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Category:Letter
MONTHYEARIR 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-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 ML23345A0682023-11-28028 November 2023 Technical Specification Bases, Manual PLA-8091, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091)2023-11-0808 November 2023 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inseervice Inspection Interval (PLA-8091) IR 05000387/20230032023-11-0303 November 2023 Integrated Inspection Report 05000387/2023003 and 05000388/2023003 PLA-8082, Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2023-11-0202 November 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Application to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML23291A1132023-10-12012 October 2023 Submittal of Revision 71 to Updated Final Safety Analysis Report and Revision 25 to Fire Protection Review Report ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23277A0412023-10-0505 October 2023 Notification of Commercial Grade Dedication Inspection (05000387/2024011 and 05000388/2024011) and Request for Information IR 05000387/20233012023-09-20020 September 2023 Initial Operator Licensing Examination Report 05000387/2023301 and 05000388/2023301 ML23254A0242023-09-0606 September 2023 Paragon Energy Solutions LLC, Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) IR 05000387/20230052023-08-31031 August 2023 Updated Inspection Plan for Susquehanna Steam Electric Station, Units 1 and 2 (Report 05000387/2023005 and 05000388/2023005) ML23228A1952023-08-21021 August 2023 Summary of August 10, 2023, Public Observation Meeting Re. Proposed Alternative PLA-8080, Proposed Relief for Valve 251130 (PLA-8080)2023-08-14014 August 2023 Proposed Relief for Valve 251130 (PLA-8080) PLA-8074, Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2023-08-0303 August 2023 Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval IR 05000387/20230022023-08-0101 August 2023 Integrated Inspection Report 05000387/2023002 and 05000388/2023002 ML23195A1852023-07-27027 July 2023 Correction to Technical Specifications Page 3.3-73 in Amendment No. 265 PLA-8076, Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076)2023-07-20020 July 2023 Unit 2 - 21st Refueling Outage Owner'S Activity Report (PLA-8076) ML23201A0152023-07-20020 July 2023 Operator Licensing Examination Approval ML23200A1012023-07-19019 July 2023 Notification of Conduct of a Fire Protection Team Inspection ML23193A0062023-07-12012 July 2023 Requalification Program Inspection PLA-8078, Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-80782023-07-0505 July 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report, Revision 1, PLA-8078 ML23163A1012023-06-12012 June 2023 10 CFR 50.46 Annual Report (Pla 8065) PLA-8054, Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence2023-06-0808 June 2023 Proposed Amendment to Licenses NPF-14 and NPF-22: Remove Control Rod Operability Separation Criteria and Replace Reference to Banked Position Withdrawal Sequence with the Analyzed Rod Position Sequence IR 05000387/20234012023-06-0707 June 2023 Security Baseline Inspection Report 05000387/2023401 and 05000388/2023401 PLA-8073, Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval2023-06-0101 June 2023 Proposed Relief Request for the Fifth 10-Year Inservice Inspection Interval PLA-8064, Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064)2023-05-17017 May 2023 Response to NRC Regulatory Issue Summary 2023-01 (PLA-8064) ML23132A3212023-05-17017 May 2023 Associated Independent Spent Fuel Storage Installation - Issuance of Amendment Nos. 285 and 269 Related to Order Approving Transfer of Licenses PLA-8067, Notification of Completion of Emergence from Bankruptcy (PLA-8067)2023-05-17017 May 2023 Notification of Completion of Emergence from Bankruptcy (PLA-8067) IR 05000387/20230012023-05-12012 May 2023 Integrated Inspection Report 05000387/2023001 and 05000388/2023001 PLA-8066, Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-80662023-05-0808 May 2023 Notification of Planned Closing Date and Information Identified in March 30, 2023 Order, PLA-8066 PLA-8053, Radiation Exposure Information and Reporting System2023-04-27027 April 2023 Radiation Exposure Information and Reporting System PLA-8058, Annual Radiological Environmental Operating Report (PLA-8058)2023-04-26026 April 2023 Annual Radiological Environmental Operating Report (PLA-8058) PLA-8041, Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041)2023-04-25025 April 2023 Radioactive Effluent Release Report and Offsite Dose Calculation Manual (PLA-8041) PLA-8047, 2022 Annual Environmental Operating Report (Nonradiological), PLA-80472023-04-19019 April 2023 2022 Annual Environmental Operating Report (Nonradiological), PLA-8047 PLA-8062, Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-80622023-04-11011 April 2023 Supplement to Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 252F007B, PLA-8062 PLA-8061, Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-80612023-04-10010 April 2023 Relief Request 4RR-10 Relief from Code Seal Weld Requirement for Valve 25F007B, PLA-8061 ML23090A2302023-03-31031 March 2023 NRC Decommissioning Funding Status Report PLA-8049 PLA-8060, Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060)2023-03-30030 March 2023 Submittal of Unit 2 Cycle 22 Core Operating Limits Report (PLA-8060) ML23095A0572023-03-29029 March 2023 NRC Decommissioning Funding Status Report December 31, 2022 PLA-8057, Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-80572023-03-15015 March 2023 Application for Order Approving Indirect Transfer of Control of Licenses and Approving Conforming License Amendments- Supplemental Information, PLA-8057 ML23065A1962023-03-0202 March 2023 EN 56387 Paragon - Part 21 Report Re Defect Identified in Automatic Transfer Switch Pn: NLI-ATS480A400X1 IR 05000387/20220062023-03-0101 March 2023 Annual Assessment Letter for Susquehanna Steam Electric Station, Units 1 and 2 (Reports 05000387/2022006 and 05000388/2022006) PLA-8052, (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums2023-02-13013 February 2023 (Sses), Proof of Financial Protection and Guarantee of Payment of Deferred Premiums IR 05000387/20220042023-02-0808 February 2023 Integrated Inspection Report 05000387/2022004 and 05000388/2022004 ML23010A0882023-01-15015 January 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Control Rod Technical Specifications 2024-02-07
[Table view] Category:Safety Evaluation
MONTHYEARML23257A1222023-09-19019 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 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 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- 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 ML11292A1372011-11-17017 November 2011 ME5050 & ME5051-Issuance of Amendments to Renewed FOLs Changes to TS SR 3.4.3.1, Safety Relief Valve Tolerances from -3% to -5% ML11221A2712011-09-0808 September 2011 License Amendment, Issuance of Amendment Adoption of TSTF-514, Revision 3 ML11152A0092011-07-21021 July 2011 Issuance of Amendment Approval of the PPL Susquehanna, LLC Cyber Security Plan ML1035600052011-01-0404 January 2011 Approval of Relief Request RR-02, Revision 1, to Allow 6 Month Extension for SRV IST ML1015204312010-06-16016 June 2010 Request for Alternative No. RR-07 Main Steam Safety Relief Valve Test Interval Extension ML0935201522010-01-0707 January 2010 Relief Requests RR-07 and RR-08 from the Requirements of the OM Code Inservice Testing of Safety Relief Valves 2023-09-19
[Table view] |
Text
Mr. Timothy S. Rausch UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 March 12, 2014 Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603-0467
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2-REQUEST FOR RELIEF 3RR-20 FROM THE REQUIREMENTS OF THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS, SECTION XI (TAC NO. MF1756)
Dear Mr. Rausch:
By letter dated May 6, 2013, as supplemented by letter dated June 6, 2013, PPL Susquehanna, LLC (the licensee), requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI for Susquehanna Steam Electric Station (SSES), Unit 2. Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(a)(3)(ii), the licensee requested that the U.S. Nuclear Regulatory Commission (NRC) authorize an alternative to the ASME Code requirements to perform a visual (VT-1) examination of 100 percent of the pump flange surface of the SSES, Unit 2 'A' Reactor Recirculating Pump (RRP) during the third 1 0-year inspection interval, on the basis that performing the required examination would result in hardship or unusual difficulty without a compensating increase of the level of quality and safety. The NRC staff determined that complying with the ASME Code requirements for 100 percent visual (VT-1) examination coverage of the 'A' RRP flange surface would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes that the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(a)(3)(ii) and is in compliance with the requirements of the ASME Code,Section XI. Therefore, the NRC staff authorizes the proposed alternative Relief Request 3RR-20 for the third 1 0-year inspection interval at SSES, Unit 2. All other ASME Code,Section XI requirements for which relief has not been specifically requested and approved remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
T. Rausch If you have any questions, please contact the SSES Project Manager, Jeffrey Whited at (301) 415-4090 or via e-mail at Jeffrey.Whited@
nrc.gov Docket No. 50-388
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ Sincerely, ena K. Khanna, Chief ant Licensing Branch 1-2 ivision of Operating Reactor Licensing Office of Nuclear Reactor Regulation UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST 3RR-20 REGARDING VISUAL EXAMINATION OF FLANGE SURFACES PPL SUSQUEHANNA, LLC SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 DOCKET NUMBER 50-388
1.0 INTRODUCTION
By letter dated May 6, 2013, 1 as supplemented by letter dated June 6, 2013, 2 PPL Susquehanna, LLC (the licensee), requested relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (Code),Section XI for Susquehanna Steam Electric Station, Unit 2 (SSES). Specifically, pursuant to Title 10 of the Code of Federal Regulations (1 0 CFR) 50.55a(a)(3)(ii), the licensee requested that the U.S. Nuclear Regulatory Commission (NRC) authorize an alternative to the requirements of the ASME Code to perform a visual (VT -1) examination of 100 percent of the pump flange surface of the SSES, Unit 2 'A' Reactor Recirculating Pump (RAP) during the third 1 0-year inspection interval, on the basis that performing the required examination would result in hardship or unusual difficulty without a compensating increase of the level of quality and safety.
2.0 REGULATORY EVALUATION
The regulations in 10 CFR 50.55a(g) specify, in part, that inservice inspection (lSI) of nuclear power plant components shall be performed in accordance with the requirements of the ASME Code. Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1, 2, and 3 components (including supports) must meet the requirements, except the design and access provisions and the pre-service examination requirements, set forth in the ASME Code,Section XI, "Rules for lnservice Inspection of Nuclear Power Plant Components," to the extent practical within the limitations of design, geometry, and materials of construction of the components.
The regulations require that inservice examination of components and system pressure tests conducted during the first 1 0-year interval, and subsequent intervals, comply with the requirements of the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b), 12 months prior to the start of the 120-month interval, subject to the limitations and modifications 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML13127A199 2 ADAMS Accession No. ML 13157A170 Enclosure listed therein. The applicable Code of record for the third lSI interval for SSES, Unit 2 is the ASME Code,Section XI, 1998 Edition thru the 2000 Addenda. The SSES, Unit 2 third 1 0-year inspection interval began June 1, 2004, and is scheduled to end May 31, 2014. As discussed in 10 CFR 50.55a(g)(5)(iii), if the licensee has determined that conformance with certain code requirements is impractical for its facility, the licensee shall notify the Commission and submit, as specified in 50.4, information to support the determinations.
As discussed in 10 CFR 50.55a(g)(6)(i), the Commission may grant such relief and may impose such alternative requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest, given the consideration of the burden upon the licensee.
As discussed in 10 CFR 50.55a(a)(3), alternatives to the requirements of paragraph (g) may be used, when authorized by the NRC, if (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The NRC staff concludes that there is regulatory basis for the licensee to request the use of an alternative and the NRC staff to authorize this alternative, pursuant to the technical evaluation that follows. The information provided by the licensee in support of the request has been evaluated by the NRC staff and the bases for disposition are documented below. 3.0 TECHNICAL EVALUATION
3.1 Licensee's
Request for Alternative 3.1.1 ASME Code Components Affected Unit 2 'A' RRP Flange Examination Category B-G-1, Pressure Retaining Bolting Item No. C6.190 Pump Flange Surface 3.1.2 ASME Code Requirement Affected ASME Code,Section XI, Table IWB-2500-1, Examination Category B-G-1, Item No. C6.190, requires a visual (VT -1) examination of 1 00 percent of a one-inch annular surface of the pump flange surrounding each pump stud when the connection is disassembled.
3.1.3 Proposed
Alternative In accordance with 10 CFR 50.55a(g)(3)(ii), the licensee requested the limited visual {VT -1) examination coverage (i.e., 98 percent) of the 'A' RRP flange surface be accepted for the third 1 0-year inspection interval. 3.1.4 Basis for Request The SSES, Unit 2 'A' RRP was disassembled during the Unit 2 16 1 h Refueling Outage which occurred in the spring of 2013. During the time the pump was disassembled, a visual (VT-3) examination of the pump bowl was performed.
However, the required visual (VT -1) examination of the flange surface was not performed.
A visual {VT -1) examination of the reassembled pump flange surface was performed subsequent to the discovery that the examination had not been performed when the pump was disassembled.
However, examination coverage of this examination was limited to approximately 98 percent of the required surfaces due to interference from pump internals.
The licensee requested this alternative based on their determination that achieving the 100 percent visual (VT -1) examination coverage required hardship or unusual difficulty once the pump had been reassembled, and would not provide a compensating increase in the level of quality and safety. 3.2 NRC Staff Evaluation The ASME Code requires visual {VT -1) examination of Category B-G-1, Item Number B6.180 flange surface when the connection is disassembled to detect discontinuities and imperfections on the surface including such conditions as cracks, wear, corrosion or erosion. The licensee stated in its submittal dated May 6, 2013, that when the pump was disassembled a visual (VT -3) examination of the pump bowl was performed along with visual examinations of the pump surfaces by pump vendor personnel and SSES Quality Control personnel prior to pump reassembly.
These exams found the pump acceptable for continued service with no evidence of degradation noted. The visual (VT-1) examination that was performed after the pump was reassembled covered approximately 98 percent of the required surfaces and also was found acceptable.
In the supplemental letter dated June 6, 2013, the licensee responded to the NRC staff's request for additional information about operational experience with leakage from the RRP flange joint, stating that no evidence of damage from leakage has been found at the RRP flange. This submittal also stated that a visual {VT -2) examination was performed on the 'A' RRP flange joint on May 21, 2013, and no leakage was identified.
The licensee's submittal dated June 6, 2013, also provided a sketch which showed the surfaces that were not visual {VT -1) examined due to interferences from pump internal structures.
This area was identified as a small area near the inner diameter of the flange surface, 0.75 inches away from the outer diameter of the pump studs. Based on the area that was examined, the NRC staff concludes that the examination that was performed interrogated the higher stressed areas of the required examination surface, which is the area immediately adjacent to the studs. This is the area where one would expect to find cracking, if present, and any wear associated with the removal/replacement of the studs. Based on the operational experience discussed above and the satisfactory VT -2 performed on May 21, 2013, the NRC staff concludes that damage due to corrosion or erosion is also unlikely. Therefore, based on the visual (VT-1) examination that was performed covering the highly stressed regions of the flange, the operational experience, satisfactory VT-2 and the added assurance of the other visual exams that were performed when the pump was disassembled, the NRC staff concludes the proposed alternative provides reasonable assurance of structural integrity and leak tightness of the 'A' RRP flange joint. The submittal dated May 6, 2013, stated that in order to achieve the 100 percent visual examination coverage of the pump flange surface, the pump would need to be disassembled.
The disassembly of the pump was expected to require an additional 4500 man-hours and expected additional radiation dose of 12.4 person-rem.
The NRC staff concludes the additional radiation dose and the personnel safety challenges associated with the disassembly and reassembly of the 'A' RRP represent significant hardship.
Based on the above evaluation, the NRC staff concludes that the visual (VT-1) examination of 98 percent of the 'A' RRP flange joint provides reasonable assurance of the leak tightness and structural integrity of the items, and that compliance with the ASME Code-specified requirements of 100 percent visual examination coverage would result in hardship without a compensating increase in the level of quality and safety.
4.0 CONCLUSION
As set forth above, the NRC staff determined that complying with the ASME Code requirement for 100 percent visual (VT-1) examination coverage of the 'A' RRP flange surface would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Accordingly, the NRC staff concludes the licensee has adequately addressed all the regulatory requirements set forth in 10 CFR 50.55a(a)(3), and is in compliance with the requirements of the ASME Code. Therefore, the NRC staff authorizes the proposed alternative Relief Request 3RR-20 for the third 1 0-year inspection interval at SSES, Unit 2. All other ASME Code,Section XI requirements for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear lnservice Inspector.
Principal Contributor:
Keith M. Hoffman Date: March 12, 2014 T. Rausch If you have any questions, please contact the SSES Project Manager Jeffrey Whited at (301) 415-4090 or via e-mail at Jeffrey.Whited@nrc.gov Docket No. 50-388
Enclosure:
Safety Evaluation Sincerely, Ira/ (JLam for) Meena K. Khanna, Chief Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPLI-2 RtF RidsNrrDeEpnb Resource RidsNrrDoriDpr Resource KHoffman, NRR RidsNrrLAABaxter Resource RidsAcrsAcnw_MaiiCTR Resource RidsNrrPMSusquehanna Resource RidsRgn1 MaiiCenter Resource RidsNrrDoriLpll-2 Resource EQuinones, OEDO, Region I ADAMS Accession No.* ML 14028A395
- Concurred via e-mail OFFICE NRR/LPLI-2/PM NRR/LPLI-2/LAit NRR/LPLI-2/LA NRR/EPNB/BC NAME JWhited KBeckford ABaxter* TLupold* DATE 03/12/2014 2/27/2014 03/07/2014 1/24/2014 OFFICIAL RECORD COPY NRR/LPLI-2/BC MKhanna (JLamb for) 03/12/2014