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Category:Letter
MONTHYEARIR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter IR 05000400/20243012023-05-15015 May 2023 Notification of Licensed Operator Initial Examination 05000400/2024301 IR 05000400/20230012023-05-10010 May 2023 Integrated Inspection Report 05000400 2023001 IR 05000400/20234042023-05-0404 May 2023 Cyber Security Inspection Report 05000400/2023404 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23118A1392023-04-28028 April 2023 Submittal of Updated Final Safety Analysis Report (Amendment 65), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes IR 05000400/20234032023-04-0505 April 2023 Security Baseline Inspection Report 05000400/2023403 IR 05000400/20230102023-03-15015 March 2023 Comprehensive Engineering Team Inspection (CETI) Inspection Report 05000400/2023010 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000400/20220062023-03-0101 March 2023 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2022006 ML23033A5272023-02-0808 February 2023 Correction of Typographical Errors Incurred During Issuance of License Amendment No. 196 IR 05000400/20220042023-02-0707 February 2023 Integrated Inspection Report 05000400/2022004 ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000400/20220032022-11-10010 November 2022 Integrated Inspection Report 05000400/2022003 IR 05000400/20223012022-11-0202 November 2022 NRC Operator License Examination Report 05000400/2022301 ML22271A6202022-09-29029 September 2022 Notification of Shearon Harris Nuclear Power Plant Comprehensive Engineering Team Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2023010 ML22258A1262022-09-14014 September 2022 NRC Operator Licensing Examination Approval 05000400/2022301 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22227A0682022-09-0202 September 2022 Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves IR 05000400/20220052022-08-24024 August 2022 Updated Inspection Plan for Shearon Harris Nuclear Power Plant (Report 05000400/2022005) IR 05000400/20224032022-08-23023 August 2022 Security Baseline Inspection Report 05000400/2022403 ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 IR 05000400/20220022022-08-0505 August 2022 Integrated Inspection Report 05000400/2022002 ML22161B0332022-07-28028 July 2022 Issuance of Amendment No. 193 Regarding Revision of Surveillance Requirements to Remove Shutdown Limitation IR 05000400/20220112022-07-20020 July 2022 Biennial Problem Identification and Resolution Inspection Report 05000400 2022011 IR 05000400/20224022022-06-30030 June 2022 Material Control and Accounting Program Inspection Report 05000400/2022402 (OUO Removed) IR 05000400/20220102022-06-13013 June 2022 Design Basis Assurance Inspection (Programs) Inspection Report 05000400/2022010 ML22138A4012022-05-26026 May 2022 Project Manager Reassignment ML22101A2822022-05-0606 May 2022 Regulatory Audit Summary Related to the Review of License Amendment Regarding Revising the Flood Hazard Protection Scheme IR 05000400/20220012022-05-0404 May 2022 Integrated Inspection Report 05000400/2022001 IR 05000400/20224012022-03-24024 March 2022 Security Baseline Inspection Report 05000400/2022401 ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 IR 05000400/20210062022-03-0202 March 2022 Annual Assessment Letter for Shearon Harris Nuclear Power Plant (Report No. 05000400/2021006) ML21351A4722022-02-10010 February 2022 Issuance of Amendment No. 190 Regarding Revision to Containment Spray Nozzle Test Frequency IR 05000400/20210042022-02-0404 February 2022 Integrated Inspection Report 05000400/2021004 ML22034A5352022-02-0202 February 2022 Notification of Licensed Operator Initial Examination 05000400/2022301 2024-01-30
[Table view] Category:Safety Evaluation
MONTHYEARML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22242A0022022-09-12012 September 2022 Issuance of Amendments to Adopt TSTF 569, Revision 2, Revise Response Time Testing Definition ML22227A0682022-09-0202 September 2022 Alternative to Certain Inservice Testing Requirements in the American Society of Mechanical Engineers Code for Operation and Maintenance for Certain Target Rock Solenoid Valves ML22126A0082022-08-0909 August 2022 Issuance of Amendment No. 194 Revise Technical Specifications Related to Reactor Protection System Instrumentation P7 ML22161B0332022-07-28028 July 2022 Issuance of Amendment No. 193 Regarding Revision of Surveillance Requirements to Remove Shutdown Limitation ML22083A0272022-03-23023 March 2022 Safety Evaluation -Harris Safety Evaluation -EPID L-2021-LLA-0149 - Revise TS Related to Reactor Protection System ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications ML22010A2812022-03-0404 March 2022 Issuance of Amendments to Adopt TSTF-577, Rev. 1 Revised Frequencies for Steam Generator Tube Inspections (EPID L-2021-LLA-0161 ML21351A4722022-02-10010 February 2022 Issuance of Amendment No. 190 Regarding Revision to Containment Spray Nozzle Test Frequency ML21320A0012022-01-20020 January 2022 Issuance of Amendment No. 189 to Regarding Administrative Change to Reflect Development of a Technical Requirements Manual ML21316A2482022-01-19019 January 2022 Issuance of Amendment No. 188, Regarding Revision of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML21155A2132021-08-26026 August 2021 Plant ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21047A4702021-04-0808 April 2021 Issuance of Amendment No. 185 Regarding Reduction of Reactor Coolant System Minimum Flow Rate and Update to the Core Operating Limits Report References ML21047A3142021-04-0202 April 2021 Issuance of Amendment No. 184 Regarding Technical Specifications Task Force (TSTF) Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times RITSTF Initiative 4B ML21033B0072021-03-22022 March 2021 Issuance of Amendment No, 183 to Correct Non-Conservative Technical Specification Related to Reactor Coolant System Pressure/Temperature Limits ML21069A0642021-03-18018 March 2021 Alternative to ASME Section XI Code Requirements to Defer Repair of Emergency Service Water System Socket Weld ML21035A1322021-03-16016 March 2021 Issuance of Amendment No. 182 Regarding Technical Specifications Related to Accident Monitoring Instrumentation, and Refueling Operations Instrumentation ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20259A5122020-12-0808 December 2020 Issuance of Amendment No. 181 Regarding Adoption of 10 CFR Part 50, Appendix J, Option B, for Type B and C Testing and for Permanent Extension of Type a, B, and C Leak Rate Testing Frequencies(L-2019-LLA-0256) ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20281A2792020-10-13013 October 2020 Correction Letter to Amendment No. 179 Regarding Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML20212L5942020-09-29029 September 2020 Issuance of Amendment No. 179 Regarding Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20099F5052020-06-29029 June 2020 Issuance of Amendment No. 177 Regarding Elimination of Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications ML19225C0692019-09-19019 September 2019 Issuance of Amendment No. 175 Modify Reactor Trip System and Engineered Safety Features Actuation System Instrumentation Trip Setpoints ML19192A0122019-09-17017 September 2019 Issuance of Amendment No. 174 Adopt Title 10 of the Code of Federal Regulations 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19108A1732019-07-18018 July 2019 Issuance of Amendment No. 173 Regarding Emergency Plan Emergency Action Level Scheme Change ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML18288A1392019-04-29029 April 2019 Issuance of Amendments 171, 263 Revising Technical Specifications to Support Self Performance of Core Reload Design and Safety Analyses ML19050A2972019-04-18018 April 2019 McGuire Nuclear Station, Units 1 and 2, Shearon Harris Nuclear Power Plant, Unit 1, H B. Robinson Steam Electric Plant, Unit 2 - Issuance of Amendments Regarding Removal ML18347A3852019-03-29029 March 2019 Issuance of Amendment No. 169, Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis ML19018A0252019-02-26026 February 2019 Relief Request I3R-18, Regarding Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Inservice Inspection Program for Containment, Third Ten-Year Interval ML18303A0482018-12-0404 December 2018 Extension of Reactor Pressure Vessel Surveillance Report for Capsule Z ML18283B5442018-11-20020 November 2018 Relief from the Requirements of the ASME Code, Section XI, Reactor Vessel Closure Head Penetration Nozzle Repair Technique ML18262A3032018-11-19019 November 2018 Issuance of Amendment No. 168 Regarding License Amendment Request for Rod Control Movable Assemblies Technical Specifications Changes ML18204A2862018-10-22022 October 2018 Issuance of Amendment No. 167 Regarding (CAC MF9996; EPID 2017-LLA-0303) ML18172A1722018-08-15015 August 2018 Issuance of Amendments to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application ML18060A4012018-04-10010 April 2018 Redacted Issuance of Amendments Revising TSs for Methodology Reports DPC-NE-3008-P, Revision 0, and DPC-NE-3009-P, Revision 0) (CAC Nos. MF8439 and MF8440; EPID L-2016-LLA-0012) ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads 2023-09-25
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May 8, 2006 Mr. Cornelius J. Gannon, Vice President Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Code: Zone 1 New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 REVIEW OF THE 2004 STEAM GENERATOR TUBE INSPECTION
SUMMARY
REPORTS (TAC NO. MC8060)
Dear Mr. Gannon:
By letters dated May 27, 2004 (Agencywide Documents Access and Management System Accession Number, ML041560343), October 28, 2004 (ML043090488), February 15, 2005 (ML050600144), August 1, 2005 (ML052210457), and February 13, 2006 (ML060530375),
Carolina Power and Light Company (the licensee) submitted information summarizing the results of its 2004 mid-cycle steam generator tube inspections at the Shearon Harris Nuclear Power Plant, Unit 1. In addition to these reports, the Nuclear Regulatory Commission (NRC) staff summarized additional information concerning the 2004 steam generator tube inspections in letters dated July 26, 2004 (ML042080426) and January 12, 2005 (ML043440363).
As discussed in the enclosed evaluation, the NRC staff concludes that the licensee provided the information required by its technical specifications. In addition, the staff did not identify any technical issues that warrant followup action at this time.
Sincerely,
/RA/
Chandu P. Patel, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
Staff Evaluation cc w/encl: See next page
ML060970591 NRR-106 OFFICE LPL2-2/GE LPL2-2/PM LPL2-2/LA NRR/DCI LPL2-2/BC NAME SCrane CPatel RSola KKarwoski MMarshall DATE 5/5/06 5/5/06 5/3/06 5/5/06 5/8/06 Mr. C. J. Gannon, Jr.
Carolina Power & Light Company cc:
David T. Conley Mr. Robert P. Gruber Associate General Counsel II - Executive Director Legal Department Public Staff NCUC Progress Energy Service Company, LLC 4326 Mail Service Center Post Office Box 1551 Raleigh, North Carolina 27699-4326 Raleigh, North Carolina 27602-1551 Chairman of the North Carolina Resident Inspector/ Harris NPS Utilities Commission c/o U. S. Nuclear Regulatory Commission Post Office Box 29510 5421 Shearon Harris Road Raleigh, North Carolina 27626-0510 New Hill, North Carolina 27562-9998 Mr. Herb Council, Chair Ms. Margaret A. Force Board of County Commissioners Assistant Attorney General of Wake County State of North Carolina P. O. Box 550 Post Office Box 629 Raleigh, North Carolina 27602 Raleigh, North Carolina 27602 Mr. Tommy Emerson, Chair Public Service Commission Board of County Commissioners State of South Carolina of Chatham County Post Office Drawer 11649 P. O. Box 87 Columbia, South Carolina 29211 Pittsboro, North Carolina 27312 Ms. Beverly Hall, Section Chief Mr. Christos Kamilaris, Manager Division of Radiation Protection Support Services N.C. Department of Environment Shearon Harris Nuclear Power Plant and Natural Resources Carolina Power & Light Company 3825 Barrett Drive P. O. Box 165, Mail Zone 1 Raleigh, North Carolina 27609-7721 New Hill, North Carolina 27562-0165 Mr. Chris L. Burton Mr. David H. Corlett, Supervisor Manager Licensing/Regulatory Programs Performance Evaluation and Shearon Harris Nuclear Power Plant Regulatory Affairs PEB 7 Carolina Power & Light Company Progress Energy P. O. Box 165, Mail Zone 1 Post Office Box 1551 New Hill, NC 27562-0165 Raleigh, North Carolina 27602-1551 Mr. John H. ONeill, Jr.
Mr. Eric McCartney Shaw, Pittman, Potts & Trowbridge Plant General Manager 2300 N Street, NW.
Shearon Harris Nuclear Power Plant Washington, DC 20037-1128 Carolina Power & Light Company P. O. Box 165, Mail Zone 3 New Hill, North Carolina 27562-0165 Mr. Robert J. Duncan II Director of Site Operations Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165
EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF THE STEAM GENERATOR TUBE INSPECTION REPORTS FOR THE 2004 OUTAGE SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 By letters dated May 27, 2004 (Agencywide Documents Access and Management System Accession Number, ML041560343), October 28, 2004 (ML043090488), February 15, 2005 (ML050600144), August 1, 2005 (ML052210457), and February 13, 2006 (ML060530375),
Carolina Power and Light Company (the licensee) submitted information summarizing the results of its 2004 mid-cycle steam generator (SG) tube inspections at Shearon Harris Nuclear Power Plant, Unit 1 (Harris). In addition to these reports, the Nuclear Regulatory Commission (NRC) staff summarized additional information concerning the 2004 SG tube inspections in letters dated July 26, 2004 (ML042080426), and January 12, 2005 (ML043440363).
Harris has three Westinghouse model Delta 75 SGs, that were put into service in 2001 during refueling outage (RFO) 10. Each SG has 6307 thermally treated Alloy 690 tubes that have an outside diameter of 0.688 inch and a nominal wall thickness of 0.040 inch. The tubes were hydraulically expanded at each end for the full depth of the tubesheet. The tubes are supported by a number of stainless steel support plates that have trifoil shaped holes through which the tubes pass. Below the support plates, is a flow distribution baffle that has octafoil-shaped holes. The tubes in rows 1 through 17 (i.e., those with a bend radius less than 12 inches) received a supplemental thermal treatment (stress relieving) after bending.
The licensee provided the scope, extent, methods, and results of its SG tube inspections in the documents referenced above. The licensee also described corrective actions (e.g., tube plugging) taken in response to the inspection findings.
As a result of the review of the reports, the NRC staff has the following comments/observations:
Following a tube leak in 2004, the licensee reviewed selected eddy current data from its 2003 (RFO 11) outage. Based on this review of the 2003 data, an indication was found in the tube in row 1, column 120 of SG C. The indication was estimated by the licensee to be 37 percent through-wall. As a result, the licensee classified the SG inspection results as Category C-1 in accordance with its technical specifications. A review of the eddy current data for this indication by the NRC resulted in a depth estimate of 40 percent through-wall. A 40 percent through-wall depth estimate would have resulted in categorizing the SG as Category C-2.
Enclosure
In addition, the licensee classified the results of its 2004 SG tube inspections as Category C-1. This classification was made based on the results of inspections performed after plugging three tubes that were damaged by a foreign object. The estimated depths of the degradation in these three tubes were in excess of 40 percent through-wall. No classification of the inspection results was performed for the three tubes plugged during the 2004 outage. Whenever SG tube inspections are performed, the technical specifications should be used in inspecting, repairing, and classifying the results. If the three tubes mentioned above were considered in the classification, the SG inspection results would have been classified as Category C-2.
Given the staffs categorization of the inspection results, the licensee would be required by its current technical specifications to perform its next SG tube inspections within 12 to 24 calendar months from the previous inspection (May 2004). If a categorization of C-1 for the 2003 and 2004 inspections were appropriate, the licensee would be permitted to extend its inspection interval to 40 months. Since the licensee plans to perform its next SG tube inspections within 12 to 24 calendar months since its previous inspection (May 2004), the categorization of the results is less important. The next inspections are planned for RFO 13 in the spring of 2006. In addition, such categorization is no longer necessary under the new standard Technical Specifications (i.e., Technical Specification Task Force 449, Revision 4), which the licensee plans to submit for NRC approval by May 31, 2006.
During a secondary side pressure test performed in 2004, the licensee was unable to exceed a test pressure of 60 pounds per square inch gauge since the capacity of the nitrogen supply system was exceeded. Presumably, the capacity of the nitrogen supply system was exceeded as a result of a secondary side leak other than the leakage through the leaking SG tube. Based on the low levels of normal operating primary-to-secondary leakage prior to the plant shutdown, there would not appear to be any tube integrity implications associated with this possible secondary side leak. The source of the leak was never identified.
Based on a review of the information provided, the staff concludes that the licensee provided the information required by its technical specifications. In addition, the staff concludes that there are no technical issues that warrant followup action at this time since the inspections appear to be consistent with the objective of detecting potential tube degradation and the inspection results appear to be consistent with industry operating experience at similarly designed and operated units.
Principal Contributor: Kenneth J. Karwoski Date: May 8, 2006