Letter Sequence Request |
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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
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ML24025C7242024-01-29029 January 2024
Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000456/2024002; 05000457/2024002
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2B Auxiliary Feedwater Pump Diesel Fuel Oil Dilution Report 05000457/2023011 and Preliminary Greater than Green Finding and Apparent Violation
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Issuance of Amendments Regarding Adoption of TSTF-370
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Request for Information for an NRC Post-Approval Site Inspection for License Renewal Inspection Report 05000546/2024010
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Review of the Fall 2022 Steam Generator Tube Inspection Report
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Supplement - Braidwood Security Rule Exemption Request ISFSI Docket No. Reference
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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
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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
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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
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Confirmation of Initial License Examination
IR 05000456/20230022023-08-0303 August 2023
Integrated Inspection Report 05000456/2023002 and 05000457/2023002
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Issuance of Amendment Nos. 232 and 232 Revision of Technical Specifications for the Ultimate Heat Sink
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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
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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
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2024-02-02
[Table view] |
Text
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.
