Text

Submittal of Third Interval Inservice Inspection (ISI) Owners Activity Reports
	ML090330171
Person / Time
Site:	Peach Bottom
Issue date:	01/29/2009
From:	Maguire W; Exelon Nuclear
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML090330171 (87)
	v • d • e

Exelon Nuclear www.exeloncorp.com Exek~n Peach Bottom Atomic Power Station Nuclear 1848 Lay Road Delta, PA.17314-9032 10 CFR 50.55a January 29, 2009 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Peach Bottom Atomic Power Station (PBAPS), Units 2 and 3 Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-277 and 50-278

Subject:

Submittal of Third Interval Inservice Inspection (ISI) Owners Activity Reports

References:

1. Peach Bottom Atomic Power Station (PBAPS), Unit 3 3R12 Submittal of Inservice Inspection Summary Report, dated January 31, 2000.

2. Peach Bottom Atomic Power Station (PBAPS), Submittal of the Third 10-Year Interval First Inspection Period, Inservice Inspection Owners Activity Report for Peach Bottom Atomic Power Station, Unit 3, dated April 26, 2002.

Attached are ISI Owner Activity Reports associated with the PBAPS Units 2 and 3, Third ISI Interval activities. These reports cover ISI activities for refueling outages completed from 2002 through 2008. These reports are submitted pursuant to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section XI, "Rules for the Inservice Inspection of Nuclear Power Plant Components," Article IWA-6200, "Requirements" (1989 Edition) and ASME Code Case 532 (Alternative Requirements to Repair and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and Section Xl, Division 1).

Attachments 1A, 1B, 2, 3A and 3B are the Owner Activity Reports for the Unit 2, first, second, and Ithird (last) periods of the 3 rd 10-year ISI interval.

The first period of the 3rd 10-year ISI interval for Unit 3 was reported as a summary report (Reference 1) and an Owners Activity Report (Reference 2) in accordance with ASME Section XI, 1989 Edition. Attachments 4, 5A, and 5B are the Owners Activity Reports for the Unit 3 second and third (last) periods of the 3rd 10-year ISI interval.

If you have any questions, feel free to contact Mr. Nicholas Alexakos at 717-456-4031.

Site Vice President Peach Bottom Atomic Power Station /

cc: F. L. Bower, Senior Resident Inspector, USNRC, PBAPS R. R. Janati, Commonwealth of Pennsylvania Region 1 Administrator, USNRC CCN: 09-10 Attachments (8):

IA. Owners Activity Report (OAR-i) for Refueling Outage 2R13, Third ISI Interval, First Period lB. Owners Activity Report (OAR-i) for Refueling Outage 2R14, Third ISI Interval, First Period

2. Owners Activity Report (OAR-i) for Refueling Outage 2R15, Third ISI Interval, Second Period 3A. Owners Activity Report (OAR-i) for Refueling Outage 2R16, Third ISI Interval, Third Period 3B. Owners Activity Report (OAR-i) for Refueling Outage 2R17, Third ISI Interval, Third Period

4. Owners Activity Report (OAR-i) for Refueling Outage 3R14, Third ISI Interval, Second Period 5A. Owners Activity Report (OAR-i) for Refueling Outage 3R15, Third ISI Interval, Third Period 5B. Owners Activity Report (OAR-l) for Refueling Outage 3R16, Third ISI Interval, Third Period

Attachment 1A Peach Bottom Atomic Power Station Unit 2 Owner Activity Report (OAR-i) for Refueling Outage 2R13 Third 10-Year ISI Interval, First Period

FORM OAR-I OWNER'S ACTIVITY REPORT Report Number: 2R13 Owner: EXELON NUCLEAR 200 Exelon Way I PATTACHMENT A Kennett Square, PA 19348 PAGE 1 OF l1>

Plant: Peach Bottom Atomic Power Station 1848 Lay Road Delta, PA 17314 Unit No.: 2 Commercial Service Date: July 5, 1974 Refueling Outage No.: 13 Current Inspection Interval: 3_d Current Inspection Period: Ist Edition and Addenda of Section XI applicable to the Inspection Plan: 1989 & 1992 Editions, 1992 Addenda Date and Revision of Inspection Plan: September 7, 2000, Revision # 0 and Changes dated March 27, 2001 Edition and Addenda of Section XI applicable to repairs and replacements: Reference CC N-416-1 CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and the examinations, tests, repairs, replacemenrts, evaluations, and corrective measures represented by this report for the period November 2, 1998 to October 5,2000 conform to the requirements of Section XI.

Signed: !* 4 * ' 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 Pennsylvania and employed by Hartford Steam Boiler Inspection & Insurance Company of Hartford, Connecticut have inspected the components described in the Owner's Data Report during the period November 2, 1998 to October 5, 2000 and state that to the best of my knowledge and belief the Owner has performed examinations and taken corrective measures described in this Owner's Data Report in accordance with the requirements of the ASME Code,Section XI.

By signing this certificate, neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the examinations and corrective measures described in this Owner's Data Report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kink arising from or connected with this inspection.

Date: _*,' * *I,-

Inspector's Signature: '"

Commissions: "

National Board, State, Province & No.

ATTACHMENT IA PAGE 2 OF 11 TABLE I ABSTRACT OF EXAMINATIONS AND TESTS

PBAPS U/2 Third Interval Inservice Inspection Abstract of Examinations and Tests ATTACHMENT 1A PAGE 3 OF I I Total Total Total Total Examinations Examinations Examinations Examinations Credited (%) Credited (%)To Examination Required For Credited For For The Date For The Category The Interval This Period Period Interval Remarks 9 or (29.0%) additional exams B-A 31 1 3.2% 3.2% sched. 2nd. Outage.of 1st. Period 24 or (38.7%) examinations sched.

B-D 62 0 0% 0% 2nd. Outage of 1st. Period Examine during system hydro B-E 62 0 0% 0% pressure test sched. 2nd. Period 4 or (40.0%) additional exams B-F 10 1 10% 10% sched. 2nd. Outage of 1st. Period 4 or (40.0%) examinations sched.

B-G-1 10 0 0% 0% 2nd. Outage of 1st. Period 3 or (27.3%) additional exams B-G-2 11* 1 9.1% 9.1% sched. 2nd. Outage of 1st. Period 29 or (27.1 %) additional exams B-J 107 7 6.5% 6.5% sched. 2nd. Outage of 1st. Period 6 or (31.6%) examinations sched.

B-K 19 0 0% 0% 2nd. Outage of 1st. Period Examine when pump is B1M-2 1" 0 0% 0% disassembled for maintenance Examine when pump is BýM-2 20* 0% 0% 0% disassembled for maintenance I or (33.3%) examinations sched B-N-1 3 0 0% 0% 2nd. Outage of 1st. Period Min. of 3.7% additional exams B-N-2 57 7 12.3% 12.3% sched 2nd. Outage of 1st. Period B-O E X E M P T 1 or (20.0%) additional exams B-P 5 1 20% 20% sched. 2nd. Outage of 1st. Period 1 or (50.0%) examinations sched.

C-A 2 0 0% 0% 2nd. Outage of 1st. Period 2 or (50.0) examinations sched.

C-B 4 0 0% 0% 2nd. Outage of 1st. Period 5 or (33.3%) additional exams C-C 14 1 7.1% 7.1% sched 2nd. Outage of 1st. Penod 19 or (24.3%) additional exams C-F-2 78 4 5.1% 5.1% sched. 2nd. Outage of 1st. Interval Expected completion of lst.Period C-H 27 5 18.5% 18.5% pressure tests is 11/04/2002 5 or (19.2%) additional exams D-A 26 4 15.4% 15.4% sched. 2nd. Outage of 1st. Period Expected completion of lst.Period D-B 9 1 11.1% 11.1% pressure tests is 11/04/2002 Includes 100% General Visual /

E-A 29 24 50% 50% VT-3 exam during 2R13 ILRT E-B OPTIONAL EXAMS NOT PERFORMED AT PBAPS Per CRR- 11, examination sched.

E-C 1 0 0% 0% during 2nd. Period 100% credit as permitted by IWB-E-D 1 1 100% 100% 2412 (a) (5) 1995 & later Editions E-F OPTIONAL EXAMS NOT PERFORMED AT PBAPS Per CRR-07, exam satisfied with E-G 76 76 50% 50% Cat.E-A, General Visual / VT-3 1 exam result of ILRT, credit to be E-P 85 1 100% 100% taken for Appendix J Tests 45 or (23.4%) additional exams F-A 192 40 20.8% 20.8% sched. 2nd. Outage of 1st. Period

ATTACHMENT 1A PAGE 4 OF 11 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT' REQUIRED EVALUATION FOR CONTINUED SERVICE

ATTACHMENT 1A PAGE 5 OF 11 Their were no flaws or relevant conditions that required evaluation for continued service as a result of the items examined during the period November 2, 1998 to October 5, 2000.

ATTACHMENT 1A PAGE 6 OF 11 TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE

12/06/00 age 1 of 5

SUMMARY

OF ASME REPAIRS AND RLLACEMENTS COMPLETED FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 NOVEMBER 1, 1998 TO OCTOBER 5, 2000 (END OF 2R13 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair/ replacement activity ATTACHMENT 1A PAGE 7 OF 11 SYSTEM 01: MAIN STEAM SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement RV-2-02-071A Installed a rebuilt safety relief valve No 09/2612000 00-063, R0782758 Class 1 Replacement RV-2-02-071 B Installed a rebuilt safety relief valve No 09/26/2000 00-064, R0707129 Class 1 Replacement RV-2-02-071 E Installed a rebuilt safety relief valve No 09/26/2000 00-065, R0707117 Class 1 Replacement RV-2-02-071 F Installed a rebuilt safety relief valve No 09/26/2000 00-066, R0707122 Class 1 Replacement RV-2-02-071 G Installed a rebuilt safety relief valve No 09/26/2000 00-067, R0707466 Class 1 Replacement RV-2-02-071 H Installed a rebuilt safety relief valve No 09/26/2000 00-068, R0707102 Class 1 Replacement RV-2-02-070B Installed a rebuilt safety relief valve No 09/26/2000 00-069, R0707124 Class 3 Replacement 1-GG-S-2 Installed new hydraulic snubber No 09/24/2000 00-015, R0507538 Class 3 Replacement 1-GG-S-6 Installed new hydraulic snubber No 09/24/2000 00-016, R0507537 Class 3 Replacement 1-GG-S-4 Installed new hydraulic snubber No 09/24/2000 00-017, R0467877 Class 3 Replacement 1 -GG-S-20 Installed new hydraulic snubber No 09/21/2000 00-018, R0477405 Class 1 Replacement SS-A-1 Installed new hydraulic snubber No 09/24/2000 00-027, R0481800 Class 2 Replacement 7-DB-S-10 Installed new hydraulic snubber No 09/25/2000 00-028, R0478031 Class 1 Replacement HV-2-01A-83A Installed new valve bonnet No 10/06/2000 00-113, M1283826 Class 1 Replacement HV-2-01 A-84A Installed new valve bonnet No 10/06/2000 00-114, M1283827 Class 1 Replacement HV-2-01A-84C Installed new valve bonnet No 10/06/2000 00-115, M1283709 Class 1 Replacement HV-2-01A-83C Installed new valve bonnet No 10/06/2000 00-116, M1283708

12/06/00 age 2 of 5

SUMMARY

OF ASME REPAIRS AND REPLACEMENTS COMPLETED FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 NOVEMBER 1, 1998 TO OCTOBER 5, 2000 (END OF 2R13 REFUEL OUTAGE)

ATTACHMENT 1A Denotes that use of Code Case N-416-1 was employed in completing the repair I replacement activity PAGE 8 OF 11 SYSTEM 03: CONTROL ROD DRIVE Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and WIO #

Class 1 Replacement CRD-2-03-2634 Installed new CRD flange tube on CRD No 03/11/1999 98-172, C0185393 Class 1 Replacement CRD-2-03-1295 Installed new CRD flange tube on CRD No 11/09/2000 00-003, R0792638 Class 1 Replacement CRD-2-03-1517 Installed new CRD flange tube on CRD No 11/09/2000 00-003, R0792638 Class 1 Replacement CRD's 14-43, 26-27, 26-35, Exchanged CRD's with rebuilt CRD's during 2R13 outage No 09/29/2000 00-054, R0788362 42-43, 46-35, 50-15, 50-47, Also installed 35 CRD bolts-(incidental replacement) 58-35, 30-15, 34-23, 26-43, 22-47, 22-15, and 46-23.

Class 2 Replacement AO-2-03-033 Installed new air operated valve and piping No 09/29/2000 00-103, C0192800 SYSTEM 06: FEEDWATER SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement MO-2-06D-2163B Replaced valve bonnet and seal welded. leakoff plug. No 09/18/2000 00-076, C0193081 Class 1 Replacement 6-DDNL-S-6 Installed new hydraulic snubber No 09/24/2000 00-019, R0481887 Class 1 Replacement 6-DDNL-S-14 Installed new hydraulic snubber No 09/24/2000 00-020, R0470776 Class 1 Replacement CHK-2-06-96B Welded in new seal plate on check valve No 09/24/2000 00-110, C0195111

12/06/00 age 3 of 5 L

SUMMARY

OF ASME REPAIRS AND REPLACEMENTS COMPLETED FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 NOVEMBER 1, 1998 TO OCTOBER 5, 2000 (END OF 2R13 REFUEL OUTAGE) ATTACHMENT 1A PAGE 9 OF 11 Denotes that use of Code Case N-416-1 was employed in completing the repair/ replacement activity SYSTEM 07: PRIMARY CONTAINMENT Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

M Replacement N-006 installed new CRD Hatch bolting, rods, and studs No 10/02/2000 00-053, R0781380

- M Replacement N-017 RHR Head Spray piping modification per ECR 98-03204 No 10/01/2000 00-104, C0193607 M Replacement N-11OG Replaced stud on RPV stabilizer assembly manhole No 09/23/2000 00-109, C0195083 M Repair N-002 Seal weld stud to primary cont. equip. access hatch No 09/30/2000 00-122, R0782035 SYSTEM 10: RESIDUAL HEAT REMOVAL Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement PB-2-10-M-HX-2BE024 Installation of modified split ring No 03/11/1999 94-193, C0158530 Class 2 Replacement 10-GB-S-12 Installed new pressurized snubber No 05/31/2000 00-083, C0193948

- Class 2 Repair PB-2-1 0-M-HX-2BE024 Repaired cracked partition welds at hx waterbox inlet No 06/23/2000 00-090, C0193919 Class 2 Replacement 10-GB-S-54 Installed new hydraulic snubber No 09/27/2000 00-021, R0481888 Class 2 Replacement 10-GB-S-58 Installed new hydraulic snubber No 09/19/2000 00-022, R0480328 Class 2 Replacement 10-HB-S-7 Installed new hydraulic snubber No 09/19/2000 00-023, R0477872 Class 2 Replacement 10-GB-S-80 Installed new mechanical snubber No, 09/19/2000 00-035, C0192103

- Class 2 Replacement MO-2-10-033 RHR Head Spray piping modification per ECR 98-03204 No 10/01/2000 00-104, C0193607

12/06100,,_,age 4 of 5

SUMMARY

OF ASME REPAIRS AND REPLACEMENTS COMPLETED FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 NOVEMBER 1, 1998 TO OCTOBER 5, 2000 (END OF 2R13 REFUEL OUTAGE) ATTACHMENT 1A PAGE 10 OF 11 Denotes that use of Code Case N-416-1 was employed in completing the repair / replacement activity SYSTEM 12: REACTOR WATER CLEANUP SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement 12-DCN-S-2 Installed new hydraulic snubber No 09/27/2000 00-024, R0496718 SYSTEM 13: REACTOR CORE ISOLATION COOLING SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement VRV-2-13C-139A,B,C,D Installed new vacuum relief valves No 01/11/1999 98-173, C0185372 Class 2 Replacement PSD-2-13-003 Installed eight new all-thread studs on rupture disc No 01/11/1999 99-001, C0182404 Class 2 Replacement PSD-2-13-004 Installed eight new all-thread studs on rupture disc No 01/11/1999 99-002, C0184832

- Class 2 Replacement CHK-2-13C-38 Replaced check valve and associated piping , No 09/18/2000 00-078, C0192861 SYSTEM 14: CORE SPRAY COOLING SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- Class 2 Replacement RV-2-14-020A Installed new relief valve No 0712611999 99-072, R0481251

03/10/00, .... ,age 5of 5

SUMMARY

OF ASME REPAIRS AND REPLACEMENTS COMPLETED FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 IF NOVEMBER 1, 1998 TO OCTOBER 5, 2000 (END OF 2R13 REFUEL OUTAGE)

ATTACHMENT IA PAGE 11 OF 11 Denotes that use of Code Case N-416-1 was employed in completing the repair / replacement activity SYSTEM 23: HIGH PRESSURE COOLANT INJECTION SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement VRV-2-23C-4998B Installed new vacuum relief valve No 11/04/1999 99-139, C0191342 Class 2 Replacement 23-DBN-S-3 Installed new hydraulic snubber No 09/18/2000 00-025, R0468349 Class 2 Replacement 23-HB-S-30 Installed new hydraulic snubber No 09/20/2000 00-026, R0481889 Class 2 Replacement 23-DBN-S-2 Installed new hydraulic snubber No 09/18/2000 00-049, R0468348 Class 2 Replacement 23-DBN-S-27 Installed new pressurized reservoir snubber No 09/22/2000 00-111, C0195126 SYSTEM 33: EMERGENCY SERVICE WATER SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed! Or Test Complete R&R Plan # and W/O #

3 Replacement PB-2-33-0BP057 Installed new pump and seismic restraints' No 05/03/2000 00-001, C0191657

Attachment 1 B Peach Bottom Atomic Power Station Unit 2 Owner Activity Report (OAR-i) for Refueling Outage 2R14 Third 10-Year ISI Interval, First Period

ATTACHMENT 1B PAGE 1 OF 9 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: 2R14 Owner: EXELON NUCLEAR 200 Exelon Way Kennett Square, PA 19348 Plant: Peach Bottom Atomic Power Station 1848 Lay Road Delta, PA 17314 Unit No.: 2 Commercial Service Date: July 5, 1974 Refueling Outage No.: 14 Current Inspection Interval: 3 rd Current Inspection Period: I" Edition and Addenda of Section XI applicable to the Inspection Plan: 1989 Edition & 1992 Edition including 1992 Addenda Date and Revision of Inspection Plan: June 28, 2002, Revision 2 Edition and Addenda of Section XI applicable to repairs and replacements: 1989 Edition and Code Case N-416-1 CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report for the period October 6, 2000 to November 2, 2002 conform to the requirements of Section XI.

Signed: a IF

" in Date: 6J]Z "LtOr CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the Commonwealth of Pennsylvania and employed by Hartford Steam Boiler Inspection &

Insurance Company of Connecticut, of Hartford, Connecticut, have inspected the components described in the Owner's Data Report during the period October 6, 2000 to November 2, 2002 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 examinations, tests, repairs, replacements, evaluations, and corrective measures 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 loss of any kind arising from or connected with this inspection.

Date: ZX) .(

Inspector's Signature:

Commissions: A kA National Board, State, Provinc'e & No.

Peach Bottom Atomic Power Station, Unit 2 ATTACHMENT 1B Third Interval, First Period OAR-1 PAGE 2 OF 9 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Tota Exainatons Examinations Total Credited (%) Examinations Examination Category Examinations Credited For Credited (%)

For (%)RemarksCedite Category Description Required For The 1st The st Tdate for The Interval Period Perio Teo Date for (21113 &2R14) & 21R14) The Interval (21111Period RPV Pressure B-A Retaining 31 12 38.7 38.7 RPV Circumferential shell weld exempted per approved Relief request RR-41 Welds B-D RPV Nozzles, 61 20 32.8 32.8 Case N-598, Alternative Requirements to Required Percentages of Examinations, Inner Radius Section Xl, Division 1 per approved Relief Request RR-33 Partial B-E Penetration 62 0 0.0 0.0 B-E examinations completed during RPV Hydro performed in second period (P2R15).

Welds in Piping B-G-1 Bolting > 2 inch 109 63 57.8 57.8 Code Case N-598 per approved Relief Request RR-33 B-G-2 Bolting < 2 inch 108 38 35.2 35.2 Code Case N-598 per approved Relief Request RR-33 Integral 1) Code Case N-598 per approved Relief Request RR-33 B-K Attachments 16 6 37.5 37.5 2) Use of ASME CC N-509, Alternative Rules for the Selection and Examination of (vessels, Class 1, 2, and 3 Integrally Welded Attachments Section Xl, Division 1, included piping, pumps) Category B-H as B-K Internal B-L-2 Surfaces of 1 1 100.0 100.0 Pump Casings Internal B-M-2 Surfaces of 29 13 44.8 44.8 Valve Bodies B-N-i Reactor Vessel 1 33.3 33.3 Interior Core Support Structures and B-N-2 55 16 29.1 29.1 Interior Attachments All Pressure B-P Retaining 6 2 33.3 33.3 Components Welds in C-A Pressure 2 0 0.0 0.0 Code Case N-598 per approved Relief Request RR-33 Vessels C-B Nozzle Welds in Vessels 8 I 3 37.5 37.5 I

Peach Bottom Atomic Power Station, Unit 2 ATTACHMENT 1B Third Interval, First Period OAR-1 PAGE 3 OF 9 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Examinations Total TotaExainatons Credited (%) Examinations Category Examinations Credited For Credited (%) Remarks Examination Category Description Required For The 1st The CtTdate for The Interval Period Peri Teo Date for (2R 3&RI4) Period The Interval (2R13 &2R14) (2R13 &2R14)

ASME Class 2 Integral 15 5 33.3 33.3 Code Case N-598 per approved Relief Request RR-33 Attachments to Piping All Class 2 C-H Pressure 51 16 31.4 31.4 Retaining Componnets ASME Class 3 D-A Integral 25 0 0.0 0.0 Code Case N-598 per approved Relief Request RR-33 Attachments to Piping Class 3 ECCS, D-B Ect. System 9 3 33.3 33.3 Pressure Tests General Visual performed in refueling outage P2R13 as ILRT. Not required to count E-A Surfaces 57 17 29.8 29.8 double credit for inspection of Drywell, Torus, or Vent System for both 10CFR50.55a period and ILRT requirements.

Augmented EC Exams (Pits, 0 0.0 0.0 Alternative examination program per approved Request for Alternative CRR-1 1 Wall Thickness)

E-D 63 63 100.0 100.0 10CFR5O Appendix J examination of seals and gaskets per approved Request for Alternative CRR-01 E-G 76 76 100.0 100.0 10CFR50 Appendix J and Code Category E-A examination per approved Request for Alternative CRR-07 E-P 1 1 100.0 100.0 In accordance with 10CFR50 Appendix J Test Program and Schedule F-A Supports 167 77 46.1 46.1 Code Case N-598 per approved Relief Request RR-33 R-A Risk Informed 135 40 29.6 29.6 Implemented RI-ISI starting 2nd Period, replacing Categories B-F, B-J, and C-F-2.

Welds I______________ ____ ___________________________

TABLE 2 ATTACHMENT 1B ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE PAGE 4 OF 9 Flaw or Relevant Condition Found Examination Item Item Description Flaw Characterization (IWA-3300) During Scheduled ASME XI Category Number Examination or Test

........... ..... ....... . ......(Yes ye oorr No) o . ......... .......

CH-C-1 Twenty (20) recordable indications. Sizing of Yes B-A B1.21 Closure Head dollar Plate Weld indications were acceptable.

CH-MA One (1) recordable indication. Sizing of indication B-A B51.22 "" Yes Closure Head Meridional Weld at 0 Deg. was acceptable.

Sixty-five (65) recordable indications. Sixteen B122 CH-MB evaluated as rejectable. Accepted by flaw evaluation B-A Yes Closure Head Meridional Weld at 60 Deg. (Ref. GENE-995-004-0902,Rev.I and GENE-0000-

.. . .. ... . . .. . . . . .. . . . . . . 0 00..R ev -0 _[. ........ . .................. . ............ . ....................

B 1.22 CH-MC Three (3) recordable indications. Sizing of B-A Yes Closure Head Meridional Weld at 120 Deg. indications were acceptable.

B-A CH-MD Four (4) recordable indications. Sizing of Yes Closure Head Meridional Weld at 180 Deg. indications were acceptable.

B-A B 1.22 CH-ME Three (3) recordable indications. Sizing of Yes Closure Head Meridional Weld at 120 Deg. indications were acceptable.

B-A CH-MF Four (4) recordable indications. Sizing of B1.22 Closure Head Meridional Weld at 120 Deg. Yes indications were acceptable.

....... .. ......... ca-..

os _... .o..e B-A RPV-MB RPV-MBFour (4) recordable indications. Two (2) ndications B 1.22 Bottom Head Meridional Weld at 60 Deg. evaluated as non relevant rea_*gtw(2in clad reflectors. Sizing of ctoswrecet Yes rm two (2) indications were accept able.

RPV-ME Three (3) recordable indications. Sizing o B-A B 1.22 f No Bottom Head Meridional Weld at 60 Deg. indications were acceptable. IWB-2430 Additional Examination.

NIA.... ..... .. One (1) recordable indication. Sizing of in B-D idication tB3.90 Main Kecirculatlon Yes was acceptable.

Outlet Nozzle-to-Vessel Weld Final U2-13-PI-2R14 OAR-I

TABLE 2 ATTACHMENT 1B ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE PAGE 5 OF 9 Flaw or Relevant Condition Found Examination Item During Scheduled ASME XI Item Description FIaw Characterization (IWA-3300)

Category Number Examination or Test E.....

.... _ es........

(Yes or No)__ or N)........ ............

No H-9 Three (3) recordable indications. Sizing of B-N-2 B13.30 Augmented UT Examination Core Shroud Support Plate Weld indications were acceptable.

... .. . ......................................................... S..............

............. in accordance with BWVIP-38 1 14HB-H5(IA)

C-C One (1) linear (2.7") indication, rejectable.

C3.20 Integral Attachment Yes (N-509) Indication removed, re-examination acceptable.

F-A 12DE-H33 Relevant Condition - Setting out of tolerance.

FS.10 Spring Hanger Yes (N-491-1) Accepted by engineering evaluation.

IF-A (N-491-1) F1.20 1DB-H9B Relevant Condition - Unacceptable thread Yes Rigid Restraint engagement. Accepted by engineering evaluation.

.....i..

F-A i (N-491-1) 1OHB-S5 Relevant Condition - Unacceptable thread I No

,,_[..

Rigid Restraint engagement. Accepted by engineering evaluation. N-491-1, -2430 Additional Examination.

F-A i F1.20 0OGB-S56 Relevant Condition - Loose wall plate studs. Yes (N-491-1)

Rigid Restraint 1 Repaired, re-examination acceptable.

..,L.

N/A N/A 14 inch High Pressure Service Water Piping Minimum Wall Thickness Violations. No

........................ [...................

I..............................................................................................................

Final U2-13-P1-2R14 OAR-1

TABLE 3 ATTACHMENT 1B ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 6 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 6, 2000 TO NOVEMBER 2, 2002 (INCLUDES 2R14 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair / replacement activity SYSTEM 01: MAIN STEAM SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement RV-2-02-070A Installed a rebuilt safety relief valve No 9/20/2002 02-031, R0783804 Class 1 Replacement RV-2-02-071 A Installed a rebuilt safety relief valve No 9/20/2002 02-047, R0876672 Class 1 Replacement RV-2-02-071 C Installed a rebuilt safety relief valve No 9/20/2002 02-048, R0782754 Class 1 Replacement RV-2-02-071 D Installed a rebuilt safety relief valve No 9/20/2002 02-049, R0782757 Class 1 Replacement RV-2-02-071J Installed a rebuilt safety relief valve No 9/20/2002 02-050, R0783627 Class 1 Replacement RV-2-02-071 K Installed a rebuilt safety relief valve No 9/20/2002 02-052, R0782756 Class 1 Replacement RV-2-02-071 L Installed a rebuilt safety relief valve No 9/20/2002 02-051, R0782755 Class 2 Replacement 7-DB-S-14 Installed new snubber No 9/14/2002 00-030, R0477959 Class 1 Replacement AO-2-01 A-086A Installed 20 new bonnet nuts No 9/20/2002 02-011, C0200315 Class 3 Replacement 1-GG-S-27 Installed new snubber and rod eye No 9/15/2002 02-076, R0467885 Class 3 Replacement 1-GG-S-103-B Installed new snubber No 9/15/2002 02-084, C0200967 SYSTEM 02: REACTOR AND RECIRCULATION Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement PB-2-02A-2BP034 Installed new pump cover and internals No 9/30/2002 02-125, C0194212

TABLE 3 ATTACHMENT 1B ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 7 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 6, 2000 TO NOVEMBER 2, 2002 (INCLUDES 2R14 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair/ replacement activity SYSTEM 03: CONTROL ROD DRIVE Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement CRD's 02-19, 02-31, 14-07, Exchanged CRD's with rebuilt CRD's during 2R14 outage No 9/18/2002 02-028, R0851351 34-11, 34-47, 34-51, 50-19, 50-23, 54-35 SYSTEM 06: FEEDWATER SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement 6-DDNL-S-7 Installed new snubber No 9/17/2002 02-055, R0470771 Class 1 Replacement CHK-2-06-96B Installed two new bonnet studs No 9/25/2002 02-151, C0202710 SYSTEM 10: RESIDUAL HEAT REMOVAL Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement RV-2-10-181 D Installed new RHR Hx. 2DE024 Shell Side relief valve No 2/27/2001 00-059, R0601013

- Class 2 Repair PB-2-1 0-M-HX-2CE024 Repaired cracked partition welds at hx waterbox inlet No 1/18/2001 00-132, C0195473 Class 2 Replacement RV-2-10-181C Installed new RHR Hx. 2CE024 Shell Side relief valve No 2/20/2001 01-006, R0707120 Class 2 Replacement RV-2-10-181 B Installed new RHR Hx. 2BE024 Shell Side relief valve No 212612002 02-002, R0601014

TABLE 3 ATTACHMENT 1B ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 8 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 6, 2000 TO NOVEMBER 2, 2002 (INCLUDES 2R14 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair / replacement activity SYSTEM 11: STANDBY LIQUID CONTROL SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement PB-2-1 1-M-PP-2BP040 Installed a new fluid end to pump No 1/2/2001 00-140, C0192156 Class 2 Replacement RV-2-11-39A Installed new relief valve No 9/20/2002 02-016, R0849828 Class 2 Replacement RV-2-11-39B Installed new relief valve No 9/20/2002 02-017, R0849827 SYSTEM 12: REACTOR WATER CLEANUP SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement 12-DCN-S-7 Installed new snubber, rod eye, and pipe clamp No 9/25/2002 02-056, R0470780 Class 1 Replacement 12-DCN-S-8-A Installed new snubber No 9/14/2002 02-119, C0201425 SYSTEM 23: HIGH PRESSURE COOLANT INJECTION SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement VRV-2-23C-4998B Installed new vacuum relief valve. No 3/15/2001 01-088, C0196924 Class 2 Replacement VRV-2-23C-4998A Installed new vacuum relief valve. No 4/2/2002 01-089, C0196928 Class 2 Replacement CHK-2-23B-62 Installed new hinge pin plugs No 9/18/2002 02-014, R0781995 Class 2 Replacement CHK-2-23C-65 Installed new check valve No 10/3/2002 02-126, C0199297

TABLE 3 ATTACHMENT 1B ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 9 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 6, 2000 TO NOVEMBER 2, 2002 (INCLUDES 2R14 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair / replacement activity SYSTEM 32: HIGH PRESSURE SERVICE WATER SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 3 Replacement RV-2-32-180B Installed new RHR Hx. 2BE024 Tube Side relief valve No 2/26/2001 00-108, R0605930 Class 1

3 Replacement RV-2-32-180D Installed new RHR Hx. 2DE024 Tube Side relief valve No 5/18/2001 01-110, R0640862 SYSTEM 48: EMERGENCY COOLING WATER Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 3 Replacement PB-2-48A-OOP186 Install seismic restraint, Emergency Cooling Water Pump No 11/29/2001 01-141, R0050429

Attachment 2 Peach Bottom Atomic Power Station Unit 2 Owner Activity Report (OAR-i) for Refueling Outage 2R15 Third 10-Year ISI Interval, Second Period

ATTACHMENT 2 PAGE 1 OF 10 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: 2R15 Owner: EXELON NUCLEAR 200 Exelon Way Kennett Square, PA 19348 Plant: Peach Bottom Atomic Power Station 1848 Lay Road Delta, PA 17314 Unit No.: 2 Commercial Service Date: July 5, 1974 Refueling Outage No.: 15 Current Inspection Interval: 3 rd Current Inspection Period: 2 nd Edition and Addenda of Section XI applicable to the Inspection Plan: 1989 Edition & 1992 Edition including 1992 Addenda Date and Revision of Inspection Plan: September 7, 2004, Revision 1 Edition and Addenda of Section XI applicable to repairs and replacements: 1989 Edition and Code Case N-416-1 CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report for the period November 3, 2002 to October 9, 2004 conform to the requirements of Section XI.

Signed: d______ Date:OV-20O CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the Commonwealth of Pennsylvania and employed by Hartford Steam Boiler Inspection &

Insurance Company of Connecticut, of Hartford, Connecticut, have inspected the components described in the Owner's Data Report during the period November 3, 2002 to October 9, 2004 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 examinations, tests, repairs, replacements, evaluations, and corrective measures 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 loss of any kind arising from or connected with this inspection.

Date: 2.,. ?

L.K Inspector's Signature:

Commissions: - 1Z. PL- Z ! A-L National BoaYd, State, Province & No.

Peach Bottom Atomic Power Station, Unit 2 ATTACHMENT 2 Third Interval, Second Period OAR-1 PAGE 2 OF 10 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Total Examination Examinations Examinations Examinations Examinations Required For Credited For Credited (%) Credited (%) Remarks Category The The 2nd For The 2nd To Date for Interval Period (P2R15) Period (P2R15) The Interval B-A 31 8 25.8 64.5 RPV Circumferential shell weld exempted per approved Relief request RR-41 Case N-598, Alternative Requirements to Required Percentages of Examinations, Section Xl, Division I per approved Relief Request RR-33 B-E 62 62 100.0 100.0 B-E examinations completed during RPV Hydro performed in second period.

B-G-1 109 0 0.0 57.8 Code Case N-598 per approved Relief Request RR-33 B-G-2 108 28 25.9 61.1 Code Case N-598 per approved Relief Request RR-33

1) Code Case N-598 per approved Relief Request RR-33 B-K 16 6 37.5 75.0 2) Use of ASME CC N-509, Alternative Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded AttachmentsSection XI, Division 1, included Category B-H as B-K B-L-2 1 0 0.0 100.0 B-M-2 29 11 37.9 82.8 B-N-1 3 1 33.3 66.7 B-N-2 55 13 23.6 52.7 B-P 6 1 16.7 50.0 C-A 2 0 0.0 0.0 Code Case N-598 per approved Relief Request RR-33 C-B 8 2 25.0 62.5 C-C 15 4 26.7 60.0 Code Case N-598 per approved Relief Request RR-33 C-H 51 16 31.4 62.7 D-A 25 7 28.0 28.0 Code Case N-598 per approved Relief Request RR-33 D-B 9 3 33.3 66.7

Peach Bottom Atomic Power Station, Unit 2 ATTACHMENT 2 Third Interval, Second Period OAR-1 PAGE 3 OF 10 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Total Examinations Examinations Examinations Examinations Examination Required For Credited For Credited (%) Credited (%) Remarks Category The The 2nd For The 2nd To Date for Interval Period (P2R15) Period (P2R15) The Interval General Visual performed in P2R13 (1st Period) prior to ILRT. Not required to count double credit E-A 57 17 29.8 59.6 for inspection of Drywell, Torus, or Vent System for both 10CFR50.55a period and ILRT requirements.

E-C 3 2 66.7 66.7 Alternative examination program per approved Request for Alternative CRR-1 1 E-D 63 0 0.0 100.0 10CFR50 Appendix J examination of seals and gaskets in the 1st period per approved Request for Alternative CRR-01 E-G 76 0 0.0 100.0 10CFR50 Appendix J and Code Category E-A examination in the 1st period per approved Request for Alternative CRR-07 E-P 1 0 0.0 100.0 Examined in the 1st period In accordance with 10CFR50 Appendix J Test Program and Schedule F-A 167 41 24.6 70.7 Code Case N-598 per approved Relief Request RR-33 R-A 135 37 27.4 57.0 Implemented RI-ISI starting 2nd Period, replacing Categories B-F, B-J, and C-F-2.

TABLE 2 ATTACHMENT 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE PAGE 4 OF 10 T.....

Flaw or Relevant Condition Found Examination Item During Scheduled ASME XI Item Description Flaw Characterization (IWA-3300)

Category Number Examination or Test

-]~~~~~~ . . .... . ... ....... . . .~~~ . .... .. ................... . . . .. .. . . ... (Yes

. . . ..or No)

I CH-MB Two (2) recordable indications. Accepted by flaw No B-A I Closure Head Meridional Weld at 60 Deg. evaluation. IWB-2420 Successive Examination One (1) subsurface flaw indication on adjacent B-D B3.90 Main Recirculation circumferential weld RPV-Cl. Accepted by flaw Yes Outlet..

u ......

et. .......

Nozzle-to-Vessel ! to- .-*... s.es.... ...

Weld ....................

[evaluation.

"i...... ........................ ..........................

C-C C3.20 1ODDN-H91(IA) One (1) linear (2.85") indication, rejectable.

Integral Attachment Yes (N-509) Indication removed, re-examination acceptable.

No C-C C3.20 14HB-H18(IA) One (1) linear (1.25") indication, rejectable.

Integral Attachment N-509, 1.3 (IWC-2430) Additional (N-509) Indication removed, re-examination acceptable.

......... .. .... .......... .. . ........... . .... ............... .... ...... Examination.

23-0-43 ID geometric indication recorded in repair area. No C-F-2 C5.21 1Valve to Elbow Weld Sizing of indication was acceptable. Baseline Exam.

C F................................

C -F -2 23-0-44 t Eleven (11) relevant indications. Sizing of No C5.21 1Valve to Elbow Weld indications were acceptable. Baseline Exam.

Pitting was inspected and depths measured.

E-C E4.11 Torus Wetted Pressure Boundary Yes Accepted by Engineering Evaluation.

F-A 48GB-S12 Relevant Condition - Rust & cracked concrete i 1FI.30Ye Rigid Restraint (N-491-1) ................. noted during exam. Acceptable per Section XI. Yes F-A F1.30 48GB-S17 Relevant Condition - Rust & cracked concrete (N-491-1) Rigid Restraint noted during exam. Acceptable per Section XI.

.--- ..---...... i....-....--....-.....-.-.-.-..- _.___ _ _......___ _ _ _ __ _

F-A 48GB-$32 Relevant Condition - Rust & cracked concrete (N-491-1) F1.30 Rigid Restraint noted during exam. Acceptable per Section XI.

............... ..... ............. ....... ... ............. ... ...... ..... ..... .. ................ . Y.e...........s.......

e...

Final U2-13-P2-2R15 OAR-1 Page 4 of 9

TABLE 2 ATTACHMENT 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE PAGE 5 OF 10 Flaw or Relevant Condition Found Examination Item During Scheduled ASME XI Category Number Item Description Flaw Characterization (IWA-3300)

Examination or Test (Yes or No)

F-A F1.30 48HB-S33 Relevant Condition - Rust & cracked concrete Yes (N-491-1) Rigid Restraint noted during exam. Acceptable per Section XI.

~~

.. ~.,.. ........................

RI.11 ID geometric indication recorded. Sizing of No R-A RElbow to Pipe Weld indication was acceptable. Baseline Exam.

R1.20 i10-2DA20-6 ID geometric indication recorded. Sizing of No R-A Elbow to Pipe Weld indication was acceptable. Baseline Exam.

N/A N/A High Pressure Srvice Water System Wall thickness measurements less than minimum 14 inch NOD carbon steel piping wall.

N/A N/A High Pressure Srvice Water System Wall thickness measurements less than minimum 14xl8xl8 inch NOD carbon steel pipe tee. wall.

Final U2-13-P2-2R15 OAR-1 Page 5 of 9

TABLE 3 ATTACHMENT 2 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 6 OF 10 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 NOVEMBER 3, 2002 TO OCTOBER 9, 2004 (INCLUDES 2R15 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair/ replacement activity SYSTEM 01: MAIN STEAM SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- Class 1 Replacement HV-2-01A-83A & 84A Installed new valves No 9/22/2004 04-012, C0208124 Class 1 Replacement RV-2-02-071 G Installed a rebuilt safety relief valve No 10/4/2004 04-045, R0876673 Class 1 Replacement RV-2-02-071 E Installed a rebuilt safety relief valve No 10/4/2004 04-046, R0851874 Class 1 Replacement RV-2-02-071 H Installed a rebuilt safety relief valve No 10/4/2004 04-047, R0852188 Class 1 Replacement RV-2-02-071 B Installed a rebuilt safety relief valve No 10/4/2004 04-048, R0850766 Class 1 Replacement RV-2-02-071 F Installed a rebuilt safety relief valve No 10/4/2004 04-049, R0851812 Class 1 Replacement RV-2-02-070B Installed a rebuilt safety relief valve No 10/4/2004 04-050, R0851537 Class 2 Replacement 1DB-H1170 Relocated spring hanger support No 9/23/2004 04-156, C0210216 Class 1 Replacement MO-2-01A-077 Installed helicoil for a stripped pressure seal bonnet stud No 9/22/2004 04-160, R0487872 Class 1 Replacement RV-2-02-071 F Installed a rebuilt safety relief valve No 10/4/2004 04-161, R0851812 SYSTEM 02: REACTOR AND RECIRCULATION Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- Class 1 Replacement HV-2-02-15, HV-2-02-16 Installed new valves No 10/8/2004 04-152, R0922216

TABLE 3 ATTACHMENT 2 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 7 OF 10 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 NOVEMBER 3, 2002 TO OCTOBER 9, 2004 (INCLUDES 2R15 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair / replacement activity SYSTEM 03: CONTROL ROD DRIVE Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement CRD's 06-27, 10-27, 10-47, Exchanged CRD's with rebuilt CRD's No 10/8/2004 04-080, R0935052 14-15, 14-51, 18-03, 18-39, 18-51, 22-51, 26-55, 30-07, 38-59, 42-03, 42-55, 46-43, 54-15, 54-31, 54-39, 54-43

- Class 1 Replacement cleanout pipe caps Remove/install pipe caps to flush scram disch. Header No 9/22/2004 04-094, C0209098 SYSTEM 06: FEEDWATER SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement CHK-2-06-96B Installed new bonnet modification No 10/4/2004 04-039, C0208272 SYSTEM 10: RESIDUAL HEAT REMOVAL Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- Class 2 Replacement MO-2-10-026B Installed branch connection over hole for FME retrieval No 10/6/2004 04-169, C0211427

TABLE 3 ATTACHMENT 2 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 8 OF 10 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 NOVEMBER 3, 2002 TO OCTOBER 9, 2004 (INCLUDES 2R15 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair / replacement activity SYSTEM 12: REACTOR WATER CLEANUP SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- Class 1 Replacement MO-2-12-068 Installed new valve No 10/8/2004 04-077, R0612166 SYSTEM 14: CORE SPRAY SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- Class 2 Replacement RV-2-14-020B Installed new relief valve No 9/26/2004 02-013, R0735131 SYSTEM 23: HIGH PRESSURE COOLANT INJECTION SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- Class 2 Replacement MO-2-23-014 Installed new valve No 10/1/2004 02-093, R0786125 Class 1 Repair MO-2-23-016 Performed weld overlay on pressure seal bonnet No 12/19/2002 02-211, C0203523 Class 2 Replacement MO-2-23-015 Installed 8 new pressure seal studs and nuts No 9/23/2004 03-058, C0204882

- Class 2 Replacement RV-2-23B-034 Installed new relief valve No 5/12/2004 04-092, R0781699 Class 2 Replacement 2-23MO-H47 Replaced spring can all thread rod No 5/12/2004 04-108, C0209683 Class 2 Replacement AO-2-23-137 Removed &reinstalled piping to perform boroscope insp. No 9/30/2004 04-151, C0211189

TABLE 3 ATTACHMENT 2 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 9 OF 10 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 NOVEMBER 3, 2002 TO OCTOBER 9, 2004 (INCLUDES 2R15 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair / replacement activity SYSTEM 32: HIGH PRESSURE SERVICE WATER SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 3 Replacement RV-2-32-180C Installed new RHR Hx. 2CE024 Tube Side relief valve No 12/3/2003 00-002, R0752895 Class 3 Replacement PB-2-32-2DP042 Installed new pump and pump bowls No 1113/2003 02-163, C0202851

- Class 3 Replacement PB-2-32-RO-2789B/D Replaced piping between RO-2789B to RO-2789D No 1/7/2003 02-170, C0202662 Class 3 Replacement RV-2-32-180A Installed new RHR Hx. 2AE024 Tube Side relief valve No 1/12/2004 03-107, R0752896 Class 3 Replacement RV-2-32-180B Installed new RHR Hx. 2BE024 Tube Side RV bolting nuts No 5/27/2004 04-109, C0209424

- Class 3 Replacement PB-2-32-RO-2789C Installed new outlet restricting orifice & associated piping No 9/20/2004 04-147, C0209471 SYSTEM 52: DIESEL GENERATOR Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 3 Replacement XJ-70133D Installed two new studs for thread engagement issue No 6/23/2004 04-127, R0904428

TABLE 3 ATTACHMENT 2 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 10 OF 10 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 NOVEMBER 3, 2002 TO OCTOBER 9, 2004 (INCLUDES 2R15 REFUEL OUTAGE)

Denotes that use of Code Case N-416-1 was employed in completing the repair I replacement activity SYSTEM 65A: HYDRAULIC SNUBBERS Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement 7-DB-S-1 1 Installed new snubber, rod eye, and extension piece No 10/2/2004 00-029, R0707171 Class 1 Replacement SS-C-6 Installed new snubber, rod eye paddle, & extension piece No 9/23/2004 04-052, C0208085 Class 1 Replacement 10-GB-S-50 Installed new pipe end load pin No 9/24/2004 04-061, C0208067 Class 1 Replacement 1-GG-S-24 Installed new snubber and rod eye extension piece No 9/20/2004 04-085, R0705716 Class 1 Replacement 7-DB-S-13 Installed new snubber No 9/21/2004 04-093, R0706728 Class 2 Replacement 7-DB-S-15 Installed new snubber No 9/24/2004 04-153, C0211249 Class 2 Replacement 23-DBN-S-29 Installed new snubber No 9/27/2004 04-159, C0211296 Class 3 Replacement 1-GG-S-83 Installed new pipe clamp fasteners No 9/25/2004 04-164, C0211349 Class 3 Replacement 1-GG-S-1 Installed new pipe clamp fasteners No 9/25/2004 04-165, C0211358 Class 3 Replacement 1-GG-S-78 Installed new pipe clamp fasteners No 9/26/2004 .04-166, C0211368 Class 3 Replacement 1-GG-S-80 Installed new pipe clamp fasteners No 9/26/2004 04-167, C0211369 SYSTEM 65B: MECHANICAL SNUBBERS Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement 1-GG-S-203-A Installed new snubber No 9/20/2004 04-054, C0208087 Class 1 Replacement 1-GG-S-206-B Installed new snubber No 9/20/2004 04-056, C0208089

Attachment 3A Peach Bottom Atomic Power Station Unit 2 Owner Activity Report (OAR-i) for Refueling Outage 2R16 Third 10-Year ISI Interval, Third Period

ATTACHMENT 3A PAGE 1 OF 8 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: 2R16 Owner: EXELON NUCLEAR 200 Exelon Way Kennett Square, PA 19348 Plant: Peach Bottom Atomic Power Station 1848 Lay Road Delta, PA 17314 Unit No.: 2 Commercial Service Date: July 5, 1974 Refueling Outage No.: 16 Current Inspection Interval: 3 rd Current Inspection Period: 3 rd Edition and Addenda of Section XI applicable to the Inspection Plan: 1989 & 1992 Editions, 1992 Addenda Date and Revision of Inspection Plan: February 21, 2006, Revision 2 Edition and Addenda of Section XI applicable to repairs and replacements: 1989 Edition and Code Case N-416-1 CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report for the period October 10, 2004 to October 4, 2006 conform to the requirements of Section XI.

Signed: /fL1 &.

/t { 79 Date: O" '2-2200O CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the Commonwealth of Pennsylvania and employed by Hartford Steam Boiler Inspection &

Insurance Company of Connecticut, of Hartford, Connecticut, have inspected the components described in the Owner's Data Report during the period October 10, 2004 to October 4, 2006 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 examinations, tests, repairs, replacements, evaluations, and corrective measures 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 loss of any kind arising from or connected with this inspection.

Date: 6? J 7.C.flx, Inspector's Signature:

Commissions: QY%* N* _ qk7 , ,

National BoArd, State, Province & N1o.

Peach Bottom Atomic Power Station, Unit 2 ATTACHMENT 3A Third Interval, Third Period OAR Refueling Outage P2R16 PAGE 2 OF 8 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Total Examinations Examinations Examinations Examinations Examination Category Credited For Credited (%) Credited (%)

Category Description equired For The 3rd For The 3rd Credite for The Pro Period Peid Period To Date for Interval (P2R16) (P2R16) The Interval RPV Pressure B-A Retaining 31 0 0.0 64.5 RPV Circumferential shell weld exempted per approved Relief request RR-41 Welds B-D RPV Nozzles, 61 18 29.5 82.0 Case N-598, Altemative Requirements to Required Percentages of Inner Radius _Examinations, Section XI, Division 1 per approved Relief Request RR-33 Partial B-E Penetration 62 0 0.0 100.0 B-E examinations completed during RPV Hydro performed in second period.

Welds in Piping B-G-1 Bolting > 2 inch 109 46 42.2 100.0 Code Case N-598 per approved Relief Request RR-33 B-G-2 Bolting < 2 inch 108 23 21.3 82.4 Code Case N-598 per approved Relief Request RR-33 Integral 1) Code Case N-598 per approved Relief Request RR-33 B-K Attachments 16 25.0 100.0 2) Use of ASME CC N-509, Alternative Rules for the Selection and (vessels, Examination of Class 1, 2, and 3 Integrally Welded Attachments Section Xl, piping, pumps) Division 1, included Category B-H as B-K Internal B-L-2 Surfaces of 1 0 0.0 100.0 Pump Casings Internal B-M-2 Surfaces of 29 5 17.2 100.0 Valve Bodies Reactor Vessel B-N-1 Interior 3 0 0.0 66.7 Core Support B-N-2 Structures and 55 14 25.5 78.2 Interior Attachments All Pressure B-P Retaining 6 2 33.3 83.3 Components Welds in C-A Pressure 2 1 50.0 50.0 Code Case N-598 per approved Relief Request RR-33 Vessels Unit 2 Final Third Interval OAR-1

Peach Bottom Atomic Power Station, Unit 2 ATTACHMENT 3A Third Interval, Third Period OAR Refueling Outage P2R16 PAGE 3 OF 8 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Total Examinations Examinations Examinations Examinations Examination Category Required For Credited For Credited (%) Credited (%) Remarks Category Description The The 3rd For The 3rd To Date for Period Period Interval The Interval (P2R16) (P2R16)

Nozzle Welds C-B NoVe in Vessels 8 3 37.5 100.0 ASME Class 2 CC Integral C-C Attachments to 15 5 33.3 93.3 Code Case N-598 per approved Relief Request RR-33 Piping All Class 2 Pressure C-H Retaining 51 14 27.5 90.2 Componnets ASME Class 3 0A Integral D-A Attachments to 25 9 36.0 64.0 Code Case N-598 per approved Relief Request RR-33 Piping Class 3 ECCS, D-B Ect. System 9 1 11.1 77.8 Pressure Tests General Visual performed in P2R1 3 (1st Period) prior to ILRT. Not required to E-A Surfaces 57 3 5.3 64.9 count double credit for inspection of Drywell, Torus, or Vent System for both 10CFR50.55a period and ILRT requirements.

Augmented EC Exams (Pits, E-C a3 1 33.3 100.0 Alternative examination program per approved Request for Alternative CRR-1 1 Thickness)

E-D 63 0 0.0 10 1CFR50 Appendix J examination of seals and gaskets in the 1st period per approved Request for Alternative CRR-01 E-G 76 0 0.0 100.0 10CFR50 Appendix J and Code Category E-A examination in the 1st period per approved Request for Alternative CRR-07 E-P 1 0 0.0 100.0 Examined in the 1st period In accordance with 10CFR50 Appendix J Test Program and Schedule F-A Supports 167 47 28.1 98.8 Code Case N-598 per approved Relief Request RR-33 R-A Risk Informed 135 26 19.3 76.3 Implemented RI-ISI starting 2nd Period, replacing Categories B-F, B-J, and C-F Welds 1 12.

Unit 2 Final Third Interval OAR-1

ATTACHMENT 3A PAGE 4 OF 8 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw or Relevant Condition Found Examination Item During Scheduled ASME XI Item Description Flaw Character Category Number Examination or Test

..... ..................... (Yes or No)

F-A 14GB-H40 Relevant Condition - Loose spacer and bent clamp. Yes (N-491-1) F1.20 Spring Hanger Accepted by Engineering Evaluation.

S 0...................................

Relevant Condition - Missing bolts, wrong size F-A SF1.40 RHRHX-A-LS Cortimsi bolts, gap in plate. Repaired fror and the re-examination Yes (N-491 -1) Heat........

Exchanger Low..er.Support.was acceptable.

F-A i ] Concrete is missing from around one of the four 1 Yes

~Yes F1.20 Spring Hanger 23-HB-H-35bolts (N-491-1)

........................................................................................... a..................r P...................................................

i.......

. ...... ... l..........................

l............ ....................................

N/A ~6-inch Carbon Steel Emergency Service Water Pnhl ek N/A No ripe HPCI Turbine Steam Supply Valve MO-2 N/A N/A Small steam leak on valve leak-off plug. No 014, ASME Class 2 Final U2-13-P3-2R16 OAR-1

TABLE 3 ATTACHMENT 3A ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 5 OF 8 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 10, 2004 TO OCTOBER 4, 2006 (INCLUDES 2R16 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-2 was employed in completing the repair/ replacement activity SYSTEM 01: MAIN STEAM SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement RV-2-02-071 D Installed a rebuilt safety relief valve No 2/4/2005 04-175, C0211903 Class 1 Replacement AO-2-01 A-086C Installed 5 new studs and nuts as incidental replacement No 10/2/2006 04-136, R0968832 Class 1 Replacement AO-2-01 A-080C Installed new studs and nuts as incidental replacement No 9/30/2006 06-101, R0978348 Class 1 Replacement RV-2-02-071A Installed a rebuilt safety relief valve No 9/26/2006 06-118, R0955420 Class 1 Replacement RV-2-02-071 C Installed a rebuilt safety relief valve No 9/26/2006 06-119, R0924536 Class 1 Replacement RV-2-02-071 D Installed a rebuilt safety relief valve No 9/26/2006 06-120, R0918419 Class 1 Replacement RV-2-02-071 J Installed a rebuilt safety relief valve No 9/27/2006 06-121, R0931486 Class 1 Replacement RV-2-02-071 K Installed a rebuilt safety relief valve No 9/27/2006 06-122, R0936216 Class 1 Replacement RV-2-02-071 L Installed a rebuilt safety relief valve No 9/27/2006 06-123, R0924578 Class 1 Replacement RV-2-02-070B Installed a rebuilt safety relief valve No 9/26/2006 06-124, R0917366 SYSTEM 03: CONTROL ROD DRIVE Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement CRD's 02-27, 06-35, 06-47, Exchanged CRD's with rebuilt CRD's No 9/25/2006 06-046, R0983803 18-11, 22-11, 22-31, 22-55, 22-59, 26-03, 26-59, 30-31, 34-19, 34-23, 34-39, 38-31, 38-47, 38-51, 46-11, 50-31

- Class I Replacement SVD cleanout pipe caps Install pipe caps/connections on scram disch. header No 9/27/2006 06-126, C0216745

TABLE 3 ATTACHMENT 3A ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 6 OF 8 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 10, 2004 TO OCTOBER 4, 2006 (INCLUDES 2R16 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-2 was employed in completing the repair/ replacement activity SYSTEM 10: RESIDUAL HEAT REMOVAL Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement RV-2-10-181A Installed new RHR Hx. 2AE024 Shell Side relief valve No 2/20/2006 06-001, R0795544

- Class 3 Replacement MO-2-10-089C Installed new RHR Hx 2CE024 HPSW Outlet Valve No 9/20/2006 06-134, C0216868 Class 3 Replacement PB-2-10-2AE024 Replaced lower heat exchanger support bolting Yes 9/22/2006 06-186, C0216303 Class 2 Replacement PB-2-10-2DP035 Installed new pump rotating assembly No 10/2/2006 06-190, C0218990 SYSTEM 11: STANDBY LIQUID CONTROL SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W1O #

Class 2 Replacement RV-2-11-39A Installed new relief valve No 9/23/2006 06-132, R0988018 Class 2 Replacement RV-2-11-39B Installed new relief valve No 9/23/2006 06-133, R0981054 Class 2 Replacement RV-2-11-39A Installed new relief valve No 9/29/2006 06-192, R0988018 SYSTEM 14: CORE SPRAY SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement RO-2-14-037D Installed new studs/nuts due to thread engagement issue No 8/9/2005 05-116, C0213871 Class 2 Replacement RV-2-14-020A Installed new relief valve No 8/2/2006 06-150, R0813398

TABLE 3 ATTACHMENT 3A ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 7 OF 8 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 10, 2004 TO OCTOBER 4, 2006 (INCLUDES 2R16 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-2 was employed in completing the repair/ replacement activity SYSTEM 23: HIGH PRESSURE COOLANT INJECTION SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Repair MO-2-23-014 Repaired seal weld on threaded bonnet leakoff plug No 4/26/2005 05-107, C0213614 SYSTEM 33: EMERGENCY SERVICE WATER Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 3 Replacement XJ-70133C Installed 8 new bolts due to thread engagement issue No 2/15/2005 04-177, R0932884 Class 3 Replacement AO-2-33-2335G Installed 6 new studs/nuts due to thread engagement issue No 4/19/2005 05-003, C0212167

- Class 3 Replacement HV-2-33-517 Installed new valve No 9/30/2006 04-086, C0208469 Class 3 Repair CHK-0-33-515A Weld build up disc arm and valve body stop location No 6/13/2005 04-174, R0812619

- Class 3 Replacement RTV-0-33-244B Replaced degraded piping downstream of RTV-0-33-244B No 5/10/2006 05-147, C0215848

TABLE 3 ATTACHMENT 3A ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 8 OF 8 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 10, 2004 TO OCTOBER 4, 2006 (INCLUDES 2R16 REFUEL OUTAGE)

Denotes that use of Code Case N-416-2 was employed in completing the repair/ replacement activity SYSTEM 65A: HYDRAULIC SNUBBERS Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement 13-DBN-S-15 Installed new snubber No 9/19/2006 06-014, C0216161 Class 2 Replacement 23-DBN-S-1 Installed new snubber No 9/19/2006 06-016, C0216163 Class 1 Replacement SS-B-6 Installed new snubber No 9/27/2006 06-017, C0216165 Class 2 Replacement 1-DB-S-15-A Installed new snubber No 9/29/2006 06-084, R0780512 Class 2 Replacement 1-DB-S-25-A Installed new snubber No 9/29/2006 06-085, R0780902 Class 2 Replacement 1-DB-S-2-A Installed new snubber No 9/29/2006 06-086, R0780903 Class 2 Replacement 1-DB-S-38-A Installed new snubber No 9/29/2006 06-087, R0780974 SYSTEM 65B: MECHANICAL SNUBBERS Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement 14-MO-S-26 Installed new snubber No 9/28/2006 06-021, C0216175

Attachment 3B Peach Bottom Atomic Power Station Unit 2 Owner Activity Report (OAR-i) for Refueling Outage 2R17 Third 10-Year ISI Interval, Third Period

ATTACHMENT 3B PAGE 1 OF 11 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: 2R17 Owner: EXELON NUCLEAR 200 Exelon Way Kennett Square, PA 19348 Plant: Peach Bottom Atomic Power Station 1848 Lay Road Delta, PA 17314 Unit No.: 2 Commercial Service Date: July 5, 1974 Refueling Outage No.: 17 Current Inspection Interval: 3 rd Current Inspection Period: 3 rd Edition and Addenda of Section XI applicable to the Inspection Plan: 1989 Edition & 1992 Edition including 1992 Addenda Date and Revision of Inspection Plan: September 16, 2008, Revision 2 Edition and Addenda of Section XI applicable to repairs and replacements: 1989 Edition and Code Case N-416-1 CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report for the period October 5, 2006 to November 4, 2008 conform to the requirements of Section XI.

Signed: 6dmdu/)

. " g{' Date: /.ZtZo, CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the Commonwealth of Pennsylvania and employed by Hartford Steam Boiler Inspection &

Insurance Company of Connecticut, of Hartford, Connecticut, have inspected the components described in the Owner's Data Report during the period October 5, 2006 to November 4, 2008 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 examinations, tests, repairs, replacements, evaluations, and corrective measures 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 loss of any kind arising from or connected with this inspection.

Date: ,*.

Inspector's Signature:

Commissions: P~2AL-

- ýA ýA -V

)

Peach Bottom Atomic Power Station, Unit 2 ATTACHMENT 3B Third Interval, Third Period OAR Through Refueling Outage 2R17 PAGE 2 OF 11 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Examinations Examinations Total Examinations CreditedoFo Examinations Examiatio ReqiredFor he 3dFor Credited Crdite (%) Examinations Credited (%)Reak Category Required For e3rd For The 3rd To Date for The Period Period (P2R16 To Daterval Interval (P2R16 & & P2R17) The Interval P2R17)

B-A 31 11 35.5 100.0 RPV Circumferential shell weld exempted per approved Relief request RR-41 Case N-598, Alternative Requirements to Required Percentages of Examinations,Section XI, Division 1 per approved Relief Request RR-33 B-E 62 0 0.0 100.0 B-E examinations completed during RPV Hydro performed in second period.

B-G-1 109 46 42.2 100.0 Code Case N-598 per approved Relief Request RR-33 B-G-2 108 42 38.9 100.0 Code Case N-598 per approved Relief Request RR-33

1) Code Case N-598 per approved Relief Request RR-33 B-K 16 743.8 118.8 2) Use of ASME CC N-509, Alternative Rules for the Selection and Examination of Class 1,2, and 3 Integrally Welded AttachmentsSection XI, Division 1, included Category B-H as B-K B-L-2 1 0 0.0 100.0 B-M-2 29 5 17.2 100.0 B-N-1 3 1 33.3 100.0 B-N-2 55 26 47.3 100.0 B-P 6 3 50.0 100.0 C-A 2 2 100.0 100.0 Code Case N-598 per approved Relief Request RR-33 C-B 8 3 37.5 100.0 C-C 15 9 60.0 120.0 Code Case N-598 per approved Relief Request RR-33 Unit 2 Final Third Interval OAR-1

Peach Bottom Atomic Power Station, Unit 2 ATTACHMENT 3B Third Interval, Third Period OAR Through Refueling Outage 2R17 PAGE 3 OF 11 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Examinations Examinations Total Examinations Credited For Examinations Examination Required For The 3rd Credited (%) Credited (%) Remarks Category The Period For The 3rd To Date for Interval (P2R16 & & P2R167 The Interval P2R17) &_P2R17)

C-H 51 19 37.3 100.0 D-A 25 18 72.0 100.0 Code Case N-598 per approved Relief Request RR-33 D-B 9 3 33.3 100.0 General Visual performed in P2R13 (1st Period) prior to ILRT. Not required to count E-A 57 23 40.4 100.0 double credit for inspection of Drywell, Torus, or Vent System for both 10CFR50.55a period and ILRT requirements.

E-C 3 1 33.3 100.0 Alternative examination program per approved Request for Alternative CRR-11 E-D 63 0 0.0 100.0 OCFR50.Appendix 1Request J examination of seals and gaskets in the 1st period per approved for Alternative CRR-01 10CFR50 approved Appendix J and Code Category E-A examination in the 1st period per Request for Alternative CRR-07 E-P 1 0 0.0 100.0 Examined in the 1st period In accordance with 10CFR50 Appendix J Test Program and Shdl Schedule F-A 167 75 44.9 115.6 Code Case N-598 per approved Relief Request RR-33 R-A 135 58 43.0 100.0 Implemented RI-ISI starting 2nd Period, replacing Categories B-F, B-J, and C-F-2.

Unit 2 Final Third Interval OAR-1

ATTACHMENT 3B PAGE 4 OF 11 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE i............................

Faorievn'atoniun.

Flaw or Relevant Condition Found Examination Item During Scheduled ASME XI Category Number Number ~Item Description Flaw Characterization (IWA-3300)ExmntoorTs Examination or Test

[.....................

S..........

................... - (Yes or No)

Identified 17 previously recorded unacceptable B-A B 1.22 RPV Top Head Meridional Weld CH-MB indications. Resultes deemed acceptable per GE Yes

...... Reeppoo.trt...........................................t 10DDN-H92 (IA)

C iRelevant Condition - lugs are not same size as C-C C3.20 required by drawing. Accepted by Engineering Yes Evaluation.

D1 .20 33HB-H-148(IA) Relevant Condition - missing cotter pin. Repaired, Yes D-A Integral Attachment re-examination acceptable.

Drywell Relevant Condition - missing cotter pin on swing E-A E1.12 i N- I Equipment Hatch bolt at 8 o'clock position. Repaired, re-examination Yes Sacceptable.. ..... .. ... .

Relevant Condition - Pitting was inspected and E-C E4.11 Torus Wetted Pressure Boundary depths measured. Accepted by Engineering Yes Evaluation.

Relevant Condition - piece of moisture barrier No E-D E5.30 M Bar rier coating torn loose at azimuth 240. Repaired, re- (Found during another scheduled IWE Moisture Barrier ....................

.....exam...................

................ ............ exmiatoo a

... c..p.b..

acce.ptable.............. ...... ... . . . . . . . . . . . . . . . . . . . ....................................

E5.30 2-MBAR-INT Relevant Condition - coating is peeling from 050- Yes E-D Moisture Barrier 090 Azimuth. Repaired, re-examination acceptable.

iF-A 10DDN-H92 Relevant Condition - two loose bolts. Accepted by Spring Hanger Engineering Evaluation.

F-A (N-491-1) F 1.20 S.................................................................. M-1747-S-7 Relevant Condition - inadequate clearances Yes Rigid Restraint Accepted by Engineering Evaluation.

F-A .......... Relevant Condition - Load indicator is missing on 32GB-H28 (N-491-1) F1.30 the North Spring Can. As-found load was Yes Spring Hanger . . .acceptable.

Final U2-13-P3-2R17 OAR-i

ATTACHMENT 3B PAGE 5 OF 11 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw or Relevant Condition Found Examination Item During Scheduled ASME XI Category C~ategory .Number I Number Item Description Flaw Characterization (IWA-3300) E m ao orrTTest lxamination E

(Yes or No)

F-A 1GG-H711 F1Relevant Condtion - distance between pipe and

(- ...................... Fl ...30 .... . ........

9 ............................................... ...........

...................... support E isn...

n.......ri less

...then

.u required. Accepted

.v..u.t.o................................. ....... by

....................... Yes (N49 - 1) Guideierig~alain.-

F-A F1.30 1GG-S35 Relevant Condition -jam nut loose. Repaired, re- Yes (N-491 - 1) Snubber examination acceptable.

R-A RI.11 Core Spray System Pipe to Safe-End Weld 14- 1 Acceptable, previously identified, ID Geometry. Yes A-43 RI.ecIo High Pressure Coolant Injection System elbow 2 Acceptable ID Root Geometries. Yes R-A RIto pipe weld 23-2TE20-1 1.

Residual Heat Removal System elbow to pipe R-A R1.20 weld 10-2DA20-4 2 Acceptable Backing Ring ID Geometries. Yes Residual Heat Removal System elbow to pipe R-A R1.20 wedl2~72 iweld 10-2DA20-7 Acceptable Backing Ring ID Geometries. Yes R-A R1.20 i Residual Heat Removal System pipe to elbow 1 Acce Yes weld weld I2 10-2XBO20-3 I-2XAcc-eptable Backing Ring ID Geometry.Ye N/A N/A 6-inch Emergency Service Water Piping Pin-hole leak No F-A High Pressure Service Water Rigid Restraint 2- Not carring the design load due to gaps. Restraint (N-491-1) 32GB-$58, ASME Class 3 was shimmed and repaired. No F-A F High Pressure Service Water Rigid Restraint 2- Not caring the design load due to gaps. Restraint N (N-491-1) 32GB-H43, ASME Class 3 was shimmed and repaired.

................... O.A.........

O.A.......R.-.......................

Final U2-I3-P3-2R17 OAR-1

ATTACHMENT 3B PAGE 6 OF 11 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw or Relevant Condition Found Examinat ion iItem During Scheduled ASME XI Item Description Flaw Characterization (IWA-3300)

Categor Y Number Examination or Test (Yes or No)

F-A IFl3 High 32GB-S59, Pressure ASME Service Class Water 3 Rigid Restraint 2- Not shimmed was carring theand design repaired. load due to gaps. Restraint N (N-491-. ) 11.30 No F-A 32GB-H27, ASME Class 3 Rigid Restraint 2- was shimmed F.0 High Pressure Service Water Not earring theand repaired.

design load due to gaps. Restraint No (N-491-1)

SF1.30 No F-A High Pressure Service Water Rigid Restraint 2- Not carring the design load due to gaps. Restraint (N-491-1) 33HB-S63, ASME Class 3 was shimmed and repaired.

High Pressure Service Water Rigid Restraint 2- Not carring the design load due to gaps. Restraint F-A F1.30 33HB-S64, ASME Class 3 was shimmed and repaired. No (N-491-1)

N/A

~~6-inch Class 3, ASME Class 3 Emergency Service Water Piping, ASME Pi-leLa.

in-oeLekN P

N N/A High Pressure Service Water Check Valve 2 N/A Pin-hole Leak. No N/A S.................................................

N/A CHK-2-32-502C, ASME Class 3 Pin-hole Leak. No 6-inch Emergency Service Water Piping, ASME N/A Class 3, ASME Class 3 33 504Dlas -- 2-0C Emergency Service Water Hand Valve HV l N/A N/A Pin-Hole Leak. No N/A N/A Cls SECas3jPin-hole Leak. No 6-inch Emergency Service Water Piping, ASME N/A Class 3, ASME Class 3 SN/A Class N/A_6-inch3,Emergency ASME Class Service 3 Water Piping, ASMEPin-holeLeak._No __

Final U2-13-P3-2R17 OAR-1

ATTACHMENT 3B PAGE 7 OF 11 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE

.. . ....-- --F---ia---w--- t e-----evaa--

Flaw or Relevant Condition Found Examination Item . . .. .. . . . .. iDuring Scheduled ASME XI Examiatio .Ie Item Description Flaw Characterization (WA-o3300) D i Shud M.

Category Number Examination or Test

_ _ _(Yes or No) 6-inch Emergency Service Water Piping, ASME I Pin-hole Leak. No Class 3, ASME Class 3 Emergency Service Water Hand Valve HV N/A N/A I Minimum Wall Thickness Violation No

. . ......................... I.33-504C O......................

Final U2-I3-P3-2R17 OAR-1

TABLE 3 ATTACHMENT 3B ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 8 OF 11 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 5, 2006 TO NOVEMBER 4, 2008 (END OF 10 YEAR INTERVAL INCLUDES 2R17 REFUEL OUTAGE)

Denotes that use of Code Case N-416-2 was employed in completing the repair/ replacement activity SYSTEM 01: MAIN STEAM SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement AO-2-01A-080C Installed 5 new nuts and welded new stellite inbody seat No 10/2/2008 07-127, R1056916 Class 1 Replacement RV-2-02-071 B Installed a rebuilt safety relief valve No 9/24/2008 08-024, R0985094 Class 1 Replacement RV-2-02-071E Installed a rebuilt safety relief valve No 9/24/2008 08-025, R0985084 Class 1 Replacement RV-2-02-071F Installed a rebuilt safety relief valve No 9/24/2008 08-026, R0985095 Class 1 Replacement RV-2-02-071G Installed a rebuilt safety relief valve No 9/24/2008 08-027, R0985093 Class 1 Replacement RV-2-02-071 H Installed a rebuilt safety relief valve No 9/24/2008 08-028, R0985091 Class 1 Replacement RV-2-02-070B Installed a rebuilt safety relief valve No 9/25/2008 08-029, R0988101 Class 1 Replacement RV-2-02-071D Installed a rebuilt safety relief valve No 9/25/2008 08-130, R1051573 SYSTEM 03: CONTROL ROD DRIVE Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement CRD's 02-43, 06-43, 10-19, Exchanged CRD's with rebuilt CRD's No 9/23/2008 07-135, R1055889 22-31, 22-59, 26-59, 30-03, 30-27, 30-31, 30-39, 30-55, 34-03, 34-07, 34-39, 38-31, 42-59, 46-55, 54-19 Class 1 Repair CV-2-03A-13127BQ Weld repaired indications in valve tail piece section No 9/26/2008 08-138, R1086467

TABLE 3 ATTACHMENT 3B ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 9 OF 11 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 5, 2006 TO NOVEMBER 4,2008 (END OF 10 YEAR INTERVAL INCLUDES 2R17 REFUEL OUTAGE)

Denotes that use of Code Case N-416-2 was employed in completing the repair / replacement activity SYSTEM 10: RESIDUAL HEAT REMOVAL Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement RV-2-10-181 C Installed new RHR Hx. 2CE024 Shell Side relief valve No 2/20/2007 06-209, R0863938 Class 2 Replacement PB-2-M-HX-2CE024 New 2CE024 Hx Upper Head Channel Cover Studs/Nuts No 2/20/2007 06-211, C0219541 Class 2 Replacement RV-2-10-181 D Installed new RHR Hx. 2DE024 Shell Side relief valve No 1/28/2008 07-035, R0864255 Class 2 Replacement PB-2-10-2DE024 Installed new RHR Hx. 2DE024 Floating Head No 2/1/2008 07-108, C0221745 Class 2 Replacement RV-2-10-181B Installed new RHR Hx. 2BE024 Shell Side relief valve No 4/14/2008 08-002, R0900643 Class 1 Replacement AO-2-10-046A RHR Loop "A"Check Valve, new weld plugment No 9/30/2008 08-084, C0223978

- Class 3 Replacement MO-2-10-089A Installed new RHR Hx 2AE024 HPSW Outlet Valve No 7/11/2008 08-095, C0212558 SYSTEM 11: STANDBY LIQUID CONTROL SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement RV-2-11-39B Installed new relief valve No 12/13/2006 06-212, C0219567 Class 2 Replacement RV-2-11-39A Installed new relief valve No 12/14/2006 06-213, C0219573 Class 2 Replacement RV-2-11-39A Installed new relief valve No 9/22/2008 07-105, R1047769 Class 2 Replacement RV-2-11-39B Installed new relief valve No 9/22/2008 07-106, R1047770

TABLE 3 ATTACHMENT 3B ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 10 OF 11 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 5, 2006 TO NOVEMBER 4, 2008 (END OF 10 YEAR INTERVAL INCLUDES 2R17 REFUEL OUTAGE)

Denotes that use of Code Case N-416-2 was employed in completing the repair I replacement activity SYSTEM 23: HIGH PRESSURE COOLANT INJECTION SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement VRV-2-23C-140A Installed new vacuum relief valve. No 9/20/2008 02-007, R0783924 Class 2 Replacement VRV-2-23C-140B Installed new vacuum relief valve. No 9/20/2008 02-007, R0783924 Class 2 Replacement VRV-2-23C-140C Installed new vacuum relief valve. No 9/20/2008 02-007, R0783924 Class 2 Replacement VRV-2-23C-140D Installed new vacuum relief valve. No 9/20/2008 02-007, R0783924

- Class M Replacement MO-2-23-031 Replaced leak between MO-2-23-031 and nozzle N-233 No 11/16/2006 06-200, C0219131 Class 2 Replacement MO-2-23-014 Installed new valve yoke studs No 9/23/2008 08-030, R1029543 SYSTEM 32: HIGH PRESSURE SERVICE WATER SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 3 Replacement RV-2-32-180D Installed new RHR Hx. 2DE024 Tube Side Relief Valve No 1/29/2008 07-033, R0881264 Class 3 Replacement RV-2-32-180B Installed new RHR Hx. 2BE024 Tube Side Relief Valve No 4/14/2008 08-003, R0862930 Class 3 Replacement 32GB-S59, 32GB-H27 Install shims on 32GB-S59 & H27 HPSW rigid restraint No 7/2/2008 08-096, C0224873 Class 3 Replacement 32GB-S58, 32GB-H43 Install shims on 32GB-S58 & H43 HPSW rigid restraint No 7/1/2008 08-097, C0224811 Class 3 Replacement 2-32GB-S60 Re-install I-beam/shims on 32GB-S60 HPSW rigid restrain No 7/11/2008 08-122, C0212558

TABLE 3 ATTACHMENT 3B ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 11 OF 11 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 OCTOBER 5, 2006 TO NOVEMBER 4, 2008 (END OF 10 YEAR INTERVAL INCLUDES 2R17 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-2 was employed in completing the repair/ replacement activity SYSTEM 33: EMERGENCY SERVICE WATER Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Compiete R&R Plan # and W/O #

Class 3 Replacement HV-0-33-510, HV-0-33-11431A Installed 16" pipe spool & 2" pipe/valve hot tap connection No 1/23/2008 07-088, C0220220 Class 3 Replacement HV-0-33-504D Replaced leak in 6" pipe downstream of HV-0-33-504D No 7/22/2008 08-123, C0225717 Class 3 Replacement HV-0-33-504A Replaced leak in 6" pipe downstream of HV-0-33-504A No 8/1/2008 08-124, C0225613 Class 3 Replacement HV-0-33-504C Replaced low wall in 6" pipe downstream of HV-0-33-504C No 8/27/2008 08-125, C0225784 SYSTEM 65A: HYDRAULIC SNUBBERS Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement SS-3-D Installed new hydraulic snubber load pins No 10/1/2008 08-076, C0224178 Class 1 Replacement 12-DCN-S-5 Installed new hydraulic snubber No 9/25/2008 08-136, C0226356 SYSTEM 65B: MECHANICAL SNUBBERS Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement 10-GB-S-75 Installed new mechanical snubber No 9/26/2008 08-038, C0223573 Class 2 Replacement 1-GG-S-101-B Installed new mechanical snubber No 9/20/2008 08-047, C0223839 Class 2 Replacement 1-GG-S-102-A Installed new mechanical snubber No 9/21/2008 08-050, C0223842

Attachment 4 Peach Bottom Atomic Power Station Unit 3 Owner Activity Report (OAR-i) for Refueling Outage 3R14 Third 10-Year ISI Interval, Second Period

ATTACHMENT 4 PAGE 1 OF 8 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: 3R14 Owner: EXELON NUCLEAR 200 Exelon Way Kennett Square, PA 19348 Plant: Peach Bottom Atomic Power Station 1848 Lay Road Delta, PA 17314 Unit No.: 3 Commercial Service Date: December 23, 1974 Refueling Outage No.: 14 Current Inspection Interval: 3 rd Current Inspection Period: 2nd Edition and Addenda of Section XI applicable to the Inspection Plan: 1989 Edition & 1992 Edition including 1992 Addenda Date and Revision of Inspection Plan: December 20, 2002, Revision 0 Edition and Addenda of Section XI applicable to repairs and replacements: 1989 Edition and Code Case N-416-1 CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report for the period January 1, 2002 to October 12, 2003 conform to the requirements of Section XI.

Signed: Date: 0) 00t?

CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the Commonwealth of Pennsylvania and employed by Hartford Steam Boiler Inspection &

Insurance Company of Connecticut, of Hartford, Connecticut, have inspected the components described in the Owner's Data Report during the period January 1, 2002 to October 12, 2003 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 examinations, tests, repairs, replacements, evaluations, and corrective measures 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 loss of any kind arising from or connected with this inspection.

Date:

Inspector's Signature:

Commissions: t73 W A, v.

National Board, State, Province 9 No.

Peach Bottom Atomic Power Station, Unit 3 ATTACHMENT 4 Third Interval, Second Period OAR-1 PAGE 2 OF 9 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Examinations Examinations Examinations Examination Required For The Credited For Credited N Credited N Remarks Category Interval The For The 2nd thru 2nd Period 2nd Priod Period (3R14) (3R14) of The Interval B-A 31 9.0 29.0 67.7 RPV Circumferential shell weld exempted per approved Relief request RR-41 3.1 70.5 Case N-598, Alternative Requirements to Required Percentages of Examinations, Section Xl, Division 1 per approved Relief Request RR-33 B-E 62 62.0 100.0 100.0 B-E examinations completed during RPV Hydro performed in second period.

B-G-1 109 17.0 15.6 57.8 Code Case N-598 per approved Relief Request RR-33 B-G-2 116 24.0 20.7 57.8 Code Case N-598 per approved Relief Request RR-33

1) Code Case N-598 per approved Relief Request RR-33 B-K 18 6.0 33.3 66.7 2) Use of ASME CC N-509, Alternative Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded Attachments Section Xl, Division 1, included Category B-H as B-K B-L-2 2 1.0 50.0 50.0 B-M-2 11 3.0 27.3 45.5 B-N-1 3 1.0 33.3 66.7 B-N-2 49 12.0 24.5 59.2 B-P 6 1.0 16.7 50.0 C-A 2 0.0 0.0 50.0 Code Case N-598 per approved Relief Request RR-33 C-B 8 0.0 0.0 12.5 C-C 17 5.0 29.4 64.7 Code Case N-598 per approved Relief Request RR-33 C-H 51 15.0 29.4 60.8 RPV flange leakoff drain piping test not completed for 2nd period.

D-A 18 0.0 0.0 0.0 Code Case N-598 per approved Relief Request RR-33 D-B 3 1.0 33.3 66.7 Final Unit 3 OAR-1 KAH Verification Markup

Peach Bottom Atomic Power Station, Unit 3 ATTACHMENT 4 Third Interval, Second Period OAR-1 PAGE 3 OF 9 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Examination Total Examinations Examinations Examinations Credited (%) Examinations Ceie %

Cation Required For The Credited For Credited N Remarks Category Interval The 2nd Period For The 2nd thru 2nd Period 2nd Priod Period (3R14) (3R14) of The Interval E-A 68 17.0 25.0 5An additional GV of Containment was performed in this interval for the ILRT requirements E-C 3 2.0 66.7 66.7 Alternative examination program per approved Request for Alternative CRR-1 1 E-D 63 0.0 0.0 0.0 E-G 76 0.0 0.0 0.0 E-P 1 0.0 0.0 0.0 F-A 158 39.0 24.7 66.5 Code Case N-598 per approved Relief Request RR-33 R-A 139 24.0 17.3 63.3 Implemented RI-ISI starting 2nd Period, replacing Categories B-F, B-J, and C-F R2.

Final Unit 3 OAR-1 KAH Verification Markup

ATTACHMENT 4 PAGE 4 OF 9 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw or Relevant Condition Found Examination Item IteimnDescription Flaw Characterization (IWA-3300) During Scheduled ASME XI Category Number Examination or Test (Yes or No)

S...................................................... ..... .......... ...................................

Relevant Condition - Pitting was inspected and E-C E4.11 Torus Wetted Pres sure Boundary depths measured. Accepted by Engineering Yes Evaluation.

F-A F1.10 12DCN-H150 .. ...........

............. Relevant Condition - Spring setting > 10% from (N-491-1) Spring Hanger Yes F-A 1ODDN-H66A design. Acceptable per engineering evaluation.

F1.20 Spring Hanger (N-491-1)

S..........................................................

1OGB-S56 Relevant Condition - 5 loose bolts on both anchorYe F-A F1.20 t reworked, expanded sample,

Yes Rigid Restraint plates. Unacceptable, Relevant Condition - Spring setting > 10% from

!F-A 1DB-H32 design. Acceptable per engineering evaluation.

F1.20 pi Haanger Spring Hne (N-49l-1)

Relevant Condition - Spring setting > 10% from Yes F-A 1DB-H34 design. Acceptable per engineering evaluation.

F1.20 (N-491-1) Spring Hanger F-A IDB-H43 Relevant Condition - Spring setting > 10% from (N-491 -l1) Fl0 Spring Hanger design. Acceptable per engineering evaluation.Ye F-A F1.20 DB-H44 Relevant Condition- Spring setting>10% fromYes (N-49 1-1) Spring Hanger design. Acceptable per engineering evaluation. Y

! Fl 20 .i "* Yes F-A 1DB-H46 Relevant Condition - Spring setting > 10% from . Y (N-491-1) Spring Hanger design. Acceptable per engineering evaluation.

F-A 23DBN-H40 Relevant Condition - Spring setting > 10% from (N-491-1) Fl.20 Spring Hanger design. Acceptable per engineering evaluation. Yes I.. .......... .........................................

Final U3-13-P2-3R14 OAR-1

ATTACHMENT 4 PAGE 5 OF 9 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw or Relevant Condition Found Examination Item During Scheduled ASME XI Item Description Flaw Characterization (IWA-3300) Examination or Test Category Number

.___(Yes or No)

F-A F1.20 I1GG-H290 Relevant Condition ..- Sliding . . ....* (UCAR)*.. plate , . iY es (N-491-1) Spring Hanger cnlppea. Acceptable per engineering evaluation.

F-A F1.30 33HB-S121 Relevant Condition - No clearance on south side.

Yes (N-491-1) Rigid Restraint Accepted per engineering evaluation.

NA........................................ .............................

N/A N/A Relevant Condition -Measured wall thickness less No High Pressure Service Water system piping than (Min. Wall) acceptance criteria.

Relevant Condition -Measured wall thickness less No N~/A N/A High Pressure Service Water system piping than (Min. Wall) acceptance criteria.

.i...... ......................... . ...... . --------------

N /A Relevant Condition -Measured wall thickness less No N/A High Pressure Service Water system piping than (Min. Wall) acceptance criteria.

Final U3-13-P2-3R14 OAR-1

TABLE 3 ATTACHMENT 4 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 6 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 JANUARY 1, 2002 TO OCTOBER 12, 2003 (INCLUDES 3R14 REFUEL OUTAGE)

Denotes that use of Code Case N-416-1 was employed in completing the repair/ replacement activity SYSTEM 01: MAIN STEAM SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement RV-3-02-071 L Installed a rebuilt safety relief valve No 10/7/2003 02-186, R0821531 Class 1 Replacement RV-3-02-071 K Installed a rebuilt safety relief valve No 10/7/2003 02-187, R0821530 Class 1 Replacement RV-3-02-071J Installed a rebuilt safety relief valve No 10/7/2003 02-188, R0822430 Class 1 Replacement RV-3-02-071 F Installed a rebuilt safety relief valve No 10/7/2003 02-189, R0822431 Class 1 Replacement RV-3-02-071 B Installed a rebuilt safety relief valve No 10/7/2003 02-190, R0822428 Class 1 Replacement RV-3-02-070A Installed a rebuilt safety relief valve No 10/7/2003 02-191, R0822429 Class 1 Replacement RV-3-02-071 C Installed a rebuilt safety relief valve No 10/7/2003 02-209, R0747164 Class 1 Replacement AO-3-01A-086D Installed 1 new bonnet stud and 12 new bonnet nuts Yes 10/2/2003 03-019, R0888761 Class 1 Replacement RV-3-02-071 D Installed a rebuilt safety relief valve No 10/7/2003 03-090, C0206707 Class 1 Replacement RV-3-02-071 G Installed a rebuilt safety relief valve No 10/7/2003 03-092, C0206710 SYSTEM 02: REACTOR AND RECIRCULATION Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement PB-3-02A-3AP034 Installed new pump cover and internals No 10/9/2003 03-068, C0202973

TABLE 3 ATTACHMENT 4 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 7 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 JANUARY 1, 2002 TO OCTOBER 12, 2003 (INCLUDES 3R14 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair/ replacement activity SYSTEM 03: CONTROL ROD DRIVE Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement CRD's 10-31, 18-15, 22-47, Exchanged CRD's with rebuilt CRD's during 3R14 outage No 10/8/2003 03-036, R0882893 26-27, 26-31, 34-23, 34-27, 34-39, 38-19, 50-39, 54-19, 58-23, 58-31 SYSTEM 10: RESIDUAL HEAT REMOVAL Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) DescriDtion Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement RV-3-10-181 A Installed new RHR Hx. 3AE024 Shell Side relief valve No 11/12/2002 02-168, R0658138 Class 2 Replacement RV-3-10-181 D Installed new RHR Hx. 3DE024 Shell Side relief valve No 2/2/2003 03-004, R0716858

- Class 3 Replacement MO-3-10-089D Installed new RHR Hx 3DE024 HPSW Outlet Valve No 6/19/2003 03-007, C0199233 Class 2 Repair PB-3-10-3DE024 Repaired seal weld betwn floating head & floating tubesht No 7/9/2003 03-062, C0202412 Class 2 Replacement 2" RHR Stayfull Piping Replaced piping interferring with recirc motor replacement No 6/23/2003 03-064, C0203872

TABLE 3 ATTACHMENT 4 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 8 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 JANUARY 1, 2002 TO OCTOBER 12, 2003 (INCLUDES 3R14 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair / replacement activity SYSTEM 11: STANDBY LIQUID CONTROL SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement RV-3-11-39A Installed new relief valve No 9/26/2003 02-179, R0880506 Class 2 Replacement RV-3-11-39B Installed new relief valve No 9/26/2003 02-180, R0881500 SYSTEM 13: REACTOR CORE ISOLATION COOLING SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement VRV-3-13C-139A Installed new vacuum relief valve No 8/14/2002 02-138, R0755065 Class 2 Replacement VRV-3-13C-139B Installed new vacuum relief valve No 8/14/2002 02-139, R0755065 Class 2 Replacement VRV-3-13C-139C Installed new vacuum relief valve No 8/14/2002 02-140, R0755065 Class 2 Replacement VRV-3-13C-139D Installed new vacuum relief valve No 8/14/2002 02-141, R0755065 SYSTEM 14: CORE SPRAY COOLING SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component l.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- ' Class 2 Replacement RV-3-14-020B Installed new relief valve No 5/19/2003 02-019, R0696586 Class 2 Replacement RV-3-14-020A Installed new relief valve No 7/15/2003 03-015, R0702441 Class 2 Replacement 14GB-H43 Installed missing center bolt set on pipe clamp assembly Yes 9/27/2003 03-094, C0206788

TABLE 3 ATTACHMENT 4 ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 9 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 JANUARY 1, 2002 TO OCTOBER 12, 2003 (INCLUDES 3R14 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-1 was employed in completing the repair/ replacement activity SYSTEM 23: HIGH PRESSURE COOLANT INJECTION SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement AO-3-23-018 Installed 3 bearing cover studs (incidental replacement) No 10/3/2003 03-003, R0874645 SYSTEM 32: HIGH PRESSURE SERVICE WATER SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 3 Replacement PB-3-32-RO-3789D Installed blank flange in RO-3789D (new press. boundary) No 1/29/2003 03-037, C0202412 Class 3 Replacement RV-3-32-180B Installed new RHR Hx. 3BE024 Tube Side relief valve No 7/11/2003 99-142, R0696587 SYSTEM 65A: HYDRAULIC SNUBBERS Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement 1-DB-S-15-A Installed new snubber and load pin bushings Yes 10/6/2003 03-009, R0650212 Class 3 Replacement 1-GG-S-53 Installed new snubber load pins No 9/24/2003 03-026, C0203431

Attachment 5A Peach Bottom Atomic Power Station Unit 3 Owner Activity Report (OAR-i) for Refueling Outage 3R15 Third 10-Year ISI Interval, Third Period

ATTACHMENT 5A PAGE 1 OF 9 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: 3R15 Owner: EXELON NUCLEAR 200 Exelon Way Kennett Square, PA 19348 Plant: Peach Bottom Atomic Power Station 1848 Lay Road Delta, PA 17314 Unit No.: 3 Commercial Service Date: December 23, 1974 Refueling Outages No.: 15 Current Inspection Interval: 3rd Current Inspection Period: 3 rd Edition and Addenda of Section XI applicable to the Inspection Plan: 1989 Edition & 1992 Edition including 1992 Addenda Date and Revision of Inspection Plan: September 12, 2005, Revision 1 Edition and Addenda of Section XI applicable to repairs and replacements: 1989 Edition and Code Case N-416-1 CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report for the period October 13, 2003 to October 16, 2005 conform to the requirements of Section XI.

Signed: 41I Date: L-7l CERTIFICATE OF INSERVICE INSPECTION 1, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the Commonwealth of Pennsylvania and employed by Hartford Steam Boiler Inspection &

Insurance Company of Connecticut, of Hartford, Connecticut, have inspected the components described in the Owner's Data Report during the period October 13, 2003 to October 16, 2005 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 examinations, tests, repairs, replacements, evaluations, and corrective measures 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 loss of any kind arising from or connected with this inspection.

Date: tI 2So -z>

Inspector's Signature:

Commissions:0 B 2- 2, A .(

National Board, State, Province A Nd.

Peach Bottom Atomic Power Station, Unit 3 ATTACHMENT 5A Third Interval, Third Period OAR Refueling Outage 3R15 PAGE 2 OF 9 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Examination Total Examinations Examinations Examinations Examinations Category Required For The Credited For Credited (%) Credited (%) Remarks Interval Credit d For The 3rd thru 3rd Period IntervalThe 3rd Period Period of The Interval B-A 31 0.0 0.0 67.7 RPV Circumferential shell weld exempted per approved Relief request RR-41 Case N-598, Alternative Requirements to Required Percentages of B-D 61 6.0 9.8 80.3 Examinations, Section Xl, Division 1 per approved Relief Request RR-33 B-E 62 0.0 0.0 100.0 B-E examinations completed during RPV Hydro performed in P3R14 B-G-1 109 46.0 42.2 100.0 Code Case N-598 per approved Relief Request RR-33 B-G-2 116 30.0 25.9 83.6 Code Case N-598 per approved Relief Request RR-33

1) Code Case N-598 per approved Relief Request RR-33 B-K 18 2.0 11.1 77.8 2) Use of ASME CC N-509, Alternative Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded AttachmentsSection XI, Division 1, included Category B-H as B-K B-L-2 2 0.0 0.0 50.0 B-M-2 11 5.0 45.5 90.9 B-N-1 3 0.0 0.0 66.7 B-N-2 49 13.0 26.5 85.7 B-P 6 1.0 16.7 66.7 C-A 2 1.0 50.0 100.0 Code Case N-598 per approved Relief Request RR-33 C-B 8 1.0 12.5 25.0 C-C 17 6.0 35.3 100.0 Code Case N-598 per approved Relief Request RR-33 C-H 51 11.0 21.6 82.4 RPV flange leakoff drain piping test not completed for 2nd period.

D-A 18 5.0 27.8 27.8 Code Case N-598 per approved Relief Request RR-33 D-B 3 0.0 0.0 66.7 VT-3 of the submerged portions of the Torus and Vent System have been extended 1 year. Will be performed during first outage in 4th E-A 68 11.0 16.2 66.2 interval per Interval per IWA-2430(d). An additional GV of Containment was performed in this interval for the ILRT

_requirements Final Unit 3 OAR-1 3R15 only

Peach Bottom Atomic Power Station, Unit 3 ATTACHMENT 5A Third Interval, Third Period OAR Refueling Outage 3R15 PAGE 3 OF 9 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Examination Total Examinations Examinations Examinations Examinations Category Required For The Credited For Credited (%) Credited (%) Remarks Interval Credit d For The 3rd thru 3rd Period IntervalThe 3rd Period Period of The Interval E-C 3 0.0 0.0 66.7 Alternative examination program per approved Request for Alternative CRR-1 1 E-D 63 63.0 100.0 100.0 10CFR50 Appendix J examination of seals and gaskets during P3R1 5 per approved Request for Alternative CRR-01 E-G 76 76.0 100.0 100.0 10CFR50 Appendix J and Code Category E-A examination during P3R1 5 per approved Request for Alternative CRR-07 E-P 1 1.0 100.0 100.0 During P3R15 in accordance with 10CFR50 Appendix J Test Program and Schedule F-A 158 36.0 22.8 89.2 Code Case N-598 per approved Relief Request RR-33 R-A 139 29.0 20.9 84.2 Implemented RI-ISI starting 2nd Period, replacing Categories B-F, B-I_ _J, and C-F-2.

Final Unit 3 OAR-1 3R15 only

ATTACHMENT 5A PAGE 4 OF 9 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination Item Flaw or Relevant Condition Found During Item Description Flaw Characterization (IWA-3300)

Scheduled ASME XI Examination or Test Category Number (Yes or No) 6DDN7L-H6 .Relevant Condition - loose jam nut; cold setting out F- i~P S Hn rof tolerance. re-examined afterear , acetbe YesYes~~ ................ __

~~

Relevant Condition - broken tack welds on bolt IOHB-S6 head and nut. Load pin on clamp is out of vertical F-A ....

Fl.. ........

.20 ...[1Restraint.. ......

nt......

I.........................................

.al.n alignment. t ........ ..........

.......................................... _NNo,o............d.....s expanded samle al.e............... .......... .............

IOHB-S9 Relevant Condition - no thread engagement in site F-A................... ............... FF 1.20 2 0...

.. ........ e._ t a n....................................................

Restraint ...............

.......... . .................................... holes.

......................... le s-.A..ept Accepted e as-is..i bby .evaluation.

.s..y a..... o............................................

t....n ........

...... .. No, e.xpanded sampe e..s ..

.Y ...................................................

10GB-S62A Relevant Condition - anchor plate bolt was missing.

F-A

. Fl.20

......... Rigid

..................... 0 'B Restraint f g ... ............. . . ..... . . . ..- ... ......... ------- 1 Accepted cby-n-d

....--- ~ l evaluation. n o f.et to e a ...

.u Yes 1OGB-H69 Relevant Condition - cold setting out of tolerance.

F-A F1.20 1 Spring Hanger - Accepted by evaluation. Yes 10MO-$79 F-A F..20 . Rigid Restraint .. Relevant Condition - missing cotter pin 1OGB-S46 Relevant Condition - missing jam nut, spherical i..F.-A ... .............................

.F L 1.20. ........

1Rigid .!... ...... ...........

Restraint . ....

........... a_...

bearing ___outu oof.f.ppaddle.

..a.... ........

10GB-S45 Relevant Condition - missing jam nut, spherical No epanded sam~ple.

F-A :F1.20 Rigid Restraint bearigout of paddle.

1GG-H313 Relevant Condition - loose jam nuts on pipe clamp F-A F1.30_ Spring Hanger end. _

Yes__

1GG-H299 Relevant Condition - misalignment of ucar plate; Yes F-A i...........................

.F F1.30 .......1................

Spring ..Sr . r...................

. Hanger

.n..

..... 1/3

. of ucar ..ua

.. lat. w plate ....

.g s ................

as...

wasmissmn s .

High Pressure Service Water system piping (IR 199832) Relevant Condition -Measured wall thickness less N/A N/A than minimum wall acceptance criteria. No Final U3-13-P3-3R15 OAR-i

ATTACHMENT 5A PAGE 5 OF 9 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE

.......................... i.. ........

i.......................................... ..... ............

Exmo tFlaw or Relevant Condition Found During n umber Item Description Flaw Characterization (IWA-3300) Scheduled ASME XI Examination or Test Category I..........

..Number

........... .Ye

.No........ -

High Pressure Service Water system piping Relevant Condition - Meausred wall thickness less N/A................................

N_A ..N N/A / ................ IR .2.93.0 83) ....... .....

.....(,,.

(R238)than ........ ... ..... .. . ......

..................................................... n..i.'.i_.u..........e mn umwall acceptance criteria. Noo ........ ...... ..... ......

.......................... N .~- . ...... ... . .. ... ........ ..............................

.an..e....ite High Pressure Service Water system piping Relevant Condition - Measured wall thickness less A..........

....N ..........................

N .A.-....

...IR .2267973).7 3)........ ...... . .... ......

............ ... th a mn umwall wal ac e ta c criteria. ra .. . . ...._ Noo ..... .. . .mn_ ....rt . .... .........

N/A N/A 1(JR than acceptance I OGB-S44 Snubber Relevant Condition - 10 of 18 bolts found loose on F-A F1.20 .. (JR 332980) snubber mounting plates . ... No ___-

i 23DDN-S300A pipe support Relevant Condition - lower anchor bolts on HPCI F-A...............................

... F1.20

..... ((IR 332355)---pe .............................

.................... ..... ........ ... .......... ............. support

................. -P ...P ........... are................................................................

partially...pulled

.. . ................................. out of wall. . ...................

............. ........................ No.. .... .

S10GB-H87 Relevant Condition - Loose nut found on spring can F-A Fl .20 Spring Hanger base plate. No -

i23DDN-S22A I Relevant Condition - Support was found 3/4" out of -- -

F-A F1.20 1 Rigid Restraint alignment and one loose bolt on base plate. No 23DDN-S23A Relevant Condition - Support was found out of F-A F1.20 - Rigid Restraint -alignment. No 23DDN-S31 Relevant Condition - Support was found out of F-A F1.20 1 Rigid Restraint I algnment. No 23DDN-S24 Relevant Condition - Support was found out of F-A F ............

..... a iF1.20

........... Rgid . .Restraint

....-. A.R.............................

I........ ... ..... . ............................. .........

..... .. . . . . .... alignmet__ . .

. .. . ... .. .. ... . ... ........ No . ... . . . .. .. ........ ... .... .. ....

Final U3-I3-P3-3R15 0AR-1

TABLE 3 ATTACHMENT 5A ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 6 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 13, 2003 TO OCTOBER 16, 2005 (END OF 3R15 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-2 was employed in completing the repair / replacement activity SYSTEM 01: MAIN STEAM SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement AO-3-01A-080A Installed new bonnet nuts as incidental replacement No 10/3/2005 05-063, R0948673 Class 1 Replacement AO-3-01A-080D Installed new bonnet nuts as incidental replacement No 10/3/2005 05-066, R0948673 Class 1 Replacement RV-3-02-071 A Installed a rebuilt safety relief valve No 9/25/2005 05-067, R0892990 Class 1 Replacement RV-3-02-071 D Installed a rebuilt safety relief valve No 9/25/2005 05-068, R0946312 Class 1 Replacement RV-3-02-071 E Installed a rebuilt safety relief valve No 9/24/2005 05-070, R0884101 Class 1 Replacement RV-3-02-070B Installed a rebuilt safety relief valve No 9/24/2005 05-071, R0885698 Class 1 Replacement RV-3-02-071 H Installed a rebuilt safety relief valve No 9/24/2005 05-072, R0888173 Class 1 Replacement RV-3-02-071 B Installed a rebuilt safety relief valve No 9/25/2005 05-118, R0949234 SYSTEM 03: CONTROL ROD DRIVE Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement CRD's 10-11, 10-15, 10-43, Exchanged CRD's with rebuilt CRD's No 10/7/2005 05-017, R0960523 14-27, 14-35, 14-39, 18-27, 18-51, 26-07, 26-19, 26-23, 30-43, 30-55, 38-23, 42-03, 42-35, 46-19, 46-23, 50-35

- Class 2 Replacement SVD cleanout pipe caps Remove/install pipe caps to flush scram disch. header No 10/1/2005 05-085, R0967521

TABLE 3 ATTACHMENT 5A ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 7 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 13, 2003 TO OCTOBER 16, 2005 (END OF 3R15 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-2 was employed in completing the repair / replacement activity SYSTEM 06: FEEDWATER Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement CHK-3-06-096A Installed new valve bonnet No 10/1/2005 02-184, R0873962 Class 1 Repair MO-3-06-038B Machined bonnet stem bore dia. per engineering analysis No 10/4/2005 05-123, R0744837 SYSTEM 10: RESIDUAL HEAT REMOVAL Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement RV-3-10-181 B Installed new RHR Hx. 3BE024 Shell Side relief valve No 1/29/2004 03-111, R0717546

- ' Class 3 Replacement MO-3-10-089C Installed new RHR Hx 3CE024 HPSW Outlet Valve No 10/5/2005 04-170, C0210627 Class 3 Replacement MO-3-10-089B Installed new RHR Hx 3BE024 HPSW Outlet Valve No 9/26/2005 05-049, C0211160 Class 2 Replacement 10GB-S46 Installed new restraint rod end and jam nuts No 10/9/2005 05-132, C0215324 Class 2 Replacement 10GB-$45 Installed new restraint eye rod end and jam nuts No 10/9/2005 05-136, C0215330 SYSTEM 11: STANDBY LIQUID CONTROL SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement RV-3-11-39B Installed new relief valve No 9/29/2005 05-031, R0950653 Class 2 Replacement RV-3-11-39A Installed new relief valve No 9/29/2005 05-032, R0950662

TABLE 3 ATTACHMENT 5A ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 8 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 13, 2003 TO OCTOBER 16, 2005 (END OF 3R15 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-2 was employed in completing the repair / replacement activity SYSTEM 13: REACTOR CORE ISOLATION COOLING SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- Class 2 Replacement CHK-3-13C-1 33 Installed new check valve No 4/21/2004 02-130, C0201541 SYSTEM 14: CORE SPRAY COOLING SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement CHK-3-14-10C Installed new check valve bonnet bolts No 7/20/2005 03-080, R0925152 Class 2 Replacement CHK-3-14-10B Installed new check valve bonnet bolts No 5/18/2004 04-098, R0937004 Class 2 Replacement RO-3-14-037C Installed new studs and nuts for thread engagement issue No 7/13/2004 04-146, C0210414 Class 2 Replacement CHK-3-14-10D Installed new check valve bonnet bolts No 5/25/2005 05-012, R0925143 SYSTEM 23: HIGH PRESSURE COOLANT INJECTION SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Descriotion Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement 3-23MO-H47 Modified and installed new operator support bracket No 5/5/2004 04-106, R0741407 Class 2 Repair 23DDN-S46 Repaired cracked weld on rigid restraint base plate No 5/6/2005 05-109, C0213715

- Class 2 Replacement MO-3-23-014 Installed new valve No 9/27/2005 05-034, C0212707 Class 2 Replacement PSD-3-23-006 Replace rupture disc bolting, incidental replacement No 9/22/2005 05-077, R0864706 Class 2 Replacement HV-3-23C-31125 Installed a 1" pipe support off of a 2" header No 4/22/2005 05-106, C0213460 Class 2 Replacement HV-3-23C-31158 Installed new valve bonnet No 9/29/2005 05-124, C0215211 Class 2 Replacement 3-23DBN-S53 Installed shims to pipe clamp on rigid restraint No 10/4/2005 05-125, C0212707

TABLE 3 ATTACHMENT 5A ABSTRACT OF ASME REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES PAGE 9 OF 9 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 13, 2003 TO OCTOBER 16, 2005 (END OF 3R15 REFUEL OUTAGE)

- Denotes that use of Code Case N-416-2 was employed in completing the repair/ replacement activity SYSTEM 32: HIGH PRESSURE SERVICE WATER SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- Class 3 Replacement RO-3-32-3789B Installed new outlet restricting orifice and associated piping No 6/12/2004 04-110, C0209102 Class 3 Replacement RO-3-32-3789D Installed new outlet restricting orifice and associated piping No 7/1/2004 04-111, C0208948 SYSTEM 33: EMERGENCY SERVICE WATER (ESW)

Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

- Class 3 Replacement HV-3-33-518 Installed new valve No 3/1/2006 03-067, C0204514 SYSTEM 65A: HYDRAULIC SNUBBERS Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement SS-B-4 Installed new snubber No 9/24/2005 02-213, R0474912 Class 1 Replacement SS-C-4 Installed new snubber No 9/24/2005 02-214, R0474913 Class 1 Replacement SS-D-3 Installed new snubber No 9/27/2005 02-216, R0474915 Class 3 Replacement I-GG-S-13 Installed new snubber No 9/27/2005 05-052, R0474916 Class 3 Replacement 1-GG-S-31 Installed new snubber No 9/27/2005 05-053, R0474918 Class 3 Replacement 1-GG-S-53 Installed new snubber No 9/28/2005 05-054, R0474919 Class 3 Replacement 1-GG-S-65 Installed new snubber No 9/29/2005 05-055, R0474920 Class 3 Replacement 1-GG-S-30 Installed new snubber rod eye extension No 10/6/2005 05-129, C0215274

Attachment 5B Peach Bottom Atomic Power Station Unit 3 Owner Activity Report (OAR-i) for Refueling Outage 3R16 Third 10-Year ISI Interval, Third Period.

ATTACHMENT 5B PAGE 1 OF 10 FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number: 3R16 Owner: EXELON NUCLEAR 200 Exelon Way Kennett Square, PA 19348 Plant: Peach Bottom Atomic Power Station 1848 Lay Road Delta, PA 17314 Unit No.: 3 Commercial Service Date: December 23, 1974 Refueling Outages No.: 16 Current Inspection Interval: 3 rd Current Inspection Period: 3 rd Edition and Addenda of Section XI applicable to the Inspection Plan: 1989 Edition & 1992 Edition including 1992 Addenda Date and Revision of Inspection Plan: September 18, 2007, Revision 2 Edition and Addenda of Section XI applicable to repairs and replacements: 1989 Edition and Code Case N-416-1 CERTIFICATE OF CONFORMANCE I certify that the statements made in this Owner's Activity Report are correct, and that the examinations, tests, repairs, replacements, evaluations, and corrective measures represented by this report for the period October 17, 2005 to November 4, 2008 conform to the requirements of Section XI.

Signed: _, , *,? . Date: 01'"Z -ZOOq CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the Commonwealth of Pennsylvania and employed by Hartford Steam Boiler Inspection &

Insurance Company of Connecticut, of Hartford, Connecticut, have inspected the components described in the Owner's Data Report during the period October 17, 2005 to November 4, 2008 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 examinations, tests, repairs, replacements, evaluations, and corrective measures 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 loss of any kind arising from or connected with this inspection.

Date: I I. aozC Inspector's Signature:

Commissions: Q) \_-u-ý 4 2 ,A t.d -

National Board, State, Province & 1klo. I

Peach Bottom Atomic Power Station, Unit 3 ATTACHMENT 5B Third Interval, Third Period OAR Refueling Outage 3R16 PAGE 2 OF 10 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Examinations Examinations Examinations Examination Total Examinations Category Required For The Credited For Credited (%) Credited (%) Remarks Interval Crditd For The 3rd thru 3rd Period of IntervalThe 3rd Period Period The Interval B-A 31 10.0 32.3 100.0 RPV Circumferential shell weld exempted per approved Relief reusRR4 request RR-41 Case N-598, Alternative Requirements to Required Percentages of B-D 61 18.0 29.5 100.0 Examinations, Section Xl, Division 1 per approved Relief Request RR-33 B-E examinations completed during RPV Hydro performed in B-E 62 0.0 0.0 100.0 P31 P3R 14 B-G-1 109 46.0 42.2 100.0 Code Case N-598 per approved Relief Request RR-33 B-G-2 116 49.0 42.2 100.0 Code Case N-598 per approved Relief Request RR-33

1) Code Case N-598 per approved Relief Request RR-33 B-K 18 8.0 44.4 111.1 2) Use of ASME CC N-509, Alternative Rules for the Selection and Examination of Class 1, 2, and 3 Integrally Welded Attachments Section Xl, Division 1, included Category B-H as B-K B-L-2 2 1.0 50.0 100.0 B-M-2 11 6.0 54.5 100.0 B-N-1 3 1.0 33.3 100.0 B-N-2 49 20.0 40.8 100.0 B-P 6 3.0 50.0 100.0 C-A 2 1.0 50.0 100.0 Code Case N-598 per approved Relief Request RR-33 C-B 8 3.0 37.5 50.0 C-C 17 9.0 52.9 117.6 Code Case N-598 per approved Relief Request RR-33 C-H 51 19.0 37.3 98.0 RPV flange leakoff drain piping test not completed for 2nd period.

Final Unit 3 OAR-1 KAH Verification Markup

Peach Bottom Atomic Power Station, Unit 3 ATTACHMENT 5B Third Interval, Third Period OAR Refueling Outage 3R16 PAGE 3 OF 10 TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Total Total Total Total Examinations Examinations Examinations Examinations Examination Remarks Category Required For The Credited (%) Credited (%)

Interval Credited For For The 3rd thru 3rd Period of The 3rd Period Period The Interval D-A 18 19.0 105.6 105.6 Code Case N-598 per approved Relief Request RR-33 D-B 3 1.0 33.3 100.0 VT-3 of the submerged portions of the Torus and Vent System have been extended 1 year. Will be performed during first outage E-A 68 32.0 47.1 97.1 in 4th interval per Interval per IWA-2430(d). An additional GV of Containment was performed in this interval for the ILRT requirements

.100.0 Alternative examination program per approved Request for Alternative CRR-1 1 E-D 63 63.0 100.0 100.0 10CFR50 Appendix J examination of seals and gaskets during P3R1 5 per approved Request for Alternative CRR-01 E-G 76 76.0 100.0 100.0 10CFR50 Appendix J and Code Category E-A examination during P3R15 per approved Request for Alternative CRR-07 E-P 1 1.0 100.0 100.0 During P3R15 in accordance with 10CFR50 Appendix J Test Program and Schedule F-A 158 58.0 36.7 103.2 Code Case N-598 per approved Relief Request RR-33 R-A 139 51.0 36.7 100.0 Implemented RI-ISI starting 2nd Period, replacing Categories B-F, B-J, and C-F-2.

Final Unit 3 OAR-1 KAH Verification Markup

ATTACHMENT 5B PAGE 4 OF 10 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw or Relevant Condition Found During Examination Item Item Description Flaw Characterization (IWA-3300) Scheduled ASME XI Examination or Test Category Number (Yes or No) 32MO-H57 .

.i v n...................

......... .. ... i.e.

.a....................................

n........ ........

F-A F1.30 Relevant Condition - Bent and loose parts. Yes (N-491-1 ).. Spring Support Accepted by Engineering Evaluation.

N-7 Vent Flange 1/64 in. wide gouge completely across No, occurred during vessel disassembly tongue sealing surface of the flange. Repaired.

E-C E4.11 Torus Wetted Pressure B oundary Relevant Condition - Pitting was inspected and Yes depths measured. Accepted by Engineering Evaluation.

E-D E5,30 3-MBAR-INT Relevant Condtion - five (5) small areas of Yes Moisture Barrier degradation. Repaired. ..

F-A FI.10 iD-4 Relevant Condition - all eight (8) bolts and nuts Yes (N-491-1 Pipe Support missing. Support plate is welded. Accepted by

~E

........................... g.n e rin ..E

.......... x.a~ at on 2....................................................................-.

Engineering Evaluation. .....................

E-A E1.12 Torus Relevant Condition - six (6) pipes were identified Yes Piping in Torus air space to have surface rust. Accepted by Engineering Evaluation F-A F1.30 33HB-S 145 Relevant Condition - loose nut on the pipe clamp Yes (N-491-1) Rigid Restraint bolt as well as an incorrectly sized bushing.

Accepted by Engineering Evaluation. Loose nut rrea paired e aand n re-examination e- a..................................................

at 0 _acceptable.

c abe. ........

F-A F1.30 33HB-H152 Relevant Condition - loose jam nut on threaded rod. Yes (N-491-1) Spring Hanger Accepted by Engineering Evaluation. Loose nut

............. ................................c..

.................................. ...a .. a.....b....le..... b. .............................................................................................

E-A E1.12 Drywell Relevant Condition - on the inside of the head Yes N-4 Drywell Head Hatch access penetration, N-4, paint is peeled off in about a 6" x 10" area. Accepted by

... E...

... va.u at. ................................................................

E....................................................................a.t........

E on.

F-A F1.20 23HB-$40 Relevant Condition - a washer is missing on the Yes (N-49 1-1) Rigid Restraint base plate #17 (northwest corner). Repaired.

Final U3-I3-P3-3R16 OAR- I

ATTACHMENT 5B PAGE 5 OF 10 TABLE 2 ITEMS WITH FLAWS OR RELEVANT CONDITIONS THAT REQUIRED EVALUATION FOR CONTINUED SERVICE Flaw or Relevant Condition Found During Examination Item Item I)escription Flaw Characterization (IWA-3300) Scheduled ASME XI Examination or Test Category Numb' (Yes or No)

E-A El.20 Vent Header Relevant Condition - 4 downcomers at the 270 Yes degree azimuth, coating is peeling near the waterline. Areas are approximately 6-8 inches long

.......... and wide. Accepted by Engineering Evaluation F-A F1.40 RHRHX-D-LS Relevant Condition - Missing bolts and gap in No (N-491-1) Heat Exchanger Lower Support plate. Accepted by Engineering Evaluation.

F-A .................................

6. ..............................................

e....a t n ion pp.. re r- n-on ot.................................................

F1.30 33HB-S63 Relevant Condition - pipe restraint found not No Pipe Restraint carrying correct load. Accepted by Engineering Evaluation.

F-A ....................

F1.30 33HB-H127 Relevant Condition - pipe restraint found not No carrying correct load. Accepted by Engineering Evaluation.

Final U3-13-P3-3R16 OAR- I

TABLE 3 ATTACHMENT 5B

SUMMARY

OF ASME REPAIRS AND REPLACEMENTS COMPLETED PAGE 6 OF 10 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 17, 2005 TO NOVEMBER 4, 2008

( END OF 10 YEAR INTERVAL)

Denotes that use of Code Case N-416-2 was employed in completing the repair / replacement activity SYSTEM 01: MAIN STEAM SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement RV-3-02-071 G Installed a rebuilt safety relief valve No 10/6/2007 05-069, R0946313 Class 1 Replacement AO-3-01 A-080C Installed 3 new bonnet studs as incidental replacement No 10/5/2007 06-180, R1018560 Class 1 Replacement AO-3-01 A-080D Installed 4 new bonnet studs & 24 nuts as incid. replace No 10/5/2007 06-181, R1018560 Class 1 Replacement RV-3-02-071 F Installed a rebuilt safety relief valve No 10/6/2007 07-037, R0949297 Class 1 Replacement RV-3-02-070A Installed a rebuilt safety relief valve No 10/3/2007 07-042, R0949210 Class 1 Replacement RV-3-02-071 J Installed a rebuilt safety relief valve No 10/6/2007 07-074, R0949450 Class 1 Replacement RV-3-02-071 K Installed a rebuilt safety relief valve No 10/6/2007 07-076, R0949298 Class 1 Replacement RV-3-02-071 L Installed a rebuilt safety relief valve No 10/6/2007 07-078, R0949503 Class 1 Replacement RV-3-02-071 C Installed a rebuilt safety relief valve No 10/6/2007 07-079, R0949456 Class 1 Replacement RV-3-02-071 D Installed a rebuilt safety relief valve No 2/6/2008 07-160, C0223239 SYSTEM 02: REACTOR AND RECIRCULATION Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement 1313-3-02A-313PO34 Installed new pump internals motor No 10/7/2007 07-049, C0219200

TABLE 3 A'TACHMENT 5B

SUMMARY

OF ASME REPAIRS AND REPLACEMENTS COMPLETED PAGE 7 OF 10 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 17, 2005 TO NOVEMBER 4, 2008

( END OF 10 YEAR INTERVAL)

- Denotes that use of Code Case N-416-2 was employed in completing the repair / replacement activity SYSTEM 03: CONTROL ROD DRIVE Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Descriotion Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement CRD's 06-19, 10-47, 22-31, Exchanged CRD's with rebuilt CRD's No 10/1/2007 06-183, R1018595 26-11, 26-31, 26-43, 30-15, 30-35, 34-31, 34-39, 34-51, 38-39, 42-23, 42-31, 50-11,-

50-19, 58-39

- Class 1 Replacement SVD cleanout pipe caps Install pipe caps/connections on scram disch. header No 10/6/2007 07-048, C0219214 SYSTEM 04: REACTOR PRESSURE VESSEL AND INTERNALS Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Repair P13-3-04-P-P-N07 Performed skim cut on flange face to remove gouge No 10/6/2007 07-148, C0222738

TABLE 3 ATTACHMENT 5B

SUMMARY

OF ASME REPAIRS AND REPLACEMENTS COMPLETED PAGE 8 OF 10 FOR PEACH BO'TOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 17, 2005 TO NOVEMBER 4, 2008 (END OF 10 YEAR INTERVAL)

- Denotes that use of Code Case N-416-2 was employed in completing the repair / replacement activity SYSTEM 10: RESIDUAL HEAT REMOVAL Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Descriotion Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement 10GB-H1132 Installed new hanger rod and clevis No 9/26/2007 05-143, C0215615 Class 2 Replacement PB-3-10-3DE024 Installed new RHR Hx. 3DE024 Floating Head No 2/2/2007 07-005, C0219318 Class 2 Replacement RV-3-10-181 C Installed new RHR Hx. 3CE024 Shell Side Relief Valve No 11/26/2007 07-142, R0907460 Class 1 Replacement AO-3-10-046A Incidental bonnet bolt replacement No 10/1/2007 07-146, C0222695 SYSTEM 11: STANDBY LIQUID CONTROL SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component ID.) Descriotion Of Work Performed Or Test Complete R&R Plan # and WJO #

Class 2 Replacement RV-3-11-39B Installed new relief valve No 12/15/2006 06-144, C0217362 Class 2 Replacement RV-3-11-39B Installed new relief valve No 10/1/2007 06-152, R1011381 Class 2 Replacement RV-3-11-39A Installed new relief valve No 10/1/2007 06-153, R1011382 Class 2 Replacement RV-3-11-39A Installed new relief valve No 12/14/2006 06-214, C0219575 SYSTEM 13: REACTOR CORE ISOLATION COOLING SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section Xl Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 1 Replacement MO-3-13-015 Installed new valve bonnet No 10/4/2007 07-102, C0219281

TABLE 3 ATTACHMENT 5B

SUMMARY

OF ASME REPAIRS AND REPLACEMENTS COMPLETED PAGE 9 OF 10 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 17, 2005 TO NOVEMBER 4, 2008 (END OF 10 YEAR INTERVAL)

Denotes that use of Code Case N-416-2 was employed in completing the repair / replacement activity SYSTEM 23: HIGH PRESSURE COOLANT INJECTION SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement HV-3-23C-55 Installed new bonnet on HPCI turb exh drain to torus valve No 9/28/2007 07-080, C0220043

- Class 2 Replacement HV-3-23C-31158 Installed new valve/piping for HPCI turb exh drain to torus No 9/28/2007 07-081, C0220043 Class 2 Replacement 23-DDN-S-300A/B Installed new base plate hilti anchor bolts No 9/25/2007 07-089, C0220627 Class 2 Replacement VRV-3-23C-140A Installed new vacuum relief valve. No 6/16/2008 08-087, R0790436 Class 2 Replacement VRV-3-23C-140B Installed new vacuum relief valve. No 6/16/2008 08-088, R0790439 Class 2 Replacement VRV-3-23C-140C Installed new vacuum relief valve. No 6/16/2008 08-089, R0790438 Class 2 Replacement VRV-3-23C-140D Installed new vacuum relief valve. No 6/16/2008 08-090, R0790440 SYSTEM 32: HIGH PRESSURE SERVICE WATER SYSTEM Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 3 Replacement RV-3-32-180A Installed new RHR Hx. 3AE024 Tube Side Relief Valve No 11/30/2006 06-157, R0821600 Class 3 Replacement RO-3789C Installed new orifice plate in RO-3789C No 11/26/2007 06-201, C0218911 Class 3 Replacement RV-3-32-180D Installed new RHR Hx. 3DE024 Tube Side Relief Valve No 7/30/2007 06-206, R0875863 Class 3 Replacement RO-3800D, RO-3789D Installed new / modified orifice plates in RO-3800D/3789D No 7/31/2007 07-097, C0220918 Class 3 Replacement RV-3-32-180C Installed new RHR Hx. 3CE024 Tube Side Relief Valve No 11/26/2007 07-143, R0889741

TABLE 3 ATTACHMENT 51

SUMMARY

OF ASME REPAIRS AND REPLACEMENTS COMPLETED PAGE 10 OF 10 FOR PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 OCTOBER 17, 2005 TO NOVEMBER 4, 2008 (END OF 10 YEAR INTERVAL)

Denotes that use of Code Case N-416-2 was employed in completing the repair/ replacement activity SYSTEM 65A: HYDRAULIC SNUBBERS Flaw or Relevant Repair, Condition Found Replacement, During Scheduled Code or Corrective Item Description Section XI Exam Date Class Measure (component I.D.) Description Of Work Performed Or Test Complete R&R Plan # and W/O #

Class 2 Replacement 10-GB-S-58 Installed new snubber No 10/5/2007 07-012, R0545777 Class 3 Replacement 1-GG-S-25 Installed new snubber No 10/1/2007 07-013, R0545115 Class 2 Replacement 10-GB-S-12 Installed new snubber No 9/26/2007 07-014, R0545327 Class 1 Replacement 6-DDNL-S-12 Installed new snubber No 9/30/2007 07-015, R0546132 Class 1 Replacement SS-3-A Installed new snubber No 9/27/2007 07-016, R0646441 Class 3 Replacement 1-GG-S-1 8 Installed new snubber No 9/30/2007 07-019, C0219939 Class 2 Replacement 10-GB-S-64 Installed new snubber No 9/26/2007 07-021, C0219945 Class.. Replacement 27-HCR-S-187 Installed new snubber No 9/26/2007 07-026, C0219969 Class 3 Replacement 1-GG-S-205-A Installed new snubber No 10/1/2007 07-029, C0219986 Class.. Replacement 1-DB-S-38-A Installed new snubber No 10/8/2007 07-038, R0815380 Class.. Replacement 1-DB-S-25-A Installed new snubber No 10/8/2007 07-040, R0815579 Class.. Replacement 1-DB-S-2-A Installed new snubber No 10/8/2007 07-041, R0815590 Class 1 Replacement SS-11-13, SS-2-13 Installed temporary struts to allow pump/motor replacement No 9/30/2007 07-107, C0219219

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