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Category:Letter
MONTHYEARML24290A1102024-10-24024 October 2024 Notification of Licensed Operator Initial Examination 05000400/2025301 05000400/LER-2024-001-01, Automatic Reactor Trip Due to Main Generator Lock-Out2024-10-23023 October 2024 Automatic Reactor Trip Due to Main Generator Lock-Out IR 05000400/20240112024-09-10010 September 2024 NRC Inspection Report 05000400/2024011 IR 05000400/20240052024-08-26026 August 2024 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400-2024005) Rev 1 ML24059A4252024-08-14014 August 2024 Issuance of Amendment No. 202 Regarding Alignment of Certain Technical Specifications with Improved Standard Technical Specifications ML24213A0522024-08-0202 August 2024 Issuance of Amendment No. 201 to Extend Completion Time of Inoperable Reactor Coolant System Accumulator Using Consolidated Line Item Improvement Process ML24212A3412024-07-31031 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000400/20240022024-07-29029 July 2024 – Integrated Inspection Report 05000400/2024002 ML24170A7312024-07-29029 July 2024 – Exemption from the Requirements of 10 CFR 50.55a(H)(2) Using the Risk-Informed Process for Evaluations Letter 05000400/LER-2024-001, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-22022 July 2024 Automatic Reactor Trip Due to Main Generator Lock-Out ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000400/20243022024-06-27027 June 2024 – NRC Operator Licensing Examination Approval 05000400/2024302 IR 05000400/20244012024-06-25025 June 2024 – Security Baseline Inspection Report05000400/2024401 ML24162A1372024-06-24024 June 2024 – Regulatory Audit Summary Related to the Review of Exemption Request from Certain Requirements in 10 CFR 50.55a(h)(2)(EPID L-2024-LLE-00040) ML24136A1382024-05-20020 May 2024 – Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2024011) and Request for Information (RFI) ML24116A2592024-05-14014 May 2024 Staff Evaluation Related to Aging Management Plan and Inspection Plan for Reactor Vessel Internals ML24127A1592024-05-0808 May 2024 – Notification of Licensed Operator Initial Examination 05000400/2024302 IR 05000400/20240012024-05-0505 May 2024 Integrated Inspection Report 05000400/2024001 ML24100A0912024-04-10010 April 2024 Operator License Examination Report ML24058A2462024-03-18018 March 2024 – Supplemental Information Needed for Using the Risk-Informed Process for Evaluations for the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) IR 05000400/20230062024-02-28028 February 2024 Annual Assessment Letter for Shearon Harris Nuclear Power Plant - NRC Inspection Report 05000400/2023006 ML24032A2632024-02-23023 February 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0044 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 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 05000400/LER-2022-006-02, Auxiliary Feedwater Pump Inoperability2023-07-11011 July 2023 Auxiliary Feedwater Pump Inoperability 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 05000400/LER-1922-006-01, Auxiliary Feedwater Pump Inoperability2023-03-10010 March 2023 Auxiliary Feedwater Pump Inoperability 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 05000400/LER-2022-007-01, Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus2023-01-26026 January 2023 Automatic Reactor Trip Due to Loss of Power from the a Auxiliary Bus ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) 05000400/LER-2022-006, Auxiliary Feedwater Pump Inoperability2022-12-20020 December 2022 Auxiliary Feedwater Pump Inoperability 2024-09-10
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24212A3412024-07-31031 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24101A0522024-04-10010 April 2024 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information - ITS Alignments LAR (L-2023-LLA-0078) ML24058A2462024-03-18018 March 2024 – Supplemental Information Needed for Using the Risk-Informed Process for Evaluations for the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) ML24025A1592024-01-25025 January 2024 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information - Rvi AMP and Inspection Plan (L-2023-LLL-0016) ML23151A3482023-05-30030 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML23142A2732023-05-22022 May 2023 Duke Fleet - Request for Additional Information Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) ML23082A0432023-03-23023 March 2023 002 Radiation Safety Baseline Inspection Information Request Final ML23020A1252023-01-23023 January 2023 Notification of Target Set Inspection and Request for Information (NRC Inspection Report 05000400/2023403) ML22115A1412022-04-25025 April 2022 NRR E-mail Capture - Duke Common EOF Relocation - Request for Addition Information ML21354A8612021-12-15015 December 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet Request RA-19-0352 - Alternative for RPV Closure Stud Exams (L-2020-LLR-0156) ML21258A3652021-09-15015 September 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000400/2021011) and Request for Information (RFI) ML21172A2432021-06-21021 June 2021 NRR E-mail Capture - Request for Additional Information - Harris RA-20-0252 - LAR to Remove Extraneous Requirements from OL and TS (L-2021-LLA-0027) ML21036A1142021-02-0505 February 2021 NRR E-mail Capture - Request for Additional Information - Harris - Relief Request RA-20-0312 - SW Pinhole Leak (L-2020-LLR-0143) ML21049A2632021-02-0404 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Energy Fleet License Amendment Request to Revise Emergency Plan ML21032A0492021-02-0101 February 2021 NRR E-mail Capture - Request for Additional Information - Duke Fleet RA-20-0263 - Use of Later ASME B&Pv, XI for Repair - Replacement (L-2020-LLR-0124) ML20323A4072020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information - Brunswick License Exemption Request from 10CFR73 Annual Force on Force Exercise Requirements (EPIC L-2020-LLE-0180) ML20297A3072020-10-13013 October 2020 NRR E-mail Capture - Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - RCS Flowrate Reduction/Lbloca LAR ML20274A0462020-09-29029 September 2020 Request for Additional Information Regarding License Amendment Request to Adopt TSTF-505, Revision 2 ML20247J3822020-09-0303 September 2020 Request for Additional Information - Shearon Harris Nuclear Power Plant, Unit 1 - Revise TS Related to Accident Monitoring and RFO Instrumentation ML19331A4002019-11-27027 November 2019 Request for Additional Information Regarding Licensing Action to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML19204A2682019-07-23023 July 2019 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information for the Escw System TS AOT Extension and Removal of an Expired Note in TS Risk Informed LAR (L-2019-LLA-0025) ML19136A2712019-05-28028 May 2019 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type ML19060A0912019-03-18018 March 2019 Request for Additional Information Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML19011A1372019-01-10010 January 2019 NRR E-mail Capture - Duke Energy Fleet RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML19007A3422018-12-21021 December 2018 NRR E-mail Capture - Duke Energy Fleet Draft RAIs - Relief Request 18-GO-001 - Proposed Alternative for Depth Sizing Qualification Examination of Welds (L-2018-LLR-0117) ML18332A4392018-11-28028 November 2018 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information for EAL Scheme Changes ML18337A1272018-11-28028 November 2018 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information Regarding the Rts/Esfas Trip Setpoints Modification LAR ML18264A0282018-10-0909 October 2018 RAI Regarding License Amendment Request to Adopt 10 CFR 50.69, Risk Informed Categorization Aad Treatment of Structures, Systems and Components for Nuclear Power Reactors ML18145A1812018-06-18018 June 2018 Request for Additional Information, License Amendment Request to Revise Updated Final Safety Analysis Report to Incorporate Tornado Missile Risk Evaluator Methodology Into Licensing Basis RA-18-0011, Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-30030 May 2018 Response to Request for Supplemental Information Regarding Duke Energy'S Response to GL 2016-01 Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools ML18116A1052018-04-25025 April 2018 NRR E-mail Capture - Harris/Robinson RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18108A7602018-04-18018 April 2018 NRR E-mail Capture - Harris/Robinson Draft RAIs - Change Technical Specifications to Support Performance of Core Reload Design and Safety Analyses (L-2017-LLA-0356) ML18058B2242018-02-26026 February 2018 Emailed Radiation Safety RFI ML18005A5482018-01-0808 January 2018 Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses (CAC No. MF9996; EPID L-2017-LLA-0303) ML17345A8772017-12-11011 December 2017 NRR E-mail Capture - Harris and Robinson Supplemental RAI - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17339A0722017-12-0404 December 2017 NRR E-mail Capture - Subject: Harris and Robinson Draft Supplemental RAIs - LAR to Adopt DPC-NE-3009-P, Revision 0, Thermal-Hydraulic Models for Transient Analysis, (L-2016-LLA-0012) ML17289A3062017-10-23023 October 2017 Shearon Harris Nuclear Plant, Unit 1 - Request for Additional Information Regarding License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements (CAC No. MF9828; EPID L-2017-LLA-0244) ML17250B0172017-09-18018 September 2017 Shearon Harris, Unit 1 - Request for Additional Information Re: License Amendment Request Proposing New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods that Exceed the LHGR Limit Detailed in RG 1.183, Table 3 (CAC No. MF9740) ML17241A0182017-08-30030 August 2017 Supplemental Information Needed for Acceptance of Requested Licensing Action Regarding Spent Fuel Storage Pool Criticality Analyses ML17192A4842017-07-11011 July 2017 NRR E-mail Capture - Duke Energy Fleet RAIs Alternative for Reactor Pressure Vessel Flange Threads Examination (MF9513 to MF9521) ML17123A1332017-05-0909 May 2017 Shearon Harris Nuclear Plant, Unit 1 - Request for Additional Information Re: License Amendment Request to Relocate Specific TS Parameters to the COLR, Remove Reference to a Plant Procedure as it Pertains to the COLR in TSs, etc. (CAC No. MF8894) ML17109A2912017-04-19019 April 2017 NRR E-mail Capture - Shearon Harris Nuclear Power Plant, Unit 1 Final Request for Additional Information Concerning LAR to Adopt TSTF-339, TSTF-5 and Other Administrative Changes ML16363A0112016-12-27027 December 2016 Notification of Shearon Harris Nuclear Power Plant Design Basis Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000400/2017007 ML16335A0462016-12-0606 December 2016 Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information Regarding License Amendment Request to Modify Diesel Fuel Oil Testing Surveillance Requirements (CAC No. MF7775) ML16288A0782016-10-26026 October 2016 Shearon Harris Nuclear Power Plant, Unit 1, and H.B. Robinson Steam Electric Plant, Unit No. 2 - Redacted, Request for Additional Information Re: Request to Adopt DPC-NF-2010 and DPC-NF-2011 Nuclear Design Methodology (CAC Nos. MF7693 and MF7694) ML16288A0042016-10-26026 October 2016 Shearon Harris Nuclear Plant, Unit 1 - Request For Additional Information Regarding License Amendment Request To Relocate The Explosive Gas Mixture And Liquid Holdup Tanks Technical Specifications Requirements (CAC No. MF8067) ML16223A4172016-08-0808 August 2016 Notification of Inspection and Request for Information ML16209A2642016-08-0202 August 2016 Shearon Harris Nuclear Plant, Unit 1 - Second Request For Additional Information Regarding License Amendment Request For A Temporary Change To Technical Specifications For The 'A' Emergency Service Water Pump Replacement (CAC No. MF7017) ML16028A1972016-02-0808 February 2016 Request for Additional Information Regarding License Amendment Request for a Temporary Change to Technical Specifications for the 'A' Emergency Service Water Pump Replacement ML15344A0302015-12-17017 December 2015 Request for Additional Information Application to Revise Technical Specifications for Methodology Report DPC-NE-2005-P, Revision 5, Thermal Hydraulic Statistical Core Design Methodology (MF5872/MF5873) 2024-07-31
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 11, 2012 Christopher L Burton, Jr., Vice President Shearon Harris Nuclear Power Plant Progress Energy Carolinas, Inc.
Post Office Box 165, Mail Code: Zone 1 New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE RELIEF REQUEST 13-09 FOR THE REACTOR VESSEL CLOSURE HEAD NOZZLES REPAIR FOR THE THIRD INSERVICE INSPECTION PROGRAM INTERVAL (TAC NO. ME8523)
Dear Mr. Burton:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated May 3, 2012, (Agencywide Documents Access and Management System Accession No. ML12128A007), Carolina Power
& Light Company, doing business as Progress Energy Carolinas, Inc. submitted Relief Request 13R-09 for the repair of degraded reactor vessel closure head nozzle penetrations for Shearon Harris Nuclear Power Plant, Unit No.1.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on May 10, 2012, it was agreed that you would provide a response 7 days after the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3302.
Sincerely, Araceli T. Billoch Colon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION SHEARON HARRIS NUCLEAR POWER PLANT UNIT NO.1 CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-400 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated May 3, 2012, Carolina Power
& Light Company, doing business as Progress Energy Carolinas, Inc. submitted Relief Request (RR) 13R-09 for the repair of degraded reactor vessel closure head (RVCH) nozzle penetrations for Shearon Harris Nuclear Power Plant, Unit No.1. To complete its review, the NRC staff requests additional information as discussed below.
- 1. Page 6, Section 5.a. of the RR states that the interpass temperature will be determined by one of the following methods: (1) heat flow calculations or (2) measurement based on a test coupon. Discuss the exact measurement method that will be used and explain why that method is selected.
- 2. Page 8, Section 5.b. of the RR states, in part, "... For this modification, the repair weld is suitable, except for the taper transition, for ultrasonic testing (UT) examination and a final surface examination can be performed .... " Discuss the examination method(s) that will be used for the taper transition. If the answer is: No examination will be performed, discuss how the taper transition can be ensured of its structural integrity (Le., no flaws).
- 3. Page 8, Section 5.b. of the RR states, in part, "...Approximately 70% of the weld surface will be scanned by UT. Approximately 83% of the RVCH ferritic steel heat affected zone (HAZ) will be covered by UT. ... " Based on the aforementioned examination coverage, Figure 4 through Figure 8 provide the coverage for UT examination with the hashed lines.
- a. Discuss the area 'and volume of the new weld that could not and will not be examined.
- b. Discuss how the area and volume of the new weld that could not be examined can be ensured of structural integrity (Le., no flaws).
- c. If 70% of the new weld surface will be scanned by UT, clarify what is the percentage of coverage for the "volume" of the weld.
- 4. Page 10, Section 5.d., last paragraph of the RR states that the stress on the postulated circumferential flaw has a margin of 1.43 with respect to the allowable stress and the depth of axial flaw has a margin of 3.9 with respect to the allowable flaw depth. First paragraph on page 11 states that the fatigue crack growth is acceptable.
- a. Provide the final crack size (length and depth) in the axial and circumferential direction at the end of 40 years and explain why the final crack size is acceptable.
ENCLOSURE
- 2
- b. Explain how the margins on stress and flaw depth satisfy the required margins in the American Society o'F Mechanical Engineers (ASME) Code.Section XI, IW8-3600.
- c. The RR states that the fracture toughness margins for flaws have been shown to be acceptable. Discuss the fracture toughness margins.
- 5. Page 11. Section 5.e. of the RR discusses the worst-case flaw in the J-groove weld.
- a. Describe the worst-case flaw.
- b. Explain why the proposed nozzle repair design configuration is considered to be acceptable for 30 years of operation after the weld repair.
- 6. Discuss whether all the flaws identified in Nozzles No.5, 17.38, and 63 will be removed as a result of the proposed repair. If not, justify how the nozzles with remnant flaws can be ensured of structural integrity so as not to affect the function of the control rod drive mechanism and the structural integrity of the reactor vessel head.
- 7. Section 6 of the RR states that the proposed repair has a design life expectancy of 14.8 effective full-power years (EFPYs). Describe in detail or submit the analysis that results in the design life of 14.8 EFPYs. Section 5.e. states that the nozzle repair design is considered to be acceptable for 30 years. Explain the discrepancy between the two different design life expentancies.
- 8. Discuss the mockup for the proposed repair in general and specifically for the welding and inspection qualification.
- 9. The RR stated that ASME Code Case N-638-1 will be implemented.
- a. Clarify whether Shearon Harris, Unit 1, has already adapted ASME Code Case N-638-1 (approved by the NRC in Regulatory Guide (RG) 1.147. Rev. 15, for use with conditions) during the third 10-year Inservice Inspection interval.
- b. If the answer to RAI-9.a. is: No, then clarify why ASME Code Case N-638-4 (approved by the NRC in RG 1.147. Rev. 16, for use with conditions) that has superseded the previous versions of that code case is not being used.
t1ay 11, 2012 Christopher L Burton, Jr., Vice President Shearon Harris Nuclear Power Plant Progress Energy Carolinas, Inc.
Post Office Box 165, Mail Code: Zone 1 New Hill, North Carolina 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE RELIEF REQUEST 13-09 FOR THE REACTOR VESSEL CLOSURE HEAD NOZZLES REPAIR FOR THE THIRD INSERVICE INSPECTION PROGRAM INTERVAL (TAC NO. ME8523)
Dear Mr. Burton:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated May 3, 2012, (Agencywide Documents Access and Management System Accession No. ML12128A007), Carolina Power
& Light Company, doing business as Progress Energy Carolinas, Inc. submitted Relief Request 13R-09 for the repair of degraded reactor vessel closure head nozzle penetrations for Shearon Harris Nuclear Power Plant, Unit No.1.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. During a discussion with your staff on May 10, 2012, it was agreed that you would provide a response 7 days after the date of this letter.
The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-3302.
Sincerely, IRA!
Araceli T. Billoch Colon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL 11-2 Reading RidsNrrDorlLpl2-2 RidsNrrPMShearonHarris JCollins, NRR ARezai RidsNrrLABClayton RidsRgn2MailCenter RidsAcrsAcnwMailCenter JTsao, NRR DAiley, NRR A DAMS Accession No. ML12128A294 *BvEmaii OFFICE LPL2-21PM LPL2*2ILA DE/EPTB* LPL2*2/BC LPL2-2/PM NAME ABiliochCol6n BClayton JTsao DBroaddus ABillochCol6n DATE 05/11/12 05/11/12 05/11/12 05/11/12 05/11/12 OFFICIAL RECORD COpy