CNL-14-013, Highlights of Improvements to the Sequoyah Nuclear Plant IPEEE Seismic Analysis Results and Supplemental Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)Regarding...

Highlights of Improvements to the Sequoyah Nuclear Plant IPEEE Seismic Analysis Results and Supplemental Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)Regarding...

ML14036A314
Person / Time
Site:	Sequoyah
Issue date:	01/31/2014
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-14-013, L44 140131 001
Download: ML14036A314 (62)

Text

L44 140131 001, Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-013 January 31, 2014 10 CFR 50.54(f)

ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Sequoyah Nuclear Plant, Unit 1 and 2 Facility Operating License No. DPR-77 and DPR-79 NRC Docket No. 50-327 and 50-328

Subject:

Highlights of Improvements to the Sequoyah Nuclear Plant IPEEE Seismic Analysis Results and Supplemental Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Sequoyah Nuclear Plant, Unit 1 Seismic Walkdown Results of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

References:

1. NRC Letter, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012

2. TVA Letter to NRC, 'Tennessee Valley Authority (TVA)- Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Sequoyah Nuclear Plant Seismic Walkdown Results for Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated November 27, 2012

3. TVA Letter to NRC, "Revised Seismic Walkdown Reports Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated October 4,2013 On March 12, 2012, the NRC issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 3 of Reference 1 contains specific Requested Actions, Requested Information, and Required Responses associated with Near Term Task Force (NTTF) Recommendation 2.3: Seismic.

Printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 January 31 , 2013 In Reference 2, Tennessee Valley Authority (TVA) provided the Sequoyah Nuclear Plant (SON) seismic walkdown reports in accordance with the NRC Request for Information (Reference 1). The SON seismic walkdown reports documented the plant walkdowns performed to identify and address plant-specific vulnerabilities and verify the adequacies of monitoring and maintenance procedures. In Section 5.1 of Enclosure 1 to Reference 2, TVA identified 10 seismic walkdowns of SON, Unit 1, which could not be walked down due to the walkdown areas being inaccessible during reactor power operations. TVA committed in Reference 2 to complete these 10 seismic walkdowns at SON , Unit 1, in the fall 2013 refueling outage. TVA has completed these remaining seismic walkdowns.

In August 2013, TVA participated in a Seismic Walkdown Audit conducted by the NRC . In Reference 3, TVA submitted revised seismic walkdown reports for SON, Units 1 and 2, as a result of the NRC audit. Included in Section 7, "IPEEE Vulnerabilities Resolution Report," of each revised seismic walkdown report, TVA provided improvements made to the individual plant examination of eternal events (IPEEE) for SON , Units 1 and 2.

The purpose of this letter is to highlight that the plant improvements made to some equipment that was modified or replaced after the original IPEEE seismic analysis result in the SON high confidence low probability of failure (HCLPF) capacity determinations that now exceed 0.30g . Enclosure 1 of this letter provides highlights of this information .

This letter also provides the results of the completed SON , Unit 1, walkdown inspections performed for the 10 seismic walkdowns identified in Reference 2. Specifically, Enclosure 2 of this letter provides the updated pages to the Seismic Walkdown Report for SON , Unit 1.

Pages 1 (cover page) , 2, 20, 4, 20, 21, 22, Appendix 0, pages 04 and 06, Appendix E, pages E1, E222-E241 , Appendix F, page F1 , and Appendix G, pages G1-G9 provided in to this letter have been revised to include the results for these walkdowns .

These pages supersede those pages submitted in Enclosure 1 to Reference 3. Pages 2E and Appendix F, pages F94-F1 07, of Enclosure 2 to this letter are new and should be inserted in the report to document these additional walkdowns. The results of the additional seismic walkdowns at SON, Unit 1 found no degraded , nonconforming, or unanalyzed conditions that required either immediate or follow-up actions identified as a result of these additional seismic walkdowns at SON , Unit 1.

There are no new regulatory commitments contained in this letter. If you have questions regarding this matter, please contact Kevin Casey at (423) 751-8523.

I declare under penalty of perjury that the foregoing is true and correct. Executed on the 31st day of January 2014.

• ce President, Nuclear Licensing Enclosures cc: See page 3

U.S. Nuclear Regulatory Commission Page3 January 31, 2014

Enclosures:

1. Sequoyah Nuclear Plant, Units 1 and 2, Highlights of Improvements Made to the IPEEE Program

2. Sequoyah Nuclear Plant, Unit 1, Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report cc: (Enclosures):

NRC Regional Administrator- Region II NRR Director- NRC Headquarters NRR Project Manager- Sequoyah Nuclear Plant NRC Senior Resident Inspector- Sequoyah Nuclear Plant

ENCLOSURE 1 SEQUOYAH NUCLEAR PLANT, UNITS 1 AND 2 HIGHLIGHTS OF IMPROVEMENTS MADE TO THE IPEEE PROGRAM

ENCLOSURE 1 On March 12, 2012, the NRC issued Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54 (f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. Within , Recommendation 2.3: Seismic, of the Request for Information letter, a specific requested action was made for licensees to report improvements made to the individual plant examination of external events (IPEEE) program. This action was completed within the requested date and was included in Section 7, IPEEE Vulnerabilities Resolution Report, of the SQN Unit 1 and 2 Seismic Walkdown Reports submitted by References 2 and 3 of the cover letter to this Enclosure. The purpose of this Enclosure is to highlight results of those improvements.

Background

On June 28, 1991, NRC issued Generic Letter 88-20, Supplement 4, Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities, 10CFR50.54(f), and NUREG-1407, Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities: Final Report. The 50.54(f) letter requested that evaluations be completed to identify any vulnerabilities associated with the occurrence of several plant-specific external events, and to assess the impact of these vulnerabilities on the potential for plant core damage or radioactive material release. This program, designated the IPEEE program, is a corollary program to the Individual Plant Examination which focused on the vulnerabilities associated with the occurrence of external events.

In the original SQN seismic IPEEE high confidence low probability of failure (HCLPF) capacity determination, the 0.30g review level earthquake (RLE) was defined at the free-field soil surface. Thus, the seismic input motion corresponding to the RLE definition at the base of the buildings (i.e., rock outcrop) was determined to be less than 0.30g. Bounding evaluations were performed to determine seismic HCLPF capacity for the equipment components that were not screened out based on the 0.30g RLE as defined at the free-field.

The general approach for these original bounding evaluations was to use simplifying conservative approximations as a first attempt for acceptance. That is, if HCLPF capacity was determined to be above the 0.30g RLE (as defined at the free-field) given these simplifying conservative approximations, then no further evaluation was required.

Subsequent to these original SQN HCLPF capacity bounding evaluations and during the NRC Request for Additional Information (RAI) process related to the definition of RLE control motion, the SQN IPEEE RLE was redefined from the free-field soil surface to rock outcrop. As a result, all of the HCLPF capacities as determined by the conservative bounding evaluations were scaled down by a factor of 0.75. Due to this scaling, the HCLPF capacity for many items dropped below 0.30g. At that time, however, no additional effort was expended to review in more detail and improve these HCLPF capacities, especially by elimination of some of the simplifying conservative approximations as used in the original bounding evaluations.

E1-1 of 2

Results of Recent Efforts For the efforts related to the 50.54(f) letter, TVA critically reviewed the SQN IPEEE seismic evaluations and the evaluations for components with seismic HCLPF capacities below 0.30g defined at the rock outcrop. The following components were evaluated: residual heat removal (RHR) heat exchangers, main control room air handling units, ice condenser, 125V vital battery chargers, 480V shutdown transformers, 480V shutdown boards, 6.9kV shutdown boards, regenerative heat exchangers, 480V motor control center boards and RHR pumps. Also included within the scope of the evaluations were the 120 VAC vital inverters and the pipe chase coolers which were replaced, modified or repaired after the IPEEE submittal. Reevaluations and plant modifications were completed for these components and resulted in HCLPF capacities exceeding 0.30g.

Revised HCLPF Item Equipment Description Capacity for RLE at Rock Outcrop 1 RHR Heat Exchangers (modified) 0.33g 2 Main Control Room Air Handling Units 0.32g 3 Ice Condenser Lower Support Structure 0.43g Top Deck Structure 0.40g Lattice Frames 0.50g 4 125V Vital Battery Chargers 0.46g 5 480V Shutdown Transformers 0.53g 6 480V Shutdown Boards 0.53g 7 6.9 kV Shutdown Boards 0.36g 8 Regenerative Heat Exchangers 0.43g 9 480V MCC Boards 0.57g 10 RHR Pumps 0.47g 11 120 VAC Vital Inverters (modified - Unit 0 Spare) 0.56g 120 VAC Vital Inverters (replaced - Units 1 & 2) 0.39g 12 Pipe Chase Coolers (repaired) 0.47g E1-2 of 2

ENCLOSURE 2 SEQUOYAH NUCLEAR PLANT, UNIT 1 FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC RESPONSE REPORT

SEQUOYAH NUCLEAR PLANT - UNIT 1 FUKUSHIMA NEAR-TERM TASK FORCE RECOMMENDATION 2.3: SEISMIC RESPONSE REPORT 10-December-2013 WorleyParsons 633 Chestnut St. Suite 400 Chattanooga TN, 37450 Tel: 423-757-8020 Fax: 423-757-5869 www.worleyparsons.com WorleyParsons Services Pty Ltd ABN 61 001 279 812

© Copyright 2013 WorleyParsons Services Pty Ltd

NTTF Recommendation 2.3: Seismic Response Report Sequoyall Unit 1 REV DESCRIPTION ORIG REVIEW WORLEY- DATE CLIENT DATE PARSONS APPROVAL APPROVAL SON Unit 1 Seismic 26-Sep-13 Walkdown Report I. Anlanaitis 2 SON Unil1 Seismic~ ,.. 10-Dec-13

~ ,,,~~

Walkdown Report R. Malone 2

REVISION LOG

Title:

Sequoyah Nuclear Plant - Unit 1 Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report Revision DESCRIPTION OF REVISION Date No. Approved o AWC for area #38: SQN-1-PMP-003-0118 removed from the list of SWEL items included in this AWC, as noted on page F77 (formerly page 413) o no pages added Appendix G: revised pagination from pages 430-438 to pages G1-G9; no pages added 2 10-Dec-2013 Revised to incorporate the completion of the 10 outage walkdown items and the 7 additional area walk-bys related to the 10 outage walkdown items completed on 21-Oct-2013.

Added Sections:

Appendix E (Page E1): Added table description and signature table for the outage inspections performed on 21-Oct-2013.

Appendix F:

o (Page F1): Added table description and signature table for the outage inspections performed on 21-Oct-2013.

o (Pages F94 through F107): Add AWCs related to the 10 outage items walked down on 21-Oct-2013.

Revised Sections:

Title Page: Revised issue date Signature Page: Updated name of originator and revised issue date Revision Log (page 2D and 2E): Added revision for revision number 2.

1. Executive Summary (page 4): Updated paragraph 3 to reflect the additional area walk-bys performed on 21-Oct-2013.

1. Executive Summary (page 4): Updated paragraph 4 to reflect the completion of the outage walkdown items performed on 21-Oct-2013.

5.1 Seismic Walkdown Procedure (page 20): Updated paragraph 1 to reflect the completion of the outage walkdown items performed on 21-Oct-2013.

5.1 Seismic Walkdown Procedure (page 20): Updated paragraph 2 to reflect the additional area walk-bys performed on 21-Oct-2013.

5.1 Seismic Walkdown Procedure Deleted paragraph 3.

5.1 Seismic Walkdown Procedure (page 21): Updated paragraph 3 (formerly paragraph 4) to reflect the increase of the total number of items in which anchorage configuration was applicable.

5.2 SWC & AWC Summary (page 21): Updated the amount of SWCs and AWCs that resulted in a YES status.

5.2 SWC & AWC Summary (page 22): Removed the 10 outage items that were declared as UNKNOWN prior to the outage walkdowns performed on 21-Oct-2013.

Appendix D:

o The class type for items 112 and 113 was changed from 5 (Horizontal Pump) to 6 (Vertical Pump) on page D4.

TVA 10534 [8-1995]

2D

REVISION LOG

Title:

Sequoyah Nuclear Plant - Unit 1 Fukushima Near-Term Task Force Recommendation 2.3: Seismic Response Report Revision DESCRIPTION OF REVISION Date No. Approved o Item 113 was changed from SQN-1-PMP-068-0031 to SQN-1-PMP-068-0050 on page D4.

o Item 115 was changed from SQN-1-PSV-001-0013B- to SQN-1-PT-001-0008C-B on page D4.

o Item 116 was changed from SQN-1-PSV-001-0024A-A to SQN PT-001-0019C-A on page D4.

o The area walkby numbers were added to item numbers 112 - 121 on page D4.

o Updated SQN U1 Areas table to include the 7 additional area walk-bys associated with the 10 outage items walked down on 21-Oct-2013 on page D6.

Appendix E o Revised the first sentence on page E1 to associate the signatures on 30-Oct-2012 with the pre-outage inspections.

o Replaced SWCs items 112 through 121 with updated items 112 through 121 reflecting walkdown observations from the outage walkdowns performed on 21-Oct-2013 (pages E222 - E241).

Appendix F o Revised the first sentence on page F1 to associate the signatures on 30-Oct-2012 with the pre-outage inspections.

Appendix G o Replaced pages G2 through G9 with revised peer review report.

TVA 10534 [8-1995]

2E

NTTF Recommendation 2.3: Seismic Response Report Sequoyah Unit 1

1. Executive Summary As a result of the Fukushima Daiichi Nuclear Power Plant accident, the U.S. Nuclear Regulatory Commission (NRC) required all US nuclear power plants to perform seismic walkdowns to identify and address degraded, non-conforming or unanalyzed conditions and to verify the current plant configuration with the current seismic licensing basis.

The NRC Near-Term Task Force (NTTF) issued a report (Reference 1) that made a series of recommendations. Subsequently, the NRC issued a 50.54(f) Letter (Reference 2) that requests information to assure that these recommendations are addressed by all U.S. nuclear power plants. This report provides guidance for conducting a seismic walkdown as required in the 50.54(f) Letter, Enclosure 3, Recommendation 2.3: Seismic.

In support of conducting the NTTF-2.3 Seismic Walkdowns, the Electrical Power Research Institute (EPRI) issued a report entitled Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic (Reference 3 - hereafter EPRI Seismic Walkdown Guidance) to provide instruction for uniform seismic walkdowns of all U.S. nuclear power plants. This document also includes guidance for reporting the findings of the required walkdowns.

At Unit 1 of the Sequoyah Nuclear Power Plant, a total of 120 general Seismic Category I equipment items were selected from the original Individual Plant Examination for External Events (IPEEE) Safe Shutdown Equipment List (SSEL) to fulfill the requirements of the NTTF-2.3 Seismic Walkdowns. The selected items were located in various environments and included many different types of equipment from multiple safety systems. A total of 53 areas were included for area walk-bys. The equipment walkdowns and area walk-bys were performed by two teams, each consisting of two seismic engineers and operations personnel, between July 13, 2012 and October 21, 2013.

A total of 120 equipment items were completed during the walkdown phase. Twelve potentially adverse seismic conditions were found and addressed through the TVA Corrective Action Program.

4

NTTF Recommendation 2.3: Seismic Response Report Sequoyah Unit 1

5. Seismic Walkdowns and Area Walk-Bys Guidance for performing the walkdowns and walk-bys required for Fukushima NTTF Recommendation 2.3 can be found in the Seismic Walkdown Guidance.

The walkdowns and walk-bys were conducted in accordance with this guideline and each was given a final status. If no potentially adverse seismic conditions were noted during a walkdown or walk-by, a YES status was given to the selected piece of equipment or area. If a potentially adverse seismic condition was noted, a NO status was given and a Corrective Action Program (CAP) entry was written. If any equipment was inaccessible, or if a portion of an item of equipment was unobservable, an UNKNOWN status was given.

It should also be noted that during the course of performing the walkdowns and walk-bys, five (5) Service Requests (SRs) were generated to address general housekeeping issues which did not present potentially adverse seismic conditions (per the criteria established in the Seismic Walkdown Guidance). Notes were taken regarding these minor housekeeping issues based on general observations made during the course of performing walkdowns and walk-bys.

5.1. Seismic Walkdown Procedure One hundred twenty (120) Seismic Walkdowns Checklists (SWCs) were completed at Sequoyah Unit 1. These checklists can be found in Appendix E of this document. The primary types of potentially adverse seismic conditions that were addressed during these walkdowns include:

Bent, broken, missing, or loose hardware Corrosion (beyond mild surface oxidation)

Visible cracks in surrounding concrete Impact of soft targets Collapsing equipment Inadequate line flexibility Fifty-three (53) Area Walk-by Checklists (AWCs) were completed at Sequoyah Unit 1.

These checklists can be found in Appendix F of this document. The primary areas of observation for potentially adverse seismic conditions that were considered during these walk-bys include:

Anchorage of equipment Cable/conduit raceways and HVAC ducts Spatial interactions between equipment Flooding/Spray hazards Fire hazards 20

NTTF Recommendation 2.3: Seismic Response Report Sequoyah Unit 1 Housekeeping and temporary equipment Of the one hundred twenty (120) SWEL items, there were eight (8) pneumatic valves (equipment class 7) and eight (8) motor-operated valves (equipment class 8) for which anchorage configuration verification is not applicable. Anchorage configuration verification for fifty-four (54) out of the one hundred four (104) applicable SWEL items was verified by drawings and/or calculations.

For cabinets and panels that were selected for walkdown, NRC guidance was followed to determine which could and could not be opened for internal inspection. An excerpt from the guidance document, Reference 7- FAQ Clarification on Cabinets Walkdown 9-18-12 is shown below -

Cabinets on the SWEL with undue safety or operational hazards can be considered inaccessible and opening of the cabinet can be deferred in accordance with the 50.54(f) letter. For those cabinets that are not to be opened, and will not be placed on the inaccessible list for later inspection (e.g., extensive disassembly is required), licensees should document the justification for not opening the cabinet on the walkdown check sheet.

All cabinets meeting the above were documented in the individual walkdowns.

5.2. SWC & AWC Summary The results documented by the Seismic Walkdowns and/or Area Walk-bys for Sequoyah Unit 1 are summarized below:

118 SWCs and 42 AWCs resulted in a YES status 2 SWCs and 11 AWCs resulted in a NO status o Potentially Adverse Seismic Condition 1 SQN-0-PMP-067-0440-B - ERCW Pump L-B o Potentially Adverse Seismic Condition 2 SQN-1-FCV-067-0176 - S.I. Pump AND RM CLR-30-180 Supply o Potentially Adverse Seismic Condition 3 Area 4 - DGB Bay 1B o Potentially Adverse Seismic Condition 4 Area 25 - RHR Pump Room Area Area 43 - SI Pump Room Area o Potentially Adverse Seismic Condition 5 Area 22 - 480V Board Room 1B o Potential Adverse Seismic Condition 6 Area 23 - 480V Board Room 1A o Potentially Adverse Seismic Condition 7 Area 37 - 669 Mechanical Equip Room 21

NTTF Recommendation 2.3: Seismic Response Report Sequoyah Unit 1 o Potentially Adverse Seismic Condition 8 Area 40 - Shutdown Board B Area o Potentially Adverse Seismic Condition 9 Area 1 - DGB Bay 1A o Potentially Adverse Seismic Condition 10 Area 36 - 6.9 kV Shutdown Board Room B o Potentially Adverse Seismic Condition 11 Area 30 - CRDM Room o Potentially Adverse Seismic Condition 12 Area 45 - Unit 1 Penetration Room 22

Risk New or 5 Safety Enhanced Area Anchorage Item # Class UNID Description System Building Elevation Significant Replaced Functions for IPEEE Walkby Verification 87 17 SQN-1-GENB-082-0001B DIESEL GEN. 1B-B 082 DIESEL GEN. 722 0 4 Y 88 18 SQN-1-LOCL-500-0163 FLOOR PANEL DIESEL GEN BLDG 500 DIESEL GEN. 722 0 4 89 18 SQN-1-LOCL-500-0005 FLOOR PANEL AUX BLDG 500 AUXILIARY 653 0 25 90 18 SQN-1-LOCL-500-0214A FLOOR PANEL AUX BLDG 500 AUXILIARY 690 0 27 91 18 SQN-1-LOCL-500-0214B FLOOR PANEL AUX BLDG 500 AUXILIARY 690 0 27 92 18 SQN-0-LOCL-500-0155 FLOOR PANEL AUX BLDG 500 AUXILIARY 690 0 27 93 19 SQN-1-TE-300-0451A-A DIESEL GEN 1A-A EXHAUST-HIGH TEMP 300 DIESEL GEN. 740 2, 4 3 94 19 SQN-1-TE-300-0451B-A DIESEL GEN 1A-A EXHAUST-LOW TEMP 300 DIESEL GEN. 740 2, 4 3 95 19 SQN-1-TE-300-0449A-B DIESEL GEN 1B-B EXHAUST-HIGH TEMP 300 DIESEL GEN. 740 2, 4 6 96 19 SQN-1-TE-300-0449B-B DIESEL GEN 1B-B EXHAUST-LOW TEMP 300 DIESEL GEN. 740 2, 4 6 97 19 SQN-1-TS-001-0018A-B STM FLOW TO AFPT ISOL - HIGH TEMP 001 AUXILIARY 669 0 34 98 19 SQN-1-TS-001-0018B-B STM FLOW TO AFPT ISOL - HIGH TEMP 001 AUXILIARY 669 0 34 99 20 SQN-1-PNLA-082-TT /3-A DG 1A-A CONTROL PNL 082 DIESEL GEN. 722 0 1 100 20 SQN-1-LOCL-500-M002 TURB CONTROL PANEL 500 CONTROL 732 0 13 Y 101 20 SQN-1-LOCL-500-M004 REACT CONTROL PANEL 500 CONTROL 732 0 13 Y 102 20 SQN-1-LOCL-500-M008 TURB SUP CONT 500 CONTROL 732 0 13 Y 103 20 SQN-1-LOCL-500-M009 VENT-ICE CONT-REACT BD 500 CONTROL 732 0 13 Y 104 21 SQN-1-HEX-072-0030 CONTAINMENT SPRAY HEAT EXCHANGER 1A 072 AUXILIARY 690 5 42 Y 105 For Item #105, refer to SWEL 2.

106 21 SQN-1-HEX-072-0007 CONTAINMENT SPRAY HX 1B 072 AUXILIARY 690 5 39 Y 107 21 SQN-1-HEX-074-0027 RESIDUAL HEAT EXCHANGER 1B 074 AUXILIARY 690 Y 1, 3, 4 Y 39 Y 108 21 SQN-1-HEX-074-0015 RHR HEAT EXCHANGER 1A 074 AUXILIARY 690 Y 1, 3, 4 Y 42 109 21 SQN-1-TNK-082-0164 DSL 1A1 STARTING AIR TANK A 35 CF 082 DIESEL GEN. 722 0 1 Y 110 21 SQN-1-TNK-082-0205 DSL 1B2 STARTING AIR TNK A 35 CU FT 082 DIESEL GEN. 722 0 4 Y 111 21 SQN-1-TNK-070-0063 COMPONENT COOLING WATER SURGE TANK 070 AUXILIARY 734 (RCA) Y 0 32 Y 112 6 SQN-1-PMP-068-0008 REACTOR COOLANT PUMP 1 068 REACTOR 695 2 51 113 6 SQN-1-PMP-068-0050 REACTOR COOLANT PUMP 3 068 REACTOR 695 2 52 114 7 SQN-1-FCV-063-0090 SIS ACCUM TK 3 FLOW ISOLATION VLV 063 REACTOR 693 5 50 115 0 SQN-1-PT-001-0008C-B SG 2 MAIN STM PRESS 001 AUXILIARY 747 2, 3 53 116 0 SQN-1-PT-001-0019C-A SG 3 MAIN STM PRESS 001 AUXILIARY 747 2, 3 53 117 8 SQN-1-FCV-063-0118-A SIS ACCUM TK 1 FLOW ISOLATION VLV 063 REACTOR 693 3 49 118 10 SQN-1-AHU-030-0080 CONTROL ROD DRIVE COOLING UNIT 1DB 030 REACTOR 680 5 48 119 10 SQN-1-CLR-030-0074 REACTOR LOWER COMPT COOLING UNIT A-A 030 REACTOR 693 5 47 120 21 SQN-1-TNK-063-0081 SIS ACCUMULATOR NO 3 063 REACTOR 693 1, 3 50 121 21 SQN-1-TNK-063-0119 SIS ACCUMULATOR NO 1 063 REACTOR 693 1, 3 49 Safety Function(s):

0 - Support Function 1 - Reactivity Control 2 - RCS Pressure Control 3 - RCS Inventory Control 4 - Decay Heat Removal 5 - Containment Isolation D4

SQN U1 Areas Area Building Elevation Description 1 Diesel Gen 722 Bay 1A 2 Diesel Gen 740 1A Bd Rm 3 Diesel Gen 740 1A Fan Rm 4 Diesel Gen 722 Bay 1B 5 Diesel Gen 740 1B Bd Rm 6 Diesel Gen 740 1B Fan Rm 7 ERCW Pump 720 1A Pump Rm 8 ERCW Pump 704 1A Bd Rm 9 ERCW Pump 688 1A Strainer Rm 10 ERCW Pump 704 1B Bd Rm 11 ERCW Pump 720 2B Pump Rm (South Side) 12 Control 732 Cont. Mech. Eqpt. Room 13 Control 732 Control Room Unit 1 14 Auxiliary 734 125V Batt Bd Room II 15 Auxiliary 734 480V Shtdwn Bd Rm 1A2 16 Auxiliary 734 480V Shtdwn Bd Rm 1B1 17 Auxiliary 734 480V Shtdwn Bd Rm 1B2 18 Auxiliary 749 480V XFMR Rm 1B 19 Auxiliary 749 480V XFMR Rm 1A 20 Auxiliary 749 125V Batt Rm 1 21 Auxiliary 749 125V Batt Rm 2 22 Auxiliary 749 480V Bd Rm 1B 23 Auxiliary 749 480V Bd Rm 1A 24 Auxiliary 749 480V 1A Mech Eq Room 25 Auxiliary 653 RHR Pump Area 26 Auxiliary 669 SI Pump Rm 1A 27 Auxiliary 690 CCS Pump Area 28 Auxiliary 714 SFP Pit 29 Auxiliary 714 SFP HEX Area 30 Auxiliary 759 CRDM Room 31 Auxiliary 734 6.9kV Shtdwn Bd Rm A (East Side) 32 Auxiliary 734 Surge Tnk B Area 33 Auxiliary 653 RHR Pump Rm 1B 34 Auxiliary 669 Aux Feedwtr Pmp 1A-S 35 Auxiliary 669 Chg. Pump Rm 1B-B 36 Auxiliary 734 6.9kV Shtdwn Bd Rm B 37 Control 669 669 Mech Room 38 Auxiliary 690 Aux Feedwtr Pmp B Area 39 Auxiliary 690 1B RHR CCS HEX Room 40 Auxiliary 714 Shtdwn Bd B Area 41 Auxiliary 653 RHR Pump Rm 1A 42 Auxiliary 690 1A RHR CCS HEX Room 43 Auxiliary 669 SI Pump Area 44 Auxiliary 734 125V Batt Bd Room IV 45 Auxiliary 669 Unit 1 Penetration Rm 46 Auxiliary 763 763 Mech Equip Rm 1B-B 47 Reactor 693 LCC Fan Room 1 48 Reactor 680 Lower Containment Control Rod Area 49 Reactor 693 Accumulator Room #1 50 Reactor 693 Accumulator Room #3 51 Reactor 695 Reactor Coolent Pump 1 Area 52 Reactor 695 Reactor Coolent Pump 3 Area 53 Auxiliary 747 Valve Vault Room D6

Appendix E: SWCs The following signatures are provided for the engineers responsible for the Seismic Walkdown Checklists in Sequoyah Unit 1 for all pre-outage inspections.

Name Date Isaac Antanaitls James Edgar Steven Summers Phillip York 10(30/ IZ The following signatures are provided for the engineers responsible for the Seismic Walkdown Checklists in Sequoyah Unit 1 for all outage inspections performed on 21-0ct-2013.

Name Signature Date Robert Malone Steven Summers E

Status: Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No. SQN-1-PMP-068-0008 Equip. Class1 6 - Vertical Pump Equipment Description Reactor Coolant Pump 1 Location: Bldg. RB Floor El. 695 Room, Area 51 - Reactor Coolant Pump 1 Area Manufacturer, Model, Etc. (optional but recommended)

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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y N U N/A

3. Is the anchorage free of corrosion that is more than mild surface Y N U N/A oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y N U N/A

5. Is the anchorage configuration consistent with plant documentation? Y N U N/A (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 Y N U potentially adverse seismic conditions?

1 Enter the equipment class name from Appendix B: Classes of Equipment.

E222

Equipment ID No. SQN-1-PMP-068-0008 Equip. Class1 6 - Vertical Pump Equipment Description Reactor Coolant Pump 1 Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y N U N/A

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

9. Do attached lines have adequate flexibility to avoid damage? Y N U N/A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 E223

Status: Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No. SQN-1-PMP-068-0050 Equip. Class1 6 - Vertical Pump Equipment Description Reactor Coolant Pump 3 Location: Bldg. RB Floor El. 695 Room, Area 52 - Reactor Coolant Pump 3 Area Manufacturer, Model, Etc. (optional but recommended)

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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y N U N/A It should be noted that maintenance was being performed on the pump therefore the equipment was partially disassembled.

3. Is the anchorage free of corrosion that is more than mild surface Y N U N/A oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y N U N/A

5. Is the anchorage configuration consistent with plant documentation? Y N U N/A (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 Y N U potentially adverse seismic conditions?

1 Enter the equipment class name from Appendix B: Classes of Equipment.

E224

Equipment ID No. SQN-1-PMP-068-0050 Equip. Class1 6 - Vertical Pump Equipment Description Reactor Coolant Pump 3 Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y N U N/A

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

9. Do attached lines have adequate flexibility to avoid damage? Y N U N/A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 E225

Status: Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No. SQN-1-FCV-063-0090 Equip. Class1 7 - Pneumatic Valve Equipment Description SIS Accum Tk 3 Flow Isolation Vlv Location: Bldg. RB Floor El. 693 Room, Area 50 - Accumulator Room 3 Manufacturer, Model, Etc. (optional but recommended)

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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y N U N/A Inline valve therefore no anchorage to inspect.

3. Is the anchorage free of corrosion that is more than mild surface Y N U N/A oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y N U N/A

5. Is the anchorage configuration consistent with plant documentation? Y N U N/A (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 Y N U potentially adverse seismic conditions?

1 Enter the equipment class name from Appendix B: Classes of Equipment.

E226

Equipment ID No. SQN-1-FCV-063-0090 Equip. Class1 7 - Pneumatic Valve Equipment Description SIS Accum Tk 3 Flow Isolation Vlv Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y N U N/A

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

9. Do attached lines have adequate flexibility to avoid damage? Y N U N/A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 E227

Status: Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No. SQN-1-PT-001-0008C-B Equip. Class1 0 - Other Equipment Description SG 2 MAIN STM PRESS Location: Bldg. AUX Floor El. 747 Room, Area 53 - Valve Vault Room Manufacturer, Model, Etc. (optional but recommended)

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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y N U N/A

3. Is the anchorage free of corrosion that is more than mild surface Y N U N/A oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y N U N/A Anchorage does not attach to concrete but instead is attached to a wall rack.

5. Is the anchorage configuration consistent with plant documentation? Y N U N/A (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 Y N U potentially adverse seismic conditions?

1 Enter the equipment class name from Appendix B: Classes of Equipment.

E228

Equipment ID No. SQN-1-PT-001-0008C-B Equip. Class1 0 - Other Equipment Description SG 2 MAIN STM PRESS Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y N U N/A

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

9. Do attached lines have adequate flexibility to avoid damage? Y N U N/A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 E229

Status: Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No. SQN-1-PT-001-0019C-A Equip. Class1 0 - Other Equipment Description SG 3 MAIN STM PRESS Location: Bldg. AUX Floor El. 747 Room, Area 53 - Valve Vault Room Manufacturer, Model, Etc. (optional but recommended)

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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y N U N/A

3. Is the anchorage free of corrosion that is more than mild surface Y N U N/A oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y N U N/A Anchorage does not attach to concrete but instead is attached to a wall rack.

5. Is the anchorage configuration consistent with plant documentation? Y N U N/A (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 Y N U potentially adverse seismic conditions?

1 Enter the equipment class name from Appendix B: Classes of Equipment.

E230

Equipment ID No. SQN-1-PT-001-0019C-A Equip. Class1 0 - Other Equipment Description SG 3 MAIN STM PRESS Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y N U N/A

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

9. Do attached lines have adequate flexibility to avoid damage? Y N U N/A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 E231

Status: Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No. SQN-1-FCV-063-0118-A Equip. Class1 8 - Motor Operated Valve Equipment Description SIS Accum Tk 1 Flow Isolation Vlv Location: Bldg. RB Floor El. 693 Room, Area 49 - Accumulator Room 1 Manufacturer, Model, Etc. (optional but recommended)

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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y N U N/A In-Line valve. No anchorage.

3. Is the anchorage free of corrosion that is more than mild surface Y N U N/A oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y N U N/A

5. Is the anchorage configuration consistent with plant documentation? Y N U N/A (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 Y N U potentially adverse seismic conditions?

1 Enter the equipment class name from Appendix B: Classes of Equipment.

E232

Equipment ID No. SQN-1-FCV-063-0118-A Equip. Class1 8 - Motor Operated Valve Equipment Description SIS Accum Tk 1 Flow Isolation Vlv Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y N U N/A

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

9. Do attached lines have adequate flexibility to avoid damage? Y N U N/A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 E233

Status: Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No. SQN-1-AHU-030-0080 Equip. Class1 10 - Air Handling Unit Equipment Description Control Rod Drive Cooling Unit 1DB Location: Bldg. RB Floor El. 680 Room, Area 48 - Lower Containment Control Rod Area Manufacturer, Model, Etc. (optional but recommended)

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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y N U N/A

3. Is the anchorage free of corrosion that is more than mild surface Y N U N/A oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y N U N/A

5. Is the anchorage configuration consistent with plant documentation? Y N U N/A (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 Y N U potentially adverse seismic conditions?

1 Enter the equipment class name from Appendix B: Classes of Equipment.

E234

Equipment ID No. SQN-1-AHU-030-0080 Equip. Class1 10 - Air Handling Unit Equipment Description Control Rod Drive Cooling Unit 1DB Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y N U N/A

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

9. Do attached lines have adequate flexibility to avoid damage? Y N U N/A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 E235

Status: Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No. SQN-1-CLR-030-0074 Equip. Class1 10 - Air Handling Unit Equipment Description Reactor Lower Compt Cooling Unit A-A Location: Bldg. RB Floor El. 693 Room, Area 47 - LCC Fan Room 1 Manufacturer, Model, Etc. (optional but recommended)

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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y N U N/A

3. Is the anchorage free of corrosion that is more than mild surface Y N U N/A oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y N U N/A

5. Is the anchorage configuration consistent with plant documentation? Y N U N/A (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 Y N U potentially adverse seismic conditions?

1 Enter the equipment class name from Appendix B: Classes of Equipment.

E236

Equipment ID No. SQN-1-CLR-030-0074 Equip. Class1 10 - Air Handling Unit Equipment Description Reactor Lower Compt Cooling Unit A-A Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y N U N/A

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

9. Do attached lines have adequate flexibility to avoid damage? Y N U N/A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 E237

Status: Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No. SQN-1-TNK-063-0081 Equip. Class1 21 - Tank Equipment Description SIS Accumulator No 3 Location: Bldg. RB Floor El. 693 Room, Area 50 - Accumulator Room #3 Manufacturer, Model, Etc. (optional but recommended)

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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y N U N/A

3. Is the anchorage free of corrosion that is more than mild surface Y N U N/A oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y N U N/A

5. Is the anchorage configuration consistent with plant documentation? Y N U N/A (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 Y N U potentially adverse seismic conditions?

1 Enter the equipment class name from Appendix B: Classes of Equipment.

E238

Equipment ID No. SQN-1-TNK-063-0081 Equip. Class1 21 - Tank Equipment Description SIS Accumulator No 3 Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y N U N/A

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

9. Do attached lines have adequate flexibility to avoid damage? Y N U N/A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 E239

Status: Y N U Seismic Walkdown Checklist (SWC)

Equipment ID No. SQN-1-TNK-063-0119 Equip. Class1 21 - Tank Equipment Description SIS Accumulator No 1 Location: Bldg. RB Floor El. 693 Room, Area 49 - Accumulator Room #1 Manufacturer, Model, Etc. (optional but recommended)

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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable Anchorage

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

2. Is the anchorage free of bent, broken, missing or loose hardware? Y N U N/A

3. Is the anchorage free of corrosion that is more than mild surface Y N U N/A oxidation?

4. Is the anchorage free of visible cracks in the concrete near the anchors? Y N U N/A

5. Is the anchorage configuration consistent with plant documentation? Y N U N/A (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 Y N U potentially adverse seismic conditions?

1 Enter the equipment class name from Appendix B: Classes of Equipment.

E240

Equipment ID No. SQN-1-TNK-063-0119 Equip. Class1 21 - Tank Equipment Description SIS Accumulator No 1 Interaction Effects

7. Are soft targets free from impact by nearby equipment or structures? Y N U N/A

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

9. Do attached lines have adequate flexibility to avoid damage? Y N U N/A

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

Other Adverse Conditions

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

Comments (Additional pages may be added as necessary)

Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 E241

Appendix F: A WCs The following signatures are provided for the engineers responsible for the Area Walk-By Checklists in Sequoyah Unit 1 for all pre-outage inspections.

Name Signature Date Isaac Antanaitis

~-#* -- wjs r/t"

"" JJL.

(

James Edgar L - ~ IO/'Jo/12.

I' Robert Malone - //-~/1-- ;c/?,C) j'L Steven Summers

/~ P"' ,.,_

Phillip York f!JI(l f/11-- f {j / '3() / 12 The following signatures are provided for the engineers responsible for the Area Walk-By Checklists in Sequoyah Unit 1 for all outage inspections performed on 21-0ct-2013.

Name Signature Date Robert Malone

<~ - /t.~~~

Steven Summers M 1?/r()/l'f F

Status: Y N U Area Walk-By Checklist (AWC)

Location: Bldg. RB Floor El. 693 Room, Area1 47 - LCC Fan Room 1 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

1. Does anchorage of equipment in the area appear to be free of Y N U N/A potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Y N U N/A degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit Y N U N/A raceways and 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 Y N U N/A interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

F94

Location: Bldg. RB Floor El. 693 Room, Area1 47 - LCC Fan Room 1

5. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

8. Have you looked for and found no other seismic conditions that could Y N U adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

The following SWEL items are included in this Area Walk-By:

- SQN-1-CLR-030-0074 Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 F95

Status: Y N U Area Walk-By Checklist (AWC)

Location: Bldg. RB Floor El. 680 Room, Area1 48 - Lower Containment Control Rod Area 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

1. Does anchorage of equipment in the area appear to be free of Y N U N/A potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Y N U N/A degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit Y N U N/A raceways and 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 Y N U N/A interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

F96

Location: Bldg. RB Floor El. 680 Room, Area1 48 - Lower Containment Control Rod Area

5. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

8. Have you looked for and found no other seismic conditions that could Y N U adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

The following SWEL items are included in this Area Walk-By:

- SQN-1-AHU-030-0080 Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 F97

Status: Y N U Area Walk-By Checklist (AWC)

Location: Bldg. RB Floor El. 693 Room, Area1 49 - Accumulator Room #1 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

1. Does anchorage of equipment in the area appear to be free of Y N U N/A potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Y N U N/A degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit Y N U N/A raceways and 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 Y N U N/A interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

F98

Location: Bldg. RB Floor El. 693 Room, Area1 49 - Accumulator Room #1

5. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

8. Have you looked for and found no other seismic conditions that could Y N U adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

The following SWEL items are included in this Area Walk-By:

- SQN-1-TNK-063-0119

- SQN-1-FCV-063-0118 Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 F99

Status: Y N U Area Walk-By Checklist (AWC)

Location: Bldg. RB Floor El. 693 Room, Area1 50 - Accumulator Room #3 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

1. Does anchorage of equipment in the area appear to be free of Y N U N/A potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Y N U N/A degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit Y N U N/A raceways and 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 Y N U N/A interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

F100

Location: Bldg. RB Floor El. 693 Room, Area1 50 - Accumulator Room #3

5. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

8. Have you looked for and found no other seismic conditions that could Y N U adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

The following SWEL items are included in this Area Walk-By:

- SQN-1-TNK-063-0081

- SQN-1-FCV-063-0090 Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 F101

Status: Y N U Area Walk-By Checklist (AWC)

Location: Bldg. RB Floor El. 695 Room, Area1 51 - Reactor Coolant Pump 1 Area 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

1. Does anchorage of equipment in the area appear to be free of Y N U N/A potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Y N U N/A degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit Y N U N/A raceways and 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 Y N U N/A interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

F102

Location: Bldg. RB Floor El. 695 Room, Area1 51 - Reactor Coolant Pump 1 Area

5. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

8. Have you looked for and found no other seismic conditions that could Y N U adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

The following SWEL items are included in this Area Walk-By:

- SQN-1-PMP-068-0008 Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 F103

Status: Y N U Area Walk-By Checklist (AWC)

Location: Bldg. RB Floor El. 695 Room, Area1 52 - Reactor Coolant Pump 3 Area 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

1. Does anchorage of equipment in the area appear to be free of Y N U N/A potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Y N U N/A degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit Y N U N/A raceways and 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 Y N U N/A interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

F104

Location: Bldg. RB Floor El. 695 Room, Area1 52 - Reactor Coolant Pump 3 Area

5. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

8. Have you looked for and found no other seismic conditions that could Y N U adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

The following SWEL items are included in this Area Walk-By:

- SQN-1-PMP-068-0050 Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 F105

Status: Y N U Area Walk-By Checklist (AWC)

Location: Bldg. AUX Floor El. 747 Room, Area1 53 - Valve Vault Room 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.

Note: Y = Yes, N = No, U = Unknown, N/A = Not Applicable

1. Does anchorage of equipment in the area appear to be free of Y N U N/A potentially adverse seismic conditions (if visible without necessarily opening cabinets)?

2. Does anchorage of equipment in the area appear to be free of significant Y N U N/A degraded conditions?

3. Based on a visual inspection from the floor, do the cable/conduit Y N U N/A raceways and 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 Y N U N/A interactions with other equipment in the area (e.g., ceiling tiles and lighting)?

1 If the room in which the SWEL item is located is very large (e.g., Turbine Hall), the area selected should be described.

This selected area should be based on judgment, e.g., on the order of about 35 feet from the SWEL item.

F106

Location: Bldg. AUX Floor El. 747 Room, Area1 53 - Valve Vault Room

5. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause flooding or spray in the area?

6. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions that could cause a fire in the area?

7. Does it appear that the area is free of potentially adverse seismic Y N U N/A interactions associated with housekeeping practices, storage of portable equipment, and temporary installations (e.g., scaffolding, lead shielding)?

8. Have you looked for and found no other seismic conditions that could Y N U adversely affect the safety functions of the equipment in the area?

Comments (Additional pages may be added as necessary)

The following SWEL items are included in this Area Walk-By:

- SQN-1-PT-001-0008C-B

- SQN-1-PT-001-0019C-A Evaluated by: Lance Summers Date: 10/21/13 Robert Malone 10/21/13 F107

Appendix G: Peer Review Report G

0 12345467894 83885628688 8439888 0 0 E==F0#03G2HE;:<0I<0

/*J*KL*+0#10#:<3M NOOPMPOQROSMPONTPUMM VWXYZ[\]M^Y_W\aMN`\bcMdbecMfM

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-u*0z5w6(t(Jw-(s'0+*z5(+*K*'-,0w,0}*t('*}0('0{I0I*qs+-0<:#%#9"000'0w(-(s'0-s0-u(,0{I0 -+w('('~10q*+0s5+0+*JsKK*'}w-(s',10w660rw6l}sr'0-*wK0K*KL*+,0+*J*()*}0w}}(-(s'w60-+w('('~000 =u*0q5+qs,*0st0-u*0w}}(-(s'w60-+w('('~0rw,0-rs;ts6}000F(+,-10w}}(-(s'w60-*Ju'(Jw60-+w('('~0rw,0 q+s)(}*}0s'0*z5(qK*'-0w'Jus+w~*0w'}0,*(,K(J0('-*+wJ-(s'0*)w65w-(s',10w,0w'0*'uw'J*K*'-0-s0 -u*0w'Jus+w~*0w'}0('-*+wJ-(s'0(,,5*,0s)*+)(*r0q+s)(}*}0('0-u*0{I0-+w('('~0Js5+,*0002*Js'}10 LwJl~+s5'}0('ts+Kw-(s'0rw,0q+s)(}*}0s'0-u*0,(-*;,q*J(t(J0,*(,K(J0q+s~+wK,0(Kq6*K*'-*}0L.0 =v70w-02HE000=u(,0q+s)(}*}0-*wK0K*KL*+,0r(-u0u(,-s+(Jw60LwJl~+s5'}0s'0-u*0,Jsq*0w'}0 t('}('~,0st0q+(s+0,*(,K(J0+*)(*r,10w,0r*660w,0-s0}**q*'0-u*(+05'}*+,-w'}('~0st0-u*0,*(,K(J0 6(J*',('~0Lw,(,0ts+02HE0000 wKq6*,0st0-u*0w}}(-(s'w60q6w'-;,q*J(t(J0-+w('('~0Kw-*+(w60q+s)(}*}0ts+0-u*0-*wK0K*KL*+,0 ('J65}*0-u*0ts66sr('~>0

    !0/*,J+(q-(s'0st02HE0,*(,K(J0}*,(~'0Lw,(,0:0<9~04s5,'*+;,uwq*}0~+s5'}0Ks-(s'0
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    !02Jsq*0st0-u*0E5J6*w+0{*+ts+Kw'J*0{6w'0xE((10E&I0<#3#10vs65K*0#y0JsKK(-K*'-,0 w-02HE000=u(,0('J65}*}0-u*0ts66sr('~0Kws+0J()(6G,*(,K(J0q+s~+wK,>0 0{+s~+wKKw-(J0Js'-+s60st0,wt*-.;+*6w-*}0}*,(~'0Ks}(t(Jw-(s',0 12345467894 83 562 6 84000!000"#$%0&'()*+,(-.0/+0102-*003$000!00045'-,)(66*107803%9:";<$$"000!000=*6>0#%";"$?;3#3@000 0AAABCD8 0

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