16330A118).
- The NRG approved the use of OMN-20 for Sequoyah Nuclear Plant on March 2, 2017 (NRG ADAMS Accession Number ML170598791 ).
- The NRG approved the use of OMN-20 for Palo Verde Nuclear Generating Station on March 16, 2017 (NRG ADAMS Accession Number ML17074A209).
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