RS-12-177, E Plan for Future Seismic Walkdown of Inaccessible Equipment

E Plan for Future Seismic Walkdown of Inaccessible Equipment

ML13120A189
Person / Time
Site:	Oyster Creek
Issue date:	04/26/2013
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
References
RS-12-177, RA-13-022, RS-13-065 12Q0108.80-R-001, Rev 1
Download: ML13120A189 (165)

Text

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 E

Plan for Future Seismic Walkdown of Inaccessible Equipment Sixteen (16) items could not be walked down during the 180-day period following the issuance of the 1 OCFR50.54(f) letter due to their being inaccessible. The items will be walked down during a unit outage or time when the equipment is accessible, as appropriate. Table E-1 summarizes the reasons each item is inaccessible during normal plant operation and notes the Oyster Creek Station Issue Report IR that has been written to track completion of the Seismic Walkdowns (and Area Walk-bys) for these items. It is noted that SSCs identified on Table E-1 require a complete inspection including, as applicable, internal inspections of electrical cabinets for other adverse seismic conditions, as required.

Certain cabinets require supplemental internal inspection for other adverse seismic conditions as summarized in Table E-2. Supplemental internal inspections of these cabinets are required due to clarification provided by the NRC after the online seismic walkdowns were completed. These Supplemental inspections will be completed during a unit outage or another time when the equipment is accessible, as appropriate. It is noted, that SSCs identified on Table E-1 do not appear on Table E-2.

E-1

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Table E-1. Inaccessible and Deferred Equipment Component Reason for Action Resolution/ Milestone ID Description Inaccessibility IDR) Status Completion SAFETY RELIEF Located in V-1-160 VALVE NR28D Drywell 1382250 Open 4Q2012 (SOUTH HEADER)

SAFETY RELIEF Located in V-1-164 VALVE NR28H Drywell 1382250 Open 4Q2012 (NORTH HEADER)

ELECTROMATIC Located in V-1 -173 RELIEF VALVE Drywell 1382250 Open 402012 NR108-A(SOUTH HEADER)

ELECTROMATIC Located in V-i-i175 RELIEF VALVE Drywell 1382250 Open 4Q2012 NR108-C(NORTH HEADER)

ELECTROMATIC Located in V-1 -177 RELIEF VALVE Drywell 1382250 Open 4Q2012 NR108-E(SOUTH HEADER)

CU INLET Located in V-16-1 ISOLATION VALVE Drywell 1382250 Open 4Q2012 FROM REACTOR VESSEL V-1-106 MAIN STEAM LINE'A' Located in 1382250 Open 4Q2012 DRAIN VALVE Drywell MAIN STEAM LINE'A' Located in V-1-7 OUTLET ISOLATION Drywell 1382250 Open 4Q2012 VALVE(NS03-A)

MSIV'S SOLENOID Located in RK-41 1-1 AIR VALVE & Trunnion Room 1382250 Open 4Q2012 EQUIPMENT MOUNTING RACK MAIN STEAM LINE'B' Located in V-1-10 OUTLET ISOLATION Trunnion Room 1382250 Open 4Q2012 VALVE(NS04-B)

MCC 1A21 Clarification on 460V,3PH,3W,60HZ opening 1A21-460V FOR TURBINE cabinets was 1382250 Open 4Q2012 BUILDING provided after initial walkdown MCC 1A21B Clarification on 1A21 B- 460V,3P,3W,60HZ opening FOR REACTOR cabinets was 1382250 Open 4Q2012 BUILDING provided after initial walkdown Table E-1 Page 1 of 2 E-2

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Component Reason for Action Resolution/ Milestone ID DescriptionInaccessibility Request Status Completion ID Iaccesibiity ID (IR)

MCC 1A23 Clarification on 460V,3PH,3W,60HZ opening 1A23-460V FOR REACTOR cabinets was 1382250 Open 4Q2012 BUILDING provided after initial walkdown 460V UNIT Must physically SUBSTATION 1A2 remove 1A2-460V FOR REACTOR breakers to 1382250 Open 4Q2012 BUILDING inspect internals.

4160V BUS 1C Clarification on SWITCHGEAR opening 1C cabinets was 1382250 Open 4Q2012 provided after initial walkdown 125VDC POWER Equipment DC-C 125V PANEL DC-C always 1382250 Open 4Q2018 CENTER 'C' energized.

Table E-1 Page 2 of 2 E-3

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Table E-2. Supplemental Internal Cabinet Inspection List COMPONENT EQUIPMENT ACCESSIBLE IF NOT MILESTONE TRACKING STATUSI ID DESCRIPTION CLASS (Y/N) ACCESSIBLE, NUMBER INSPECTION WHY? COMPLETION (IR No.) RESULTS MAIN CONTROL interior RM PANEL 6R (20) inspection closed/ no 6R PROTECTION REACTOR and Control Instrumentation completed N/AN/NAisu N/A N/A issue CH. anel during online identified CH. 1 Panels walkdown MAIN CONTROL interior 7R RM PANEL 7R REACTOR (20)

Instrumentation inspection iseto closed/ no PRECTOR IndtContron completed N/A N/A N/A issue PROTECTION and Control during online identified CH.2 Panels walkdown

'C' STATION IR 1382250 BATTERY SOLID (16) Battery AR BTCHG C1 STATE STATIC Chargers and Y N/A 4Q2012 A2307028 open CHARGER C1 Inverters WO C2028232 CONTINUOUS Equipment INSTRUMENT PNL always NO.3 energized.

208/120V,3PH,4W, Opening of CIP-3 60HZ (14) Distribution N doors will N/A N/A N/A Panels introduce undue safety and operational hazard Table E-2 Page 1 of 5 E-4

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 IF NOT TRACKING STATUS /

EQUIPMENT ACCESSIBLE MILESTONE NUMBER STION COMPONENT ID DESCRIPTION CLASS (Y/N) ACCESSIBLE, COMPLETION NUMBER INSPECTION WHY? (IR No.) RESULTS 125VDC POWER Equipment PANEL DC-F always energized.

Opening of DC-F (14) Distribution N doors will N/A N/A N/A Panels introduce undue safety and operational hazard DIESEL IR 1382250 DG-1 GENERATOR (16) Battery 1 R24 refueling AR BATTERY UNIT #1 BATTERY Chargers and Y N/A A2307028 open CHARGER CHARGER Inverters outage WO C2028232 DIESEL IR 1382250 GENERATOR #1 (20) AR DG-1 SWGR UNIT Instrumentation y N/A 1R24 refueling A2307028 open SWITCHGEAR and Control outage WO Panels C2028232 CORE SPRAY/AUTO '20' (20 IR 1382250 AR ER18A DEPRESS'N Instrumentation 1 R24 refueling A2307028 open SYSTEM RELAY and Control Y N/A outage WO LOI PANEL SYSTEM RAELAY Panels C 8 LOGIC C2028232 Table E-2 Page 2 of 5 E-5

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 COMPONENT EQUIPMENT ACCESSIBLE IF NOT MILESTONE TRACKING STATUSI ID DESCRIPTION CLASS (Y/N) ACCESSIBLE, COMPLETION NUMBER INSPECTION WHY? (IR No.) RESULTS 120VAC Equipment INSTRUMENT always PANEL 4- energized.

208/120V,3PH,4W Opening of IP-4 (14) Distribution N doors will N/A N/A N/A Panels introduce undue safety and operational hazard TRANSFORMER Equipment FROM MCC 1A2- always 460V TO IP-4 energized.

Opening of IT-4A (04) N doors will N/A N/A N/A Transformers introduce undue safety and operational hazard LOCALSHTON(20) IR 1382250 AR SHUTDOWN Instrumentation 1 R24 refueling A2307028 open LSP-1A2 PANEL- USS IA2 and Control N/A outage W2 PUMP/BREAKER _ OPanels CONTROL C2028232 Table E-2 Page 3 of 5 E-6

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 IF NOT TRACKING STATUS!/

STION COMPONENT EQUIPMENT ACCESSIBLE MILESTONE NUMBER ID DESCRIPTION CLASS (Y/N) ACCESSIBLE, COMPLETION NUMBER INSPECTION WHY? (IR No.) RESULTS 480/120VAC Equipment TRANSFORMER always TO PROTECTION energized.

SYS PANELS 1&2 Opening of PS-1 (04) N doors will N/A N/A N/A Transformers introduce undue safety and operational hazard 120V VITAL AC Equipment POWER PANEL always 208/120V,3PH,4W, energized.

60HZ Opening of VACP-1 (14) Panels Distribution N doors will introduce N/A N/A N/A undue safety and operational hazard 120V VITAL AC Equipment POWER PANEL always TRANSFORMER energized.

480/208/120V Opening of VACP-1 XE (04) N doors will N/A N/A N/A Transformers introduce undue safety and operational hazard Table E-2 Page 4 of 5 E-7

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 COMPONENT EQUIPMENT ACCESSIBLE IF NOT MILESTONE TRACKING STATUSI ID DESCRIPTION CLASS (Y/N) ACCESSIBLE, NUMBER INSPECTION WHY? COMPLETION (IR No.) RESULTS MCC 1A21A 460V, IR 1382250 AR 1A21A-460V 3P, 3W, 60HZ, (01) MCC Y N/A 1 R24 refueling A2307028 OPEN FOR REACTOR outage WO BUILDING C2028232 USS 1A2-460V (04) Major 1A2-460V XF 4160-480V/277V Transformers N disassembly N/A N/A N/A 3PH 60HZ required Table E-2 Page 5 of 5 E-8

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 F

Peer Review Report This appendix includes the Peer Review Team's report, including the signed Peer Review Checklist for SWEL from Appendix F of the EPRI guidance document. (Ref. 1)

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Peer Review Report for Near Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdown Inspection of Oyster Creek Generatin2 Station October 12, 2012 Prepared by Peer Reviewers Walter Diordievic (Team Leader)

Todd A. Bacon Tony Perez Walter Djordjevic O il- October 12, 2012 Peer Review Team Leader Certification Signature Date Sheet 1 of 11 F-2

12Q0108.80-R-OO1, Rev. 1 Correspondence No.: RS-12-177 IIntroduction 1.1 OVERVIEW This report documents the independent peer review for the Near Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdowns performed by Stevenson &

Associates (S&A) for Unit 1 of the Oyster Creek Generating Station (OCGS). The peer review addresses the following activities:

• Review of the selection of the structures, systems, and components, (SSCs) that are included in the Seismic Walkdown Equipment List (SWEL).

• Observation of the seismic walkdowns on August 23, 2012 and adherence to the Seismic Walkdown Guidance (SWG)1 by Mr. Todd Bacon.

• Review of a sample of the checklists prepared for the Seismic Walkdowns & Walk-Bys.

• Review of licensing basis evaluations, as applicable.

" Review of the decisions for entering the potentially adverse conditions into the plant's Corrective Action Plan (CAP).

• Review of the final submittal report The peer reviewers for OCGS, Unit 1 are Messrs. Walter Djordjevic, Todd A. Bacon, and Tony Perez, all of S&A. Mr. Djordjevic is designated the Peer Review Team Leader.

None of the aforementioned engineers is involved in the seismic walkdown inspection process so that they can maintain their independence from the project. Mr. Djordjevic is an advanced degree structural engineer, has over thirty years of nuclear seismic experience and has been trained as a Seismic Capability Engineer (EPRI SQUG training), EPRI IPEEE Add-on, Seismic Fragility and Seismic Walkdown Engineer (SWE). Mr. Bacon is a civil-structural engineer with over thirty years of nuclear engineering experience and has received the Seismic Walkdown Engineer (SWE) training. Mr. Perez is a mechanical engineer with 15 years of experience and a trainee in a 9 month Senior Reactor Operator Certificate training program. Mr. Djordjevic, as Peer 1 EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Review Team Leader, has participated in all phases of the peer review process for OCGS Unit 1.

The SWEL development was performed by Mr. T. K. Ram of S&A. No findings were cited on the peer review checklist. The completed SWEL Peer Review Checklist is found in Attachment 1. The discussion for the SWEL development peer review is found in Section 2.

The peer review of the seismic walkdown inspection started on August 23, 2012 with a peer check of the actual walkdowns for Unit 1. Mr. Bacon joined the walkdown team for a portion of the day's planned walkdowns to observe the conduct of walkdowns and adherence to the SWG. Interviews were conducted by Messrs. Bacon and Djordjevic with the SWE inspection team after review of a sample of the Unit 1 Seismic Walkdown Checklists (SWCs) and the Area Walk-by Checklists (AWCs) to ascertain procedural compliance with the SWG. The interviews were conducted with Mr. Mark Etre of the SWE inspection team on October 1, 2012 and Mr. Seth Baker of the SWE walkdown inspection team on October 2, 2012. The discussion of the sample SWCs and AWCs is provided in Section 3.

No issues were identified which challenged the current licensing basis.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 2Peer Review - Selection of SSCs 2.1 PURPOSE The purpose of this section is to describe the process to perform the peer review of the selected structures, systems, and components, (SSCs) that were included in the Seismic Walkdown Equipment List (SWEL).

This section documents the Peer Review - Selection of SSCs performed for Oyster Creek Generating Station - Unit 1.

2.2 PEER REVIEW ACTIVITY - SELECTION OF SSCs The guidance in EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 2012, Section 3: Selection of SSCs was used as the basis for this review.

This peer review was based on reviews of the following documents:

• Seismic Walkdown Interim Report, Revision 2, dated 08/10/2012 This peer review was based on interviews with the following individual who was directly responsible for development of the SWEL:

e Mr. Tribhawan (TK) Ram, Senior Mechanical Engineer This peer review utilized the checklist shown in the SWG, Appendix F: Checklist for Peer Review of SSC Selection.

For SWEL 1 development, the following actions were completed in the peer review process:

" Verification that the SSCs selected represented a diverse sample of the equipment required to perform the following five safety functions:

o Reactor Reactivity Control (RRC) o Reactor Coolant Pressure Control (RCPC) o Reactor Coolant Inventory Control (RCIC) o Decay Heat Removal (DHR) o Containment Function (CF)

This peer review determined that the SSCs selected for the seismic walkdowns represent a diverse sample of equipment required to perform the five safety functions.

• Verification that the SSCs selected include an appropriate representation of items having the following sample selection attributes:

o Various types of systems o Major new and replacement equipment Sheet 4 of 11 F-5

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 o Various types of equipment o Various environments o Equipment enhanced based on the findings of the IPEEE o Risk insight consideration This peer review determined that the SSCs selected for the seismic walkdowns include a sample of items that represent each attribute/consideration identified above.

For SWEL 2 development, the following actions were completed in the peer review process:

" Verification that spent fuel pool related items were considered and appropriately added to SWEL 2.

This peer review determined that spent fuel pool related items were given appropriate consideration. Portions of the spent fuel pool cooling system are classified as Seismic Category 1 (Class I) and SWEL 2 was sufficiently populated as appropriate. There were items identified as potentially related to rapid drain down and these items were added to SWEL 2 as appropriate.

" Verification that appropriate justification was documented for spent fuel pool related items that were not added to the SWEL 2.

This peer review determined that an appropriate level of justification was documented for those items related to the spent fuel pool that were not added to SWEL 2.

2.3 PEER REVIEW FINDINGS - SELECTION OF SSCs This peer review found that the process for selecting SSCs that were added to the SWEL was consistent with the process outlined in the SWG Section 3: Selection of SSCs.

The peer review checklist is attached to this document with additional findings documented as appropriate.

This peer review resulted in no additional findings.

2.4 RESOLUTION OF PEER REVIEW COMMENTS - SELECTION OF SSCS All comments requiring resolution were incorporated prior to completion of this peer review.

2.5 CONCLUSION

OF PEER REVIEW- SELECTION OF SSCS This peer review concludes that the process for selecting SSCs to be included on the seismic walkdown equipment list appropriately followed the process outlined in the SWG, Section 3:

Selection of SSCs. It is further concluded that the SWEL sufficiently represents a broad population of plant Seismic Category 1 (Class I) equipment and systems to meet the objectives of the NRC 50.54(f) letter.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 3Review of Sample Seismic Walkdown & Area Walk-Bys Checklists 3.1 OVERVIEW A peer review of the SWCs and AWCs was performed on August 23, 2012, after which an interview was conducted by Messrs. Djordjevic and Bacon with the SWE inspection team in accordance with the SWG requirements on October 1 and 2, 2012. The SWE trained walkdown engineers were Messrs. Mark Etre and Seth Baker.

3.2 SAMPLE CHECKLISTS Table 3-1 lists the SWC and AWC samples which represent approximately 25% of the SWCs and 25% of the AWCs. The sample includes the equipment inspected during the peer review participation and other equipment items from other classes to introduce diversity to the sampling procedure.

Table 3-1: Table of SWC and AWC Samples from Seismic Walkdown Inspection for Unit 1 Equipment Equipment Class Walkdown Item Observations Identification (GIP) 1A2-460V XF 4 - Transformers USS 1A2-460V Trans. No concerns 4160-480V/277V 3PH 60HZ 1A21A-460V 1 - Motor Control MCC 1A21A No concerns Centers 460V,3P,3W,60HZ for Reactor Building 7R 1 - Motor Control Main Control Room No concerns Centers Panel 7R Reactor Protection CH.2 305-125\26-19 21 - Tanks and Heat Main Control Room No concerns Exchangers Panel 7R Reactor Protection CH.2 Battery Bank C 15 - Batteries on Vital Bank 'C' Station No concerns Racks Battery (Lead Acid)

CV-305-126\30- 7 - Fluid Operated CRD Inlet Scram No concerns 03 Valves Valve (South)

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Equipment Equipment Class Walkdown Item Observations Identification (GIP)

CV-305-127\30- 7 - Fluid Operated CRD Outlet Scram No concerns 03 Valves Valve (South)

DC-C 125V 14 - Distribution 125VDC Power Panel No concerns Panels DC-C Center 'C' DG-1 SWGR 20 - Instrumentation Diesel Generator No.1 No concerns and Control Panels Unit Switchgear and Cabinets DPT-6-1A0091 B 18 - Instruments on Fuel Zone Level 'B' No concerns Racks Wide Range Level Transmitter FN-732-3 9 - Fans USS 1A2-460V No concerns Transformer Cooling Fan H-21-1A 21 - Tanks and Heat Cont. Spray System No concerns Exchangers Heat Exchanger 1-1 LI-18-170 18 - Instruments on Skimmer Surge Tank No concerns Racks 'A' Fuel Pool Level Indicator LS-862-1OC 0 - Other Hi-Hi Level(Pump Cut- No concerns off) On Tank T-39-003 LSP-1A2 20 - Instrumentation Local Shutdown No concerns and Control Panels Panel- USS 1A2 and Cabinets Pump/Breaker Control P-18-1C 5 - Horizontal Pumps Augmented Spent No concerns Fuel Pool Pump (NN01-C)

P-39-13 5 - Horizontal Pumps Fuel Oil Pump to Day No concerns Tank T-39-3 PI-305-131\06-15 0 - Other Accumulators Gas No concerns Pressure Indicator PS-RE0017A 18 - Instruments on Low Reactor Press. No concerns Racks Switch Readies Core Spray Valves RK-411 -1 18 - Instruments on MSIV'S Solenoid Air No concerns Racks Valve and Equipment Mounting Rack Sheet 7 of 11 F-8

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Equipment Equipment Class Walkdown Item Observations Identification (GIP)

SO-305-117\06 Motor-Operated Channel I Scram Air No concerns 15 and Solenoid- Pilot Solenoid Valve Operated Valves (North)

SO-305-120\06 Motor-Operated Directional Flow No concerns 15 and Solenoid- Control Withdraw Operated Valves Solenoid Valve (North)

T-18-1A 21 - Tanks and Heat Skimmer Surge Tank No concerns Exchangers 'A' For Spent Fuel Storage Pool T-39-5 21 - Tanks and Heat M-39-1 Cooling Water No concerns Exchangers Tank V-1-7 7 - Fluid Operated Main Steam Line 'A' No concerns Valves Outlet Isolation Valve(NS03-A)

V-1-173 7 - Fluid Operated Electromatic Relief No concerns Valves Valve NR108-A (South Header)

V-17-212 8 - Motor-Operated SDC Loop 'A' Outlet No concerns and Solenoid- Header Vent Valve Operated Valves V-18-80 0 - Other P1-18-88 Isolation No concerns Valve V-20-15 8 - Motor-Operated "A" Containment No concerns and Solenoid- Isolation Valve -

Operated Valves SYS.I VACP-1 XF 4 - Transformers 120V Vital AC Power No concerns Panel Transformer 480/208/120V Sheet 8 of 11 F-9

12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 Area Walkdown Description Observations DGB Area 2 - El. 23.00' No concerns RB Area 6 - El. 51.00' Bent hanger rod by airlock - IR 01402715.

RB Area 10 - El. 23.00' No concerns RB Area 15 - El. 51.00' No concerns RB Area 19 - El. 19.00' No concerns TB Area 25 - El. 23.00' No concerns OB Area 5 - El. 35.00' No concerns 3.3 EVALUATION OF FINDINGS There were no findings that challenged the licensing basis. Tables 5-2 and 5-3 of the Seismic Walkdown Report (final submittal report) provide the lists of the issues identified for the equipment seismic walkdowns and area walk-bys.

The scaffolding and seismic housekeeping procedures were reviewed by the SWEs in order to gain a full understanding of the plant practices in regard to those procedures.

There were no seismic concerns noted in Unit 1 with regard to scaffold erection. The scaffolds were properly tied off and braced, and properly tagged with respect to the procedure.

Concerning seismic housekeeping, there was one instance found throughout the plant concerning ladder storage adjacent to a tank. It can be concluded that OCGS, Unit 1 implements their seismic housekeeping program consistently and to a high standard.

Items identified during the Seismic Walkdowns and Area Walk-bys were ultimately not judged to be "Potentially Adverse Seismic Conditions", as summarized in Sections 5.2 and 5.3 of the Seismic Walkdown Report. There were minor instances of loose hardware (bolts/nuts) and a few bent hanger rods. There was an instance of an open s-hook on a light fixture. In all instances issues identified were judged that they would not prevent the equipment from performing its safety-related function.

The Seismic Walkdown Checklists document the details of all issues identified, the action taken and the conclusion rendered by the SWE inspectors.

The peer reviewers consider the judgments made by the SWEs to be appropriate and in concurrence with the SWG.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 4 Review of Licensing Basis Assessments Tables 5-2 and 5-3 of the Seismic Walkdown Report provide a list of the issues identified during the Unit 1 seismic walkdown inspections for the SWEL components and how they were addressed. If an Oyster Creek Generating Station IR request was generated it is shown in the Tables. Interviews were conducted by Messrs. Djordjevic and Bacon with the SWE inspection team on October 1 and October 2, 2012 to discuss the issues identified.

No potentially adverse seismic conditions were identified that resulted in a seismic licensing basis evaluation. The peer reviewers concur with this outcome.

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12Q0108.80-R-001, Rev. 1 Correspondence No.: RS-12-177 5Review Final Submittal Report & Sign-off The final submittal report has been reviewed by Messrs. W. Djordjevic, A. Perez and T. A.

Bacon and found to meet the requirements of the EPRI 1025286 - Seismic Walkdown Guidance. The Peer Review determined that the objectives and requirements of the 50.54(f) letter2 are met. Further, the efforts completed and documented within the final submittal report are in accordance with the EPRI guidance document.

2 NRC Letter to All Power Reactor Licensees et al., "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," Enclosure 3, "Recommendation 2.3: Seismic," dated March 12, 2012 11 F-1 2

12Q0108.80-R-001, Rev. 1 Attachment 1 Correspondence No.: RS-12-177 Sheet I of 2 Peer Review Checklist for SWEL - Oyster Creek Generating Station - Unit 1 Instructions for Completing Checklist This peer review checklist may be used to document the review of the Seismic Walkdown Equipment List (SWEL) in accordance with Section 6: Peer Review. The space below each question in this checklist should be used to describe any findings identified during the peer review process and how the SWEL may have changed to address those findings. Additional space is provided at the end of this checklist for documenting other comments.

1. Were the five safety functions adequately represented in the SWEL I selection? YlZ NEI No comments.

2. Does SWEL I include an appropriate representation of items having the following sample selection attributes:

a. Various types of systems? Y NEI No comments.

b. Major new and replacement equipment? YE NEI No comments.

c. Various types of equipment? YE NEI No comments.

d. Various environments? YEINW1 No comments.

e. Equipment enhanced based on the findings of the IPEEE (or equivalent) program? YM NEI No comments.

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12Q0108.80-R-001, Rev. 1 Attachment 1 Correspondence No.: RS-12-177 Sheet 2 of 2 Peer Review Checklist for SWEL - Oyster Creek Generating Station - Unit 1

f. Were risk insights considered in the development of SWEL 1? YO N[-]

No comments.

3. For SWEL 2:

a. Were spent fuel pool related items considered, and if applicable included in SWEL 2?

No comments.

b. Was an appropriate justification documented for spent fuel pool related items not YO NE included in SWEL 2?

No comments.

4. Provide any other comments related to the peer review of the SWELs.

None.

5. Have all peer review comments been adequately addressed in the final SWEL? YS N[l Tony Perez Peer Reviewer # 1: Date: 08/31/2012 Walter Djordjevic O il Peer Reviewer #2: Date: 09/02/2012 F-14

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Annex A Updated Transmittal # I Ai

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Contents of Annex A Al Introduction ....................................................................................................... Al-A 1 .1 P u rp o s e .............................................................................................................. A l -1 A1.2 Background ................................................................................................... Al-2 A1.3 Plant Overview ............................................................................................... A1-2 A1.4 Approach ........................................................................................................... Al-2 A1.5 Conclusion .......................................................................................................... Al-2 A2 Seism ic Licensing Basis .......................................................................................... A2-1 A3 PersonnelQualifications........................................................................................... A3-1 A3.1 Overview ............................................................................................................ A3-1 A3.2 Project Personnel ............................................................................................... A3-1 A3.2.1 Stevenson & Associates Personnel ......................................................... A3-2 A3.2.2 Additional Personnel ............................................................................... A3-2 A4 Selection of SSCs ..................................................................................................... A4-1 A5 Seism ic Walkdowns and Area Walk-Bys .................................................................. A5-1 A5.1 Overview ............................................................................................................ A5-1 A5.2 Seism ic W alkdowns ............................................................................................ A5-1 A5.2.1 Adverse Anchorage Conditions .............................................................. A5-2 A5.2.2 Configuration Verification ........................................................................ A5-2 A5.2.3 Adverse Seism ic Spatial Interactions ...................................................... A5-2 A5.2.4 Other Adverse Seism ic Conditions ........................................................ A5-2 A5.2.5 Conditions Identification during Seism ic Walkdowns ................................. A5-2 A5.3 Area W alk-Bys .................................................................................................... A5-2 A5.3.1 Conditions Identification during Area W alk-bys ......................................... A5-3 A5.4 Supplemental Information on Electrical Cabinet Inspections ................................ A5-3 Aii

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A6 Licensing Basis Evaluations..................................................................................... A6-1 A7 IPEEE VulnerabilitiesResolution Report ............................................................ A 7-1 A8 Peer Review ............................................................................................................... A8-1 A9 References ................................................................................................................ A9-Appendices AA ProjectPersonnelResumes and SWE Certificates................................................ AA-1 AC Seismic Walkdown Checklists (SWCs) ................................................................... AC-1 AD Area Walk-By Checklists (AWCs) ............................................................................ AD-1 AE Plan for Future Seismic Walkdown of Inaccessible Equipment............................. AE-1 AF Peer Review Report.................................................................................................. AF-1 Tables Table A3-1. Personnel Roles .................................................................... . . ..... A3-1 Table A5-2. Conditions Identified during Seismic Walkdowns ..................................... A5-4 Table A5-3. Conditions Identified during Area Walk-Bys ............................................. A5-5 Table AC-I. Summary of Seismic Walkdown Checklists ............................................. AC-2 Table AC-2. Summary of Seismic Walkdown Checklists for Supplemental Internal Inspe ctio n s ......................................................................................... A C-3 Table AD-1. Summary of Area Walk-By Checklists ...................................................... AD-2 Table AE-I. Inaccessible and Deferred Equipment List ............................................... AE-1 Aiii

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A I introduction A1.1 PURPOSE This updated transmittal report is being provided in compliance with the requirements contained in Enclosure 3 of the NRC 50.54(f) letter dated March 12, 2012 (Ref. 13). This new report section, Annex A, contains the results of the follow-on inspection activities that have been completed to address commitments contained in Exelon letter to the NRC, "180-day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)

Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated November 19, 2012 (RS-12-177). Annex A, includes follow-on Seismic Walkdown results associated with NRC Commitment Nos. 1 and 2 listed in Enclosure 2 of the above Exelon letter.

Additionally, the update includes the current status of the resolution of conditions found during the initial Seismic Walkdowns and Area Walk-Bys as documented in Tables 5-2 and Table 5-3, respectively, from Enclosure 1 of the above Exelon letter.

Commitment No. 1, for the completion of the 16 remaining inspection (SWEL) items previously deferred due to inaccessibility listed in Table E-1, remains open. This update documents the completion of 15 of the 16 inspection items in accordance with the individual item completion schedule. The remaining inspection item, listed in Table AE-1, will be completed by the original 4Q2018 (December 31, 2018) commitment date. A subsequent NRC transmittal will be issued to document results of this inspection and the completion of Commitment No. 1.

Commitment No. 2, for the completion of the 6 remaining internal electrical cabinet inspections listed in Table E-2, has been completed. All 6 inspection items were completed by the commitment date of 4Q2012 (December 31, 2012) and the results are documented in this update.

The initial NRC Transmittal report documented that 3 conditions identified during the Seismic Walkdowns, and listed in Table 5-2, remained open. This update documents that all 3 conditions are now resolved with all follow-on actions complete.

The initial NRC Transmittal report documented that 3 conditions identified during the Area Walk-Bys, and listed in Table 5-3, remained open. This update documents that all 3 conditions are now resolved with all follow-on actions complete.

Annex A, includes updates to each report section where the status has changed or new information is available in accordance with Section 8 of EPRI 1025286, "Seismic Walkdown Guidance - For Resolution of Fukushima Near Term Task Force Recommendation 2.3 Seismic" (Ref. 1).

Al-1

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A

1.2 BACKGROUND

See Section 1.2 A1.3 PLANT OVERVIEW See Section 1.3 A1.4 APPROACH See Section 1.4 A

1.5 CONCLUSION

As of December 31, 2012, Seismic Walkdowns have been completed at the Oyster Creek Generating Station Unit 1 on 15 of the16 items deferred due to inaccessibility along with 6 remaining supplemental inspections of electrical cabinets, in accordance with the NRC endorsed walkdown methodology. Area Walk-Bys were also completed, as required, during these follow-on activities. No degraded, nonconforming, or unanalyzed conditions that required either immediate or follow-on actions were identified.

Additional follow-on activities required to complete the efforts to address Enclosure 3 of the 50.54(f) letter include inspection of one item deferred due to inaccessibility, as listed in Table AE-1 of this Annex A.

As of January 18, 2013, all conditions identified during the walkdowns and walk-bys as documented in IRs listed in Table 5-2 and Table 5-3 have been corrected.

No IRs were generated during the follow-on walkdowns. The updated completion status for the previous IRs is shown in Table A5-2 and Table A5-3 in Section A5 of this Annex A.

A1-2

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A 2 Seismic Licensing Basis See Section 2, no new licensing basis evaluations resulted from the follow-on walkdown activities.

A2-1

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A3 Personnel Qualifications A3.1 OVERVIEW This section of the report identifies the personnel that participated in the NTTF 2.3 Seismic Walkdown efforts. A description of the responsibilities of each Seismic Walkdown participant's role(s) is provided in Section 2 of the EPRI guidance document.

Resumes provided in Appendix A, and Appendix AA in this Annex A, provide detail on each person's qualifications for his or her role.

A3.2 PROJECT PERSONNEL Table A3-1 below summarizes the names and corresponding roles of personnel who participated in the NTTF 2.3 Seismic Walkdown effort.

Table A3-1. Personnel Roles Equipment Seismic L Name Naeeient Selection Plant Walkdown icensing Basis IPEEE Reiwr Peer evwr Engineer Operations Engineer Review Reviewer Reviewer (SWE)

A. Perez XM K. Hull X T.K. Ram X M. Etre X X S. Baker X X W. Ho (Exelon) X X X A. Osam-Duodu X (Exelon)(3)

X(2)

M. Hand (Exelon)(3)

E. DeMonch (Exelon) X Notes:

1. Peer Review Team member for SWEL review only.

2. Peer Review Team Leader.

3. Personnel for follow-on activities only. Resumes provided in Appendix AA.

A3-1

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A3.2.1 Stevenson & Associates Personnel See Section 3.2.1, no new S&A personnel participated in the follow-on activities.

A3.2.2 Additional Personnel See Section 3.2.2, the following additional Exelon personnel participated in the follow-on activities:

Exelon Engineering staff member Mr. Anthony Osam-Duodu is a member of the peer review team for updated transmittal #1. He has worked at Oyster Creek Generating Station since 2007. He has a Ph. D. in Civil Engineering from Columbia University, New York. He is also a Seismic Capability Engineer (SCE). Anthony has over 25 years of experience covering all aspect of Civil/Structural Engineering and Project Management. He has been involved in all aspects of plant modification/configuration change activities at Oyster Creek. Other activities include the following: SQUG walkdown/seismic evaluation, Equipment Dynamic Qualification Test reviews, Rigging evaluations, Lead Shielding, Scaffolding, Structural Monitoring, and other support activities.

Exelon Engineering Design staff member, Mr. Michael Hand, is Peer Review Team Leader for updated transmittal #1. Mr. Hand is a Structural Engineer, Level 3 and has worked at Oyster Creek since 2006. He holds the Seismic Capability Engineer (SCE) certification and is fully qualified to perform all aspects of structural/seismic SSC analysis, design and qualification. He also is Program Owner of the OC Structures Monitoring Program and ensures compliance with Maintenance Rule requirements. Mr.

Hand has over 30 years experience in various aspects of civil/structural engineering and project management, including 13 years of nuclear experience, and is often called upon to mentor less experienced engineers.

A3-2

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A4 Selection of SSCs See Section 4, no changes were made to the SWEL for the follow-on walkdowns.

A4-1

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A 5 Seismic Walkdowns and Area Walk-Bys A5.1 OVERVIEW Follow-on Seismic Walkdowns and Area Walk-Bys were conducted by a two (2) person team of trained Seismic Walkdown Engineers (SWEs), in accordance with the EPRI guidance document during the fourth quarter of 2012. The Seismic Walkdowns and Area Walk-Bys are discussed in more detail in the following sub-sections.

Consistent with the EPRI guidance document, Section 4: Seismic Walkdowns and Area Walk-Bys, the SWEs used their engineering judgment, based on their experience and training, to identify potentially adverse seismic conditions. Where needed, the engineers were provided the latitude to rely upon new or existing analyses to support their judgment.

The SWEs conducted the Seismic Walkdowns and Area Walk-Bys together as a team.

During the evaluations, the SWEs actively discussed their observations and judgments with each other. The results of the Seismic Walkdowns and Area Walk-Bys reported herein are based on the comprehensive agreement of the SWEs.

A5.2 SEISMIC WALKDOWNS These follow-on Seismic Walkdowns focused on the seismic adequacy of the items previously deferred due to inaccessibility listed on Table E-1 of this report. The Seismic Walkdowns also evaluated the potential for nearby SSCs to cause adverse seismic interactions with the items being inspected. The Seismic Walkdowns focused on the following adverse seismic conditions associated with the subject equipment:

" Adverse anchorage conditions

" Adverse seismic spatial interactions

" Other adverse seismic conditions The results of the follow-on Seismic Walkdowns were documented in Appendix AC of this Annex A, using the Seismic Walkdown Checklist (SWC) template provided in the EPRI guidance document. Seismic Walkdowns were performed and SWCs were completed for 15 of the 16 items identified on Table E-1 of this report. Additionally, photos have been included with most SWCs to provide a visual record of the item along with any comments noted on the SWC. Drawings and other plant records are cited in some of the SWCs, but are not included with the SWCs because they are readily retrievable documents through the station's document management system.

During the follow-on walkdowns, one item on Table E-1 was found energized and thus inaccessible. The walkdown of this item is deferred to a time when the equipment is accessible. Appendix AE of this Annex A identifies the inaccessible equipment along with the plan for future Seismic Walkdowns.

The following subsections describe the approach followed by the SWEs to identify potentially adverse anchorage conditions, adverse seismic interactions, and other adverse seismic conditions during the Seismic Walkdowns.

A5-1

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A5.2.1 Adverse Anchorage Conditions See Section 5.2.1, no adverse anchorage conditions were identified during the follow-on walkdowns.

A5.2.2 Configuration Verification See Section 5.2.2, no additional configuration verification was required. However, the configuration of all accessible internal anchors of electrical cabinets was verified.

A5.2.3 Adverse Seismic Spatial Interactions See Section 5.2.3, no adverse seismic spatial interactions were identified during the follow-on walkdowns.

A5.2.4 Other Adverse Seismic Conditions See Section 5.2.4, no other adverse seismic conditions were identified during the follow-on walkdowns.

A5.2.5 Conditions Identification during Seismic Walkdowns No conditions were identified during the follow-on walkdowns.

Per Section 5.2.5 and Table 5-2, during the previous Seismic Walkdowns five (5) conditions were identified and entered into the Corrective Action Program. Corrective actions were completed to address two (2) of the five (5) conditions. Subsequent to the issuance of the last report corrective actions were completed to address the remaining three (3) conditions. Table A5-2 of this Annex A provides an updated summary of the conditions and the status of the corrective actions to address these conditions.

A5.3 AREA WALK-BYS The purpose of the Area Walk-Bys is to identify potentially adverse seismic conditions associated with other SSCs located in the vicinity of the items being inspected. Vicinity is generally defined as the room containing the item. If the room is very large (e.g.,

Turbine Hall), then the vicinity is identified based on judgment, e.g., on the order of about 35 feet from the item. Additional vicinity associated with these follow-on Seismic Walkdowns but not covered in Appendix D, is described on the Area Walk-By Checklist (AWC), shown in Appendix AD of this Annex A. A total of four (4) additional AWCs were completed for Oyster Creek Unit 1 as a result of these follow-on walkdowns.

The key examination factors that were considered during Area Walk-Bys include the following:

• Anchorage conditions (if visible without opening equipment)

• Significantly degraded equipment in the area

• A visual assessment (from the floor) of cable/conduit raceways and HVAC ducting (e.g., condition of supports or fill conditions of cable trays)

• Potentially adverse seismic interactions including those that could cause flooding, spray, and fires in the area A5-2

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065

" Other housekeeping items that could cause adverse seismic interaction (including temporary installations and equipment storage)

• Scaffold construction was inspected to meet Exelon Procedure MA-AA-796-024, Scaffold Installation Inspection and Removal

• Seismic housekeeping was examined to meet station procedure 119.5, Loose Equipment Storage The Area Walk-Bys are intended to identify adverse seismic conditions that are readily identified by visual inspection, without necessarily stopping to open cabinets or taking an extended look. Therefore, the Area Walk-By took significantly less time than it took to conduct the Seismic Walkdowns described above. If a potentially adverse seismic condition was identified during the Area Walk-By, then additional time was taken, as necessary, to evaluate adequately whether there was an adverse condition and to document any findings.

The results of the Area Walk-Bys were documented on the AWCs included in Appendix AD of this Annex A. A separate AWC was filled out for each area inspected. A single AWC was completed for areas where more than one item was located.

Additional details for evaluating the potential for adverse seismic interactions that could cause flooding, spray, or fire in the area are provided in Section 5.3 of this report.

A5.3.1 Conditions Identification during Area Walk-Bys No conditions were identified during the Area Walk-Bys associated with the follow-on walkdowns.

Per Section 5.3.1 and Table 5-3, during the previous seismic walkdowns five (5) conditions were identified and entered into the Corrective Action Program. Corrective actions were completed to address two (2) of the five (5) conditions. Subsequent to the issuance of the last report corrective actions were completed to address the remaining three (3) conditions. Table A5-3 of this Annex A provides an updated summary of the conditions and the status of the corrective actions to address these conditions.

A5.4 SUPPLEMENTAL INFORMATION ON ELECTRICAL CABINET INSPECTIONS See Section 5.4, these follow-on walkdowns completed the supplemental internal inspections of six (6) open items on Table E-2. No conditions were identified.

Components identified as "always energized" in Table E-2 were excluded from the inspections due to associated safety and operational hazard.

The Seismic Walkdown Checklists (SWC) for these six (6) components were documented in Appendix AC of this Annex A to indicate the results of these supplemental internal inspections.

A5-3

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Table A5-2. Conditions Identified during Seismic Walkdowns Actions Complete Item ID Description of Issue Action Request ID (IR) Yes/No 1A2-460V Loose bolts at 1A2-460V USS 1403294 Yes DC-F Loose thermometer at DC-F 1406823 Yes panel 1A21B-460V Open hooks at 1A21B-460V 1403305 Yes MCCV MCC MCC Broken bolts at containment H-21-1A spray heat exchangers H-21-1A 1403183 Yes and -1B Seismic interaction between valves V-15-133 and V-6-2917 Notes:

1) "Yes" indicates that any corrective actions resulting from the issue are complete

2) "No" indicates that any corrective actions resulting from the issue are NOT complete. Actions are tracked by the IR number in the station CAP.

A5-4

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Table A5-3. Conditions Identified during Area Walk-Bys Item ID Action Actions Description of Issue Request Complete ID (IR) Yes/No RK-3 Area Bent hanger rod by RB 51' airlock. 1402715 Yes Diesel Fuel Oil Loose ladder adjacent to diesel oil tank 1405874 Yes Storage A-480V Switchgear Bent hanger rod at 1A23-460V MCC 1403359 Yes Room 4160V A&B Loose nut at strap hanger adjacent to 1B-4160V 1405576 Yes Room switchgear DG 1 Room Mislabeled level indicators at EDG day tanks 1405561 Yes Notes:

1) "Yes" indicates that any corrective actions resulting from the issue are complete

2) "No" indicates that any corrective actions resulting from the issue are NOT complete. Actions are tracked by the IR number in the station CAP.

A5-5

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A 6 Licensing Basis Evaluations See Section 6, no new licensing basis evaluations were performed as a result of conditions identified during the follow-on Walkdowns or Area Walk-Bys.

A6-1

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A7 IPEEE Vulnerabilities Resolution Report See Section 7, no changes to the IPEEE vulnerabilities resolution were made for this Annex A.

A7-1

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A8 Peer Review A peer review team consisting of at least two individuals was assembled and peer reviews were performed in accordance with Section 6: Peer Reviews of the EPRI guidance document. The Peer Review process included the following activities:

• Review of the selection of SSCs included on the SWEL, if the SWEL has been revised

• Review of a sample of the checklists prepared for the Seismic Walkdowns and Area Walk-Bys

• Review of Licensing basis evaluations, as applicable

• Review of the decisions for entering the potentially adverse conditions into the CAP process

• Review of the submittal report

• Provide a summary report of the peer review process in the submittal report The peer reviews were performed independently from this report and the summary Peer Review Report is provided in Appendix AF of this Annex A.

A8-1

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 A9 References See Section 9, no new references were added for this Annex A.

A9-I

Oyster Creek Generating Station Unit I Correspondence No.: RS-13-065 Appendix AA Project Personnel Resumes and SWE Certificates Resumes and certificates (where applicable) for the following people are found in Appendix A:

T.K. Ram , Equipm ent Selection Engineer ........................................................ A-2 K. Hull, Equipm ent Selection Engineer .............................................................. A-4 M. Etre, SW E, Licensing Basis Reviewer ........................................................... A-7 S. Baker, SW E, Licensing Basis Reviewer ......................................................... A-10 W. Ho, SWE, Licensing Basis Reviewer, IPEEE Reviewer ................................. A-13 A. Perez, SW EL Peer Reviewer .................................................................. A-16 Resumes and certificates (where applicable) for the following people are found in Appendix AA of this Annex A:

A . Osam -Duodu, Peer Reviewer ................................................................... AA-2 M. Hand, Peer Review Team Leader ............................................................. AA-5 AA-1

uyster ureeK "enerating otation unit i Correspondence No.: RS-13-065 CURRICULUM VITAE NAME: ANTHONY OSAM-DUODU PROFESSION: CIVIL/STRUCTURAL ENGINEER KEY QUALIFICATIONS:

Anthony Osam-Duodu has extensive experience as a Civil Engineer covering the areas of planning, design, and construction supervision. The over twenty five (25) years of experience cover all aspects of Civil Engineering and Project Management. He is also a Seismic Capability Engineer (EPRI SQUG training).

He has been involved in all aspects of plant modification/configuration change activities at Oyster Creek Generating Station. Other activities at the plant include the following: SQUG walkdown/seismic evaluation, Equipment Dynamic Qualification Test reviews, Rigging evaluations, Lead Shielding, Scaffolding, Structural Monitoring, and other support activities.

As a project manager/engineer on various civil engineering projects (as described in this Resume), Anthony has effectively performed the following Project Management activities:

0 Responsible for all the services associated with the day-to-day administration of the contracts and the technical control of the various civil works.

0 Ensured that works were carried out in accordance with the Technical Specifications and Contract Documents.

" Prepared reports for the various projects.

" Checked and certified interim and final payment certificates for contractors/vendors.

EDUCATION 1997 Certificate,Institution of Management and Public Administration (GIMPA).

World Bank/Works Procurement Management Course.

1980-86 MS. & Ph.D. Civil Engineering, Columbia University, New York.

1977 B.Sc. Civil Engineering, University of Science and Technology, Ghana.

EMPLOYMENT RECORD 4/2007 - 6/2007 Oyster Creek GeneratingStation

& 9/2007 - Present Engineer III Involved in all aspects of plant modification/configuration change activities at the plant. Other activities include the following: SQUG walkdown/seismic evaluation, Equipment Dynamic Qualification Test reviews, Rigging evaluations, Lead Shielding, Scaffolding, Structural Monitoring, and other support activities.

AA-2

uyster LreeK k.enerating atauon unit Correspondence No.: RS-13-065 NOV. 2005 - OCT. 2006 Icon Engineering,New Jersey.

Project Engineer Prepared the Engineering Report for three accessory building structures at the Bayonne Golf Club, New Jersey. The structures are the Storage Building, The Gate House, and the Comfort Station. Designed and supervised the said three structures at the Bayonne Golf Club.

JUNE 1995 - JULY 2005 Departmentof Urban Roads, Accra.

Principal Consulting Engineer Performed field study of the various bridges/culverts in Metropolitan/Municipal Assembly areas in Ghana. This involved evaluation of the structural performance of said structures, design and supervision of their maintenance/rehabilitation.

MAR. 1993- MAY 1995 The Consortium (CIHSD), Accra.

Principal Consulting Engineer Designed and supervision of a clinic and administration office structures for the Accra market.

Accra Sewerage System Improvement/ Water Supply Improvement Study in association with Messrs. SOGREAH of France.

DEC. 1987- FEB. 1993 Departmentof EnvironmentalProtection, Trenton, NJ.

Senior Engineer Coordinated with and provided technical assistance to other Agencies, Divisions and Bureaus.

JUNE 1986- MAR. 1987 Gibbs & Hill Consulting Engineers,New York.

Structural Engineer Assisted in the structural design of a nuclear plant in Texas.

AA-3

Ey WS Q U G" Presentsthis Certificate ofAchievement To Certify That j

77.6h.

Anthony Osa ýDuodu has Completedthe SQUG Wafkdown Screenin" andSeismic EvaluationTraining Course I YHfedAugust 23-27ZVI 20 I C 0~

-CD (CDa oC Richrd G. Starck' t, MIPR Associarm Inc. I1 SQUG Instrucir 00

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uyster LreeK %,eneraungotauon unit i Correspondence No.: RS-13-065 MICHAEL J. HAND Structural Engineer EDUCATION Bachelor of Science - Civil Engineering Technology, Fairleigh Dickinson University EXPERIENCE EXELON GENERATION, Oyster Creek Nuclear Generating Station, Forked River, NJ (July 2006 to Present)

STRUCTURAL ENGINEER (Level 3), Design structural plant modifications, defend plant design basis, manage Structures Monitoring Program and perform inspections, subject matter expert in seismic design and qualification of systems, structures and components using industry standards and methods such as SQUG-GIP, IEEE 344, EPRI, STERI, NARE, SQURTS. Perform System Manager duties for structural (building) systems such as Maintenance Rule reviews and project presentations. Requires thorough knowledge of 10CFR50 NRC regulations and industry guidelines. Mentor next generation of Structural Engineers in nuclear.

PORT AUTHORITY OF NEW YORK AND NEW JERSEY, Newark, NJ (2003 to 2006)

STRUCTURAL ENGINEER, Engineering Dept.-Quality Assurance Division; Perform structural condition inspections and prepare condition survey reports for various Port Authority structures such as buildings, bridges, tunnels, waterfront structures, and high mast lighting structures. Perform emergency structural integrity inspections and prepare design for temporary corrective repair as required. Duties include field audit and review of reports prepared by consultants.

INNOVATIVE ENGINEERING, Toms River, NJ (2001 to 2003)

SENIOR STRUCTURAL ENGINEER, Performed structural analysis and design for wireless telecommunications industry. Designed antenna and steel equipment frames on building rooftops and on grade. Required familiarity with applicable building and design codes such as AISC (steel), ACI (concrete), AITC (timber), NYC Building Code, IBC and BOCA Codes, and industry specifications such as EIA/TIA design standards. Qualified existing structures for additional loading. Used Staad.Pro frame analysis program and wrote programs in MS Excel for quick analysis of various steel and masonry configurations. Used Autocad 2000.

STRATUS ENGINEERING, Cranbury, NJ (2000 to 2001)

PROJECT MANAGER / STRUCTURAL ENGINEER, Managed project team of architects, structural engineers, designers and drafters for design and preparation of drawings and specifications for major structural modifications to the East River Power Plant in New York City. Included checking and verification of Staad.Pro computer model input for structural frame analysis. Designed a reinforced concrete, explosion-resistant gas compressor room.

Also performed manual structural analyses for various concrete and steel structures for Consolidated Edison.

PORT AUTHORITY OF NEW YORK AND NEW JERSEY, Jersey City, NJ (1988 to 2000)

ENGINEERING PROJECT MANAGER / STRUCTURAL TASK LEADER, Engineering Dept.; Managed preparation of multi-discipline construction plans and specifications for the repair of deteriorated runways, taxiways, railroad facilities, roadways, bridges, buildings and tunnels at various PA facilities, Develop baseline schedules, cost plans and project scope through contact and negotiations with client Line Department. Duties included preparation of "short form" contracts, reviewing and analyzing bid results, and recommending award of contract. Also managed consultants in performing the above mentioned design services, to ensure that contract documents are prepared in conformance with Port Authority standards, on time and within budget. Coordinated several groups in project effort including other governmental agencies and outside interests.

Port Authority Awards:

• "James G. Hellmuth Unit Citation Award", 1998 for the Rehabilitation of Runway 4R-22L, Newark Int. Airport; Managed and coordinated project team from all Engineering Department divisions for successful completion of record setting overlay of deteriorating runway in preparation of new, larger aircraft. Required presentations to, and coordination with airline representatives to obtain 30% reduction in aircraft departures to allow for an unprecedented continuous two-week closure in lieu of a 6-9 month intermittent nighttime closure.

• "EngineeringExcellence Award", 1997 for five years perfect attendance. AA-5

uyster ureeK kenerating zration unit i Correspondence No.: RS-13-065 MICHAEL J. HAND PROJECT MANAGER, STRUCTURAL INTEGRITY UNIT, RAIL PLANNING DIV., PATH; Provided Project Management (Stage I-IV) services essential to the structural integrity, maintenance and rehabilitation of PATH structures. Addressed priority structural repairs through implementation of the major works program. Responded to real and perceived structural integrity issues presented by the facility, with follow-up for resolution as required.

Acted as principal link between facility, Engineering Department, and other departments and outside entities.

STONE AND WEBSTER ENGINEERING CORP., New York, NY (July 1987 to November 1987)

STRUCTURAL ENGINEER; Qualification and analysis of pipe supports by manual calculation and computer analysis for the Sequoia Nuclear Power Plant, Tennessee Valley Authority. Included use of ASME Codes, AISC and AWS Specifications and STRUDL computer program frame analysis.

GIBBS & HILL, INC., New York, NY (1985 to 1987)

ASSOCIATE STRUCTURAL ENGINEER, FIELD ENGINEER; Qualified various steel frames and connections for the Comanche Peak Nuclear Power Plant, TX. Position required manual calculation and computer analysis capabilities as well as analysis by computer program. At the Susquehanna Steam Electric Station, PA, checked structural integrity of changes made to cable tray supports. Routed and designed supports for electrical conduit and process piping.

NUCLEAR POWER SERVICES, INC., Secaucus, NJ (1981 to 1985)

STRUCTURAL ENGINEER; Determined loads in building steel due to pipe and conduit supports under seismic conditions for the Braidwood Nuclear Power Plant, Braidwood, I1l. Position required structural analysis capabilities as mentioned above.

FIELD ENGINEER; Resolved pipe support field installation problems presented by the craft at the Byron Nuclear Power Plant, Byron Ill., and the Perry Nuclear Power Plant, North Perry, OH. Position required a familiarity with pipe support erection tolerances, installation procedures, and welding methods and procedure (including AWS standards). Checked structural integrity of changes made to pipe supports by manual calculation. Also performed as-built field inspections on installed pipe supports and piping systems to ensure compliance with NRC I.E.Bulletin 79-14 specifications.

STRUCTURAL DESIGN ENGINEER; Analyzed pipe supports by manual calculation to ensure structural integrity using working stress methods with reference to ASME Section III Codes and AISC Specifications. Included STRUDL and BASEPLATE program computer modeling.

CERTIFICATIONS and TRAINING Seismic Capability Engineer (SCE) Situational Leadership Training - Port Authority of NY & NJ Engineer-In-Training (E-I-T) Certificate Management Training Series - Port Authority of NY & NJ Pursuing PE license in New Jersey STAAD.PRO Training Certificate AFFILIATIONS American Society of Civil Engineers, American Institute of Steel Construction National Society of Professional Engineers Toastmasters International (Communication and Leadership Training) - Past President The Engineering Advisory Group (at PANYNJ) - Past President VOLUNTEER SERVICE: Boy Scouts of America - Assistant Scoutmaster St. Rose of Lima Catholic Church - Building Committee, Liturgical Minister AA-6

ý,Certf has Compleftet reening andSeimsic C

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Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Appendix A C Seismic Walkdown Checklists (SWCs)

Table AC-1 provides a description of each item, anchorage verification confirmation, a list of Area Walk-By Checklists associated with each item and comments of each Seismic Walkdown Checklist. All items in Table AC-1 were deferred items listed in Table E-1 of this report, and were accessible during the follow-on walkdowns.

Table AC-2 provides a description of each item subject to supplemental internal inspections. All items in Table AC-2 were electrical cabinets subject to Supplemental Internal Inspections as listed in Table E-2 of this report, and were accessible without safety and operational hazard.

AC-1

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Table AC-1. Summary of Seismic Walkdown Checklists Anchorage Area Walk Component ID DESCRIPTION Configuration Comments Confirmed? by SAFETY RELIEF VALVE NR28D N/A V-1-160 (SOUTH HEADER) 31 This is an In-Line Component SAFETY RELIEF VALVE NR28H N/A V-1-164 (NORTH HEADER) 32 This is an In-Line Component ELECTROMATIC RELIEF VALVE N/A V-1-173 NR108-A(SOUTH HEADER) 31 This is an In-Line Component ELECTROMATIC RELIEF VALVE N/A V-1-175 NR108-C(NORTH HEADER) 32 This is an In-Line Component ELECTROMATIC RELIEF VALVE N/A V-1-177 NR108-E(SOUTH HEADER) 31 This is an In-Line Component CU INLET ISOLATION VALVE FROM N/A V-16-1 REACTOR VESSEL 31 This is an In-Line Component V-1-106 MAIN STEAM LINE A DRAIN VALVE N/A 30 This is an In-Line Component MAIN STEAM LINEA OUTLET N/A V-1-7 ISOLATION VALVE(NS03-A) 30 This is an In-Line Component MSIV'S SOLENOID AIR VALVE & Not one of the 50% for which an anchor RK-411-1 EQUIPMENT MOUNTING RACK N/A 29 configuration verification is required MAIN STEAM LINE'B' OUTLET N/A V-1-10 ISOLATION VALVE(NS04-B) 29 This is an In-Line Component MCC 1A21 460V,3PH,3W,60HZ FOR YES Supports are consistent with Drawing 1A21-460V TURBINE BUILDING 9 3E-153-38-016 Rev 0 MCC 1A21B 460V,3P,3W,60HZ FOR REACTOR BUILDING Supports are consistent with 1A21 B-460V 7 Calculation C-1302-732-5320-014 Rev 0 MCC 1A23 460V,3PH,3W,60HZ FOR See Seismic Qualification SQ-OC-1A23-REACTOR BUILDING YES 460V-MCC Rev 1. Upper supports are consistent with Drawing 3E-153-38-016 1A23-460V 9 Rev 0 460V UNIT SUBSTATION 1A2 FOR REACTOR BUILDING See Seismic Qualification S,-OC-1A2-460V-USS Rev 2. Partial Inspection opened one panel, however, could see approximately 1/3 of the total anchorages. No issues found.

Therefore, the anchor Inspection is met. The other panels would not be opened by ops due to the fact that, this IA2-460V Iis always energized.

lC 4160V BUS 1C SWITCHGEAR YES 28 See SQ-OC-1C-4160V Rev 03 AC-2

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Table AC-2. Summary of Seismic Walkdown Checklists for Supplemental Internal Inspections Component ID DESCRIPTION BTCHG Cl 'C' STATION BATTERY SOLID STATE STATIC CHARGER Cl DG-1 BATTERY CHARGER DIESEL GENERATOR UNIT #1 BATTERY CHARGER DG-1 SWGR DIESEL GENERATOR #1 UNIT SWITCHGEAR ER18A CORE SPRAY/AUTO DEPRESS'N SYSTEM RELAY LOGIC PANEL LSP-1A2 LOCAL SHUTDOWN PANEL- USS 1A2 PUMP/BREAKER CONTROL 1A21A-460V MCC 1A21A 460V, 3P, 3W, 60HZ, FOR REACTOR BUILDING AC-3

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-160 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

SAFETY RELIEF VALVE NR28D (SOUTH HEADER)

Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): DW, 46.00 ft, 31 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Not Applicable

4. Is the anchorage free of visible cracks in the concrete near the anchors? Not Applicable

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-4

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 3 Status: Ml N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-160 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

SAFETY RELIEF VALVE NR28D (SOUTH HEADER)

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments See Seismic Qualification SQ-OC-V-1-0160 Rev 0 Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AC-5

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 3 Status: MII N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-160 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

SAFETY RELIEF VALVE NR28D (SOUTH HEADER)

IMG_4478 IMG_4479 AC-6

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-164 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

SAFETY RELIEF VALVE NR28H (NORTH HEADER)

Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): DW, 46.00 ft, 32 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Not Applicable

4. Is the anchorage free of visible cracks in the concrete near the anchors? Not Applicable

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-7

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 3 Status: MI- N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-164 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

SAFETY RELIEF VALVE NR28H (NORTH HEADER)

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments See Seismic Qualification SQ-OC-V-1-0164 Rev 0 Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AC-8

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 3 Status: M-* N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-164 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

SAFETY RELIEF VALVE NR28H (NORTH HEADER)

IMG_4486 IMG_4487 AC-9

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 3 Status: F-] N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-173 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-A(SOUTH HEADER)

Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): DW, 46.00 ft, 31 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Not Applicable

4. Is the anchorage free of visible cracks in the concrete near the anchors? Not Applicable

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-10

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 3 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-173 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-A(SOUTH HEADER)

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments See Seismic Qualification SQ-OC-V-1-0173 Rev 0 Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AC-11

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-173 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-A(SOUTH HEADER)

IM(,._4489 IMU.44813 AC-12

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-175 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-C(NORTH HEADER)

Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): DW, 46.00 ft, 32 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Not Applicable

4. Is the anchorage free of visible cracks in the concrete near the anchors? Not Applicable

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-13

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 4 Status: M-Z N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-175 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-C(NORTH HEADER)

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Conduit Box partiallyopen. Peroperations this is being worked on during the Outage and will be repairedpriorto start-up.

Comments See Seismic Qualification SQ-OC-V-1-0175 Rev 0 Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AC-14

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-175 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-C(NORTH HEADER)

IMG_4482 IMG_4483 AC-15

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-175 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-C(NORTH HEADER)

IMG_4485 IMG_4484 AC- 16

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-177 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-E(SOUTH HEADER)

Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): DW, 46.00 ft, 31 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Not Applicable

4. Is the anchorage free of visible cracks in the concrete near the anchors? Not Applicable

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-17

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-177 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-E(SOUTH HEADER)

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Minor damage to flexible conduit. Per operations this is being worked on during the Outage and will be repairedpriorto start-up.

Comments See Seismic Qualification SQ-OC-V-1-0177 Rev 0 Evaluated by: Mark S. Etre Date: 1012612012

• Seth W. Baker 10/26/2012 Photos AC-18

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-177 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-E(SOUTH HEADER)

IMG_4474 IMG_4475 AC-19

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 4 Status: [-Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1 -1i77 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

ELECTROMATIC RELIEF VALVE NR108-E(SOUTH HEADER)

IMG_4476 IMG_4477 AC-20

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-16-1 Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

Description:

CU INLET ISOLATION VALVE FROM REACTOR VESSEL Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): DW, 46.00 ft, 31 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Not Applicable

4. Is the anchorage free of visible cracks in the concrete near the anchors? Not Applicable

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-21

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-16-1 Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

Description:

CU INLET ISOLATION VALVE FROM REACTOR VESSEL Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments See Seismic Qualification SQ-OC-V-16-0001 Rev 0 Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AC-22

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 4 Status: N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-16-1 Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

Description:

CU INLET ISOLATION VALVE FROM REACTOR VESSEL IMG-4471 IMG-4472 IMG_4473 AC-23

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-16-1 Equipment Class: (8) Motor-Operated and Solenoid-Operated Valves Equipment

Description:

CU INLET ISOLATION VALVE FROM REACTOR VESSEL AC-24

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-106 Equipment Class: (0) Other Equipment

Description:

MAIN STEAM LINE 'A' DRAIN VALVE Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): DW, 23.00 ft, 30 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Not Applicable

4. Is the anchorage free of visible cracks in the concrete near the anchors? Not Applicable

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-25

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 3 Status: M-J N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-106 Equipment Class: (0) Other Equipment

Description:

MAIN STEAM LINE A DRAIN VALVE Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments ECR Number OC 09-00484 002 Modified this motor operated valve to a manual valve.

Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AC-26

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 3 Status: M-i N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-106 Equipment Class: (0) Other

niiinmant rflarwrinfinn" MAIN .TF:AMA I INF 'A' rfRAIN VAI VEI IMG_4466 IMG_4465 AC-27

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-7 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

MAIN STEAM LINE'A' OUTLET ISOLATION VALVE(NS03-A)

Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): DW, 23.00 ft, 30 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Not Applicable

4. Is the anchorage free of visible cracks in the concrete near the anchors? Not Applicable

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-28

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-7 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

MAIN STEAM LINE' OUTLET ISOLATION VALVE(NS03-A)

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes Nearby rack has adequate clearanceto valve.

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

Overhead lines well supported

9. Do attached lines have adequate flexibility to avoid damage? Yes Welded airlinesinto valve provide ductile flexibility. The valve is failsafe, so rupture of air is no issue.

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments See Seismic Qualification SQ-OC-V-1-0007 Rev 1 Valve packing is leaking. Per operations this is being worked on during the Outage and will be repaired prior to start-up.

Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 AC-29

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-7 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

MAIN STEAM LINE'A' OUTLET ISOLATION VALVE(NS03-A)

Photos 1MG 4461 IMr, AAR9 IMG_4463 IM(_4464 AC-30

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-7 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

MAIN STEAM LINEA OUTLET ISOLATION VALVE(NS03-A)

AC-31

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: RK-411-1 Equipment Class: (18) Instruments on Racks Equipment

Description:

MSIV'S SOLENOID AIR VALVE & EQUIPMENT MOUNTING RACK Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): RB, 23.00 ft, 29 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks in the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-32

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: RK-411-1 Equipment Class: (18) Instruments on Racks Equipment

Description:

MSIV'S SOLENOID AIR VALVE & EQUIPMENT MOUNTING RACK Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments See Seismic Qualification SQ-OC-RK-41 1-001 Rev 0 General housekeeping concerns regarding transient materials throughout area. No soft targets in the area. Per discussions with operations all of the housekeeping concerns will be resolved prior to start-up. Scaffolding is installed per the Oyster Creek Scaffolding procedures and is Seismically restrained.

Surface oxidation present, but no apparent loss of cross section or strength.

Rack is adequately braced to wall.

Evaluated by: Mark S. Etre Date: 10/26/2012 AC-33

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: RK-411-1 Equipment Class: (18) Instruments on Racks Equipment

Description:

MSIV'S SOLENOID AIR VALVE & EQUIPMENT MOUNTING RACK Seth W. Baker 10/26/2012 Photos IMG_4442 IMG 4443 IMG_4444 IMIU...444q AC-34

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: RK-41 1-1 Equipment Class: (18) Instruments on Racks inmanf rflarrintinn" MSIV'S SOLENOID AIR VALVE & EQUIPMENT MOUNTING RACK

-M -ý FW IIAf*' AAAR IMG_4448 IMG_4449 AC-35

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-10 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

MAIN STEAM LINE'B' OUTLET ISOLATION VALVE(NS04-B)

Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): RB, 23.00 ft, 29 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% No of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Not Applicable

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Not Applicable

4. Is the anchorage free of visible cracks in the concrete near the anchors? Not Applicable

5. Is the anchorage configuration consistent with plant documentation? (Note: Not Applicable This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-36

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-10 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

MAIN STEAM LINE'B' OUTLET ISOLATION VALVE(NS04-B)

Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Comments See Seismic Qualification SQ-OC-V-1-0010 Rev 1 General housekeeping concerns regarding transient materials throughout area. No soft targets in the area. Per discussions with operations all of the housekeeping concerns will be resolved prior to start-up. Scaffolding is installed per the Oyster Creek Scaffolding procedures and is Seismically restrained.

Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 AC-37

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 4 Status: r N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-10 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

MAIN STEAM LINE'B' OUTLET ISOLATION VALVE(NS04-B)

Photos IRAr' AAan IRAIr AAr4 IMG_4452 IMG_4453 AC-38

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 4 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: V-1-10 Equipment Class: (7) Fluid-Operated Valves Equipment

Description:

MAIN STEAM LINE'B' OUTLET ISOLATION VALVE(NS04-B)

IMG-4454 IMIi qq0 AC-39

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21 460V,3PH,3W,60HZ FOR TURBINE BUILDING Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): RB, 23.00 ft, 09 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% Yes of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks in the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-40

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21 460V,3PH,3W,60HZ FOR TURBINE BUILDING Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Performed internalinspection and did not find any OtherAdverse Conditions.

The lower and side panels were opened. The Breakers were not removed.

There were no issues found in the areas opened. There is no reason to believe that the areasin the buckets pose an issue and the intent of reviewing Other Adverse Conditions are satisfied.

Comments See Seismic Qualification SQ-OC-1A21-460V-MCC Rev 0 Supports are consistent with Drawing 3E-153-38-016 Rev 0 Calculation C-1 302X-322C-A06 qualifies the Oyster Creek safety-related masonry walls for seismic to address NRC IE Bulletin 80-11.

Evaluated by: Mark S. Etre Date: 10/26/2012 AC-41

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21 460V,3PH,3W,60HZ FOR TURBINE BUILDING Seth W. Baker 10/26/2012 Photos IRA-2 tnAO IMG_0945 IMG_4505 AC-42

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21-460V Equipment Class: (1) Motor Control Centers Fnhiinmant r'tz_..rintinn" MCC 1A21 460V,3PH,3W,60HZ FOR TURBINE BUILDING IRA~r-- AJ;NiR IftAt Akn-7 IMG_4508 IMG_4510 AC-43

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 5 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21-460V Equipment Class: (1) Motor Control Centers ni iinmn nt rlct-rintinn" MCC 1A21 460V,3PH,3W,60HZ FOR TURBINE BUILDING IMU_4511 IMG_4512 IMG-4513 SQUG SEWS AC-44

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 6 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21 460V,3PH,3W,60HZ FOR TURBINE BUILDING EBASCO SERVICES INCORPORATED I O Two World Trade CGente&.

New York. N.Y. 10048 4

April 29, 1981 GPU Services Incorporated Attention: Mr. Leon Garibian 100 Interpace Parkway Parsippany, NJ 07054

Dear Leon:

Re: OYSTER CREEK NUCLEAR STATION FINAL SUBMITTAL OF MASONRY WALL EVALUATION CALCULATION BOOKS I am sending to you together with this letter, 20 volumes of calculation books and 11 volumes of computer output. This will mark the end of our involvement for the re-evaluation of the Safety-Related Concrete Masonry Walls as required by NRC IE Bulletin 80-11.

Should you have any questions regarding the calculations and sketches, please do not hestitate to call. We will be glad to help.

Very truly yours, E Odar Assistant Chief Civil Engineer GW:dl cc: K D Chiu G Wu C1302X322CA06 VOL 1, 19810427, REEVALUATION OF CONCRETE MASONRY WALL NRC IE BULLETIN 80-11 GENERAL AC-45

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21B-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21B 460V,3P,3W,60HZ FOR REACTOR BUILDING Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): RB, 23.00 ft, 07 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% Yes of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks in the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-46

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21B-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21B 460V,3P,3W,60HZ FOR REACTOR BUILDING Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Performedinternal inspection and did not find any Other Adverse Conditions.

The lower and side panels were opened. The Breakers were not removed.

There were no issues found in the areas opened. There is no reason to believe that the areas in the buckets pose an issue and the intent of reviewing Other Adverse Conditions are satisfied.

Comments See Seismic Qualification SQ-OC-1A21B-460V-MCC Rev 0 Supports are consistent with Calculation C-1 302-732-5320-014 Rev 0 MCC is approximately 3" from large square column, the relative stiffness of the MCC is in the strong direction, it is unlikely to impact the column.

Evaluated by: Mark S. Etre Date: 10/26/2012 AC-47

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21B-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A2lB 460V,3P,3W,60HZ FOR REACTOR BUILDING Seth W. Baker 10/26/2012 Photos I MusUvof IMG_4524 AC-48

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21 B-460V Equipment Class: (1) Motor Control Centers Fnuinment Descrintinn: MCC 1A21B 460V,3P,3W,60HZ FOR REACTOR BUILDING IMG_4527 IMG_4528 AC-49

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 5 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: (A21 B460V Equipment Class: (1) Motor Control Centers Eauioment Descrintion: MCC 1A21B 460V,3P,3W,60HZ FOR REACTOR BUILDING Inn( ; 4 IMGi.4531 IMG_4532 AC-50

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 6 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A21B-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21B 460V,3P,3W,60HZ FOR REACTOR BUILDING AC-51

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A23-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A23 460V,3PH,3W,60HZ FOR REACTOR BUILDING Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): RB, 23.00 ft, 09 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% Yes of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks in the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-52

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A23-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A23 460V,3PH,3W,60HZ FOR REACTOR BUILDING Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Performed internalinspection and did not find any OtherAdverse Conditions.

The lower and side panels were opened. The Breakers were not removed.

There were no issues found in the areas opened. There is no reason to believe that the areasin the buckets pose an issue and the intent of reviewing Other Adverse Conditions are satisfied.

Comments See Seismic Qualification SQ-OC-1A23-460V-MCC Rev 1 Upper supports are consistent with Drawing 3E-153-38-016 Rev 0 Calculation C-1 302X-322C-A06 qualifies the Oyster Creek safety-related masonry walls for seismic to address NRC IE Bulletin 80-11.

Evaluated by: Mark S. Etre Date: 10/26/2012 AC-53

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A23-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A23 460V,3PH,3W,60HZ FOR REACTOR BUILDING Seth W. Baker 10/26/2012 Photos IMG_0952 IMG_0955 AC-54

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 6 Status: 1111 N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A23-460V Equipment Class: (1) Motor Control Centers IEauinment Depcrintinn: MCC 1A23 460V,3PH,3W,60HZ FOR REACTOR BUILDING IMU_4b I( IM(U_4516 IMG_4519 IMG_4520 AC-55

Oyster Creek Generating Station Unit I Correspondence No.: RS-13-065 Sheet 5 of 6 Status: M N U Seism Ic Walkdown Checklist (SWC)

Equipment ID No.: 1A23-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A23 460V,3PH,3W,60HZ FOR REACTOR BUILDING IM(._.4b21 IMU_4522 SQUG SEWS AC-56

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 6 of 6 Status: Y] N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A23-460V Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A23 460V,3PH,3W,60HZ FOR REACTOR BUILDING FAAS0o SVIwCES IMcORPORATE0

-W~IGO~rn 4!

Aprl 29, 1961 GP'JJServices lacotporaice Ategirlonw Mr. 1.eoi Garjblaft 100 Iflterpoco ?akuat.jiy 1fOrLpplany, N-3 07054 Dvar Leon:

Ll": OYSTE.R CREIK ?dJCLFAR StATIO MflAL SUiM2flAL OF IFASONRY WAM.j, 9VA1wrio* CALCUx,&TzOL ECOyS t am sending to yutogothoe vijttb his lettc!-ý20 volumn of colcular'ion hoo~s nitt 11 Vol~umes of computer aoutput. This. will mark the involvamftc for the re-evaluation of thie Sfoty-Rt~1eted end of aue Concreto Kuqonry Walls as rcequired by HaC IZ Bulle~tin a0-il, Should you have any questions Te~arding the calculations and sketches, please do mno fiemtitllte to call, W~e wdl1 be glamd to help.

Vey nluy yours.

' I. J#

A~ssistaltt chief Civil ansiueer GI~dl CC: K D Chfu C'Wi, 0

C1302X322CA06 VOL 1, 19810427, REEVALUATION OF CONCRETE MASONRY WALL NRC IE BULLETIN 80-11 GENERAL AC-57

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 6 Status: M-j N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A2-460V Equipment Class: (2) Low Voltage Switchgear Equipment

Description:

460V UNIT SUBSTATION 1A2 FOR REACTOR BUILDING Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): RB, 23.00 ft, 11 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% Yes of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks in the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-58

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A2-460V Equipment Class: (2) Low Voltage Switchgear Equipment

Description:

460V UNIT SUBSTATION 1A2 FOR REACTOR BUILDING Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

PartialInspection opened one panel, however, could see approximately 1/3 of the total internals. The Breakers were not removed. There were no issues found in the areas opened. The internal inspections were verified for at least 1/3 of the space that could be seen with the door open.

Therefore, the intent of no other adverse conditions is met. The other panels would not be opened by ops due to the fact that, this is always energized.

Comments Nearby masonry block Wall is braced. Calculation C-1 302X-322C-A06 qualifies the Oyster Creek safety-related masonry walls for seismic to address NRC IE Bulletin 80-11. The walls are modified with bracing. Gap between large angle brace and wall is /" will still confine the wall.

See Seismic Qualification SQ-OC-1A2-460V-USS Rev 2 One side panel was opened. The Breakers were not removed. There were no issues found in the areas opened. The internal Anchor Bolts were verified for at least 1/3 of the space that could be seen with the door open. There is no reason to believe that the other anchors pose an issue and the intent of reviewing anchorage AC-59

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A2-460V Equipment Class: (2) Low Voltage Switchgear Equipment

Description:

460V UNIT SUBSTATION 1A2 FOR REACTOR BUILDING is satisfied.

Calculation C-1 302X-322C-A06 qualifies the Oyster Creek safety-related masonry walls for seismic to address NRC IE Bulletin 80-11.

Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos IMG_0847 IMG_0849 IMG_0850 IMG_0853 AC-60

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 6 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A2-460V Equipment Class: (2) Low Voltage Switchgear Equipment

Description:

460V UNIT SUBSTATION 1A2 FOR REACTOR BUILDING IMG_4541 IMG_4542 AC-61

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 5 of 6 Status: MI- N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1A2-460V Equipment Class: (2) Low Voltage Switchgear Equipment

Description:

460V UNIT SUBSTATION 1A2 FOR REACTOR BUILDING IMU_4b43 IMG_4544 SQUG SEWS AC-62

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 6 of 6 Status: -qN U Seismic Walkdown Checklist (SWC)

Equipment ID No.: IA2-460V Equipment Class: (2) Low Voltage Switchgear Equipment

Description:

460V UNIT SUBSTATION 1A2 FOR REACTOR BUILDING 56A8OO WA~VICES INCOR9ORATED 4

April 29, 1981 GFU Seirvior c o~og l.

Atronption: Ktr. 14en Garibialt 100 Interpaco Park~y D'car Leon:

1-: OYSTER CREEKt SUCLWA StATIONI PIIIAL S=427TrAL OF )%Aý.ey WAALL.

£ at #etdjn 8 to you togcthar vuih thts letter,20 voluman ot celculaon~jo bo04 and 1I V*ouMea of ¢OMpUCer output. This will mark tbe ai*d QC our in-vvet fr tite re-evatwon vi the Saf*ty-Relatd eConcret. XKsonry Wells as requiLed by Fac IX Ullotin 80-11÷ 51hould you hiave *ay qu:estions re Rrdino the .caljuatiovo and Skete;hea pleose do WE heatitoteo call. We wIl be glad to help.

Very t"lly yoiurs, A~tmet;*3Lt- ChiX. Civil Engs.ncee Cli: dl cc: K D Chin 0 WaX C1302X322CA06 VOL 1, 19810427, REEVALUATION OF CONCRETE MASONRY WALL NRC IE BULLETIN 80-11 GENERAL AC-63

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 8 Status: M N U Seismic Walkdown Checklist (SWC)

EquipmentlD No.: 1C Equipment Class: (3) Medium Voltage Switchgear Equipment

Description:

4160V BUS 1C SWITCHGEAR Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): TB, 23.00 ft, 28 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% Yes of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks in the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

AC-64

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 8 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1C Equipment Class: (3) Medium Voltage Switchgear Equipment

Description:

4160V BUS 1C SWITCHGEAR Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

Other Adverse Conditions

11. Have you looked for and found no adverse seismic conditions that could Yes adversely affect the safety functions of the equipment?

Internal inspections have been performed and no other adverse conditions have been found.

Comments See SQ-OC-1C-4160V Rev 03 Anchorage within cabinet has been inspected.

Anchor for breaker guide rails on floor is missing nut inside cubicle AL P. The guide rails are not part of the cabinet frame and serve no structural purpose. Therefore there is no seismic issue.

Evaluated by: Mark S. Etre Date: 10/26/2012 1 Seth W. Baker 10/26/2012 AC-65

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 8 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1C Equipment Class: (3) Medium Voltage Switchgear Equipment

Description:

4160V BUS lC SWITCHGEAR Photos IMG 1092 IMG_1093 IMG_1094 AC-66

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 8 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1C Equipment Class: (3) Medium Voltage Switchgear Equipment

Description:

4160V BUS lC SWITCHGEAR I RAf.:* 11I MA IRII*A** A[ --*A-IMG_4546 IMG_4547 AC-67

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 5 of 8 Status: I N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1C Equipment Class: (3) Medium Voltage Switchgear Equipment

Description:

4160V BUS 1C SWITCHGEAR IMG_4548 IMG_4549 IMG_4550 IMG_4551 AC-68

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 6 of 8 Status: MI- N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1C Equipment Class: (3) Medium Voltage Switchgear Equipment

Description:

4160V BUS lC SWITCHGEAR IMG_4552 IMG_4553 AC-69

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 7 of 8 Status: MI- N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1C Equipment Class: (3) Medium Voltage Switchgear Equipment

Description:

4160V BUS lC SWITCHGEAR IMG_4554 IMG_4555 AC-70

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 8 of 8 Status: M N U Seismic Walkdown Checklist (SWC)

Equipment ID No.: 1C Equipment Class: (3) Medium Voltage Switchgear Equipment

Description:

4160V BUS 1C SWITCHGEAR IMG_4556 AC-71

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 4 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: BTCHG C1 (SEE APPENDIX C PAGE C-37)

Equipment Class: (16) Inverters Equipment

Description:

'C' STATION BATTERY SOLID STATE STATIC CHARGER Cl Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): TB, 23.00 ft, 26 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50% Yes of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware? Yes

3. Is the anchorage free of corrosion that is more than mild surface oxidation? Yes

4. Is the anchorage free of visible cracks in the concrete near the anchors? Yes

5. Is the anchorage configuration consistent with plant documentation? (Note: Yes This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of Yes potentially adverse seismic conditions?

SEE SWC IN APPENDIX C FOR RESPONSES Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Yes

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and Yes masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage? Yes

10. Based on the above seismic interaction evaluations, is equipment free of Yes potentially adverse seismic interaction effects?

SEE SWC IN APPENDIX C FOR RESPONSES AC-72

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 4 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: BTCHG C1 (SEE APPENDIX C PAGE C-37)

Equipment Class: (16) Inverters Equipment

Description:

'C' STATION BATTERY SOLID STATE STATIC CHARGER Cl Other Adverse Conditions (SUPPLEMENTAL CABINET INSPECTION)

11. Have you looked for and found no adverse seismic conditions that could adversely affect the safety functions of the equipment?

a. Internalcomponents secured? (i.e. no loose or missing fasteners) Yes*

b. Are adjacentcabinets secured together? N/A

c. No other adverse seismic conditions? Yes*

Internal inspections have been performed and no other adverse conditions have been found.

Comments See SQ-OC-BT CHG Cl & C2 Rev 00 Equipment has External anchorage.

Comments See SQ-OC-BT CHG Cl & C2 Rev 00 External Anchorage was completed during online walk down.

8/22/2012 &

12/10/12* *for Evaluated by: Mark S. Etre Date: Internals inspection.

Seth W. Baker Date: 8/22/2012

)0"

• 12/10/12 D' for Internals Wing Ho Date: inspection Only.

Photos AC-73

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 4 Status: Y N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: BTCHG C1 (SEE APPENDIX C PAGE C-37)

Equipment Class: (16) Inverters Equipment

Description:

'C' STATION BATTERY SOLID STATE STATIC CHARGER C1 IAA^ 4 ,00 IRAt2- 4rl1, IMG_1072 IMG_1073 AC-74

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 4 Status: MI- N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: BTCHG Cl (SEE APPENDIX C PAGE C-37)

Equipment Class: (16) Inverters Equipment

Description:

'C' STATION BATTERY SOLID STATE STATIC CHARGER Cl IMG_1506 AC-75

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 3 Status: Y N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: DG-1 BATTERY CHARGER (SEE APPENDIX C PAGE C- 75)

Equipment Class: (16) Inverters Equipment

Description:

DIESEL GENERATOR UNIT #1 BATTERY CHARGER Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): DG BLDG, 23.00 ft, 01 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50%

of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware?

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?

5. Is the anchorage configuration consistent with plant documentation? (Note:

This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

SEE SWC IN APPENDIX C FOR RESPONSES Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

SEE SWC IN APPENDIX C FOR RESPONSES AC-76

2 Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 3 Status: Mi- N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: DG-1 BATTERY CHARGER (SEE APPENDIX C PAGE C- 75)

Equipment Class: (16) Inverters Equipment

Description:

DIESEL GENERATOR UNIT #1 BATTERY CHARGER Other Adverse Conditions (SUPPLEMENTAL CABINET INSPECTION)

11. Have you looked for and found no adverse seismic conditions that could adversely affect the safety functions of the equipment?

a. Internal components secured? (i.e. no loose or missing fasteners) Yes

b. Are adjacentcabinets secured together? N/A

c. No other adverse seismic conditions? Yes Comments

• (Cover Panelremoved) have been performed and no other adverse conditions have been found.

See SQ-OC-M-39-001 Rev 06 Equipment has external anchorage.

Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos IMUj 15h4 IMU 1160 AC-77

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: DG-1 BATTERY CHARGER (SEE APPENDIX C PAGE C- 75)

Equipment Class: (16) Inverters FnaiinmnPnt 1)pQrp-rntinn" "IF5FI (FNFPATCR I INIT #1 RATTFRV (-IAR(F:R IM5 11 d IMWj_13b AC-78

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 5 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: DG-1 SWGR (SEE APPENDIX C PAGE C-78)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

Description:

DIESEL GENERATOR #1 UNIT SWITCHGEAR Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): DG BLDG, 23.00 ft, 01 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50%

of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware?

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?

5. Is the anchorage configuration consistent with plant documentation? (Note:

This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

SEE SWC IN APPENDIX C FOR RESPONSES Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

SEE SWC IN APPENDIX C FOR RESPONSES AC-79

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 5 Status: -i] N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: DG-1 SWGR (SEE APPENDIX C PAGE C-78)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

Description:

DIESEL GENERATOR #1 UNIT SWITCHGEAR Other Adverse Conditions (SUPPLEMENTAL CABINET INSPECTION)

11. Have you looked for and found no adverse seismic conditions that could adversely affect the safety functions of the equipment?

a. Internalcomponents secured? (i.e. no loose or missing fasteners) Yes

b. Are adjacentcabinets secured together? Yes

c. No otheradverse seismic conditions? Yes Comments Equipment has internal and external anchorage.

Evaluated by: Mark S. Etre Date: 10/26/2012 SSeth W. Baker 10/26/2012 Photos 1MG_1190 IMG_1195 AC-80

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 5 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: DG-1 SWGR (SEE APPENDIX C PAGE C-78)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets Enuinment Descrintion: DIESEL GENERATOR #1 UNIT SWITCHGEAR Iu1 4 11dt IUI(-..; 1TiKV IMG_1363 IMG_1364 AC-81

7 Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 5 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: DG-1 SWGR (SEE APPENDIX C PAGE C-78)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets Fnaiinm*nt ntzAqrrintinn" DIESEL GENERATOR #1 UNIT SWITCHGEAR IM(i_135i5 1MG_1366 AC-82

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 5 of 5 Status: MI N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: DG-1 SWGR (SEE APPENDIX C PAGE C-78)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets Fnnuinmnnt npqrrintinn" DIESEL GENERATOR #1 UNIT SWITCHGEAR IMW3137i IMU 1368 AC-83

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 4 Status: M-I N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: ER18A (SEE APPENDIX C PAGE C-87)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

Description:

CORE SPRAY/AUTO DEPRESS'N SYSTEM RELAY LOGIC PANEL Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): RB, 23.00 ft, 12 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50%

of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware?

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?

5. Is the anchorage configuration consistent with plant documentation? (Note:

This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

SEE SWC IN APPENDIX C FOR RESPONSES Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

SEE SWC IN APPENDIX C FOR RESPONSES AC-84

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 4 Status: EM N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: ER18A (SEE APPENDIX C PAGE C-87)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

Description:

CORE SPRAY/AUTO DEPRESS'N SYSTEM RELAY LOGIC PANEL Other Adverse Conditions (SUPPLEMENTAL CABINET INSPECTION)

11. Have you looked for and found no adverse seismic conditions that could adversely affect the safety functions of the equipment?

a. Internal components secured? (i.e. no loose or missing fasteners) Yes

b. Are adjacent cabinets secured together? Yes

c. No other adverse seismic conditions? Yes Comments See Seismic Qualification SQ-OC-ER-18A Rev 1 Calculation C-1 302X-322C-A06 qualifies the Oyster Creek safety-related masonry walls for seismic to address NRC IE Bulletin 80-11.

Equipment has External anchorage.

Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AC-85

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-1 3-065 Sheet 3 of 4 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: ER18A (SEE APPENDIX C PAGE C-87)

Equipment Class: (20) Instrumentation and Control Panels and Cabir lets Equipment

Description:

CORE SPRAY/AUTO DEPRESS'N SYSTEM REL AY LOGIC PANEL IMG-0908 IMG_0910 IMG-4514 AC-86

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 4 Status: F-Y N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION Equipment ID No.: ER18A (SEE APPENDIX C PAGE C-87)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets

nliinmant nizer-rintinnm *CP: qPPAVIAI ITr) n1:PPIFq'NM RYV.TF::M PFI: AV I (rI.1 PANIFI IMG_4515 IMG_4516 AC-87

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 3 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTALCABINET INSPECTION Equipment ID No.: LSP-1A2 (SEE APPENDIX C PAGE C- 132)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

Description:

LOCAL SHUTDOWN PANEL- USS 1A2 PUMP/BREAKER CONTROL Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): RB, 23.00 ft, 16 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50%

of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware?

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?

5. Is the anchorage configuration consistent with plant documentation? (Note:

This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

SEE SWC IN APPENDIX C FOR RESPONSES Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

SEE SWC IN APPENDIX C FOR RESPONSES AC-88

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 3 Status: I--Y N U Seismic Walkdown Checklist (SWC) SUPPLEMENTALCABINET INSPECTION Equipment ID No.: LSP-1A2 (SEE APPENDIX C PAGE C- 132)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

Description:

LOCAL SHUTDOWN PANEL- USS 1A2 PUMP/BREAKER CONTROL Other Adverse Conditions (SUPPLEMENTAL CABINET INSPECTION)

11. Have you looked for and found no adverse seismic conditions that could adversely affect the safety functions of the equipment?

a. Internalcomponents secured? (i.e. no loose or missing fasteners) Yes

b. Are adjacent cabinets secured together? N/A

c. No other adverse seismic conditions? Yes Comments Equipment has external anchorage.

See SQ-OC-LSP-1A2 Rev 02 Evaluated by: Mark S. Etre Date: 10/26/2012 SSeth W. Baker 10/26/2012 Photos IMG_1009 IMG_1010 AC-89

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 3 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTALCABINET INSPECTION Equipment ID No.: LSP-1A2 (SEE APPENDIX C PAGE C- 132)

Equipment Class: (20) Instrumentation and Control Panels and Cabinets Equipment

Description:

LOCAL SHUTDOWN PANEL- USS 1A2 PUMP/BREAKER CONTROL IMG_1011 IMG_1015 AC-90

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 6 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION)

Equipment ID No.: 1A21A-460V (SEE APPENDIX C PAGE C-8)

Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21A 460V,3P,3W,60HZ FOR REACTOR BUILDING Project: Oyster Creek SWEL Location (Bldg, Elev, Room/Area): RB, 23.00 ft, 08 Manufacturer/Model:

Instructions for Completing Checklist This checklist may be used to document the results of the Seismic Walkdown of an item of equipment on the SWEL. The space below each of the following questions may be used to record the results of judgments and findings. Additional space is provided at the end of this checklist for documenting other comments.

Anchorage

1. Is anchorage configuration verification required (i.e., is the item one of the 50%

of SWEL items requiring such verification)?

2. Is the anchorage free of bent, broken, missing or loose hardware?

3. Is the anchorage free of corrosion that is more than mild surface oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors?

5. Is the anchorage configuration consistent with plant documentation? (Note:

This question only applies if the item is one of the 50% for which an anchorage configuration verification is required.)

6. Based on the above anchorage evaluations, is the anchorage free of potentially adverse seismic conditions?

SEE SWC IN APPENDIX C FOR RESPONSES Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures?

8. Are overhead equipment, distribution systems, ceiling tiles and lighting, and masonry block walls not likely to collapse onto the equipment?

9. Do attached lines have adequate flexibility to avoid damage?

10. Based on the above seismic interaction evaluations, is equipment free of potentially adverse seismic interaction effects?

SEE SWC IN APPENDIX C FOR RESPONSES AC-91

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 6 Status: EM N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION)

Equipment ID No.: 1A21A-460V (SEE APPENDIX C PAGE C-8)

Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21A 460V,3P,3W,60HZ FOR REACTOR BUILDING Other Adverse Conditions (SUPPLEMENTAL CABINET INSPECTION)

11. Have you looked for and found no adverse seismic conditions that could adversely affect the safety functions of the equipment?

a. Internalcomponents secured? (i.e. no loose or missing fasteners) Yes

b. Are adjacentcabinets secured together? Yes

c. No other adverse seismic conditions? Yes The lower and side panels were opened. The Breakers were not removed. There were no issues found in the areasopened. There is no reason to believe that the areasin the buckets pose an issue and the intent of reviewing Other Adverse Conditions are satisfied.

Comments External Anchorage was completed during online walk down. External anchorage is as documented in SQ-OC-1A2A-460V-MCC External Supports are consistent with Calculation C-1 302-732-5320-014 Rev 0 Equipment has external anchorage.

Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 AC-92

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 6 Status: M* N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION)

Equipment ID No.: IA2IA-460V (SEE APPENDIX C PAGE C-8)

Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21A 460V,3P,3W,60HZ FOR REACTOR BUILDING Photos Photos IMG_0974 IRI./;- IILI/&

IMG_0976 IMG_0978 AC-93

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 6 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION)

Equipment ID No.: 1A21A-460V (SEE APPENDIX C PAGE C-8)

Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC lA21A 460V,3P,3W,60HZ FOR REACTOR BUILDING AC-94

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 5 of 6 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION)

Equipment ID No.: 1A21A-460V (SEE APPENDIX C PAGE C-8)

Equipment Class: (1) Motor Control Centers Equipment

Description:

MCC 1A21A460V,3P,3W,60HZ FOR REACTOR BUILDING IMG_4538 IMi._4tiJi AC-95

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 6 of 6 Status: M N U Seismic Walkdown Checklist (SWC) SUPPLEMENTAL CABINET INSPECTION)

Equipment ID No.: 1A21A-460V (SEE APPENDIX C PAGE C-8)

Equipment Class: (1) Motor Control Centers Eauipment DescriDtion: MCC 1A21A 460V,3P,3W,60HZ FOR REACTOR BUILDING IMG_4540 AC-96

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Appendix AD Area Walk-By Checklists (AWCs)

Table AD-1 provides the location of each walk-by area that was previously inaccessible and deferred, as well as a list of walkdown items associated with each area.

AD-1

Oyster Creek Generating Station Unit I Correspondence No.: RS-13-065 Table AD-1. Summary of Area Walk-By Checklists Area Area Description Components Within Area Comments General housekeeping concerns regarding transient materials throughout area during the outage. No soft targets in the area. Per discussions with operations all of the housekeeping concerns will be resolved prior to Trunnion start-up. Scaffolding is installed per the Oyster Creek 29 Room RK-411-1 & V-1-10 Scaffolding procedures and is Seismically restrained.

General housekeeping concerns regarding transient materials throughout area during the outage. No soft targets in the area. Per discussions with operations all of the housekeeping concerns will be resolved prior to Drywell West start-up. Scaffolding is installed per the Oyster Creek 30 Side V-1-7 & V-1-106 Scaffolding procedures and is Seismically restrained.

General housekeeping concerns regarding transient materials throughout area during the outage. No soft targets in the area. Per discussions with operations all of the housekeeping concerns will be resolved prior to Drywell South- V-1-177, V-16-1, V-1-160 & start-up. Scaffolding is installed per the Oyster Creek 31 West V-1-173 Scaffolding procedures and is Seismically restrained.

General housekeeping concerns regarding transient materials throughout area during the outage. No soft targets in the area. Per discussions with operations all of the housekeeping concerns will be resolved prior to Drywell North- start-up. Scaffolding is installed per the Oyster Creek 32 West V-1-164 & V-1-175 Scaffolding procedures and is Seismically restrained.

AD-2

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 2 Status: M N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 29: RB, 23 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

1. Does anchorage of equipment in the area appear to be free of potentially Yes adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Yes degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and Yes HVAC ducting appear to be free of potentially adverse seismic conditions (e.g.,

condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

4. Does it appear that the area is free of potentially adverse seismic spatial Yes interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

5. Does it appear that the area is free of potentially adverse seismic interactions Yes that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic interactions Yes that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic interactions Yes associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

AD-3

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 2 Status: M N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 29: RB, 23

8. Have you looked for and found no other seismic conditions that could Yes adversely affect the safety functions of the equipment in the area?

Generalhousekeeping concerns regardingtransientmaterials throughout area during the outage. No soft targets in the area. Per discussions with operationsall of the housekeeping concerns will be resolved prior to start-up.

Scaffolding is installedper the Oyster Creek Scaffolding procedures and is Seismically restrained.

Comments Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AD-4

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet I of 4 Status: M-j N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 30: DW, 23 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

1. Does anchorage of equipment in the area appear to be free of potentially Yes adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Yes degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and Yes HVAC ducting appear to be free of potentially adverse seismic conditions (e.g.,

condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

4. Does it appear that the area is free of potentially adverse seismic spatial Yes interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

5. Does it appear that the area is free of potentially adverse seismic interactions Yes that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic interactions Yes that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic interactions Yes associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

AD-5

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 4 Status: Mi N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 30: DW, 23

8. Have you looked for and found no other seismic conditions that could Yes adversely affect the safety functions of the equipment in the area?

General housekeeping concerns regardingtransientmaterials throughout area during the outage. No soft targets in the area. Perdiscussions with operations all of the housekeeping concerns will be resolved priorto start-up.

Scaffolding is installedper the Oyster Creek Scaffolding proceduresand is Seismically restrained.

Comments Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AD-6

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 4 Status: MII N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 30: DW, 23 IMG_4468 IMG-4469 AD-7

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 4 of 4 Status: M N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 30: DW, 23 IMG_4470 AD-8

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 3 Status: M N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 31: DW, 46 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

1. Does anchorage of equipment in the area appear to be free of potentially Yes adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Yes degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and Yes HVAC ducting appear to be free of potentially adverse seismic conditions (e.g.,

condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

4. Does it appear that the area is free of potentially adverse seismic spatial Yes interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

5. Does it appear that the area is free of potentially adverse seismic interactions Yes that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic interactions Yes that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic interactions Yes associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

AD-9

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 3 Status: M N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 31: DW, 46

8. Have you looked for and found no other seismic conditions that could Yes adversely affect the safety functions of the equipment in the area?

General housekeeping concerns regardingtransientmaterials throughout area during the outage. No soft targets in the area. Perdiscussions with operations all of the housekeeping concerns will be resolved priorto start-up.

Scaffolding is installedper the Oyster Creek Scaffolding procedures and is Seismically restrained.

Comments Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AD-10

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 3 of 3 Status: N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 31: DW, 46 IMG._4479 AD-11

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 1 of 2 Status: M N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 32: DW, 46 Instructions for Completing Checklist This checklist may be used to document the results of the Area Walk-By near one or more SWEL items. The space below each of the following questions may be used to record the results of judgments and findings.

Additional space is provided at the end of this checklist for documenting other comments.

1. Does anchorage of equipment in the area appear to be free of potentially Yes adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Yes degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit raceways and Yes HVAC ducting appear to be free of potentially adverse seismic conditions (e.g.,

condition of supports is adequate and fill conditions of cable trays appear to be inside acceptable limits)?

4. Does it appear that the area is free of potentially adverse seismic spatial Yes interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

5. Does it appear that the area is free of potentially adverse seismic interactions Yes that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic interactions Yes that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic interactions Yes associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

AD-12

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Sheet 2 of 2 Status: M N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area): Area 32: DW, 46

8. Have you looked for and found no other seismic conditions that could Yes adversely affect the safety functions of the equipment in the area?

General housekeeping concerns regardingtransientmaterials throughout area during the outage. No soft targets in the area. Perdiscussions with operations all of the housekeeping concerns will be resolved priorto start-up.

Scaffolding is installedper the Oyster Creek Scaffolding procedures and is Seismically restrained.

Comments Evaluated by: Mark S. Etre Date: 10/26/2012 Seth W. Baker 10/26/2012 Photos AD-13

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Appendix AE Plan for Future Seismic Walkdown of Inaccessible Equipment One (1) item was not accessible during the follow-on walkdowns. This item will be walked down during a time when the equipment is accessible. Table AE-1 summarizes the reasons this item is inaccessible during normal plant operation and notes the Oyster Creek Station Issue Report IR that has been written to track completion of the Seismic Walkdown for this item.

Per Section 5.4, supplemental internal inspections of certain cabinets are required due to clarification provided by the NRC after the online Seismic Walkdowns were completed.

Therefore the item identified on Table AE-1 requires a complete inspection, including internal inspection for other adverse seismic conditions.

The Area Walk-By of the vicinity of this equipment was completed previously and was documented in Appendix D of this report.

Table AE-1. Inaccessible and Deferred Equipment Component Description Reason for Action Resolution/ Milestone ID Inaccessibility Request ID Status Completion (I R)__ _ _ __ _ _ _

125VDC Equipment DC-C 125V POWER PANEL always IR 1451018 Open 4Q2018 DC-C CENTER energized.

________ IC'I_ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _

AE-1

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Appendix AF Peer Review Report This appendix includes the Peer Review Team's report on the follow-on seismic Walkdowns and Walk-Bys.

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Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Peer Review Report for Near Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdown Inspection of Oyster Creek Generating Station Annex A March 15, 2013 Prepared by Peer Reviewers Michael Hand (Team Leader)

Anthony Osam-Duodu Michael Hand / A eL 2 566-

' 3 Peer Review Team Leader Certification Signature ate AF-2

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 IIntroduction 1.1 OVERVIEW This report documents the independent peer review for the Near-Term Task Force (NTTF)

Recommendation 2.3: Seismic Walkdown, Annex 'A' follow-on activities performed by Exelon Oyster Creek Engineering Department for Unit 1 of the Oyster Creek Generating Station (OCGS). This peer review includes review of pages iii and ix of Report RS-12-177 as updated to reflect Annex 'A'. The peer review process includes the following activities:

• Review the selection of the structures, systems, and components (SSCs) included in this follow-on walkdown.

" Review the checklists of the items completed during the follow-on Seismic Walkdowns and Area Walk-Bys.

• Review the licensing basis evaluations.

• Review the decisions for entering the adverse seismic conditions identified during the follow-on walkdowns into the plant's Corrective Action Plan (CAP).

" Review the final submittal report.

• Summarize the results of the peer review process in the final submittal report.

The peer reviewers for OCGS, Unit 1 are Messrs. Michael Hand and Anthony Osam-Duodu, all of Oyster Creek. Mr. M. Hand is designated the Peer Review Team Leader. None of the aforementioned engineers were involved in the follow-on seismic walkdown inspection process, and so that they can maintain their independence from the project. Mr. Hand is a civil-structural engineer, with over 30 years of experience, including 13 years nuclear seismic experience. He is also a Seismic Capability Engineer (EPRI SQUG training). Mr. Osam-Duodu has over 25 years of experience covering all aspect of Civil/Structural Engineering and Project Management. He is also a Seismic Capability Engineer (EPRI SQUG training).

The peer review of the follow-on seismic walkdown inspection started on March 6, 2013.

The peer review discussions on the follow-on activities are documented herein.

No issues were identified which challenged the current licensing basis.

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Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 2Peer Review - Selection of SSCs 2.1 PURPOSE The purpose of this section is to describe the process to perform the peer review of the selected structures, systems, and components, (SSCs) that were included in the Seismic Walkdown Equipment List (SWEL).

However, this peer review is performed for the SSC's that were previously inaccessible and were completed during the follow-on Seismic Walkdowns and Area Walk-Bys. There are no changes to the SWEL, so the selection of new SSCs does not apply in this case.

This peer review is based on an interview with the seismic walkdown engineer (SWE) and report preparer, Mr. Wing Ho subsequent to performance of those activities.

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Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 3Review of Follow-on Seismic Walkdown & Area Walk-By Checklists 3.1 OVERVIEW A peer review of the remaining (Annex 'A') SWCs and AWCs was performed on March 11, 2013, after which an interview was conducted by Messrs. Hand and Osam-Duodu with the SWE trained walkdown engineer, Mr. Wing Ho, in accordance with the requirements of the EPRI Document No. 1025286 entitled "Seismic Walkdown Guidance For Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic" (SWG requirements). Mr. Ho provided input as a participant with the other SWE's, Mssrs Mark Etre and Seth Baker of Stevenson &

Associates, Inc, to satisfy the peer reviewers that the walkdowns were conducted appropriately by qualified personnel in accordance with the SWG requirements.

3.2 FOLLOW-ON SEISMIC WALKDOWN CHECKLISTS 100% of the equipment inspected during the follow-on walkdown are included in the peer review, see follow-on Seismic Walkdown, and Area Walk-By Checklists presented below:

Table A3-1 Follow-on Seismic Walkdown Checklists Component ID Description Observations V-1-160 SAFETY RELIEF VALVE NR28D (SOUTH HEADER) No concerns V-1-164 SAFETY RELIEF VALVE NR28H (NORTH HEADER) No concerns V-1-173 ELECTROMATIC RELIEF VALVE NR108-A(SOUTH HEADER) No concerns V-1-175 ELECTROMATIC RELIEF VALVE NR108-C(NORTH HEADER) No concerns V-1-177 ELECTROMATIC RELIEF VALVE NR108-E(SOUTH HEADER) No concerns V-16-1 CU INLET ISOLATION VALVE FROM REACTOR VESSEL No concerns V-1-106 MAIN STEAM LINE 'A' DRAIN VALVE No concerns V-1-7 MAIN STEAM LINE'A' OUTLET ISOLATION VALVE(NS03-A) No concerns RK-41 1-1 MSIV'S SOLENOID AIR VALVE & EQUIPMENT MOUNTING No concerns RACK V-1-10 MAIN STEAM LINE'B' OUTLET ISOLATION VALVE (NS04-B) No concerns 1A21-460V MCC 1A21 460V,3PH,3W,60HZ FOR TURBINE BUILDING No concerns 1A21B-460V MCC 1A21B 460V,3P,3W,60HZ FOR REACTOR BUILDING No concerns 1A23-460V MCC 1A23 460V,3PH,3W,60HZ FOR REACTOR BUILDING No concerns 1A2-460V 460V UNIT SUBSTATION IA2 FOR REACTOR BUILDING No concerns 1C 4160V BUS 1C SWITCHGEAR No concerns AF-5

Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 Table A3-2 Follow-on Seismic Walkdown Checklists for Supplemental Internal Inspections Component ID Description Observations BTCHG C1 'C' STATION BATTERY SOLID STATE STATIC No concerns CHARGER C1 DG- BATTERY DIESEL GENERATOR UNIT #1 BATTERY CHARGER No concerns CHARGER DG-1 SWGR DIESEL GENERATOR #1 UNIT SWITCHGEAR No concerns ER18A CORE SPRAY/AUTO DEPRESS'N SYSTEM RELAY No concerns LOGIC PANEL LSP-1A2 LOCAL SHUTDOWN PANEL- USS 1A2 PUMP/BREAKER No concerns CONTROL 1A21A-460V MCC 1A21A 460V, 3P, 3W, 60HZ, FOR REACTOR No concerns BUILDING Table A3-3 Follow-on Area Walk-By Checklists Area Area Description Components Within Area Observations 29 Trunnion Room RK-41 1-1 & V-1-10 No concerns 30 Drywell West Side V-1-7 &V-1 -106 No concerns 31 Drywell South-West V-1-177, V-16-1, V-1-160 & V-1-173 No concerns 32 Drywell North-West V-1 -164 & V-1 -175 No concerns 3.3 EVALUATION OF FINDINGS There were no issues that challenged the licensing bases.

The outcome of the walkdowns indicated that there were no major concerns from the inspections conducted, and the peer reviewers consider the engineering judgments made by the inspectors as appropriate and acceptable, per the EPRI Seismic Walkdown Guidance.

Further, all the outstanding uncompleted corrective action issues in Report RS-12-177 have been addressed, as shown in Tables A5-2 and A5-3 of Annex 'A'.

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Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 4Review of Licensing Basis Assessments There were no issues that challenged the licensing bases for the follow-on items, so there were no assessments required. The peer reviewers concur with this outcome.

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Oyster Creek Generating Station Unit 1 Correspondence No.: RS-13-065 5Review Final Submittal Report & Sign-off The final supplemental report has been reviewed by Messrs. M. Hand and A. Osam-Duodu per the requirements of EPRI Seismic Walkdown Guidance (EPRI Report 1025286), and found to be acceptable. The review comments have been duly addressed and appropriately incorporated in the Report.

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