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Category:E-Mail
MONTHYEARML23355A2202023-12-21021 December 2023 Radiation Protection Inspection - Inspection Report 2024-01 ML23332A0042023-11-27027 November 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Revised Alternative 0-ISI-47 ML23319A1662023-11-0202 November 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant, Exemption Request Related to 10 CFR 37.11(c)(2) ML23243A9892023-08-29029 August 2023 Inspection Information Request ML23208A0872023-07-26026 July 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry 1, 2, and 3, Alternative Request 0-ISI-47 to Use an Alternative to ASME Code, Section XI, Examination Requirements for Examination Categories B-N-1 and B-N-2 ML23124A0082023-05-0303 May 2023 NRR E-mail Capture - Request for Additional Information Related to Proposed Alternative Requests for the 5th 10-Year Inservice Testing Interval for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML23117A0702023-04-26026 April 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, 1, 2, and 3, License Amendment Request to Revise Tech Specs Surveillance Requirements 3.4.3.2 and 3.5.1.11 Safety Relief Valves (BFN TS-540) ML23097A0172023-04-0606 April 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Adopt TSTF-566-A and TSTF-580-A, Revision 1 ML23073A2082023-03-10010 March 2023 TVA Intentions on EA-22-122 - Choice Letter Response Email Message ML23073A2072023-03-10010 March 2023 TVA Intentions on EA-22-122 - Choice Letter Response Email Message - NRC Acknowledgement ML23075A0502023-03-10010 March 2023 TVA Intentions on EA-22-122 - Choice Letter Response Email Message and TVA Intentions on EA-22-122 - Choice Letter Response Email Message -- NRC Acknowledgement ML23052A0792023-02-21021 February 2023 NRR E-mail Capture - Acceptance Review for Browns Ferry and Sequoyah License Amendment Request to Adopt TSTF-541 ML23041A0022023-02-0909 February 2023 NRR E-mail Capture - Request for Additional Information Related to TVA Alternative Request BFN-0-ISI-32 (CNL-22-025) ML23013A1512023-01-13013 January 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Use Later ASME OM Code Edition and Alternative Requests BFN-IST-01 Through BFN-IST-05 ML23013A0382023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML23017A0062023-01-12012 January 2023 Initial Information Request Inspection Report: 2023001 ML23013A0362023-01-12012 January 2023 NRR E-mail Capture - (External_Sender) State Consultation for Alabama - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML23004A0352023-01-0404 January 2023 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Delete TS 3.6.3.1 by Adopting TSTF-478 ML22348A0972022-12-14014 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-529, Revision 4 (L-2022-LLA-0088) ML22348A0442022-12-13013 December 2022 NRR E-mail Capture - State Consultation - Browns Ferry, Units 1, 2 and 3; Sequoyah, Units 1 and 2; and Watts Bar, Units 1 and 2, License Amendment Request to Adopt TSTF-554-A, Revision 1 (L-2022-LLA-0100) ML22304A1852022-10-31031 October 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Remove Site Acreage Description from TS 4.1 ML22299A0292022-10-26026 October 2022 NRR E-mail Capture - Request for Additional Information for Relief Request BFN-2-ISI-003 Re Weld Examination Coverage ML22292A2722022-10-19019 October 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Adopt TSTF-505 and TSTF-439 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22265A1492022-09-21021 September 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Alternative Request BFN-0-ISI-32 ML22259A0392022-09-14014 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 5 ML22259A0382022-09-14014 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 4 ML22259A0372022-09-13013 September 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 3 ML22238A0672022-08-24024 August 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions - Part 2 ML22238A0652022-08-19019 August 2022 NRR E-mail Capture - Browns Ferry TSTF-505 Audit Questions ML22215A2752022-08-0303 August 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-554 ML22208A2172022-07-15015 July 2022 NRR E-mail Capture - Request for Additional Information Related to TVA Relief Request BFN-21-ISI-02 (CNL-21-081) ML22194A8762022-07-13013 July 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Adopt TSTF-529 ML22173A1682022-06-21021 June 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Unit 2, Relief Request BFN-2-ISI-003 ML22168A0802022-06-17017 June 2022 NRR E-mail Capture - Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22160A4742022-06-0303 June 2022 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Additional Information Re LAR to Use Advanced Framatome Methodologies in Support of Atrium 11 Fuel ML22146A3342022-05-25025 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, Relief Requests (EPID L-2022-LLR-0045 - 0047) ML22168A0392022-05-13013 May 2022 NRR E-mail Capture - Draft Request for Confirmation of Information and Additional Information Related to Tva'S Request to Use Control Bay Chiller Cross-Tie ML22144A1002022-05-12012 May 2022 NRR E-mail Capture - Request for Additional Information Related to Tva'S Request to Revised the TVA Plants' Radiological Emergency Plans ML22131A1692022-05-0303 May 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, License Amendment Request to Adopt TSTF-505 and TSTF-439 ML22091A1942022-03-0808 March 2022 2022 BFN POV Inspection Information Request ML22055A0772022-02-22022 February 2022 NRR E-mail Capture - Results of NRC SUNSI Review of Browns Ferry Nuclear Plant, Units 1, 2, and 3, Updated Final Safety Analysis Report, Amendment 29 ML22047A1612022-02-16016 February 2022 NRR E-mail Capture - Request for Additional Information Regarding Tva'S Request to Expand the SFP Criticality Safety Analysis for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML22038A1882022-02-0404 February 2022 NRR E-mail Capture - Acceptance Review Results for TVA Fleet License Amendment Request to Revise the TVA Radiological Emergency Plan ML22032A0322022-01-27027 January 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Unit 2, Alternative Request BFN-21-ISI-02 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22010A0282022-01-0606 January 2022 NRR E-mail Capture - Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Adopt TSTF-205-A, Rev. 3 and TSTF-563-A, and Rescind the Consolidation of Several Surveillance Requirements ML21349A2262021-12-15015 December 2021 NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, License Amendment Request to Revise TS 3.8.7 for Installation of the Control Bay Chiller Cross-Tie ML21343A4212021-12-0909 December 2021 NRR E-mail Capture - Acceptance Review Results for Watts Bar Nuclear Plant, Units 1, 2, and 3, License Amendment Request to Revise TS 3.8.7 for Installation of the Control Bay Chiller Cross-Tie ML21334A3012021-11-30030 November 2021 NRR E-mail Capture - Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Acceptance of License Amendment Request Regarding Adoption of TSTF-568-A 2023-08-29
[Table view] Category:Inspection Plan
MONTHYEARIR 05000259/20230052023-08-29029 August 2023 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2023005, 05000260/2023005 and 05000296/2023005 IR 05000259/20220062023-03-0101 March 2023 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022006, 05000260/2022006 and 05000296/2022006 ML23020A0602023-01-20020 January 2023 Long Term Steam Dryer Inspection Plan IR 05000259/20220052022-08-30030 August 2022 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 Report 05000259/2022005, 05000260/2022005 and 05000296/2022005 ML22210A1342022-07-20020 July 2022 Requalification Inspection Notification Letter ML22174A2722022-06-24024 June 2022 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000259/20224012022-03-0808 March 2022 Information Request for the Cyber-Security Baseline Inspection Notification to Perform Inspection 05000259/2022401; 05000260/2022401; 05000296/2022401 ML22091A1942022-03-0808 March 2022 2022 BFN POV Inspection Information Request IR 05000259/20210062022-03-0202 March 2022 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 (Report No. 05000259/2021006, 05000260/2021006 and 05000296/2021006 ML22025A4132022-01-25025 January 2022 RP Inspection Doc Request ML22018A0292022-01-18018 January 2022 Region 2 RFI - 2022 Program Inspections ML21343A4232021-12-0909 December 2021 Notification of an NRC Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000259/2022010, 05000260/2022010, and 05000296/2022010) and Request for Information (RFI) IR 05000259/20210052021-08-23023 August 2021 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2, and 3- Report Nos. 05000259/2021005, 05000260/2021005 and 5000296/2021005 IR 05000259/20200062021-03-0303 March 2021 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020006, 05000260/2020006 and 05000296/2020006 ML21047A4732021-02-16016 February 2021 Notification of Browns Ferry Nuclear Power Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2021010, 05000260/2021010, and 05000296/2021010 ML20338A3682020-12-0303 December 2020 Notification of Inspection and Request for Information ML20266G4472020-09-22022 September 2020 Notification of Inspection and Request for Information IR 05000259/20200052020-08-18018 August 2020 Updated Inspection Plan for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2020005, 05000260/2020005, and 05000296/2020005 ML20191A2232020-07-0909 July 2020 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000259/20190062020-03-0303 March 2020 Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1,2,and 3 - NRC Report 05000259/2019006, 05000260/2019006, and 05000296/2019006 ML19108A1682019-04-18018 April 2019 EP Exercise Inspection RFI IR 05000259/20180062019-03-0404 March 2019 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 and 3 - Report 05000259/2018006, 05000260/2018006 and 05000328/2018006 ML19030A6712019-01-25025 January 2019 U2 ISI RFI ML19024A4112019-01-24024 January 2019 Transmittal of RP Baseline Inspection Document Request 2019 ML18264A2052018-09-21021 September 2018 U1 ISI Emailed RFI Notification ML18059A1052018-02-28028 February 2018 EOC Assessment Letter ML18029A4672018-01-29029 January 2018 Notification of Browns Ferry Nuclear Plant Design Bases Assurance Inspection - U.S. Nuclear Regulatory Commission Inspection Report 05000259/2018010, 05000260/2018010, and 05000296/2018010 ML18029A2552018-01-29029 January 2018 U3 RFI Email Request ML17236A1972017-08-24024 August 2017 Updated Inspection Plan ML17156A1612017-06-0202 June 2017 Notification of Inspection and Request for Information IR 05000259/20160062017-03-0101 March 2017 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Report 05000259/2016006, 05000260/2016006 and 05000296/2016006) IR 05000259/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3, NRC Inspection Reports 05000259/2016005, 05000260/2016005 and 05000296/2016005 ML16243A2242016-08-30030 August 2016 Notification of Inspection and Request for Information ML16120A1182016-04-27027 April 2016 Notification of Conduct of a Triennial Fire Protection Baseline Inspection - U.S. Nuclear Regulatory Commission Inspection Report Nos. 05000259/2016011, 05000260/2016011 and 05000296/2016011 IR 05000259/20150062016-03-0202 March 2016 Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 NRC Inspection Reports 05000259/2015006, 05000260/2015006 and 05000296/2015006 ML16013A0812016-01-12012 January 2016 Browns Ferry Nuclear Plant, Unit 3 - Notification of Inspection and Request for Information ML15348A1802015-12-14014 December 2015 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection IR 05000259/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for the Browns Ferry Nuclear Plant Units 1, 2 and 3, NRC Inspection Report 005000259/2015005, 005000260/2015005, and 005000296/2015005 IR 05000259/20140012015-03-0404 March 2015 Annual Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 - NRC Inspection Reports 05000259/2014001, 05000260/2014001 and 05000296/2014001 IR 05000259/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Browns Ferry Nuclear Plant Units 1, 2 and 3 (NRC Inspection Reports 05000259/2014006, 05000260/2014006 and 05000296/2014006) ML14063A1092014-03-0404 March 2014 2013 Annual Assessment Letter for Browns Ferry ML14031A4122014-01-31031 January 2014 U3 2014002 ISI RFI Final - Copy ML13353A5852013-12-19019 December 2013 PIR Notification Letter 2014 ML13246A1842013-09-0303 September 2013 Mid Cycle Assessment Letter ML13084A0052013-03-25025 March 2013 Emergency Preparedness Inspection Notification and Request for Information IR 05000259/20120012013-03-0404 March 2013 Annual Assessment Letter for Browns Ferry Nuclear Plant, Units 1, 2 & 3 (IR 05000259-12-001, 05000260-12-001, and 05000296-12-001) ML13037A1662013-02-0101 February 2013 Notification of Inspection and Request for Information IR 05000259/20120062012-09-0404 September 2012 Browns Ferry 2012 Mid Cycle ML12248A2962012-09-0404 September 2012 Mid Cycle ML12066A0602012-03-0505 March 2012 Inspection/Activity Plan, 30/01/2012 - 06/01/2013, RPT 22 2023-08-29
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Text
From: Magyar, Michael To: "Coons, Ryan William"
Subject:
BFN U2 ISI Request for Information Date: Thursday, December 03, 2020 9:31:00 AM Attachments: BFN U2 2021001 RFI - MCM.pdf Mr. Ryan Coons, Please find attached the NRC request for information for the upcoming Browns Ferry U2 Inservice Inspection in accordance with IP 71111.08, Inservice Inspection Activities, currently scheduled for March 1 - March 5, 2021.
Please confirm receipt of this request by return email.
Thank you in advance for your help in compiling the requested information.
Michael Magyar RII/DRS/EB3 - Reactor Inspector Phone: (404) 997-4459 Email: Michael.Magyar@nrc.gov ML20338A368
BROWNS FERRY NUCLEAR PLANT UNIT 2 - NOTIFICATION OF INSPECTION AND REQUEST FOR INFORMATION Ryan Coons:
From March 01 - March 05, 2021, the Nuclear Regulatory Commission (NRC) will perform the baseline in-service inspection at the Browns Ferry Nuclear Plant, Unit 2 in accordance with NRC inspection procedure IP 71111.08, Inservice Inspection Activities.
Experience has shown that this inspection is resource intensive for both the NRC inspectors and your staff. In order to minimize the impact to your onsite resources and to ensure a productive inspection, we are requesting in advance documents needed for this activity.
Section A of the enclosure identifies information to be provided prior to the inspection to ensure adequate sample selection and preparation. The NRC requests that these documents be provided to the lead inspector no later than February 19, 2021. Section B of the enclosure identifies additional information the inspectors will need upon arrival at the site to complete the review of inspection samples. The inspection staff will appreciate if all the documents requested 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.
Please note that our inspection dates are subject to change based on your updated schedule of outage activities. If there are any questions about this inspection, changes to the schedule of activities, or the material requested, please contact the lead inspector, Michael Magyar, at (404) 997-4459 or michael.magyar@nrc.gov or the Engineering Branch 3 Chief, Binoy Desai at (404) 997-4519.
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding, 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 component of NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html.
PAPERWORK REDUCTION ACT STATEMENT 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.
PUBLIC PROTECTION NOTIFICATION 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.
INSERVICE INSPECTION DOCUMENT REQUEST Site: Browns Ferry Nuclear Plant Unit 2 Docket No.: 50-260 Inspection Dates: March 01 - March 05, 2021 Entrance Meeting: March 01, 2021 Inspection Procedure: IP 71111.08, Inservice Inspection Activities, Dated January 1, 2019 Inspector(s): Michael Magyar, Reactor Inspector (Lead Inspector)
A. Information Requested for the In-Office Preparation Week Please provide the information requested in this section to the NRC Region II Office in care of the lead inspector by February 19, 2021, in order to facilitate the selection of specific items that will be reviewed during the onsite inspection week. The information can be provided in hard copy or electronic format; however, electronic format is preferred, either by digital data storage device (compact disk, flash drive, etc.), or web-based document management system.
The inspector(s) will select specific samples from the information provided for items A.1 and A.2 below and then request additional documents needed for the onsite inspection week(s) as described in Section B of this enclosure. The specific documents selected for Section B should be available and ready for review on the first day of inspection. If requested documents are large and only hard copies are available, please inform the inspector(s) and provide the subject documentation during the first day of the onsite inspection. All documents requested in this section correspond to the Unit scheduled to be in a refueling outage during the onsite inspection week(s), unless an information request item explicitly states that it applies to all operating Units. Additionally, some of the information requested may not apply to the site depending on the scope of refueling outage activities or other plant-specific conditions. If there are any questions regarding this information request, please contact the lead inspector as soon as possible.
A.1 Non-destructive Examination and Welding Activities
- a. A detailed schedule (including preliminary dates) of nondestructive examinations (NDEs) planned for the structures, systems, and components (SSCs) listed below as part of the Inservice Inspection Program required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC),Section XI, as incorporated by reference in 10 CFR 50.55a, and other augmented in-service inspection activities:
- ASME Class 1, 2, and 3 components and supports (including Risk-Informed ISI Program)
- ASME Class MC and metallic liners of Class CC components (e.g. reactor building containment liner)
- ASME Class CC components Enclosure
2
- b. A detailed schedule (including preliminary dates) of welding activities to be completed on ASME Code Class 1, 2, or 3 components and supports during the upcoming refueling outage.
- c. A list of NDE reports (ultrasonic, radiographic, magnetic particle, and liquid penetrant) addressing surface or volumetric indications that were analytically evaluated and accepted for continued service in ASME Code Class 1, 2, and 3 components since the beginning of the last refueling outage. This should also include any evaluations for continuous service performed as a result of Section XI pressure test(s) conducted during start up from the last refueling outage.
- d. A list of the welds in ASME Code Class 1, 2, and 3 systems that have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage. Please include a brief description of the welds such as system, material, pipe size, weld number, and NDEs performed. Additionally, please indicate which of those welds are risk-significant.
- e. If NDE of pressure retaining welds in the reactor vessel shell required by the ASME BPVC,Section XI, Subsection IWB (also known as 10-year Reactor Vessel ISI) 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 include reference numbers for applicable procedures that will be used to conduct these examinations.
- f. A copy of ASME BPVC,Section XI Relief Requests and associated NRC Safety Evaluation Reports applicable to the NDEs scheduled for the upcoming refueling outage.
- g. A list of temporary Code or temporary non-Code repairs installed in ASME Class components (e.g., pinhole leaks or mechanical clamping devices).
- h. A copy of the most recent program self-assessments addressing the ISI Program and welding activities.
A.2 Other Information Related to ISI Activities
- a. A list with a brief description of ISI-related issues entered into the corrective action program for all operating Units since the beginning of the last Unit 2 refueling outage.
For example, provide a list of condition reports based upon database searches using keywords related to piping, vessels, and supports degradation such as: ISI, ASME Code,Section XI, NDE, welding, reactor vessel, reactor coolant system, crack, wear, thinning, leakage, thru-wall, rust, corrosion, BWRVIP, or errors in piping examinations.
- b. Copy of the sites response to recent NRC generic communications and other industry operating experience notifications associated with the inservice inspection and structural integrity of ASME Class components issued since the beginning of the last refueling Enclosure
3 outage (e.g. Generic Letters, Information Notices, etc.).
- c. Names and contact information for the following program leads:
- ISI Program (examination, planning)
- Reactor Containment Building ISI Program
- Repair and Replacement Program
- Snubbers and Supports Inspection Program
- d. Current outage and ISI program information including:
- Current edition and addendum of the ASME Code being used for inspection, NDE, welding and repair/replacement activities
- Current edition and addendum of the ASME Code being used for containment inspections
- Current ISI interval number, period within the interval, outage within the period and total number of outages overall for the interval (e.g. the first outage of the third period in the fourth interval of the ISI inspection program, and the fifth outage for the interval B. Information Requested for the Onsite Inspection Week Please provide the information requested below in hard copy or electronic (preferred) format to the lead inspector at the entrance meeting, in order to finalize the planning of inspection activities onsite. Prior to the onsite inspection, the inspector(s) will select part of the inspection samples from the information provided in response to Section A of this enclosure, and then request additional information needed to complete the review.
There is a possibility that some of the inspection samples for which direct observation is desired (e.g. planned NDEs) will not be selected until the inspector(s) arrives onsite and confirms the current schedule of refueling outage activities for that week. All documents requested in this section correspond to the Unit scheduled to be in a refueling outage during the onsite inspection week, unless an information request item explicitly states that it applies to all operating Units. Additionally, some of the information requested may not apply depending on the scope of refueling outage activities or other plant-specific conditions.
B.1 Non-destructive Examination Activities, Welding Activities, and Schedule Information
- a. Updated schedules for the planned NDE and welding activities described in the response to items A.1.a and A.1.b of this enclosure.
- b. For the NDEs selected by the inspector(s) from item A.1.a of this enclosure, please provide a 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, please provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Please include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and Enclosure
4 transducers including serial numbers) and NDE personnel qualification records.
- c. For the NDE reports with relevant indications on ASME Code Class 1, 2, and 3 components selected by the inspector(s) from item A.1.c of this enclosure, please provide a copy of the examination records, NDE qualification records, and associated corrective action documents, including technical evaluations supporting the acceptability of the indications for continuous service.
- d. For the ASME Code Class 1, 2, and 3 welds selected by the inspector(s) from item A.1.d of this enclosure, please provide copies of the following documentation for each subject weld:
- weld data sheet (traveler)
- weld configuration and supporting drawings (e.g. ISI isometric drawings)
- applicable ASME BPVC Edition and Addenda
- Weld Procedure Specification (WPS) used to fabricate the welds
- Procedure Qualification Records (PQRs) supporting the WPS
- mechanical test reports supporting the applicable PQRs
- welder performance qualifications records, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS
- examination records for the NDEs performed during weld fabrication
- personnel qualification records for both fabrication and preservice NDEs
- nonconformance reports for the selected welds (if applicable)
B.2 Other Information Related To ISI Activities
- a. For the ISI-related corrective action issues selected by the inspector(s) from item A.2.a of this enclosure, please provide a copy of the corrective action documents and supporting documentation (e.g. cause evaluations, work orders, corrective action plan, etc.).
- b. An updated list of ISI-related issues entered into the corrective action program for the current refueling outage.
- c. A copy of or ready access to:
- applicable editions and sections of the ASME BPVC (e.g. Sections II, III, V, IX, and XI) for the inservice inspection and repair/replacement activities selected for review
- EPRI and other industry standards applicable to the inservice inspection activities selected for review (e.g. BWRVIP documents)
- a current revision of the ISI Program Manual and Plan for the current interval Inspector(s) Contact Information:
Michael Magyar Reactor Inspector Engineering Branch 3 Division of Reactor Safety 404-997-4459 Enclosure
5 Mailing Address:
US NRC Region II Attn: Michael Magyar 245 Peachtree Center Avenue, Suite 1200 Atlanta, GA 30303 Enclosure