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Category:Letter
MONTHYEARIR 05000454/20230042024-02-0202 February 2024 Integrated Inspection Report 05000454/2023004 and 05000455/2023004 ML24022A2722024-01-23023 January 2024 Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000454/2024011 ML24018A0362024-01-17017 January 2024 Paragon Energy Solutions, Defect with Detroit Diesel/Mtu Fuel Injectors P/N R5229660 Cat Id 0001390618 ML23320A1762023-12-13013 December 2023 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0027 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23277A0032023-12-11011 December 2023 Issuance of Amendments Regarding Adoption of TSTF-370 ML23318A5102023-12-0101 December 2023 Relief from the Requirements of the ASME Code IR 05000454/20233012023-11-27027 November 2023 NRC Initial License Examination Report 05000454/2023301 and 05000455/2023301 BYRON 2023-0065, Unit 2 - 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 Guideline2023-11-17017 November 2023 Unit 2 - 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 BYRON 2023-0063, Day Inservice Inspection Report for Interval 4, Period 3, (B2R24)2023-11-16016 November 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B2R24) IR 05000454/20230032023-11-13013 November 2023 Integrated Inspection Report 05000454/2023003 and 05000455/2023003 and Exercise of Enforcement Discretion RS-23-117, 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 ML23313A0852023-11-0909 November 2023 Submittal of 2023-301 Byron Initial License Examination Post-Examination Comments 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 ML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection RS-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 ML23278A0272023-10-0505 October 2023 Operator Licensing Examination Approval - Byron Station, October 2023 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. ML23251A1622023-09-29029 September 2023 Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals 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) ML23242A3282023-09-0101 September 2023 Amendment No. 233 Correction IR 05000454/20235012023-08-31031 August 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000454/2023501 and 05000455/2023501 IR 05000454/20230052023-08-30030 August 2023 Updated Inspection Plan for Byron Station (Report 05000454/2023005 and 05000455/2023005) IR 05000454/20230022023-08-0303 August 2023 Integrated Inspection Report 05000454/2023002 and 05000455/2023002 ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23192A0362023-07-25025 July 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report ML23122A3022023-07-20020 July 2023 Issuance of Amendments Technical Specifications 2.1.1 and 4.2.1 to Allow a Previously Irradiated Accident Tolerant Fuel Lead Test Assembly to Be Further Irradiated in Unit No. 2 IR 05000454/20234022023-07-18018 July 2023 Baseline Security Inspection Document; 05000454/2023402; 05000455/2023402 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant 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 ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information 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 ML23159A1302023-06-0808 June 2023 Day Inservice Inspection Report for Interval 4, Period 3, (B1R25) ML23159A1542023-06-0808 June 2023 2022 Regulatory Commitment Change Summary Report 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 ML23157A2832023-06-0606 June 2023 Notification of NRC Baseline Inspection and Request for Information BYRON 2023-0029, Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements2023-06-0101 June 2023 Response to Request for Additional Information Regarding Steam Generator Tube Inspection Reports to Reflect TSTF-577 Reporting Requirements 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 ML23003A7882023-05-11011 May 2023 Report for December 12-16, 2022, Regulatory Audit Regarding Reinsertion of a High Burnup Accident Tolerant Fuel Lead Test Assembly 2024-02-02
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23297A2352023-10-26026 October 2023 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection ML23209A7242023-07-31031 July 2023 Request for Information on the NRC Quadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000454/2024010 and 05000455/2024010 ML23198A0372023-07-17017 July 2023 Information Request to Support Upcoming Problem Identification and Resolution (PIR) Inspection at Byron Nuclear Plant ML23172A1172023-06-22022 June 2023 Notification of NRC Fire Protection Team Inspection Request for Information ML23110A3202023-04-21021 April 2023 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23069A0342023-03-0606 March 2023 Unit 1 Lr Commitment 10 RAI Set 1 - (Non-Proprietary) ML23069A0332023-03-0606 March 2023 Email to K. Lueshen Byron and Braidwood Commitment 10 - Request for Additional Information Set 1 ML23115A2412023-01-20020 January 2023 NRR E-mail Capture - Preliminary RAIs Related to L-2022-LLA-0131 - Byron, Unit 2, Reinsertion of an Accident Tolerant Fuel Lead Test Assembly ML22237A0272022-08-25025 August 2022 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information 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 ML22116A1272022-04-26026 April 2022 Unit 2 RFI for an NRC Triennial Heat Exchanger/Sink Performance Inspection and RFI IR 05000454/2022002 05000455/2022002 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 ML21273A3312021-10-0404 October 2021 Information Request to Support Upcoming Biennial Problem Identification and Resolution (Pi&R) Inspection at Byron Station ML21256A1902021-09-10010 September 2021 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application ML21203A3112021-07-21021 July 2021 NRR E-mail Capture - Final Byron Permanently Defueled Technical Specifications (PDTS) - Second Round RAI 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 ML21189A1612021-07-0808 July 2021 NRR E-mail Capture - Second Round Request for Additional Information - Byron Permanently Defueled Technical Specification Amendment 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 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) ML21036A1102021-02-0404 February 2021 NRR E-mail Capture - Draft RAIs for Byron Station, Unit Nos. 1 and 2, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition 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 ML21004A1452020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding Relief Requests Braidwood I4R-11 and Byron I4R-18 ML20329A4852020-11-24024 November 2020 Notification of NRC Fire Protection Team Inspection Request for Information ML20294A5492020-10-21021 October 2020 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information ML20289A1142020-10-0909 October 2020 NRR E-mail Capture - Preliminary RAIs for LAR Regarding Non-conservative TS EDG Frequency Tolerance ML20077M2212020-03-20020 March 2020 Ti 2515/194 Inspection Documentation Request ML20008D3992020-01-0808 January 2020 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000454/2020001 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 ML19032A1062019-02-0101 February 2019 NRR E-mail Capture - Preliminary RAIs for Byron On--time Extension of Completion Time 3.8.1, A.2 ML19011A3452019-01-11011 January 2019 NRR E-mail Capture - Preliminary RAIs Regarding Byron Request to Use ATF LTAs ML18149A2842018-05-24024 May 2018 NRR E-mail Capture - B/B 50.69 RAI - Potential Typo 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) ML18022A0422018-01-19019 January 2018 18 Byron Station, Units 1 and 2 - Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection (DRS-I.Hafeez) 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 ML17159A6292017-06-0707 June 2017 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML17137A0562017-05-17017 May 2017 Information Request to Support Upcoming Temporary Instruction 191 Inspection at Byron Station, Units 1 and 2 ML17062A4912017-03-0303 March 2017 NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Fleet Alternative to RPV Threads in Flange Examination (CAC Nos. MF8712-MF8729) ML17019A2022017-01-19019 January 2017 NRR E-mail Capture - Preliminary RAIs for Byron Station TORMIS License Application Request ML16355A0322016-12-19019 December 2016 Notification of NRC Inspection and Request for Information (Msh) ML16343A2522016-12-0808 December 2016 NRR E-mail Capture - Preliminary Request for Additional Information (RAI) Regarding Relief Request I4R-10 ML16196A1102016-07-14014 July 2016 Notification of NRC Triennial Heat Sink Performance Inspection and Request for Information; Inspection Report 05000454/2016004; 05000455/2016004 2023-07-31
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 2443 WARRENVILLE ROAD, SUITE 210 LISLE, IL 60532-4352 February 2, 2010 Mr. Charles G. Pardee Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Road Warrenville IL 60555
SUBJECT:
BYRON STATION UNIT 2 - NOTIFICATION OF NRC INSPECTION AND REQUEST FOR INFORMATION
Dear Mr. Pardee:
On April 19, 2010, the NRC will begin the Baseline Inservice Inspection (NRC Inspection Procedure (IP) 71111.08) at the Byron Station, Unit 2. This inspection is scheduled to be performed April 19 through 30, 2010.
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 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 on-site portions of the inspection.
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Ms. T. Hulbert, of your organization. If there are any questions about this inspection or the material requested, please contact the inspector Mr. T. Bilik at (630) 829-9744.
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.
C. Pardee 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 (PARS) component of NRC's document 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 No. 50-455 License No. NPF-66
Enclosure:
INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: Distribution via ListServ
INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: April 19 - 30, 2010 Inspection Procedures: IP 71111.08, Inservice Inspection Inspector: Tom Bilik (630) 829-9744 tom.bilik@nrc.gov A. Information Requested for the In-Office Preparation Week The following information (electronic copy CD ROM if possible) is requested by April 12, 2010, 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 request 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. If you have any questions regarding this information, please call the inspector as soon as possible.
- 1. 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 commitments as part of an industry initiative. Specifically, identify any dissimilar metal weld examinations performed to meet the MRP-139 Program that are scheduled to occur during the outage. 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 exam;
- 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; and
- d. welding on Code Class 1, 2, or 3 components.
Also, provide the inspector with the on-site training necessary to observe these activities; (e.g., confined space, scaffolding, or fall protection).
1 Enclosure
INSERVICE INSPECTION DOCUMENT REQUEST
- 2. A copy of the NDE procedures and welding procedures used to perform the activities identified in A.1 (including NDE calibration and flaw 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 A(1).
- 4. A copy of the 10-year ISI program showing those required exams scheduled to be performed during this outage, and those that 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 steam generator (SG) related issues (e.g.,
piping/SG tube degradation, or damage (cracks, wall thinning, wear, corrosion or errors identified in piping/SG tube examinations) entered into your corrective action system since the beginning of the last refueling outage (both Units).
Also, include a list of corrective action records associated with foreign material introduced/identified in the primary or secondary piping systems since the beginning of the last refueling outage (both Units).
- 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, which 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.
2 Enclosure
INSERVICE INSPECTION DOCUMENT REQUEST
- 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.
- 12. Copy of previous outage SG tube operational assessment completed following ET of the SGs.
- 13. Copy of the document defining the planned ET scope for the SGs and the scope expansion criteria which will be used. Also, identify and describe any deviations in this scope or expansion criteria from the EPRI Guidelines.
- 14. Copy of the document describing the ET probe types, Examination Technique Specification Sheets, and ET acquisition equipment to be used, including the areas of the SG (e.g., top of tube sheet, U-bends) that each probe will be used in.
- 15. 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.
- 16. Identify changes made to the dissimilar metal weld examination program Materials Reliability Program (MRP) for Unit 2 welds subject to the requirements of the MRP. Primary System Piping Butt Weld Inspection and Evaluation Guidelines (MRP-139), which have been implemented since the completion of the last NRC inspection. For example, identify a program change if welds have been moved in/out of scope, schedules of planned weld examinations have been changed, or planned methods for mitigation of susceptible welds have changed since the NRC documented its review of this program in inspection report 05000455/2008005.
- 17. Identify any current, or planned, deviations from the Materials Reliability Program: Primary System Piping Butt Weld Inspection, and Evaluation Guidelines (MRP-139), and provide a copy of the basis document supporting these deviations.
- 18. Identify and provide scheduled dates for any dissimilar metal weld mitigation activities (overlay repair, inlay repair, mechanical stress improvement, etc.),
which will occur during the upcoming Unit 2 outage.
B. Information To Be Provided On-Site To The Inspector Following The Entrance Meeting
- 1. For welds selected by the inspector from A.2 and A.6 above, provide copies of the following documents:
3 Enclosure
INSERVICE INSPECTION DOCUMENT REQUEST
- a. Document of the weld number and location (e.g., system, train, branch);
- b. Document with a detail of the weld construction;
- c. Applicable Code Edition and Addenda for weldment;
- d. Applicable Code Edition and Addenda for welding procedures;
- e. Applicable weld procedures (WPS) used to fabricate the welds;
- 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. Radiographs of the selected welds and access to equipment to allow viewing radiographs; and
- k. Copies of the preservice examination records for the selected welds.
- 2. For the ISI related corrective action issues selected by the inspector from A.8 above, provide a copy of the corrective actions, and supporting documentation.
- 3. For the nondestructive examination reports with relevant indications on Code Class 1 and 2 Systems selected by the inspector from 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. 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.
- 6. Copy of any documentation of:
- a. engineering evaluations/assessments of boric acid related deposits and associated wastage or corrosion for safety-significant components; and
- b. corrective actions for coolant leakage including boric acid deposits on safety-related components identified since the beginning of the last refueling outage.
- 7. 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.
- 8. Provide a copy of the EPRI Examination Technique Specification Sheets, which support qualification of the ET probes to be used during the upcoming SG tube inspections.
4 Enclosure
INSERVICE INSPECTION DOCUMENT REQUEST
- 9. Provide a copy of the guidance to be followed if a loose part or foreign material is identified in the SGs.
- 10. Copy of document describing actions to be taken if a new SG tube degradation mechanism is identified.
- 11. 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.
- 12. Provide a copy of the site specific documents, which implement the MRP-139 Program, and a copy of the baseline and inservice inspection schedules for the welds affected by this program.
- 13. Identify any dissimilar welds, which were excluded from the MRP-139 Guidelines, where the site is relying on NSSS vendor documents to exclude these welds from this program. For these welds, (if any) provide a copy of the NSSS vendor documents and site documents, which provide the basis for excluding these welds from the MRP-139 Program.
- 14. Ready access to:
- a. Sections V, IX, and XI of the ASME Code, with Editions applicable to the inservice inspection program and the repair/replacement program;
- b. MRP-139, Materials Reliability Program: Primary System Piping Butt Weld Inspection and Evaluation Guideline and associated site implementing procedures; and
- 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, and 1003138, Pressurized Water Reactor Steam Generator Examination Guidelines.
Ready access is typically facilitated by providing copies of these standards at the on-site NRC inspection location for the duration of the inspection.
5 Enclosure
C. Pardee 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 (PARS) component of NRC's document 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 No. 50-455 License No. NPF-66
Enclosure:
INSERVICE INSPECTION DOCUMENT REQUEST cc w/encl: Distribution via ListServ DISTRIBUTION:
Susan Bagley RidsNrrDorlLpl3-2 Resource RidsNrrPMByron Resource RidsNrrDirsIrib Resource Cynthia Pederson Steven Orth Jared Heck Allan Barker Carole Ariano Linda Linn DRPIII DRSIII Patricia Buckley Tammy Tomczak ROPreports Resource DOCUMENT NAME: G:\DRS\WIP\Ltr 020210 Byron ISI Request for Information TXB.doc 9 Publicly Available 9 Non-Publicly Available 9 Sensitive 9 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 TBilik:Is DHills DATE 02/02/10 02/02/10 OFFICIAL RECORD COPY