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MONTHYEARML0724300342007-09-17017 September 2007 Evaluation of Inservice Inspection Program RR 12R-48 Pertaining to Structural Weld Overlays on Pressurizer Spray Project stage: Acceptance Review ML0814007922008-05-19019 May 2008 Pressurizer Weld Overlay Examination Results Related to Braidwood Station Relief Request I2R-48 Project stage: Request 2007-09-17
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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
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Exel6n Nuclear u"a;7 e`Y-f . ~Yl _OFD ~~7T:
May 19, 2008 BW 080050 U. S. Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555-0001 Braidwood Station, Unit 2 Facility Operating License No. NPF-77 NRC Docket No. STN 50-457
Subject:
Pressurizer Weld Overlay Examination Results Related to Braidwood Station Relief Request 1211-48 References : (1) Letter from T. Coutu (Exelon Generation Company, LLC) to U. S. NRC, "Second 10-Year Inservice Inspection Interval, Relief Request 1211-48, Structural Weld Overlays on Pressurizer Spray, Relief, Safety and Surge Nozzle Safe-ends and Associated Alternative Repair Techniques," dated February 23, 2007 (2) Letter from R. Gibbs (U . S. NRC) to C. M. Crane, "Braidwood Station, Units 1 and 2 Evaluation of Inservice Inspection Program Relief Request 1211-48 Pertaining to Structural Weld Overlays on Pressurizer Spray, Relief, Safety, and Surge Nozzle Safe Ends (TAC NOS. MD4590, and MD4591)," dated September 17, 2007 The Reference 1 submittal proposed an alternative (i.e., Relief Request 1211-48), in accordance with 10 CFR 50.55a(a)(3)(i), to the repair/replacement requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 1989 Edition, no Addenda, IWA-4000, for the structural weld overlays on the Braidwood Station pressurizer spray, relief, safety and surge nozzle safe-ends.
Reference 2 documents a commitment made in Reference 1 to provide the details of the ultrasonic examination results of the structural weld overlays on the Braidwood Station Unit 2 pressurizer spray, relief, safety and surge nozzle safe-ends to the NRC within 14 days of the completion of the final ultrasonic examination (UT) . The commitment made in Reference 1 requires that a discussion of any repairs to the overlay material and/or base metal and the reason for the repairs also be discussed within the 14-day report.
May 19, 2008 U. S. Nuclear Regulatory Commission Page 2 in accordance with the Reference 1 commitment, Exelon Generation Company, LLC is providing the details of the repairs to the overlay material and/or base metal, the reason for these repairs, and the UT results of the structural weld overlays on the Braidwood Station Unit 2 pressurizer spray, relief, safety and surge nozzles in an attachment to this letter . The final weld overlay UT conducted during the Unit 2 Spring 2008 refuel outage was completed on May 8, 2008 .
This submittal does not contain any new regulatory commitments.
Should you have any questions concerning this letter, please contact Mr. David Gullott, Regulatory Assurance Manager, at (815) 417-2800 .
Respectfully, Bryan Hanson Site Vice President Braidwood Station Attachment : Unit 2 Spring 2008 Refuel Outage Repairs and Indications for Pressurizer Weld Overlays
ecc : IEMA - Division of Nuclear Safety Site Vice President - Braidwood Station Regulatory Assurance Manager - Braidwood Station Director- Licensing and Regulatory Affairs Manager, Licensing - Byron, Braidwood, and LaSalle County Stations Braidwood Commitment Tracking Coordinator Exelon Document Control Desk Licensing
ATTACHMENT Unit 2 Spring 2008 Refuel Outage Repairs and Indications for Pressurizer Weld Overlays The following is a summary of the results of the Braidwood Unit 2 weld overlay repair and inspection results.
After mirror insulation was removed, an initial bare metal visual (BMV) examination of the existing dissimilar metal welds was performed by Exelon certified VT-2 examiners to confirm there was no existing through-wall leakage. No leakage was identified on any of the six nozzle welds . After the BMV examinations were completed, the existing weld toes were identified and documented . The base metal was ground/cleaned approximately 1 .5 inches beyond the overlay end on the stainless steel pipe/fitting side and a minimum 1 .5 times the nozzle end thickness beyond the overlay end on the nozzle side. The cleaned surfaces were examined by the liquid penetrant (PT) method . Since there were no indications exceeding 1/16" in length documented for any of the six nozzles, subsequent base metal repairs were not required . A sacrificial weld layer was deposited over the existing base metal using ER309L in accordance with Code Case N-504-2 or Inconel 52MS in accordance with Relief Request 12R-48 . The sacrificial layer was examined using visual, PT, and ultrasonic (UT) methods. The remaining layers of Inconel 52MS were applied untif adequate deposit-thickness-was achieved to meet design and final -inspection requirements . Overlay surfaces were prepared to meet surface requirements for UT examinations and final PT and UT examinations were performed.
The following tables provide the weld overlay repair and inspection results for Braidwood Unit 2 pressudzer spray, relief, safety and surge nozzles . Comments regarding in-process repair activities are based on entries provided through the welding vendor's "Anomoly Tracking Sheets" or through final approved NDE data reports.
Sur " e Nozzle (Overlay Weld Number 2PN-01-SW-01 Examination Results Comments Base Metal NRI No evidence of through-wall leakage was noted.
BMV Base Metal NRI No recordable indications were noted (including area where Code Data PT Plate attached b welding was removed),
In-process NRI The argon supply to welding heads (two welding heads were used) was Repair lost and tungsten stub out occurred . Grinding created two areas, 2.25" long X .75" wide X .180" deep and 2.25" long X .80"wide X .09U" deep.
Visual and liquid penetrant examinations were performed on both areas, no indications were noted. Grinding went into layers 2 and 3 (temperbead layers), so 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> hold clock for sure line overlay was reinitiated.
Final Overlay NRI No indications were noted.
PT Final Overlay NRI No recordable indications were noted.
L UT _
S ray Nozzle (Overlay Weld Number 2PN-02-SW-02 Examination Results Comments Base Metal NRI No evidence of through-wall leakage was noted.
BMV Base Metal NRI No recordable indications were noted.
PT Final Overlay NRI No recordable indications were noted.
PT Final Overlay I NRI I No recordable indications were noted.
UT Page 1 of 3
ATTACHMENT Unit 2 Spring 2008 Refuel Outage Repairs and Indications for Pressurizer Weld Overlays Relief PORV Nozzle (Overlay Weld Number 2PN-03-SW-03 Examination Results Comments Base Metal NRI No evidence of through-wall leakage was noted.
BMV Base Metal NRI No indications were noted.
PT Final Overlay NRI No indications were noted.
PT Final Overlay I NRI No recordable indications were noted.
UT "A" Safet Nozzle (Overlay Weld Number 2PN-04-SW-04 Examination Results Comments Base Metal NRI No evidence of through-wall leakage was noted.
BMV Base Metal NRI No indications were noted.
PT In-process NRI The argon supply to welding head was lost and tungsten stub out Repair occurred . Grinding resulted in an area 2.20" long X .700" wide X .200" deep. Visual and liquid penetrant examinations were performed with no indications noted.
Final Overlay Three Three linear indications (.064" X .500", .064" X .190", and .040" X .400").
PT Indications All three indications were flapped out and reexamined by liquid penetrant .
All three indications were reduced to an acceptable length < .0625") .
Final Overlay NRI No recordable indications were noted.
UT "B" Safe Nozzle (Overlay Weld Number 2PN-05-SW-05 Examination Results Comments Base Metal NRI No evidence of through-wail leakage was noted.
BMV Base Metal NRI No recordable indications were noted.
PT In-Process NRI During welding on the P3 nozzle material, welder believed he violated the Repair WPS "bead overlap requirement' associated with beads 7, 8, 11, and 12.
PCI Weld Engineering reviewed the condition . Weld beads 6 through 12 were ground from the nozzle and a liquid penetrant examination was performed and accepted, allowing welding to continue.
In-Process NRI The argon supply to welding head was lost and tungsten stub out Repair occurred. Grinding resulted in an area 2.50" long X .600" wide X .200" deep. Visual and liquid penetrant examinations were performed with no indications noted.
Final Overlay NRI No indications were noted.
PT Final Overlay NRI ( No recordable indications were noted.
UT
ATTACHMENT Unit 2 Spring 2008 Refuel Outage Repairs and Indications for Pressurizer Weld Overlays "C" Safet Nozzle (Overlay Weld Number 2PN-06-SW-06 Examination Results Comments Base Metal NRI No evidence of through-wall leakage was noted.
BMW Base Metal NRI No indications were noted.
PT In-Process NRI The argon supply to welding head was lost and tungsten stub out Repair occurred. Grinding resulted in an area 2.00" long X .800" wide X .25Y' deep. Visual and liquid penetrant examinations were performed with no indications noted .
Final Overlay NRI No indications were noted.
PT Final Overlay NRI No recordable indications were noted.
NRI - No recordable indication.