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| | number = ML11084A004 | | | number = ML11084A004 |
| | issue date = 03/31/2011 | | | issue date = 03/31/2011 |
| | title = Edwin I. Hatch Nuclear Plant, Units 1 and 2, Safety Evaluation to Use Subsequent Edition of American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance | | | title = Safety Evaluation to Use Subsequent Edition of American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance |
| | author name = Kulesa G J | | | author name = Kulesa G |
| | author affiliation = NRC/NRR/DORL/LPLII-1 | | | author affiliation = NRC/NRR/DORL/LPLII-1 |
| | addressee name = Ajluni M J | | | addressee name = Ajluni M |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000321, 05000366 | | | docket = 05000321, 05000366 |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 March 31, 2011 Mr. M. J. Ajluni Nuclear licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, SAFETY EVALUATION TO USE SUBSEQUENT EDITION OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE FOR OPERATION AND MAINTENANCE (TAC NOS. ME4964 AND ME4965) | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 31, 2011 Mr. M. J. Ajluni Nuclear licensing Director Southern Nuclear Operating Company, Inc. |
| | 40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 |
| | |
| | ==SUBJECT:== |
| | EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, SAFETY EVALUATION TO USE SUBSEQUENT EDITION OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE FOR OPERATION AND MAINTENANCE (TAC NOS. ME4964 AND ME4965) |
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| ==Dear Mr. Ajluni:== | | ==Dear Mr. Ajluni:== |
| By letter dated October 29, 2010, Southern Nuclear Operating Company, Inc. (SNC, the licensee), submitted a request for approval to use a portion of a later edition of the American Society of Mechanical Engineers (ASME), Gode for Operation and Maintenance of Nuclear Power Plants (OM Code) for the inservice testing (1ST) program at Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (Hatch 1 and 2). Specifically, approval was requested to apply the requirements of Mandatory Appendix I, paragraph 1-3410, of the 2004 Edition of the ASME OM Code for testing of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. The licensee requested approval for the remainder of the Hatch 1 and 2 fourth 10-year 1ST interval, which began on January 1, 2006, and is scheduled to end on December 31,2015. Based on the review of the information the licensee provided, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee's request to use a portion of the later edition of the ASME Code can be authorized pursuant to Title 10 of the Gode of Federal Regulations (10 CFR), Part 50, Section 55a(f)(4)(iv), for Hatch 1 and 2, for the licensee's fourth 10-year 1ST interval.
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| All other ASME Code, Section XI requirements for which the later code edition was not specifically requested and authorized herein by the NRC staff remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
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| M. Ajluni -If you have any questions, please contact the Project Manager, Patrick Boyle at 301-415-3936.
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| Sincerely, Gloria Kulesa, Branch Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and Safety cc w/encl: Distribution via UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO USE OF A LATER EDITION OF THE ASME OM CODE FOR INSERVICE TESTING OF CLASS 1 MAIN STEAM PRESSURE RELIEF VALVES WITH AUXILIARY ACTUATING DEVICES FOR THE FOURTH 10-YEAR INTERVAL SOUTHERN NUCLEAR OPERATING COMPANY, INC. EDWIN I. HATCH NUCLEAR PLANT UNIT NOS. 1 AND 2 DOCKET NOS. SO-321 AND SO-366
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| ==1.0 INTRODUCTION== | | By letter dated October 29, 2010, Southern Nuclear Operating Company, Inc. (SNC, the licensee), submitted a request for approval to use a portion of a later edition of the American Society of Mechanical Engineers (ASME), Gode for Operation and Maintenance of Nuclear Power Plants (OM Code) for the inservice testing (1ST) program at Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (Hatch 1 and 2). Specifically, approval was requested to apply the requirements of Mandatory Appendix I, paragraph 1-3410, of the 2004 Edition of the ASME OM Code for testing of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. The licensee requested approval for the remainder of the Hatch 1 and 2 fourth 10-year 1ST interval, which began on January 1, 2006, and is scheduled to end on December 31,2015. |
| | Based on the review of the information the licensee provided, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee's request to use a portion of the later edition of the ASME Code can be authorized pursuant to Title 10 of the Gode of Federal Regulations (10 CFR), Part 50, Section 55a(f)(4)(iv), for Hatch 1 and 2, for the licensee's fourth 10-year 1ST interval. All other ASME Code, Section XI requirements for which the later code edition was not specifically requested and authorized herein by the NRC staff remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. |
| | |
| | M. Ajluni - 2 If you have any questions, please contact the Project Manager, Patrick Boyle at 301-415-3936. |
| | Sincerely, Gloria Kulesa, Branch Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 |
| | |
| | ==Enclosure:== |
| | |
| | Safety Evaluation cc w/encl: Distribution via Listserv |
| | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO USE OF A LATER EDITION OF THE ASME OM CODE FOR INSERVICE TESTING OF CLASS 1 MAIN STEAM PRESSURE RELIEF VALVES WITH AUXILIARY ACTUATING DEVICES FOR THE FOURTH 10-YEAR INTERVAL SOUTHERN NUCLEAR OPERATING COMPANY, INC. |
| | EDWIN I. HATCH NUCLEAR PLANT UNIT NOS. 1 AND 2 DOCKET NOS. SO-321 AND SO-366 |
| | |
| | ==1.0 INTRODUCTION== |
| | |
| | By letter dated October 29. 2010 (Agencywide Documents Access and Management System, Accession No. ML103090168), Southern Nuclear Operating Company, Inc. (SNC, the licensee), |
| | submitted a request, NL-10-1021. for approval to use a portion of a later edition of the American Society of Mechanical Engineers (ASME), Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the inservice testing (1ST) program at Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (Hatch 1 and 2). The licensee requested to apply the requirements of Mandatory Appendix I, paragraph 1-3410 of the 2004 Edition of the ASME OM Code for testing of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices in lieu of the OM Code 2001 Edition through 2003 Addenda requirements. |
| | Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR). Part SO. |
| | Section SSa(f)(4)(iv), the licensee requested in NL-10-1021. to use portions of the 2004 Edition of the ASME OM Code subject to the limitations and modifications listed in 10 CFR SO.SSa(b). |
| | |
| | ==2.0 REGULATORY EVALUATION== |
| | |
| | Section SO.SSa(f). "Inservice testing reqUirements," requires, in part, that 1ST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed at 120-month (10-year) 1ST program intervals in accordance with the specified ASME Code and applicable addenda incorporated by reference in the regulations. In accordance with 10 CFR SO.SSa(f)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 120-month 1ST program interval. In accordance with 10 CFR SO.SSa(f)(4)(iv), 1ST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to Nuclear Regulatory Commission (NRC) approval. |
| | Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. NRC Regulatory Issue Summary (RIS) 2004-12, Enclosure |
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| By letter dated October 29. 2010 (Agencywide Documents Access and Management Accession No. ML 103090168), Southern Nuclear Operating Company, Inc. (SNC, the submitted a request, NL-10-1021.
| | - 2 "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI", |
| for approval to use a portion of a later edition of the Society of Mechanical Engineers (ASME), Code for Operation and Maintenance ofPower Plants (OM Code) for the inservice testing (1ST) program at Edwin I. Hatch Plant, Unit Nos. 1 and 2 (Hatch 1 and 2). The licensee requested to apply the requirements Mandatory Appendix I, paragraph 1-3410 of the 2004 Edition of the ASME OM Code for of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices in lieu of OM Code 2001 Edition through 2003 Addenda Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR). Part Section SSa(f)(4)(iv), the licensee requested in NL-10-1021.
| | (ADAMS Accession No. ML042090436) provides guidance for use of later code editions. |
| to use portions of the 2004 of the ASME OM Code subject to the limitations and modifications listed in 10 CFR
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| ==2.0 REGULATORY EVALUATION== | | ==3.0 TECHNICAL EVALUATION== |
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| Section SO.SSa(f). "Inservice testing reqUirements," requires, in part, that 1ST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed at 120-month (10-year) 1ST program intervals in accordance with the specified ASME Code and applicable addenda incorporated by reference in the regulations.
| | 3.1 Licensee's Request for Alternative The Hatch 1 and 2 fourth 1O~year 1ST interval began on January 1, 2006, and ends on December 31, 2015. The applicable Code of Record for Hatch 1 and 2 is the ASME OM Code, 2001 Edition through 2003 Addenda. This Code requires, in part, that Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices that have been maintained, refurbished or removed/reinstalled be remotely actuated to verify open and close capability of the valve. |
| In accordance with 10 CFR SO.SSa(f)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 120-month 1ST program interval.
| | The licensee requested approval to use the portion of the 2004 Edition of the ASME OM Code related to disposition after testing or maintenance of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. Specifically, the licensee proposes to apply the requirements of Mandatory Appendix I, paragraph 1-3410, which states: |
| In accordance with 10 CFR SO.SSa(f)(4)(iv), 1ST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to Nuclear Regulatory Commission (NRC) approval.
| | (a) Valves and accessories that comply with their respective acceptance criteria for the tests specified may be returned to service without further testing, except as required by 1-3410(d). |
| Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. NRC Regulatory Issue Summary (RIS) 2004-12, Enclosure
| | (b) Valves and accessories that do not comply with their respective acceptance criteria shall be adjusted, refurbished, or replaced, in accordance with written procedures. Valves shall be adjusted to meet the acceptance criteria of 1 1310(e). |
| -"Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI", (ADAMS Accession No. ML042090436) provides guidance for use of later code editions.
| | (c) Refurbished equipment shall be subjected to the test(s) specified in 1-3310, as applicable. If disassembly includes valve disk (main) components, then valve disk stroke capability shall be verified by mechanical examination or tests. |
| | (d) Each valve with an auxiliary actuating device that has been removed for maintenance or testing and reinstalled after meeting the requirements of 1~331 0, shall have the electrical and pneumatic connections verified either through mechanical/electrical inspection or test prior to the resumption of electric power generation. Main disc movement and set-pressure verification are not required. |
| | (e) Valves and accessories that do not comply with their respective acceptance criteria, whether the problem is associated with the component, the system, or associated equipment, shall be evaluated to determine the ability of the valve to perform its intended function until the next testing interval or maintenance opportunity. Corrective actions shall be taken, as appropriate, to ensure valve operability. |
| | The licensee proposes to apply these paragraphs to all Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices in the 1ST program at Hatch 1 and 2. The essential difference between the two code editions involves the testing specified in sub-paragraph (d) above for Main Steam Pressure Relief Valves With Auxiliary Actuating Devices after removal and reinstallation following maintenance or testing. Whereas the earlier code required that the |
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| ===3.0 TECHNICAL===
| | - 3 valves be remotely actuated to verify open and close capability, the newer code allows only an inspection of the valves' electrical and pneumatic connections (Le. main valve disc movement is not necessarily required). |
| | Federal Register (FR), Volume 73, Number 176, dated September 10, 2009 (73 FR 52730), |
| | incorporates by reference the 2004 Edition of the ASME OM Code for 1ST programs in 10 CFR 50.55a(b), subject to the limitations or modification imposed by 10 CFR 50.55a(b)(3). There are no further limitations or modifications imposed by 10 CFR 50.55a(b)(3) on the use of paragraph 1-3410, as regards 1ST of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. |
| | 3.2 NRC Staff's Evaluation The licensee has requested approval to test the Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices in accordance with Mandatory Appendix I, paragraph 1-3410 of the 2004 Edition of the ASME OM Code. The NRC staff has determined that there are no further limitations or modifications imposed by 10 CFR 50.55a(b)(3) on the use of the 2004 Edition of the ASME OM Code for Mandatory Appendix I, paragraph 1-3410, with regards to 1ST of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. Additionally, the NRC staff has not identified any additional related requirements in the 2004 Edition of the OM Code that need to be met in order to implement Mandatory Appendix I, paragraph 1-3410. |
| | Therefore, use of the 2004 Edition of the ASME OM Code in lieu of the 2001 through 2003 Addenda for 1ST of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices per Mandatory Appendix I, paragraph 1-3410, is acceptable. |
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| EVALUATION
| | ==4.0 CONCLUSION== |
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| ===3.1 Licensee's===
| | As set forth above, the NRC staff determines that the licensee's request, NL-10-1021, to use the 2004 edition of the ASME OM Code, Mandatory Appendix 1, paragraph 1-3410, for testing the Class 1 Main Steam Pressure Relief Valves with Auxiliary Actuating Devices for the remainder of the fourth 10-year 1ST interval at Hatch Unit 1 and Unit 2 is acceptable. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(f)(4)(iv), consistent with the ASME OM Code's requirements. |
| | Therefore, the NRC staff authorizes the request, NL-10-1021, for the remainder of the Hatch 1 and 2, fourth 10-year 1ST interval which commenced on January 1, 2006, and ends on December 31,2015. |
| | Principal Contributor: John G. Billerbeck, NRRlDCI Date: March 31, 2011 |
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| Request for Alternative The Hatch 1 and 2 fourth 1 1ST interval began on January 1, 2006, and ends on December 31, 2015. The applicable Code of Record for Hatch 1 and 2 is the ASME OM Code, 2001 Edition through 2003 Addenda. This Code requires, in part, that Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices that have been maintained, refurbished or removed/reinstalled be remotely actuated to verify open and close capability of the valve. The licensee requested approval to use the portion of the 2004 Edition of the ASME OM Code related to disposition after testing or maintenance of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. Specifically, the licensee proposes to apply the requirements of Mandatory Appendix I, paragraph 1-3410, which states: (a) Valves and accessories that comply with their respective acceptance criteria for the tests specified may be returned to service without further testing, except as required by 1-3410(d). (b) Valves and accessories that do not comply with their respective acceptance criteria shall be adjusted, refurbished, or replaced, in accordance with written procedures.
| | M. Ajluni -2 If you have any questions, please contact the Project Manager, Patrick Boyle at 301-415-3936. |
| Valves shall be adjusted to meet the acceptance criteria of 1310(e). (c) Refurbished equipment shall be subjected to the test(s) specified in 1-3310, as applicable.
| | Sincerely, IRA! |
| If disassembly includes valve disk (main) components, then valve disk stroke capability shall be verified by mechanical examination or tests. (d) Each valve with an auxiliary actuating device that has been removed for maintenance or testing and reinstalled after meeting the requirements of 0, shall have the electrical and pneumatic connections verified either through mechanical/electrical inspection or test prior to the resumption of electric power generation.
| | Gloria Kulesa, Branch Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366 |
| Main disc movement and set-pressure verification are not required. (e) Valves and accessories that do not comply with their respective acceptance criteria, whether the problem is associated with the component, the system, or associated equipment, shall be evaluated to determine the ability of the valve to perform its intended function until the next testing interval or maintenance opportunity.
| |
| Corrective actions shall be taken, as appropriate, to ensure valve operability.
| |
| The licensee proposes to apply these paragraphs to all Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices in the 1ST program at Hatch 1 and 2. The essential difference between the two code editions involves the testing specified in sub-paragraph (d) above for Main Steam Pressure Relief Valves With Auxiliary Actuating Devices after removal and reinstallation following maintenance or testing. Whereas the earlier code required that the
| |
| -valves be remotely actuated to verify open and close capability, the newer code allows only an inspection of the valves' electrical and pneumatic connections (Le. main valve disc movement is not necessarily required).
| |
| Federal Register (FR), Volume 73, Number 176, dated September 10, 2009 (73 FR 52730), incorporates by reference the 2004 Edition of the ASME OM Code for 1ST programs in 10 CFR 50.55a(b), subject to the limitations or modification imposed by 10 CFR 50.55a(b)(3).
| |
| There are no further limitations or modifications imposed by 10 CFR 50.55a(b)(3) on the use of paragraph 1-3410, as regards 1ST of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. 3.2 NRC Staff's Evaluation The licensee has requested approval to test the Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices in accordance with Mandatory Appendix I, paragraph 1-3410 of the 2004 Edition of the ASME OM Code. The NRC staff has determined that there are no further limitations or modifications imposed by 10 CFR 50.55a(b)(3) on the use of the 2004 Edition of the ASME OM Code for Mandatory Appendix I, paragraph 1-3410, with regards to 1ST of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. Additionally, the NRC staff has not identified any additional related requirements in the 2004 Edition of the OM Code that need to be met in order to implement Mandatory Appendix I, paragraph 1-3410. Therefore, use of the 2004 Edition of the ASME OM Code in lieu of the 2001 through 2003 Addenda for 1ST of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices per Mandatory Appendix I, paragraph 1-3410, is acceptable.
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| ==4.0 CONCLUSION== | | ==Enclosure:== |
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| As set forth above, the NRC staff determines that the licensee's request, NL-10-1021, to use the 2004 edition of the ASME OM Code, Mandatory Appendix 1, paragraph 1-3410, for testing the Class 1 Main Steam Pressure Relief Valves with Auxiliary Actuating Devices for the remainder of the fourth 10-year 1ST interval at Hatch Unit 1 and Unit 2 is acceptable.
| | Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION: |
| Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(f)(4)(iv), consistent with the ASME OM Code's requirements.
| | PUBLIC LPL2-1 RlF RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource RidsNrrDciCptb (AMcMurtray) RidsNrrLAMO'Brien Resource RidsRgn2MailCenter Resource RidsNrrPMHatchResource RidsNrrDirsltsbResource RidsAcrsAcnw_MailCTRResource NSanfilippo, EDO R-II JBillerbeck NRRIDCI ADAMS Accession No ML11084A004 "memo transmitted SE dated 03124/11 ML110871843 OFFICE NRRlLPL2-1/PM NRR/LPL2-1/LA NRR/CPTB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME PBoyle MOBrien AMcMurtray" GKulesa PBoyle DATE 03/30/11 03/30/11 03/24/11 03/31111 03/31/11 OFFICIAL RECORD COpy}} |
| Therefore, the NRC staff authorizes the request, NL-10-1021, for the remainder of the Hatch 1 and 2, fourth 10-year 1ST interval which commenced on January 1, 2006, and ends on December 31,2015. Principal Contributor:
| |
| John G. Billerbeck, NRRlDCI Date: March 31, 2011 M. Ajluni If you have any questions, please contact the Project Manager, Patrick Boyle at Docket Nos. 50-321 and Safety cc w/encl: Distribution via DISTRIBUTION:
| |
| PUBLIC LPL2-1 RlF RidsNrrDorlLpl2-1 Resource RidsNrrDciCptb (AMcMurtray) | |
| RidsRgn2MailCenter Resource RidsNrrDirsltsbResource NSanfilippo, EDO R-II ADAMS Accession No ML11084A004 Sincerely, IRA! Gloria Kulesa, Branch Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrDorlDpr Resource RidsNrrLAMO'Brien Resource RidsNrrPMHatchResource RidsAcrsAcnw_MailCTRResource JBillerbeck NRRIDCI "memo transmitted SE dated 03124/11 ML 110871843 OFFICE NRRlLPL2-1/PM NRR/LPL2-1/LA NRR/CPTB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME PBoyle MOBrien AMcMurtray" GKulesa PBoyle DATE 03/30/11 03/30/11 03/24/11 03/31111 03/31/11 OFFICIAL RECORD COpy}} | |
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Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis
NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024
SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations
IR 05000321/20240902024-05-15015 May 2024
NRC Inspection Report 05000321-2024090 and 05000366-2024090, Investigation Report 2-2023-003; and Apparent Violation
NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024
Annual Radiological Environmental Operating Reports for 2023
05000321/LER-2024-002, Manual Reactor Trip Due to Loss of Feedwater2024-05-0909 May 2024
Manual Reactor Trip Due to Loss of Feedwater
NL-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024
Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.
NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024
Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5
NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024
Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023
IR 05000032/20240112024-04-25025 April 2024
Notification of Edwin I. Hatch Nuclear Plant - Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 0500032/2024011 and 05000366/2024011
05000366/LER-2024-002, Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications2024-04-24024 April 2024
Incorrectly Installed Temporary Modification Results in a Condition Prohibited by Plant Technical Specifications
ML23032A3322024-04-24024 April 2024
Issuance of Amendments Nos. 322 and 267, Regarding LAR to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in TS Table 1.1-1, Modes
IR 05000321/20240012024-04-22022 April 2024
Integrated Inspection Report 05000321/2024001 and 05000366/2024001
NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint2024-04-19019 April 2024
Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint
05000321/LER-2024-001, Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)2024-04-0909 April 2024
Primary Containment Penetration Exceeded Maximum Allowable Primary Containment Leakage Rate (La)
NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024
Response to Request for Additional Information Exemption Requests for Physical.
NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024
Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.
ML23275A2402024-03-22022 March 2024
SNC Fleet - Issuance of Environmental Assessment and Finding of No Significant Impact Regarding Exemption from the Requirements of 10 CFR Part 73, Section 73.2, Definitions (EPID Nos. L-2023-LLE-0018 & L-2023-LLE-0021) - Letter
NL-24-0062, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-03-12012 March 2024
Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis
NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024
Correction of Technical Specification Omission
ML24069A0012024-03-0909 March 2024
– Correction of Amendment No. 266 Regarding License Amendment Request Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program (TSTF-425, Revision 3)
ML24047A0362024-03-0404 March 2024
Response to Hatch and Vogtle FOF Dates Change Request (2025)
NL-24-0061, Cycle 32 Core Operating Limits Report Version 12024-03-0101 March 2024
Cycle 32 Core Operating Limits Report Version 1
2024-09-09
[Table view]
Category:Safety Evaluation
MONTHYEARML23032A3322024-04-24024 April 2024
Issuance of Amendments Nos. 322 and 267, Regarding LAR to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in TS Table 1.1-1, Modes
ML23202A1122023-08-0202 August 2023
Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML23034A2462023-02-21021 February 2023
Audit Summary for License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs
ML22363A3932023-02-15015 February 2023
Issuance of Amendments Nos. 321 and 266, Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program
ML22346A1482023-02-0909 February 2023
Issuance of Amendments 320 and 265, Regarding LAR to Revise Technical Specifications to Adopt TSTF-208 and Administrative Correction for Duplicate Technical Specifications 3.4.10
ML22297A1462022-12-22022 December 2022
Issuance of Amendments Nos. 319 and 264, Regarding Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times – RITS
ML22293A0302022-11-0707 November 2022
Amendments 318 & 263 Issuance, Regarding LAR to Adopt TSTF-227, Revision to EOC-RPT Pump Actions, and TSTF-297, ATWS-RPT (EPID L-2021-LLA- 0227)
ML22192A1172022-09-0202 September 2022
Issuance of Amendments Nos. 317 & 262, Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-207-A, Completion Time for Restoration of Various Excessive Leakage Rates
ML22192A1992022-08-19019 August 2022
Issuance of Amendments Nos. 316 and 261, Regarding Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
ML22101A0942022-05-20020 May 2022
Issuance of Amendments Nos. 315 and 260, Regarding Request to Eliminate Automatic Main Steam Line Isolation on High Turbine Building Area Temperature
ML21349A5182022-02-0202 February 2022
Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-554, Revise RCS Leakage
ML21270A0862021-11-18018 November 2021
Issuance of Amendments Regarding Revision to Technical Specifications 5.7, High Radiation, Administrative Controls
ML21264A6442021-09-24024 September 2021
Issuance of Amendment to Revise Technical Specification 3.7.2, Plant Service Water (Psw) System and Ultimate Heat Sink (UHS) (EPID L-2021-LLA-0164) (Emergency Circumstances)
ML21217A0912021-09-21021 September 2021
SNC Fleet, Issuance of Amendments Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions
ML21167A3152021-07-30030 July 2021
Issuance of Amendments Regarding Revision to Technical Specifications to Adopt TSTF-541, Rev.2, Add Exceptions to Surveillance Requirements for Valves & Dampers Locked in Actuated Position
ML21161A2012021-06-22022 June 2021
Associated Independent Spent Fuel Storage Facilities - Reduction in Commitment to the Quality
ML21109A3592021-04-22022 April 2021
Issuance of Amendment No. 254, Regarding Revision to Technical Specifications for One-Time Extension of Completion Times Related to Residual Heat Removal System (Emergency Circumstances)
ML20294A0762020-12-0707 December 2020
Issuance of Amendments Nos. 308 and 253, Regarding Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements
ML20254A0752020-09-18018 September 2020
Safety Evaluation by the Office of Nuclear Reactor Regulation Related to Amendment No. 307 to Facility Operating License No. DPR-57 and Amendment No. 252 to Facility Operating License No. NPF-5
ML20202A0052020-09-15015 September 2020
Issuance of Amendments Nos. 306 and 251, Regarding the Application to Revise Technical Specifications to Adopt TSTF-568, Revise Appliciability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2
ML20077J7042020-06-26026 June 2020
Issuance of Amendment Nos. 305 and 250, Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
ML20066F5922020-06-11011 June 2020
Issuance of Amendments Nos. 304 and 249, Regarding License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)
ML20143A2332020-06-0303 June 2020
Relief Request for Deferral of ASME Boiler and Pressure Vessel Code, Section XI, Required Summary Report Submittal (EPID L-2020-LLR-0074 (COVID-19))
ML20034E8942020-02-11011 February 2020
Relief Request Gen-ISI-ALT-2019-01 for Proposed Alternative to Use of ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1
ML19337C3222020-01-29029 January 2020
Issuance of Amendments Revision to Technical Specifications to Adopt TSTF-563
ML19239A2442019-11-19019 November 2019
Issuance of Amendments Regarding Revision to Technical Specification Requirements During Handling Irradiated Fuel and Core Alterations
ML19267A0232019-11-13013 November 2019
Issuance of Amendments the Revision to Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable (Residual Heat Removal) RHR Shutdown Cooling Subsystems, Using Consolidated Line Item Improvement Process
ML19212A0542019-09-20020 September 2019
Issuance of Amendments 299 and 244 Regarding Revision to Technical Specifications to Adopt Tstf-564, Safety Limit (Minimum Critical Power Ratio) MCPR
ML19198A1042019-09-0404 September 2019
Issuance of Amendments Regarding Revision to Technical Specification 3.6.4.1 - Secondary Containment
ML19177A1662019-07-0808 July 2019
Edwin Hatch Unit Nos. 1 and 2, Issuance of Amendments Regarding License Amendment Request to Correct Non-Conservative Technical Specification Allowable Values for the Condensate Storage Tank Low Level Transfer Function
ML19091A2912019-04-30030 April 2019
Issuance of Amendments 296 and 241 to Revise Technical Specifications 3.6.2.5, Condition C, Residual Heat Removal Drywell Spray End State
ML19064A7742019-04-26026 April 2019
Issuance of Amendments Regarding License Amendment Request to Revise Technical Specification 5.2.2.g and Update Emergency Plan Minimum on Shift Staff Tables
ML19044A5552019-04-0303 April 2019
Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109
ML19064A0872019-03-0808 March 2019
Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-08
ML19053A0932019-02-22022 February 2019
Issuance of Amendments to Revise Technical Specification 3.8.1, AC Sources - Operating (EPID L-2019-LLA-0026) (Emergency Circumstances)
ML19035A5502019-02-0606 February 2019
Relief Request HNP ISI RR 05-02 Regarding Reactor Pressure Vessel Head Stud Inservice Inspection Requirements
ML19010A0092019-01-28028 January 2019
Issuance of Amendments to Revise Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation
ML19011A0102019-01-22022 January 2019
Proposed Alternative HNP-ISI-ALT-05-04 for the Implementation of BWRVIP Guidelines
ML18320A0572018-11-30030 November 2018
Plant, Units 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2017-03, Code Case N-513-4 for Moderate Pressure
ML18289A6192018-10-18018 October 2018
Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-07
ML18222A2962018-08-29029 August 2018
Issuance of Amendments to Revise Technical Specification 3.7.7, ECCS - Operating (CAC Nos. MF9997 and MF9998; EPID L-2017-LLA-0263)
ML18183A0732018-07-26026 July 2018
Unites 1, 2, 3, and 4; and Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2(CAC Nos. MG0188, MG0189, MG0191, MG0192, MG0193, MG0194, and MG0195; EPID L-2017-LLA-0293)
ML18163A1602018-06-15015 June 2018
Proposed Alternative RR-V-11, Extension of Main Steam Safety Relief Valve Test Interval
ML18123A3682018-05-31031 May 2018
Issuance of Amendments to Adopt TSTF-542, RPV Water Inventory Control (CAC Nos. MF9662 and MF9663; EPID L-2017-LLA-0215)
ML18102B0162018-04-16016 April 2018
Proposed Inservice Inspection Alternative HNP-ISI-ALT-05-05 (CAC Nos. MF9812 and MF9813; EPID L-2017-LLR-0053)
ML18022A1072018-01-25025 January 2018
Inservice Inspection Alternative GEN-ISI-ALT-2017-02, Version 1.0, Regarding the Use of ASME Code Case N-789-1 (CAC Nos. MF9942, MF9943, MF9944, and MF9945; EPID L-2017-LLR-0059)
ML17355A4402018-01-22022 January 2018
Issuance of Amendments to Revise TS 3.6.4.1, Secondary Containment (CAC Nos. MF9590 and MF9591; EPID L-2017-LLA-0216)
ML17271A3072017-11-30030 November 2017
Issuance of Amendments to Revise Actions of TS 5.5.12, Primary Containment Leakage Rate Testing Program
ML17279A0452017-10-26026 October 2017
Relief Requests ISI-RR-13, -14, -18, -19, -23, and -24 for Relief from Inservice Inspection Requirements
ML17268A0442017-10-20020 October 2017
Relief Requests ISI RR 16, ISI-RR-17, ISI-44-21, and ISI-RR-22 for Relief from Inservice Inspection Requirements
2024-04-24
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 31, 2011 Mr. M. J. Ajluni Nuclear licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, SAFETY EVALUATION TO USE SUBSEQUENT EDITION OF AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE FOR OPERATION AND MAINTENANCE (TAC NOS. ME4964 AND ME4965)
Dear Mr. Ajluni:
By letter dated October 29, 2010, Southern Nuclear Operating Company, Inc. (SNC, the licensee), submitted a request for approval to use a portion of a later edition of the American Society of Mechanical Engineers (ASME), Gode for Operation and Maintenance of Nuclear Power Plants (OM Code) for the inservice testing (1ST) program at Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (Hatch 1 and 2). Specifically, approval was requested to apply the requirements of Mandatory Appendix I, paragraph 1-3410, of the 2004 Edition of the ASME OM Code for testing of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. The licensee requested approval for the remainder of the Hatch 1 and 2 fourth 10-year 1ST interval, which began on January 1, 2006, and is scheduled to end on December 31,2015.
Based on the review of the information the licensee provided, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee's request to use a portion of the later edition of the ASME Code can be authorized pursuant to Title 10 of the Gode of Federal Regulations (10 CFR), Part 50, Section 55a(f)(4)(iv), for Hatch 1 and 2, for the licensee's fourth 10-year 1ST interval. All other ASME Code,Section XI requirements for which the later code edition was not specifically requested and authorized herein by the NRC staff remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
M. Ajluni - 2 If you have any questions, please contact the Project Manager, Patrick Boyle at 301-415-3936.
Sincerely, Gloria Kulesa, Branch Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO USE OF A LATER EDITION OF THE ASME OM CODE FOR INSERVICE TESTING OF CLASS 1 MAIN STEAM PRESSURE RELIEF VALVES WITH AUXILIARY ACTUATING DEVICES FOR THE FOURTH 10-YEAR INTERVAL SOUTHERN NUCLEAR OPERATING COMPANY, INC.
EDWIN I. HATCH NUCLEAR PLANT UNIT NOS. 1 AND 2 DOCKET NOS. SO-321 AND SO-366
1.0 INTRODUCTION
By letter dated October 29. 2010 (Agencywide Documents Access and Management System, Accession No. ML103090168), Southern Nuclear Operating Company, Inc. (SNC, the licensee),
submitted a request, NL-10-1021. for approval to use a portion of a later edition of the American Society of Mechanical Engineers (ASME), Code for Operation and Maintenance of Nuclear Power Plants (OM Code) for the inservice testing (1ST) program at Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (Hatch 1 and 2). The licensee requested to apply the requirements of Mandatory Appendix I, paragraph 1-3410 of the 2004 Edition of the ASME OM Code for testing of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices in lieu of the OM Code 2001 Edition through 2003 Addenda requirements.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR). Part SO.
Section SSa(f)(4)(iv), the licensee requested in NL-10-1021. to use portions of the 2004 Edition of the ASME OM Code subject to the limitations and modifications listed in 10 CFR SO.SSa(b).
2.0 REGULATORY EVALUATION
Section SO.SSa(f). "Inservice testing reqUirements," requires, in part, that 1ST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed at 120-month (10-year) 1ST program intervals in accordance with the specified ASME Code and applicable addenda incorporated by reference in the regulations. In accordance with 10 CFR SO.SSa(f)(4)(ii), licensees are required to comply with the requirements of the latest edition and addenda of the ASME Code incorporated by reference in the regulations 12 months prior to the start of each 120-month 1ST program interval. In accordance with 10 CFR SO.SSa(f)(4)(iv), 1ST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(b), subject to Nuclear Regulatory Commission (NRC) approval.
Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. NRC Regulatory Issue Summary (RIS) 2004-12, Enclosure
- 2 "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI",
(ADAMS Accession No. ML042090436) provides guidance for use of later code editions.
3.0 TECHNICAL EVALUATION
3.1 Licensee's Request for Alternative The Hatch 1 and 2 fourth 1O~year 1ST interval began on January 1, 2006, and ends on December 31, 2015. The applicable Code of Record for Hatch 1 and 2 is the ASME OM Code, 2001 Edition through 2003 Addenda. This Code requires, in part, that Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices that have been maintained, refurbished or removed/reinstalled be remotely actuated to verify open and close capability of the valve.
The licensee requested approval to use the portion of the 2004 Edition of the ASME OM Code related to disposition after testing or maintenance of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. Specifically, the licensee proposes to apply the requirements of Mandatory Appendix I, paragraph 1-3410, which states:
(a) Valves and accessories that comply with their respective acceptance criteria for the tests specified may be returned to service without further testing, except as required by 1-3410(d).
(b) Valves and accessories that do not comply with their respective acceptance criteria shall be adjusted, refurbished, or replaced, in accordance with written procedures. Valves shall be adjusted to meet the acceptance criteria of 1 1310(e).
(c) Refurbished equipment shall be subjected to the test(s) specified in 1-3310, as applicable. If disassembly includes valve disk (main) components, then valve disk stroke capability shall be verified by mechanical examination or tests.
(d) Each valve with an auxiliary actuating device that has been removed for maintenance or testing and reinstalled after meeting the requirements of 1~331 0, shall have the electrical and pneumatic connections verified either through mechanical/electrical inspection or test prior to the resumption of electric power generation. Main disc movement and set-pressure verification are not required.
(e) Valves and accessories that do not comply with their respective acceptance criteria, whether the problem is associated with the component, the system, or associated equipment, shall be evaluated to determine the ability of the valve to perform its intended function until the next testing interval or maintenance opportunity. Corrective actions shall be taken, as appropriate, to ensure valve operability.
The licensee proposes to apply these paragraphs to all Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices in the 1ST program at Hatch 1 and 2. The essential difference between the two code editions involves the testing specified in sub-paragraph (d) above for Main Steam Pressure Relief Valves With Auxiliary Actuating Devices after removal and reinstallation following maintenance or testing. Whereas the earlier code required that the
- 3 valves be remotely actuated to verify open and close capability, the newer code allows only an inspection of the valves' electrical and pneumatic connections (Le. main valve disc movement is not necessarily required).
Federal Register (FR), Volume 73, Number 176, dated September 10, 2009 (73 FR 52730),
incorporates by reference the 2004 Edition of the ASME OM Code for 1ST programs in 10 CFR 50.55a(b), subject to the limitations or modification imposed by 10 CFR 50.55a(b)(3). There are no further limitations or modifications imposed by 10 CFR 50.55a(b)(3) on the use of paragraph 1-3410, as regards 1ST of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices.
3.2 NRC Staff's Evaluation The licensee has requested approval to test the Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices in accordance with Mandatory Appendix I, paragraph 1-3410 of the 2004 Edition of the ASME OM Code. The NRC staff has determined that there are no further limitations or modifications imposed by 10 CFR 50.55a(b)(3) on the use of the 2004 Edition of the ASME OM Code for Mandatory Appendix I, paragraph 1-3410, with regards to 1ST of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices. Additionally, the NRC staff has not identified any additional related requirements in the 2004 Edition of the OM Code that need to be met in order to implement Mandatory Appendix I, paragraph 1-3410.
Therefore, use of the 2004 Edition of the ASME OM Code in lieu of the 2001 through 2003 Addenda for 1ST of Class 1 Main Steam Pressure Relief Valves With Auxiliary Actuating Devices per Mandatory Appendix I, paragraph 1-3410, is acceptable.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the licensee's request, NL-10-1021, to use the 2004 edition of the ASME OM Code, Mandatory Appendix 1, paragraph 1-3410, for testing the Class 1 Main Steam Pressure Relief Valves with Auxiliary Actuating Devices for the remainder of the fourth 10-year 1ST interval at Hatch Unit 1 and Unit 2 is acceptable. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(f)(4)(iv), consistent with the ASME OM Code's requirements.
Therefore, the NRC staff authorizes the request, NL-10-1021, for the remainder of the Hatch 1 and 2, fourth 10-year 1ST interval which commenced on January 1, 2006, and ends on December 31,2015.
Principal Contributor: John G. Billerbeck, NRRlDCI Date: March 31, 2011
M. Ajluni -2 If you have any questions, please contact the Project Manager, Patrick Boyle at 301-415-3936.
Sincerely, IRA!
Gloria Kulesa, Branch Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-1 RlF RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource RidsNrrDciCptb (AMcMurtray) RidsNrrLAMO'Brien Resource RidsRgn2MailCenter Resource RidsNrrPMHatchResource RidsNrrDirsltsbResource RidsAcrsAcnw_MailCTRResource NSanfilippo, EDO R-II JBillerbeck NRRIDCI ADAMS Accession No ML11084A004 "memo transmitted SE dated 03124/11 ML110871843 OFFICE NRRlLPL2-1/PM NRR/LPL2-1/LA NRR/CPTB/BC NRRlLPL2-1/BC NRRlLPL2-1/PM NAME PBoyle MOBrien AMcMurtray" GKulesa PBoyle DATE 03/30/11 03/30/11 03/24/11 03/31111 03/31/11 OFFICIAL RECORD COpy
