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| | issue date = 09/14/2009 | | | issue date = 09/14/2009 |
| | title = Request for Additional Information Related to Relief Request 12R-50 | | | title = Request for Additional Information Related to Relief Request 12R-50 |
| | author name = David M J | | | author name = David M |
| | author affiliation = NRC/NRR/DORL/LPLIII-2 | | | author affiliation = NRC/NRR/DORL/LPLIII-2 |
| | addressee name = Pardee C G | | | addressee name = Pardee C |
| | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear |
| | docket = 05000456, 05000457 | | | docket = 05000456, 05000457 |
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Category:Letter
MONTHYEARML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary IR 05000456/20240112024-09-12012 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000456/2024011 and 05000457/2024011 ML24164A0032024-09-10010 September 2024 Issuance of Amendment Nos. 235 and 235 Revision of Technical Specifications for the Ultimate Heat Sink IR 05000456/20240052024-08-29029 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2024005 and 05000457/2024005) ML24227A0522024-08-29029 August 2024 Audit Plan for LAR to Remove ATWS Mtc Limit ML24225A1112024-08-13013 August 2024 Notification of NRC Fire Protection Team Inspection Request for Information ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000456/20240022024-08-0808 August 2024 Integrated Inspection Report 05000456/2024002 and 05000457/2024002 ML24172A1252024-07-26026 July 2024 Environmental Assessment and Finding of No Significant Impact Related to a Requested Increase in Ultimate Heat Sink Temperature (EPID L-2024-LLA-0075) - Transmittal Letter ML24179A3262024-07-23023 July 2024 LTR - Constellation - SG Welds and Nozzles (L-2023-LLR-0053, L-2023-LLR-0054, L-2023-LLR-0055, L-2023-LLR-0056) 05000456/LER-2024-001, Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open2024-07-0303 July 2024 Submittal of LER 2024-001-00 for Braidwood Station, Unit 1, Trip on Low Steam Generator Level Due to Failure to Verify Isolation Valves Were Open ML24163A3922024-06-25025 June 2024 Individual Notice of Consideration of Issuance of Amendments to Renewed Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, & Opportunity for a Hearing (EPID L-2024-LLA-0075)- Letter RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations ML24164A2132024-06-13013 June 2024 Information Request to Support Upcoming Problem Identification and Resolution (Pi&R) Inspection at Braidwood Nuclear Plant RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink IR 05000456/20240102024-05-31031 May 2024 License Renewal Phase 1 Report 05000456/2024010 RS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report ML24136A0132024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report ML24136A2452024-05-15015 May 2024 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000457/2024004 ML24128A1212024-05-0707 May 2024 Response to Braidwood and Dresden FOF Dates Change Request (2025) ML24122A6522024-05-0101 May 2024 Submittal of 2023 Annual Radioactive Effluent Release Report RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests IR 05000456/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000456/2024301; 05000457/2024301 RS-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) ML24116A0052024-04-25025 April 2024 Transmittal of Braidwood Station, Unit 1, Core Operating Limits Report, Braidwood Unit 1 Cycle 25 IR 05000456/20240012024-04-24024 April 2024 Integrated Inspection Report 05000456/2024001 and 05000457/2024001 ML24113A1272024-04-22022 April 2024 Audit Plan in Support of Review of LAR Revision of TS 3.7.15, 3.7.16, and 4.3.1 (EPID: L-2023-LLA-0136) (Non-Proprietary) IR 05000457/20240902024-04-19019 April 2024 Final Significance Determination for 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Dilution Issue - NRC Inspection Report 05000457/2024090 ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML24094A2692024-04-0303 April 2024 Notification of Deviation from Pressurized Water Reactor Owners Group (PWROG) Report, WCAP-17451-P, Revision 2, Reactor Internals Guide Tube Wear Westinghouse Domestic Fleet Operational Projections RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24057A0372024-03-26026 March 2024 Proposed Alternative from Certain Requirements Contained in the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI RS-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds ML24067A3252024-03-0707 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites ML24066A0122024-03-0606 March 2024 Operator Licensing Examination Approval Braidwood Station, Units 1 and 2, March 2024 IR 05000456/20244012024-03-0505 March 2024 Cyber Security Inspection Report 05000456/2024401 and 05000457/2024401 (Public) IR 05000456/20230062024-02-28028 February 2024 Annual Assessment Letter for Braidwood Station, Units 1 and 2 (Report 05000456/2023006 and 05000457/2023006) ML24057A3022024-02-26026 February 2024 Regulatory Conference Supplemental Information ML24047A2382024-02-20020 February 2024 Regulatory Conference to Discuss Risk Associated with 2b Auxiliary Feedwater Pump Diesel Engine Fuel Oil Leak RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators IR 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 2024-09-23
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24263A1272024-09-23023 September 2024 – Request for Additional Information (EPID 2023-LLA-0136) - Non-Proprietary ML24197A0162024-07-12012 July 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - License Amendment Request to Adopt TSTF-591 ML24142A3352024-05-21021 May 2024 Quad Cities—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes ML24053A3382024-02-22022 February 2024 NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC - Fleet Request - Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds (L-2023-LLR-0062) ML24039A0412024-01-30030 January 2024 NRR E-mail Capture - Request for Additional Information Regarding Braidwood Request for Alternative (I4R-18) ML23339A0452023-12-0505 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 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 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 ML22129A0132022-05-0606 May 2022 NRR E-mail Capture - Draft RAIs for Requests for Alternatives I4R-17, I4R-23, ISI-05-018, I6R-10 ML22271A0772022-05-0606 May 2022 NRR E-mail Capture - Final RAIs 9.1.2021 Constellation Relief Request 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 2024-09-23
[Table view] |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 September 14, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB..BRAIDWOOD STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST 12R-50 (TAC NOS. ME1038 AND ME1039)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC) dated March 31,2009, (Agencywide Documents Access and Management System Accession No. ML090960468), Exelon Generation Company, LLC (the licensee) submitted Relief Request (RR) 12R-50 for the second 1 O-year inservice inspection interval at Braidwood Station, Units 1 and 2. This RR was submitted due to the impracticality of satisfying the relevant requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI for the specified ASME Code Class 1 and 2 components.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosed Request for Additional Information (RAI). Your staff has agreed to provide a response to this RAI within 45 days after the date of this letter. The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1547.
Marshall J. David, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456 and STN Request for Additional cc w/encl: Distribution via REQUEST FOR ADDITIONAL INFORMATION BRAIDWOOD STATION, UNITS 1 AND 2 DOCKET NOS. STN 50-456 AND STN 50-457 The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided by Exelon Generation Company, LLC (the licensee) in its letter dated March 31,2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090960468), pertaining to Relief Request (RR) 12R-50 for the second 1 O-year inservice inspection (lSI) interval at Braidwood Station, Units 1 and 2. This RR was submitted due to the impracticality of satisfying the relevant requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI for the specified ASME Code Class 1 and 2 components.
The ASME Code of record for the Braidwood Station, Units 1 and 2, second 10-year interval lSI program is the 1989 Edition of the ASME Code,Section XI with no Addenda. The NRC staff requires further information to complete its assessment of RR 12R-50. Reactor Vessel Head-to-Flange Welds 1 RV-03-001 and 2RV-03-001 The ASME Code,Section XI, requires essentially 100 percent volumetric coverage of the examination volume specified in Figure IWB-2500-5 for the reactor pressure vessel (RPV) head-to-flange welds. This examination volume includes the actual weld, as well as the adjacent base metal on either side of the weld extending to a distance of one-half the thickness of the vessel wall from the extremities of the weld crown. To obtain the total examination coverage, the licensee presents the calculated circumference in RR Attachment 1-2, "Weld 1 RV-03-001
," sheet 11 of 19, and RR Attachment 2-2, "Weld 2RV-03-001," sheet 12 of 13, for the 1 RV-03-001 and 2RV-03-001 RPV head-to-flange circumference welds, respectively.
This circumference value is used to determine the total weld metal volume, and subsequently the total inspection volume coverage.
It is not clear to the NRC staff how this circumference value was calculated.
Clarify the circumference calculations presented in the stated attachments. The NRC staff requests that you discuss the extent to which these RPV head-to-flange welds were examined during the first lSI interval, including the percentage of credible volumetric examination coverage that was achieved during these previous examinations.
Discuss any relevant conditions or indications that were found during these previous examinations. Pressurizer Spray and Relief Nozzle-to-Vessel Welds 1 PZR-01-N2, 1 PZR-01-N3, N2 and 2PZR-01-N3 For the pressurizer spray and relief nozzle-to-vessel welds 'I PZR-01-N2, 1 PZR-01-N3, 2PZR-01-N2 and 2PZR-01-N3, discussed in RR Attachments 1-3, "Weld 1PZR-01-N2," 1-4, "Weld 1 PZR-01-N3," 2-3, "Weld 2PZR-01-N2," and 2-4, "Weld 2PZR-01 -N3," were there any indications of the presence of unacceptable flaws or conditions found during the limited scope volumetric examination?
ENCLOSURE
-2Discuss the extent to which these pressurizer spray and relief nozzle-to-vessel welds were examined during the first lSI interval, including the percentage of credible volumetric examination coverage that was achieved during these previous examinations.
Discuss any relevant conditions that were found during these previous examinations. Pipe-to-Valve Circumferential Weld 1RC-17-13 It appears to the NRC staff that there is a typographical error in RR Attachment 1-5, "Weld 1RC-17-13." Section 3 references Figure 4-3, "Examination Volume for Thermal Fatigue Cracking of Sweepolets," from EPRI TR-112657, "Revised Risk-Informed Inservice Inspection Evaluation Procedure." Clarify the RR to reference the correct figure, or confirm that the reference to Figure 4-3 is appropriate. For the pipe-to-valve circumferential weld 1 RC-17-13 discussed in RR Attachments 1-5, indicate whether the limited scope volumetric examination found any presence of indications during the examinations of the subject pipe-to valve circumferential welds. The NRC staff requests that you discuss the extent to which the pipe-to-valve circumferential weld 1 RC-17-13 was examined during the first lSI interval, including the percentage of credible volumetric examination coverage that was achieved during these previous examinations.
Discuss any relevant conditions that were found during these previous examinations.
Include clarification on the consideration of this weld as a "structural discontinuity" during the first lSI inspection interval. RR Attachment 1-5, Section 4 states that the sUbject weld had been examined during the first lSI inspection interval, and was reselected again in the second interval under the risk-informed lSI program. Why was this weld selected for the risk-informed program? Were there any other welds that could have been selected for which greater coverage could have been obtained?
If so, why wasn't one of these welds selected? Steam Generator Auxiliary Feedwater Safe End-to-Nozzle Weld 1SG-05-SGSE-02 It appears to the NRC staff that there is a typographical error in RR Attachment 1-6, "Weld 1SG-05-SGSE-02." Section 3 references Figure 4-3 from EPRI TR-112657.
Clarify the RR to reference the correct figure, or confirm that the reference to Figure 4-3 is appropriate. It appears to the NRC staff that there is another typographical error in RR Attachment 1-6. Section 3 references ASME Code,Section XI, Table IWB-2500-1, in lieu of Table 2500-1, for categorizing this weld. Clarify the RR to reference the correct table. Discuss the extent to which this steam generator auxiliary feedwater safe end-to-nozzle weld was examined during the first lSI interval, including the percentage of credible volumetric examination coverage that was achieved during these previous examinations.
In addition, discuss any relevant conditions that were found during these previous examinations.
-3Indicate if any other adjacent or similar welds were examined for this system. If any, indicate the percentage of credible surface examination coverage that was achieved.
If less than essentially 100 percent coverage was achieved for any of these welds, provide supplemental information justifying why compliance with the ASME Code,Section XI requirements for essentially 100 percent volumetric examination coverage of these welds was impractical. For the steam generator auxiliary feedwater safe end-to-nozzle weld 1 SG-05-SGSE-02, discussed in RR Attachment 1-6, indicate if any presence of indications were found in the subject auxiliary feedwater safe end-to-nozzle welds during the limited scope volumetric examinations. Steam Generator Tube Sheet-to-Stub Barrel Weld 2SG-01-SGC-02 For the steam generator tube sheet-to-stub barrel weld 2SG-01-SGC-02, discussed in RR Attachment 2-5, "Weld 2SG-01-SGC-02," indicate if any presence of indications were found in the subject steam generator tube sheet-to-stub barrel welds during the limited scope volumetric examinations. Discuss the extent to which this steam generator tube sheet-to-stub barrel weld was examined during the first lSI interval, including the percentage of credible volumetric examination coverage that was achieved during these previous examinations.
Discuss any relevant conditions that were found during these previous examinations.
September 14, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB..BRAIDWOOD STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST 12R-50 (TAC NOS. ME1038 AND ME1039)
Dear Mr. Pardee:
By letter to the Nuclear Regulatory Commission (NRC) dated March 31,2009, (Agencywide Documents Access and Management System Accession No. ML090960468), Exelon Generation Company, LLC (the licensee) submitted Relief Request (RR) 12R-50 for the second 10-year inservice inspection interval at Braidwood Station, Units 1 and 2. This RR was submitted due to the impracticality of satisfying the relevant requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI for the specified ASME Code Class 1 and 2 components.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete its review. The specific information requested is addressed in the enclosed Request for Additional Information (RAI). Your staff has agreed to provide a response to this RAI within 45 days after the date of this letter. The NRC staff considers that timely responses to RAls help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1547.
Sincerely, /RA by C. Gratton for M. David/ Marshall J. David, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-456 and STN Request for Additional cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-2 RlF RidsNrrDorlLpl3-2 Resource RidsNrrPMBraidwood Resource RidsNrrLA THarris Resource RidsNrrDciCvib Resource RidsAcrsAcnw_MailCTR Resource RidsRgn3MailCenter Resource RidsOgcRp Resource NRRRidsNrrDorlDpr Resource TMcLellan, NRR HGonzalez, NRR ADAMS Accession Number* ML092510225 "Date of RAI Memo NRR-088 OFFICE LPL3-2/PM LPL3-2/LA DCI/CVIB/BC LPL3-2/BC NAME CGratton for MDavid THarris MMitchell" SCampbell DATE 9/14/09 9/11/09 8/31/09 9/14/09 OFFICIAL RECORD COPY