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Category:Letter
MONTHYEARIR 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 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 05000400/20243012024-02-21021 February 2024 – NRC Operator Licensing Examination Approval 05000400/2024301 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 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 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 REGION II SAM NUNN ATLANTA FEDERAL CENTER 61 FORSYTH STREET, SW, SUITE 23T85 ATLANTA, GEORGIA 30303-8931 March 13, 2009 Mr. Christopher L. Burton Vice President Carolina Power & Light Company Shearon Harris Nuclear Plant P.O. Box 165, Mail Zone 1 New Hill, NC 27562-0165
SUBJECT:
SHEARON HARRIS NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Burton:
From April 27 to May 1, 2009, the NRC will perform the baseline inservice inspection (ISI) at the Shearon Harris Nuclear Plant (NRC Inspection Procedure 71111.08). Experience has shown that this inspection is resource intensive both for the NRC inspectors and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. These documents have been divided into two groups. The first group (section A of the enclosure) identifies information to be provided prior to the inspection to ensure that the inspectors are adequately prepared. The second group (section B of the enclosure) identifies the information the inspectors will need upon arrival at the site. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Michael Wallace of your organization. Our inspection dates are subject to change based on your updated schedule of outage activities. If there are any questions about this inspection or the material requested, please contact the inspector Rich C. Chou at (404) 562-4670 (rich.chou@nrc.gov).
In accordance with 10 CFR 2.390 of the NRCs Rules of Practice, a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS).
CP&L 2 ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
George T. Hopper, Chief Engineering Branch 3 Division of Reactor Safety Docket No. 50-400 License No. NPF-63
Enclosure:
Pre-Inspection Document Request (cc w/encl: See page 3)
_________________________ XG SUNSI REVIEW COMPLETE OFFICE RII:DRS RII:DRS SIGNATURE /RA? /RA/
NAME Rich Chou George Hopper DATE 03/13/2009 03/13/2009 4/ /2009 4/ /2009 4/ /2009 4/ /2009 4/ /2009 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO CP&L 3 cc w/encl:
Brian C. McCabe Beverly O. Hall Manager Chief, Radiation Protection Section Nuclear Regulatory Affairs Department of Environmental Health Progress Energy N.C. Department of Environmental Electronic Mail Distribution Commerce & Natural Resources Electronic Mail Distribution R. J. Duncan, II Vice President Public Service Commission Nuclear Operations State of South Carolina Carolina Power & Light Company P.O. Box 11649 Electronic Mail Distribution Columbia, SC 29211 J. Wayne Guganious Chairman Training Manager North Carolina Utilities Commission Shearon Harris Nuclear Power Plant Electronic Mail Distribution Progress Energy Carolinas, Inc.
Electronic Mail Distribution Robert P. Gruber Executive Director Kimberly Harshaw Public Staff - NCUC Manager 4326 Mail Service Center Support Services Raleigh, NC 27699-4326 Progress Energy Carolinas, Inc.
Electronic Mail Distribution Herb Council Chair David H. Corlett, Supervisor Board of County Commissioners of Wake Licensing/Regulatory Programs County Carolina Power & Light Company P.O. Box 550 Electronic Mail Distribution Raleigh, NC 27602 David T. Conley Tommy Emerson Associate General Counsel Chair Legal Department Board of County Commissioners of Progress Energy Service Company, LLC Chatham County Electronic Mail Distribution 186 Emerson Road Siler City, NC 27344 Christos Kamilaris, Director Fleet Support Services Kelvin Henderson Carolina Power & Light Company Plant General Manager Electronic Mail Distribution Carolina Power and Light Company Shearon Harris Nuclear Power Plant John H. O'Neill, Jr. Electronic Mail Distribution Shaw, Pittman, Potts & Trowbridge 2300 N. Street, NW Senior Resident Inspector Washington, DC 20037-1128 Carolina Power and Light Company Shearon Harris Nuclear Power Plant T. D. Walt U.S. NRC Vice President 5421 Shearon Harris Rd Nuclear Oversight New Hill, NC 27562-9998 Carolina Power and Light Company Electronic Mail Distribution
CP&L 4 Letter to Christopher L. Burton from George Hopper dated March 13, 2009
SUBJECT:
SHEARON HARRIS NUCLEAR PLANT - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION Distribution w/encl:
RIDSNRRDIRS PUBLIC M. Vaaler, NRR (PM - Harris)
INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: April 27- May 1, 2009 Inspection Procedures: IP 71111.08 Inservice Inspection (ISI) Activities Inspectors: Rich C. Chou, Reactor Inspector A. Information Requested for the In-Office Preparation Week The following information should be sent to the Region II office in hard copy or electronic format (CD preferred), in care of Rich C. Chou by April 9, 2009, to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The inspector will select specific items from the information requested below and then request from your staff additional documents needed during the onsite inspection week (section B of this enclosure). We ask that the specific items selected from the lists be available and ready for review on the first day of inspection. *Please provide requested documentation electronically if possible. If requested documents are large and only hard copy formats are available, please inform the inspector, and provide subject documentation during the first day of the onsite inspection. If you have any questions regarding this information request, please call the inspector as soon as possible.
A.1 ISI / Welding Programs and Schedule Information a) A detailed schedule (including preliminary dates) of:
i) Nondestructive examinations (NDEs) planned for Class 1 & 2 systems and containment, performed as part of your ASME Section XI, Risk Informed (if applicable), and augmented ISI Programs during the upcoming outage.
Provide a status summary of the NDE inspection activities vs. the required inspection period percentages for this Interval by category per ASME Section XI, IWX-2400. (Do not provide separately if other documentation requested contains this information) ii) Reactor pressure vessel head (RPVH) visual examinations planned for the upcoming outage.
iii) Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope. (If applicable) iv) Examinations planned as part of your Boric Acid Corrosion Control Program. (Mode 3 walkdowns, bolted connection walkdowns, etc.)
v) Welding activities that are scheduled to be completed during the upcoming outage. (ASME Class 1, 2, or 3 structures, systems, or components (SSCs)
Enclosure
2 b) A copy of ASME Section XI Code Relief Requests and associated NRC Safety Evaluations applicable to the examinations identified above.
c) A list of NDE reports (ultrasonic, radiography, magnetic particle, and liquid penetrant) which have identified surface or volumetric indications that were analytically evaluated and accepted for continued service on Code Class 1, 2, &
3 systems since the beginning of the last refueling outage. This should include the previousSection XI pressure test(s) conducted during start up and any evaluations associated with the results of the pressure tests.
d) A list with a brief description (e.g. system, material, pipe size, weld number, and NDE performed) of the welds in Code Class 1, 2, and 3 systems which have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage, or are planned to be fabricated this refueling outage. Also, please indicate which of those welds are risk significant.
e) If reactor vessel shell weld examinations required by the ASME Code are scheduled to occur during the upcoming outage, provide a detailed description of the welds to be examined, and the extent of the planned examination. Please also provide reference numbers for applicable procedures that will be used to conduct these examinations.
f) Copy of any 10 CFR Part 21 reports applicable to your SSCs within the scope of Section XI of the ASME Code that have been identified since the beginning of the last refueling outage.
g) A list of any temporary non-code repairs in service (e.g. pinhole leaks).
h) Please provide copies of the most recent self assessments for the ISI, Welding, and Alloy 600 Programs.
A.2 Boric Acid Corrosion Control Program (BACCP) a) Copy of the procedures that govern the scope, equipment and implementation of the inspections required to identify boric acid leakage and the procedures for boric acid leakage/corrosion evaluation.
b) Please provide a list of leaks (including code class of the components) that have been identified since the last refueling outage and associated corrective action documentation. If during the last cycle, the Unit was shutdown, please provide documentation of containment walk-down inspections performed as part of the BACCP.
c) Please provide a copy of the most recent self-assessment performed for the BACCP.
Enclosure
3 A.3 Additional information related to all ISI activities a) A list with a brief description of ISI and BACCP related issues (e.g., condition reports) entered into your corrective action program since the beginning of the last refueling outage. For example, a list based upon data base searches using key words related to piping or SG tube degradation such as: ISI, ASME Code,Section XI, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping examinations.
b) Please provide names and phone numbers for the following program leads:
ISI contacts (Examination, planning)
Containment Exams Snubbers and Supports Repair and Replacement Program Manager Licensing Contact Site Welding Engineer Boric Acid Corrosion Control Program B. Information to be provided on-site to the inspector at the entrance meeting (April 27, 2009):
B.1 ISI / Welding Programs and Schedule Information a) Updated schedules for ISI/NDE activities, including SG ISI, planned welding activities, and schedule showing contingency repair plans, if available.
b) For ASME Class 1, 2, and 3 welds selected by the inspector from the lists provided from section A of this enclosure, please provide copies of the following documentation for each subject weld:
i) Weld data sheet (traveler) ii) Weld configuration and system location iii) Applicable Code Edition and Addenda for weldment iv) Applicable Code Edition and Addenda for welding procedures v) Applicable weld procedures (WPS) used to fabricate the welds vi) Copies of procedure qualification records (PQRs) supporting the WPS from B.1.b.v vii) Copies of mechanical test reports identified in the PQRs above viii) Copies of the nonconformance reports for the selected welds (If Applicable) ix) Radiographs of the selected welds and access to equipment to allow viewing radiographs (If RT was performed) x) Copies of the preservice examination records for the selected welds.
xi) Copies of welder performance qualifications records applicable to WPS, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS (At least six months prior to date subject work) xii) Copies of NDE personnel qualifications (VT, PT, MT, UT, RT) as applicable Enclosure
4 c) For the ISI related corrective action issues selected by the inspector from section A of this enclosure, provide a copy of the corrective actions and supporting documentation.
d) For the NDE reports with relevant indications on Code Class 1, 2, & 3 systems selected by the inspector from section A above, provide a copy of the examination records, examiner qualification records, and associated corrective action documents.
e) A copy of (or ready access to) most current revision of the ISI Program Manual and Plan for the current Interval.
f) For the NDEs selected by the inspector from section A of this enclosure, provide copy of the NDE procedures used to perform the examinations (including calibration and flaw characterization/sizing procedures). For ultrasonic examination procedures qualified in accordance with ASME Code,Section XI, Appendix VIII, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Also, include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and NDE personnel qualification records.
B.2 Boric Acid Corrosion Control Program (BACCP) a) Please provide boric acid walk down inspection results, an updated list of boric acid leaks identified so far this outage, associated corrective action documentation, and overall status of planned boric acid inspections.
b) Please provide any engineering evaluations completed for boric acid leaks identified since the end of the last refueling outage. Please include a status of corrective actions to repair and/or clean these boric acid leaks. Please specify which known leaks, if any, have remained in service or will remain in service as active leaks.
c) In accordance with NRC inspection procedure 71111.08, the inspector would like to conduct an independent boric acid walk down of the Reactor Building early in the inspection week. Please have knowledgeable BACCP staff available to accompany the inspector during the walk down.
B.3 Codes and Standards a) Ready access to: (i.e. copies provided to the inspector to use for the duration of the inspection at the on-site inspection location, or room number and location where available) i) Applicable editions of the ASME Code (Sections V, IX and XI) for the inservice inspection program and the repair/replacement program.
Enclosure
5 Inspector Contact Information:
Rich C. Chou Reactor Inspector 404-562-4670 rich.chou@nrc.gov Mailing Address:
US NRC Region 2 Attn: Rich C. Chou 61 Forsyth Street SW, Suite 23T85 Atlanta, GA 30303 Enclosure