ML12361A110

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Report 12Q0108.40-R-001, Rev. 3, Seismic Walkdown Report in Response to the 50.54(f) Information Request Re Fukushima Near-Term Force Recommendation 2.3: Seismic for Quad Cities Generating Station Unit 1. Part 10 of 10
ML12361A110
Person / Time
Site: Quad Cities 
Issue date: 10/31/2012
From: Delaney M
Stevenson & Associates
To:
Office of Nuclear Reactor Regulation
Shared Package
ML123620010 List:
References
RS-12-169 12Q0108.40-R-001, Rev 3
Download: ML12361A110 (62)
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Text

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-1 2-169 Sheet 1 of 7 Status:

T N

U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area):

AWC-U1-25 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)?

Rod removed from room cooler pipe support 1-3960-H209 (at 1st elbow past cooler). Tag on the empty clevis indicates that the hanger was removed.

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)?

Overhead light fixtures judged to be acceptable.

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)?

D-183

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 2 of 7 Status: [li N

U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area):

AWC-U1-25

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?

Louvres for room cooler bent. One louvre missing fastener on one side.

Judged to be acceptable.

Comments Seismic Walkdown Team: D. Carter & J. Griffith - 8/23/2012 Evaluated by:

),JAdk-David Carter Date:

10/4/2012 James Griffith 10/4/2012 Photos D-184

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 3 of 7 Status:

TJ N U Area Walk-By Checklist (AWC)

D-185

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 4 of 7 Status:

I N U

Area Walk-By Checklist (AWC)

D-186

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 5 of 7 Status: Ei] N U

Area Walk-By Checklist (AWC)

D-187

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 6 of 7 Status:

Y N U Area Walk-By Checklist (AWC)

D-188

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 7 of 7 Status: FYI N U

Area Walk-By Checklist (AWC)

D-189

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 1 of 10 Status: F N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area):

AWC-Ul-26 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?

Minor corrosion of anchors at varous locations, judged to be acceptable.

RHR Pump C has minor spalling in the grout pad. Judged to be acceptable.

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)?

Overhead light fixtures judged to be acceptable.

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)?

Cart near robust heat exchanger for the C RHR pump. Judged to be acceptable.

D-190

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 2 of 10 Status: EZI N U Area Walk-By Checklist (AWC)

Location (Bldg, Elev, Room/Area):

AWC-U1-26

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?

Large amount of dirt, paint chips, hoses, etc. not a seismic concem.

Comments Seismic Walkdown Team: D. Carter & J. Griffith - 8/23/2012 Evaluated by:

,,-fak David Carter Date

10/4/2012 4 #

James Griffith 10/4/2012 D-191

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 3 of 10 Status: FYl] N U

Area Walk-By Checklist (AWC)

D-192

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 4 of 10 Status: FYI N U Area Walk-By Checklist (AWC)

Quad Cities 195 D-193

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 5 of 10 Status: ELI N U Area Walk-By Checklist (AWC)

D-194

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 6 of 10 Status: r-ii N U

Area Walk-By Checklist (AWC)

D-195

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 7 of 10 Status:

v N U Area Walk-By Checklist (AWC)

D-196

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 8 of 10 Status: [T N U Area Walk-By Checklist (AWC)

D-197

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 9 of 10 Status: [*

N U Area Walk-By Checklist (AWC)

D-198

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 10 of 10 Status: [*] N U Area Walk-By Checklist (AWC)

D-199

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 E

Plan for Future Seismic Walkdown of Inaccessible Equipment Ten (10) items could not be walked down during the 180-day period following the issuance of the 10CFR50.54(f) letter due to their being inaccessible. The items will be walked down during a unit outage or another time when the equipment is accessible, as appropriate. Table E-1 summarizes the reason(s) each item is inaccessible during normal plant operation and notes the Quad Cities Station Issue Report (IR) that has been written to schedule the Seismic Walkdowns (and Area Walk-bys) for the item.

In addition, certain cabinets require internal inspection for other adverse seismic conditions as summarized in Table E-2. Supplemental internal inspections of these cabinets are required due to clarification informally provided to the industry after the online seismic walkdowns were completed. These supplemental inspections will be completed during a unit outage or time when the equipment is accessible, as appropriate.

E-1

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Table E-1. Seismic Walkdown Inaccessible Items Action Resolution/

Milestone Component ID Description Reason for Inaccessibility Request Status Completion ID (IR)

Status Comleio 1-0203-VLV, PNEUMATIC MAIN STEAM INBOARD Located in Drywell 0001AH25 ISOLATION VALVE LocatedinDrywell 1-0203-lA-1 SOV, FOR MSIV Located in MSIV Room 1-0203-3A VALVE, ERV Located in Drywell 1-0203-4A VALVE, SRV Located in Drywell 1-0220-45 VALVE, PNUEMATIC 1B RECIRC LOOP Located in Clean-up Heat SMPL DOWNSTREAM SV Exchanger Room 1-1201-2 VALVE - *PMP SUCT ISOL VLV (HW)

Located in Drywell Tracking Q1 R22 Located in Clean-up HeatTrcig QR2 1-1201-5 VALVE - RECIRC PMP SUCT ISOL VLV Excanger Room Exchanger Room 1-1301-16-MO VLV, ISOLATION -RCIC STEAM SUPPLY Located in MSIV Room ISOL VLV 1-1301-17-MO VLV, ISOLATION - *U1 MAIN STM TO RCIC Located in MSIV Room DOWNSTREAM SV (HW) 1-6705-13-1 SWGR 13-1 Anchorage check only -

1412648 equipment is energized E-2

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Table E-2. Deferred Internal Cabinet Inspection IF NOTTRCIG SAU/

EQUIPMENT ACCESSIBLE IB MILESTONE TRACKING STATUS/

COMPLTIONNUMBER (IR INSPECTION COMPONENT ID DESCRIPTION CLASS (Y/N)

ACCESSIBLE,wY COMPLETION NUMBER (RESULPETIO CLSS(YN)WHY?

NUMBER)

RESULTS_

1-7800-18195 MCC -MCC 18/19-5 (01) Motor YES N/A QIR26 1422578 Tracking Control Centers C(01) Motor YES N/A Q1R22 1422578 Tracking 1-7800-18-B MCC-MCC 18-B Control Centers 1-7800-18-2 MCC-MCC 18-2 (01) Motor YES N/A Q1R28 1422578 Tracking Control Centers 1-7800-19-1 MCC - MCC 19-1 (01) Motor YES N/A Q1R23 1422578 Tracking Control Centers 2SOVD MCC MCC(01)

Motor 250VDC MCC 1 MCC ControCenters YES N/A Q1R22 1422578 Tracking 250VDC MCC MCC (01) Motor YES N/A QIR22 1422578 Tracking 1A Control Centers (02) Low 1-7100-18 SWGR 18 Voltage YES N/A Q1R22 1422578 Tracking Switchcqear (03) Medium 1-6705-13-1 SWGR 13-1 Voltage YES N/A Q1R26 1422578 Tracking Switchqear Filled with oil, NO OTHER 1-7100 TRANSFORMER 18 (04)

NO and no cabinet is 8/20/2012 N/A ADVERSE 4160V-480V Transformers joined to this SEISMIC transformer.

CONDITIONS 901-61 PNL, CONTROL (14) Distribution YES N/A Q1R22 1422578 Tracking Panels Table E-2 Page 1 of 3 E-3

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 EQUIPMENT ACCESSIBLE IF NOT MILESTONE TRACKING STATUS /

COMPONENT ID DESCRIPTION CLSS (YIN)

ACCESSIBLE, COMPLETION NUMBER (IR INSPECTION COPNNTI ESRPIOLW (Y/)

wHY?

COMPLETION NUMBER)

RESULTS 901-62 PNL, CONTROL (14) Distribution YES N/A Q1R22 1422578 Tracking Panels (16) Battery 1-8300-1 CHRGR #1, 125V Chargers and YES N/A QIR22 1422578 Tracking Inverters (16) Battery 1-8350 CHRGR #1, 250V Chargers and YES N/A QIR22 1422578 Tracking Inverters (20)

NO OTHER Instrumentation ADVERSE 901-3 PANEL and Control YES N/A 8/20/2012 N/A SEISMIC Panels and CONDITIONS Cabinets (NO PHOTO

__LLOWED)

(20)

NO OTHER Instrumentation ADVERSE

.901-33 PANEL and Control YES N/A 8/20/2012 N/A AERSE Panel andSEISMIC Panels and CONDITIONS Cabinets (20)

NO OTHER Instrumentation ADV ER 901-39 PANEL and Control YES N/A 8/20/2012 N/A ADVERSE Panels and SEISMIC Cabinets aCONDITIONS Cabinets (20)

NO OTHER (20)

ADVERSE Instrumentation SEISM 901-5 PANEL and Control YES N/A 8/20/2012 N/A CNITIO CONDITIONS Panels and (NO PHOTO CabinetsALLOWED RACK, AUTO (18) 2201-32 BLOWDOWN Instruments on YES N/A Q1R22 1422578 Tracking Racks I

Table E-2 Page 2 of 3 E-4

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 IF NOTTRCIG SAU/

EQUIPMENT ACCESSIBLE IB MILESTONE TRACKING STATUS/

COMPONENT ID DESCRIPTION CLASS (Y/N)

ACCESSIBLE, CMLTO UBR(RISETO WHY?

COMPLETION NUMBER (IR INSPECTION WHY?

NUMBER)

RESULTS (18) 2201-73A RACK Instruments on YES N/A Q1R22 1422578 Tracking Racks RACK, U-1 DG RELAY & (18) 2251-10 METERING Instruments on YES N/A Q1R22 1422578 Tracking Racks RACK, DG ENGINE (18) 2251-113 CONTROL Instruments on YES N/A Q1R22 1422578 Tracking Racks (18) 2251-86 RACK Instruments on YES N/A Q1R26 1422578 Tracking Racks (18) 2251-87 RACK Instruments on YES N/A Q1R25 1422578 Tracking Racks Table E-2 Page 3 of 3 E-5

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 F

Peer Review Report This appendix includes the Peer Review Report, including the signed Peer Review Checklist for SWEL from Appendix F of the EPRI guidance document.

F-1

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Peer Review Report For Near Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdown Inspection of Quad Cities Nuclear Station Unit 1 October 8. 2012 Prepared by Peer Reviewers Walter Diordievic (Team Leader)

Todd A. Bacon Tribhawan K. Ram Walter Djordjevic I"*/

10/8/2012 Peer Review Team Leader Certification Signature Date Sheet 1 of 11 F-2

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 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 Quad Cities Nuclear Station (QCNS). 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 seismic walkdown on August 7, 2012 by Peer Review Team Leader, Mr. Walter Djordjevic Review of a sample of the checklists prepared for the Seismic Walkdowns & Walk-Bys Review of any licensing basis evaluations Review of the decisions for entering the potentially adverse conditions in to the plant's Corrective Action Plan (CAP)

Review of the final submittal report The peer reviewers for QCNS, Unit 1 are Messrs. Walter Djordjevic, Todd A. Bacon, and Tribhawan K. Ram, 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 25 years of nuclear engineering experience and received the Seismic Walkdown Engineer (SWE) training. Mr. Ram is an advanced degree nuclear engineer with over 25 years of nuclear power plant experience. Mr. Djordjevic led the seismic peer review activities and Mr. Ram led the SWEL selection peer review. Mr. Djordjevic, as Peer Review Team Leader, has participated in all phases of the peer review process for Quad Cities, Unit 1.

The SWEL development was performed by Mr. Tony Perez of S&A. There were a few observations noted on the SWEL Peer Review Checklist which were resolved. No findings were cited. The completed SWEL Peer Review Checklist is found in. The discussion for the SWEL development peer review is found in Section 2.

Sheet 2 of 11 F-3

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 The peer review of the seismic walkdown inspection started on August 7, 2012 with a peer check of the actual walkdowns for Quad Cities, Unit 2. Mr. Djordjevic joined the walkdown team for a portion of the day's planned walkdowns to observe the conduct of walkdowns and adherence to the Seismic Walkdown Guidance (SWG)'. No additional peer review site visits were made for the Unit 1 walkdown as the same procedures were implemented and nearly the same SWEL equipment was inspected. However, an interview was conducted by Messrs. Djordjevic and Bacon with the SWE inspection team on September 7, 2012 after review of a sample of the Unit 1 Seismic Walkdown Checklists (SWCs) and Area Walk-By Checklists (AWCs) to ascertain the procedural compliance with the SWG. The discussion of the sample SWCs and AWCs is provided in Section 3.

No issues were identified which challenged the current licensing basis.

Seismic Walkdown Guidance For Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, EPRI Report 1025286, June 2012.

Sheet 3 of 11 F-4

Quad Cities Generating Station Unit 1 12QO108.40-R-O01 Rev. 3 Correspondence No.: RS-12-169 2Peer Review - Selection of SSCs 2.1 PURPOSE The purpose of this section is to describe the process that was used 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 Quad Cities 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:

1.

UFSAR chapters 3, 6, 7, 8, and 9

2.

SWEL 1 List

3.

P&ID M-38 for Spent Fuel Pool Cooling System This peer review was based on interviews.with the following individual who was (were) directly responsible for development of the SWEL:

Tony Perez, Senior Mechanical Engineer This peer review utilized the checklist shown in the SWG Appendix F: Checklist for Peer Review of SSC Selection. The completed checklist is included in this report as.

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

1.

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

A. Reactor Reactivity Control (RRC)

B. Reactor Coolant Pressure Control (RCPC)

C. Reactor Coolant Inventory Control (RCIC)

D. Decay Heat Removal (DHR)

Sheet 4 of 11 F-5

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 E. 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. This conclusion was based on a review of UFSAR chapters 3, 6, 7, 8, and 9 which determined that all five safety functions (RRC, RCPC, RCIC, DHR, and CF) are adequately represented.

2.

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

A. Various types of systems B. Major new and replacement equipment C. Various types of equipment D. Various environments E. 'Equipment enhanced based on the findings of the IPEEE F. 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. The justification for this conclusion is: a) Based on a review of UFSAR chapters referenced above and the SWEL 1 list, it was determined that appropriate variety of equipment and systems are represented (e.g., EDG, EDG Fuel Oil Transfer, RHR, RHR Service Water, HPCI, Batteries, Battery Chargers, Low and Med Vol Switchgear and MCCs); b) The "New or Replace" equipment are indicated as such; c) A variety of location environments are included: e.g., MCCs (TB and RB), Pumps (TB, DG, and RB), Tanks and Heat Exchangers (DG and RB),. and Valves (RB @ EL 554, 595, and 623); d) The IPEEE Enhancement related equipment is indicated as such; and e) The risk quantification has been included in the "Comments" column.

Note: Because of accessibility reasons, some equipment has appropriately been deferred to Outage.

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

1.

Verification that SFP related items were considered and appropriately added to SWEL 2.

This peer review determined that there was no spent fuel pool cooling system Seismic CAT 1 items. This determination is based on a review of the licensing and design basis documents including SFP Cooling System P&ID M-38.

Sheet 5 of 11 F-6

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169

2. 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 having.no items on SWEL 2. The justification for not including any Seismic Category I Structure has appropriately been documented in the interim report. There are no rapid drain down related components in SWEL2. Appropriate justification for this item is included in the interim report as well.

2.3 PEER REVIEW FINDINGS - SELECTION OF SSCs This peer review found that the process for selection for SWEL 2 SSCs was consistent with the process outlined in the SWG Section 3: Selection of SSCs.

The peer review checklist is attached to this document.

This peer review resulted in no additional findings.

2.4 RESOLUTION OF PEER REVIEW COMMENTS - SELECTION OF SSCs There were no, additional comments requiring resolution.

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 equipment and systems to meet the objectives of the NRC 50.54(f) Letter.

Sheet 6 of 11 F-7

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 3

Review of Sample Seismic Walkdown & Area Walk-Bys Checklists 3.1 OVERVIEW A peer review of the SWCs and AWCs was performed on September 7, 2012, after which an interview was conducted by Messrs. Djordjevic and Bacon with the SWE inspection team in accordance with the SWG requirements. The SWE trained walkdown engineers were Messrs. James Griffith and Michael Wodarcyk.

3.2 SAMPLE CHECKLISTS Table 3-1 lists the SWC and AWC samples which represent.16% of the SWCs and 19%

of the AWCs. The sample includes the equipment inspected during the peer review and other equipment items from other classes to introduce diversity to the sampling procedure.

Table 3-1: Table of SWC and A WC Samples from Seismic Walkdown Inspection for Unit I Equipment Equipment Walkdown Observations Identification Class Item Solenoid DRN 1A 1-302-20A 8

SCRAM PILOT No concerns Hydraulic Control 1-305-26-31 0

Units No concerns Hydraulic 1-305-34-35 0

Control Units No concerns Scram Water 1-305-125-30-03 21 Accumulator No concerns CRD Scam Inlet Flexible pipes in contact 1-305-126-26-31 7

Valve adjudged acceptable CRD Scam Inlet 1-305-126-34-03 7

Valve No concerns CRD Scam Outlet 1-305-127-34-03 7

Valve No concerns 1A LPCI LOOP 1-1001-29A 8

Valve No concerns 1B RHR Heat Exchanger Relief Interaction with lead blanket 1-1001-166B 7

Valve adjudged acceptable Sheet 7 of 11 F-8

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment Equipment Walkdown Observations Identification Class Item HPCI Condensate 1-2304 5 Pump No concerns 1-4605 21 Blowdown Tank No concerns 1A RHRSW Pump 1-5745A 10 Cubicle Cooler No concerns Diesel Generator Lube Oil Heat 1-6654 21 Exchanger No concerns 1-7800-19-1 1 MCC 19-1 No concerns 1-8350 16 250V Charger #1 No concerns Previously missing (as noted in IPEEE) anchors noted which are no longer missing -

250 VDC Batt 1 15 Station Batteries acceptable 901-61 14 Control Panel No concerns Area Walkdown Description Observations U1 Oil Day Tank Room No concerns RB near 1-1601-23 & -24 No concerns Missing bolts forsmall diameter conduit support. Action Request (IR) written - closed to work order. Not a seismic SB - Cable spreading room concern.

Storage issue corrected during walkdown -General IR written to address seismic housekeeping of TB near MCC 18-2 temporary/portable equipment.

TB RHR SW Vault near 1-3903 Open S-hooks adjudged acceptable as their failure will not

& 1-5749 affect any components. IR written - closed to work order.

Sheet 8 of 11 F-9

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 3.3 EVALUATION OF FINDINGS There were no findings that challenged the licensing basis. The plant was found to have some seismic housekeeping and maintenance (concerning loose screws and fasteners) issues. Tables 5-2 and 5-3 of the Seismic Walkdown Report (final submittal report) provide the lists of the issues encountered 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, if an item posed a potential proximity hazard to a vital component and it was removed "on the spot" in accordance with the housekeeping procedure, it was still dispositioned to an IR. A generic IR (IR No. 01405922) was written addressing instances of seismic housekeeping.

The instances of loose screws and fasteners are seen as simple general maintenance issues and none of them were adjudged a concern from the seismic performance viewpoint. However, I Rs were generated to repair the affected components.

There were instances of partially open s-hooks on light fixtures but they were isolated and not "clustered" around a single fixture.

In most cases they were adjudged not to be immediate seismic interaction hazards to the equipment in their general proximity.

Importantly, if the situation warranted a correction then an IR was specifically generated for that component, or area in the case of area walk-bys.

In all instances 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.

Sheet 9 of II F-1 0

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 41Review of Assessment of Identified Issues Tables 5-2 and 5-3 provide a list of the issues encountered during the Unit 1 seismic walkdown inspections for the SWEL components and how they were addressed. If a Quad Cities IR request was generated it is shown in the Tables. An interview was conducted by Messrs. Djordjevic and Bacon with the SWE inspection team on September 7, 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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Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 5Review Final Submittal Report & Sign-off The entire final submittal report has been reviewed by Messrs. W. Djordjevic 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) 2 letter 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(0 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

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 1 of 3 : Peer Review Checklist QCNS Unit I Peer Review Checklist for SWEL 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. 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 1 selection?

YE NEI Appropriate equipment has been included to maintain the five safety functions: RRC, DHR, RCIC, RCPC, and CF

2. Does SWEL 1 include an appropriate representation of items having the following sample selection attributes:
a. Various types of systems?

YZ NEI Various system types (e.g., EDG, EDG Fuel Oil Transfer, RHR, RHR Service Water, HPCI, Batteries, Battery Chargers, Low and Med Vol Switchgear and MCCs) have been included.

b. Major new and replacement equipment?

YZ NEI "New or Replace" equipment is included in the list.

c. Various types of equipment?

YZ NEI The equipment represents all required 21 types except 13 and 19. The screenings

  1. 1, #2, and #3 resulted in no equipment in the latter two categories.
d. Various environments?

Y0 NIM Appropriate environments (e. g., Reactor, DG, and Turbine buildings) have been included.

F-1 3

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 2 of 3 QCNS Unit 1 Peer Review Checklist for SWEL

e. Equipment enhanced based on the findings of the IPEEE (or equivalent) program?

Included as indicated in the column, "IPEEE Enhancement."

YM NEL

f. Were risk insights considered in the development of SWEL 1?

Risk quantifications (F-V and RAW) provided in the "Comments" column YO NI

3. For SWEL2:
a. Were spent fuel pool related items considered, and if applicable included in SWEL 2?

There are no items on SWEL2.

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

Appropriate justification has been provided in the Interim Report.

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?

YN NEI F-1 4

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Sheet 3 of 3 Peer Reviewer

  1. 1:

Peer Reviewer

  1. 2:

TK Ram (Quad Cities 1)

Date: 8/26/12 kdor Walter Diordievic Date: 917/12 F-1 5

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 G

IPEEE Vulnerability Status Table G-1 lists the plant improvements, the IPEEE/SQUG proposed resolution, the actual resolution and resolution date.

G-1

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Table G-1. IPEEE Vulnerability Status Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Hydraulic Control

1) No seismic capacity based N/A
1) Unit consists of valves and 1)

Unit on earthquake experience or accumulators which are in the 01/28/1987 U1 HCU generic seismic testing earthquake experience and ruggedness data is available, generic seismic testing

2) Red gas bottles at South ruggedness data. Rack load bank restrained by only one path and anchorage are chain as well as an orange separately analyzed and are gas bottle and an OK. CRD piping and scram unrestrained green trash can header seismically supported.

are impact hazards.

Outlier is resolved.

(See A3).

2) Gas bottles need a second 2) chain near the bottom.

03/28/2005 Relocate trash can.

(See A3).

Hydraulic Control

1) No seismic capacity based N/A Unit consists of valves and 01/28/1987 Unit on earthquake experience or accumulators which are in the U2 HCU generic seismic testing earthquake experience and ruggedness data is available generic seismic testing for class 0 equipment.

ruggedness data. Rack load path and anchorage are separately analyzed and are OK. CRD piping and scram header seismically supported.

Outlier is resolved.

Nitrogen Bottle Nitrogen bottle is restrained Gas bottles need a second Justified acceptability of a 12/28/1998 N/A (1), N/A (2) only by top chain, chain near the bottom.

single tight chain, as stated in station procedures.

Table G-1 Page 1 of 24 G-2

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Exhaust Silencer The silencer saddle not N/A Analyze piping adequacy for 07/31/2000 1-6667 positively supported.

support of silencer.

1/-6667 2-6667 Fan and Damper Seismic demand exceeds N/A Develop realistic, median-02/20/2000 1-5727 capacity amplified floor spectra to Y-5727 potentially reduce seismic 2-5727 demand to an acceptable level.

MCC and Panel Seismic demand exceeds Develop realistic, median-Used the MCC seismic test 02/28/2003 MCC 28-3 capacity amplified floor spectra to contained in Equipment MCC 29-1 potentially reduce seismic Qualification (EQ) Binder EQ-06/30/2000 250VDC MCC 1A demand to an acceptable 24D/Q.

250VDC MCC 1 B level.

07/31/2000 250VDC MCC 2A 250VDC MCC 2B 10/01/2001 12/06/2001 Transformer Seismic demand exceeds N/A Develop realistic, median-06/30/2000 MCC 28-1A-1 TR capacity amplified floor spectra to MCC 29-1-1 TR potentially reduce seismic 03/16/1999 SWGR 18TR demand to an acceptable level.

SWGR 19 TR SWGR 28 TR SWGR 29 TR Unit 2 250 VDC Right rear anchor bolt N/A Install missing anchor bolt.

09/24/1998 Battery Charger missing.

NItms ahb./1 Table G-1 Page 2 of 24 G-3

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date MCC and Panel

1) Seismic demand exceeds
1) Develop realistic, median-
1) Used the MCC seismic test 1)

MCC 18-1A capacity.

centered floor spectra.

contained in Equipment 06/30/2000 MCC 19-1-1

2) Unit has missing or loose Qualification (EQ) Binder EQ-MCC 19-1-1 PNL sheet metal screws which 24D/Q.

1)

MCC 28-1A attach the MCC unit to the

2) Install missing screws and 01/20/1997 base channel.

tighten loose screws.

01/29/1999

2) Install missing screws and tighten loose screws.

01/20/1997 MCC

1) Seismic demand exceeds
1) Develop realistic, median-
1) Used the MCC seismic test 1)

MCC 18-3 capacity.

centered floor spectra.

contained in Equipment 06/30/2000 Qualification (EQ) Binder EQ-

2) MCC is not bolted to 24D/Q.

adjacent distribution panel

2) Bolt MCC to adjacent (3/16" gap).

panel.

3) Missing several corner
3) Install missing screws and
2) Bolt MCC to adjacent panel.

2) sheet metal screws which tighten loose screws.

04/26/1999 attach the MCC units to the base channel.

3) Install missing screws and 3) tighten loose screws.

01/20/1997 Table G-1 Page 3 of 24 G-4

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date MCC

1) Seismic demand exceeds
1) Develop realistic, median-
1) Used the MCC seismic test 1)

MCC 19-1 capacity.

centered floor spectra.

contained in Equipment 06/30/2000

2) The welding includes both Qualification (EQ) Binder EQ-19-1 and 19-6 and not well
2) Upgrade weld of MCC to 24D/Q.

distributed. Welds should be embeds.

upgraded on the left end unit

2) Upgrade weld of MCC to 2) and the 2 right end units (next embeds.

08/19/2002 to 19-6).

3) Install missing mounting
3) Missing some sheet metal screws.
3) Install missing mounting 3) screws which attach the MCC screws.

01/20/1997 unit to the base channel.

MCC

1) Seismic demand exceeds
1) Develop realistic, median-
1) Used the MCC seismic test 1)

MCC 19-4 capacity.

centered floor spectra.

contained in Equipment 06/30/2000 Qualification (EQ) Binder EQ-

2) The welding for 19-4 is not
2) Upgrade weld of MCC to 24D/Q.

well distributed. Welds embed welding.

should be upgraded on the left end of 19-4 (next to 19

2) Upgrade weld of MCC to 2) 1).

embed welding.

08/19/2002 Panel

1) Seismic demand exceeds
1) Develop realistic, median-
1) Develop realistic, median-1) 2201-32 capacity.

centered floor spectra to centered floor spectra to 04/19/2004 potentially reduce seismic potentially reduce seismic

2) %" gapped anchorage on demand to an acceptable demand to an acceptable level.

one side of panel.

level.

2)

2) Braced panel to wall.

03/30/2004

2) Shim the gap closed since panel contains essential relays.

1/25/2002 Table G-1 Page 4 of 24 G-5

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Panel Seismic demand exceeds Develop realistic, median-Develop realistic, median-1) 2202-32 capacity.

centered floor spectra.

centered floor spectra.

04/19/2004 2) 03/30/2004 03/13/2002 Damper Damper on small duct line Evaluate or modify damper.

Evaluate or modify damper.

02/25/2003 2-9472-32 which may disconnect.

MCC

1) Seismic demand exceeds
1) Develop realistic, median-
1) Used the MCC seismic test 1)

MCC 18-1A-1 capacity.

centered floor spectra to contained in Equipment 06/30/2000 MCC 28-1A-1 potentially reduce seismic Qualification (EQ) Binder EQ-MCC 18-1A-1 PNL

2) MCC or panel is not bolted demand to an acceptable 24D/Q.

MCC 28-1A to adjacent panel.

level.

MCC 28-1B PNL #1

2) Bolt (or tie) units together 2)

PNL #2 since cubicles contain

2) Bolt (or tie) units together 04/18/1998 essential relays.

since cubicles contain essential relays.

03/10/1997 03/10/1997 12/22/1997 MCC and Panel

1) Seismic demand exceeds
1) Develop realistic, median-
1) Used the MCC seismic test 1)

MCC 29-1-1 capacity.

centered floor spectra.

contained in Equipment 06/30/2000 MCC 29-1-1 PNL

'2) MCC or Panel is not bolted Qualification (EQ) Binder EQ-MCC 29-4 to adjacent panel (there is

2) Install spacers and bolt 24D/Q.

only a 3/8"gap).

MCC to adjacent panel.

2) Install spacers and bolt MCC 2) to adjacent panel.

02/14/2000 Table G-1 Page 5 of 24 G-6

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date MCC

1) Seismic demand exceeds
1) Develop realistic, median-
1) Used the MCC seismic test 1)

MCC 18-1B capacity.

centered floor spectra.

contained in Equipment 06/30/2000

2) MCC 18-1 B is right next to Qualification (EQ) Binder EQ-(touching) MCC 18-1A-1 but
2) Bolt MCC units together.

24D/Q.

not bolted together.

3) Unit has very deficient
2) Bolt MCC units together.

2) welds and welds should be 03/31/1997 added.

4) Missing two internal 1/4"
3) Upgrade MCC to embed 3) machine screws that attach
3) Upgrade MCC to embed welds.

05/21/2002 the unit to the base channel welds.

that is bolted to the

4) Install missing mounting 4) embedded angle.
4) Install missing mounting screws.

01/20/1997 screws.

Bus Panel is 1/2" away from block N/A Install neoprene or like material 07/07/1997 125 VDC Bus 1A way on rear and it is an between wall and panel.

125 VDC Bus 1A-1 interaction hazard.

Bus

1) Anchorage demand N/A
1) Evaluate anchorage capacity 1) 125 VDC Bus 1 B exceeds capacity based on based on more refined weight 10/09/1999 125 VDC Bus 1 B-1 conservative weight estimate.

value.

2) There are lights above the units with open hooks and it
2) Close S-hooks on lights 2) is an interaction hazard.

above bus.

01/07/1997 MCC

1) Welded to embedded N/A
1) Upgrade MCC to embed 1) 250VDC MCC 2 angle distributed fairly even welds.

11/09/2001 but symmetric. Anchorage is unacceptable on North side by SRT inspection.

2) There are lights above the
2) Close S-hooks on lights 2) units with open hooks and it above MCC.

01/07/1997 is an interaction issue.

Panel Nearby cable tray support is N/A Attach cable tray support to 03/13/2002

.2202-70B an impact hazard.

panel to eliminate impact.

Table G-1 Page 6 of 24 G-7

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Panel Adjacent gas bottle with Add lower restraint to ensure Justified acceptability of a 12/28/1998 2212-32 single loose chain is an bottle does not slip out.

single tight chain, as stated in impact hazard.

station procedures.

MCC & Battery Overhead fluorescent light N/A Repair (close S-hook) on 01/07/1997 Chargers above hung with an open S-overhead light MCC 18-2 hook 11-8300-1A 1-8350 2-8300-1 01/07/1997 2-8300-1A 2-8350 1-8300-1 Cooler Cooling water line lacks N/A Coolers are rod-hung and thus 05/21/2002 1-5746A flexibility and since cooler is flexible. Laterally restrain 1-5746B rod hung so water line may coolers to preclude piping 08/29/2002 2-5746A be in danger of breaking due rupture potential or perform a 2-5746B to displacement potential of detailed analysis of piping 11/12/2001 1-5747 rods flexibility/loading on cooler or 2-5747 evaluate effects of loss of 10/24/2001 1-5748A service water inventory and 1-5748B loss of cooling capability.

09/18/2002 2-5748A 2-5748B 12/27/2001 09/06/2002 09/06/2002 12/27/2001 12/27/2001 Table G-1 Page 7 of 24 G-8

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Cooler Information on bolt type is not N/A Capacity of Cinch Anchor is 02/25/2003 1-5745A available. Bolt type and size based on "Lead Expansion (SQUG 1-5745C are assumed to be the same Anchor Load Capacity in outlier 2-5745A as ones used in Dresden Reactor Building at the closure 2-5745C which are '/" Cinch Anchor.

Savannah River Site",

report date) 1-5749 Bolt type is not covered by Westinghouse Savannah River Y-5749 the GIP - Cinch Anchor.

Company, RTR-2661, Aug. 15, 2-5749 1989 (Ref. 16). The resulting anchorage capacity was shown to exceed the design basis seismic demand loads and outlier is resolved.

Switchgear Overhead trolley hoist is an N/A Use a clamp or similar device 03/09/1999 SWGR 28 impact hazard.

to prevent the hoist from rolling SWGR 18 freely.

SWGR 19 Switchgear Overhead trolley hoist is an N/A Restrain trolley to eliminate 03/09/1999 SWGR 29 impact hazard and needs to impact hazard.

be parked Switchgear

1) Could not open units to
1) Schedule an appropriate
1) Switchgear was welded at 1)

SWGR 13 determine if the units are plug time for internal inspection, rear to existing embedments.

11/11/2002 SWGR 14 welded at the base.

2) Schedule an appropriate SWGR 13-1
2) Verify if end two units of time for internal inspection.

2)

SWGR 14-1 SWGR 14-1 are tied to other

3) Remove breaker or 05/20/2002 SWGR 23-1 10 units.

positively restrain.

2) Remove breaker or positively SWGR 24-1
3) Spare breaker stored near restrain.

05/30/2002 SWGR 24-1 is an impact hazard.

05/21/2002 05/30/2002 11/02/2001 12/26/2001 Table G-1 Page 8 of 24 G-9

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition" Date Switchgear

1) Could not open units to
1) Schedule an appropriate
1) Switchgear was welded at 1)

SWGR 13 determine if the units are plug time for internal inspection, rear to existing embedments.

11/08/2001 SWGR 14 welded at the base.

SWGR 23

2) A light with open S-hook
2) Repair (close S-hooks)
2) Repair (close S-hooks) 10/30/2001 SWGR 24 above the switchgear is an overhead light, overhead light.

impact hazard.

2)

3) Spare breaker stored near
3) Remove breaker or
3) Remove breaker or positively 01/07/1997 SWGR 24 is an impact positively restrain, restrain.

hazard.

01/07/1997 3) 11/11/2002 Panel Anchor at corner of panel is N/A Tighten/repair loose anchor 01/14/1997 901-39 loose.

Panel.

Panel has one gapped N/A Tighten/repair anchor.

05/06/1997 901-48 anchor (loose washer)

Panel Panel is not bolted to N/A Connect (bolt) panels together 05/04/1998 2202-70A adjacent panel to preclude impact potential.

901-32 11/25/1998 901-46 901-47 11/25/1998 901-48 902-39 10/15/1999 902-46 Panel Cabinet is too close to a N/A Insert neoprene or like material 02/12/1998 2252-10 conduit snuggly against the between wall and panel, or wall which thus poses an positively secure panel to wall.

impact hazard.

Table G-1 Page 9 of 24 G-10

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Panel Tool box (on wheels) located N/A Move tool box and stress 02/25/2003 2251-12 next to panels and the Exciter seismic housekeeping to plant SQUG 2251-98 which thus poses an impact personnel.

closure hazard.

report date 10/22/2007 Panel Adjacent ductwork supported Insert neoprene or like Trimmed duct angles for 09/20/1998 902-33 on rod hangers is W" away material between wall and clearance.

(gap) from top of cabinet and panel, or positively secure poses an interaction hazard.

panel to wall.

Panel

1) 901-27 not attached to Modify internal rack (stiffen
1) Connect panels together 1) 901-27 panel 901-46 it) and restrain PC cards 04/13/1999 with strap or bar to preclude 2)Panel internal PC card cards from falling out.
2) Modify internal rack (stiffen 2) racks for which cards falling it) and restrain PC cards with 12/14/1998 out of very flexible internal strap or bar to preclude cards rack is a concern.

from falling out.

Panel

1) Panel is not bolted to
1) Connect (bolt) panels
1) Connect (bolt) panels 11/25/1998 901-33 adjacent panel 901-47, thus it together to preclude impact together to preclude impact is an impact hazard.

potential.

potential.

2) Adjacent ductwork
2) Connect (bolt) panels
2) Connect (bolt) panels supported on rod hangers is together to preclude impact together to preclude impact W" away (gap) from top of potential. Insert neoprene or potential.

cabinet and poses an like material between duct interaction hazard.

and panel, or positively Ductwork angles trimmed to secure panel to duct.

increase gap-Battery Rack Some Styrofoam spacers on N/A Insert "full height" Styrofoam 08/29/1996 125 VDC BATT 1 the front or ends of rack are spacers, or secure (glue or tie) 250 VDC BATT 1 short and can fall loose (that spacers to rack (or battery 125 VDC BATT 2 is, through) and a few already cells) so that they cannot slide have even though there has out.

been no earthquake.

08/22/1996 Table G-1 Page 10 of 24 G-11I

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Battery Rack

1) Some Styrofoam spacers N/A
1) Insert "full height" Styrofoam 1) 250 VDC BATT 2 on the front or ends of rack spacers, or secure (glue or tie) 08/22/1996 are short and can fall loose spacers to rack (or battery (that is, through) and a few cells) so that they cannot slide already have even though out.

there has been no

2) Determine qualified life of 2) earthquake.

cells or replace 03/31/1998

2) Battery age unknown Valve Valve is located in RWCU N/A Review of photographs shows 06/19/1996 1-0220-45 room which is inaccessible supports at or near valve 2-0220-45 therefore caveats 7-9 and the (body); thus, the line will not be

-review for seismic interaction subjected to large bending cannot be resolved. Valve is forces and is adjudged located on 3/4" line which lies acceptable. This outlier is outside of the GIP database considered resolved.

thus caveats 4 and 5 cannot be resolved.

Rack Rack mounted (enclosed in N/A Replace it with Mercoid Snap 06/19/1996 PE-1 panel) Mercoid switch which Action (Orange High) is designated as "bad actor" mechanical switch or equivalent Pressure Switch Missing one of the four Repair (replace) missing Replaced pressure switch.

02/05/1999 1-4641-42A screws attaching itto the screw.

support.

RHR Heat Support steel was identified Commonwealth Edison Commonwealth Edison 5/17/1996 Exchanger as marginal based on design evaluated and made evaluated and made 1-1003A basis review and A-46 modifications to (upgraded) modifications to (upgraded) the 1-1003B (SQUG) assessments.

the supports.

supports.

2-1003A 2-1003B 10/23/1996 Table G-1 Page 11 of 24 G-12

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Cable Spreading An enveloping support in the N/A This outlier is resolved by 12/03/1996 Room Unit 1/2 cable Spreading outlier analysis. A limit analysis LAR 001 Room was chosen for limited per Section 8.4.8 was analytical review. The performed and the hanger support is a 3-tier, rod hung passed.

trapeze supporting 3 trays.

The support has two different types of ceiling anchorages:

embedded strut and weldment to building steel.

The embedded strut version loads exceed allowables for the vertical capacity check.

Cable Spreading A second enveloping support N/A HCLPFsse is 0.11 g peak 04/20/2001 Room in the Unit 'A Cable ground acceleration (PGA).

LAR 002 Spreading Room was chosen This hanger requires more for limited analytical review, detailed analysis to determine if The support is an unbraced lateral bracing is required to floor mounted Unistrut frame achieve the SSE demand level.

with 6 tiers supporting 6 trays. The loads in the bolted post connections to the floor 10/23/2001 baseplates exceed allowables for the lateral load check.

Table G-1 Page 12 of 24 G-1 3

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Unit 1 &2 Cable An enveloping support in Unit N/A HCLPFsse is 0.09 PGA. This 11/20/2002 Tunnels 1 Cable Tunnel was chosen hanger type requires further LAR 004 for limited analytical review, investigation to determine the The support is an eight tier, extent of problem and whether floor to ceiling, unbraced or not lateral bracing will be frame with 3x3 steel angle required to achieve the SSE posts and 2x2 steel angle demand level.

11/27/2002 cross members supporting four trays. The welded floor anchorage is not ductile. The stress in the welds exceeds allowables for the lateral load check. This hanger type is prevalent in the Unit 1 Cable Tunnel. In the Unit 2 Cable Tunnel this hanger type is found only on the east wall at the Unit 1 side.

Turbine Building An enveloping support in the N/A This outlier is resolved by 12/03/1996 Unit Turbine Building, El. 639, was outlier analysis. A limit analysis 1/2 chosen for limited analytical per Section 8.4.8 was LAR 007 review. The support is a two-performed and the hanger tier, rod hung trapeze passed.

supporting 2 trays. The support loads in welded steel anchorage exceed the allowables for the vertical capacity check. The rod fatigue check was also not met.

Table G-1 Page 13 of 24 G-14

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition I IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Turbine Building An enveloping support in the HCLPFsse is 0.22 PGA.

HCLPFsse is 0.22 PGA. This 04/28/2000 Unit Turbine Building, El. 639, was which meets the SSE hanger type meets SSE 1/2 chosen for limited analytical demand with no additional demand with no additional LAR 008 review. The support is an margin per the CDFM margin per the CDFM method unbraced, floor mounted, method NP-6041 Seismic NP-6041 Seismic margins Unistrut frame with two tiers margins Report. A more Report. A more detailed supporting 2 trays and 2, 3" detailed analysis is needed analysis is needed to determine conduit. The left post welded to determine if more design if more design margin is floor anchorage is not ductile.

margin is available or available or whether or not a The stress in the welds whether or not a design design modification will be exceeds allowables for the modification will be needed.

needed.

lateral load check.

Turbine Building So. An enveloping support in the N/A This outlier is resolved by 12/03/1996 End Turbine Building, El. 639, was outlier analysis. A limit analysis LAR 010 chosen for limited analytical per Section 8.4.8 was review. The support is an performed and the hanger unbraced, floor mounted, passed.

Unistrut frame with two tiers supporting 2 trays and 2, 3" conduit. The left post welded floor anchorage is not ductile.

The stress in the welds exceeds allowables for the lateral load check.

Table G-1 Page 14 of 24 G-1 5

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date Reactor Building An enveloping support in the HCLPFsse is 0.16 PGA 1)HCLPFsse is 0.16 PGA peak 12/06/1995 Units Reactor Building Units 1/2, El peak ground acceleration ground acceleration (PGA).

1 595 was chosen for limited (PGA). This hanger may This hanger may require lateral LAR 011 analytical review. The require lateral bracing.

bracing. Additional walkdowns support is a 2 bay, 3-tier, rod Additional walkdowns to to identify this hanger type may hung trapeze supporting identify this hanger type may be required in the Reactor and 6trays. The support has two be required in the Reactor Turbine Buildings.

01/16/2003 different type of ceiling and Turbine Buildings.

anchorages: embedded strut and weldment to building steel. The embedded strut version loads exceed allowables for the vertical

2) Also, reduced load limits capacity check the rod fatigue based on calculation have been evaluation criteria due to provided to SLICE.

short hanger rods interspersed among longer rod hangers. This general problem of mixed long and short hangers existed in the Turbine Building, as well.

Reactor Building A floor-mounted HCU cable N/A HCLPFsse is 0.1Og peak 04/08/2002 Units duct support in the Reactor ground acceleration (PGA).

1/2 Building Units 1/, El. 595, was This hanger may require lateral LAR 012 chosen as an enveloping bracing.

support for limited analytical review. The support consists of a 3" pipe column, 9-1/2 ft.

11/11/2002 tall supporting a 8"x24" cable duct containing the equivalent of fifteen (15) 3" conduit. The anchorage loads exceed the allowables for the lateral load 02/21/2002 check.

Table G-1 Page 15 of 24 G-16

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition" Date Contact 52X-No GERS (Generic N/A Evaluate circuit. Any available 05/06/2000 SWGR 18; Equipment Ruggedness test data will also be pursued.

SWGR 19; Spectra)

As required, replace relay.

SWGR 28:

SWGR 29 Contact 52Y-No GERS N/A Evaluate circuit. Any available 05/06/2000 SWGR 18; test data will also be pursued.

SWGR 19; As required, replace relay.

SWGR 28:

SWGR 29 Contact 52N-No GERS N/A Evaluate circuit. Any available 05/06/2000 SWGR 18; test data will also be pursued.

SWGR 19; As required, replace relay.

SWGR 28:

SWGR 29 Contact 52Z-No GERS N/A

-Evaluate circuit. Any available 05/06/2000 SWGR 18; test data will also be pursued.

SWGR 19; As required, replace relay.

SWGR 28:

SWGR 29; SWGR 23-1 Contact CR-No GERS N/A Evaluate circuit. Any available 05/06/2000 MCC 28-1A test data will also be pursued.

As required, replace relay.

Contact CR/a-No GERS N/A Evaluate circuit. Any available 05/06/2000 MCC 28-1a test data will also be pursued.

As required, replace relay.

ABB ITE27-Demand exceeds capacity N/A Refine amplification factors /

01/14/1999 2251-86; evaluate circuit. As required, 2251-87; replace relay.

2252-86; 2252-87 Table G-1 Page 16 of 24 G-1 7

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date ABB ITE81-No GERS N/A Evaluate circuit. Any available 01/23/1999 MCC 18/19-5; test data will also be pursued.

MCC28/29-5 As required, replace relay.

AGASTAT EGPD-Capacity exceeded N/A Refine amplification factors /

08/25/2000 SWGR 19; evaluate circuit. As required, SWGR 29 replace relay.

AGASTAT EGPD-Capacity exceeded N/A Panel mounting improvement 11/25/2002 2201-32; (Relay Report Att. G). Refine 2251-86; amplification factors / evaluate 2251-87; circuit. As required, replace SWGR 13-1; relay.

09/05/2000 2202-32; 2252-86; 2252-87; SWGR 23-1 AGASTAT ETR Capacity exceeded N/A Refine amplification factors /

09/07/2000 2212-127; evaluate circuit. As required, 2251-86; replace relay.

2251-87; 2252-86; 2252-87 ALLIS-CHALMERS No GERS N/A Evaluate circuit. Any available 05/06/2000 298-A-test data will also be pursued.

2251-12; As required, replace relay.

2252-12 AMF R10-E2-Y2-No GERS N/A Evaluate circuit. Any available 08/23/2000 V15.OK-test data will also be pursued.

125VDC CHGR 2A As required, replace relay.

AUTOTRANSFER No GERS N/A Evaluate circuit. Any available 05/28/2002 SWITCH-test data will also be pursued.

2212-46 As required, replace relay.

02/22/2002 10/25/2002 Table G-1 Page 17 of 24 G-1 8

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition' Date AUTOTRANSFER No GERS N/A Evaluate circuit. Any available 02/22/2002 SWITCH-test data will also be pursued.

901-49; As required, replace relay.

12/17/2002 901-50; 902-49; 11/25/2002 902-50 03/28/2002 03/13/2002 BARTON 288-No GERS N/A Evaluate circuit. Any available 07/11/2000 2201-7; test data will also be pursued.

2201-8; As required, replace relay.

2202-7; 2202-8 181 -CFF-No GERS N/A Evaluate circuit. Any available 05/28/2002 2251-10; test data will also be pursued.

2212-45; As required, replace relay.

04/07/2002 2252-10 03/05/2002 10/25/2002 GE CR120KT-Demand exceeds capacity N/A Refine amplification factors /

06/05/2000 901-46; evaluate circuit. As required, 901-33; replace relay.

902-32 GE CR120KT-No GERS N/A Evaluate circuit. Any available 05/22/2000 901-46; test data will also be pursued.

901-47; As required, replace relay.

902-46; 902-47 Table G-1 Page 18 of 24 G-19

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date GE HEA61B-Demand exceeds capacity N/A Used switchgear and relay 07/08/1999 SWGR 13; seismic test lab test data to SWGR 13-1; accept.

SWGR 14; SWGR 14-1; SWGR 23; SWGR 23-1; SWGR 24; SWGR 24-1; GE HFA1 51-Demand exceeds capacity N/A Refine amplification factors /

08/22/2000 2201-32; evaluate circuit. As required, 2212-127; replace relay.

2212-45; 2251-10; 901-32; 901-33; 901-8; MCC 18/19-5; SWGR 13; SWGR 14; SWGR 14-1; 2202-32; 2252-10; 902-33; 902-8; MCC 28/29-5; SWGR 23; SWGR 23-1; SWGR 24; SWGR 24-1; Table G-1 Page 19 of 24 G-20

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date GE HFA151-More than 3 NC contacts N/A Evaluate circuit. Any available 04/26/2003 SWGR 13-1; test data will also be pursued.

127B13-1X4 As required, replace relay.

Replaced with qualified relay.

GE HFA151-Demand exceeds capacity N/A Refine amplification factors /

08/22/2000 SWGR 18 (182A) evaluate circuit. As required, 227-B18-X1 replace relay.

227-B 18-X2 227-B 18-X3 GE HGA 1-Demand exceeds capacity, N/A Reduced Amplification Factor 10/31/2000 2201-32; contact configuration not AF), due to panel bracing.

2202-32; specified Used switchgear and relay 01/29/2001 SWGR 14-1; seismic test lab test data to SWGR 24-1 accept.

07/08/1999 GE HGA 1-Contact configuration not N/A Resolved via additional 04/12/2000 2212-50; specified evaluation.

0-5203-127 FO GE HGA 1-Demand exceeds capacity, N/A Refine amplification factors /

03/10/2000 SWGR 13-1 contact configuration not evaluate circuit. As required, specified replace relay.

GE HGA111-Capacity exceeded N/A Panel mounting improvement 10/31/2000 2201-32 (Relay Report Att. G).

GE HMA111-Capacity exceeded N/A Refine amplification factors /

01/12/1999 1426 JB evaluate circuit. As required, replace relay.

Table G-1 Page 20 of 24 G-21

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date GE IAC51A-Capacity exceeded N/A Used switchgear and relay 07/08/1999 SWGR 13; seismic test lab test data to SWGR 13-1; accept.

SWGR 14; SWGR 14-1; SWGR 23; SWGR 23-1; SWGR 24; SWGR 24-1 GE-IAC51A-Capacity exceeded N/A Refine amplification factors /

07/08/1999 SWGR 13-1; evaluate circuit. As required, SWGR 14-1; replace relay.

SWGR 23-1; SWGR 24-1 GE IAV51D-No GERS N/A Evaluate circuit. Any available 10/30/2000 2212-45; test data will also be pursued.

2252-10 As required, replace relay.

GE IAV69A-No GERS N/A Evaluate circuit. Any available 03/15/2003 SWGR 18; test data will also be pursued.

227-1-B18 As required, replace relay.

227-2-B 18 GE IAV69A-Capacity exceeded N/A Used switchgear and relay 07/08/1999 SWGR 13; seismic test lab test data to SWGR 13-1; accept.

SWGR 14; SWGR 14-1; SWGR 23; SWGR 23-1; SWGR 24; SWGR 24-1 GE-ICW-No GERS N/A Evaluate circuit. Any available 05/22/2000 2212-45; test data will also be pursued.

2252-10; As required, replace relay.

2251-10; Table G-1 Page 21 of 24 G-22

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date GE IJD53C-No "Hi-G" marking on relay N/A Refine amplification factors /

06/01/2000 SWGR 13; evaluate circuit. As required, SWGR 14; replace relay.

SWGR 23; SWGR 24 GE PJC1 1-Capacity exceeded N/A Used switchgear and seismic 10/09/1999 SWGR 13-1; test data, 1.5 x realistic, SWGR 14-1; median-centered spectra and SWGR 23-1; contact state to accept.

SWGR 24-1 1(2)(O)-6601-SDR-No GERS N/A Evaluate circuit. Any available 04/07/2002 2251-12; test data will also be pursued.

2212-46; As required, replace relay.

03/05/2002 2252-12 10/25/2002 05/28/2002 HACR-IV No GERS N/A Evaluate circuit. Any available 04/13/2000 2212-123; test data will also be pursued.

2251-112; As required, replace relay.

2252-112 K2-YT-1 15V-9 No GERS N/A Evaluate circuit. Any available 08/23/2000 125VDC CHGR 1, test data will also be pursued.

1A As required, replace relay.

LS 1-5241-3 No GERS N/A Evaluate circuit. Any available 08/31/2002 1-5202 Day Tank test data will also be pursued.

LS 1/2-5241-5 As required, replace relay.

03/15/2003 0-5202 Day Tank LS 2-5241-3 06/29/2002 2-5202 Day Tank OHMITE 57029-No GERS N/A Evaluate circuit. Any available 03/31/2000 2212-46; test data will also be pursued.

2251-12; As required, replace relay.

2252-12 Table G-1 Page 22 of 24 G -23

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed A

Cdti Resolution Vulnerability*

Resolution of Condition**

Actual Resolution o oniion Date PCP E15450, No GERS N/A Evaluate circuit. Any available 08/23/2000

A2331A1, test data will also be pursued.

LR6436,CP30078, As required, replace relay.

1 2-WAV-125VDC CHGR 2, 125VDC CHGR 2A SIGMA 70RE22-No GERS N/A Evaluate circuit. Any available 08/23/2000 11ODC test data will also be pursued.

125VDC CHGR 1A As required, replace relay.

125VDC CHGR 2 250VDC CHGR 1 250VDC CHGR 1/2 250VDC CHGR 2 ER and FSR -

No GERS N/A Evaluate circuit. Any available 04/07/2002 2251-12; test data will also be pursued.

2212-46; As required, replace relay.

03/05/2002 2252-12 10/25/2002 05/28/2002 SQUARE D 8504 -

No GERS N/A Evaluate circuit. Any available 03/31/2000 2212-46; test data will also be pursued.

2251-12; As required, replace relay.

03/31/2000 2252-12 W A21 1 K5-NEMA 5 N/A Any available test data will be 10/09/1999 2251-98; pursued (Relay Report Att. G).

2252-98 W GCA-NEMA 5 N/A Any available test data will be 10/09/1999 2251-100 pursued (Relay Report Att. G).

W SA NEMA 5 N/A Any available test data will be 11/18/2000 SWGR13-1; pursued (Relay Report Att. G).

SWGR14-1; SWGR 24-1 Table G-1 Page 23 of 24 G -24

Quad Cities Generating Station Unit 1 12Q0108.40-R-001 Rev. 3 Correspondence No.: RS-12-169 Equipment ID Description of Condition /

IPEEE Report Proposed Actual Resolution of Condition Resolution Vulnerability*

Resolution of Condition**

Date 1920-0203-NEMA 5 N/A Any available test data will be 06/19/2003 3ANB/C/DIE-PC pursued (Relay Report Att. G).

2201-5; 06/29/2002 2202-5 YARWAY 4418C-No GERS N/A Evaluate circuit. Any available 03/10/2000 2201-5; test data will also be pursued.

2202-5; As required, replace relay.

2201-6; 2202-6; ZENITH TIMER-No GERS N/A Evaluate circuit. Any available 08/23/2003 125VDC CHGR 1; test data will also be pursued.

125VDC CHGR 1A; As required, replace relay.

250VDC CHGR 1; 250VDC CHGR %;

250VDC CHGR 2; GE CEH BAD ACTOR N/A Evaluate circuit. As required, 05/22/2000 replace relay.

GE HGA1 1 BAD ACTOR N/A Evaluate circuit. As required, 03/10/2000 replace relay.

WESTINGHOUSE BAD ACTOR N/A Evaluate circuit-As required, 03/10/2000 SG replace relay.

WESTINGHOUSE BAD ACTOR N/A Evaluate circuit. As required, 05/28/2002 SV DG-FFCO+

replace relay.

FSR 04/07/2002 03/05/2002 10/25/2002

  • IPEEE "Vulnerability" = Vulnerability, Outlier, Anomaly, Enhancement, Finding, etc...
    • If this is different than the original planned, else N/A Table G-1 Page 24 of 24 G-25
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