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Category:Inspection Plan
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 IR 05000266/20220062023-03-0101 March 2023 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2022006 and 05000301/2022006) ML23003A8022023-01-0303 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22256A3182022-09-13013 September 2022 Request for Information for an NRC Quadrennial Comprehensive Engineering Team Inspection Report 05000266/2023010 05000301/2023010 IR 05000266/20220052022-08-26026 August 2022 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2022005 and 05000301/2022005) ML22175A2002022-06-27027 June 2022 Request for Information for an NRC Triennial Heat Exchanger/Sink Performance Inspection and Request for Information: Inspection Report 05000266/2022004: 05000301/2022004 ML22172A2132022-06-22022 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection ML22173A0172022-06-22022 June 2022 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Point Beach Nuclear Plant IR 05000266/20210062022-03-0202 March 2022 Annual Assessment Letter for Point Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2021006 and 05000301/2021006) ML22041B0752022-02-10010 February 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000266/2022002 ML21253A1672021-09-10010 September 2021 Notification of NRC Design Bases Assurance Inspection (Programs) and Initial Request for Information Inspection Report 05000266/2022010 05000301/2022010 IR 05000266/20210052021-09-0101 September 2021 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2021005 and 05000301/2021005) ML21214A2812021-08-0202 August 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21180A2302021-06-29029 June 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2021004 and 05000301/2021004 ML21074A3962021-03-15015 March 2021 Information Request for NRC Triennial Evaluations of Changes, Tests, and Experiments (50.59) Baseline Inspection; Inspection Report 05000266/2021010; 05000301/2021010 IR 05000266/20200062021-03-0404 March 2021 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2020006 and 05000301/2020006) IR 05000266/20200052020-09-0101 September 2020 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2020005 and 05000301/2020005) ML20218A4322020-08-0505 August 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2020004 ML20168A8912020-06-15015 June 2020 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Point Beach Nuclear Plant, Units 1 and 2 IR 05000266/20190062020-03-0303 March 2020 Annual Assessment Letter for Point Beach Nuclear Plants, Units 1 and 2 (Report 05000266/2019006 and 05000301/2019006) IR 05000266/20190052019-08-28028 August 2019 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2019005 and 05000301/2019005) ML19190A1532019-07-0909 July 2019 Ltr. 07/09/19 Point Beach Nuclear Plant, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information; Inspection Report 05000266/2019012; 05000301/2019012 (DRS-G.Hausman) ML19136A1402019-05-15015 May 2019 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Garza) ML19094B1182019-04-0404 April 2019 Ltr. 04/04/19 Point Beach Nuclear Plant, Units 1 and 2 - Request for Information for an NRC Design Bases Assurance Inspection (Program): Implementation of the EQ Program; Inspection Report 05000266/2019013 and 05000301/2019013 (DRS-B.Jose) IR 05000266/20180062019-03-0404 March 2019 Annual Assessment Letter for Point Beach Nuclear Plant (Report 05000266/2018006 and 05000301/2018006) ML19037A3102019-02-0505 February 2019 Ltr. 02/05/19 Point Beach Nuclear Plant, Units 1 and 2 - Information Request for the Cyber-Security Full Implementation Inspection, Notification to Perform Inspection; Inspection Report 05000266/2019412; 05000301/2019412 (DRS-G.Hausman) ML19024A2772019-01-24024 January 2019 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2019001 (DRS-M.Domke) IR 05000266/20180052018-08-28028 August 2018 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2018005 and 05000301/2018005) IR 05000266/20170062018-03-0202 March 2018 Annual Assessment Letter for Point Beach Plant, Units 1 and 2 (Report 05000266/2017006 and 05000301/2017006) IR 05000266/20170052017-08-28028 August 2017 Updated Inspection Plan (Report 05000266/2017005 and 05000301/2017005) ML17088A7242017-03-29029 March 2017 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000266/2017007; 05000301/2017007 IR 05000266/20160062017-03-0101 March 2017 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2016006 and 05000301/2016006) ML17039B0182017-02-0808 February 2017 Information Request to Support Upcoming Temporary Instruction 2515/191 Inspection at Point Beach Nuclear Plant, Units 1 and 2 - Inspection Report 05000266/2017008; 05000301/2017008 IR 05000266/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Point Beach Nuclear Plant Units 1 and 2 (Report 05000266/2016005; 05000301/2016005) IR 05000266/20150062016-03-0202 March 2016 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Inspection Report 05000266/2015006 and 05000301/2015006) IR 05000266/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2015005; 05000301/2015005) ML15131A3132015-05-0808 May 2015 Ltr. 05/08/15 Point Beach Nuclear Plant, Units 1 and 2 - Information Request for an NRC Triennial Permanent Modifications and 10 CFR 50.59 (Mod/50.59) Baseline Inspection 05000266/2015010; 05000301/2015010 (Jjc) ML15124A9012015-05-0101 May 2015 Ltr. 05/01/15 Point Beach Nuclear Plant, Unit 2 - Notification of NRC Inspection and Request for Information (Msh) IR 05000266/20140012015-03-0404 March 2015 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2014001; 05000301/2014001) ML15050A2702015-02-19019 February 2015 Information Request to Support Upcoming Problem Identification and Resolution Inspection at Point Beach Nuclear Plant, Units 1 and 2 ML14245A1662014-09-0202 September 2014 Mid-Cycle Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 IR 05000266/20130012014-03-0404 March 2014 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2013001; 05000301/2013001) ML14038A3472014-02-0606 February 2014 ISI Request for Information ML13246A2212013-09-0303 September 2013 2013 Point Beach MOC Letter Combined ML13172A4072013-06-20020 June 2013 Notification of NRC Triennial Fire Protection Baseline Inspection Request for Information 05000266-13-010; 05000301-13-010 ML13129A1952013-05-0909 May 2013 Ltr 5/9/13 Point Beach Ti 2515-182 Phase 2 Request for Information IR 05000266/20120012013-03-0404 March 2013 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (05000266/2012001; 05000301/2012001) 2024-02-05
[Table view] Category:Letter
MONTHYEARML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection L-2024-001, Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-01-26026 January 2024 Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) ML24005A3242024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0040 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23352A2752024-01-23023 January 2024 Issuance of Amendment Nos. 274 and 276 Regarding Revision to Technical Specification 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-174, Subsequent License Renewal Application - Third Annual Update2023-12-13013 December 2023 Subsequent License Renewal Application - Third Annual Update L-2023-176, Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-159, Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 3 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks and Security Event Notifications Final Rule IR 05000266/20234022023-11-14014 November 2023 Security Baseline Inspection Report 05000266/2023402 and 05000301/2023402 ML23279A0672023-11-0909 November 2023 Issuance of Relief Request I6 RR 02 - Examination of the Unit 2 Steam Generator Feedwater Nozzle Extension to Nozzle Weld Sixth 10 Year Inservice Inspection Program Interval IR 05000266/20230032023-10-16016 October 2023 Integrated Inspection Report 05000266/2023003 and 05000301/2023003 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 L-2023-128, License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program2023-09-19019 September 2023 License Amendment Request to Revise TS 5.5.17, Pre-Stressed Concrete Containment Tendon Surveillance Program ML23243A9102023-09-0606 September 2023 Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors IR 05000266/20235012023-08-29029 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000266/2023501 and 05000301/2023501 ML23208A2262023-08-28028 August 2023 Exemption from the Requirements of 10 CFR 50,46, Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors (EPID L-2022-LLE-0026) - Letter ML23208A0952023-08-28028 August 2023 Issuance of Amendment Nos. 273 and 275 Regarding Revising Licensing Basis to Address Generic Safety Issue-191 and Respond to Generic Letter 2004-02 Using a Risk Informed Approach IR 05000266/20230052023-08-24024 August 2023 Updated Inspection Plan for Point Beach Nuclear Plant (Report 05000266/2023005 and 05000301/2023005) ML23160A0642023-08-21021 August 2023 Issuance of Amendment Nos. 272 and 274 Regarding Revision to Use Beacon Power Distribution Monitoring System L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update ML23221A0522023-08-0909 August 2023 Confirmation of Initial License Examination, March 2024 L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 ML23201A0872023-08-0303 August 2023 Audit Plan in Support of Review of License Amendment L-2023-089, Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections2023-07-24024 July 2023 Refueling Outage Owner'S Activity Report (OAR-1) Unit 2 for Inservice Inspections IR 05000266/20230022023-07-18018 July 2023 Integrated Inspection Report 05000266/2023002 and 05000301/2023002 IR 05000266/20234012023-07-13013 July 2023 Public-Point Beach Nuclear Plant-Security Baseline Inspection Report 05000266/2023401; 05000301/2023401; Independent Spent Fuel Storage Security Inspection Report 07200005/2023401 L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III L-2023-088, 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval2023-06-27027 June 2023 10 CFR 50.55a Requests, Relief Requests I6-RR-1, I6-RR-2, and I6-RR-3 Sixth Ten-Year Inservice Inspection Program Interval ML23171B1062023-06-21021 June 2023 Info Meeting with a Question and Answer Session to Discuss NRC 2022 EOC Plant Performance Assessment of Ptbh, Units 1 and 2 ML23163A2422023-06-13013 June 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000266/2023004 L-2023-075, Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-022023-06-0909 June 2023 Response to Request for Additional Information (RAI) Regarding Exemption Request, License Amendment Request and Revised Response in Support of a Risk-Informed Resolution of Generic Letter 2004-02 L-2023-073, Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response2023-06-0101 June 2023 Subsequent License Renewal Application, Second Annual Update Request for Additional Information Set 1 Response ML23103A1332023-06-0101 June 2023 Issuance of Amendment Nos. 271 and 273 Regarding Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal ML23118A1762023-05-0404 May 2023 Audit Summary for License Amendment Request Regarding Risk-Informed Approach for Closure of Generic Safety Issue 191 IR 05000266/20230012023-05-0101 May 2023 Integrated Inspection Report 05000266/2023001 and 05000301/2023001 ML23114A1222023-04-25025 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-2023-058, 2022 Annual Monitoring Report2023-04-10010 April 2023 2022 Annual Monitoring Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-02-05
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 February 6, 2014 Mr. Eric McCartney Site Vice President NextEra Energy Point Beach, LLC 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNIT 2 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. McCartney:
On March 17, 2014, the U. S. Nuclear Regulatory Commission (NRC) will begin the Baseline Inservice Inspection, Inspection Procedure (IP) 71111.08. This on-site inspection is scheduled to be performed March 17, 2014 through April 4, 2014.
Experience has shown that this inspection is resource intensive both for the NRC inspector and your staff. In order to minimize the impact to your on-site resources and to ensure a productive inspection for both sides, we have enclosed a request for documents needed for this inspection. These documents have been divided into two groups. The first group identifies information necessary to ensure that the inspector is adequately prepared. The second group identifies the information the inspector will need upon arrival at the site. It is important that all of these documents are up-to-date and complete, to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection.
We have discussed the schedule for inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. R. Clark, of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector Ms. E. Sanchez Santiago at 630 829-9715 or via e-mail at elba.sanchezsantiago@nrc.gov.
This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number.
E. McCartney In accordance with 10 CFR 2.390 of the NRC's "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 System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-266; 50-301;72-005 License Nos. DPR-24; DPR-27
Enclosure:
Inservice Inspection Document Request w/Enclosure (Information for Preparation Week and Information Available On-site During Inspection) cc w/encl: Distribution via ListServ'
INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: March 17, 2014, through April 4, 2014 Inspection Procedures: Inspection Procedure 71111-08, Inservice Inspection Lead Inspector: Elba Sanchez Santiago, DRS (630) 829-9715 elba.sanchezsantiago@nrc.gov A. Information for the In-Office Preparation Week The following information is requested as an (electronic copy CD ROM if possible) by March 10, 2014, to facilitate the selection of specific items that will be reviewed during the on-site inspection week. The inspector will select specific items from the information requested below and a list of additional documents needed on-site from your staff. We request that the specific items selected from the lists be available and ready for review on the first day of inspection. The following information is applicable to Unit 2 unless otherwise indicated. If you have any questions regarding this information, please call the inspector as soon as possible.
- 1. For the upcoming outage, a detailed schedule and description of:
- a. non-destructive examinations (NDE) planned for Class 1 and 2 Systems and containment, performed as part of your ASME Code Inservice Inspection (ISI)
Program (include edition and addenda of Code committed to), and NDE examinations planned for other systems performed as part of a Risk-Informed (RI)-ISI Program, or other augmented inspection programs (e.g., ASME Code Case N-770-1 examination of dissimilar metal welds and examinations to meet an industry initiative). For each weld examination, include the weld identification number, description of weld (component name), category, class, type of exam and procedure number, and date of examination;
- b. reactor vessel upper head examinations required by 10 CFR 50.55a(g)(6)(ii)(D) and Code Case N-729-1;
- c. steam generator (SG) tube inspection and repair activities for the upcoming outage or SG secondary side examinations 1; and
- d. welding on Code Class 1, 2, or 3 components.
- 2. A copy of the NDE procedures and welding procedures used to perform the activities identified in Item A.1 (including NDE Calibration and Flaw 1
Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur and no further information is required for the items identified above requesting SG related information.
1 Enclosure
Characterization/Sizing Procedures and Welding Procedure Qualification Records).
For ultrasonic examination procedures qualified in accordance with Appendix VIII, of Section XI of the ASME Code, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets).
- 3. A copy of ASME Section XI, Code Relief Requests applicable to the examinations identified in Item A.1. This would include the NRC approved Relief Request for implementing a risk-informed ISI Program (if applicable).
- 4. A copy of the 10-year ISI Program showing those required exams scheduled to be performed this outage, and those which have been completed.
- 5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye penetrant), which have identified relevant indications on Code Class 1 and 2 Systems since the beginning of the last refueling outage.
- 6. List with short description 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 and identify the system, weld number, and reference applicable documentation (e.g., NIS-2 forms with definitions of system and component acronyms).
- 7. If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the inspection period, provide a detailed description of the welds to be examined, and the extent of the planned examination.
- 8. List with description of ISI and SG related issues such as piping or SG tube degradation or damage (e.g., cracks, wall thinning, wear, MIC) or errors identified during piping/SG tube examinations that have been entered into your corrective action system since the beginning of the last refueling outage. Also, include a list of corrective action records associated with foreign material introduced/identified in the reactor vessel, primary coolant system, steam generator or feed systems since the beginning of the last refueling outage.
- 9. Copy of any 10 CFR Part 21 reports applicable to your structures systems or components within the scope of Section XI of the ASME Code that have been identified since the beginning of the last refueling outage.
- 10. Copy of SG history documentation given to vendors performing eddy current (ET) testing of the SGs during the upcoming outage. 1.
- 11. Copy of procedure containing screening criteria used for selecting tubes for in-situ pressure testing and the procedure to be used for in-situ pressure testing. 1 12.
Copy of previous outage SG tube operational assessment completed following ET of the SGs. 1 1
Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur and no further information is required for the items identified above requesting SG related information.
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- 13. Copy of the document defining the planned SG ET scope (e.g., 100 percent of unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion transition regions with rotating probe) and identify the scope expansion criteria, which will be applied. Also identify and describe any deviations in this scope or expansion criteria from the EPRI Guidelines.1
- 14. Copy of the document describing the ET acquisition equipment to be applied including ET probe types. Also identify the extent of planned tube examination coverage with each probe type (e.g., rotating probe - 0.080 inches, 0.115 inches pancake coils and mid-range + point coil applied at the top-of-tube-sheet plus 3 inches to minus 12 inches).
- 15. Provide procedures with guidance/instructions for identifying (e.g., physically locating the tubes that require repair) and plugging SG tubes. 1
- 16. Identify and quantify any SG tube leakage experienced during the previous operating cycle. Also provide documentation identifying which SG was leaking and corrective actions completed or planned for this condition.
- 17. Copy of current calculations for EDY, and RIY as defined in Code Case N-729-1 that establish the volumetric and visual examination frequency for the reactor vessel head and J-groove welds.
- 18. Point of contact information (name and site number) for the following activities:
- a. Inservice Inspection - Site and vendor leads;
- b. Boric Acid Inspections and Evaluations;
- c. Reactor Vessel Head Inspection - Site and vendor leads; and
- d. SG Inspection - Site and vendor leads.
B. On-Site Information to be Provided to the Inspector on the First Day of the Inspection (e.g., Following the Entrance Meeting). Please Provide Hard Copies (e.g., Paper Records) of the Following Documents.
- 1. For welds selected by the inspector from Items A.1.d and A.6 above, provide copies of the following documents:
- a. Document of the weld number and location (e.g., system, train, branch);
- b. Document with a detail of the weld construction (e.g., drawing);
- c. Applicable Code Edition and Addenda for construction of the weldment (e.g.,
B31.1 or ASME Section III);
- d. Applicable Code Edition and Addenda for weld procedure qualification;
- e. Applicable weld procedures (WPS) used to fabricate the welds; 1
Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur and no further information is required for the items identified above requesting SG related information.
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- f. Copies of procedure qualification records (PQRs) supporting the WPS;
- g. Copies of welders performance qualification records (WPQ);
- h. Copies of mechanical test reports identified in the PQRs above;
- i. Copies of the nonconformance reports for the selected welds;
- j. Access to radiographs and equipment to view radiographs of the selected welds; and
- k. Copies of the pre-service examination records for the selected welds.
- 2. For the ISI related corrective action issues selected by the inspector from Item A.8 above, provide a copy of the corrective actions and supporting documentation.
- 3. For the non-destructive examination reports with relevant indications on Code Class 1 and 2 Systems selected by the inspector from Item A.5 above, provide a copy of the examination records and associated corrective action documents.
Updated schedules for Item A.1 (including schedule showing contingency repair plans if available).
- 4. Copy of the procedures which govern the scope, equipment used, and implementation of the inspections required to identify boric acid leakage from systems and components above the vessel head.
- 5. Copy of:
- a. Engineering evaluations/assessments of boric acid related deposits and associated wastage or corrosion for safety significant components; and
- b. Corrective action records for coolant leakage including boric acid deposits on safety-related components identified since the beginning of the last refueling outage.
- 6. Copy of the plant procedures used to perform inspections to identify reactor coolant system leaks or boric acid deposits and the procedures for resolution of leaks or boric acid deposits.
- 7. Fabrication Drawings (D size) of the reactor vessel welds (including vessel head J-groove welds) if any are to be examined during the outage. Also provide any drawings used by NDE vendors to locate these welds.
- 8. Copy of the documents which demonstrate that the procedures to be used for volumetric examination of the reactor vessel head penetration J-groove welds were qualified by a blind demonstration test in accordance with 10 CFR 50.55a(g)(6)(ii)(D).
- 9. Copy of volumetric, surface and visual examination records for the prior inspection of the reactor vessel head and head penetration J-groove welds.
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- 10. Provide a copy of the EPRI Examination Technique Specification Sheets and vendor documents, which support qualification of the ET probes to be used during the upcoming SG tube inspections.1
- 11. Provide a copy of the guidance to be followed if a loose part or foreign material is identified in the SGs. 1
- 12. Identify the types of SG tube repair processes which will be implemented for defective SG tubes (including any NRC reviews/evaluation/approval of this repair process). Provide the flaw depth sizing criteria to be applied for ET indications identified in the SG tubes. 1
- 13. Copy of document describing actions to be taken if a new SG tube degradation mechanism is identified. 1
- 14. Provide document which defines the scope of SG secondary side examinations (if any are planned) and identify site specific operational history related to degradation of SG secondary side components (if any).
- 15. Provide procedures with guidance/instructions for identifying (e.g., physically locating the tubes that require repair) and plugging SG tubes.1
- 16. Provide copies of the following standards at the on-site NRC inspection location for the duration of the inspection:
- a. Sections V, IX and XI of the ASME Code with Editions applicable to the Inservice Inspection Program and the repair/replacement program;
- b. Copy of the performance demonstration initiative (PDI) generic procedures with the latest applicable revisions that support site qualified ultrasonic examination of piping welds and components (e.g., PDI-UT-1, PDI-UT-2, PDI-UT-3, PDI-UT-10 etc.);
- c. EPRI and industry standards referenced in the site procedures used to perform the SG tube eddy current examination, which includes EPRI documents: TR-107621-R1, Steam Generator Integrity Assessment Guidelines, TR-107620-R1, Steam Generator In-Situ Pressure Test Guidelines, Steam Generator Management Program: Steam Generator Integrity Assessment Guidelines, Part 10, and 1003138, Pressurized Water Reactor Steam Generator Examination Guidelines1; and
- d. Boric Acid Corrosion Guidebook Revision 1 - EPRI Technical Report 1000975.
- 17. Provide training (e.g., Scaffolding, Fall Protection, FME) if required to access the non-destructive examinations selected by the inspector for observation.
If you have questions regarding the information requested, please contact the lead inspector.
1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur and no further information is required for the items identified above requesting SG related information.
5
E. McCartney In accordance with 10 CFR 2.390 of the NRC's "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 System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-266; 50-301;72-005 License Nos. DPR-24; DPR-27
Enclosure:
Inservice Inspection Document Request w/Enclosure (Information for Preparation Week and Information Available On-site During Inspection) cc w/encl: Distribution via ListServ' DISTRIBUTION:
Ernesto Quinones RidsNrrDorlLpl3-1 Resource RidsNrrPMPointBeach RidsNrrDirsIrib Resource Cynthia Pederson Darrell Roberts Steven Orth Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley DOCUMENT NAME: G:\DRSIII\DRS\Ltr 020614 Point Beach ISI Request for Information.docx Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII NAME ESanchezSantiago:ls DHills DATE 02/06/14 02/06/14 OFFICIAL RECORD COPY