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Category:Letter
MONTHYEARPLA-8145, Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-81452024-10-21021 October 2024 Biennial 10 CFR 50.59 and 72.48 Summary Report and Changes to Regulatory Commitments - PLA-8145 ML24291A1562024-10-16016 October 2024 Missed Annual Inventory Required by 40 CFR 266, Subpart in PLE 0026645 PLA-8148, Registration for the Use of Spent Fuel Storage Casks 311, 308, and 3102024-10-15015 October 2024 Registration for the Use of Spent Fuel Storage Casks 311, 308, and 310 PLA-8141, Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-81412024-09-18018 September 2024 Response to Request for Additional Information Regarding Relief Request 1RR06, PLA-8141 PLA-8142, Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-81422024-09-18018 September 2024 Registration for the Use of Spent Fuel Storage Casks 306, 309, and 307 - PLA-8142 ML24260A2312024-09-17017 September 2024 Senior Reactor and Reactor Operator Initial License Examinations 05000387/LER-2024-002, B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor2024-09-16016 September 2024 B Diesel Generator Inoperable Due to Failed Excitation System Linear Reactor ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 ML24233A2192024-09-0303 September 2024 – Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code IR 05000387/20240052024-08-29029 August 2024 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2024005 and 05000388/2024005) 05000387/LER-2023-004-01, Manual Reactor Scram Due to Degraded Main Condenser Vacuum2024-08-26026 August 2024 Manual Reactor Scram Due to Degraded Main Condenser Vacuum 05000387/LER-2024-001-01, Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear2024-08-21021 August 2024 Main Steam Isolation Valve Leakage Due to Valve Body Seat Wear IR 05000387/20240022024-08-12012 August 2024 Integrated Inspection Report 05000387/2024002 and 05000388/2024002 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification PLA-8117, 23rd Refueling Outage Owners Activity Report (PLA-8117)2024-07-23023 July 2024 23rd Refueling Outage Owners Activity Report (PLA-8117) ML24197A0982024-07-15015 July 2024 Request for Information for a Biennial Problem Identification and Resolution Inspection; Inspection Report 05000387/2024010 and 05000388/2024010 ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 PLA-8126, Response to Request for Confirmation of Information Regarding Relief Request 1RR062024-05-29029 May 2024 Response to Request for Confirmation of Information Regarding Relief Request 1RR06 PLA-8122, Annual Radiological Environmental Operating Report (PLA-8122)2024-05-28028 May 2024 Annual Radiological Environmental Operating Report (PLA-8122) PLA-8123, Main Steam Isolation Valve Leakage2024-05-23023 May 2024 Main Steam Isolation Valve Leakage PLA-8115, Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115)2024-05-23023 May 2024 Relief Request IRR06 One Time Extension to the Fourth 10-Year Inservice Testing Program Interval (PLA-8115) IR 05000387/20240012024-05-13013 May 2024 Integrated Inspection Report 05000387/2024001 and 05000388/2024001 IR 05000387/20244042024-05-0707 May 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000387/2024404 and 05000388/2024404 ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-80942024-04-22022 April 2024 Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 PLA-8095, 2023 Annual Radiological Environmental Operating Report (PLA-8095)2024-04-22022 April 2024 2023 Annual Radiological Environmental Operating Report (PLA-8095) PLA-8101, Re 2023 Annual Report of Radiation Exposure2024-04-22022 April 2024 Re 2023 Annual Report of Radiation Exposure PLA-8102, Annual Environmental Operating Report (Nonradiological) PLA-81022024-04-11011 April 2024 Annual Environmental Operating Report (Nonradiological) PLA-8102 PLA-8113, Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113)2024-04-11011 April 2024 Response to Request for Additional Information Regarding Relief Request 4RR-11 (PLA-8113) PLA-8112, Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-81122024-04-0909 April 2024 Relief Request 4RR-11 Relief from End of Interval Boundary Leakage Test PLA-8112 PLA-8110, Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110)2024-04-0404 April 2024 Submittal of Unit 1 Cycle 24 Core Operating License Report (Pla 8110) PLA-8100, Property Insurance Program (PLA-8100)2024-04-0101 April 2024 Property Insurance Program (PLA-8100) ML24092A4022024-04-0101 April 2024 Annual Financial Report (PLA-8098) PLA-8109, Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109)2024-03-21021 March 2024 Supplement to Request for Exemption from Certain Requirements of 10 CR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance (PLA-8109) ML24067A2512024-03-19019 March 2024 Authorized Alternative to Requirements of the ASME Code PLA-8107, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance2024-03-19019 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 Resulting from Fuel Basket Design Control Compliance ML24044A2532024-03-14014 March 2024 Associated Independent Spent Fuel Storage Installation – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0077 (Security Notifications, Reports, and Recordkeeping & Suspicious Activity Reporting)) IR 05000387/20240112024-02-29029 February 2024 Commercial Grade Dedication Inspection Report 05000387/2024011 and 05000388/2024011 IR 05000387/20230062024-02-28028 February 2024 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2023006 and 05000388/2023006) ML24039A1882024-02-27027 February 2024 Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods ML24037A3072024-02-22022 February 2024 Summary of Regulatory Audit in Support of Relief Request 5RR-02 PLA-8099, Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099)2024-02-13013 February 2024 Proof of Financial Protection and Guarantee of Payment of Deferred Premiums (PLA-8099) IR 05000387/20230042024-02-0707 February 2024 Integrated Inspection Report 05000387/2023004 and 05000388/2023004 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval PLA-8077, Emergency Plan Revision 67 (PLA-8077)2023-12-27027 December 2023 Emergency Plan Revision 67 (PLA-8077) IR 05000387/20230102023-12-11011 December 2023 Fire Protection Team Inspection Report 05000387/2023010 and 05000388/2023010 PLA-8088, Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088)2023-12-0505 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks and Security Event Notifications Implementation (PLA-8088) PLA-8089, Submittal of Revision to Inservice Testing Program Plan2023-12-0505 December 2023 Submittal of Revision to Inservice Testing Program Plan PLA-8084, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22023-11-29029 November 2023 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 2024-09-06
[Table view] Category:Safety Evaluation
MONTHYEARML24233A2192024-09-0303 September 2024 – Authorized Alternative to Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code ML24127A2262024-05-29029 May 2024 Issuance of Amendment Nos. 288 and 272 Adoption of TSTF-563 ML24082A1372024-04-22022 April 2024 Issuance of Amendment Nos. 287 and 271 Adoption of TSTF-568, Revision 2 and Associated Technical Specification Changes ML24080A3952024-03-28028 March 2024 Relief Request - RR02 ML24067A2512024-03-19019 March 2024 Authorized Alternative to Requirements of the ASME Code ML24039A1882024-02-27027 February 2024 Issuance of Amendment Nos. 286 and 270 Changes to Technical Specifications for Control Rods ML23257A1222023-09-19019 September 2023 Authorization and Safety Evaluation for Alternative Request for Valve 251130 ML23207A1762023-08-0101 August 2023 Authorization and Safety Evaluation for Relief Request 4RR-10 ML23073A1072023-03-30030 March 2023 Enclosure 4 - Safety Evaluation Nonproprietary Susquehanna Steam Electric Station,Units 1,2 & Associated Independent Spent Fuel Storage Installation-Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L- ML23073A0822023-03-30030 March 2023 Enclosure 2 - Draft Conforming Amendments - Susquehanna Steam Electric Station, Units 1 & 2 & Associated Independent Spent Fuel Storage Installation- Order Approving Indirect Transfer of Licenses & Draft Conforming License Amendments EPID L ML23010A1082023-01-15015 January 2023 Issuance of Amendment No. 268 Change to Control Rod Technical Specifications ML22294A1502022-11-17017 November 2022 Issuance of Amendment Nos. 284 and 267 Relocating Technical Specification Unit Staff Qualification Requirements to Quality Assurance Program ML22256A0542022-10-28028 October 2022 Issuance of Amendment Nos. 283 and 266 Change to Reactor Steam Dome Pressure--Low Instrument Function Allowable Value in Technical Specifications ML22200A0622022-08-30030 August 2022 Issuance of Amendment Nos. 282 and 265 Regarding Risk-Informed Completion Times in Technical Specifications ML22146A2072022-07-15015 July 2022 Issuance of Amendment Nos. 281 and 264 Revise Technical Specifications to Adopt TSTF-564, Safety Limit MCPR - NON-PROPRIETARY - ML21229A1572021-11-0404 November 2021 Issuance of Amendment No. 263 Temporary Change to Unit 2 Technical Specification 3.8.7 to Allow Replacement of Unit 1 480 Volt Load Center Transformers ML21095A3042021-04-19019 April 2021 Relief Request 4RR-02 Regarding Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds ML20317A3142021-03-10010 March 2021 Issuance of Amendment Nos. 280 and 262 Revise Technical Specification 3.8.1, AC Sources-Operating, to Create a New Condition for an Inoperable Manual Synchronization Circuit ML20342A2372021-02-18018 February 2021 Issuance of Amendment Nos. 279 and 261 Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements ML20168B0042021-01-21021 January 2021 Issuance of Amendment Nos. 278 and 260 to Allow Application of Advanced Framatome Atrium 11 Fuel Methodologies (EPID L-2019-LLA-0153) (Redacted) ML20297A5642020-12-22022 December 2020 Issuance of Amendment Nos. 277 and 259 Revise Technical Specifications to Adopt TSTF-529, Revision 4, Clarify Use and Application Rules ML20199G7492020-10-0808 October 2020 Issuance of Amendment Nos. 276 and 258 Revise Technical Specification 5.5.2 to Modify the Design-Basis Loss-of-Coolant Accident Analysis ML20028E8842020-02-10010 February 2020 Correction to Amendment Nos. 275 and 257 Temporary Changes to Allow Replacement of the Emergency Service Water System Piping ML19248A8442020-01-17017 January 2020 Issuance of Amendment Nos. 275 and 257 Temporary Changes to Allow Replacement of Emergency Service Water System Piping ML19336D0642020-01-13013 January 2020 Issuance of Amendment Nos. 274 and 256 to Revise Shutdown Margin Definition to Address Advanced Fuel (TSTF-535, Revision 0) ML19155A2642019-07-16016 July 2019 Issuance of Amendment Nos. 273 and 255 Adoption of TSTF-439, Revision 2, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML19154A0602019-06-24024 June 2019 Issuance of Amendment Nos. 272 and 254 Technical Specifications to Adopt TSTF-501, Revision 1, Relocated Stored Fuel Oil and Lube Oil Volume Values to Licensee Control ML18302A3032019-01-0303 January 2019 SE Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order Ea-13-109 (CAC Nos. MF4364 and MF4365; EPID No. L-2014-JLD-0055 ML18284A4552018-11-0707 November 2018 Safety Evaluation Regarding Implementation of Mitigation Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML18222A2032018-09-26026 September 2018 Issuance of Amendment Nos. 271 and 253 Revising Technical Specifications to Adopt TSTF-542, Revision 2 (CAC Nos. MG0269 and MG0270; EPID L-2017-LLA-0306) ML17187A2972017-07-28028 July 2017 Susquehanna Steam Electric Station, Units 1 and 2 - Issuance of Amendments Revising Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF9154 and MF9155) ML17067A4442017-03-27027 March 2017 Issuance of Amendments Secondary Containment Access Openings ML16320A0802016-11-30030 November 2016 NON-PROPRIETARY - Safety Evaluation by NRR Related to Indirect Transfer of Renewed Operating Licenses from Talen Energy Corporation to Riverstone Holdings, LLC for the Susquehanna Steam Electric Station, Units 1 and 2 ML16005A2342016-05-20020 May 2016 Issuance of Amendments Adoption of TSTF-425 ML16069A1992016-05-10010 May 2016 Relief Requests for the Third 10-Year Inservice Inspection Interval (CAC Nos. MF6302 Through MF6307) ML16062A2162016-03-28028 March 2016 Issuance of Amendments Emergency Action Level Scheme Change ML15267A3812015-11-0202 November 2015 Issuance of Amendments Approval of Cyber Security Plan Milestone 8 ML15243A1402015-09-30030 September 2015 Issuance of Amendments Revisions to Technical Specification 3.4.10, Reactor Coolant System Pressure and Temperature (P/T) Limits ML15098A4782015-04-28028 April 2015 Relief Requests 4RR-01: Use of a Risk-Informed Inservice Inspection Alternative for the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF5097 and MF5098) ML15054A0582015-04-10010 April 2015 Letter Forwarding Order Approving Transfer of Licenses and Conforming Amendments Related to Susquehanna Steam Electric Station, Units 1 and 2 (TAC MF4426 and MF4427) ML14141A0732014-06-0909 June 2014 Relief Requests for the Fourth 10-Year Inservice Inspection Interval (TAC Nos. MF2705 Through MF2714) ML14122A1972014-05-22022 May 2014 Relief Requests for the Fourth 10-Year Inservice Testing Interval (TAC Nos. MF2905 Through MF2912 and MF2915) ML14111A0522014-05-14014 May 2014 Issuance of Amendments Regarding Change to Technical Specification Surveillance Requirement 3.5.1.12 ML14028A3952014-03-12012 March 2014 Request for Relief 3RR-20 from the Requirements of the American Society of Mechanical Engineers Section XI ML14036A2572014-02-26026 February 2014 Issuance of Amendment Change to Allow Only One Manual Trip System to Be Operable for the Residual Heat Removal Shutdown Cooling System in Modes 4 and 5 ML12160A1942012-06-11011 June 2012 Review of 60-Day Response to Request for Information Regarding Recommendation 9.3, of the Near-Term Task Force Related to the Fukushima Daiichi Nuclear Power Plant Accident ML1211701292012-04-27027 April 2012 Correction to Issuance of Amendment ML12096A1582012-04-19019 April 2012 Issuance of Amendment Temporary Change to Unit 2 Technical Specifications 3.8.7 and 3.7.1 to Allow Implementation of Multiple Spurious Operations Modifications on SSES Unit 1, 4160 V Buses ML12062A1332012-03-0606 March 2012 ME7902 & ME7903-Approval of RR-2012-001 Use of Later Edition of the ASME OM Code for Check Valve Condition Monitoring Program ML12046A0462012-02-23023 February 2012 Relief Request No. 3RR-18, Regarding Relief from the Requirements of the ASME Code for Successive Inspections 2024-09-03
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Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 March 6, 2012 Mr. Timothy S. Rausch Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467 SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 RE: RELIEF REQUEST NO. 2012-001, REVISION 1, THE USE OF SUBSEQUENT ASME OM CODE EDITION AND ADDENDA APPLICABLE TO SECTION ISTC-S222 AND APPENDIX II CHECK VALVE CONDITION MONITORING PROGRAM (TAC NOS. ME7902 AND ME7903)
Dear Mr. Rausch:
By letter dated January 31, 2012, as supplemented by letter dated February 13, 2012, PPL Susquehanna LLC, Inc. (PPL or the licensee) submitted a request to the U. S. Nuclear Regulatory Commission (NRC) for the use of subsequent American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code) requirements at Susquehanna Steam Electric Station, Units 1 and 2. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part SO, Subsection SO.SSa(f)(4)(iv), the licensee requested to apply the requirements of Subsection ISTA (in its entirety), paragraph ISTC-S222, and Mandatory Appendix II (in its entirety) of the 2004 Edition of ASME OM Code through 2006 Addenda for the check valves in the Check Valve Condition Monitoring Program for the remainder of the Third 10-Year Interval for the Inservice Testing Program which began on June 1,2004, and is scheduled to end on May 31,2014, at the Susquehanna Steam Electric Station (SSES), Units 1 and 2, subject to the limitations and modifications listed in 10 CFR SO.SSa(b).
The NRC staff has reviewed the subject request and concludes, as set forth in the enclosed safety evaluation, that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR SO.SSa(f)(4)(iv), and is in compliance with the ASME OM Code requirements.
These requirements will be used for check valves at SSES Units 1 and 2, in lieu of the corresponding requirements in the 1998 Edition of ASME OM Code through 2000 Addenda. Therefore, the NRC staff authorizes this request for the remainder of the Third 10-Year Interval for the Inservice Testing Program which began on June 1,2004, and is scheduled to end on May 31, 2014 at the SSES, Units 1 and 2, subject to the limitations and modifications listed in 10 CFR SO.SSa(b).
All other ASME OM Code requirements for which relief was not specifically requested and approved remain applicable.
T. S. Rausch Please contact me at (301) 415-1771, or the Project Manager, Bhalchandra K. Vaidya at (301) 415-3308, if you have any questions.
Sincerely, Chief Plant licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and Safety cc w/encl: Distribution via UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555*0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST NO. 2012*001, REVISION 1 REGARDING USE OF LATER EDITION AND ADDENDA FOR INSERVICE TESTING PROGRAM FOR CHECK VALVES PPLSUSQUEHANNA,LLC ALLEGHENY ELECTRIC COOPERATIVE, INC. SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50*387 AND 50-388
1.0 INTRODUCTION
By letter dated January 31,2012 (ML 12031A238) as supplemented later by letter dated February 13,2012 (ML 120440669), PPL Susquehanna, LLC, the licensee, requested 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). This request is applicable to the Inservice Testing (1ST) Program at Susquehanna Steam Electric Station (SSES) Units 1 and 2. The licensee requested to apply the requirements of Subsection 1ST A (in its entirety), paragraph ISTC-5222, and Mandatory Appendix II (in its entirety) of the 2004 Edition of ASME OM Code through 2006 Addenda to selected check valves in the SSES 1ST Program in lieu of the corresponding requirements of the 1998 Edition of ASME OM Code through 2000 Addenda. Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Subsection 50.55a(f)(4)(iv), the licensee requested to apply the requirements of Subsection ISTA (in its entirety), paragraph ISTC-5222, and Mandatory Appendix II (in its entirety) of the 2004 Edition of ASME OM Code through 2006 Addenda for the check valves in the Check Valve Condition Monitoring Program for the remainder of the Third 10*Year Interval for the Inservice Testing Program which began on June 1, 2004, and is scheduled to end on May 31, 2014, at the SSES, Units 1 and 2, subject to the limitations and modifications listed in 10 CFR 50.55a(b).
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(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 Enclosure
-2 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 SO.SSa(b), subject to NRC approval.
Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met. Regulatory Issue Summary (RIS) 2004-12, "Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI," provides guidance for use of later Code editions.
3.0 TECHNICAL
EVALUATION
3.1 Licensee's
Request 2012-001 The SSES Units 1 and 2 third 10-year 1ST interval began on June 1, 2004. The applicable Code of Record for SSES Units 1 and 2 is the ASME OM Code, 1998 Edition through 2000 Addenda. This Code requires, in part, that valves in the scope of the 1ST Program as specified in 1100(a) shall be tested in accordance with the applicable requirements of Subsection ISTC. For check valves, as an alternative to the testing requirements of ISTC, ISTC-S222 allows the owner to implement a check valve condition monitoring program in accordance with the requirements of Mandatory Appendix II. The requirements of Mandatory Appendix II may be applied to any valve or group of valves up to and including the entire 1ST Program check valve population.
Any valves not included in the condition monitoring program are required to be tested in accordance with the applicable Subsection ISTC requirements.
In addition, the following requirements must be complied with by owners choosing to use Mandatory Appendix II of the 1998 Edition of OM Code: (1) Paragraph 10 CFR SO.SSa(b)(3)(iv)(A):
Valve opening and closing functions must be demonstrated when flow testing or examination methods (nonintrusive, or disassembly and inspection) are used. (2) Paragraph 10 CFR SO.SSa(b)(3)(iv)(B):
The initial interval for tests and associated examinations may not exceed two fuel cycles or 3 years, whichever is longer; any extension of this interval may not exceed one fuel cycle per extension with the maximum interval not to exceed 10 years; trending and evaluation of existing data must be used to reduce or extend the time interval between tests. (3) Paragraph 10 CFR SO.SSa(b){3){iv)(D):
The applicable provisions of subsection ISTC must be implemented if the Appendix II condition monitoring program is discontinued.
The licensee requested approval to use the corresponding portions of the 2004 Edition of the ASME OM Code through 2006 Addenda related to establishment of a check valve condition monitoring program. These portions include: Subsection ISTA which specifies general requirements for the 1ST Program including the scope of components to be tested;
-3 ISTC-S222 which allows the owner to implement at his discretion a check valve condition monitoring program in accordance with the requirements of Mandatory Appendix II; and Mandatory Appendix II which specifies the requirements for implementation of a check valve condition monitoring program. Unlike the version of Mandatory Appendix II contained in the 1998 Edition of OM Code, the version contained in the 2004 Edition of OM Code has no further requirements specified by 10 CFR SO.SSa(b)(3)(iv), as all of the previously specified requirements were subsequently incorporated into the later Code. The licensee proposes to apply the requirements noted above, to selected check valves in the scope of the SSES 1ST Program. A list of check valves selected for the condition monitoring program will be maintained in the respective Unit 1 or Unit 21ST Program Plans. Federal Register Notice dated June 21, 2011 (76 FR 36232), incorporated the 2004 Edition of ASME OM Code including Addenda through 2006, by reference in 10 CFR SO.SSa(b), subject to the limitations and modifications imposed by 10 CFR SO.SSa(b)(3).
Regulations in 10 CFR SO.SSa(b)(3) do not impose any additional limitations or modifications on the use of Mandatory Appendix II and the related requirements of Subsection ISTC. Note: Regulation in paragraph 10 CFR SO.SSa(b)(3)(i) does impose a limitation related to quality assurance as specified by OM Code Subsection 1ST A. However, this limitation is applicable to all licensees and all OM Code editions and is not specifically related to the implementation of a check valve condition monitoring program. 3.2 NRC Staff Evaluation The licensee has requested approval to apply the requirements of Subsection 1ST A (in its entirety), paragraph ISTC-S222, and Mandatory Appendix II (in its entirety) of the 2004 Edition of ASME OM Code through 2006 Addenda to selected check valves in the SSES 1ST Program. These requirements will be used for various check valves at SSES, in lieu of the corresponding requirements of the 1998 Edition of ASME OM Code through 2000 Addenda. The NRC staff has determined that there are no further limitations or modifications imposed by 10 CFR SO.SSa(b)(3) on the use of these portions of the 2004 Edition of the ASME OM Code through 2006 Addenda. Additionally, the NRC staff has not identified any additional related requirements in the 2004 Edition of the OM Code through 2006 Addenda that need to be met in order to implement the requested portions.
Therefore, use of Subsection ISTA (in its entirety), paragraph ISTC-S222, and Mandatory Appendix II (in its entirety) from the 2004 Edition of the ASME OM Code through 2006 Addenda for selected check valves at SSES Units 1 and 2, is acceptable.
4.0 CONCLUSION
As set forth above, the NRC staff determines that the licensee's request to apply the requirements of Subsection ISTA (in its entirety), paragraph ISTC-S222, and Mandatory Appendix II (in its entirety), using the 2004 Edition of ASME OM Code through 2006 Addenda for various check valves in the SSES 1ST Program, for the remainder of the third 10-year 1ST interval, is acceptable.
These requirements will be used for check valves at SSES Units 1 and 2, in lieu of the corresponding requirements in the 1998 Edition of ASME OM Code through 2000 Addenda. Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR SO.SSa(f)(4)(iv), and is in compliance with the ASME OM Code requirements.
All other ASME OM Code requirements for which relief was not specifically requested and approved remain applicable.
Therefore, the NRC staff authorizes this request for the remainder of the Third 10-Year Interval for the 1ST Program which began on June 1,2004, and is scheduled to end on May 31,2014, at the SSES, Units 1 and 2, subject to the limitations and modifications listed in 10 CFR SO.SSa(b).
Principal Contributor:
J. Billerbeck, NRR/EPTB Date: March 6, 2012 T. S. Rausch Please contact me at (301) 415-1771, or the Project Manager, Bhalchandra K. Vaidya at (301) 415-3308, if you have any questions.
Sincerely, lraJ George A. Wilson, Chief Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and Safety cc w/encl: Distribution via DISTRIBUTION:
PUBLIC LPL 1-1 R/F RidsNRRDorILPI1-1 RidsN RRPMSusquehanna RidsNrrLASLittle RidsOGCRp RidsNrrDeEptb RidsNrrDorlDpr RidsNrrDirsltsb RidsAcrsAcnw&m MailCenter RidsRg1MailCenter Lydia Chang, EDO Region 1 Contact RidsOgcRp J. Billerbeck, NRR/EPTB ADAMS Accession No.: ML 12062A133
(*) No substantial change from the SE Input Memo LPL 1-1/PM NAME "1 DATE 03/05/12 LPL 1-1/LA SLittie 03/05/12 NRR/EPTB/BC
(*) AMcMurtray 03/01/12 LPL 1-1/BC GWilson 03/06/12 OFFICIAL RECORD COPY