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| issue date = 07/24/2012
| issue date = 07/24/2012
| title = 2012 Inservice Inspection Summary Report
| title = 2012 Inservice Inspection Summary Report
| author name = Jordan A J
| author name = Jordan A
| author affiliation = Dominion Energy Kewaunee, Inc
| author affiliation = Dominion Energy Kewaunee, Inc
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:Dominion Energy Kewaunee, Inc. :"Dominion N490 Hwy 42, Kewaunee, WI 54216 .ftminlll Web Address: www.dom.com U. S. Nuclear Regulatory Commission Serial No. 12-426 Attention:
{{#Wiki_filter:Dominion Energy Kewaunee, Inc.                                 :"Dominion N490 Hwy 42, Kewaunee, WI 54216                               .     ftminlll Web Address: www.dom.com U. S. Nuclear Regulatory Commission                         Serial No. 12-426 Attention: Document Control Desk                             KPS/LIC/NW: RO Washington, DC 20555                                         Docket No. 50-305 2JUL 242012         License No. DPR-43 DOMINION ENERGY KEWAUNEE, INC.
Document Control Desk KPS/LIC/NW:
KEWAUNEE POWER STATION 2012 INSERVICE INSPECTION  
RO Washington, DC 20555 Docket No. 50-305 2JUL 242012 License No. DPR-43 DOMINION ENERGY KEWAUNEE, INC.KEWAUNEE POWER STATION 2012 INSERVICE INSPECTION  


==SUMMARY==
==SUMMARY==
REPORT As required by American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section X1, 10 CFR 50.55a, and Wisconsin Administrative Code, Department of Safety and Professional Services, SPS 341.55(3), various inservice inspection (ISI)examinations were performed during the 2012 refueling outage at the Kewaunee Power Station (KPS). The refueling outage took place from April 6, 2012 through May 10, 2012.This letter transmits the ISI Summary Report as required by paragraph IWA-6230 of ASME Section X1. ISI activities performed at KPS during the period July 28, 2011 through April 5, 2012 are also covered by this report.Two separate ASME Section Xl ISI programs are implemented at KPS. One program is for pressure retaining piping/vessels and component supports, and the other program is for the metal containment (MC). The 2012 refueling outage inservice inspections met the requirements of these two distinct inspection program intervals as listed below:* Class 1, Class 2, and Class 3 component inspections were performed for the second inspection outage of the third period of the fourth interval.
REPORT As required by American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section X1, 10 CFR 50.55a, and Wisconsin Administrative Code, Department of Safety and Professional Services, SPS 341.55(3), various inservice inspection (ISI) examinations were performed during the 2012 refueling outage at the Kewaunee Power Station (KPS). The refueling outage took place from April 6, 2012 through May 10, 2012.
These inspections met the requirements of ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda with implementation in accordance with the KPS Fourth Ten-Year ISI Program 2004-2014." Class MC component inspections were performed for the second inspection outage of the second period of the second interval.
This letter transmits the ISI Summary Report as required by paragraph IWA-6230 of ASME Section X1. ISI activities performed at KPS during the period July 28, 2011 through April 5, 2012 are also covered by this report.
These inspections met the requirements of ASME Boiler and Pressure Vessel Code Section X1, 2001 Edition, 2003 Addenda with implementation in accordance with the KPS Second Ten-Year ISI Class MC Program 2006-2016.
Two separate ASME Section Xl ISI programs are implemented at KPS. One program is for pressure retaining piping/vessels and component supports, and the other program is for the metal containment (MC). The 2012 refueling outage inservice inspections met the requirements of these two distinct inspection program intervals as listed below:
The following examinations and tests were performed for Class 1, Class 2, and Class 3 components and their supports:* Pressurizer heater penetrations" Steam generator nozzle to safe end welds* Steam generator channel head to tubesheet weld* Class 1 and Class 2 piping welds* Class 1, Class 2 and Class 3 piping and component supports and hangers" Class 1 valves Serial No. 12-426 Page 2 of 3" Class 1 and Class 2 steam generator primary manway bolting, pressurizer manway bolting, flange bolting and valve bonnet bolting* Steam generator main steam nozzle to vessel weld and main steam nozzle inner radius* Letdown heat exchanger circumferential weld* Charging pump pulsation dampener circumferential weld" Seal water injection filter circumferential weld" Regenerative heat exchanger circumferential weld and welded attachment
* Class 1, Class 2, and Class 3 component inspections were performed for the second inspection outage of the third period of the fourth interval.       These inspections met the requirements of ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda with implementation in accordance with the KPS Fourth Ten-Year ISI Program 2004-2014.
* Class 2 safety injection pump casing weld" Class 2 preservice of safety injection piping and supports" Class 2 preservice of residual heat removal piping and supports* Class 1 system leakage test" Class 2 and Class 3 system leakage tests The following items were examined for the Class MC reactor building containment vessel: " Accessible surface areas" Bolted connections Hydraulic snubbers were examined as required by KPS Snubber Program.Documentation summarizing the ISI activities performed during the KPS 2012 refueling outage and associated results is provided in attachments 1-5 of this letter. The final reports for each of these examinations are maintained in the Quality Assurance/Quality Control Records Vault at KPS.The next refueling outage at KPS is tentatively scheduled for the fall of 2013.If you have questions or require additional information, please feel free to contact Mr. Jack Gadzala at 920-388-8604.
    " Class MC component inspections were performed for the second inspection outage of the second period of the second interval.         These inspections met the requirements of ASME Boiler and Pressure Vessel Code Section X1, 2001 Edition, 2003 Addenda with implementation in accordance with the KPS Second Ten-Year ISI Class MC Program 2006-2016.
Very truly yours, Site Vii President, Kewaunee Power Station Commitments made by this letter: NONE Serial No. 12-426 Page 3 of 3 Attachments:
The following examinations and tests were performed for Class 1, Class 2, and Class 3 components and their supports:
* Pressurizer heater penetrations
    " Steam generator nozzle to safe end welds
* Steam generator channel head to tubesheet weld
* Class 1 and Class 2 piping welds
* Class 1, Class 2 and Class 3 piping and component supports and hangers
    " Class 1 valves
 
Serial No. 12-426 Page 2 of 3
    " Class 1 and Class 2 steam generator primary manway bolting, pressurizer manway bolting, flange bolting and valve bonnet bolting
* Steam generator main steam nozzle to vessel weld and main steam nozzle inner radius
* Letdown heat exchanger circumferential weld
* Charging pump pulsation dampener circumferential weld
    " Seal water injection filter circumferential weld
    " Regenerative heat exchanger circumferential weld and welded attachment
* Class 2 safety injection pump casing weld
    " Class 2 preservice of safety injection piping and supports
    " Class 2 preservice of residual heat removal piping and supports
* Class 1 system leakage test
    " Class 2 and Class 3 system leakage tests The following items were examined for the Class MC reactor building containment vessel:
    " Accessible surface areas
    " Bolted connections Hydraulic snubbers were examined as required by KPS Snubber Program.
Documentation summarizing the ISI activities performed during the KPS 2012 refueling outage and associated results is provided in attachments 1-5 of this letter. The final reports for each of these examinations are maintained in the Quality Assurance/Quality Control Records Vault at KPS.
The next refueling outage at KPS is tentatively scheduled for the fall of 2013.
If you have questions or require additional information, please feel free to contact Mr. Jack Gadzala at 920-388-8604.
Very truly yours, Site Vii   President, Kewaunee Power Station Commitments made by this letter: NONE
 
Serial No. 12-426 Page 3 of 3 Attachments:
: 1. Summary of Relevant Conditions and Disposition.
: 1. Summary of Relevant Conditions and Disposition.
: 2. Examination Summary for Class 1, Class 2, and Class 3 Inservice Inspection Program for Fourth Ten-Year Interval.3. Examination Summary for Class MC Inservice Inspection Program For Second Ten-Year Interval.4. Summary of Examinations that were Limited by Geometric, Metallurgical, or Design/Access Restrictions (10 Total).5. Form OAR-1 Owner's Activity Report; Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service; and Table 2 Abstract of Repair/Replacement Activities Required for Continued Service.cc: Regional Administrator U. S. Nuclear Regulatory Commission Region III 2443 Warrenville Road Suite 210 Lisle, Illinois 60532-4352 Mr. K. D. Feintuch Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station Serial No. 12-426 ATTACHMENT 1 2012 INSERVICE INSPECTION  
: 2. Examination Summary for Class 1, Class 2, and Class 3 Inservice Inspection Program for Fourth Ten-Year Interval.
: 3. Examination Summary for Class MC Inservice Inspection Program For Second Ten-Year Interval.
: 4. Summary of Examinations that were Limited by Geometric, Metallurgical, or Design/Access Restrictions (10 Total).
: 5. Form OAR-1 Owner's Activity Report; Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service; and Table 2 Abstract of Repair/Replacement Activities Required for Continued Service.
cc:     Regional Administrator U. S. Nuclear Regulatory Commission Region III 2443 Warrenville Road Suite 210 Lisle, Illinois 60532-4352 Mr. K. D. Feintuch Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station
 
Serial No. 12-426 ATTACHMENT 1 2012 INSERVICE INSPECTION  


==SUMMARY==
==SUMMARY==
REPORT  
REPORT


==SUMMARY==
==SUMMARY==
OF RELEVANT CONDITIONS AND DISPOSITION KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
OF RELEVANT CONDITIONS AND DISPOSITION KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
Serial No. 12-426 Docket No. 50-305 Attachment 1 Page 1 of 1  
 
Serial No. 12-426 Docket No. 50-305 Attachment 1 Page 1 of 1


==SUMMARY==
==SUMMARY==
OF RELEVANT CONDITIONS AND DISPOSITION Type or Location of Relevant Examination No. of Relevant Conditions Conditions Method (Description)
OF RELEVANT CONDITIONS AND DISPOSITION Type or Location of Relevant           Examination       No. of Relevant Conditions Conditions                     Method                 (Description)
: 1. Piping Supports and Hangers Visual (VT-3) 6 (Items)2. Valve Bonnet Bolting Visual (V'T-3) 2 (Items)3. System Leakage Pressure Tests Visual (VT-2) 19 (Items)Dispositioning of Class 1, Class 2, and Class 3 relevant conditions have been completed in accordance with the rules of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda for Fourth Ten-Year Interval examinations.
: 1. Piping Supports and Hangers           Visual (VT-3)               6 (Items)
Dispositioning of Class MC relevant conditions has been completed in accordance with the rules of ASME Boiler and Pressure Vessel Code Section Xl, 2001 Edition, 2003 Addenda for Second Ten-Year Interval examinations.
: 2. Valve Bonnet Bolting                   Visual (V'T-3)             2 (Items)
Applicable codes, standards, and engineering criteria were used to disposition indications associated with the non-code-required examinations.
: 3. System Leakage Pressure Tests         Visual (VT-2)               19 (Items)
Relevant conditions for Class 1, Class 2, Class 3, and Class MC components have been summarized with disposition as noted below: 1. Visual (VT-3) relevant conditions on 3" auxiliary feedwater piping supports FDW-H41 and FDW-H41 B were evaluated and accepted by Kewaunee Power Station (KPS)Engineering and Inservice Inspection (ISI) personnel.
Dispositioning of Class 1, Class 2, and Class 3 relevant conditions have been completed in accordance with the rules of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda for Fourth Ten-Year Interval examinations. Dispositioning of Class MC relevant conditions has been completed in accordance with the rules of ASME Boiler and Pressure Vessel Code Section Xl, 2001 Edition, 2003 Addenda for Second Ten-Year Interval examinations. Applicable codes, standards, and engineering criteria were used to disposition indications associated with the non-code-required examinations. Relevant conditions for Class 1, Class 2, Class 3, and Class MC components have been summarized with disposition as noted below:
All dispositioned relevant conditions were reviewed by the Authorized Nuclear Inservice Inspector.
: 1. Visual (VT-3) relevant conditions on 3" auxiliary feedwater piping supports FDW-H41 and FDW-H41 B were evaluated and accepted by Kewaunee Power Station (KPS)
: 2. Visual (VT-3) relevant condition on 2" safety injection support RSI-H7 was evaluated and accepted by KPS Engineering and ISI personnel.
Engineering and Inservice Inspection (ISI) personnel. All dispositioned relevant conditions were reviewed by the Authorized Nuclear Inservice Inspector.
The dispositioned relevant condition was reviewed by the Authorized Nuclear Inservice Inspector.
: 2. Visual (VT-3) relevant condition on 2" safety injection support RSI-H7 was evaluated and accepted by KPS Engineering and ISI personnel. The dispositioned relevant condition was reviewed by the Authorized Nuclear Inservice Inspector.
: 3. Visual (VT-3) relevant conditions on 6" main steam valve supports MSRH-H1 and MSRH-H2 were evaluated, repaired, and accepted by KPS Engineering and ISI personnel.
: 3. Visual (VT-3) relevant conditions on 6" main steam valve supports MSRH-H1 and MSRH-H2 were evaluated, repaired, and accepted by KPS Engineering and ISI personnel. All dispositioned relevant conditions were reviewed by the Authorized Nuclear Inservice Inspector.
All dispositioned relevant conditions were reviewed by the Authorized Nuclear Inservice Inspector.
: 4. Visual (VT-3) relevant condition on 8" Service Water Support RSW-H62 was evaluated, repaired, and accepted by KPS Engineering and ISI personnel. The dispositioned relevant condition was reviewed by the Authorized Nuclear Inservice Inspector.
: 4. Visual (VT-3) relevant condition on 8" Service Water Support RSW-H62 was evaluated, repaired, and accepted by KPS Engineering and ISI personnel.
: 5. Visual (VT-3) relevant conditions recorded on valve bonnet bolting (2 valves), were evaluated and accepted by KPS Engineering and ISI personnel. The dispositioned relevant conditions were reviewed by the Authorized Nuclear Inservice Inspector.
The dispositioned relevant condition was reviewed by the Authorized Nuclear Inservice Inspector.
: 6. Visual (VT-2) relevant conditions recorded during system leakage pressure tests (19 Items) were evaluated and accepted by KPS Engineering and ISI personnel. The dispositioned relevant condition was reviewed by the Authorized Nuclear Inservice Inspector.
: 5. Visual (VT-3) relevant conditions recorded on valve bonnet bolting (2 valves), were evaluated and accepted by KPS Engineering and ISI personnel.
 
The dispositioned relevant conditions were reviewed by the Authorized Nuclear Inservice Inspector.
: 6. Visual (VT-2) relevant conditions recorded during system leakage pressure tests (19 Items) were evaluated and accepted by KPS Engineering and ISI personnel.
The dispositioned relevant condition was reviewed by the Authorized Nuclear Inservice Inspector.
Serial No. 12-426 ATTACHMENT 2 2012 INSERVICE INSPECTION  
Serial No. 12-426 ATTACHMENT 2 2012 INSERVICE INSPECTION  


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==SUMMARY==
==SUMMARY==
FOR CLASS 1, CLASS 2, AND CLASS 3 INSERVICE INSPECTION PROGRAM FOR FOURTH TEN-YEAR INTERVAL KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
FOR CLASS 1, CLASS 2, AND CLASS 3 INSERVICE INSPECTION PROGRAM FOR FOURTH TEN-YEAR INTERVAL KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION 4TH INTERVAL:
 
3RD PERIOD: 2ND OUTAGE 2012 EXAMINATION  
KEWAUNEE POWER STATION 4TH INTERVAL: 3RD PERIOD: 2ND OUTAGE 2012 EXAMINATION  


==SUMMARY==
==SUMMARY==
INTRODUCTION An Inservice Inspection (ISI) Program (Scheduled and Augmented) was performed at the Kewaunee Power Station from July 28, 2011 through April 5, 2012 (Non-Refueling Outage) and from April 6, 2012 through May 10, 2012 (Closing of GI following Refueling Outage) by Kewaunee Power Station personnel, Lambert, MacGill, and Thomas, Inc.(LMT Inc.) and Industrial Testing Laboratories Services (ITLS) examination personnel.
INTRODUCTION An Inservice Inspection (ISI) Program (Scheduled and Augmented) was performed at the Kewaunee Power Station from July 28, 2011 through April 5, 2012 (Non-Refueling Outage) and from April 6, 2012 through May 10, 2012 (Closing of GI following Refueling Outage) by Kewaunee Power Station personnel, Lambert, MacGill, and Thomas, Inc.(LMT Inc.) and Industrial Testing Laboratories Services (ITLS) examination personnel.
Examinations were performed to satisfy the requirements of: " ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda" Westinghouse NASL-06-8:
Examinations were performed to satisfy the requirements of:
Pressurizer Heater Sleeve Cracking* Reactor Vessel Upper Internals Guide Tube Guide Cards per MRP-227-A:
" ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda
Pressurized Water Reactor Internals Inspection and Evaluation Guidelines The Inservice Inspection Program Plan and Augmented Inspection Program Plan located under Tab C were prepared by Kewaunee Power Station for the 4th Interval:
" Westinghouse NASL-06-8: Pressurizer Heater Sleeve Cracking
3rd Period: 2nd Outage as identified in the Kewaunee Power Station Fourth 10-Year Inservice Inspection (ISI) Program 2004 -2014. Examinations during this Refueling Outage were performed to continue 4th Interval; 3rd Period Examination Requirements of ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda and Kewaunee Power Station Fourth 10-Year Inservice Inspection (ISI) Program 2004-2014.
* Reactor Vessel Upper Internals Guide Tube Guide Cards per MRP-227-A: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines The Inservice Inspection Program Plan and Augmented Inspection Program Plan located under Tab C were prepared by Kewaunee Power Station for the 4th Interval: 3rd Period: 2nd Outage as identified in the Kewaunee Power Station Fourth 10-Year Inservice Inspection (ISI) Program 2004 - 2014. Examinations during this Refueling Outage were performed to continue 4th Interval; 3rd Period Examination Requirements of ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda and Kewaunee Power Station Fourth 10-Year Inservice Inspection (ISI) Program 2004-2014.
The following items were examined: " Pressurizer Heater Penetrations
The following items were examined:
* Steam Generator Nozzle to Safe End Welds" Steam Generator Channel Head to Tubesheet Weld" Class 1 and Class 2 Piping Welds* Class 1, Class 2 and Class 3 Piping and Component Supports and Hangers" Class 1 Valves" Class 1 and Class 2 Steam Generator Primary Manway Bolting, Pressurizer Manway Bolting, Flange Bolting and Valve Bonnet Bolting* Steam Generator Main Steam Nozzle to Vessel Weld and Main Steam Nozzle Inner Radius" Letdown Heat Exchanger Circumferential Weld Page 1 of 4  
" Pressurizer Heater Penetrations
" Charging Pump Pulsation Dampener Circumferential Weld* Seal Water Injection Filter Circumferential Weld* Regenerative Heat Exchanger Circumferential Weld and Welded Attachment" Class 2 Safety Injection Pump Casing Weld" Class 2 Preservice of Safety Injection Piping and Supports* Class 2 Preservice of Residual Heat Removal Piping and Supports" Class 1 System Leakage Test" Class 2 and Class 3 System Leakage Tests EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.
* Steam Generator Nozzle to Safe End Welds
Some of the arrangements and details of the Kewaunee Power Station Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established.
" Steam Generator Channel Head to Tubesheet Weld
Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions.
" Class 1 and Class 2 Piping Welds
In each case, the occurrence and cause of the limitation was documented.
* Class 1, Class 2 and Class 3 Piping and Component Supports and Hangers
In all cases, the maximum achievable amount of surface or volume was examined.Witnessing and surveillance of the examinations were conducted by personnel from: Nuclear Regulatory Commission and Hartford Steam Boiler Inspection and Insurance Company of CT.RESULTS Examinations resulted with the following Relevant Conditions being noted on the basis of procedure recording criteria.Relevant Conditions detected during the 2012 Refueling Outage are listed in Table 1 along with a brief summary. Specific data relative to all Relevant Conditions and their disposition by either (1) corrective measures or, (2) acceptance by ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda Acceptance Criteria or Evaluation are located in Tab F of the Final Report.Page 2 of 4 TABLE 1 TYPE OR LOCATION OF NO. OF RELEVANT RELEVANT CONDITIONS METHOD CONDITIONS" Piping Supports and Hangers Visual (VT-3) 6 Items" Valve Bonnet Bolting Visual (VT-3) 2 Items" System Leakage Pressure Tests Visual (VT-2) 19 Items 1. Visual (VT-3) Relevant Conditions on 3" Auxiliary Feedwater Piping Supports FDW-H41 and FDW-H41B were Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
" Class 1 Valves
" Class 1 and Class 2 Steam Generator Primary Manway Bolting, Pressurizer Manway Bolting, Flange Bolting and Valve Bonnet Bolting
* Steam Generator Main Steam Nozzle to Vessel Weld and Main Steam Nozzle Inner Radius
" Letdown Heat Exchanger Circumferential Weld Page 1 of 4
 
" Charging Pump Pulsation Dampener Circumferential Weld
* Seal Water Injection Filter Circumferential Weld
* Regenerative Heat Exchanger Circumferential Weld and Welded Attachment
" Class 2 Safety Injection Pump Casing Weld
" Class 2 Preservice of Safety Injection Piping and Supports
* Class 2 Preservice of Residual Heat Removal Piping and Supports
" Class 1 System Leakage Test
" Class 2 and Class 3 System Leakage Tests EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.
Some of the arrangements and details of the Kewaunee Power Station Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established. Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In each case, the occurrence and cause of the limitation was documented. In all cases, the maximum achievable amount of surface or volume was examined.
Witnessing and surveillance of the examinations were conducted by personnel from: Nuclear Regulatory Commission and Hartford Steam Boiler Inspection and Insurance Company of CT.
RESULTS Examinations resulted with the following Relevant Conditions being noted on the basis of procedure recording criteria.
Relevant Conditions detected during the 2012 Refueling Outage are listed in Table 1 along with a brief summary. Specific data relative to all Relevant Conditions and their disposition by either (1) corrective measures or, (2) acceptance by ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda Acceptance Criteria or Evaluation are located in Tab F of the Final Report.
Page 2 of 4
 
TABLE 1 TYPE OR LOCATION OF                                                 NO. OF RELEVANT RELEVANT CONDITIONS                           METHOD                     CONDITIONS
" Piping Supports and Hangers                   Visual (VT-3)                   6 Items
" Valve Bonnet Bolting                           Visual (VT-3)                   2 Items
" System Leakage Pressure Tests                 Visual (VT-2)                   19 Items
: 1. Visual (VT-3) Relevant Conditions on 3" Auxiliary Feedwater Piping Supports FDW-H41 and FDW-H41B were Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
: 2. Visual (VT-3) Relevant Condition on 2" Safety Injection Support RSI-H7 was Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
: 2. Visual (VT-3) Relevant Condition on 2" Safety Injection Support RSI-H7 was Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
: 3. Visual (VT-3) Relevant Conditions on 6" Main Steam Valve Supports MSRH-H1 and MSRH-H2 were Evaluated, Repaired and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
: 3. Visual (VT-3) Relevant Conditions on 6" Main Steam Valve Supports MSRH-H1 and MSRH-H2 were Evaluated, Repaired and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
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: 5. Visual (VT-3) Relevant Conditions recorded on Valve Bonnet Bolting (2 Valves), were Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
: 5. Visual (VT-3) Relevant Conditions recorded on Valve Bonnet Bolting (2 Valves), were Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
: 6. Visual (VT-2) Relevant Conditions recorded during System Leakage Pressure Tests (19 Items) were: Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
: 6. Visual (VT-2) Relevant Conditions recorded during System Leakage Pressure Tests (19 Items) were: Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
Page 3 of 4  
Page 3 of 4


==SUMMARY==
==SUMMARY==
An Inservice Inspection Program was performed at the Kewaunee Power Station from July 28, 2011 through April 5, 2012 (Non-Refueling Outage) and from April 6, 2012 through May 10, 2012 (Closing of GI following Refueling Outage). Examinations were performed as scheduled in the Kewaunee Power Station Fourth 10-Year Inservice Inspection (ISI) Program 2004 -2014 to continue examinations for the 4th Interval; 3rd Period. A total of 27 Relevant Conditions were detected.
 
All Relevant Conditions were corrected or accepted by ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda Acceptance Criteria or Evaluation requirements.
An Inservice Inspection Program was performed at the Kewaunee Power Station from July 28, 2011 through April 5, 2012 (Non-Refueling Outage) and from April 6, 2012 through May 10, 2012 (Closing of GI following Refueling Outage). Examinations were performed as scheduled in the Kewaunee Power Station Fourth 10-Year Inservice Inspection (ISI) Program 2004 -2014 to continue examinations for the 4th Interval; 3rd Period. A total of 27 Relevant Conditions were detected. All Relevant Conditions were corrected or accepted by ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda Acceptance Criteria or Evaluation requirements.
Phillip E. Bukes Date Engineering Programs Inservice Inspection Program Owner Page 4 of 4 Serial No. 12-426 ATTACHMENT 3 2012 INSERVICE INSPECTION  
Phillip E. Bukes                 Date Engineering Programs Inservice Inspection Program Owner Page 4 of 4
 
Serial No. 12-426 ATTACHMENT 3 2012 INSERVICE INSPECTION  


==SUMMARY==
==SUMMARY==
Line 94: Line 150:
==SUMMARY==
==SUMMARY==
FOR CLASS MC INSERVICE INSPECTION PROGRAM FOR SECOND TEN-YEAR INTERVAL KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
FOR CLASS MC INSERVICE INSPECTION PROGRAM FOR SECOND TEN-YEAR INTERVAL KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION 2ND INTERVAL:
 
2ND PERIOD: 2ND OUTAGE 2012 EXAMINATION  
KEWAUNEE POWER STATION 2ND INTERVAL: 2ND PERIOD: 2ND OUTAGE 2012 EXAMINATION  


==SUMMARY==
==SUMMARY==
INTRODUCTION An Inservice Inspection (ISI) Program for the Class MC Reactor Building Containment Vessel was performed at the Kewaunee Power Station from April 6, 2012 through May 10, 2012 (Closing of G I following Refueling Outage) by Kewaunee Power Station and Lambert, MacGill and Thomas Inc. examination personnel.
INTRODUCTION An Inservice Inspection (ISI) Program for the Class MC Reactor Building Containment Vessel was performed at the Kewaunee Power Station from April 6, 2012 through May 10, 2012 (Closing of G I following Refueling Outage) by Kewaunee Power Station and Lambert, MacGill and Thomas Inc. examination personnel.
Examinations were performed to satisfy the requirements of:-ASME Boiler and Pressure Vessel Code Section XI, 2001 Edition, 2003 Addenda The Inservice Inspection Program Plan located under Tab C was prepared by Kewaunee Power Station for the 2nd Interval; 2nd Period; 2nd Outage as identified in the Kewaunee Power Station Second 10-Year Inservice Inspection (ISI) Program 2006-2016.
Examinations were performed to satisfy the requirements of:
Examinations during this Refueling Outage were performed to complete the 2nd Interval, 2nd Period examination requirements of ASME Boiler and Pressure Vessel Code Section XI, 2001 Edition, 2003 Addenda and Kewaunee Power Station Second 10-Year Inservice Inspection (ISI) Program 2006-2016.
- ASME Boiler and Pressure Vessel Code Section XI, 2001 Edition, 2003 Addenda The Inservice Inspection Program Plan located under Tab C was prepared by Kewaunee Power Station for the 2nd Interval; 2nd Period; 2nd Outage as identified in the Kewaunee Power Station Second 10-Year Inservice Inspection (ISI) Program 2006-2016. Examinations during this Refueling Outage were performed to complete the 2nd Interval, 2nd Period examination requirements of ASME Boiler and Pressure Vessel Code Section XI, 2001 Edition, 2003 Addenda and Kewaunee Power Station Second 10-Year Inservice Inspection (ISI) Program 2006-2016.
The following items were examined for the Class MC Reactor Building Containment Vessel: " Accessible Surface Areas* Bolted Connections EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.
The following items were examined for the Class MC Reactor Building Containment Vessel:
Page 1 of 2 Some of the arrangements and details of the Kewaunee Power Station Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established.
  "Accessible Surface Areas
Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions.
* Bolted Connections EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.
In all cases the maximum achievable amount of surface or volume was examined.Witnessing and surveillance of the examinations were conducted by Hartford Steam Boiler Inspection and Insurance Company of CT.RESULTS Examinations resulted in No Relevant Conditions being noted on the basis of procedure recording criteria.
Page 1 of 2
 
Some of the arrangements and details of the Kewaunee Power Station Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established. Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In all cases the maximum achievable amount of surface or volume was examined.
Witnessing and surveillance of the examinations were conducted by Hartford Steam Boiler Inspection and Insurance Company of CT.
RESULTS Examinations resulted in No Relevant Conditions being noted on the basis of procedure recording criteria.


==SUMMARY==
==SUMMARY==
An Inservice Inspection Program for the Class MC Reactor Building Containment Vessel was performed at the Kewaunee Power Station from April 6, 2012 through May 10, 2012 (Closing of G 1 following Refueling Outage). Examinations were performed as scheduled in the Kewaunee Power Station Second 10-Year Inservice Inspection (ISI) Program 2006-2016.
 
Examinations resulted in No Relevant Conditions being noted on the basis of procedure recording criteria.)',L e13a&eaM Phillip E. Bukes Engineering Programs Inservice Inspection Program Owner Date Page 2 of 2 Serial No. 12-426 ATTACHMENT 4 2012 INSERVICE INSPECTION  
An Inservice Inspection Program for the Class MC Reactor Building Containment Vessel was performed at the Kewaunee Power Station from April 6, 2012 through May 10, 2012 (Closing of G 1 following Refueling Outage). Examinations were performed as scheduled in the Kewaunee Power Station Second 10-Year Inservice Inspection (ISI) Program 2006-2016. Examinations resulted in No Relevant Conditions being noted on the basis of procedure recording criteria.
                                          )',L e13a&eaM Phillip E. Bukes                           Date Engineering Programs Inservice Inspection Program Owner Page 2 of 2
 
Serial No. 12-426 ATTACHMENT 4 2012 INSERVICE INSPECTION  


==SUMMARY==
==SUMMARY==
REPORT  
REPORT


==SUMMARY==
==SUMMARY==
OF EXAMINATIONS THAT WERE LIMITED BY GEOMETRIC, METALLURGICAL, OR DESIGN/ACCESS RESTRICTIONS (10 TOTAL)KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
OF EXAMINATIONS THAT WERE LIMITED BY GEOMETRIC, METALLURGICAL, OR DESIGN/ACCESS RESTRICTIONS (10 TOTAL)
Serial No. 12-426 Docket No. 50-305 Attachment 4 Page 1 of 1  
KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
 
Serial No. 12-426 Docket No. 50-305 Attachment 4 Page 1 of 1


==SUMMARY==
==SUMMARY==
OF EXAMINATIONS THAT WERE LIMITED BY GEOMETRIC, METALLURGICAL, OR DESIGN/ACCESS RESTRICTIONS Year Component Identification Method of % Recorded as Not Examination Examined and Limitation 30.0%2012 Regenerative Heat Exchanger UT Rigid Clamp Support Tubesheet To Shell Weld ARG-W1 1 and 3 Welded Lugs 59.0%2012 Letdown Heat Exchanger Head UT 2 Integrally Welded Circumferential Weld AHNR-W2 Attachments and 2 2" Nozzles 23.0%2012 Seal Water Injection Filter 1A Shell UT Welded Name Plate and Circumferential Weld AFSI-Wl Integrally Welded Support For Filter Cover 50.0%2012 Circumferential Pipe Weld SI-W52 on UT Reducer To Pipe Weld 4" Safety Injection
OF EXAMINATIONS THAT WERE LIMITED BY GEOMETRIC, METALLURGICAL, OR DESIGN/ACCESS RESTRICTIONS Year       Component Identification         Method of       % Recorded as Not Examination   Examined and Limitation 30.0%
_Configuration 17.0%2012 Circumferential Pipe Weld RHR-W229 UT Pipe To Tee Weld on 8" Residual Heat Removal Configuration 50.0%2012 Circumferential Pipe Weld RHR-W436 UT Valve To Pipe Weld on 12" Residual Heat Removal Configuration 54.0%2012 Circumferential Pipe Weld RHR-W437 UT Pipe To Valve Weld on 12" Residual Heat Removal Configuration and 1 2 Gamma Plugs 50.0%2012 Circumferential Pipe Weld RHR-W438 UT Valve To Pipe Weld on 12" Residual Heat Removal Configuration 54.0%2012 Circumferential Pipe Weld RHR-W439 UT Pipe To Valve Weld on 12" Residual Heat Removal Configuration and 2 Gamma Plugs Circumferential Pipe Weld AFW-W192 15.0%2012 Crm3" Aurenial Peed UT Flange To Pipe Weld on Auxiliary Feedwater Configuration Serial No. 12-426 ATTACHMENT 5 2012 INSERVICE INSPECTION  
2012 Regenerative Heat Exchanger                     UT Rigid Clamp Support Tubesheet To Shell Weld ARG-W1 1                     and 3 Welded Lugs 59.0%
2012 Letdown Heat Exchanger Head                     UT   2 Integrally Welded Circumferential Weld AHNR-W2                             Attachments and 2 2" Nozzles 23.0%
2012 Seal Water Injection Filter 1A Shell             UT Welded Name Plate and Circumferential Weld AFSI-Wl                       Integrally Welded Support For Filter Cover 50.0%
2012 Circumferential Pipe Weld SI-W52 on               UT   Reducer To Pipe Weld 4" Safety Injection                 _Configuration 17.0%
2012 Circumferential Pipe Weld RHR-W229               UT     Pipe To Tee Weld on 8" Residual Heat Removal                                 Configuration 50.0%
2012 Circumferential Pipe Weld RHR-W436               UT   Valve To Pipe Weld on 12" Residual Heat Removal                                 Configuration 54.0%
2012 Circumferential Pipe Weld RHR-W437               UT     Pipe To Valve Weld on 12" Residual Heat Removal                               Configuration and 1                                                         2 Gamma Plugs 50.0%
2012 Circumferential Pipe Weld RHR-W438               UT   Valve To Pipe Weld on 12" Residual Heat Removal                                 Configuration 54.0%
2012 Circumferential Pipe Weld RHR-W439               UT     Pipe To Valve Weld on 12" Residual Heat Removal                               Configuration and 2 Gamma Plugs Circumferential Pipe Weld AFW-W192                             15.0%
2012 Crm3" Aurenial Peed                               UT   Flange To Pipe Weld on   Auxiliary Feedwater                                   Configuration
 
Serial No. 12-426 ATTACHMENT 5 2012 INSERVICE INSPECTION  


==SUMMARY==
==SUMMARY==
REPORT FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINED SERVICE TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
REPORT FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINED SERVICE TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.
S DoeminiW Form OAR-1 Owner's Activity Report Report Number: 2012 Refueling Outage Class 1, Class 2 and Class 3 Plant Kewaunee Power Station, N490 Highway 42, Kewaunee, Wisconsin 54216-9511 Unit No. No.1 Commercial service date June 16,1974 Refueling outage no. K1R32 (if applicable)
 
Current inspection interval 4th (1 st, 2 n, 3 T , 4 th, other)Current inspection period 3rd (1 st, 2 nd, 3rd)Edition and Addenda of Section Xl applicable to the inspection plans 1998 Edition 2000 Addenda Date and revision of inspection plans September 14, 2010 Revision 4 Edition and Addenda of Section Xl applicable to repair/replacement activities, if different than the inspection plans Not Applicable Code Cases used: N-460, N-498-4. N-532-4, N-566-2, N-722-1 and N-770-1 (if applicable)
S     DoeminiW                                           Form OAR-1 Owner's Activity Report Report Number:         2012 Refueling Outage Class 1, Class 2 and Class 3 Plant     Kewaunee Power Station, N490 Highway 42, Kewaunee, Wisconsin 54216-9511 Unit No. No.1                         Commercial service date           June 16,1974         Refueling outage no. K1R32 (if applicable)
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completion of KR32 conform to the requirements of Section XI.(refueling outage number)Signed fJAP JM, 1. i&&AM r r& u Date M u1ý.01.Owner'o r Owner's Designee, Title q CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by IYh c7" of ,4t1oft,-r/
Current inspection interval                             4th (1 st, 2 n, T 3 , 4 th, other)
c--, have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or con ith this inspection.
Current inspection period                           3rd
________________
( 1 st, 2 nd, 3rd)
_7"__ Commissions ,v /,9ZZ 10,0,J 1, /0/3/DnspectQe Signature National Board, State, Province and Endorsements Date 3/ efliY1Z lDo u ini Form OAR-1 Owner's Activity Report Report Number: 2012 Refueling Outage Class MC Plant Kewaunee Power Station, N490 Highway 42, Kewaunee, Wisconsin 54216-9511 Unit No. No.1 Commercial service date June 16,1974 Refueling outage no. K1R32 (if applicable)
Edition and Addenda of Section Xl applicable to the inspection plans                 1998 Edition 2000 Addenda Date and revision of inspection plans               September 14, 2010 Revision 4 Edition and Addenda of Section Xl applicable to repair/replacement activities, if different than the inspection plans Not Applicable Code Cases used:           N-460, N-498-4. N-532-4, N-566-2, N-722-1 and N-770-1 (if applicable)
Current inspection interval 2nd (1 st, 2 , 3 rd, 4t", other)Current inspection period 2nd (1st, 2 Ad, 3 rd)Edition and Addenda of Section Xl applicable to the inspection plans 2001 Edition 2003 Addenda Date and revision of inspection plans March 9. 2009 Revision 3 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Not Applicable Code Cases used: N-532-4 (if applicable)
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completion of                 KR32                         conform to the requirements of Section XI.
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completion of KR32 conform to the requirements of Section Xl.(refueling outage number)Signed a & e. X a .n /t 4b Owner or Owner's Designee, Title V Date CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of and employed by of ,-,TFZ,'b c'7 have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or cotmeztewith this inspection.
(refueling outage number)
CGAP -7C'6r¶1 Commissions A/68 /d6 2Z $4/.#A' 4VI'/01'Inspectrss Signature National Board, State, Province and Endorsements Date / / M- Y/z Kewaunee Power Station Table 1 -4th Interval:
Signed               JM, i&&AM           r               r&                     fJAPu    1.              Date M     u1ý.01.
3rd Period: 2nd Outage -KR32 Items with Flaws or Relevant Conditions that Required Evaluation For Continued Service Examination Item Number Item Description Evaluation Description Category B-G-2 B7.70 3" VALVE PS-1B. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ENGINEERING EVALAUTION.
Owner'o r Owner's Designee, Title                                       q CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of           W/6eo''AJ*/                    and employed by     IYh   c7"         of   ,4t1oft,-r/ c--,
B-G-2 B7.70 8" VALVE RHR-1A. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ENGINEERING EVALUATION.
have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.
B-P B15.60 REACTOR COOLANT PUMP 1B MAIN FLANGE. EVIDENCE OF COOLANT ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.LEAKAGE.B-P B15.70 1.0" VALVE RC-413. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.B-P B15.70 0.75" VALVE SI-45B. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ENGINEERING EVALUATION.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or con             ith this inspection.
C-H C7.10 12" VALVE SI-351A. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.C-H C7.10 6" VALVE RHR-400A.
________________                             _7"__     Commissions       ,v /,9ZZ                 /0/3/
EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.F-A F1.10C RSI-H7. MISALIGNMENT OF SUPPORT. ACCEPTABLE PER ENGINEERING EVALUATION.
10,0,J 1,
F-A F1.20A FDW-H41. MISALIGNMENT OF SUPPORT. ACCEPTABLE PER ENGINEERING EVALUATION.
DnspectQe Signature                                                         National Board, State, Province and Endorsements Date           3/ efliY1Z
F-A F1 .20C FDW-H41 B. MIASLIGNMENT OF SUPPORT. ACCEPTABLE PER ENGINEERING EVALUATION.
 
Page 1 of 1 ft Kewaunee Power Station Table 2 -4th Interval:
lDo uini                                                Form OAR-1 Owner's Activity Report Report Number:         2012 Refueling Outage Class MC Plant     Kewaunee Power Station, N490 Highway 42, Kewaunee, Wisconsin 54216-9511 Unit No.         No.1                     Commercial service date                 June 16,1974         Refueling outage no. K1R32 (if applicable)
3rd Period: 2nd Outage -KR32 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Complete Repair / Replacement Plan Number 0.75" VALVE CVC-236B 0.75" VALVE SI-44B 1" FLANGE DOWNSTREAM OF RC-43-2 STEAM GENERATOR 1A AND 1B WELDED SUPPORT PADS 0.75" PIPING TO VALVE RHR-600 2" VALVE CVC-10 2" VALVE LD-13 3" HYDRAULIC SNUUBER RSI-H2 3" VALVE CVC-4A 6" SUPPORT MSRH-H1 6" SUPPORT MSRH-H2 3" VALVE SW-30B2 3" VALVE SW-914D COMPONENT COOLING WATER PUMP 1A CASING COMPONENT COOLING WATER PUMP 1B INSPECTION PORT PLUGS DIESEL GENERATOR 1A INBOARD AND OUTBOARD JACKET WATER COOLERS TUBE BUNDLES SERVICE WATER PUMP 1B1 REPAIR DUE TO EVIDENCE OF LEAKAGE.REPAIR DUE TO EVIDENCE OF LEAKAGE.REPLACE FLANGE STUDS DUE TO DAMAGE.REPAIR DUE TO LOOSE BOLTING.REPAIR DUE TO THROUGH WALL LEAK.REPAIR BY SEAL WELDING DUE TO EVIDENCE OF LEAKAGE.REPLACE DUE TO EVIDENCE OF LEAKAGE.REPAIR DUE TO DAMAGED CLAMP FASTENERS.
Current inspection interval                                   2nd (1 st,   2       , 3 rd, 4t", other)
REPLACE VALVE BONNET STUDS DUE TO THREAD ENGAGEMENT.
Current inspection period                           2nd (1st,   2     Ad, 3 rd)
REPAIR DUE TO OUTSIDE COLD SETTING AND BROKEN BOLT.REPAIR DUE TO OUTSIDE COLD SETTING.REPLACE DUE TO LEAKAGE BY SEAT.REPLACE DUE TO DEGRADATION.
Edition and Addenda of Section Xl applicable to the inspection plans                       2001 Edition 2003 Addenda Date and revision of inspection plans                 March 9. 2009 Revision 3 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Not Applicable Code Cases used:                     N-532-4 (if applicable)
REPLACE DUE TO MATERIAL LOSS.REPLACE DUE TO EVIDENCE OF LEAKAGE.REPLACE DUE TO EVIDENCE OF LEAKAGE.REPLACE DUE TO HIGH VIBRATION.
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completion of                     KR32                           conform to the requirements of Section Xl.
05/09/2012 05/09/2012 05/08/2012 04/26/2012 05/10/2012 05/10/2012 04/25/2012 05/22/2012 04/28/2012 05/11/2012 05/11/2012 05/22/2012 05/22/2012 04/28/2011 01/23/2012 05/19/2011 05/19/2011 KW100898729 KW100898730 KW100764227 KW100887793 KW100894787 KW 100880536 KW 100843446 KW 100881586 KW100780980 KW100884240 and KW100889310.
(refueling outage number)
KW100883633 KW 100787871 KW100801068 KW100413571 KW100666359 KW100273546 KW100784137 I _____________________________________________  
Signed       a       & e.                 X a* a                      .n             /t4b        L1*          Date Owner or Owner's Designee, Title                               V CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of         *          '-'*"'-'                  and employed by /*,"06c7'            of ,-,TFZ,'b c'7 have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.
.5. ___________________________________________
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or cotmeztewith this inspection.
I __________________ .L Page 1 of 1}}
CGAP     -7C'6r¶1                                 Commissions       A/68 /d6 2Z $4/.#A' 4VI'/01' Inspectrss Signature                                                             National Board, State, Province and Endorsements Date       / / M- Y/z
 
Kewaunee Power Station Table 1 - 4th Interval: 3rd Period: 2nd Outage - KR32 Items with Flaws or Relevant Conditions that Required Evaluation For Continued Service Examination Item Number                           Item Description                             Evaluation Description Category B-G-2       B7.70   3" VALVE PS-1B. EVIDENCE OF COOLANT LEAKAGE.                 ACCEPTABLE PER ENGINEERING EVALAUTION.
B-G-2       B7.70   8" VALVE RHR-1A. EVIDENCE OF COOLANT LEAKAGE.               ACCEPTABLE PER ENGINEERING EVALUATION.
B-P       B15.60   REACTOR COOLANT PUMP 1B MAIN FLANGE. EVIDENCE OF COOLANT ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.
LEAKAGE.
B-P       B15.70   1.0" VALVE RC-413. EVIDENCE OF COOLANT LEAKAGE.         ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.
B-P       B15.70   0.75" VALVE SI-45B. EVIDENCE OF COOLANT LEAKAGE.             ACCEPTABLE PER ENGINEERING EVALUATION.
C-H         C7.10   12" VALVE SI-351A. EVIDENCE OF COOLANT LEAKAGE.         ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.
C-H         C7.10   6" VALVE RHR-400A. EVIDENCE OF COOLANT LEAKAGE.         ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.
F-A       F1.10C   RSI-H7. MISALIGNMENT OF SUPPORT.                             ACCEPTABLE PER ENGINEERING EVALUATION.
F-A       F1.20A   FDW-H41. MISALIGNMENT OF SUPPORT.                           ACCEPTABLE PER ENGINEERING EVALUATION.
F-A       F1 .20C FDW-H41 B. MIASLIGNMENT OF SUPPORT.                         ACCEPTABLE PER ENGINEERING EVALUATION.
Page 1 of 1
 
ft Kewaunee Power Station Table 2 - 4th Interval: 3rd Period: 2nd Outage - KR32 Abstract of Repair/Replacement Activities Required for Continued Service Code Class                     Item Description                               Description of Work                 Date Complete   Repair / Replacement Plan Number 0.75" VALVE CVC-236B                             REPAIR DUE TO EVIDENCE OF LEAKAGE.                    05/09/2012    KW100898729 0.75" VALVE SI-44B                               REPAIR DUE TO EVIDENCE OF LEAKAGE.                    05/09/2012    KW100898730 1" FLANGE DOWNSTREAM OF RC-43-2                   REPLACE FLANGE STUDS DUE TO DAMAGE.                    05/08/2012    KW100764227 STEAM GENERATOR 1A AND 1B WELDED SUPPORT         REPAIR DUE TO LOOSE BOLTING.                          04/26/2012    KW100887793 PADS 0.75" PIPING TO VALVE RHR-600                     REPAIR DUE TO THROUGH WALL LEAK.                      05/10/2012    KW100894787 2" VALVE CVC-10                                   REPAIR BY SEAL WELDING DUE TO EVIDENCE OF              05/10/2012    KW 100880536 LEAKAGE.
2" VALVE LD-13                                   REPLACE DUE TO EVIDENCE OF LEAKAGE.                    04/25/2012    KW 100843446 3" HYDRAULIC SNUUBER RSI-H2                       REPAIR DUE TO DAMAGED CLAMP FASTENERS.                05/22/2012    KW 100881586 3" VALVE CVC-4A                                   REPLACE VALVE BONNET STUDS DUE TO THREAD              04/28/2012    KW100780980 ENGAGEMENT.
6" SUPPORT MSRH-H1                               REPAIR DUE TO OUTSIDE COLD SETTING AND                05/11/2012    KW100884240 and KW100889310.
BROKEN BOLT.
6" SUPPORT MSRH-H2                                REPAIR DUE TO OUTSIDE COLD SETTING.                    05/11/2012    KW100883633 3" VALVE SW-30B2                                  REPLACE DUE TO LEAKAGE BY SEAT.                        05/22/2012    KW 100787871 3" VALVE SW-914D                                  REPLACE DUE TO DEGRADATION.                            05/22/2012    KW100801068 COMPONENT COOLING WATER PUMP 1A CASING            REPLACE DUE TO MATERIAL LOSS.                         04/28/2011    KW100413571 COMPONENT COOLING WATER PUMP 1B INSPECTION        REPLACE DUE TO EVIDENCE OF LEAKAGE.                   01/23/2012    KW100666359 PORT PLUGS DIESEL GENERATOR 1A INBOARD AND OUTBOARD          REPLACE DUE TO EVIDENCE OF LEAKAGE.                   05/19/2011    KW100273546 JACKET WATER COOLERS TUBE BUNDLES SERVICE WATER PUMP 1B1                            REPLACE DUE TO HIGH VIBRATION.                         05/19/2011    KW100784137 I _____________________________________________ .5. ___________________________________________ I __________________ .L Page 1 of 1}}

Latest revision as of 01:17, 12 November 2019

2012 Inservice Inspection Summary Report
ML12215A012
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 07/24/2012
From: Jordan A
Dominion Energy Kewaunee
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
12-426
Download: ML12215A012 (20)


Text

Dominion Energy Kewaunee, Inc.  :"Dominion N490 Hwy 42, Kewaunee, WI 54216 . ftminlll Web Address: www.dom.com U. S. Nuclear Regulatory Commission Serial No.12-426 Attention: Document Control Desk KPS/LIC/NW: RO Washington, DC 20555 Docket No. 50-305 2JUL 242012 License No. DPR-43 DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION 2012 INSERVICE INSPECTION

SUMMARY

REPORT As required by American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section X1, 10 CFR 50.55a, and Wisconsin Administrative Code, Department of Safety and Professional Services, SPS 341.55(3), various inservice inspection (ISI) examinations were performed during the 2012 refueling outage at the Kewaunee Power Station (KPS). The refueling outage took place from April 6, 2012 through May 10, 2012.

This letter transmits the ISI Summary Report as required by paragraph IWA-6230 of ASME Section X1. ISI activities performed at KPS during the period July 28, 2011 through April 5, 2012 are also covered by this report.

Two separate ASME Section Xl ISI programs are implemented at KPS. One program is for pressure retaining piping/vessels and component supports, and the other program is for the metal containment (MC). The 2012 refueling outage inservice inspections met the requirements of these two distinct inspection program intervals as listed below:

  • Class 1, Class 2, and Class 3 component inspections were performed for the second inspection outage of the third period of the fourth interval. These inspections met the requirements of ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda with implementation in accordance with the KPS Fourth Ten-Year ISI Program 2004-2014.

" Class MC component inspections were performed for the second inspection outage of the second period of the second interval. These inspections met the requirements of ASME Boiler and Pressure Vessel Code Section X1, 2001 Edition, 2003 Addenda with implementation in accordance with the KPS Second Ten-Year ISI Class MC Program 2006-2016.

The following examinations and tests were performed for Class 1, Class 2, and Class 3 components and their supports:

  • Pressurizer heater penetrations

" Steam generator nozzle to safe end welds

  • Class 1 and Class 2 piping welds
  • Class 1, Class 2 and Class 3 piping and component supports and hangers

" Class 1 valves

Serial No.12-426 Page 2 of 3

" Class 1 and Class 2 steam generator primary manway bolting, pressurizer manway bolting, flange bolting and valve bonnet bolting

  • Letdown heat exchanger circumferential weld
  • Charging pump pulsation dampener circumferential weld

" Seal water injection filter circumferential weld

" Regenerative heat exchanger circumferential weld and welded attachment

  • Class 2 safety injection pump casing weld

" Class 2 preservice of safety injection piping and supports

" Class 2 preservice of residual heat removal piping and supports

  • Class 1 system leakage test

" Class 2 and Class 3 system leakage tests The following items were examined for the Class MC reactor building containment vessel:

" Accessible surface areas

" Bolted connections Hydraulic snubbers were examined as required by KPS Snubber Program.

Documentation summarizing the ISI activities performed during the KPS 2012 refueling outage and associated results is provided in attachments 1-5 of this letter. The final reports for each of these examinations are maintained in the Quality Assurance/Quality Control Records Vault at KPS.

The next refueling outage at KPS is tentatively scheduled for the fall of 2013.

If you have questions or require additional information, please feel free to contact Mr. Jack Gadzala at 920-388-8604.

Very truly yours, Site Vii President, Kewaunee Power Station Commitments made by this letter: NONE

Serial No.12-426 Page 3 of 3 Attachments:

1. Summary of Relevant Conditions and Disposition.
2. Examination Summary for Class 1, Class 2, and Class 3 Inservice Inspection Program for Fourth Ten-Year Interval.
3. Examination Summary for Class MC Inservice Inspection Program For Second Ten-Year Interval.
4. Summary of Examinations that were Limited by Geometric, Metallurgical, or Design/Access Restrictions (10 Total).
5. Form OAR-1 Owner's Activity Report; Table 1 Items with Flaws or Relevant Conditions that Required Evaluation for Continued Service; and Table 2 Abstract of Repair/Replacement Activities Required for Continued Service.

cc: Regional Administrator U. S. Nuclear Regulatory Commission Region III 2443 Warrenville Road Suite 210 Lisle, Illinois 60532-4352 Mr. K. D. Feintuch Project Manager U.S. Nuclear Regulatory Commission One White Flint North, Mail Stop 08-H4A 11555 Rockville Pike Rockville, MD 20852-2738 NRC Senior Resident Inspector Kewaunee Power Station

Serial No.12-426 ATTACHMENT 1 2012 INSERVICE INSPECTION

SUMMARY

REPORT

SUMMARY

OF RELEVANT CONDITIONS AND DISPOSITION KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

Serial No.12-426 Docket No. 50-305 Attachment 1 Page 1 of 1

SUMMARY

OF RELEVANT CONDITIONS AND DISPOSITION Type or Location of Relevant Examination No. of Relevant Conditions Conditions Method (Description)

1. Piping Supports and Hangers Visual (VT-3) 6 (Items)
2. Valve Bonnet Bolting Visual (V'T-3) 2 (Items)
3. System Leakage Pressure Tests Visual (VT-2) 19 (Items)

Dispositioning of Class 1, Class 2, and Class 3 relevant conditions have been completed in accordance with the rules of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda for Fourth Ten-Year Interval examinations. Dispositioning of Class MC relevant conditions has been completed in accordance with the rules of ASME Boiler and Pressure Vessel Code Section Xl, 2001 Edition, 2003 Addenda for Second Ten-Year Interval examinations. Applicable codes, standards, and engineering criteria were used to disposition indications associated with the non-code-required examinations. Relevant conditions for Class 1, Class 2, Class 3, and Class MC components have been summarized with disposition as noted below:

1. Visual (VT-3) relevant conditions on 3" auxiliary feedwater piping supports FDW-H41 and FDW-H41 B were evaluated and accepted by Kewaunee Power Station (KPS)

Engineering and Inservice Inspection (ISI) personnel. All dispositioned relevant conditions were reviewed by the Authorized Nuclear Inservice Inspector.

2. Visual (VT-3) relevant condition on 2" safety injection support RSI-H7 was evaluated and accepted by KPS Engineering and ISI personnel. The dispositioned relevant condition was reviewed by the Authorized Nuclear Inservice Inspector.
3. Visual (VT-3) relevant conditions on 6" main steam valve supports MSRH-H1 and MSRH-H2 were evaluated, repaired, and accepted by KPS Engineering and ISI personnel. All dispositioned relevant conditions were reviewed by the Authorized Nuclear Inservice Inspector.
4. Visual (VT-3) relevant condition on 8" Service Water Support RSW-H62 was evaluated, repaired, and accepted by KPS Engineering and ISI personnel. The dispositioned relevant condition was reviewed by the Authorized Nuclear Inservice Inspector.
5. Visual (VT-3) relevant conditions recorded on valve bonnet bolting (2 valves), were evaluated and accepted by KPS Engineering and ISI personnel. The dispositioned relevant conditions were reviewed by the Authorized Nuclear Inservice Inspector.
6. Visual (VT-2) relevant conditions recorded during system leakage pressure tests (19 Items) were evaluated and accepted by KPS Engineering and ISI personnel. The dispositioned relevant condition was reviewed by the Authorized Nuclear Inservice Inspector.

Serial No.12-426 ATTACHMENT 2 2012 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION

SUMMARY

FOR CLASS 1, CLASS 2, AND CLASS 3 INSERVICE INSPECTION PROGRAM FOR FOURTH TEN-YEAR INTERVAL KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION 4TH INTERVAL: 3RD PERIOD: 2ND OUTAGE 2012 EXAMINATION

SUMMARY

INTRODUCTION An Inservice Inspection (ISI) Program (Scheduled and Augmented) was performed at the Kewaunee Power Station from July 28, 2011 through April 5, 2012 (Non-Refueling Outage) and from April 6, 2012 through May 10, 2012 (Closing of GI following Refueling Outage) by Kewaunee Power Station personnel, Lambert, MacGill, and Thomas, Inc.(LMT Inc.) and Industrial Testing Laboratories Services (ITLS) examination personnel.

Examinations were performed to satisfy the requirements of:

" ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda

" Westinghouse NASL-06-8: Pressurizer Heater Sleeve Cracking

  • Reactor Vessel Upper Internals Guide Tube Guide Cards per MRP-227-A: Pressurized Water Reactor Internals Inspection and Evaluation Guidelines The Inservice Inspection Program Plan and Augmented Inspection Program Plan located under Tab C were prepared by Kewaunee Power Station for the 4th Interval: 3rd Period: 2nd Outage as identified in the Kewaunee Power Station Fourth 10-Year Inservice Inspection (ISI) Program 2004 - 2014. Examinations during this Refueling Outage were performed to continue 4th Interval; 3rd Period Examination Requirements of ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda and Kewaunee Power Station Fourth 10-Year Inservice Inspection (ISI) Program 2004-2014.

The following items were examined:

" Pressurizer Heater Penetrations

" Steam Generator Channel Head to Tubesheet Weld

" Class 1 and Class 2 Piping Welds

  • Class 1, Class 2 and Class 3 Piping and Component Supports and Hangers

" Class 1 Valves

" Class 1 and Class 2 Steam Generator Primary Manway Bolting, Pressurizer Manway Bolting, Flange Bolting and Valve Bonnet Bolting

" Letdown Heat Exchanger Circumferential Weld Page 1 of 4

" Charging Pump Pulsation Dampener Circumferential Weld

  • Seal Water Injection Filter Circumferential Weld
  • Regenerative Heat Exchanger Circumferential Weld and Welded Attachment

" Class 2 Safety Injection Pump Casing Weld

" Class 2 Preservice of Safety Injection Piping and Supports

" Class 1 System Leakage Test

" Class 2 and Class 3 System Leakage Tests EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.

Some of the arrangements and details of the Kewaunee Power Station Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established. Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In each case, the occurrence and cause of the limitation was documented. In all cases, the maximum achievable amount of surface or volume was examined.

Witnessing and surveillance of the examinations were conducted by personnel from: Nuclear Regulatory Commission and Hartford Steam Boiler Inspection and Insurance Company of CT.

RESULTS Examinations resulted with the following Relevant Conditions being noted on the basis of procedure recording criteria.

Relevant Conditions detected during the 2012 Refueling Outage are listed in Table 1 along with a brief summary. Specific data relative to all Relevant Conditions and their disposition by either (1) corrective measures or, (2) acceptance by ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda Acceptance Criteria or Evaluation are located in Tab F of the Final Report.

Page 2 of 4

TABLE 1 TYPE OR LOCATION OF NO. OF RELEVANT RELEVANT CONDITIONS METHOD CONDITIONS

" Piping Supports and Hangers Visual (VT-3) 6 Items

" Valve Bonnet Bolting Visual (VT-3) 2 Items

" System Leakage Pressure Tests Visual (VT-2) 19 Items

1. Visual (VT-3) Relevant Conditions on 3" Auxiliary Feedwater Piping Supports FDW-H41 and FDW-H41B were Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
2. Visual (VT-3) Relevant Condition on 2" Safety Injection Support RSI-H7 was Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
3. Visual (VT-3) Relevant Conditions on 6" Main Steam Valve Supports MSRH-H1 and MSRH-H2 were Evaluated, Repaired and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
4. Visual (VT-3) Relevant Condition on 8" Service Water Support RSW-H62 was Evaluated, Repaired and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
5. Visual (VT-3) Relevant Conditions recorded on Valve Bonnet Bolting (2 Valves), were Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.
6. Visual (VT-2) Relevant Conditions recorded during System Leakage Pressure Tests (19 Items) were: Evaluated and Accepted by: Kewaunee Power Station Engineering and Inservice Inspection Personnel and reviewed by the Authorized Nuclear Inservice Inspector.

Page 3 of 4

SUMMARY

An Inservice Inspection Program was performed at the Kewaunee Power Station from July 28, 2011 through April 5, 2012 (Non-Refueling Outage) and from April 6, 2012 through May 10, 2012 (Closing of GI following Refueling Outage). Examinations were performed as scheduled in the Kewaunee Power Station Fourth 10-Year Inservice Inspection (ISI) Program 2004 -2014 to continue examinations for the 4th Interval; 3rd Period. A total of 27 Relevant Conditions were detected. All Relevant Conditions were corrected or accepted by ASME Boiler and Pressure Vessel Code Section XI, 1998 Edition, 2000 Addenda Acceptance Criteria or Evaluation requirements.

Phillip E. Bukes Date Engineering Programs Inservice Inspection Program Owner Page 4 of 4

Serial No.12-426 ATTACHMENT 3 2012 INSERVICE INSPECTION

SUMMARY

REPORT EXAMINATION

SUMMARY

FOR CLASS MC INSERVICE INSPECTION PROGRAM FOR SECOND TEN-YEAR INTERVAL KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION 2ND INTERVAL: 2ND PERIOD: 2ND OUTAGE 2012 EXAMINATION

SUMMARY

INTRODUCTION An Inservice Inspection (ISI) Program for the Class MC Reactor Building Containment Vessel was performed at the Kewaunee Power Station from April 6, 2012 through May 10, 2012 (Closing of G I following Refueling Outage) by Kewaunee Power Station and Lambert, MacGill and Thomas Inc. examination personnel.

Examinations were performed to satisfy the requirements of:

- ASME Boiler and Pressure Vessel Code Section XI, 2001 Edition, 2003 Addenda The Inservice Inspection Program Plan located under Tab C was prepared by Kewaunee Power Station for the 2nd Interval; 2nd Period; 2nd Outage as identified in the Kewaunee Power Station Second 10-Year Inservice Inspection (ISI) Program 2006-2016. Examinations during this Refueling Outage were performed to complete the 2nd Interval, 2nd Period examination requirements of ASME Boiler and Pressure Vessel Code Section XI, 2001 Edition, 2003 Addenda and Kewaunee Power Station Second 10-Year Inservice Inspection (ISI) Program 2006-2016.

The following items were examined for the Class MC Reactor Building Containment Vessel:

"Accessible Surface Areas

  • Bolted Connections EXAMINATIONS The examinations performed were in accordance with an approved Inservice Inspection Program Plan located under Tab C of the final report. Examination Procedures were approved prior to the start of examinations and certification documents relative to personnel, equipment and materials were reviewed and determined to be satisfactory.

Page 1 of 2

Some of the arrangements and details of the Kewaunee Power Station Components and Piping Systems were designed and fabricated before ASME Boiler and Pressure Vessel Code Section XI Code requirements were established. Examinations performed were intended to examine 100% of the required surface or volume. In some cases, examinations were limited by geometric, metallurgical or design/access restrictions. In all cases the maximum achievable amount of surface or volume was examined.

Witnessing and surveillance of the examinations were conducted by Hartford Steam Boiler Inspection and Insurance Company of CT.

RESULTS Examinations resulted in No Relevant Conditions being noted on the basis of procedure recording criteria.

SUMMARY

An Inservice Inspection Program for the Class MC Reactor Building Containment Vessel was performed at the Kewaunee Power Station from April 6, 2012 through May 10, 2012 (Closing of G 1 following Refueling Outage). Examinations were performed as scheduled in the Kewaunee Power Station Second 10-Year Inservice Inspection (ISI) Program 2006-2016. Examinations resulted in No Relevant Conditions being noted on the basis of procedure recording criteria.

)',L e13a&eaM Phillip E. Bukes Date Engineering Programs Inservice Inspection Program Owner Page 2 of 2

Serial No.12-426 ATTACHMENT 4 2012 INSERVICE INSPECTION

SUMMARY

REPORT

SUMMARY

OF EXAMINATIONS THAT WERE LIMITED BY GEOMETRIC, METALLURGICAL, OR DESIGN/ACCESS RESTRICTIONS (10 TOTAL)

KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

Serial No.12-426 Docket No. 50-305 Attachment 4 Page 1 of 1

SUMMARY

OF EXAMINATIONS THAT WERE LIMITED BY GEOMETRIC, METALLURGICAL, OR DESIGN/ACCESS RESTRICTIONS Year Component Identification Method of  % Recorded as Not Examination Examined and Limitation 30.0%

2012 Regenerative Heat Exchanger UT Rigid Clamp Support Tubesheet To Shell Weld ARG-W1 1 and 3 Welded Lugs 59.0%

2012 Letdown Heat Exchanger Head UT 2 Integrally Welded Circumferential Weld AHNR-W2 Attachments and 2 2" Nozzles 23.0%

2012 Seal Water Injection Filter 1A Shell UT Welded Name Plate and Circumferential Weld AFSI-Wl Integrally Welded Support For Filter Cover 50.0%

2012 Circumferential Pipe Weld SI-W52 on UT Reducer To Pipe Weld 4" Safety Injection _Configuration 17.0%

2012 Circumferential Pipe Weld RHR-W229 UT Pipe To Tee Weld on 8" Residual Heat Removal Configuration 50.0%

2012 Circumferential Pipe Weld RHR-W436 UT Valve To Pipe Weld on 12" Residual Heat Removal Configuration 54.0%

2012 Circumferential Pipe Weld RHR-W437 UT Pipe To Valve Weld on 12" Residual Heat Removal Configuration and 1 2 Gamma Plugs 50.0%

2012 Circumferential Pipe Weld RHR-W438 UT Valve To Pipe Weld on 12" Residual Heat Removal Configuration 54.0%

2012 Circumferential Pipe Weld RHR-W439 UT Pipe To Valve Weld on 12" Residual Heat Removal Configuration and 2 Gamma Plugs Circumferential Pipe Weld AFW-W192 15.0%

2012 Crm3" Aurenial Peed UT Flange To Pipe Weld on Auxiliary Feedwater Configuration

Serial No.12-426 ATTACHMENT 5 2012 INSERVICE INSPECTION

SUMMARY

REPORT FORM OAR-1 OWNER'S ACTIVITY REPORT TABLE I ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINED SERVICE TABLE 2 ABSTRACT OF REPAIR/REPLACEMENT ACTIVITIES REQUIRED FOR CONTINUED SERVICE KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

S DoeminiW Form OAR-1 Owner's Activity Report Report Number: 2012 Refueling Outage Class 1, Class 2 and Class 3 Plant Kewaunee Power Station, N490 Highway 42, Kewaunee, Wisconsin 54216-9511 Unit No. No.1 Commercial service date June 16,1974 Refueling outage no. K1R32 (if applicable)

Current inspection interval 4th (1 st, 2 n, T 3 , 4 th, other)

Current inspection period 3rd

( 1 st, 2 nd, 3rd)

Edition and Addenda of Section Xl applicable to the inspection plans 1998 Edition 2000 Addenda Date and revision of inspection plans September 14, 2010 Revision 4 Edition and Addenda of Section Xl applicable to repair/replacement activities, if different than the inspection plans Not Applicable Code Cases used: N-460, N-498-4. N-532-4, N-566-2, N-722-1 and N-770-1 (if applicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completion of KR32 conform to the requirements of Section XI.

(refueling outage number)

Signed JM, i&&AM r r& fJAPu 1. Date M u1ý.01.

Owner'o r Owner's Designee, Title q CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of W/6eoAJ*/ and employed by IYh c7" of ,4t1oft,-r/ c--,

have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or con ith this inspection.

________________ _7"__ Commissions ,v /,9ZZ /0/3/

10,0,J 1,

DnspectQe Signature National Board, State, Province and Endorsements Date 3/ efliY1Z

lDo uini Form OAR-1 Owner's Activity Report Report Number: 2012 Refueling Outage Class MC Plant Kewaunee Power Station, N490 Highway 42, Kewaunee, Wisconsin 54216-9511 Unit No. No.1 Commercial service date June 16,1974 Refueling outage no. K1R32 (if applicable)

Current inspection interval 2nd (1 st, 2 , 3 rd, 4t", other)

Current inspection period 2nd (1st, 2 Ad, 3 rd)

Edition and Addenda of Section Xl applicable to the inspection plans 2001 Edition 2003 Addenda Date and revision of inspection plans March 9. 2009 Revision 3 Edition and Addenda of Section XI applicable to repair/replacement activities, if different than the inspection plans Not Applicable Code Cases used: N-532-4 (if applicable)

CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code, Section Xl; and (c) the repair/replacement activities and evaluations supporting the completion of KR32 conform to the requirements of Section Xl.

(refueling outage number)

Signed a & e. X a* a .n /t4b L1* Date Owner or Owner's Designee, Title V CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of * '-'*"'-' and employed by /*,"06c7' of ,-,TFZ,'b c'7 have inspected the items described in this Owner's Activity Report, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section XI.

By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or a loss of any kind arising from or cotmeztewith this inspection.

CGAP -7C'6r¶1 Commissions A/68 /d6 2Z $4/.#A' 4VI'/01' Inspectrss Signature National Board, State, Province and Endorsements Date / / M- Y/z

Kewaunee Power Station Table 1 - 4th Interval: 3rd Period: 2nd Outage - KR32 Items with Flaws or Relevant Conditions that Required Evaluation For Continued Service Examination Item Number Item Description Evaluation Description Category B-G-2 B7.70 3" VALVE PS-1B. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ENGINEERING EVALAUTION.

B-G-2 B7.70 8" VALVE RHR-1A. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ENGINEERING EVALUATION.

B-P B15.60 REACTOR COOLANT PUMP 1B MAIN FLANGE. EVIDENCE OF COOLANT ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.

LEAKAGE.

B-P B15.70 1.0" VALVE RC-413. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.

B-P B15.70 0.75" VALVE SI-45B. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ENGINEERING EVALUATION.

C-H C7.10 12" VALVE SI-351A. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.

C-H C7.10 6" VALVE RHR-400A. EVIDENCE OF COOLANT LEAKAGE. ACCEPTABLE PER ASME SECTION XI CODE CASE N-566-2.

F-A F1.10C RSI-H7. MISALIGNMENT OF SUPPORT. ACCEPTABLE PER ENGINEERING EVALUATION.

F-A F1.20A FDW-H41. MISALIGNMENT OF SUPPORT. ACCEPTABLE PER ENGINEERING EVALUATION.

F-A F1 .20C FDW-H41 B. MIASLIGNMENT OF SUPPORT. ACCEPTABLE PER ENGINEERING EVALUATION.

Page 1 of 1

ft Kewaunee Power Station Table 2 - 4th Interval: 3rd Period: 2nd Outage - KR32 Abstract of Repair/Replacement Activities Required for Continued Service Code Class Item Description Description of Work Date Complete Repair / Replacement Plan Number 0.75" VALVE CVC-236B REPAIR DUE TO EVIDENCE OF LEAKAGE. 05/09/2012 KW100898729 0.75" VALVE SI-44B REPAIR DUE TO EVIDENCE OF LEAKAGE. 05/09/2012 KW100898730 1" FLANGE DOWNSTREAM OF RC-43-2 REPLACE FLANGE STUDS DUE TO DAMAGE. 05/08/2012 KW100764227 STEAM GENERATOR 1A AND 1B WELDED SUPPORT REPAIR DUE TO LOOSE BOLTING. 04/26/2012 KW100887793 PADS 0.75" PIPING TO VALVE RHR-600 REPAIR DUE TO THROUGH WALL LEAK. 05/10/2012 KW100894787 2" VALVE CVC-10 REPAIR BY SEAL WELDING DUE TO EVIDENCE OF 05/10/2012 KW 100880536 LEAKAGE.

2" VALVE LD-13 REPLACE DUE TO EVIDENCE OF LEAKAGE. 04/25/2012 KW 100843446 3" HYDRAULIC SNUUBER RSI-H2 REPAIR DUE TO DAMAGED CLAMP FASTENERS. 05/22/2012 KW 100881586 3" VALVE CVC-4A REPLACE VALVE BONNET STUDS DUE TO THREAD 04/28/2012 KW100780980 ENGAGEMENT.

6" SUPPORT MSRH-H1 REPAIR DUE TO OUTSIDE COLD SETTING AND 05/11/2012 KW100884240 and KW100889310.

BROKEN BOLT.

6" SUPPORT MSRH-H2 REPAIR DUE TO OUTSIDE COLD SETTING. 05/11/2012 KW100883633 3" VALVE SW-30B2 REPLACE DUE TO LEAKAGE BY SEAT. 05/22/2012 KW 100787871 3" VALVE SW-914D REPLACE DUE TO DEGRADATION. 05/22/2012 KW100801068 COMPONENT COOLING WATER PUMP 1A CASING REPLACE DUE TO MATERIAL LOSS. 04/28/2011 KW100413571 COMPONENT COOLING WATER PUMP 1B INSPECTION REPLACE DUE TO EVIDENCE OF LEAKAGE. 01/23/2012 KW100666359 PORT PLUGS DIESEL GENERATOR 1A INBOARD AND OUTBOARD REPLACE DUE TO EVIDENCE OF LEAKAGE. 05/19/2011 KW100273546 JACKET WATER COOLERS TUBE BUNDLES SERVICE WATER PUMP 1B1 REPLACE DUE TO HIGH VIBRATION. 05/19/2011 KW100784137 I _____________________________________________ .5. ___________________________________________ I __________________ .L Page 1 of 1