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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
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I I I Jon A. Franke Site Vice President PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.2904 Fax 570.542.1504 jfranke@pplweb.com
\ \ I I I \***/ ,' ****** # ... * * *" KAY 0 62013 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION PROPOSED RELIEF REQUEST NO. 3RR-20 TO THE THIRD 10-YEAR INSERVICE INSPECTION PROGRAM FOR SUSQUEHANNA SES UNIT 2 PLA-7014 Docket No. 50-388 The purpose of this letter is to request relief pursuant to the requirements of 10 CFR 50.55a(a)(3)(ii) from the provisions of the ASME Section XI, 1998 Edition, 2000 Addenda, Code Category B-G-1, Item B6.190, Examination ofPump Flange surfaces when disassembled.
In accordance with the ASME Code, a one-inch annular surface surrounding each stud on the pump flange surface must be visually examined (VT -1) when the pump is disassembled.
PPL Susquehanna, LLC (PPL) hereby requests relief for Susquehanna Steam Electric Station (SSES) Unit 2, to deviate from the requirement to perform a 1 00% visual examination of the 'A' Reactor Recirculation Pump Flange surface. During the current SSES Unit 2 16th Refueling and Inspection Outage, the 'A' Reactor Recirculation pump was disassembled for a pump motor replacement.
As a result of the missed opportunity to perform a visual examination (VT -1) of the pump flange when it was disassembled, a 1 00% visual examination of the required pump flange surface could not be performed.
As discussed during the May 2, 2013 conference call between PPL and the Nuclear Regulatory Commission (NRC), the ability to perform the VT -1 examination was no longer a viable option because the 'A' Reactor Recirculation pump had been reassembled.
Following the conference call, discussions with the SSES Engineering staff revealed that there was an opportunity to perform a partial examination of the flange surface. A qualified visual (VT -1) inspector was dispatched and the flange surface was inspected. No discontinuities or imperfections were identified.
Because the pump had been reassembled, examination coverage of the flange surface was limited to approximately 98% of the required surface due to interference from pump internals.
Since this inspect i on was not a 100% visual examination of the pump flange surface, PPL will list it as a limited examination. ' TM Document Control Desk PLA-7014 PPL requests that this relief request be approved by May 14, 2013 in order to support the SSES Unit 2 16th Refuel Outage startup. Please contact Mr. John Tripoli, Manager-Nuclear Regulatory Affairs at ( 570) 542-3100 if there are any questions concerning this letter. This letter contains no regulatory commitments.
Sincerely, Franke Attachment 1: PPL Susquehanna, LLC Third 10-Year Interval Request for Relief No. 3RR20 Attachment 2: Photos of the 'A' Recirculation Pump Flange Stud Area Attachment 3: Photo of the 'A' Recirculation Pump Sectional Drawing Copy: NRC Regional Administrator
-Region I Mr. P. W. Finney, NRC Sr. Resident Inspector Mr. J. A. Whited, NRC Project Manager Mr. L. J. Winker, PA DEP/BRP Attachment 1 to PLA-7014 PPL Susquehanna, LLC Third 10-Year Interval Request for Relief No. 3RR20 Attachment to PLA-7014 Page 1 of2 PPL SUSQUEHANNA, LLC SUSQUEHANNA SES, UNIT 2 THIRD 10-YEARINTERVAL REQUEST FOR RELIEF NO. 3RR20 SYSTEM/COMPONENT (S) FOR WHICH RELIEF IS REQUESTED The Unit 2 'A' Reactor Recirculation Pump Flange CODE REQUIREMENTS The 1998 Edition thru the 2000 Addenda of ASME Section XI, Table IWB-2500-1, Category B-G-1, Item B6 .190, requires a visual (VT -1) examination of a one-inch annular surface of the pump flange surrounding each stud when the connection is disassembled.
PPL Susquehanna, LLC (PPL) Susquehanna Steam Electric Station (SSES) Unit 2 is in the third period of the third inspection interval.
This is the last Unit 2 outage in the third ten-year inspection interval.
RELIEF REQUESTED Relief is requested in accordance with 10 CFR 50.55a(a)(3)(ii) from the provisions of Table IWB-2500-1, Category B-G-1, Item B6.190 Pump Flange Surface Examinations.
BASIS FOR RELIEF Table IWB-2500-1, Examination Category B-G-1, Item B6.190 requires a VT-1 visual examination of a one inch annular surface of the pump flange surface surrounding each stud when the pump is disassembled.
The SSES Unit 2 'A' Reactor Recirculation pump was disassembled during the Unit 2 16th Refuel and Inspection Outage (U2-16RIO).
During the time the pump was disassembled, a VT-3 of the pump bowl was performed.
However, the required VT -1 examination (examination for discontinuities) of the flange surface was not performed.
This omission was not recognized until the pump had been reassembled.
Originally, PPL reported that access to this area of the pump was not available.
After discussions with the SSES engineering staff, a qualified visual inspector was dispatched, and a VT -1 examination was performed on the pump flange surface. Since the pump was reassembled prior to this examination being performed, interferences from the pump internals limited the examination of the flange to approximately 98%. To obtain a 100% visual examination of the pump flange surface, the pump would have to be disassembled.
PPL estimates that disassembly of the pump would require an additional4500 man-hours of time with an expected dose of 12.4 person-rem.
The flange surface is acceptable for continued service based on upon the satisfactory results of a Attachment to PLA-7014 Page 2 of2 surface inspection that was performed by the pump vendor and SSES Quality Control personnel prior to pump reassembly.
No evidence of degradation was noted. Although the examinations were not VT -1 qualified, and not credited for ASME credit, it adds additional assurance that the flange surface (including the 2% of the flange surface that was not accessible) is acceptable for continued service. PPL will also perform at VT -2 examination on the pump prior to startup of Unit 2. ALTERNATIVE EXAMINATIONS None IMPLEMENTATION SCHEDULE PPL requests that this relief request be approved by May 14, 2013 in order to support the SSES Unit 2 16th Refuel Outage startup.
Attachment 2 to PLA-7014 Photos of the 'A' Recirculation Pump Flange Stud Area
Attachment 3 to PLA-7014 Photo of the 'A' Recirculation Pump Sectional Drawing Unit 2 'A' Recirculation Pump Sectional Drawing-Top of the Bottom Flange Surface