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Category:Letter
MONTHYEARIR 05000348/20240022024-08-12012 August 2024 – Integrated Inspection Report 05000348-2024002 and 05000364-2024002 and Exercise of Enforcement Discretion ML24215A3772024-08-0707 August 2024 2024 Farley Requal Inspection Corporate Notification Letter ML24201A2032024-08-0101 August 2024 Request for Withholding Information from Public Disclosure for Joseph M. Farley Nuclear Plant, Units 1 and 2, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions ML24200A1392024-07-25025 July 2024 Regulatory Audit in Support of Review of the License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature ML24199A2072024-07-24024 July 2024 TS 3-6-5 LAR - Individual Notice Transmittal Letter and NSHC - Rev 1 (1) - Letter NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) ML24184A0452024-07-0202 July 2024 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML24178A3762024-07-0101 July 2024 Nonacceptance of Requested Licensing Action License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, Using Risk-Informed Process for Evaluations NL-24-0230, Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000348/20240012024-04-24024 April 2024 Integrated Inspection Report 05000348/2024001 and 05000364/2024001 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions IR 05000348/20240102024-04-16016 April 2024 NRC Inspection Report 05000348/2024010 and 05000364/2024010 IR 05000348/20240112024-04-12012 April 2024 Fire Protection Team Inspection Report 05000348/2024011 and 05000364/2024011 NL-24-0134, Renewed National Pollutant Discharge Elimination System (NPDES) Permit2024-04-12012 April 2024 Renewed National Pollutant Discharge Elimination System (NPDES) Permit NL-24-0088, Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency2024-04-0505 April 2024 Application to Revise Technical Specifications Regarding Change to Containment Spray Nozzle Test Frequency NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information ML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding 2024-08-07
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24179A1242024-06-27027 June 2024 ISFSI Request for Information (2024) ML24143A0412024-05-28028 May 2024 Supplemental Information Needed for Using the Risk-Informed Process for Evaluation for the LAR to Change Technical Specification 3.6.5, Containment Air Temperature, Actions ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23243A9952023-08-31031 August 2023 Request for Baseline RP Inspection ML23236A0022023-08-22022 August 2023 NRR E-mail Capture - Request for Additional Information - Farley, Units 1&2, Emergency TS 3.6.5 LAR ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23095A0832023-04-0505 April 2023 NRR E-mail Capture - for Your Action - RAI - Farley - Containment Isolation Valves, Surveillance Requirement 3.6.3.5 LAR (L-2022-LLA-0189) ML23086A0232023-03-24024 March 2023 NRR E-mail Capture - for Your Action - Draft RAIs - Farley Surveillance Requirement (SR) 3.6.3.5 License Amendment Request (LAR) (L-2022-LLA-0189) ML23003A8092023-01-0303 January 2023 NRR E-mail Capture - for Your Action - RAI - Farley - ISI Alternative FNP-ISI-ALT-05-05 (L-2022-LLR-0068) ML22334A1482022-11-30030 November 2022 NRR E-mail Capture - for Your Action - RAI - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML22123A1802022-05-0303 May 2022 NRR E-mail Capture - Correction - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22123A1782022-05-0303 May 2022 NRR E-mail Capture - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22112A0892022-04-22022 April 2022 NRR E-mail Capture - Draft RAIs for Farley LAR Re. TS 5.5.17 ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML21321A3772021-11-16016 November 2021 NRR E-mail Capture - RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21321A3752021-11-10010 November 2021 NRR E-mail Capture - Draft RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21127A1132021-05-0606 May 2021 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000348/2021012 and 05000364/2021012 ML21012A3242021-01-12012 January 2021 NRR E-mail Capture - Request for Additional Information - Farley, 1 and 2 - Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20351A4042020-12-16016 December 2020 NRR E-mail Capture - Draft RAIs for Farley 50.69 (ML20170B114) ML20293A0752020-10-14014 October 2020 NRR E-mail Capture - RAIs for SNC Fleet EP LAR (L-2020-LLA-0150 and L-2020-LLA-0151) ML20254A1912020-09-10010 September 2020 004 Radiation Safety Baseline Inspection Information Request ML20174A5812020-06-22022 June 2020 Notification of Inspection and Request for Information ML20149K6252020-05-27027 May 2020 NRR E-mail Capture - RAIs for SNC Fleet Fire Protection Exemption Requests ML20149K4392020-05-21021 May 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate RAI Sfnb RAI No. 2 ML20121A1472020-04-29029 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Measurement Uncertainty Recapture Power Uprate Follow-up RAI Emib No. 1 ML20115E3922020-04-24024 April 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding TS 3.3.1 and TS 3.3.7 License Amendment Request ML20084G5272020-03-23023 March 2020 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Measurement Uncertainty Recapture Power Uprate ML20055E9752020-02-28028 February 2020 Request for Additional Information Update the Spent Fuel Pool Criticality Safety Analysis (EPID L-2019-LLA-0212) Non-Proprietary Version ML19150A1022019-05-29029 May 2019 Request for Additional Information Regarding Relief Request FNP-ISI-05-04, Version 1.0 (L-2019-LLR-0020) ML19066A0422019-03-0707 March 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-03, Version 1.0 ML19056A2142019-02-25025 February 2019 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Relief Request FNP-ISI-RR-02, Version 1.0 ML19052A1712019-02-20020 February 2019 Rad Safety Inspection Document Request ML18355A4772019-01-0404 January 2019 Request for Additional Information Revise TS 5.2.2.g and Update Emergency Plan Minimum On-Shift Staff Tables ML18337A4032018-12-0606 December 2018 Request for Additional Information Revise Technical Specification 5.2.2.G and Updating Emergency Plan Minimum On-Shift Staff Tables ML18239A1542018-08-24024 August 2018 Emergency Preparedness Inspection and Request for Information ML18087A1462018-05-0101 May 2018 Request for Additional Information TS 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML18058A0812018-02-27027 February 2018 Enclosurequest for Additional Information(Rai for Review of Southern Nuclear Operating Company'S Decommissioning Funding Plan Updates for Joseph M. Farley,Unit 1 and 2;Edwin I. Hatch,Units 1 and 2; and Vogtle Electric Generating Plant, Unit ML18058B1522018-02-27027 February 2018 Emailed RP RFI 2018-02 ML17360A0552017-12-20020 December 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 7 to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program (CAC Nos. MF8844, MF8845; EPID No. L-2016-LLA-0015) ML17306A0872017-11-0808 November 2017 Request for Additional Information Regarding the Decommissioning Funding Status Reports (EPID L-LRO-2017-0008) ML17219A0012017-08-0303 August 2017 NRR E-mail Capture - Joseph M. Farley, Units 1 and 2 - Supplemental RAI Request No. 5(b), 5(c), and 6 Related to License Amendment Request to Revise TS 5.5.17 Containment Leakage Rate Testing Program ML17194A7872017-07-21021 July 2017 Request for Additional Information ML17095A4152017-04-17017 April 2017 Request for Additional Information ML17065A2012017-03-24024 March 2017 Request for Additional Information ML17069A2792017-03-16016 March 2017 Unit 2, Request for Additional Information ML17058A1132017-03-15015 March 2017 Request for Additional Information ML17061A0792017-03-0202 March 2017 NRR E-mail Capture - Joseph M. Farley Nuclear Plant, Units 1 and 2 - Request for Additional Information Regarding Alternative Request RR-PR-03 ML17010A0142017-01-19019 January 2017 Request for Additional Information Regarding License Aging Management Program ML16243A1992016-08-30030 August 2016 Notification of Inspection and Request for Information ML16222A2952016-08-29029 August 2016 Request for Additional Information 2024-06-27
[Table view] |
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February 22, 2007Southern Nuclear Operating Company, Inc.ATTN:Mr. J. Randy JohnsonVice PresidentP. O. Box 1295 Birmingham, AL 35201
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Johnson:
From April 16 - 27, 2007, the NRC will perform the baseline inservice inspection (ISI) at theFarley Nuclear Plant, Unit 2 (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 onsite 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 understandthat our regulatory contacts for this inspection will be Anna Cook and Danny Cordes of your ISI 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 lead inspector Barry Miller at (404) 562-4632 (bwm1@nrc.gov).In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and itsenclosure will be available electronically for public inspection in the NRC PublicDocument Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).Sincerely,\\RA by R. Carrion Acting For\\George T. Hopper, ChiefEngineering Branch 3 Division of Reactor SafetyDocket No. 50-364License No. NPF-8
Enclosure:
See next page SNC2
Enclosure:
Inservice Inspection Document Requestcc w/encl:B. D. McKinney, Licensing Services Manager, B-031 Southern Nuclear Operating Company, Inc.
Electronic Mail DistributionL. M. Stinson,Vice President,Fleet Operations Support-Farley Plant Southern Nuclear Operating Company, Inc.
Electronic Mail DistributionJ. T. GasserExecutive Vice President Southern Nuclear Operating Company, Inc.
Electronic Mail DistributionBentina C. TerrySouthern Nuclear Operating Company, Inc.
Bin B-022 P. O. Box 1295 Birmingham, AL 35201-1295State Health OfficerAlabama Department of Public Health RSA Tower - Administration 201 Monroe St., Suite 700 P. O. Box 303017 Montgomery, AL 36130-3017M. Stanford BlantonBalch and Bingham Law Firm P. O. Box 306 1710 Sixth Avenue North Birmingham, AL 35201William D. OldfieldQuality Assurance Supervisor Southern Nuclear Operating Company Electronic Mail Distribution
_______ML070530475
__OFFICERII:DRSRII:DRSSIGNATUREBWM1RPC1 ForNAMEBMillerGHopperDATE2/22/20072/22/2007 E-MAIL COPY? YESNO YESNO YESNO YESNO YESNO YESNO YESNO INSERVICE INSPECTION DOCUMENT REQUESTInspection Dates:April 16 - 27, 2007Inspection Procedures:IP 71111.08 "Inservice Inspection (ISI) Activities" Inspector:Barry Miller, Reactor Inspector A.Information Requested for the In-Office Preparation WeekThe following information should be sent to the Region II office in hard copy orelectronic format (CD preferred), in care of Barry Miller by April 9, 2007, 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 requesteddocumentation electronically if possible. If requested documents are large and onlyhard copy formats are available, please inform the inspector and provide subjectdocumentation during the first day of the onsite inspection. If you have any questionsregarding this information request, please call the inspector as soon as possible.A.1ISI / Welding Programs and Schedule Informationa)A detailed schedule (including preliminary dates) of:i) Nondestructive examinations (NDEs) planned for Class 1 & 2 systemsand containment, performed as part of your ASME Section XI, Risk Informed (if applicable), and augmented ISI Programs during the upcoming outage.ii) Reactor pressure vessel head (RPVH) examinations planned for theupcoming outage, if any.iii)Examinations planned for Alloy 82/182/600 components that are notincluded in the Section XI scope. (If applicable)iv)Examinations planned as part of your Boric Acid Corrosion ControlProgram (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))b)A copy of ASME Section XI Code Relief Requests and associated NRC SafetyEvaluations applicable to the examinations identified above. c)A list of NDE reports (ultrasonic, radiography, magnetic particle, dye penetrant,visual VT-1, VT-2, and VT-3) which have identified recordable indications 2(geometric or flaw) on Code Class 1 & 2 systems since the beginning of the lastrefueling outage. The list of NDE reports should include a brief description of the SSC where the recordable indication was identified.d)A list with a brief description (e.g. system, material, pipe size, weld number, andNDE performed) of the welds in Code Class 1 and 2 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. e)If reactor vessel weld examinations required by the ASME Code are scheduledto 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 ofSection 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.2Reactor Pressure Vessel Upper Head (RPVUH)
Not applicableA.3Boric Acid Corrosion Control Program (BACCP)a) Copy of the procedures that govern the scope, equipment and implementation ofthe 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 havebeen 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.
3A.4Steam Generator (SG) Inspectionsa)A detailed schedule of:i) SG tube inspection, data analyses, and repair activities for the upcomingoutage. (If occurring)ii) SG secondary side inspection activities for the upcoming outage. (Ifoccurring)b)Please provide a copy of your SG ISI Inspection Program and Plan. Pleaseinclude a copy of the Operational Assessment from last outage, and a copy of the following documents as they become available: i)Degradation Assessmentii)Condition Monitoring Assessment c)If you are planning on modifying your Technical Specifications such that they areconsistent with TSTF-449, please provide copies of your correspondence with the NRC regarding deviations from the STS.d)Copy of SG history documentation given to vendors performing eddy current(ET) testing of the SGs during the upcoming outage.e)Copy of SG Eddy Current Data Analyst Guidelines, and Site Validated EddyCurrent Technique. Additionally, please provide a copy of EPRI Appendix H Eddy Current Technique Qualification Records.f)Identify and quantify any SG tube leakage experienced during the previousoperating cycle. Also provide documentation identifying which SG was leaking and corrective actions completed or planned for this condition. (If applicable)g) Provide past history of the condition and issues pertaining to the secondary sideof the steam generators (including items such as loose parts, fouling, top of tube sheet condition, crud removal amounts, etc.)h)Please provide copies of your most recent self-assessments of the SGmonitoring, loose parts monitoring, and secondary side water chemistry control programs.i)Please also indicate where the primary, secondary, and resolution analyses arescheduled to take place.j)Please provide a summary of the scope of the SG ISI examinations, includingexamination methods such as Bobbin, Rotating Pancake, or Plus Points, and the percentage of tubes to be examined. *Do not provide these documentsseparately if already included in other information requested.
4A.5Additional information related to all ISI activitiesa) A list with a brief description of ISI, BACCP, and SG ISI related issues (e.g.,condition reports) entered into your corrective action program since the beginning of the last refueling outage (for Units 1 and 2). 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/SG tube 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 SG Inspection Activities (site lead and vendor contact)B.Information to be provided onsite to the inspector at the entrance meeting(April 16, 2007):B.1ISI / Welding Programs and Schedule Informationa)Updated schedules for ISI/NDE activities, including SG ISI, planned weldingactivities, and schedule showing contingency repair plans, if available.b)For ASME Class 1 and 2 welds selected by the inspector from the lists providedfrom 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 WPSfrom B.1.b.vvii)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 allowviewing 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 5prior to date subject work)xii)Copies of NDE personnel qualification (VT, PT, UT, RT), as applicable.c)For the ISI-related corrective action issues selected by the inspector from sectionA of this enclosure, provide a copy of the corrective actions and supporting documentation.d)For the NDE reports with recordable indications on Code Class 1 & 2 systemsselected 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 Manualand Plan for the current Interval. f)For the NDEs selected by the inspector from section A of this enclosure, providea 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.2Reactor Pressure Vessel Upper Head (RPVUH)
Not applicableB.3Boric Acid Corrosion Control Program (BACCP)a)Please provide boric acid walkdown inspection results, an updated list of boricacid 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 leaksidentified 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 liketo conduct an independent boric acid walkdown of the Reactor Building early in the inspection week. Please have knowledgeable BACCP staff available to accompany the inspector during the walkdown.
6B.4Steam Generator (SG) Inspectionsa)Copies of the Examination Technique Specification Sheets (ETSSs) andassociated justification for any revisions.b)Copy of the guidance to be followed if a loose part or foreign material is identifiedin the SGs.c)Please provide a copy of the ET procedures used to perform the SG ISI(specifically calibration and flaw characterization/sizing procedures, etc.). Also include documentation for the specific equipment to be used.d)Please provide copies of your responses to NRC and industry operatingexperience communications such as Generic Letters, Information Notices, etc.
(As applicable to SG inspections) *Do not provide these documents separately ifalready included in other information requested such as the degradation
assessment.e)List of corrective action documents generated by the vendor and/or site withrespect to SG inspection activities.B.5Codes and Standards a)Ready access to: (i.e., copies provided to the inspector to use for the duration ofthe inspection at the onsite inspection location, or room number and location where available)i) Applicable editions of the ASME Code (Sections V, IX, and XI) for theinservice inspection program and the repair/replacement program. ii) EPRI and industry standards referenced in the procedures used toperform the SG tube eddy current examination.Inspector Contact Information
- Barry MillerReactor Inspector 404-562-4632 bwm1@nrc.gov Mailing Address
- US NRC Region 2 Attn: Barry Miller 61 Forsyth Street SW, Suite 23T85 Atlanta, GA 30303