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Category:Letter
MONTHYEARIR 05000456/20230042024-02-0202 February 2024 Integrated Inspection Report 05000456/2023004 and 05000457/2023004 ML24025C7242024-01-29029 January 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002 IR 05000457/20230112024-01-25025 January 2024 2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 RS-24-004, Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-01-11011 January 2024 Proposed Alternative to the Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators ML23348A2162023-12-15015 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0030 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000456/20200232023-12-15015 December 2023 Baseline Security Inspection Document; 05000456/2023/402; 05000457/2023/402 ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23313A1552023-12-0101 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23331A8922023-11-22022 November 2023 Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference 05000457/LER-2023-001, Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case2023-11-17017 November 2023 Submittal of LER 2023-001-00 for Braidwood Station, Unit 2, Train B Auxiliary Feedwater Pump Was Inoperable Due to Degraded Oil in the Crank Case ML23321A0442023-11-17017 November 2023 Notification of Deviation from Electric Power Research Institute (EPRI) Topical Report MRP-227, Revision 1-A, Materials Reliability Program: Pressurized Water Reactor Internals Inspection and Evaluation Guideline RS-23-118, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums RS-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds IR 05000456/20234012023-10-18018 October 2023 Security Baseline Inspection Report 05000456/2023401 and 05000457/2023401 IR 05000456/20230102023-10-18018 October 2023 Functional Engineering Inspection Commercial Grade Dedication Report 05000456/2023010 and 05000457/2023010 RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. ML23226A0062023-09-19019 September 2023 Review of License Renewal Commitment Number 10 Submittal ML23180A1692023-09-11011 September 2023 Calvert Cliff Units 1 & 2, and R.E. Ginna Plant - Withdrawal of Proposed Alternatives to American Society of Mechanical Engineers (ASME) Requirements (Epids L-2022-LRR-0074, 0076, 0079, 0091, 0092, 0093 and 0094) IR 05000456/20230052023-08-30030 August 2023 Updated Inspection Plan for Braidwood Station Report 05000456/2023005 and 05000457/2023005 ML23234A2462023-08-25025 August 2023 Confirmation of Initial License Examination IR 05000456/20230022023-08-0303 August 2023 Integrated Inspection Report 05000456/2023002 and 05000457/2023002 ML23188A1292023-07-26026 July 2023 Issuance of Amendment Nos. 233 and 233 Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1 ML23087A0762023-07-13013 July 2023 Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information 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 RS-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23110A1152023-06-12012 June 2023 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2023-LLA-0042) (Letter) RS-23-074, Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-06-0909 June 2023 Supplement to Application for License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RS-23-050, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube.2023-05-22022 May 2023 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube. ML23138A1342023-05-18018 May 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Braidwood Station and Byron Station ML23132A0472023-05-12012 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report ML23130A0072023-05-10010 May 2023 Submittal of Core Operating Limits Report Cycle 24, Rev. 16 IR 05000456/20230012023-05-0808 May 2023 Integrated Inspection Report 05000456/2023001 and 05000457/2023001 ML23114A2522023-04-28028 April 2023 Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI ML23118A0202023-04-28028 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 RS-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML23095A1292023-04-0505 April 2023 Steam Generator Tube Inspection Report for Refueling Outage 23 ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 RS-23-052, License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink2023-03-24024 March 2023 License Amendment to Braidwood Station, Units 1 and 2, Technical Specification 3.7.9, Ultimate Heat Sink RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations 2024-02-02
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23339A0452023-12-0505 December 2023 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010 ML23191A8442023-07-10010 July 2023 05000456; 05000457 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23094A1352023-04-0404 April 2023 Request for Information for Nrc Commercial Grade Dedication Inspection Inspection Report 05000456/2023010 05000457/2023010 ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23018A1632023-01-18018 January 2023 Notification of NRC Baseline Inspection and Request for Information ML22241A0522022-08-29029 August 2022 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000456/2022004 05000457/2022004 ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22091A0852022-04-0101 April 2022 NRR E-mail Capture - Braidwood and Byron - Final RAI Regarding Proposed Alternative for Various Pressurizer Welds (EPID L-2021-LLR-0035 and 0036) ML22041B5362022-02-10010 February 2022 NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541 ML22034A9862022-02-0404 February 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000456/2022402 05000457/2022402 ML21350A4372021-12-16016 December 2021 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team) Inspection Report 05000456/2022010 and 05000457/2022010 ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21228A2352021-08-17017 August 2021 Notification of NRC Baseline Inspection and Request for Information Inspection Report 05000457/2021004 ML21193A0942021-07-12012 July 2021 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML21189A1602021-07-0808 July 2021 NRR E-mail Capture - Request for Additional Information - Braidwood, Byron, and Ginna - Amendment to Address the Issues in Westinghouse NSALs ML21144A2132021-05-24024 May 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21117A0342021-05-0505 May 2021 Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893 ML21062A0652021-03-0101 March 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting ML21057A1022021-02-25025 February 2021 Notification of NRC Fire Protection Team Inspection Request for Information; Inspection Report 05000456/2021010; 05000457/2021010 ML21049A2572021-02-18018 February 2021 Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237) ML21029A3302021-01-29029 January 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative Request to Use ASME Code Case N-885 ML21020A1292021-01-20020 January 2021 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2021002; 05000457/2021002 ML21004A1452020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18 ML20289A1142020-10-0909 October 2020 NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance ML20153A7042020-06-0101 June 2020 NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26 ML20104C1452020-04-10010 April 2020 NRR E-mail Capture - Preliminary RAIs for Exelon'S April 6, 2020, Application to Defer Braidwood, Unit 2, Steam Generator Inspections ML20023A0812020-01-23023 January 2020 NRR E-mail Capture - RAIs for L-2019-LLA-0201 - Braidwood, Units 1 and 2, LAR to Revise TS 3.7.9, Ultimate Heat Sink ML19350B2952019-12-16016 December 2019 NRR E-mail Capture - Draft Request for Additional Information Regarding Braidwood Station, Units 1 and 2, Impractical Inservice Inspection Requirements (L-2019-LLA-0081) ML19275H1362019-10-0202 October 2019 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879 ML19252C1542019-08-22022 August 2019 NRR E-mail Capture - Issuance of the Remainder of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19232A2242019-08-0707 August 2019 NRR E-mail Capture - Partial Issuance of Final RAIs for Braidwood/Byron TSTF-505 Application ML19207A0672019-07-26026 July 2019 NRR E-mail Capture - Partial Issuance of Preliminary RAIs for Braidwood/Byron TSTF-505 Application ML19179A0612019-07-19019 July 2019 Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879 ML19128A2362019-05-0202 May 2019 NON- PROPRIETARY- Request for Additional Information- Amendment Request Regarding Utilization of Tvel TVS-K Lead Test Assemblies Braidwood Station, Units 1 and 2 ML19066A0432019-03-0707 March 2019 NRR E-mail Capture - Preliminary RAIs for Quality Assurance Review of Braidwood Tvel LTA Application ML18324A8072018-12-12012 December 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action One-Time Extension of Technical Specification 3.8.1, AC Sources-Operating, A2 Completion Time ML18192C1712018-07-11011 July 2018 NRR E-mail Capture - Preliminary Request for Additional Information Regarding Braidwood Station, Units 1 and 2, Relief Request IR4-03 ML18190A4072018-07-0505 July 2018 NRR E-mail Capture - Preliminary Request for Additional Information Regarding Braidwood Station, Units 1 and 2, Relief Request IR4-06 ML18150A6902018-05-30030 May 2018 NRR E-mail Capture - Preliminary RAIs Regarding Braidwood TORMIS Amendment Request ML18149A2842018-05-24024 May 2018 NRR E-mail Capture - B/B 50.69 RAI - Potential Typo ML18135A2202018-05-15015 May 2018 NRR E-mail Capture - Preliminary RAIs for Braidwood Relief Request IR4-05 ML18129A1082018-05-0909 May 2018 NRR E-mail Capture - Preliminary RAIs for Braidwood and Byron Stations 50.69 Amendment ML18067A1482018-03-0808 March 2018 Enclosurequest for Additional Information (Letter to P. R. Simpson Request for Additional Information Regarding Exelon Generating Company, Llc'S Decommissioning Funding Plan Update for Independent Spent Fuel Storage Installation) ML18009B0012018-01-0808 January 2018 Request for Information for an NRC Design Bases Assurance Inspection (Program): Implementation of the Environmental Qualification Program Inspection Report 05000456/2018012; 05000457/2018012 (DRS-J.Bozga) ML17276A0782017-09-27027 September 2017 NRR E-mail Capture - Request for Additional Information Regarding TSTF-547 Supported Amendment ML17228A7972017-08-16016 August 2017 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information (Meb) ML17179A2852017-06-28028 June 2017 NRR E-mail Capture - Request for Additional Information Regarding Braidwood and Byron Amendments to Remove Obsolete License and Technical Specification Items 2023-07-10
[Table view] |
Text
January 18, 2023 Mr. David Rhoades Senior Vice President Constellation Energy Generation, LLC President and Chief Nuclear Officer (CNO)
Constellation Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
BRAIDWOOD STATION, UNIT 2NOTIFICATION OF NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Rhoades:
On April 24, 2023, the U.S. Nuclear Regulatory Commission (NRC) will begin the Baseline Inservice Inspection Procedure 71111.08. This onsite inspection is scheduled to be performed April 24, 2023, through May 12, 2023.
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 onsite 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, 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 inspection activities with your staff and understand that our regulatory contact for this inspection will be Mr. R. Schliessmann of your organization. If there are any questions about this inspection or the material requested, please contact the lead inspector Atif Shaikh at 630-829-9824, or via e-mail at Atif.Shaikh@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.
D. Rhoades This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, Signed by Shaikh, Atif on 01/18/23 Atif Shaikh, Senior Reactor Inspector Engineering and Reactor Projects Branch Division of Operating Reactor Safety Docket Nos. 05000456 and 05000457 License Nos. NPF-72 and NPF-77
Enclosure:
Document Request for Inservice Inspection cc: Distribution via LISTSERV
D. Rhoades Letter to David Rhoades from Atif Shaikh dated January 18, 2023.
SUBJECT:
BRAIDWOOD STATION, UNIT 2NOTIFICATION OF NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION DISTRIBUTION:
Jessie Quichocho Marc Ferdas RidsNrrDorlLpl3 RidsNrrPMBraidwood Resource RidsNrrDroIrib Resource John Giessner Julio Lara Diana Betancourt-Roldan Allan Barker R3-DORS ADAMS Accession Number: ML23018A163 Publicly Available Non-Publicly Available Sensitive Non-Sensitive OFFICE RIII NAME AShaikh:mb DATE 01/18/2023 OFFICIAL RECORD COPY
DOCUMENT REQUEST FOR INSERVICE INSPECTION Inspection Report: 05000456/2023002 and 05000457/2023002 Inspection Dates: April 24 - May 12, 2023 Inspection Procedures: Inspection Procedure 71111-08, Inservice Inspection Lead Inspector: Atif Shaikh, DORS/ERPB 630-829-9824 Atif.Shaikh@nrc.gov A. Information for the In-Office Preparation Week The following information (electronic copy) is requested by March 31, 2023, 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 request a list of additional documents needed onsite to 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 the outage unit 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 (NDEs) planned for Class 1 and 2 Systems and containment, performed as part of your American Society of Mechanical Engineers (ASME) Code Inservice Inspection (ISI) Program (include edition and addenda of Code committed to), and NDEs planned for other systems performed as part of a Risk-Informed ISI Program, or other augmented inspection programs (e.g., ASME Code Case N-770 examination of dissimilar metal welds and examinations to meet an industry initiative);
- b. Reactor vessel upper head examinations required by Title 10 of the Code of Federal Regulations (CFR), Part 50.55a(g)(6)(ii)(D) and Code Case N-729;
- 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. 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.
- 2. A copy of the NDE procedures, SG eddy current examination (ET) acquisition and analysis procedures, and welding procedures used to perform the activities identified in Item A.1 (including NDE calibration and flaw characterization/sizing procedures 1Note 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.
Enclosure
DOCUMENT REQUEST FOR INSERVICE INSPECTION 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 Electric Power Research Institute performance demonstration qualification summary sheets). For SG tube ET this includes the acquisition and analysis procedures.
- 3. A copy of ASME Section XI, Code Relief Requests applicable to the examinations identified in Item A.1.
- 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 of repair/replacement welds in Code Class 1, 2 and 3 Systems, which have been fabricated 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. List of reactor vessel weld examinations required by the ASME Code that are scheduled to occur during the upcoming refueling outage, and please provide a detailed description of the welds and the extent of the planned examination.
- 8. Corrective action list of ISI and SG-related issues such as piping or SG tube degradation or damage (e.g., cracks, wall thinning, wear, microbiologically induced corrosion) or errors identified during piping/SG tube examinations since the beginning of the last refueling outage. Also, include a list of corrective actions associated with foreign material in the reactor vessel, primary coolant system, SG or feed systems since the beginning of the last refueling outage.
- 9. Title 10 CFR Part 21 reports applicable to your structures, systems, or components within the scope of ASME Code Section XI that have been identified since the beginning of the last refueling outage.
- 10. Copy of SG history documentation given to vendors performing ET 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 (provide this document even if no SG ET is planned for current outage).
- 13. Copy of most recent SG Degradation Assessment (provide this document even if no SG ET is planned for current outage).
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.
2
DOCUMENT REQUEST FOR INSERVICE INSPECTION
- 14. Copy of most recent SG Condition Monitoring Assessments.1
- 15. 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 Electric Power Research Institute Guidelines.1
- 16. 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).1
- 17. Provide procedures with guidance/instructions for identifying (e.g., physically locating the tubes that require repair) and plugging SG tubes.1
- 18. 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.
- 19. Point of contact information (name and site number) for the following activities:
- a. ISISite and vendor leads;
- b. Boric Acid Inspections and Evaluations;
- c. Reactor Vessel Head InspectionSite and vendor leads;
- d. SG InspectionSite and vendor leads;
- e. Aging Management Programs; and
- f. Site Welding Engineer.
B. Onsite 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, if possible) of the Following Documents.
- 1. For welds selected by the inspector from Item 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 portions of the Design Specification and applicable Code of construction for the weldment (e.g., B31.1 or ASME Section III);
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.
3
DOCUMENT REQUEST FOR INSERVICE INSPECTION
- d. Applicable Code Edition and Addenda for weld procedure qualification;
- e. Applicable weld procedure specifications and weld data sheets used to fabricate the welds;
- f. Copies of procedure qualification records supporting the weld procedure specifications;
- g. Copies of welders performance qualification records;
- h. Copies of mechanical test reports identified in the weld procedure qualification records above;
- i. Copies of the nonconformance reports for the selected welds;
- j. Access to radiographs and equipment to view radiographs of the selected welds;
- k. ASME Code section XI repair replacement plan and reconciliation for replacement components/materials;
- l. Certified Material Test Reports for replacement pressure boundary materials; and
- m. Copies of the NDE required by the construction Code and the pre-service examination records required by the ASME Code Section XI 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 NDE 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.
- 4. Updated schedules for Item A.1 (including schedule showing contingency repair plans if available).
- 5. 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.
- 6. 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.
- 7. Copy of:
- a. Engineering evaluations/assessments of boric acid related deposits and associated wastage or corrosion for safety-related components; and 4
DOCUMENT REQUEST FOR INSERVICE INSPECTION
- b. Corrective action records for coolant leakage including boric acid deposits on safety-related components identified since the beginning of the last refueling outage.
- 8. 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.
- 9. 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).
- 10. Copy of volumetric, surface and visual examination records for the prior inspection of the reactor vessel head and head penetration J-groove welds.
- 11. Provide a copy of the Electric Power Research Institute Examination Technique Specification Sheets and vendor related documents, which support qualification of the ET probes to be used during the upcoming SG tube inspections.1
- 12. Provide a copy of the guidance to be followed if a loose part or foreign material is identified in the SGs.1
- 13. Identify the types of SG tube repair processes which will be implemented for defective SG tubes (including any U.S. Nuclear Regulatory Commission 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
- 14. Copy of document describing actions to be taken if a new SG tube degradation mechanism is identified.1
- 15. 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).
- 16. Provide procedures with guidance/instructions for identifying (e.g., physically locating the tubes that require repair) and plugging SG tubes.
- 17. Provide copies of the following standards at the onsite U.S. NRC inspection location for the duration of the inspection:
- a. Sections V, IX, and XI of the ASME Code with Editions applicable to the ISI Program and the Repair/Replacement Program; 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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DOCUMENT REQUEST FOR INSERVICE INSPECTION
- 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. Electric Power Research Institute and industry standards referenced in the site procedures used to perform the SG tube ET, which includes Electric Power Research Institute documents: SG Examination Guidelines, SG Integrity Assessment Guidelines, SG In-Situ Pressure Test Guidelines; and
- d. Boric Acid Corrosion Guidebook Revision 1Electric Power Research Institute Technical Report 1000975.
- 18. Provide training (e.g., Scaffolding, Fall Protection, Foreign Material Exclusion) if required to access the NDEs selected by the inspector for observation.
If you have questions regarding the information requested, please contact the lead inspector.
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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