ML16021A089

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Submittal of the In-Service Inspection (ISI) Owners Activity Report (OAR) for the 20th Refueling Outage
ML16021A089
Person / Time
Site: Peach Bottom  
Issue date: 01/20/2016
From: Pat Navin
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
P3R20
Download: ML16021A089 (9)
v • d • e


Text

{{#Wiki_filter:Exelon Generation.. January 20, 2016 U. S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 1 OCFR 50.55a Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

Submittal of the In-Service Inspection (ISi) Owner's Activity Report (OAR) for the 201h Refueling Outage for Unit 3 Enclosed in Attachment 1 is the ISi Owner's Activity Report covering ISi activities associated with the second period of the current ISi inspection interval for Unit 3. This report is submitted pursuant to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Rules for the lnservice Inspection of Nuclear Power Plant Components," Article IWA-6200, "Requirements" (2001 Edition through 2003 Addenda) and ASME Code Case N-532-4 (Repair/Replacement Activity Documentation Requirements and In-Service Summary Report Preparation and Submission, section XI, Division 1 ). If you have any questions or require additional information, feel free to contact Brian Rufo at 717-456-3250. Patrick D. Navin Plant Manager Peach Bottom Atomic Power Station Attachments cc: US NRC, Administrator, Region I US NRC, Senior Resident Inspector R. R. Janati, Commonwealth of Pennsylvania S. Gray, State of Maryland B. Watkins, PSE&G, Financial Controls and Co-owner Affairs CCN: 16-01 Peach Bottom Atomic Power Station Unit 3 Owner's Activity Report for the 201h Refueling Outage

PEACH BOTTOM ATOMIC POWER STATION, UNIT No. 3-P3R20 OAR REPORT FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number P3R20 ~------------------------------- PI ant Peach Bottom Atomic Power Station, 1848 Lay Road, Delta, PA 17314 Unit No. 3 Commercial Service Date December 23, 1974 Refueling Outage No. 20 --- Current Inspection Interval ISi = Fourth I CISI = Second Current Inspection Period ISi =Third I CISI = Third Edition and Addenda of Section XI Applicable to the inspection plans 2001 Edition through 2003 Addenda Date and revision of inspection plan _0_9_/0_2_/2_0_1_4_R_e_v_4 ________________ _ Edition & Addenda of Section XI Applicable to repairs and replacements, if different than the inspection plan 2001 Edition through 2003 Addenda (same as inspection plan) Code Cases used: N-460. N-513-3. N-532-4. N-578-1. N-700 & N-702 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 XI; and (c) the repair/replacement activities and evaluations supporting th completion of P3R20 conform to the requirements of Section XI. Signed Brian Rufo, ISi Pro ram Owner Date 1 /14/2016 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 Pennsylvania and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut 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 an kind arisin from connected with this inspection.

TABLE 1 01/12/16, PAGE 1OF1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT N0.3 OCTOBER 24, 2013 TO OCTOBER 22, 2015 (END OF P3R20 REFUEL OUTAGE) Examination Item Item Description Evaluation Description Category Number E-A El.I I Coating Relevant Condition - Coating damage was identified on the Subpile Room subpile room floor exceeded the acceptance criteria. The damage was evaluated by the coatings engineer and it was determined that the maximum unqualified coating limit was not exceeded and no repair was required. (Ref IR - 2561005) E-A El.IO Moisture Barrier Relevant Condition - Cracked concrete, moisture barrier damage; IWE-3510.4. Condition was evaluated to be acceptable. Repairs planned for P3R21. (Ref IR 2561844) F-A Fl.30C 1GG-H299 Relevant Condition - Ucar plate (item 2) was found broken; Support this condition exceeded the allowable criteria ofIWF-3410. The condition was evaluated and determined not to impact the functionality of the suooort. <ReflR - 2560404) F-A Fl.20A 23DDN-S31 Relevant Condition-Strut found out of alignment, IWF-Support 3410(a). IWF-3122.3 allows for acceptance after engineering evaluation. The as found condition was evaluated, ECR 15-00368, and found to be acceptable in the as-found orientation. (Ref IR - 2565122) F-A Fl.20C 7DB-H75 Relevant Condition - The stanchion was found misaligned Spring Can 2.3". Evaluation determined that the stanchion is located such that it will be centered within a reasonable tolerance when the unit is online and thermal effects are taken into account, reference ECR 12-00016. No actions required as found is acceptable. (Ref IR-2565125)

TABLE 1 01/12/16, PAGE 2 OF 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT N0.3 OCTOBER 24, 2013 TO OCTOBER 22, 2015 (END OF P3R20 REFUEL OUTAGE) Examination Item Item Description Evaluation Description Category Number F-A Fl.20 Drywell Head Relevant Condition - Identified missing coating, damage to flange surface, and cracked tack welds which required evaluation per IWE-3000. All three conditions were previously identified and evaluated. The current conditions were compared and found to be acceptable, no changes to the conditions previously identified and evaluated. (RefIR-2566726)

T. TABLE 2 01/15/2016 Page1of4 + ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 24, 2013 TO OCTOBER 22, 2015 t f-i SYSTEM 01: MAIN STEAM AND TURBINE SYSTEM Replacement, J

Repair, 1

Code _ or Corrective Class Measure I 1 Replacement, Replacement. Replacement, Replacement, Item Description {com_j)()oent I.DJ RV-3-02-0709 RV-3-02-071A RV-3-02-071 F RV-3-02-071 L i Replacement. l HV-3-01A-83A-D SYSTEM 03: Code Class 1 T l _J 1 CONTROL ROD DRIVE

Repair, Replacement, or Corrective Measure Replacement Item Description (component l.D.)

CRD's 02-19, 14-11, 14-19 14-23, 18-03, 18-07, 22-03 22-07, 22-19, 26-31, 26-59 30-03, 34-15, 38-03, 38-43 _42-55, 46-47, 50-15, 54-47 ( END OF P3R20 REFUEL OUT AGE ) 1 Description Of Work Performed ~ eplace Main Steam Safe;; R~li~f Valve Ree!?ce Main Steam S~ Relief Valve Replace Main Steam Safety Relief Valve Replace Main Steam Safety Relief Valve nstall Main Steam Back Supports Description Of Work Performed ExChangeciCRD's with rebuilt CRD's 1 SYSTEM 04: REACTOR PRESSURE VESSEL & INTERNALS l T I Code Class

Repair, Replacement, ]

or Corrective Measure Repair 1 Description Of Work Performed Re~ctor vessel lug !3epair 94 d~~e lug in reactor vessel Flaw or Relevant Condition Found During Scheduled Section XI Exam J Or Test No Date J Co~plete R&R Plan # and W/O # No No No No 10/1/2015 15-043; R1217926 l 10/2/2015.I 15-044; R1218952 _ 10/2/2015 _- 15-046; R1217928 _ 10/1/2015 15-048; R1212500 9/26/2015 15-108; C0255970 l Flaw or Relevant 1 Condition Found j During Scheduled Section XI Exam Or Test No t Flaw or Relevant Condition Found During Scheduled Section XI Exam Or Test No Date J complete_ R&R Plan# and W/O # 10/6/2015 t 15-051; R1276199 _ Date Complete I R&R Plan # and W/O # 10/15/2015 I 15-220; C0258822

TABLE2 -i-101/15/2016 Page 2 of 4 -_y ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 24, 2013 TO OCTOBER 22, 2015 I T SYSTEM 06: l FEEDWATER 1 1 r

Repair,

~ Replacement, Code 1 or Corrective ~ Measure Repair 1 Item Description -{component l.D.) CHK-3-06-288 SYSTEM 10: RcSIDUAL HEAT REMOVAL T Code Class 2 SYSTEM 12: t r -1 Code Class 1

Repair,

-it Replacement, or Corrective Measure I Reolacement, T Item Description (component l.D.l PB-3-10-3BE024 REACTOR WATER CLEAN UP

Repair, Replacement, or Correctiv~

Measure Replacement T Item Description (component l.D.) RWCU Pipin9 SYSTEM 14: CORE SPRAY Item Description (component l.D.) M0:.3-14-012A - {END OF P3R20 REFUEL OUTAGE) t Description Of Work Performed Bonnet modification of feedwater check valve 1 T Description Of Work Performed Replace Hx floatina head ** Description Of Work Performed Piping replacement upstream of CHK-3-12-062 _ _ t;>escription_ Of W~rk Performed Reoair valve due to degrade<:! performance Flaw or Relevant Condition Found During Scheduled Section XI Exam Or Test No i Date + complete R&R Plan # and W/O # 10/6/2015. 15-202; R1016927 Flaw or Relevant 1 Condition Found During Scheduled Secti-on XI Exam 1-Date -L Or Test No l i Complete R&R Plan # and W/O # 10/14/2015 15~Cl18 ; C0239938 Flaw or Relevant~ Conditfon Found During Scheduled Section XfExam J Date j Or Te~t. Complete;~ R&R_ Plan# and W/O # ~ 10/13/2015 15-159; C0255958 c;omru!lte ~&R Pla!_'I_ # and W/O #_ 9129/2015 -f.p 15-114; C0256126

TABLE2 +- 01/15/2016 Page 3 of 4 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES I FOR PEACH BOTIOM ATOMIC POWER STATION, U__!.llT NO. 3 OCTOBER 24,_2013 TO OC_TOBER 22, 2015 ( END OF P3R20~EFUEL OUTAGE ) r ~ l SYSTEM23: HIGH PRESSURE COOLANT INJECTION SYSTEM -+ l I Code J Class I 2 t

Repair, Re_placement, or Corrective Item Description (component l.D.)

M0-3-23-019 HV-3-23C-33442/43 l J SYSTEM65A: HYDRAULIC SNUBBERS

Repair, Replacement, Code..__~ or Co. rrectlve8 Class

_ Measure 1 Replacement 1 Replacement 1 Replacement ~ 1 Replacement 1 J Replacement 2 Replacement 1 ~ Replacement 2 Replacement 2 Replacement 2 Replacement 2 Replacement 1 1 Replacement 1 Replacement ~ 2 + ~epair 2 Repair 1 f Repair 1 Repair T r Item Description (component l.D.) SS-B-1 SS-8-5 6-DDNL-S-14 6-DDNL-S-6 SS-D-1 10-GB-S-54 SS-C-1 10-G8-S-49 10-G8-S-48 1-08-S-417 1-08-S-416 SS-D-4 SS-A-4 1-08-S-414 1-08-S-415 SS-A-6 SS-A-5 t Description Of ~ork Performed_ Install new HPCI vent line branch connections j Repair valve internals -1 Descrietion Of Work f>erformed Replace Snubber SS-8-1 Replace Snubber SS-8-5 "U3" Feedwater Snubber - REPLACE "U3" Feedwater Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3HRHR Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3" RHR Snubber - REPLACE "U3" RHR Snubber - REPLACE

'U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber -=-REPLACE "U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber - REPLACE t

1 Flaw or Relevant Condition Found During Scheduled Section XI Exam -, Date 1 Or Test ! Complete R&R Plan# and W/O # No 101812015 1*.13-129; C0247318. No 10/9/2015 15-116; C0250475 j --t Flaw or Relevant 1 Condition Found During Scheduled

  • Section XI Exam Date Or!_est No No No No No No No No No No No No No No No No No Complete 1012/2015 10/1/2015 9/23/2015 9730/2015-L!Q/1/2015

.!. 10!15/2~5 9/30/2015 10/14/2015 10/14/2015 + 10/12/2015 10/15/2015 10/15/2015 10/15/2015 10/13/2015 i 10/14/201~ 5 10/12/2015 10/5/2015 R&R Plan # and W/O # 091; R0508767 13-092; R0545765 15-086; R0546136 15-087; R0545108 15-088; R0545102 15-091; R0.§45192 15-092; R0545224 15-093; R0545772 15-094; R0545775 15-221; C0258943 15-222; C0258948 15-225; C0258981 15-226; C0258982 15-227; C0258955 15-228; C0258962 15-229; Co258983 15-230; C0258992

l TABLE2 01/15/2016 Page 4 of 4 ..L r ~ I ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES ~ I 6 I j FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 ~ I T t 1 _J J_ SYSTEM 658: MECHANICAL SNUBBERS I I

Repair, Replacement, or Corrective i J

I Code ~ Measure t Replacement, 1 Replacement, I I 2 -f Replacement. _ 2 I Replacement, I j Item Description (comoonentl.D.) 10~GB-S-44 SS-6-A 10-GB-S-63 14-GB-S-33 OCTOBER 24, 2013 TO OCTOBER 22, 2015 ( END OF P3R20 REFUEL OUTAGE) r J-- - 1 Descriotion Of Wo<k Pe.tanned "U3" RHR Snubber - REPLACE. - "U3" Recirc Snubber - REPLACE "U3" RHR Snubber - REPLACE "U3" Core Spray Snubber - REPLACE I 2 Replacement, l 14-MO-H-57 l"U3" Core Spray Snubber - REPLACE -+ -i 1 1 2 1 1 1 Replacement, j H-3LS-142-1 f "U3" CRD Supply Bundle Snubber - REPLACE Replacement, H-3LS-142-8 "U3" CRD Supply Bundle Snubber - REPLA_C_E __ _ ~ Replacement, :_ 23-0DN-S-300L__ "U3" HPCI Snubber - REPLACE 1 Replacement, H-3LS-142-2 "U3" CRD Supply Bundle Snubber-REPLACE Replacement, I H=3LS-142-4 -- "U3" CRD Supply Bundle Snubber - REPLACE Replacement. T H-3LS-142-5 -- "U3" CRD Supply Bundle Snubber - REPLACE l-l- Flaw or Relevantl-Condition Found I During Scheduled * { Section XI Exam Date l OrTe$t _COrnQlete ~~R Plan][clnd ~KS# l No 9/23/2015 J No 9/25/2015 15-068; C0255566 1 No 9/21/2015, 15-070; C0255568 No 9/23/2015 15-071; C0255569 No 9/23/2015 15-072; C0255570 No 10/6/2015 15-073; C0255571 No ~- 10/6/2015 - 15-074; C0255572 No 9/23/2015 - 15-079; C0255577 i No .L 10/6/2015 15-080; C0255578 l No + 10/6/2015 15-081; C0255579 No 10/6/2015 15-082; C0255580

Exelon Generation.. January 20, 2016 U. S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 1 OCFR 50.55a Peach Bottom Atomic Power Station (PBAPS) Units 2 and 3 Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

Submittal of the In-Service Inspection (ISi) Owner's Activity Report (OAR) for the 201h Refueling Outage for Unit 3 Enclosed in Attachment 1 is the ISi Owner's Activity Report covering ISi activities associated with the second period of the current ISi inspection interval for Unit 3. This report is submitted pursuant to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section XI, "Rules for the lnservice Inspection of Nuclear Power Plant Components," Article IWA-6200, "Requirements" (2001 Edition through 2003 Addenda) and ASME Code Case N-532-4 (Repair/Replacement Activity Documentation Requirements and In-Service Summary Report Preparation and Submission, section XI, Division 1 ). If you have any questions or require additional information, feel free to contact Brian Rufo at 717-456-3250. Patrick D. Navin Plant Manager Peach Bottom Atomic Power Station Attachments cc: US NRC, Administrator, Region I US NRC, Senior Resident Inspector R. R. Janati, Commonwealth of Pennsylvania S. Gray, State of Maryland B. Watkins, PSE&G, Financial Controls and Co-owner Affairs CCN: 16-01 Peach Bottom Atomic Power Station Unit 3 Owner's Activity Report for the 201h Refueling Outage

PEACH BOTTOM ATOMIC POWER STATION, UNIT No. 3-P3R20 OAR REPORT FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number P3R20 ~------------------------------- PI ant Peach Bottom Atomic Power Station, 1848 Lay Road, Delta, PA 17314 Unit No. 3 Commercial Service Date December 23, 1974 Refueling Outage No. 20 --- Current Inspection Interval ISi = Fourth I CISI = Second Current Inspection Period ISi =Third I CISI = Third Edition and Addenda of Section XI Applicable to the inspection plans 2001 Edition through 2003 Addenda Date and revision of inspection plan _0_9_/0_2_/2_0_1_4_R_e_v_4 ________________ _ Edition & Addenda of Section XI Applicable to repairs and replacements, if different than the inspection plan 2001 Edition through 2003 Addenda (same as inspection plan) Code Cases used: N-460. N-513-3. N-532-4. N-578-1. N-700 & N-702 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 XI; and (c) the repair/replacement activities and evaluations supporting th completion of P3R20 conform to the requirements of Section XI. Signed Brian Rufo, ISi Pro ram Owner Date 1 /14/2016 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 Pennsylvania and employed by The Hartford Steam Boiler Inspection and Insurance Company of Connecticut 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 an kind arisin from connected with this inspection.

TABLE 1 01/12/16, PAGE 1OF1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT N0.3 OCTOBER 24, 2013 TO OCTOBER 22, 2015 (END OF P3R20 REFUEL OUTAGE) Examination Item Item Description Evaluation Description Category Number E-A El.I I Coating Relevant Condition - Coating damage was identified on the Subpile Room subpile room floor exceeded the acceptance criteria. The damage was evaluated by the coatings engineer and it was determined that the maximum unqualified coating limit was not exceeded and no repair was required. (Ref IR - 2561005) E-A El.IO Moisture Barrier Relevant Condition - Cracked concrete, moisture barrier damage; IWE-3510.4. Condition was evaluated to be acceptable. Repairs planned for P3R21. (Ref IR 2561844) F-A Fl.30C 1GG-H299 Relevant Condition - Ucar plate (item 2) was found broken; Support this condition exceeded the allowable criteria ofIWF-3410. The condition was evaluated and determined not to impact the functionality of the suooort. <ReflR - 2560404) F-A Fl.20A 23DDN-S31 Relevant Condition-Strut found out of alignment, IWF-Support 3410(a). IWF-3122.3 allows for acceptance after engineering evaluation. The as found condition was evaluated, ECR 15-00368, and found to be acceptable in the as-found orientation. (Ref IR - 2565122) F-A Fl.20C 7DB-H75 Relevant Condition - The stanchion was found misaligned Spring Can 2.3". Evaluation determined that the stanchion is located such that it will be centered within a reasonable tolerance when the unit is online and thermal effects are taken into account, reference ECR 12-00016. No actions required as found is acceptable. (Ref IR-2565125)

TABLE 1 01/12/16, PAGE 2 OF 1 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT N0.3 OCTOBER 24, 2013 TO OCTOBER 22, 2015 (END OF P3R20 REFUEL OUTAGE) Examination Item Item Description Evaluation Description Category Number F-A Fl.20 Drywell Head Relevant Condition - Identified missing coating, damage to flange surface, and cracked tack welds which required evaluation per IWE-3000. All three conditions were previously identified and evaluated. The current conditions were compared and found to be acceptable, no changes to the conditions previously identified and evaluated. (RefIR-2566726)

T. TABLE 2 01/15/2016 Page1of4 + ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 24, 2013 TO OCTOBER 22, 2015 t f-i SYSTEM 01: MAIN STEAM AND TURBINE SYSTEM Replacement, J

Repair, 1

Code _ or Corrective Class Measure I 1 Replacement, Replacement. Replacement, Replacement, Item Description {com_j)()oent I.DJ RV-3-02-0709 RV-3-02-071A RV-3-02-071 F RV-3-02-071 L i Replacement. l HV-3-01A-83A-D SYSTEM 03: Code Class 1 T l _J 1 CONTROL ROD DRIVE

Repair, Replacement, or Corrective Measure Replacement Item Description (component l.D.)

CRD's 02-19, 14-11, 14-19 14-23, 18-03, 18-07, 22-03 22-07, 22-19, 26-31, 26-59 30-03, 34-15, 38-03, 38-43 _42-55, 46-47, 50-15, 54-47 ( END OF P3R20 REFUEL OUT AGE ) 1 Description Of Work Performed ~ eplace Main Steam Safe;; R~li~f Valve Ree!?ce Main Steam S~ Relief Valve Replace Main Steam Safety Relief Valve Replace Main Steam Safety Relief Valve nstall Main Steam Back Supports Description Of Work Performed ExChangeciCRD's with rebuilt CRD's 1 SYSTEM 04: REACTOR PRESSURE VESSEL & INTERNALS l T I Code Class

Repair, Replacement, ]

or Corrective Measure Repair 1 Description Of Work Performed Re~ctor vessel lug !3epair 94 d~~e lug in reactor vessel Flaw or Relevant Condition Found During Scheduled Section XI Exam J Or Test No Date J Co~plete R&R Plan # and W/O # No No No No 10/1/2015 15-043; R1217926 l 10/2/2015.I 15-044; R1218952 _ 10/2/2015 _- 15-046; R1217928 _ 10/1/2015 15-048; R1212500 9/26/2015 15-108; C0255970 l Flaw or Relevant 1 Condition Found j During Scheduled Section XI Exam Or Test No t Flaw or Relevant Condition Found During Scheduled Section XI Exam Or Test No Date J complete_ R&R Plan# and W/O # 10/6/2015 t 15-051; R1276199 _ Date Complete I R&R Plan # and W/O # 10/15/2015 I 15-220; C0258822

TABLE2 -i-101/15/2016 Page 2 of 4 -_y ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 24, 2013 TO OCTOBER 22, 2015 I T SYSTEM 06: l FEEDWATER 1 1 r

Repair,

~ Replacement, Code 1 or Corrective ~ Measure Repair 1 Item Description -{component l.D.) CHK-3-06-288 SYSTEM 10: RcSIDUAL HEAT REMOVAL T Code Class 2 SYSTEM 12: t r -1 Code Class 1

Repair,

-it Replacement, or Corrective Measure I Reolacement, T Item Description (component l.D.l PB-3-10-3BE024 REACTOR WATER CLEAN UP

Repair, Replacement, or Correctiv~

Measure Replacement T Item Description (component l.D.) RWCU Pipin9 SYSTEM 14: CORE SPRAY Item Description (component l.D.) M0:.3-14-012A - {END OF P3R20 REFUEL OUTAGE) t Description Of Work Performed Bonnet modification of feedwater check valve 1 T Description Of Work Performed Replace Hx floatina head ** Description Of Work Performed Piping replacement upstream of CHK-3-12-062 _ _ t;>escription_ Of W~rk Performed Reoair valve due to degrade<:! performance Flaw or Relevant Condition Found During Scheduled Section XI Exam Or Test No i Date + complete R&R Plan # and W/O # 10/6/2015. 15-202; R1016927 Flaw or Relevant 1 Condition Found During Scheduled Secti-on XI Exam 1-Date -L Or Test No l i Complete R&R Plan # and W/O # 10/14/2015 15~Cl18 ; C0239938 Flaw or Relevant~ Conditfon Found During Scheduled Section XfExam J Date j Or Te~t. Complete;~ R&R_ Plan# and W/O # ~ 10/13/2015 15-159; C0255958 c;omru!lte ~&R Pla!_'I_ # and W/O #_ 9129/2015 -f.p 15-114; C0256126

TABLE2 +- 01/15/2016 Page 3 of 4 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES I FOR PEACH BOTIOM ATOMIC POWER STATION, U__!.llT NO. 3 OCTOBER 24,_2013 TO OC_TOBER 22, 2015 ( END OF P3R20~EFUEL OUTAGE ) r ~ l SYSTEM23: HIGH PRESSURE COOLANT INJECTION SYSTEM -+ l I Code J Class I 2 t

Repair, Re_placement, or Corrective Item Description (component l.D.)

M0-3-23-019 HV-3-23C-33442/43 l J SYSTEM65A: HYDRAULIC SNUBBERS

Repair, Replacement, Code..__~ or Co. rrectlve8 Class

_ Measure 1 Replacement 1 Replacement 1 Replacement ~ 1 Replacement 1 J Replacement 2 Replacement 1 ~ Replacement 2 Replacement 2 Replacement 2 Replacement 2 Replacement 1 1 Replacement 1 Replacement ~ 2 + ~epair 2 Repair 1 f Repair 1 Repair T r Item Description (component l.D.) SS-B-1 SS-8-5 6-DDNL-S-14 6-DDNL-S-6 SS-D-1 10-GB-S-54 SS-C-1 10-G8-S-49 10-G8-S-48 1-08-S-417 1-08-S-416 SS-D-4 SS-A-4 1-08-S-414 1-08-S-415 SS-A-6 SS-A-5 t Description Of ~ork Performed_ Install new HPCI vent line branch connections j Repair valve internals -1 Descrietion Of Work f>erformed Replace Snubber SS-8-1 Replace Snubber SS-8-5 "U3" Feedwater Snubber - REPLACE "U3" Feedwater Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3HRHR Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3" RHR Snubber - REPLACE "U3" RHR Snubber - REPLACE

'U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber -=-REPLACE "U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber - REPLACE "U3" Main Steam Snubber - REPLACE t

1 Flaw or Relevant Condition Found During Scheduled Section XI Exam -, Date 1 Or Test ! Complete R&R Plan# and W/O # No 101812015 1*.13-129; C0247318. No 10/9/2015 15-116; C0250475 j --t Flaw or Relevant 1 Condition Found During Scheduled

  • Section XI Exam Date Or!_est No No No No No No No No No No No No No No No No No Complete 1012/2015 10/1/2015 9/23/2015 9730/2015-L!Q/1/2015

.!. 10!15/2~5 9/30/2015 10/14/2015 10/14/2015 + 10/12/2015 10/15/2015 10/15/2015 10/15/2015 10/13/2015 i 10/14/201~ 5 10/12/2015 10/5/2015 R&R Plan # and W/O # 091; R0508767 13-092; R0545765 15-086; R0546136 15-087; R0545108 15-088; R0545102 15-091; R0.§45192 15-092; R0545224 15-093; R0545772 15-094; R0545775 15-221; C0258943 15-222; C0258948 15-225; C0258981 15-226; C0258982 15-227; C0258955 15-228; C0258962 15-229; Co258983 15-230; C0258992

l TABLE2 01/15/2016 Page 4 of 4 ..L r ~ I ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES ~ I 6 I j FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 ~ I T t 1 _J J_ SYSTEM 658: MECHANICAL SNUBBERS I I

Repair, Replacement, or Corrective i J

I Code ~ Measure t Replacement, 1 Replacement, I I 2 -f Replacement. _ 2 I Replacement, I j Item Description (comoonentl.D.) 10~GB-S-44 SS-6-A 10-GB-S-63 14-GB-S-33 OCTOBER 24, 2013 TO OCTOBER 22, 2015 ( END OF P3R20 REFUEL OUTAGE) r J-- - 1 Descriotion Of Wo<k Pe.tanned "U3" RHR Snubber - REPLACE. - "U3" Recirc Snubber - REPLACE "U3" RHR Snubber - REPLACE "U3" Core Spray Snubber - REPLACE I 2 Replacement, l 14-MO-H-57 l"U3" Core Spray Snubber - REPLACE -+ -i 1 1 2 1 1 1 Replacement, j H-3LS-142-1 f "U3" CRD Supply Bundle Snubber - REPLACE Replacement, H-3LS-142-8 "U3" CRD Supply Bundle Snubber - REPLA_C_E __ _ ~ Replacement, :_ 23-0DN-S-300L__ "U3" HPCI Snubber - REPLACE 1 Replacement, H-3LS-142-2 "U3" CRD Supply Bundle Snubber-REPLACE Replacement, I H=3LS-142-4 -- "U3" CRD Supply Bundle Snubber - REPLACE Replacement. T H-3LS-142-5 -- "U3" CRD Supply Bundle Snubber - REPLACE l-l- Flaw or Relevantl-Condition Found I During Scheduled * { Section XI Exam Date l OrTe$t _COrnQlete ~~R Plan][clnd ~KS# l No 9/23/2015 J No 9/25/2015 15-068; C0255566 1 No 9/21/2015, 15-070; C0255568 No 9/23/2015 15-071; C0255569 No 9/23/2015 15-072; C0255570 No 10/6/2015 15-073; C0255571 No ~- 10/6/2015 - 15-074; C0255572 No 9/23/2015 - 15-079; C0255577 i No .L 10/6/2015 15-080; C0255578 l No + 10/6/2015 15-081; C0255579 No 10/6/2015 15-082; C0255580}}

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