ML13162A071

Response to NRC Request for Information Pursuant to Title 10 Code of Federal Regulations 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights.

ML13162A071
Person / Time
Site:	Catawba
Issue date:	03/28/2013
From:	Henderson K Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13162A071 (64)

Text

Duke KELVIN HENDERSON Catawba Nuclear Station

[Energye Site Vice President Carolinas,I L Duke Energy Carolinas, LLC 4800 Concord Rd.

York, SC 29745 803-701-4251 SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED March 28, 2013 10 CFR 50.54(f) i U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

Subject:

Duke Energy Carolina, LLC (Duke Energy)

Catawba Nuclear Station (CNS), Unit I Docket Nos. 50-413 Renewed License Nos. NPF-35 Response to NRC Request for Information Pursuant to Title 10 Code of Federal Regulations 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident.

Reference:

1. NRC Letter, Request for Information Pursuantto Title 10 of the Code of FederalRegulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9,3 of the Near-Term Task Force Review of Insights form the Fukushima Dai-lchi Accident, dated March 12, 2012

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

3. NRC Letter, Endorsement of Electric Power Research Institute (EPRI) Draft Report 1025286, "Seismic Walkdown Guidance",dated May 31, 2012

4. Duke Energy's 180-Day Response to March 12, 2012, Request for Information Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights for the Fukushima Dai-IchiAccident SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED www.duke-energy. corn

SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission March 28, 2012 Page 2 On March 12, 2012, the NRC staff issued Reference 1. On November 27, 2012, Duke Energy responded to the request and submitted the Unit 1 and Unit 2 Seismic Walkdown Reports for the acce!sible areas of the plant. In the response, Duke Energy also committed to provide an updated report for those inaccessible areas within 90 days of the completion of the Unit 1 refueling outage. An electronic copy of the Unit 1 report is attached which documents the inspection results. Attachments 1A through 6A of the Unit 1 report are unchanged, but are included for completeness. Attachments 7A and 8A of the report are new and reflect the inaccessible area inspection results for Unit 1.

I A of the report contains information that Duke Energy is requesting the NRC withhold from public disclosure in accordance with the requirements of 10 CFR 2.390(d)(1). In accordance with NRC Regulatory Issue Summary 2005-26, an affidavit is not required for security-s.ensitive information withheld under 10 CFR 2.390(d)(1). A separate uncontrolled electronic copy has been provided within this letter that does not include Attachment 5.

This letter contains no new regulatory commitments.

Should you have any questions concerning this letter, or require additional information, please contact Phil Barrett at (803) 701-4138.

I declare 'under penalty of perjury that the foregoing is true and correct. Executed March 28, 2013.

Respectfully submitted, Kelvin Henderson Enclosure SECURITY-SENSITIVE INFORMATION - WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5A THIS LETTER IS UNCONTROLLED

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 1 of 15 Executive Summary The results of the Catawba Unit 1 Fukushima Near-Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdowns are provided herein. The walkdowns were performed in accordance with Electric Power Research Institute (EPRI) Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, as issued in June 2012. Catawba committed to utilize this guidance for the conduct of the seismic walkdowns via docketed correspondence dated 7/9/12. The EPRI walkdown guidance provided guidance and procedures to perform seismic walkdowns as required by the U.S. Nuclear Regulatory Commission (NRC) 50.54(f) letter regarding NTTF Recommendation 2.3: Seismic. The EPRI guidance covers selection of personnel; selection of a sample of structures, systems, and components that represent diversity of component types and assures inclusion of components from critical systems / functions; conduct of the walkdowns; evaluation of potentially adverse conditions against the plant seismic licensing basis; and reporting requirements. It also includes checklists to be used by the Seismic Walkdown Engineers (SWEs) in the performance of the seismic walkdowns and walk-bys.

ReviIsion 0 of the submittal report documented the results of the walkdown of accessible items in September 20112. Revision 1 of the submittal report adds the results of the walkdown of inaccessible items performed in November I

2012.

The results of the walkdowns and licensing basis evaluations verified the adequacy of the Catawba monitoring and maintenance procedures with regard to the seismic licensing basis.

1.0 Seis!mic Licensing Basis Site Pharacteristics:

The major Category I structures such as the Reactor Building and the Auxiliary Building are supported on continuous rock (UFSAR 2.5.4.5). In areas where the continuous rock level is below the foundation bearing level, fill concrete was required to bring the area up to a suitable elevation.

Response Spectra:

The:Catawba Unit 1 Safe Shutdown Earthquake (SSE) is conservatively specified to have a peak ground acceleration of 0.15g horizontally and 0.10 g vertically. The Operating Basis Earthquake (OBE) is 8/15 of the SSE at all frequencies (UFSAR 2.5.2.8 and CNS-1465.00-00-0007, section 3.3).

The'ground response spectra curves are enveloped for analysis and design of all Category I building foundations on closely joined rock and slightly weathered rock and for all building elevations where the floor slab rests on rocký or fill concrete.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 2 of 15 Stru6ture, System and Component (SSC) Seismic Design:

All structures, systems and components required to shut down and maintain the reactor in a safe and orderly condition or prevent the uncontrolled release of excessive amounts of radioactivity have a seismic classification of Category I. The Catawba design complies with Regulatory Guide 1.29 for SSC seismic design requirements, with the exception of SSCs provided in the Westinghouse scope. The seismic design for the Westinghouse supplied SSC satisfied the classification of safety related systems and components as outlined by ANSI-N18.2a-1975 "Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants" and is presented In UFSAR section 3.2. (CNS-1465.00-00-0007).

" Duke Class A, B, C piping per ASME Section I11,1974, Class Ill (Reference UFSAR TABLE 3-5)

• Duke Class A, B, C valves per ASME Section II1,1974 (Reference UFSAR TABLE 3-6)

" Duke Class F piping per ANSI B31.1, 1973 (Reference UFSAR TABLE 3-5)

" Duke Class F valves per ANSI B31.1, Class Ill (Reference UFSAR TABLE 3-6)

" IRegulatory Guide 1.29, "Seismic Design Classification," Revision 3, September 1978.

" Regulatory Guide 1.48, "Design Limits and Loading Combinations for Category I Fluid System Components,"

,May1973.

• Regulatory Guide 1.60, "Design Response Spectra for Seismic Design of Nucl,..)r Pcw".'"ý Plants," Revision 1, December 1973.

• Regulatory Guide 1.61, "Damping Values for Seismic Design of Nuclear Power Plants," October 1973.

" Regulatory Guide 1.92, "Combining Responses and Spatial Components in Seismic Response Analysis,"

Revision 1, February 1976.

" Regulatory Guide 1.122, "Development of Floor Response Spectra for Seismic Design of Floor Supported Equipment or Components," Revision 1, February 1978.

" Regulatory Guide 1.100, "Seismic Qualification of Electric Equipment for Nuclear Power Plants," Revision 1, August 1977.

" IEEE Standard 344-1971, "Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Station.

" IEEE Standard 344-1975, "Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 3 of 15 2.0 Personnel Qualifications The ýersonnel involved in the Catawba NTTF Recommendation 2.3 Seismic Walkdown effort satisfactorily met the qualification requirements of EPRI 1025286. The personnel responsibilities and qualifications are outlined in AIABLE 2-1 below. Additional Peer Review Team experience is outlined within the Peer Review Summary Report (ATTACHMENTS 6A and 8A). I&i TABLE 2-1 Personnel Qualifications o U.JE_ u ...

uC: .2 UJ W. W 00 n(

I ,

MakEi(RS)Blii ngneig 120{3 3

SW

~

S0U W

SWE ((f) ~ U ~ C)>3 . >)

Q) (>

M ~ CDC ~ D C c. V Q 1 Marin Elrigh,(ARES) BS/Civil Engineering Mark El (ARSSWE2(2)() 32 SWE' X-U -

David Kulla P.E. (Duke) BS/Civil Engineering 37 ________ X X ___

Bryan Hanna, P.E., (ARES) BSICivil Engineering 12 SWNE X Kevin Rubright, (ARES) BS/Civil Engineering 30 SWE X John North, P.E., (ARES) BS/Civil Engineering 2 ~ ' X __

Anthony Fazio, (Shaw) Engineering BS/Chemical >40 SWE

_40_SWE_____

(

hil BS/Mechanical Philip Berdos, (Shaw). Engineering 6 SWE X James Pappas, P.E., MS/Energy 31 SWE X (Shaw) Engineering James Adam, P.E., (Shaw) MS/Nuclear w) Engineering 45 SWE (2) x Tom R Leitch, P.E., (Duke) BS/Civil Engineering 35 SWE (2) X X X X J David Kennedy (Duke) B/Civil Engineering 22 S X (Duk~e)BSCv Michael F Medlin, P.E. Egneng Engineering 3 31 SW z X X X5/Civil Raymond C Fung, P.E., MS/Civil Engineering 32 WE X X X X (Duke) MI__Eieig 2 W ___

Robert L. Keiser P.E., MS/Civil Engineering >20 SQUG' X (Duke) SWE (')

Charles M. Conselman, P.E. BS/Civil Engineering 28 SWE (2}X) X (ARES)

Paul Baughman P.E., BS/Civil Engineering - - - XM (ARES) >40 SWE (2)

Robert N Pryce (Duke) BSIMech Engineering 28 PSRO'4) X X X Tom Baumgardner (Duke) n/a 45 PSROd'4 ) X X Fred Willis P.E., (Duke) BS/Civil Engineering 32 X Mark Shutt P E., (Duke) BS/Civil Engineering 32 X George (Sa)BS/Civil Bushnell P.E., SCUEg Engineeringg r40+ 0+ SWEUG (Shaw) ___________ __________

NOTES:

1)' SQUG Seismic Capability Engineers (SCEs) have successfully completed SQUG training.

2) Seismic Walkdown Engineers (SWEs) have successfully completed EPRI 1025286 2 day walkdown training course.

3) Senior Team Member

4) Prior Senior Reactor Operator (SRO).

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 4 of 15 3.0 Selection of Equipment for the SWEL-1 and SWEL-2 Lists The Catawba Unit 1 SWEL-1 and SWEL-2 equipment selection was performed in accordance with the EPRI guidance outlined in EPRI Technical Report #1025286 (Reference CNC-1206.03-00-0202, Rev. 0).

SWEL -1 The EPRI SWEL-1 Screening Criteria #1 through #3 are as follows:

1) Seismic Category I licensing bases

2) Exclude structures, penetrations, and piping systems

3) Equipment must perform safety function (reactor reactivity control, reactor coolant pressure control, reactor coolant inventory control, decay heat removal, containment integrity). The EPRI screening criteria further allows major NSSS equipment inside containment to be excluded.

The original Catawba IPEEE Seismic Walkdown list (CNC-1535.00-00-0005, Rev. 3), was used as an initial "Base-1 List" of potential SWEL-1 walkdown components. After exclusion of non-seismic equipment, the prior IPEEE list effectively represents the output of EPRI guidance equipment Screening criteria's #1, #2 and #3. The Catawba Unit 1 SWEL-1 "Base-1 List" Is provided in ATTACHMENT 1A. Some equipment on the list is denoted as non-seismic and two non-seismic items were included on the final SWEL-1 equipment list.

EPRIý Screening criteria #4 was then used to select equipment from this "Base-1 List." EPRI screening criteria

1. 4 requires a representative cross-section of the following sample selection attributes:

• include a variety of systems

• Include variety of types of equipment

o. Include a variety of equipment environments

• r Include major new/replacement equipment o: Include equipment enhancements implemented in response to prior IPEEE walkdown identified discrepancies The Catawba Unit 1 SWEL-1 equipment list (ATTACHMENT 2A) comprised 119 components in 26 different systems. The SWEL-1 list represented equipment from each of the EPRI guidance equipment classes, with the exception of Low Voltage Switchgear, Engine Generators, and Motor-Generator Sets. Catawba does not have any Seismic Cat I equipment within the motor generator equipment class. The SWEL-1 lists included equipment located in -40 different plant areas/rooms locations. The selected equipment locations represent a broad range of equipment environmental conditions (e.g. inside containment, partial outdoor exposure, electrical/mechanical penetration rooms, pipe-chases, control room, etc.). Modified, new, and/or replacement equipment comprised

-25% of the SWEL-1 list. Significant modified/new/replacement equipment since the IPEEE was limited, and primarily included equipment such as battery racks/chargers/inverters, MOV/AOVs, and controls upgrades/replacements. Some of the items listed included equipment which was enhanced in response to the prior IPEEE walkd own effort.

The SWEL-1 component selection further considered PRA risk significance relative to the external seismic event.

The SWEL-1 component list included a broad sampling of components, which were identified to have a significant contribution to CDF for the external seismic event.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 5 of 15 SWEC -2 The Catawba Unit 1 SWEL-2 spent fuel pool equipment list was developed in accordance with the EPRI guidance. Seismic Category I structures, piping, and containment penetrations were specifically excluded by the EPRI guidance. The four screening criteria specified were as follows:

1) Seismic Category I licensing bases

2) Spent Fuel Pool (SFP) equipment appropriate for an equipment walkdown process

3) Sample considerations represent broad population of equipment with considered sample selection attributes such as:

a. represent a variety of systems

b. major new/replacement equipment

c. variety of equipment types

d. variety of environments

4) Equipment which could result In rapid drain down of the SFP (includes both seismic and non-seismic components and similar factors outlined in 3) above, as practical).

The SWEL-2 equipment "Base-2 List" (ATTACHMENT 3A) was established based on screens #1 and #2 above.

Equipment was selected from the Base-2 List based on screening criteria #3 above, and primarily included major equipment such as the spent fuel cooling system pumps and heat-exchangers.

The'SWEL-2 list was further supplemented based on screening criteria #4 above, to include equipment which could result In SFP rapid drain-down, as defined by the EPRI guidance. The SWEL-2 Rapid Drain Down Equipment List is also provided in ATTACHMENT 3A. The screen criteria #4 did not exclude non-seismic components from SWEL-2 selection. Due to the siphon and drain down resistant design of the spent fuel pool systems at Catawba, some manual valves and a strainer that would not be in the specific "classes of equipment" outlined by the EPRI guidelines were included in the "Rapid Draindown List". The final SWEL-2 list is provided in ATTACHMENT 4A and was comprised of 9 components.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 6 of 15 4.0 Seismic Walkdowns and Area Walk-Bys Duke Energy contracted the Shaw Group I ARES Corporation team to perform the NTTF 2.3 seismic walkdowns at Catawba Nuclear Station. The Catawba Unit 1 Walkdown Summary Report, the component Seismic Walkdown Checklists (SWCs), and the Area Walk-By Checklists (AWCs), covering the accessible items, are provided in Attachment 5A 1. Duke Energy self-performed the NTTF 2.3 seismic walkdown of inaccessible items.,

The&Catawba Unit 1 Walkdown Summary Report, the component Seismic Walkdown Checklists (SWCs), and the Area Walk-By Checklists (AWCs), covering the inaccessible items, are provided in Attachment 7A.

The'seismic walkdowns and area walk-bys were conducted in accordance with the guidance outlined in EPRI Report 1025286. The EPRI Seismic Walkdown Checklists (SWC)s were completed for each equipment item on the SWEL. The EPRI Area Walk-By Checklists (AWC)s were completed for areas/rooms associated with SWEL equipment.

I The component seismic walkdown inspections were primarily focused on the identification of potentially degraded component anchorage conditions, and potentially adverse seismic interactions with surrounding SSCs.

For the non-line mounted components, the visual inspections assessed whether the anchorage was degraded (e.g. bent, loose, broken, missing, corroded, localized concrete cracks). Additionally, for at least 50% of the non-line mounted components, the as-built field anchorage was verified to be consistent with design documentation.

The'area walk-by inspections were performed for SWEL equipment areas. The area walk-bys assessed whether other surrounding equipment in the area/room (up to either 35' radius around SWEL component or the entire L room containing the SWEL component) had potentially degraded anchorage, or whether the potential for adverse seismic interactions were present.

If the Seismic Walkdown Engineers (SWEs) determined a potentially adverse seismic condition existed, then the issue was entered into the corrective action program (CAP) to allow further engineering evaluation. The CAP engineering evaluation determined whether the potentially adverse seismic condition was degraded, unanalyzed, or non-conforming to the design and licensing bases.

Seismic Walkdown Checklists (SWC) have been completed for all of the components listed on the SWEL. This total is comprised of 119 SWEL-1 components, and nine SWEL-2 components. Sixteen of the SWCs, which were inaccessible 2 during the Shaw/ARES walkdown, were completed by Duke personnel. Fourteen of these .

were completed during the outage, and two were completed prior to the outage. For the non-line mounted SWEL equipment, an anchorage as-built verification was completed for 76% of the equipment with anchorage.

Additionally, a total of 76 Area Walk-Bys Checklists (AWC) were completed. Eleven AWC's were completed by Duke personnel during the outage.

The seismic walkdowns and walk-bys identified 40 "Potentially Adverse Seismic Conditions", which are itemized in TABLE 4-1. Refer to the notes for the walkdown items for the "CAP Disposition" explanation. Each of the potentially adverse seismic conditions was entered into the CAP. Engineering evaluation of each potentially p, adverse seismic condition concluded that the condition was in conformance with the current licensing bases. In some cases work requests or CAP ACTIONS were initiated as required to resolve minor issues and/or to enhance/evaluate field equipment clearances. Potentially Adverse Seismic Condition #33 is not listed in Appendix B of ATTACHMENT 5A. It was imported from the Unit 2 walkdown report as a shared equipment walkdown item.

1 CNS documented the submittal attachments as 1A, 2A, etc. for Unit 1, and 1B, 2B, etc. for Unit 2.

2 Fourteen were Inaccessible during plant operation. Two had anchorage partly obscured and work orders were required to access the obscured anchorage.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 7 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item Potentially Adverse Condition Disposition (See notes)

1) Room 400, NN-53 Poorly restrained small cable tray with potential fbr interaction with 10" fire water header, Also, Walk-by for poor lateral support ofjunction box that connects flexible conduit/cabling to IRNTE5010.(Non- 1,9 IRN225B QA) It has a potential For cable to (car out during a seismic even[ and lose fuiction.

L.arge bore RF line (approx. 10" dia.) and branch lines are generally very poorly laterally

2) Room 400, NN-53 restrained throughout the area. One instance the unrestrained 10" line is touching a vertical Walk-by for support tbr the RN Return I leader. I1-1/4" dia. SS line (no label; dark-blue paint) runs through 2, 9 IRN225B the area and is poorly-supported (laterally). Potential For seismic interaction in several locations.

A continuation I'roni other walk-down areas (see AWC for Aux, 577', Room 400, QQ-60 area)

3) Room 407, QQ-61 of unsupported stainless steel piping (approx. 2" to 2-1/2" line / Reft" Demineralized Water) is 1,9 Walk-by for poorly supported (laterally) and is likely to interact with various structures and features during a I RN58B seismic event and cause flooding or spra'y.

') Room 400, UI-53: Area Walk- RF line valve IRF254 actuator stem is within 3/16" of vertically-mounted TS 8x8 (approx). The 1.9 By for IKC81B RF line on which the valve is mounted (inline) is poorly supported (laterally).

5) Rooni 400, L.L-53: ARea Walk- VB breaking air line and YM demincralization. Water lines are poorly supported and are 53: fre Kcurrently Walk- touching near LL-53. Also, WE (Equipment Decontamination) lines in the area are 1,9 By for I KC81I B poorly laterally supported.

Door #909 associatedt with the adjacent Unit 1, 1R flattery Enclosure opens outward toward Diesel Generator subject equipment. The door can only open about 8-9 inches and cannot be used for access. 1, 9 Dittese Geargera Ilowever, the door could be accidentally opened from the inside of the enclosure and could lBatteiy Charger strike the subject equipment.

7) Aux Bl.dg, 594',

Room 500, NN- Base of Non-QA ONFIHG (NF Ice Bin) has boric acid around perimeter. The white residue and 2,9 59 Area Walk-By corrosion is at anchors and drains.

for IKCTKB

8) DHI (Inner), FF-53:

By Area foAr Walk-ISVW, Scaffold storage needs tie-back to "dedicated" tie-off point, approved by engineering 1,9 ISA5, and department. Also, one ladder not tied back.

1SV26B

9) 1VGCPB 1:I B1 Four anchor bolts total. The two bolts on the east side have mild corrosion with the bolt in the EDG Starting Air NE corner having the most serious corrosion. 1,9 Compressor

10) IBI aVGCPBIn An adjacent hand wheel chain for EQ 1RNP08 hangs low enough such that it could impact or 2, 5 EDO Starting Air become entangled with the subject equipment.

Compressor 11)Room 372, BB-51: Two adjacent fire extinguishers (one each containing C02 and water) are hanging from small Area Walk-By for hooks and could jump off during a seismic event. The extinguishers could discharge retardant IAr B and could lurch across the floor and strike adjacent equipment. These hooks should be evaluated 1,9 to confirm the extinguishers will notjump off.

12) Yard, Bottom of IFWTK000]

Containment Basin:

Area Walk-By for Unistrut base for cable tray support and various instrumentation cabinets are severely corroded. 2, 7 IFWLT5000,1FWL T5010, IFWTKOI, and FWLT5130

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 8 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdowni Item Potentially Adverse Condition Disposition (See notes) 13)] FWLT5000:

FWST'WR tInstrumentation panel angle framic supports and associated wedge anchors arc severely oxidized 2,7 Levcl Channel /corroded.

1. 1

14) I FW L150 10:

FWST WR Instrumentation panel angle frame supports and associated %%edgeanchors are severely oxidizcd 2, 7 Level Channel /corroded.

42.

15) 1ECA: 125VDC CN-1214-08.08 Rev I does not indlicatc weld at the intcrrace between charger bottom runner and Vital Battery lield-installcd plates. See section C-C. (Shown on CN-1214-08.08 Rev 1A)

Charger

16) IEBA':IA ESSENTIAl.. One (I) anchor nut appears to lack full engagement with the anchor stud. Location ol'specific slud/nut: starting from doorway to battery rack enclosure find the second row ol'baltery BA'IFERY rack/framc anchors. Observe second anchor in fiom aisle way. 1.6 RACK

17) Aux Bldg, 543',

Room ,231, 1H11-55: Area Walk- Valve INV203A has a heavy operator with long moment amn and should be verified against By for! design isometric drawing. (Duke comment - This is a rigorously analyzed system) 19 INVPU13CC and INV202B

18) I EMXB: 600 VAC Essential Motor I out ol"96 bolts are missing Oiclow bucket IEMXB FOI D: back-left bolt location). 1, B Control Center

19) AWCAuxBldg, An approx. 2V" diameter fire suppression pipe is suspended by threaded rods and clevises. Rods BB-5455: Area are approximately 20 feet long. End of rod at lower end is adjacent to Unistrut. Clevis can swing Wl-By fr into Unistrut. Pipe connections are welded. Pipe may become damaged by interacting with 1,9 Walk-By for Unistrut. (Duke comment-Evaluation determined interaction is limited to minor scraping)

IEID and IEIF

20) IEl F: 120 VAC Vital An approximately three inch diameter rigid electrical conduit sweeps 90 degrees from I EIF to

20) II nvertcr Unistrut connectedsupport. Unistrut is connected to column and to a network of Unistrut which is also to ceiling (upper diaphragm). 2, 9

21) Aux Bldg, 543',

Room 217,FF53-J.J5 I: Ar'ca Walk-By There was a missing stud and nut on a base plate for a stand-off arm for instrument 2,9 fortNtl'85A, tubingl WLIV606 I (Non-QA).

INV77A, and INV312A

22) Aux Bldg, 543',

Room 217,FF53- Relatively congested to very congested area. There was a hand wheel for IFW24 (4" line) that is JJ51: Arca Walk-By about 3/8" from a perpendicular pipe (1YN127) (Non QA /" dia pipe). During seismic event 1,9 forlNl185A, INV77A, and interaction line could damage both pieces of equipment.

INV312A

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 9 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdownr Item Potentially Adverse Condition Disposition (See notes)

I

23) Aux Bldg, 594',

Room 570, Various:

Area Walk-By forlCRA-C-I CP, I CRA-C-I condenser head pressure transmitter (0YCPT6120) has vulnerable tubing which ICRA-C-I ,ICRA- could be compromised by lateral displacement of operator for IYC6 (YC Chiller A Supply to 1,9 PFT-tl ICRA- Channel A Header Isolation). (Duke veri fied OK per CNC- 1206.02-89-2003)

PFTF-I,ICR-AI-IIU-t, ICRA-D-1, and OYCPUCWI

24) Aux Bldg, 594',

Room 570,Various:

Area Walk-By forlCRA-C-t CP, Operator could be damaged (stein) due to potential impact with rigid vert. Support for control ICRA-C-.1 ICRA- 1,9 PFT-I, ICEA- panel. Approx 1.25" gap. (Duke verified OK per CNC-1206.02-89-2003)

PFTF-I .ICR-AHU-l, ICRA-D-I, and OYCPUCWI

25) Aux Bldg, 594',

Roomn 570.Various:

Area Walk-By fo'ICRA-C-I IcRALC-IICRA- CF, I YC5 (YC Chiller A supply to channel A header drain) has only a 3/16" gap from hand wheel 2, PFT--, ICRA- to adjacent YC drain.

PFTF-lICR-AHU-

1. ICRA-D-l, and OYCPUCWI

26) Aux Bldg, 594',

Room 570,Various:

Area Walk-By fort CRA-C-l CP, ICRA-C-IICRA- I" O.D. dr'ain line has an approximately I" gap from I YC5 drain. 2, 9 PIT-1, ICRA-PFTFi 1,I CR-AHU-1, ICRA-D-I, and OY'CPUCWI

27) Room 234, Aux Bldg, 543': Area A VQ system pipe (approx. 4" dia. CS) is within 1/8" of safety injection pump suction line Walk-By for vertical restraint. The VQ system line is only supported vertically with clevis hangers, and INIPUB, would interact significantly with the suction line vertical restraint. 1, 9 INV253B,INII36B

, INII44A, Approx. mid-line on the 4" VQ system line is a flange connection and a likely source of leak or IN I147B, and spray.

IKCHX0052

28) RN Pump House, Pit A: Area Walk- Safety hoist located over access shaft could swing toward adjacent wall and impact adjacent 2,5 By for I RN3OA, spiral tubing. Recommend securing hoist to access shaft handrail.

and ORNLT7390.

29) 1 FWLT5130 FWST Instrumentation panel angle frame supports, and associated wedge anchors are severely WR Level Ch 4 oxidized/corroded. (Also, see item 13) 30)Area Walk-By for No lateral bracing in the weak direction for IDCSMC2. (QA-4). Impact on other panels is 2,9 IMCI and 2MC2 unknown.

31) DHI,587',Room 591: Area Walk-By 1I" conduit is loosely attached to 1CA149 (QA-1) termination box (I 2"x 2"x6") for limit 2,9 for ICA62A and switches.

ICA66B

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 10 of 15 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Walkdown Item Potentially Adverse Condition Disposition (Soo notes)

32) ICRA-C-o CP: Anchorage system is very robust for seismic loads, Bolts appear to be 518" O.D. Still requires Chiller Camip Cont. 2, 9 Panel "A" Tm drawing verification.

33) Aux Bldg 594',

Room 560, FF-59 Area Walkby ror Corrosion: AHU plenum has rusty anchor bolts. 2, 9 2CRA-FAN (2CRA-AHU-l)

34) 2CRA-FAN Anchorage layout dimensions were verified; however current licensing basis were not available 2.9 (2CRA-AHU-l) to verify anchor bolt sizes.

35) 2CRA-FAN Hardware: Four anchor bolts are slightly bent. Up to approx. 3/8" gap is created between one (2CRA-AHU-I) side of nut and mounting flange.

36) CVI, 560' Deg 46, Loose locknut on rod supporting I WL820 could lead to support failure unless corrected. This RAD 47, Area 2,9 Walkby for INI54A was corrected on 12/08/2012 per work order 02070034.

37) CVI, 567', DEG Electray marked 140722 not secured to unistrut due to missing/loose fasteners, and cables are 176, RaD 50, Area not well attached to the tray due to missing/loose straps. These cnbles attach to I ND37A. This 2, 9 Walkbj, for IND2A. was corrected on 12/11/2012 per work order 02070453.

38) CVI, 567',DEG Nuc. Safety R.c, cables run from the valve operator to a junction box. Box found not fastened 176, RAD 50 to the unistrut support that goes to the wall due to fasteners between box and Unistrut being 2,9 Seismic Walkdown either loose or missing. During Seismic event, box could fall off unistrut and only be supported for I ND2A. by cables. Resolved per work order 02070468, completed 12/11/2012.

SWEL-2 A conduit/cable attached to a temperature element on one of the pump bearings, via a cable

1) IKFPUA: IA tray-mounted junction box has very little slack (IKFTE5330)(Non QA). The installation is Spent' Fuel Pool further subject to adverse seismic interaction due to a lack of support for the cable tray that Pump supports the J-box. A similar situation exists with a conduit/cable, sensor, and cable tray-supported I-box at the rear pump motor bearing.

2) CVI 568' DEG 244, RAD 47, Noted that first tubing clamp off operator for IVP7A is loose. This is VI tubing attached to 2,9 Area Walkby for IV13690. Resolved per work order 02070028, completed 12/15/2012.

1.FW8 CAP DISPOSITION Notes:

1) Field configuration meets Current Licensing Bases (CLB) requirements, and no field work required.

2), Field configuration meets CLB requirements; however, work request/work order/ACTION initiated to resolve minor issue, verify unknown condition, or enhance/correct field configuration.

3) Field configuration meets CLB requirements; however, design drawing updated to reflect field I configuration.

4) CLB not met, and required field modification. (No items required this designation.) I&SL

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 11 of 15

5) Lifeline hoist at RN Pumphouse was found installed such that it may contact safety related tubing iduring a seismic event. The hoist was secured such that no adverse interaction would occur during a

ýseismic event,

6) !Battery lEBA rack anchor (one of 48) identified to have less than full thread engagement which was evaluated and determined to be acceptable. Also, the hoist in the 1EBA Battery Room was evaluated for potential seismic interaction and it was determined that there is nothing in the travel path which would be contacted if the hoist moved.

7) The mounting bolts for the Refueling Water Storage Tank level transmitters were evaluated for corrosion and determined to be robust and acceptable as is. Work Request 01073777 will be used to address/refurbish the corroded mounts.

8) One (of 96) mounting bolt was found missing on Motor Control Center 1EMXB. Engineering initially

,determined that, based on the total number of mounting bolts, seismic anchorage is adequate.

!Subsequent review of drawing CN-1214-01, Rev. 46 (on type 4 mounting base plan view) discovered

!a note allowing the omission of this bolt per NCI 3479.

9) !Less significant item, identified in the CAP to drive appropriate actions or document disposition of the issue.

INACCESSIBLE COMPONENTS:

Unit 1 components that were Inaccessible until the next unit shutdown are listed in TABLE 4-2. There were fourteen of these components. These component seismic walkdowns and associated area walk-bys were completed by Duke Energy during the outage.

TABLE 4-2 Walkdown Inspections Performed in Fall Refueling Outage

• Unit., '. Io a on- .- * " Eq lne tl . ." .. ..' ~:.," .  :,;. . *.;;N:.-......, .

1 Reactor Bldg. 1NV52A 1A NC PUMP SEAL RETURN 1 Reactor Bldg. 1N154A C-Leg Accum A Discharge Isolation 1 Reactor Bldg. 1N1438A Emergency N2 From CLA to 1NC-34A 1 Reactor Bldg. 1ND2A ND Pump 1A Suct From Loop B 1 Reactor Bldg. 1NDIB ND Pump 1A Suct From Loop B 1 Reactor Bldg. 1NC34A Unit 1 PZR PORV 1 Reactor Bldg. 1NC32B Unit 1 PZR PORV 1 Reactor Bldg. 1NC36B Unit 1 PZR PORV 1 Reactor Bldg. 1NV865A SBMUP Suction from xfer Tube 1 Reactor Bldg. 1FW8 Refueling Cavity Drain 1 Reactor Bldg. 1FW46 Refueling Cavity Drain 1 Annulus. INVPDO042 SBMUP Discharge Pulsation Dampener 1 Annulus 1NVPUSB Standby Makeup Pump (NV) 1 Control Room 1SSPSA Solid State Prot Sys Trn A

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 12 of 15 RESOLUTION OF UNKNOWN ITEMS I

There were a total of eighteen SWCs originally designated to be "unknown" in the walkdown report in Attachment i

5A. The resolution of these items is described below.

Therelwere three SWCs in the Auxiliary Building which were designated "unknown."

" Two SWCs were associated with plant operations activities which would not allow access during the let walkdown time frame. These items were 1ETXA (4160/600 VAC Transformer) and 1SSPSA (Solid State Protection System). 1ETXA was removed from the list and replaced with 1ETXB (4160/600 VAC Transformer). This item was walked down by Duke Energy. 1SSPSA was walked down during the fall Unit 1 outage (see Table 4-2).

" One SWC (1EMXC) was inaccessible at the time of the walkdown. Also some anchors were not visually 1..

accessible. 1EMXC was removed from the list and replaced with 1ETXD (4160/600 VAC Transformer).

This item was walked down by Duke Energy.

ThereIwere eight items from the SWEL-1 list that were designated to be "unknown" because they are located in the Reactor Building.

IThese eight items are shown in Table 4-2. They are INV52A, 1NI54A, 1N1438A, 1ND2A, 1ND1B, 1NC34A, fAŽ 1NC32B, and 1NC36B. The walkdowns were performed by Duke Energy during the fall 2012 refueling outage.

There were five items from the SWEL-2 list that were designated to be "unknown" because they are located in the Reactor Building.

• These items are shown in Table 4-2. They are 1NV865A, 1FW8, 1FW46, 1NVPDO042, and 1NVPUSB.

They were all walked down by Duke Energy during the fall 2012 refueling outage.

There were two items from the SWEL-1 list that were designated to be "unknown" because the anchorage could not be' completely verified. They were resolved as described below:

1FWTK01 - Due to enclosure of the tank with sheet metal siding material, the anchorage was not visible and the anchorage configuration could not be verified. Verification would require major disassembly, which is beyond the scope and requirements of this walkdown program. This was documented in PIP.

'1DGBNGC - Anchors between the Unistrut and the concrete wall are not visible or accessible. Verification would require major disassembly, which is beyond the scope and requirements of this walkdown program.

The Unistrut and the anchors from the cubicle to the Unistrut were confirrmed in very good material condition, and the location environment is mild most of the time. This was documented in PIP.

5.0 Licensing Basis Evaluations As shown in Table 4-1, a total of 40 potentially adverse seismic conditions were identified by the seismic t \

walkdowns and area walk-bys. Also, one issue with the anchor bolts for OYCPUCW1 was identified during the TI-1 88 walk-down inspection with the regional NRC inspector. All of the potentially adverse seismic conditions were entered into the Corrective Action Program (CAP). Engineering evaluation of each potentially adverse seismic condition concluded that the condition was in conformance with the current licensing bases. In some cases work requests or CAP ACTIONS were initiated to correct minor issues and/or to enhance fiela equipment clearances.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 13 of 15 The potentially adverse seismic conditions and their individual Problem Investigation Process (PIP) tracking numbers are listed in the Unit I NTTF 2.3 Seismic Walkdown Summary Reports (Attachment 5A and Attachment 7A).

6.0 IPEEE Vulnerabilities The Catawba IPEEE NRC submittal of 6/21/94 (Reference 8) concluded that there were no seismic vulnerabilities from external events. Thus, there were no identified plant changes which would significantly reduce the risk from seismic external events. Table 3-3 of the IPEEE NRC submittal identified one enhancement to resolve minor field walk-down issues. This enhancement is described inTable 6-1.

TABLE 6-1 IPEEE Enhancements Equipment Deficiency Identified Resolution Date Resolved Installed missing spacers, added Unit 1 EDG battery racks were missing dummy batteries, stiffened side spacers. rails. Laternew racks with replaced batteries and design. 09/2812005

-(EC12956) 7.0 Peer Review Duke Energy (Duke) contracted with the Shaw Group (Shaw) / ARES Corporation (ARES) Team to perform the NTTF 2.3 peer review at the Catawba Nuclear Station (CNS). The Peer Review Report is contained in ATTACHMENT 6A.

The Peer Review Team consisted of three individuals, all of whom have seismic engineering experience as it applies to nuclear power plants. These individuals participated in the peer review of each of the activities. The peer review team is identified in Table 2-1 and their qualifications are provided in ATTACHMENT 6A.

The Shaw/ARES methodology conforms to the guidance in Section 6 of EPRI 1025286. The peer review covered the following:

• The selection of the SSCs included on the Seismic Walkdown Equipment List (SWEL).

'

• A sample of the checklists prepared for the seismic walkdowns and area walk-bys.

• The licensing basis evaluations.

The decisions for entering the potentially adverse conditions in the Corrective Action Program (CAP) process.

• The submittal report.

The peer review process for the SWEL development and the seismic walkdowns consisted of the following:

Reviewing the activity guidance in EPRI 1025286, the NEI Q&A bulletins, the NEI first-mover reports, and NRC Temporary Instruction 2515/188.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 14 of 15 6 Conducting an In-process review at the plant site, including interviews with the personnel performing the activity and reviewing in-process documentation.

a Performing an in-plant surveillance (for the walkdown activity) of a seismic walkdown and an area walk-by.

• Providing in-process observations and comments to the personnel performing the activities.

. Conducting a final review of a sample of the completed documentation.

The peer review process for the licensing basis evaluations and the decisions for entering potentially adverse conditions into the CAP consisted of reviewing the overall review process and a sample of the licensing basis reviews. The peer review process for the submittal report consisted of reviewing the draft submittal prepared by Catawba Design Engineering for licensing review.

The peer review identified several items, previously added to the Corrective Action Program, which may need i-additional detail with respect to the licensing basis review. It should be noted that these items were not considered in error, only that they may require more specific detail in the licensing basis evaluation to document that they were thoroughly assessed.

The items identified by the peer review were reviewed by CNS Civil Design Engineering. Additional detail was added to each, as appropriate to document the licensing basis evaluation.

The bulleted items of Section 1 (Purpose and Approach) of EPRI 1025286 were reviewed and determined to be properly assessed by the Peer Review Team. The conclusion of the peer review was that the CNS NTTF 2.3 seismic walkdown effort has been conducted in accordance with the guidance in EPRI 1025286. Comments made during the in-process review of the SWEL development and the walkdowns have been addressed satisfactorily.

Following completion of the walkdown of the inaccessible items by Duke Energy, the Peer Review Team performed a supplementary peer review. This is described in the Supplementary Peer Review Report in Attachment 8A. The supplementary peer review covered the walkdown of the inaccessible items and resolution of the comments on the licensing basis evaluations.

REFERENCES:

1) CNS-1465.00-00-0007, Rev. 2, Seismic Design Bases Specification Document

2) UFSAR Section 3.2.1 Seismic Classification

3) UFSAR Section 2.5.1.2 Site Geology

4) UFSAR Sections 2.5.2.6, 2.5.2.7 SSE/OBE

5) UFSAR Section 3.7 Seismic Design

6) CNC-1206.03-00-0202, Rev. 0, 10CFR50.54(f) Rec. 2.3 Fukushima Seismic Walkdowns

7) EPR'I Report 1025286, Dated June 2012, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force (NTTF) Recommendation 2.3

8) Catawba Response to GL 88-20, Individual Plant Examination of External Events (IPEEE) Submittal, dated June 21, 1994, D.L. Rehn to NRC.

9) CNC-1535.00-00-0006, Rev. 0, Seismic Hazard Curve Sensitivity for the Catawba IPEEE.

10) CNC-1535.00-00-0005, Rev. 3, Seismic Capacity Evaluations for IPEEE and EPRI Margins Study.

11) Equipment Deficiencies Identified During the 1994 IPEEE Seismic Walkdowns - (See Ref 8 Table 3-3).

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3:

NRC Submittal report for Seismic Walk-downs Catawba Unit 1 Page 15 of 15

12) CNS-1108.00-00-0002, Rev 11 "Specification for the Response Spectra and Seismic Displacements for Category I Structure

13) 7/9/12 correspondence to NRC from Ben C. Waldrep, "Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident" ATTACHMENTS:

1A) Catawba Unit 1 SWEL-1 Base-1 List 2A) Catawba Unit 1 SWEL-1 3A) Catawba Unit 1 SWEL-2 Base-2 List and Rapid Drain Down List 4A) Catawba Unit 1 SWEL-2 5A) Seismic Walkdown Summary Report and Checklists (Shaw/ARES Report) 6A) Peer Review Summary Report 7A) Seismic Walkdown Summary Report and Checklists (Duke Report) 8A) Supplementary Peer Review Report

I CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 1 of 36 Attachment 1 Page 1 of 36 Unit 1 SWEL - 1 "Base List" The Catawba Unit 1 SWEL- 1 "base list" is a copy of the original IPEEE list for Unit 1, as recorded in Calculation CNC-1535.00-00-0005, rev. 0. A copy is provided as Attachment 1.

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 2 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1 535.00-00-O005 Rev. O sht I of Lt Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study BY: 1ýJ. je,,, e.ý4Ck. By: -

Attachment 1 Page 2 of 36 PROBLEM STATEMENT:

NRC Generic Letter 88-20 requests nuclear plant licensees to perform Inlividual Plant Examinations for Extrernal Events (IPEEE) for several topics including seismic events. NUREG 1407 identifies acceptable methods for performing the Seismic IPEEE. The purpose of the seismic examination is to review the seismic margin of selected plant structures, components, and quipment for seismic vulnerabilities using a review level seismic event of O.30g peak ground acceleration. A seismic margi/ assessment was already done of CNS Unit 2 for an EPRI trial plant review in 1986 and 1987. It used the criteria of EPRI NP-6041 and was documented in EPRI NP-6359 (see the reference list below). The method selected for the Catawjba Seismic IPEEE consists of the EPRI Seismic Margins Me.thodology and the existing Catawba Probabilistic Risk Asseyment (PRA) along with the enhancements outlined in NUREG-1407. Use is made of work already done in the EPRI trial plant seismic margin assessment. Walkdown and evaluation documentation from that assessment is included along .with more rece walkdown and evaluation documentation in the attachments to this ,,/

calculation. Walkdodwns also serve the purpose of helping to validate the seismic portions of the Catawba PRA. The Seismic Review Team (SRT) for the walkdowns consisted of W.M. Hogan, D.A. Kaul, J.T.Gruber, and W.B./

Shoemaker. All are registered professional engineers. The SRT for the earlier seismic margin assessment consisted of D.R. Kulla, W. B. /

Shoemaker, B.F. Henley, and R.D. Campbell. All are registered professional engineers. No training was available at the time the earlier work was done.

R. D. Campbell is a recognized industry expert in the area of seismic evaluations of nuclear power plants. He was the primary author of the EPRI seismic margins criteria document, Reference (1). The Catawba Seismic Margins Assessment as documented in Reference (3) is recognized throughout the industry and is referenced in NUREG 1407. Given the standards available at the time each of the two portions of the seismic review was done, the Seismic Review Team meets the requirements and intent of EPRI NP-6041 and NUREG 1407.

This calculation and its attachments provide the documentation jor the seismic walkdown and evaluation for the CNS Seismic IPEEE. /

The Safe -Shutdown Equipment Lists (components to cover on walkdowns) were provided by P. T. Farish in a letter of March 11, 1993, file no. CN-

9. 1535.00 (copy in attachment to this calc.) .

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CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 3 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1535.00-00-0005 Rev, 0 sht 2 of Lf S6ismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study YBy( Ck. By: rffzi Attachment 1 QA CONDITION Page 3 of 36 This calculation is non QA Condition DESIGN J ANALYTICAL METHOD This calcuation performs no design, and it is not used to support any design /

basis designs. In the calculation attachments information gathered in seismic margin walkdowns is compiled, and evaluations are performed using the methods given in EPRI NP-6041. Any other method that may be used are documented where such methods are used in the attachments.

APPLICABLE CODES AND STANDARDS EPRI NP-6041 and NUREG-1 407 are used. Where other codes and 7 standards are recommended by these two publications such codes and standards are referenced.

DESIGN INPUTS Evaluation inputs are identified as applicable in the attachments. /

I F SAR The FSAR does not address IPEEE. This calculation has no impact on the FISAR.

ASSUMPTIONS Structure and equipment qualification data in design documents were used to help evaluate seismic margin. Other assumptions are identified as applicabl'e in the attachments.

9.

ID 1,) 1*'1

CNC-1206.03-00-0203 Rev 0 A Page 4 of 36 Catawba Nuclear Station Units 1 & 2 File No.: CNC-1535.00-00-0005 Rev. 0 sht 3 of t+

Seismic Capacity Evaluations for the IPEEE and EPRI Seismic Margins Study B: Ck. By:

C(

SOURCES OF INFORMATION I REFERENCES (1) NUREG 1407, "Procedural and Submittal Guidance for the individual Plant Examination of External Events," June, 1911 (2) EPRI NP 6041, "A Methodology for Assessment of Nuclear Plant Seismic Margin," Rev 0, Oct., 1988, Rev. 1,Aug., 1991 (3)EPRI NP-6359, Seismic Margin Assessment Margin Assessment of the Catawba Nuclear Station," April, 1989 (4)P. T. Farish letter to W. B. Shoemaker of March 11, 1993, IPEEE Safe Shutdown Equipment Lists, file CN-1535.00.

Other sources of information and references are sited where appropriate in the attachments.

CALCULATION The results of the walkdowns, evaluations and other backup information are/

provided in the attachments.

CONCLUSION N'o significant areas.of plant vulnerability were identified. Modification of the Diesel Generator Battery racks (and addition of spacers) was implemented largely as a result of the EPRI trial plant seismic margin assessment (NSMs CN-1 1161 and CN-20540) . One or two other minor improvements were made to the station which slightly reduced seismic vulnerabilties. These improvements are noted where appropriate in the calculation attachments.

.:,] :Li; o :1. :. Attachment 1 Page 4 of 36

CNC-1206.03-OO-0203 Rev 0 Attachment 1A Page 5 1of 36

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L3/4IWALK~ow&IS E, VýqL44rtoN5 llVý3ktf PAOT 3 CW*TAIN.MEN r (t2' WAL-2Y's s S9 NtS EWYINEýEIN~4r SVALAArto.JS ý-O EPAI SE~i6MC.

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FOR EPRI Wt5mLcf VNAPeh-eS 4rSESSMErJr OP: CAS L4t-ItT Z A.Jb COb~VAMON AOCAS WAUAL O,Jt-JS Fcflk F-Pez s:t&mt~c. mA P(;t tS A ES5MEN~T OP' c-N5 FRG1r'- EAV Lt4iA &5tO F cCN S 9 N~ Rizio'Vr Polk iper OV* w6-1~ 2-2ý11 Nld(vv4&" A-4FS%'E'JT OF TRIE C~tAISAA I"J(Ct--AP Sft-rJdON-'

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Attachment 1 Page 5 of 36

CNC-1206.03-00-0203 Rev 0 A Page 6 of 36 4rA -r&C HA~e - Toa Ci'JC (3s-.OO-COc-OOOý-

P(rA6- I Ct-.s %PE1E: Po~LiMpNJAVi5 RELA-Y EVAL, M-frMO Bvpui- PtPfi W~ALYoL-OWNi COVVA3/4NNT.

Attachment 1 Page 6 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 7 of 36 AT -r A c 1ý r,-\ P (,j T- *VCjN.j 113, 3 7.z2 0 0Q 0 00 a March 11, 1993 p'A(E 2.

Catawba Nuclear Station Re: Catawba Nuclear Station, Utnits I & 2 Individual Plant Examination - External Events Safe Shutdown Equipment Lists File: CN-1535.00 Please find attached for your use and information a copy of the safe shutdown equipment lists (SSELs) for Unit 1 as well as the lists of equipment required for the containment performance evaluation of Units I & 2.

Questions regarding the equipment selection may be directed to me at 382-6755.

P. T. Parish, Engineer

1) Nuclear Engineering - Severe Accident Analysis Nuclear Services Attachment cc: P. M. Abraham R. W. McAuley H. D. Brewer R. C. Bucy (CNS)

R. S. Bondurant (CNS)

J. H. Knuti (CNS)

Central Records

ý F-V-- CL APR 1(7 1C.PrT IC) NS (t O 1,4rN-F-0

ýOkA-.-o( iN G WJ0 (011711 ID () 1"I .. -I; !::;

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Attachment I Page 7 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 8 of 36 P 17 TO CNC- N!;3S.oo 000s PA&(T 3

'4 GENERIC LETTER 88-20; SUPPLEMENT 4 INDIVIDUAL PLANT EXAMINATION - EXTERNAL EVENTS SELECTION OF SAFE SHUTDOWN EQUIPMENT FOR SEISMIC EVENTS CATAWBA NUCLEAR STATION - UNIT 1

.)

Prepared By Reviewed By __

0)

Approved By 3111lq 3 IJ cl l:'l 1,.:l Attachment 1 Page 8 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 9 of 36 GENERIC LETTER 88-20; SUPPLEMENT 4 d INDIVIDUAL PLANT EXAMINATION - EXTERNAL EVENTS SELECTION OF SAFE SHUTDOWN EQUIPMENT FOR SEISMIC EVENTS CATAWBA NUCLEAR STATION - UNIT I In the NRC policy statement on severe accidents, issued on August 8, 1985. the Commission concluded that existing nuclear power plants pose no undue risks to the public health and safety.

The Commission also concluded that systematic plai*-specific examinations are beneficial in identifying plant vulnerabilities to severe accidents that could be fixed with low cost improvements. The staff issued Generic Letter 88-20 on 11/23/88, requesting that each Licensee conduct an individual plant examination (IPE) for internally initiated events. To satisfy the IPE requirement, Duke utilized the Catawba PRA report, which included the analysis of internal and external events. The Catawba EPE was submitted to the NRC in September 1992.

Supplement 4 to G.L. 88-20 was issued on 6/28/91 and requested a systematic, individual plant examination for severe accidents initiated by external events (IPEEE). Among the events to be assessed was the plant's response to a seismic event.

There are two acceptable methods for responding to the IPEEE, as identified in NUREG-1407 and EPRI NP-6041, Rev. 1; (1) use of the seismic PRA and (2) the Seismic Margin Assessment

)* (SMA) method. In addition, NUREG-1407 includes an assessment to identify vulnerabilities that involve the early failure of containment functions. In order to determine the seismic acceptability of the plant, walkdowns will be conducted of the various systems required to achieve safe shutdown and maintain containment performance. To this end, a listing of the various components and structures required for safe shutdown and containment performance will be prepared for use by the Catawba Seismic Review Team (SRT) to carry out the plant walkdowns.

The purpose of this document is to identify the various components and structures required for safe shutdown and containment performance after a seismic event and to detail the selection process employed, The listings generated herein will be used by the Catawba SRT in conducting walkdowns to assess the plant's response to a seismic event.

Methods of IPEEE Resolution As mentioned above, there are two acceptable methods for IPEEE resolution. These are detailed below, Final selection of the components and structures are based upon these two methods.

Si

:: ":* Attachment 1 Page 9 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 10 of 36 I) Semi MuA3c od -

I. Catawba has previously generated a seismic PRA as part of its formal PRA report.

Initially, seismic hazard curves for peak acceleration were developed (Catawba currently uses hazard curves developed by EPRI using the Seismicity Owners Group methodology for seismic hazards analysis of nuclear power plant sites in the central and eastern U.S.).

Next, an event tree was generated to characterize the plant response to a seismic event.

With the subsequent core melt sequences identified, a fault tree was then produced to determine flte failure sequences (cut sets) of interest. Using previously estimated fragilities of key components and structures, the conditional probability of failure as a function of ground acceleration was ascertained. Finally, a resulting set of dominant accident I sequences was developed based upon a convolution of the fragilities, fault tree cut sets, and the seismic hazard curve.

The plant component fragilities used in the analysis were calculated by Structural Mechanics Associates. The walkdowns by the SRT will complement these fragility estimates.

Thus, the seismic PRA method primarily identifies areas of seismic vulnerability by determining a set of dominant accident sequences and components.

2) SMA Method -

The SMA method, as described in NP-6041, defines an earthquake level (or a 'margin')

above the design basis earthquake for which the ability to safely shut the plant down can be demonstrated with high confidence in a cost-effective manner. It is the NRC staffs

) judgment that the use of a 0.3g review level earthquake for most nuclear plant sites in the central and eastern U.S. would serve to meet the objectives of the [PEEE. The SMA process is based upon a systems "success path" approach that defines and evaluates the capacity of the components required to bring the plant to a safe shutdown condition (either hot or cold) for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (further assumptions used in the analysis are given in the "Basic Assumptions" section of this report). Since several possible success paths may exist, cognizant engineering and operations personnel are needed for proper selection. Once chosen, a walkdown of the selected shutdown paths will determine whether the components and structures identified therein are in compliance with the 'seismic margin'.

Furthermore, the NRC defines Catawba as a 'focused-scope' plant requiring an evaluation of low-seismic-ruggedness relays in the shutdown paths. The relays associated with the shutdown paths will be reviewed against a 'bad actors' list (from EPRI NP-7148SL). The related power supply cabinets will also be reviewed for seismic ruggedness.

Method of Selection for Safe Shutdown EuLfi n A review of the current Catawba PRA report was conducted to determine those components and systems considered as important to safe plant shutdown from a PRA perspective. The review inicluded the Seismic fault tree (PRA report Section 3.2) and the Small-Break LOCA fault tree (PRA report Section 2.3) along with their respective transfers to other system trees. The ihdivldual shutdown system fault trees were also reviewed to obtain other key components, 0

!: ..." :1. ý::t I ('J 1-1ID  !::; .::[

Attachment 1 Page 10 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 11 of 36 power sources, etc. "the components and structures of concern to the seismic PRA are so noted d in the resulting equipment lists. Jj Next, in accordance with NP-6041, two success paths (primary & alternate) per the SMA approach were selected to perform each of the following shutdown functions:

o Reactivity Control o RCS Pressure and Inventory Control o Decay Heat Removal The Catawba Unit 2 SMA pilot study (EPRI NP-6359) was also used as a guide for success path selection. AlI the primary and alternate 'front-line' systems required to execute each shutdown function are shown in Table I along with their 'support' systems.

With the proper front-line and supporting systems identified, engineers traced out the success paths on the respective system flow diagrams, relying upon their knowledge and experience, Individual components and instruments were noted and listed. Several components were designated as "pressure boundary integrity only" which signifies components which are part of the pressure boundary but do not perform an active function.

MthQd of Selection for Containment Perfornanc*

The equipment and structures necessary to support containment performance were selected per guidance from NUREG-1407. The PRA report was used to generate an initial listing and included the Seismic Containment Safeguards fault tree (PRA report Section 3.2) and the Containment Safeguards fault tree (PRA report Chapter 4) along with their respective transfers to other system trees. The individual system fault trees (including the Containment Isolation fault tree) were also reviewed to obtain other key components, power sources, etc.

wgi Process Following their preparation, the initial equipment lists were reviewed by licensed operators for sound selection methodology and conformance to existing procedures. Other systems engineers were included as necessary to complete the review. The resulting comments were incorporated and the finalized safe shutdown and containment performance equipment lists are given in Tables 2 through 5. A diskette with these tables will be given to the SRT so that walkdown information can be added per reporting requirements.

I) Per IPEEE guidelines, the plant undergoes a seismic event and loses off-site power. A small-break LOCA (1 in.) is also incurred. The plant must maintain shutdown status for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />,

2) Plant shutdown is conducted using cold leg injection. For a small-break LOCA, the cold leg accumulators are excluded since this is a relatively controlled shutdown situation.

PAttachment 1 Page 11 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 12 of 36

3) Assume initial suction is from the RWST (rather than through the Volume Control Tank) iuntil RCS temperature and pressure are low enough to initiate RHR.

4) Assume manual valves, check valves, non-active relief valves, and piping are seismicaUy rugged.

5) The analysis is based upon bringing the plant to hot shutdown with the option of going to cold shutdown with RI-R.

6) Instead of the normal Containtment Spray System (NS), the RHR Auxiliary Spray headers will be used to mitigate any containment pressure increases.

1) NUREG-1407; "Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities"

2) EPRI NP-6041, Rev. 1; "A Methodology for Assessment of Nuclear Power Plant Seismic Margin"

3) EPRI NP-7148SL; "Procedure for Evaluating Nuclear Power Plant Relay Seismic

, Functionality"

4) EPRI NP-6359; "Seismic Margin Assessment of the Catawba Nuclear Station" 5 Catawba Flow Diagrams -

CN-1553-1.0, -1.1; NC System CN-1554l...0, -1.1, -1.2,-1.5, -1.6, -1.7; NV System CN-1557 (2557)-l.0; VX System CN-1557-2.0; VZ System CN-1561 series: ND System CN-1562-1.0, -1.1, -1.2, -1.3; NI System CN-1563-1.0; NS System CN-1571-1.0; FW System CN-1573-1.0, -].1, -2.0, -2.1, -2.2; KCSystem CN-1574-1.0, -1.I, -1.2, -1.4, -2.0, -2.1, -2.4, -2.5; RN System CN- 1577-1.0, - . i, -. 2, - .3; VA System CN-1578-1., -1.1, -1.2, -1.4. -1.5; VC System CN-1578-2.x series; YC System CN-1579-1.0; VD System I CN-1591-1.1; CFSystem CN- 1592 series; CA System I CN-1593-1.0, -1.1, -1.2, -1.3, -1.7 series; SM, SV Systems CN-1609 series; D/G Support Systems (KD, LD, FD, VG, VN)

6) Catawba Final Safety Analysis Report (FSAR); dated 10/91

, 7) Catawba Probabilistic Risk Assessment Report dated 9/22/92

,, ,H I.-' , ,. * :l.;~:Attachment 1 Page 12 Of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 13 of 36 WIGOKI Fuel Me-mbers this report; however, those Several individuals were involved with the preparation and review of primarily responsible are listed below:

N= orkA=*

Paul T. Farish Nuclear Services / Nuclear Engineering William B. Shoemaker Catawba / Civil Engineering Russell C. Bucy Catawba / Mechanical Engineering R. Stuart Bondurant Catawba I Electrical Engineering John H. Knuti Catawba / Operations

)

9 Attachment 1 Page 13 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 14 of 36

@ !r £09" TABLE 1 -

LISTING OF PRIMARY & ALTERNATE SHUTDOWN PATHS 0 Reactivity Control -

PrimaryPath:

Front-line System - Reactor Protection System (control rod insertion / Reactor Trip Breakers)

Support Systems - None Alternate Path:

Front-line Systems - NV, NI (emergency boration flowpath), FW Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC. Vz, YC 0 RCS Pressure and Inventory Control -

I Primary Path:

Front-line Systems & Components - CA (Motor-Driven Pumps), SO PORVs, Main Steam Isolation Valves, SG Safety Relief Valves, NV, NI (not required for inventory control for I" SBLOCA). FW Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC, VZ, YC Alternate Path:

Front-line Systems & Components - PZR PORVs, NV. NI (nitrogen aligned from cold leg accumulators for PORV actuation)

Support Systems - RN, KC. Diesel Generators & supporting systems *; VA, VC, Vz, YC The following systems are assumed to be used for all DIG support functions:

FD, KD, LD, VD, VG, VN Attachment 1 Page 14 of 36

GNG-1206.03-00-0203 Rev 0 Attachment 1A Page 15 of 36 TABLE 1 (cont.) -

t4ji C£10 d LISTING OF PRIMARY & ALTERNATE SHUTDOWN PATHS o1 Decay Heat Removal -

PrimaryPath:

Front-line Systems & Components - CA (Motor-Driven Pumps), SG PORVs, ND (if cold shutdown is needed)

Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC, VZ, YC Alternate Path:

Front-line Systems & Components - PZR PORVs, NV, NI (nitrogen aligned from cold leg accumutdatorsfor PORV actuation), ND (if cold shutdown is needed)

Support Systems - RN, KC, Diesel Generators & supporting systems *, VA, VC, VZ, YC

- The following systems are assumed to be used for all DIG support functions:

FD, KD, LD, VD, VG, VN Attachment 1 Page 15 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 16 of 36 1

TABLE 2 - 1I G11 MECHANICAL EQUIPMENT LIST FOR CATAWBA UNIT I IPEEE WALKDOWN 1____________ -1 1 -- - 1.

('R' trnln c mr)nneril.q are shown In onreniheses. A detailed wdlkdown of ti'~ese comoonenfs i~not nece__ a If the train configuration Is similor to the 'A' troin,--5 - I-

_ _--_Line Included In - Press. bndry. _

CA SYSTEM COMPONENTS Size (in.) Seismic PRA Integrity only AOV10ICA56 (40) , 4 _ __

AOV ICA60 (44) 4 __

MOV 1CA-A 10 _ _X MOV ICAI)A (98) 10 X MOV ICA1SA (18B) 6 MOV 1CAS4B (38A) 4 X MOV 1CA5BA (42B) 4 MOV ICA62A (468) 4 __

MOV ICA66B (50A) 4 X MOV 1CA174 .8 X MOV 1CA175 8 x __

ALITO.-RECIRC. VALVE ICA27 (32)

ALTO.-RECIRC. VALVE ICA20 TURBINE DRIVEN PUMP I _ x

) TOP TURBINE LUSE OIL COOLER MOTOR DRIVEN PUMP )A (11)

UPPER SURGE TANK x CONDENSER HOTWELL x CONDENSATE STORAGE TANK x The following Unit I components were included on the Unit 2 watkdown:_

I MOV iCA85B MOV 1CA116A HYDRAULIC VLV 1CF33 HYDRAULIC VLV 1CF42 HYDRAULIC VLV 1CF51 HYDRAULIC VLV 1CF60 DIESEL GENERATOR AND SUPPORTING Line included In Press. bndry.

COMPONENTS I Sze (In.) Seismic PRA __Integrlly only DIESEL GENERATOR )A (1B) X 9 SOLENOID VALVE 1FD22 (62)

FD DIG FUEL OIL FILTER 1A O1B) _

2 Page 1 Attachment 1 Page 16 of 36

CNC-1206.03-00-020 3 Rev 0 Attachment IA Page 17 of 36 TABLE 2 - @1i 012 DIESEL GENERATOR AND SUPPORTING Une I Included in Press. bndry.

COMPONENTS (cont.) Size (in.) Seismic PRA FD D/G FUEL OIL DAY TANK IA (OB) .... _

FD D/GFUEL OIL PUMP STRAINER IA (1B) 8 ..

FD D/G FUEL OIL STORAGE TANKS IA1, 1A2 (1B 1, 182)

FD DIG FUEL OIL PUMP 1A (10) B KD D/G ENGINE JACKET WATER COOLER IA (IB)

KDD/G ENGINE JACKET WATER CIRC. PUMP IA (IB)

KD D/G ENGINE JACKET WATER STANDPIPE ]A (1B)

AOV ILD4 (34) 3 .

AOV 1LD27 (57) 3 SOLENOID VLV ILD 122 (123) . 2 X LD D/G GOVERNOR LUBE OIL COOLER ID D/G LUBE OIL FILTER )A (IB1)__

LID D/G, LUBE OIL COOLER IA (I B)

LD D/G LUBE OIL STRAINER IAl (IB1) & IA2 (1B2)

LD DIG LUBE OIL SUMP TANK P A (IB) _ _

LG DIG ENGINE LUBE OIL PUMP IA (I B)_

VOD ELECTRO-HYDRAUUIC DAMPER IDSF-D-1 C7)___ _____ ____

VID ELECTRO-HYDRAULIC DAMPER 1DSF-D-2 (8) ,_ ,_

VD ELECTRO-HYDRAULIC DAMPER IDSF-D-3 (9)

VD ELECTRO-HYDRAUUC DAMPER 1DSF-D-4 (10)

) DIESEL BLDG. VENTILATION FANS IA1, 1A2 (1B. 1B2)

SOLENOID VALVE I VG25 (69) ____ ______ _____

SOLENOID VALVE 1VG26 (70) . 3 .....

SOLENOID VALVE IVG27 (71) 3 SOLENOID VALVE IVG28 (72) ' 3 _ .... ._

VG DIG ENGINE STARTING AIR TANKS iA1, 1A2 (IB, 1132)

- .I I .... I VN D/G ENGINE IWAKE AIR FILTERS IA), IA2 (IB1, 182)

VN D/G ENGINE INTAKE AIR SILENCERS IA. 1A2 (0IBI. IB2)

VN D/G ENGINE EXHAUST SILENCER IAI, 1A2 (181,182)

VN D/G ENGINE AFIERCOOLERS IAI, IA2 (131, 112)

VN D/G ENGINE TURBO-CHARGER IA , 1A2 0IB1, 112)

LiUne Included In Press. bndry....

FW SYSTEM COMPONENTS Sie (in.) Seismic PRA Inteqrqy only MOV IFWIA (32B) 4 j MOV IFW27A (558) 12 _

MOV 1FW33A (49B) 2.

9l R RWST (REFUEUNG WATER STORAGE TANK)

-T x-X Page 2 Attachment 1 Page 17 of 36

I CNC-1206.03-00-0203 Rev 0 Attachment IA Page 18 of 36

.I TABLE 2 - Ufl Gi~

-- KcSYSTEM COMPONENTS_ Ue .)

Siz_ . eIncluded In Press. bndoy _

KC SYSTEM COMPONENTS Sie(I. _ esmic PR~A in~tegrity only _

a&AOV 1ý 0 IKC57A (82B)

.. I . I ----- ------ --t-AOV 1KCD29 2 MOV 1KCtA (2B) 20 MOV )KC3A (18B) __ lO ,,10 MOV 1KC5OA (53B) 20 - __

MOV IKC51A (5413) 4 _ _

MOV 1KC56A (818) 16 MOV 1KC230A (228B) . 8 MOV 1KCC37A .(408) _ 6 KC HX IA (11)

KC PUMPS 1AI, 1A2 (011, 112) _t KC SURGE TANK IA (1B) -

RHR PUMP MECH. SEAL HX 1A (I)B)

KC PUMPS IA1, 1A2 (1B1, 112) MOTOR COOLERS '  !

AUX. SHUTDOWN PANEL AREA AIR COND, UNIT 1A - X CA MOTOR-DRIVEN PUMP IA (18) MOTOR COOLER RHR PUMP MOTOR COOLER A(1) A___

Q____

B)___

NI PUMP MOTOR COOLER IA (1B) , _ X NI PUMP BEARING OIL COOLER IA (18) ' x NS PUMP MOTOR COOLER ]A (Q13) X NV PUMP MOTOR COOLER IA (18)

NV PUMP MOTOR SPEED REDUCER OIL COOLER 1A 1B)

Une Included in Press. bndry,.

NC SYSTEM COMPONENTS Size (in.) Seismic PRA integrity only, SAFETY RELIEF VALVE INC 1_. 6 X _ __

SAFETY REUEF VALVE 1NC2 6 X SAFETY REUEF VALVE 1NC3 6 X PZR PORV 1NC32B 3 X PZR PORVW NC34A 3 X PZR PORV: INC36B 3 X MOV 1NC31B1 3 MOV INC33A 3 MOV I1NC358 3 I PZR HEATER BANK A (B) 3

_________________________________________ 3 _______ _______

Page 3 Attachment 1 Page 18 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 19 of 36 TABLE 2 -

., . /IA Line ( I Included In Pe bndi_.

ND SYSTEM COMPONENTS Size (in.) Sesic PRA r . yonlyJ W'AOV 1ND26 (60) 8 AOV IND27 (61) __ 8 ....

MOV I ND 1B (368) __ J12 ,. _.

MOV 1ND2A (37A) . 12 _

MOV IND24A (588) 2 MOV 1ND25A (59B) 2 ----

MOV IND32A (65B) 2 X MOV IND90 (91) 2 X ND PUMP 1A (1 B)

ND HX 1A (1B) x MOV IND28A was included on the Unit 2 walkdown.

Une Included In Press. bndry. .

NI SYSTEM COMPONENTS Size (in.) Seismic PRA Integrify only AOV IN150 (72) 1 AOV 1N156 I x AOV 1NI57 0.75 X AOV 1N158 0.75 X AOV IN16] (84) 1 AOV 1N1671 1 X AOV 1N1689 0.75 X AOV IN169 0.75 X AOV 1N178 1 X AOV 1N179 0.75 X AOV 1N180 0.75 X AOV INi9O 1 X AOV 1N191 0.75 X AOV 1N192 0.75 X AOV 1N1391 (393) 0.75 X AOV 1NI392 (394) 0.75 X MOV 1NI9A (10B) 4 MOV 1N154A (76A) 10 X MOV 1N16SB (88B) 10 X MOV 1NI1OOB 8 X MOV IN1103A (135B) 6 X MOV 1NI115A (144A) 2 X MOV 1NI118A (150B) 4 X MOV 1N1120B 0.75 MOV 1NI121A (152B) 4 X AMOV 1N1136B 8 _

MOV 2 xNl1478 Page 4 I.-I1:ti I1:1 :i. :1.

Attachment 1 Page 19 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 20 of 36 I.

TABLE 2 - U", £.15

___Une Included in Press. bndri. _y .

NI SYSTEM COMPONENTS (cont.) Size (in.) Seismic PRA Integrity only __

MOV IN1173A (1788) 8 MOV I NI 83B 12 MOV INII85A (184B) 10 MOV N1N332A 6 MOV INI33313' 6 MOV 1N13348 (1368) ,. 6 NI PUMP ]A (11)

MOV 1N1438A (N1RMOGEN BACKUP .O PZR PORV) I X MOV 1NI4a9,g (NiTROGEN BACKUP TO PZR PORV) 1 X Une Included In Press. bndry.

NV SYSTEM COMPONENTS Size (In.) Seismic PRA Integrity only, AOV 1NV52A 2 x AOV 1NV63B 2 x AOV 1NV74A 2 x AOV 1NV85B 2 X AOV 1NVI01A 0.75 1 X AOV INV2943 AOV3 ___ x MOV INV4A 2 X MOV INV5A 2 Ix Mov INV66A 2 X MOV 1N77A 2 X MOV I1NV89A (91B) "4 X MOV 1NV,188A (18983) ' 4 X MOV INV203A (2028) 2 X MOV 1NV252A (2538) ........ 8 MOV 1NV312A (3140) .... 3 _ ,,,

CENTRIFUGAL CHARGING PUMP IA (I B)

SEAL WATER INJECTION FILTER IA (IB) "_

,_...Line Included In Press. bndry.

RN SY"EM, COMPONENTS Size (In.) Selsmic PRA Integrity only I

AOV IRN291 (351) 12 MOV IRNI1A (5A) 48 1 SMOV IRN2B (6B) 48 OV IRN30OA (408) 4 i .

Page5

1,. i: ;:: I] Attachment 1 Page 20 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 21 of 36 TABLE 2 - tuli Ci

_ Line Included in Press. bndy.

RN SYSTEM COMPONENTS (Cont.) Size (in.) I, Seismic PRA Ierionl MOV IRN36A (37B) 4 MOV IRN48B (47A) 20 MOV IRN49A (50B) 20 MOV 1RN51A (52B) 20 MOV IRN54A (53B) 42 MOV IPN63A (58B) 42 MOV IRN144A (225B) 18 ---- x MV IRN 148A (229B) 18 X MOV IRN232A (292B) 10 MOV IRN287A (347B) 20 X_--

MOV IRN843B (57A) 42 MOV 1RN846A (848B) 10 _ __

MOV IRNS47A (8498) 10 '

RN STRAINER IA (I8) B RN PUMP IA ( B) UPPER BEARING HX _

RN PUMP LUBE INJECTION SIMPLEX STRAINER A (B)

SNSWP INTAKE (video available) I__.

The following Unit I components and structures were included on the Unit 2 walkdown:

MOV IRN3A ......

) MOV 1RN4B MOV IRN11A MOV 1RN20B MOV 1RN28A MOV 1RN38B MOV IRN67A _ __

MoV IRN69B MOV IRN250A [train B' valve (0RN31OB)NOT reviewed)

ELECTROHYDRAULIC VLV 1RN244A_____ ____

ELECTROHYDRAULIC VLV IRN304B RN PUMP IA RN PUMP 1B ,

RN PUMP INTAKE PIT A BARS, DEBRIS SCREEN, & STRUCTURE RN PUMP INTAKE PIT B BARS, DEBRIS SCREEN, & STRUCTURE _

STANDBY NUCLEAR SERVICE WATER POND -

Une Included In _ Press, bndry.

SA. SM. SV SYSTEM COMPONENTS Size (In.) Seismic PRA Integrity only AoV 1SA2 (5) 4 I AOV 1SM86 2 . X Aov sM7 2- . x Page 6 ID :iD . Attachment 1 Page 21 of 36 I

i

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 22 of 36 TABLE 2 - Wi G17

______ _____Une included in Press. b~ndr, SA, SM, SV SYSTEM COMPONENTS (cont.) Size (in.) Seismic PRA integrity only AOV 1SM88 2 X AOV 1SM89 2 X MOV ISM74B 2 X MOV 1SM75A 2 X MOV ISM76B 2 X MOV 1SM77A 2 X MSIV 1SMI 34 MSIV ISM3 34 ....

MSIV ISM5 34 MSIV 1SM7 34 MSI BYPASS VLV 1SM9 3 x MSI BYPASS VLV ISMIO 3 x rMSI BYPASS VLV iSMI1 3 x MSI BYPASS VLV lSM12 3 x SG PORV ISV1 6 X SG PORV ISV? 6 X SG PORV ISV13 6 x SG PORV ISV19 6 X

) SG SRV 1SV2 6x 10 x SG SRV ISV3 6x 10 x SG SRV 1SV4 6x 10 x SG SRV ISV5 6x 10 x SG SRV ISV6 6x 10 x SG SRV 1_SV8 6x 10 x SG SV ISV9 _ 6x 10 x SG SRV, 1SV10 6x 10 X SG MV: ISVi I 6x)o 1 X SG Sv 1SV12 6x 10 X SG SRV: 1S__1_4_ 6x 10 x SG S 1SV15 _V 6_x 10 X SG SRV 1SV16 6 _ __ X ISG SRV 1SV1 7 6x 10 X SG SRV ISV18 6x10 x SG SRV 1SV20 6x 10 x SG S ISV21

_V 6x I0 X SG SRV ISV22 6_x 10 X SG_ V23_ 6x10 W _SV23_X SG SRV

_ SV24 6x 10 x MOV 1SV25B 6 X 9 MOV ISV26B MOV_SV27A ...... _6 6 x x

1SV28A 6OV 6 X Poge 7 I.j I.! .::~  ::j .*~; Attachment 1 Page 22 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 23 of 36 TABLE 2 - bI1-018 Une Included In Press, bndq -

VA SYSTEM COMPONENTS Size (In,) Seismic PRA integrty only 4 MOV IVA28B(31A) 6 __._Xx MOV IVA29A (30B) 6 X AIR-OPERATED DAMPER 1ABF-D-10 (3)

AIR-OPERATED DAMPER IABF-D- 12 (5)

AIR-OPERATED DAMPER IABF-D- 14 (7)

AIR-OPERATED DAMPER 1ABS-D- 1(3)

ELECTRO-HYDRAUUC DAMPER IABF-D-4 ELECTRO-HYDRAULIC DAMPER 1ABF-D-6 ELECTRO-HYDRAUUC DAMPER IABF-D-1 1 ELECTRO-HYDRAULIC DAMPER IABF-D-13 ELECTRO-HYDRAUIC DAMPER JABF-D-16 ELECTRO-HYDRAUUC DAMPER IABF-D-18 MOISTURE ELIMINATOR PRHDS-IA (1B) _

AUX. BLDG. FILTER UNIT ABFU-1A (IB)'

AUX. BLDG. FAN ABFXF-1A (1B)

AUX. BLDG. FAN SUPPLY UNIT ABSU- IA (18) _ ,

Line Included in Press. bndry.

VC SYSTEM COMPONENTS ' Size (In.) Seismic PRA Integrty only .

MOV lVC5B 24 MOV ]VC6A 24 MOV IVC7B 4 1 MOV IVC8A 4 ELECTRO-HYDRAULIC DAMPER 1CR-D-2 x ELECTRO-HYDRAULIC DAMPER 1CRA-D-5 ELECTRO-HYDRAULIC DAMPER ICRA-D-7 CONTROL ROOM AHU ICR-AHU-1 PRESSURiZING FILTER 1CRA-PFT-1 PRESSURIZING FILTER FAN 1CRA-PFTF-I CONTROL ROOM AREA AHU 1CRA-AHU-1_

SWITCHGEAR ROOM AHU 1SGR-AHU-1 (2)

SW1TCHGEAR ROOM AHU 1SGR-AHU-3 (4)

HEATER UNIT ICR-H-I X HEATER UNIT ICRA-H-1 x HEATER UNIT ICRA-H-2 x HEATER UNIT 1CRA-H-3 x HEATER UNIT ICRA-H-4 x HEATER UNfT 1CRA-H-5 x HEATER UNIT 1CRA-H-7 ... _ _x Page 8 Attachment 1 Page 23 of 36

CNC-1206.03-00-0203 Rev 0 Attachment IA Page 24 of 36 TABLE 2 - ~j o1%'c

__ __ __ __ __ _-Included intos n VZ SYSTEM COMPONENTS Seismic PRA r Integrity oniv

,J NUCLEAR SERVICE WATER PUMPHOUSE FAN IA. 2A (1B, 2B) __

ELECTRO-HYDRAULIC DAMPERS A3A, A4A (A3B, A4B) _

ELECTRO-HYDRAULIC DAMPERS B3A. B4A (B3B_,.48) - -.

iUne Included In Press. bndny.

YC SYSTEM COMPONENTS Size (in.) Seismic PRA Integrlty only MOV IYC77A. (1218) 2 x ELECTRO-HYDRAUUC VLV IYC26 (100) 2.5 ELECTRO-HYDRAULIC VLV IYC58 (150) 4 ELECTRO-HYDRAULUC VLV IYC 196 (208) 3 ELECTRO-HYDRAUUC VLV 1YC203 (214) 3 ELECTRO-HYDRAULUC VLV IYC264 (274) 3 ,

ELECTRO-HYDRAUUC VLV IYC270 (281) 3 _

CONTROL ROOM AREA CHILLED WATER PUMP 1CRA-CHWP-l YC CHILLER ICRA-C-1 YC COMPRESSION TANK ICRA-CT 1

)

MISC. CIVIL STRUCTURES INSIDE DOGHOUSE X D/G BUILDING X REACTOR COOLANT PUMP SUPPORTS X CONTAINMENT INTERNAL STRUCTURE X CONTROL ROD DRIVE MECHANISM x REACTOR BUILDING X _

AUXILIARY BUILDING SHEAR WALLS ..... X _ __

9l Page 9 Attachment I Page 24 of 36

CNC-1206.03-00-0 2 0 3 Rev 0 Attachment 1A Page 25 of 36 TABLE 3 - 020O~

I ELECTRICAL EQUIPMENT LIST FOR CATAWBA UNIT I IPEEE WALKDOWN I

_____- .1i _ILL__.~~J~1I

('B train components are shown In parentheses. A detailed walkdown of these components is not necessar if the'B troin configuration Is similar to the'A' train.) -__T-

_Included In SUPPORT FOR CA SYSTEM -- Seismic PRA 4160V AC SWITCHGEAR 1ETA (1ETB) - - X 600V AC MCC I EMXC X 6]00V AC MCC I EMXI (1EMXB) X 600V AC MCC IEMXK (IEMXB) X 600V AC MCC IEMXL X 600VAC LOADCENTER 1ELXA x 600V AC LOAD CENTER 1ELXC x 600V AC LOAD CENTER lELXD x 125V DCI PANELBOARD IEPA (1 EPD) _ x 125V DC- DISTRIBUTION CENTER IEDA X 125V DC DISTRIBUTION CENTER IEDE (IEDF) x 120V AC PANELBOARD IERPA (IERPD) x 125V DC VITAL.I&C BATTERY CHARGER IEBA 125V DC VITAL I&C BATTERY CHARGER IECA 125V DC VITAL I&C BATTERY CHARGER IECS 125V DC VITAL I&C BATTERY CHARGER IEDS 48V DC ESFAS TRAIN A (B) SUPPLY POWER

) INSTR. LOOP CONTAINING lCALL/SV/EP0560 (0400)

ýINSTR. LOOP CONTAINING 1CALL/SV/EP0600 (0440)

INSTR. LOOP CONTAINING I CAFE/FT/P 5090 -

INSTR. LOOP CONTAINING 1CAFE/FT/P 5 100_ -_

INSTR. LOOP CONTAINING I CAFE/FT/P 5110 INSTR. LOOP CONTAINING ICAFE/FT/P 5120 i _

INSTR. LOOP CONTAINING 1CAPS5220. 5221, & 5222 (5230,5231 & 5232)

INSTR. LOOP CONTAINING ICFLT/P 5490 (550)

INSTR. LOOP CONTAINING ICFLT/P =500 (555W)

INSTR. LOOP CONTAINING ICFLT/P 5501 (555 1) - ____

INSTR. LOOP CONTAINING ICFLT/P 5510 & P 5511 (5570) ""

INSTR. LOOP CONTAINING ICFLT/P 5520 & I CAP 5521 (5590 & 6591)

INSTR. LOOP CONTAINING I CFLT/P 5630 (5580) _ -_

INSTR, LOOP CONTAINING 1CFLT/P 5540 (5600) 1 INSIR. LOOP CONTAINING ICFLT6610 & P 5612 (5630 & 5632).

INSTR. LOOP CONTAINING ICFLT5620 & P 5622 (5640 & 5642) _ --

POST-ACCIDENT MONITORING INSTRUMENTA7iON 9

Page I Attachment 1 Page 25 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 26 of 36 TABLE 3 - i 1 021 Included in SUPPORT FOR DIESEL GENERATORS ....... ._-- Seis**m -'PRA 125V DC BATTERY / RACK ...... x INVERTERS _ x BATTERY 1DGBA (1DGBB) AND CHARGERS X D/G CONTROL PANEL .... ___ _X DIESEL ENGINE CONTROL PANELV- X D/G NEUTRAL GROUND PANEL X AUC'IONEERING DIODE ASSEMBLY EVDA (EV-B) x LOAD SEQUENCER " _____ X INSTR, LOOP CONTAINING IFDFT5000; IFDLT5003: & 1FDPS5001 thru 5004 __

(5160; 5163; & 5160- 5164) L1 I1 INSTR LOOP CONTAINING IFDFT5I010; IFDLTS013: & 1FDP$5011 lhru 5014 (5170:5173; &*5170-5174) L__

INSTR. LOOP CONTAINING IFDLT5060; 1FDPG5061, 5062 (5200; 5201, 520'2)

INSTR. LOOP CONTAINING 1LDPT/PG5140; .

1IDPS,141; ILDPS/PT5142; ILDPT5,43; & .LDPT5.44 (5170;5171; 5172; 5173; & 5174) _

INSTR. LOOP CONTAINING ILDPG/PS5160 & 1LDPS5300 (5190 & 5310)

INSTR. LOOP CONTAINING ILDIT/PS5200 I I I INSTR. LOOP CONTAINING 1LDPT/PSJPG5220; 1LDPT/PS5230; & 1LDPSS500 ___----,,_

(5240,5250,-) _____ _

INSTR. LOOP CONTAINING 1LDTT/PS5270 .... __.-

INSTR. LOOP CONTAINING 1LDPT/PS5400 (5420) .........._

INSTR. LOOP CONTAINING LGSOC50) ___ _____ _____

) INSTR. LOOP CONTAINING 1VGPS/PGS1 00 & 1VGPSS101. 5102 (5250 & 5251,5252)

INSTR. LOOP CONTAINING 1VGPS/PG5120 & 1VGPS5121, 5122 (5270 & 5271,5272)

Included in SUPPORT FOR FW SYSTEM Seismic PRA 600V AC MCC 1EMXA (IEMXB)

INSTR. LOOP CONTAINING 1FWLT/P 5000 INSTR. LOOP CONTAINING IFWLT/P 5010 INSR. LOOP CONTAINING IFWLT/P 5020 INSTR, LOOP CONTAINING IFWLT/P 5130 Included In SUPPORT FOR KC SYSTEM Seismic PRA 4160V AC SWITCHGEAR IETA (1ETB) X 600V AC MCC 1EMXA (1EMXJ) X_*

600V AC MCC 1EMXI (0EMXJ) _ _X 9 600V AC LOAD CONTROL CENTER 1ELXA 0 ELXB) 125V DC PANELBOARD 1]EPA (1EPB) 11 1

-x

______x 126V DC DISTRIBUTION CEER 1EDE x Page 2 i::' :: J1 Attachment 1 Page 26 of 36

I CNC-1206.03-00-0203 Rev 0 Attachment IA Page 27 of 36

/

TABLE 3 - NI* 022

_______________________ Included In SUPPORT FOR KC SYSTEM (CONT.) Seismic PRA INSTR. LOOP CONTAINING IKCFE/FT/PS/P 5530 (5540) -

INSTR. LOOP CONTAINING 1KCLS/LT/P 56,30 (5640) --

Included In SUPPORT FOR NC SYSTEM Seismic PRA 6900V AC SWITCHGEAR lTD 4160V AC SWITCHGEAR 1ETB x MAIN TRANSFORMER IB AND BUS TRANSFORMER 1ATD TRANSFORMER I EMSX_

AUXILIARY POWER TRANSFORMER lTIA AUXILIARY POWER TRANSFORMER ITIB 600V AC MCC 1EMXC x 60V AC MCC 1EMXD _.,,x 600V AC LOAD CENTER 1ELXB X 120V AC PANELBOARD 1ERPA X 120V AC PANELBOARD 1ERPD x 120V AC VITAL POWER INVERTER IEID 125V DC VITAL I&C SPARE BATTERY CHARGER IEBD 125V DC VITAL I&C SPARE BATTERY CHARGER IECD

) 125V DC VITAL I&C SPARE BATTERY CHARGER I ECS I 125V DC DISTRIBUTION CENTER 1EDD I I____

INSTR. LOOP CONTAINING INCSV/LL0320 INCSVO321, & RCPS INSTR. LOOP CON'AINING 1NCSV/LL0340. 1NCSV0341, & RCPS INSTR. LOOP CONTAINING 1NCSV/LL0360o INCSVO361. & RCPSI _ _

INSTR. LOOP CONTAINING 1NCLT/PT/P 5150 _________ --

INSTR. LOOP CONTAINING 1NCLT/PT/SS5160& 1NCP 5161 _ _  !

INSTR. LOOP CONTAINING INCLT/PT/P 5170; 1NCLT/PT/P 5171; 1NCP 5173; & INCP 5174 INSTR. LOOP CONTAINING INCRD/P 5940 INSTR. LOOP CONTAINING INCRD/P 5970 INSTR. LOOP CONTAINING INCRDIP 5960 INADEQUATE CORE COOLING MONITOR

_ Included In SUPPORT FOR ND SYSTEM , SeismIc PRA 4160V AC SWTCHGEAR IETA (OET8) . ___x 600V AC MCC 1EMXA CtEMXJ) _ X 600V AC MCC 1EMXC X 600V AC MCC 1EMXD ,. _ _x 9 600V AC MCC IEMXS (IEMXL) 125V DC DISTRIBUTION CENTER IEDE (IEDF)

_ - X X

INSTR, LOOP CONTAINING INDFE/PG5040 & )NDPG5041 (5056, 5051) ..... _

Page 3 Attachment 1 Page 27 of 36

CNC-1206.03-00-0203 Rev 0 Attachment IA Page 28 of 36 TABLE 3 - wI 023

_Included In SUPPORT FOR NI SYSTEM Selsmic PRA 4160V AC SWITCHGEAR IETA (1ETB) X 600V AC MCC IEMXA (IEMXB) (1EMXJ) X 125V DC DISTRIBUTION CENTER ]EDE (1EDF) X INSTR. LOOP CONTAINING 1NILT/P 5260 INSTR. LOOP CONTAINING INILT/P 5270

, -Included in

.SUPPORT FOR NV SYSTEM Seismic PRA 4i60V AC SWITCHGEAR lETA OETB) x 600V AC MCC 1EMXA x 600V AC MCC 1EMXJ x 600V AC MCC 1EMXL X 125V DC DISTRIBUTION CENTER 1EDE (IEDF) X 120V DC PANELBOARD IERPC x INSTR. LOOP CONTAINING 1NVFE/FT/CR5120 & INVFf/CR5121_

INSTR. LOOP CONTAINING INVFE/FT5130 & 1NVFT613!I INSTR. LOOP CONTAINING INVFE/F./CR5140 & INVFT/CR5141 INSTR. LOOP CONTAINING 1NVFE/FT5150 & 1NVFT5151 INSTR. LOOP CONTAINING I NVFE/FT/P 5300 & INVP 5301 INSTR. LOOP CONTAINING INVFE/FT/P 5310 & INVP 5311

]) INSTR. LOOP CONTAINING INVFE/FT/P 5320 & INVP 5321 INSTR. LOOP CONTAINING 1NVFE/FT/P 5330 & INVP 5331 INSTR. LOOP CONTAINING I NVPT/P 5620 & INVP 5621 .....

INSTR. LOOP CONTAINING 1NVFE/Ff/P 6080

_____ Included In

SUPPORT FOR RN SYSTEM Selsmic PRA 4160V/ AC SWITCHGEAR IETA (lETS) ..... X 600V AC MCC I EMXA X 600V AC MCC IEMX(E'(1EMXF) "X . .

600V AC MCC IEMXG ,, ,X 600OV AC MCC 1EMXJ X 600V AC MCC lEMXO X 600V AC MC.C IE.MXQ 0 .E.MXR) ,,X 600V AC MCC 2EMXH X 60*0V AC MCC 2EMXP X 600V AC ,LOAD CENTER )ELXA X 125V DC DISTRIBUTION CENTER 1EDE (1EDF) X "

120V DC PANEI-BOARD IERPA X J INSTR. LOOP CONTAININIG 0RNLT/P 7350 9 INSTR. LOOP ,CONTAINING 0RNLT/P 7380]

IN*STR. LOOP CO.NT.AINING 0RWTTP 8130 1 Page 4 Cl Cl Cl 1:*l Attachment 1 Page 28 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 29 of 36 TABLE 3 - U1I 024

_______ __"__Included In UPPORT FOR RN SYSTEM (CONT.) I. SeIsmic PRA

,J INSTR.

INSTR.

LOOP CONTAINING 1RNTE/TT/P 5000 (5010)

LOOP CONTAINING 1RNPT/PS/P 5020 (5030)

INSTR. LOOP CONTAINING 1RNFE/FT/P 5800 (5850)

INSTR. LOOP CONTAINING 1RNFE/FT/P 5930 (5980)

INSTR. LOOP CONTAINING 1RNFE/FT/P 6290 (6340)

INSJ. LOOP CONTAINING IRNLT/P 7400 (7370) Z INSTR. LOOP CONTAINING I RNTEJTT/P 7460 (7430)

INSTR. LOOP CONTAINING 1RNPT/PS/P 7480 (7470)

INSTR. LOOP CONTAINING 1RNFE/FT/P 7520 (7510)

INSTR. LOOP CONTAINING 2RNLT/P 7400 (7370)

Included In REACTOR PROTECTION SYSTEM Seismic PRA REACTOR TRIP BREAKER A (8)

REACTOR TRIP BYPASS BREAKER A (B) included In

) SUPPORT FOR SA, SM, SV SYSTEMS Seismic PRA 600V AC MCC 1EMXC x 600V AC MCC 1EMXD x 600V AC MCC IEMXK X 600V AC MCC IEMXL X 125V DC PANELBOARD 1EPA x 125V DC PANELBOARD IEPD x 120V AC PANELBOARD 1ERPA __x 120V AC PANELBOARD 1ERPD _ _x INSTIR. LOOP CONTAINING ISALL/SVO020 & ISALL/SV0021 _ ....

INSTR. LOOP CONTAINING ISMLL0010 thru 0015 & ISMSV00i0thru 0013 INSTR. LOOP CONTAINING 1SMLLOO30 thru 0035 & 1SMSVO030 thru 0033 INSTR. LOOP CONTAINING ISMLLO050thru 0055 & ISMSV005Othru 0053 INSTR. LOOP CONTAINING ISMLL0070 thru 0075 & 1SMSVO070 thru 0073 INSTR. LOOP CONTAINING 1SMLL/SV/ML0O90 & 1SVLL/SV0091 INSTR. LOOP CONTAINING ISMLL/SV/ML0100 & ISVLL/SVO101 INSTR. LOOP CONTAINING ISMLL/SV/MLO1 10 & 1SVLL/SVOI 11 INSTR. LOOP CONTAINING )SMLL/SV/MLO]20 & .SVLL/SVO_21 INSTIR, LOOP CONTAINING 1SMFE/FT/P 500) & 1SMFT/P 5010 INSTR. LOOP CONTAINING 1SMFE/FT/P 5020 & 1SMFT/P 5030 INSTR. LOOP CONTAINING 1SMFE/FT/P 5040 & 1SMFT/P 5050 INSTR. LOOP CONTAINING 1SMFE/FT/P 5060 & ISMFT/P 5070 _

INSTR. LOOP CONTAINING ISMPT/CRtP 5080 W _

INSTR. LOOP CONTAINING. ISMPT/P 5090 INSTR, LOOP CONTAINING 1SMPT/P 5100 . , ' _._ _

Page 5 O"'1 i::[ O :*!; 7 *; I .*1

! ;i i Attachment 1 Page 29 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 30 of 36 TABLE 3 - 1 025

____ _________________- ____Included In SUPPORT FOR SA, SM, SV SYSTEMS (cont.) Seismic PRA INSTR. LOOP CONTAINING 1SMPT/P 5110 __.0--

INSTR. LOOP CONTAINING 1SMPT/P5120 & 1SMCR5800 _

INSTR. LOOP CONTAINING ISMPT/P 5130 INSTR. LOOP CONTAINING ISMPT/P .5140 __.

INSTR. LOOP CONTAINING 1SMPT/P 5150 INSTR. LOOP CONTAINING 1SMPT/P 5160 INSTR. LOOP CONTAINING ISM PT/P 5170 INSTR. LOOP CONTAINING ISM PT/P 5180 INSTR. LOOP CONTAINING ISMPT/P 5190 INSTR. LOOP CONTAINING ISVEP/MLO 10; & 1SVSVOO1 1 thru 0017 INSMT, LOOP CONTAINING 1SVEP/MLOO70; & 1SVSV0O71 thru 0077 INSTR. LOOP CONTAINING ISVEP/ML0130; & 1SVSVO131 thru 0137 INSTR. LOOP CONTAINING 1SVEP/ML0190; & 1SVSVO191 thru 0197 Included In Seismic PRA SOLID STATE PROTECTION SYSTEM x Included In

) SUPPORT FOR VA SYSTEM Seismic PRA POWER SUPPLY FOR VA SYSTEM INSTR. LOOP CONTAINING lVAPT/P 5000 (5020) X INSTR. LOOP CONTAINING 1VAFE/P 5280 Included in SUPPORT FOR VC SYSTEM Seismic PRA 4160V AC SWITCHGEAR IETA (2ETB) _

600V AC MCC IEMXG (2EMXH) 120V AC PANELBOARD IEKPG (2EKPH) 600/120V AC TRANSFORMER IEKTG INSTR. LOOP CONTAINING IVCPT/P 5160 x Included in SUPPORT FOR YC SYSTEM Seismic PRA 600V AC MCC 1EMXG INSTR, LOOP CONTAINING OYCFELFT P 5000 (5010)

Page 6 Attachment 1 Page 30 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 31 of 36 TABLE 4 -

N) 026 CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNIT 1

________ IPEEE WALKDOWN _ __

CONTAINMENT ISOLATION VALVES Penetr, Valve Position AND PENETRATIONS No. Valve No. Line Size (in.) No*rm Fail Shut. Post UPPER COMPARTMENT PURGE INLET M456 I IVPIB 2 - C-UPPER COMPARTMENT PURGE INLET M456 IVP2A 24 C C C C UPPER COMPARTMENT PURGE INLET M432 IVP3B 24 C -C - C UPPER COMPARTMENT PURGE INLET M432 IVP4A 24 C C C C LOWER COMPARTMENT PURGE INLET M357 1VP6B 24 LC C C C LOWER COMPARTMENT PURGE INLET M357 1VP7A 24 C C C C LOWER COMPARTMENT PURGE INLET M434 IVP8B 24 LC C C C LOWER COMPARTMENT PURGE INLET M434 1VP9A 24 C C C C CONT. PURGE EXHAUST M368 IVP10A 24 C C C C CONT. PURGE EXHAUST M368 1VP1IB 24 C C C C CONT. PURGE EXHAUST M433 1VP12A 24 C C C C CONT. PURGE EXHAUST M433 IVP13B 24 C C C C CONT. PURGE EXHAUST M119 IVPI1A 24 C C C C CONT, PURGE EXHAUST Ml 19 1VP16B 24 LC C C C INCORE INSTR. ROOM PURGE IN M213 IVPI7A 12 C C C C INCORE INSTR. ROOM PURGE IN M213 1VP18B 12 LC C C C

)RE INSTR. ROOM PURGE OUT M140 IVP19A 12 C C C C:

)RE INSTR. ROOM PURGE OUT M140 1VP20B 12 LC C C C CONT. AIR RELEASE M386 IVQ2A 4 C C C C CONT. AIR RELEASE M386 1VQ3B 4 C Al C C CONT. AIR ADDITION M204 1VQISB 4 C Al C C CONT. AIR ADDITION - M204 I 1VQ16A 4 C C C C CONT. HYDROGEN PURGE OUTLET LINE M346 IVY17A 4 C Al C C CONT. HYDROGEN PURGE OUTLET LINE M346 1VY18B 4 C Al C C VENT. UNIT CONDENSATE DRAIN HDR. M221 IWL867A 4 0 Al 0 C VENT. UNIT CONDENSATE DRAIN HDR. M221 IWL869B 4 Al 0 1C EQUIPMENT HATCH ...... 240 C C C PERSONNEL HATCH ..... 1_ C C C LOWER PERSONNEL AIR LOCK C1060 I .... _° 099......

UPPER PERSONNEL AIR LOCK C300 PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)

PERSONNEL AIR LOCK 208 V UNEAR ACTUATOR DOOR LATCHES _____

600V ACNMOC 1EMXC (1EMXD)__________

600V AC MCC 1EMXK (IEMXB) 600V AC MCC 1MXM 600V AC MCC, 1MXO _

600V AC MCC: 1MXR

,=- I _ _ _

Page I Attachment 1 Page 31 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 32 of 36 TABLE 4 -

uI 02I iUne Included In Press. bndry.

HYDROGEN MITIGATION SYSTEM Size (In.) Seismic PRA integrity onIy GLOW PLUG IGNITERS _

600V AC MCC IEMXI (1EMXB) 600/120V AC TRANSFORMER IXFMROO13 (14)

ICE BASKETS & DOORS --

Une Included in Press. bnd*y. .....

NS SYSTEM Size (in.) Seismic PRA Integrity only___

NS PUMP IA (11_)

NS HX IA (I B)

MOV INS18A 12 MOV INS29A (32A) 8 .',,

4160V AC SWITCHGEAR IETA (IE) __,,,

"'%I AC MCC1EMXA DC PANELBOARD I EDE (IEDF)

Une Included in Press. bndry. -

VX SYSTEM Size (In.) Seismic PRA Integrity only AIR-OP. DAMPER IARF-D-5 (-8)

AIR-OP. DAMPER 1ARF-D-6 (-9) .... __

AIR-OP. DAMPER 1ARF-D-7 (-10) I I

MOTOR-OP. DAMPER IARF-D-2 (-4)

CONTAINMENT AIR RETURN FAN 'IA (IS) -

600V AC MCCIEMXK (I EMXL) 120V AC PANELBOARD I EKPI (1EKPB) 9 Page 2 Attachment 1 Page 32 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 33 of 36 1

TABLE 5 -

028

, CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNIT 2

• - IPEEE WALKDOWN CONTAINMENT ISOLATION VALVES Peneir. - Valve Posfiion AND PENETRATIONS No. Valve No. Une Size (h) Nor- FoJiI Shut. Post UPPER COMPARTMENT PURGE INLET - M456 2VPIB 24 C C C C UPPER COMPARTMENT PURGE INLETL' M456 2VP2A 24 C C C C UPPER COMPARTMENT PURGE INLET M432 2VP38 24 C C C C UPPER COMPARTMENT PURGE INLET M432 2VP4A 24 C C C C LOWER COMPARTMENT PURGE INLET M357 2VP68 24 LC C C: C LOWER COMPARTMENT PURGE INLET M357 2VP7A 24 24 C[C C _C C C c

M434 '2VPB COMPARTMENT PURGE LOWER COMPARTMENT PURGE INLET INLET M434 - 2VPBA 24 C C C C CONT. PURGE EXHAUST M3684 2VP10A 24 C C C C CONT. PURGE EXHAUST M368 2VPIiB 24 C C C C CONT. PURGE EXHAUST M433 2VP]2A 24 1 C C C C CONT. PURGE EXHAUST M433 2VP 135 24*, C C C C CONT. PURGE EXHAUST M119 2VP15A 24 C C C C PURGE EXHAUST CONT. PURGE CONT. EXHAUST M1 19 M1 19 i -2VP15A2VP16B i 24 LC C: C C C C cC INCORE INSTR. ROOM PURGE IN M213 2VPI7A 12 C C C C INCORE INSTR. ROOM PURGE IN M213 2VP18B 12 LC -C C C "iRE INSTR. ROOM PURGE OUT M140 2VP19A 12 C C .C C JFRE INSTR. ROOM PURGE OUT - M140 2VP208 12 LC C C C CONT. AIR RELEASE M386 2VQ2A 4 C C C C CONT. AIR RELEASE M386 2VQ3B 4 C Ad C C CONT. AIR ADDITION M204 2VQ 158 4 C Al C C COWT. AIR ADDITION M204 2VQ 16A 4 C C C C CONT. HYDROGEN PURGE OUTLET LINE M346 2VYi 7A 4 C Al C C CONT. HYDROGEN PURGE OUTLET LINE M346 2W 18B 4 C Al C C VENT. UNIT CONDENSATE DRAIN HDR. M221 2WL867A 4 0 0 C0_

VENT. UNIT CONDENSATE DRAIN HDR. M221 2WL869B 4 0 Al 0 C EQUIPMENT HATCH ........ 240 C C C PERSONNEL HATCH 115 C C C CI_0 .. ..be.. .

LOWER PERSONNEL AIR LOCK 0____0___

C300 so' I...

..... . .... ..........................J1.

UPPER PERSONNEL AIR LOCK PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)

PERSONNEL AIR'LOCK 208 V UNEAR ACTUATOR DOOR LATCHES _

600V AC MCC 2EMXC (2EMXD) 600V AC MCC 2EMXK (2EMXB) 600 VAC MCC 2MXM ________

600 VAC MCC 2MXO 600 VAC MCC 2MXR ..

Page 1 IJ 1::j1:,lI" Attachment 1 Page 33 of 36 I-

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 34'of 36 TABLE 5 -

I1 029

_ _ Une Included In Press. bndry.

-A" HYDROGEN MITIGATION SYSTEM Size (In.) Seismic PRA integrity only GLOW PLUG IGNITERS 6[]0V AC MCC 2EMXI (2EMXB) 600/120V AC TRANSFORMER 2XFMROO13 (14)

ICE BASKETS & DOORS Une Included In Press. bnd .

NS SYSTEM Size (in.) Seismic PRA Integrity on/ly -

NS PUMP 2A (2B)

NS HX 2A (2B)

MOV 2NS18A "_ __12 MOV 2NS29A (32A) . 8 _

4160V AC SWITCHGEAR 2ETA (2ETB)

£114k AC MCC 2EMXA 76C .PANELBOARD 2EDE (2EDF) .. __

Une Included hf Press. bndry.

VX SYSTEM Size (in.) Seismic PRA - integrity only F__

(-8)

AIR-OP. DAMPER 2ARF-D-5 AIR-OP. DAMPER 2ARF-Do6 (-9)

AIR-OP. DAMPER 2ARF-D-7 (- 10)

MOTOR-OP. DAMPER 2ARF-D-2 (-4)

ZCONTAINMENT AIR RETURN FAN 2A (2B) 600V AC MCC 2EMXK (2EMXL)

-AC PANELBOARD 2EKPI (2EKPB) _ _ _ _ _

Poge 2

. :::. :, . Attachment 1 Page 34 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 351of 36 TA8LE 5 -

91 030 CONTAINMENT PERFORMANCE COMPONENT LIST FOR CATAWBA UNIT 2

• IPEEE WALKDOWNI ii----T CONTAINMENT ISOLATION VALVES Peneli. . V.lye Position AND PENETRATIONS No. Valve NO. Line Size (In.) Norm Fall Shut. Post UPPER COMPARTMENT PURGE INLET M456 2VP1B 24 C C UPPER COMPARTMENT PURGE INLET M456 2VP2A 24 C C C C UPPER COMPARTMENT PURGE INLET M432 2VP3B 24 C C C C UPPER COMPARTMENT PURGE INLET M432 2VP4A 24 C C C C LOWER COMPARTMENT PURGE INLET M357 2VP6B 24 LC C C C LOWER COMPARTMENT PURGE INLET M357 2VP7A. 24 C C C C LOWER COMPARTMENT PURGE INLET M434 2VP8B 24 LC C C C LOWER COMPARTMENT PURGE INLET M434 2VP9A 24 C C _C C CONT. PURGE EXHAUST M368 2VP1OA 24 C C C C CONT. PURGE EXHAUST M368 2VP 11B 24 C C C C CONT. PURGE EXHAUST M433 2VPI2A 24 C .C C C CONT. PURGE EXHAUST M433 2VPI3B 1 _2, C C C C CONW. PURGE EXHAUST M119 2VPI5A 24 C C C CONT. PURGE EXHAUST M119 2VPI6B 24 LC C C C INCORE INSTR. ROOM PURGE IN M213 2VP17A 12 C C C C INCORE INSTR. ROOM PURGE IN M213 2VPIB - 12 Ic C C C INr- INSTR. ROOM PURGE OUT M140 2VP19A 12 C C C C BINSTR. ROOM PURGE OUT M1 W 2VP20B 12 IC C C C

UNT. AIR RELEASE M386 2VQ2A. 4 C C C CONT, AIR RELEASE M386 2VQ3B 4 A.C C C CONT. AIR ADDITION I M204 I 2VQ158 4 C AI C C CONT. AIR ADDITION M204 2VQ16A 4 C C C CONT. HYDROGEN PURGE OUTLET LINE M346 2VY1 7A 4 C Al C C CONT. HYDROGEN PURGE OUTLET LINE M346 V2W18B 4 AJ C C VENT. UNIT CONDENSATE DRAIN HDR. M221 2WL867A 4 0 A] 0 C VENT. UNIT CONDENSATE DRAIN HDR. M221 2WL8698 4 oAl C EQUIPMENT HATCH 240 C C C PERSONNEL HATCH, 115 C C C LOWER PERSONNEL AIR LOCK C 100 1 I to 1 I on R1 I

UPPER PERSONNEL AIR LOCK C300 I b..

PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM)

PERSONNEL AIR LOCK 208 V UNEAR ACTUATOR DOOR LATCHES 600V AC MCC 2EMXC, (2EMXD)___ ___ ____

600V AC MCC 2EMXK (2EMXB) 600 VAC MCC 2MXM __,__

600 VAC MCC 2MXO 60 VAC MCC 2MXR V,

Page I Attachment 1 Page 35 of 36

CNC-1206.03-00-0203 Rev 0 Attachment 1A Page 36 'of 36 TABLE 5 -

I 1 031 Line Included in 1 IPress. bncirv.TI

_kDROGEN MITIGATION SYSTEM =Size (in,)JjSeismic!Aj ntegriy only, GLOW PLUG IGNITERS 600V AC MCC 2EMVXI (2EMXB) * ....

500/120V AC TRANSFORMER 2XFMROO13 (14)

ICE BASKETS & DOORS Une -ncluded in Press. bndry. _

NS SYSTEM Size (in.).- Seismic PRA. Integrity only, ...

'4S PUMP2A (2s)_ ..........

,JS HX 2A (28) ....

AOV 2NSI8A 12 OV 2NS29A .. A) 8 ....

,60V AC.SwMTCHGEAR.2ETA (2ETB) jOV AC MCC 2EMXA

• '-') PANELBOARD 2EDE (2EDF)-

iUne Included In Press. bndry.i VX SYSTEM Size (In.) Seismlc PRA integrity onty/

AJR-OP. DAMPER 2ARF-D-5 (-8)

AIR-OP. DAM 2A, F-D-6 (-9) ........

AIR-OP. OAM* ... 2ARF-D-7 (-10)

MOTOR-OP. DAMPER 2ARF-D-2 (-4)

CONITAINMENT AIR RETURN FAN 2A (2B) 600V AC MCC 2EMXK (2EMXL) _

120V AC PANELBOARD 2EKPI (2EKPB)

I Page 2

.4-;..,;.

'I ID ID 1-1 :1. Attachment 1 Page 36 of 36

CNC-1206.03-O0-0203 Rev 0.

Attachment 2A Page 1 of 8 I Catawba Unit 1 Swel 1 Unit I Swel 1 Pipe Mounted CLASS COUNT LOCATION COUNT 00-other 1 Aux Bldg 01-Motor Control Centers 2 Rm 103 2 02-L'owvoltage SWGR 0 Rm 104 2 03-Med Voltage Metal Clad SWGR 2 Rm 105 1 04-Transformers 2 Rm 217 3 05-Horizontal Pump 6 Rm 231 2 06-Vertical Pump 4 Rm 233 1 07-AOV 12 12 Rm 234 7 08-MOV/SOV 42 42 Rm 235 1 09-Fan 1 1 Rm 250 2 10-AHU 6 Rm 251 1 11-Chiller 1 Rm 254 1 12-Air Compressors 2 Rm 255 1 13-Motor Generators 0 Rm 300 4 14-Distribution Panels 1 Rm 318 2 15-Battery Rack 2 Rm 330 1 16-Battery Charger 6 Rm 350 5 17-Engine Generator 0 Rm 351 1 18-hn'strument Rack 9 Rm 372 5 19-Temperture Sensor 1 1 Rm 373 2 20-Instrument and Control Panel 9 Rm 400 7

[21-Tanks/HtXs 10 2 Rm 407 1 TOTAL [ 119 58 Rm 419 1 1 Rm 434 2 IRm 478 1 Rm 491 1 Rm 475 1 SYSTEM Count Rm 500 1 CA 7 Rm 560 1 CF 0 Rm 570 7 EOA 2 Rm 573 1 EPE 5 Rm 576 2 EPG 3 Control Rm 2 EPL' 4 EPQj 3 EDG Bldgs EQB 0 1A 9 EQC 4 1B 13 FD 2 FW 5 Inner DH 4 IPE 1 KC 11 Outer DH 3 KD 1 LD 2 Rx BIdg 8 NC 3 Yard 5 ND 6 RN Pumphouse (RNB) 3 NI 10 Other Aux 2 NS 4 NV 9 Total 119 RN 10 SA 1 SM 2 SV 2 VC 11 VE 1 VG 8 YC 2 TOTALS 119

Catawba Unit 1 Swel-1 Equipment Walkdown Scope CNC-1206.03-00-0203 Rev 0 Attachment 2A Page 2 of 8.

Prio__.lr -5 Safety

-Equipment ------- Dsrpi -- __- Sys -- ---- Column- -Listed on - MalNewi - -IPEEE - Reference --

Taq tern Co Grid IPEEE List Replace Equin Disc/ Dwqs Enhan S 522 Rm 1NDPUA 1A RHR Pump ND 6 Aux 105 GG 54 Yes 1,3,4 543 Rm CN-1492-1N1185A ND PUMP 1A CONT SUMP SUCT NI 8 Aux 217 EE 52 Yes 1,3,4 43.01-01 CN-71 1562-01.03 1NV77A NC Pump D Seal Supply Cont Isol NV 8 Aux 543 Rm HH 52 Yes 3 217 1NV312A Chg Line Cont Isol NV 8 Aux 544 217 R1 HH 52 Yes EC 105829 1,3,5 543 Rm CN-1492-1NV252A NV PUMPS SUCT FROM FWST NV 8 Aux 234 HH 53 Yes 1,3,4 NV.00-013 4 CN-1554-543 Rr CN-1562-1NI115A Med-Head 1A NI Pump Minflow Isolation NI 8 Aux 235 GG 53 Yes 1,3,4 01.02 CN-1492-NI.00-555 Rm CN-1492-1CA116A CA PUMP #1 SUCT FRM RN HDRA CA Aux 55R BB51 33 Yes 2,4 43.10-00 CN-8 250 1592.01-00 577 Rm 1,3,4 CN-I1573-02.00 1KC57A 1A ND HX FLOW CONTROL KC 7 Aux 300 JJ 58 Yes 554 Rm CN-17 10-1ECA 125 VDC VITAL BAT CHARGER EPL 16 Aux 350 DD 55 Yes EC-75331 1,2,3,4,5 03.01 CNM-350 1356.05-1EBA 1A Essential Battery Bank EPL 15 Aux 554 351Rm DD 54 Yes CN-11339 1,2,3,4,5 560 Rm CNM-1211.00-1-SGR-AHU-4 U1 Switchgear Room Air Handling Unit #4 VC 10 Aux 373 AA 53 Yes 1,2,3,4,5 0169-000 CN-1_ 1200-08.05 560 Rm CNM-1211.00-1-SGR-AHU-3 Ul Switchgear Room Air Handling Unit #3 VC 10 Aux 373 BB 52 Yes 1,2,3,4,5 0169-000 CN-1200-08.05 1KCPUA2 1A2 KC Pump KC 5 Aux 560 3O00Rm HH 58 1,2,3,4 IKCC37A 1A KC MINIFLOW ISOL KC 8 Aux Elev 577/ HH 57 Yes 1,2,3,4 0N-1573-Rm400 01.00 1 KC50A KC Aux Bldg Non-ESS Return Isol KC 8 Aux 577Rm HH 55 Yes 1,3,4

_______ _______________________ ___ __ 40 _____________________ ______400___

Catawba Unit 1 Swel-1 Equipment Walkdown Scope CNC-1206.03-00-0203 Rev 0 Attachment 2A Page 3 of 8.

Prior 5 Safety Equipment.

t Equimen DesripionSs S. Class tern BLDG Elevlfoom- Column Grid Listed List IPEEE on Replace Mal New/Equip IPEEE Disc/ F Reference Dwqs Enhan S T57Cas7BD EvRom EC0104015 1RN291 1A KC HX OUTLET THROTTLE RN 7 Aux 577 Rm KK 56 Yes EC7104015 1,2,3,4 1 400 EC78837 577 Rm 1NS29A NS Spray HDR 1A Cont Isol NS 8 Aux 577 HH 51 Yes 5 568 Rm CN-1492-1ND32A ND TRAIN 1A HOT LEG INJ ISOL ND 8 Aux LL 51 Yes 1,3,4 60.01-00 CN-434 _1561-01.01 1NSRD51301A NS Hx Outlet Temperature (Substituted NS 19 Aux 576 Rm NO 1,3,4 Instead of INDRD5000) 434 -

577 Rm 1ELCP0355 ELECT ENCL FOR VCT OTLT VAL TRN A NV 20 Aux 47 EE 55 NO EC 93810 1,3,4

___________ ~~~478 ____ 577RmCNM-1211.00- _____

-SGR-AHU-1 U1 Switchgear Room Air Handling Unit VC 10 Aux 577 Rm AA47 Yes 1,2,3,4,5 0169.001 495 06.0 1ETXB 4160/600 VAC TRANSFORMER - EPE EPE 4 Aux Elev 560 Rm 372 AA46 Yes 1,2,3,4,5 SYST 4160/600 VAC TRANSFORMER - EPE Elev 560 CN-1876-01, 1ETXD SYST EPE 4 Aux Rm 372 AA47 Yes 1,2,3,4.5 CN-1214-01 1CRA-PFT-1 CONTROL ROOM AREA PRESSURE 594 Rm FF Yes 1,2,3,4,5 ON-1876-01, C

1CRA-PFT- FILTER TRAIN A (SHARED) 570 F5 s24 CN-1214-01 1CRA-PFTF-1 1CRA-PFTF-1 PRESSURE FILTER VC 9 Aux 594 Rm EE 55 Yes 1,2,3,45 CNEE-0131-TRAIN FAN (SHARED) VC 9 u 571R06.39 CONTROL ROOM AREA CHILLED 594 Rm OYCPUCW1 YC 5 Aux HH 56 Yes 1,2,3,4,5 WATER PUMP (1CRA-P-1) (SHARED) 570 ICRA-C-1 CONTROL ROOM AREA CHILLER (lCRA YC 11 Aux 594 Rm GG 55 Yes EC0072138 1,2,3,4,5 C-1) 'A' TRAIN (SHARED) 570 1CRA-C-1 CF ler Compressor Control Panel "A "trn (SHAF VC 20 Aux 594 Rm GG 55 Yes EC92771 1,2,3,4,5cnm-1211.00-1 570 17 2492.00 CNM-1211.00-0391.001 CN-1CRA-D-1 A-PFT-1 INLET ISOL MAN DAMPER (SHA VC 0 Aux 5945Rm FF 55 Yes 1,2,3,4,5 1578-01.00 ux 570 C-52 03.40-00 CN-1522-00.85-01 1CR-AHU-1 TRAIN A CONTROL ROOM AHU 594 Rm CNM-1211.00 1CR-AHU-1 (SHARED) VC 10 Aux 570 GG 56 Yes 1.2,3,4,5 0177&0178 1SM3 Main Steam Isolation Valve 1C SG SM 7 DH1 DH1 DD 52 Yes EC076333 2,5 CN-1491-Inner Rm I _SM.00-029

Catawba Unit 1 Swel-1 Equipment Walkdown Scope CNC-1206.03-00-0203 Rev 0 Attachment 2A Page .+ of 8.

-Prior 5 Safety Refe- e Equipment-e o DesciptinClss-BLDG bs Clss BDG Eev/Room Column levltomFunction Ligted on Mai New/-- IPEEE Function Tlaq temr Grid IPEEE List Replace Equip Disci Dwqs Enhan _

FW STORAGE TANK WR LEVEL CH #1 FW 18 Aux Aux 594 CC 56 Yes 1,3,4 CN-1571-1FWP 5000 I _ _ _ __ _ _ __ _ _I__ _ _ Rm 573 __ _ _01.00 1VC6A CRA FILT INLET (SHARED EQUIP) VC 8 Aux Aux 594 CC 51 Yes 1,2,3,4,5 CN-1761-Rm 576 06.12 CN-1491-1CA62A CA PMP A DISCH TO S/G 1A ISOL CA DHI Rm 591 DD 44 Yes 2,4 CA.00-020 CN-8 _1592.01-00 560 Rm CN-1492-1NI173A ND HEADER 1A TO COLD LEGS C & D NI 8 Aux 318A HH 52 Yes 1,3,4 60.01-00 CN-318A _1562-01.03 560 Rm CN-1492-1NI9A NV PMP C/L INJ ISOL NI 8 Aux 318A JJ 51 Yes EC108301 1,3,4 60.01-00 CN-318A _1562-01.00 1VGTKA1 WA1 EDG Starting Air Tank VG 21 D1A 556 DD 38 Yes 1,2,3,4,5 CN-1200-1 14.01 CN-1VGTKA2 1A2 EDG Starting Air Tank VG 21 D1A 556 DD 38 Yes 11,2,3,4,5 CN-1609-1VGCPA1 WA1 EDG Starting Air Compressor NON- VG 12 D1A 556 CC 38 NO None CN-1200-14.01 QA Keep on List 1DGCA 1A EDG Charger EPQ 16 D1A ,556 CC 40 Yes EC 100375 1,2,3,4,5 1DGBA 125 VDC Diesel Aux Power Battery EPQ 15 D1A 556 CC 40 Yes EC 93195 yes 1,2,3,4,5 lVG25 1A DIG ENG STARTING AIR INLET VG 8 D1A 560 0039 Yes 1,2,3,4,5 CN-1609-1VG27 1A D/G ENG STARTING AIR INLET VG 8 DIA DIA, CC 39 Yes 1,2,3,4,5 CN-1609-CN-1499-1LDPT5144 1A DG ENG LUBE OIL INLET PRESSURE LD 18 D1A 560 DD 41 Yes 1,2,3,4,5 01.08-00 CN-I_ 1499-LD.07-00 1RN846A 1A D/G HX RETURN TO SNSWP RN 8 D1A 589 EE 38 Yes EC93045 1,2,3,4,5 1RN30A 1A RN Strainer Auto Backwash Valve RN 8 RNB 600 Pit A Yes EC 657270 1,2,3,4,5 ORNLT7390 RN Pit A Diff Level Across screen (Shared) RN 18 RNB 600 PitA _ Yes EC 73197 1,2,3,4,5 CN-1594-1A D/G Eng Fuel Oil Storage Tank WA1 1FDPS5002 Level FD SYS NON QA (Substituted for FD 18 YRD Yrd _ no 1,2,3,4,5 1FDLT5000) 522 RmCN-1 200-1B Containment Spray Pump NS 6 Aux 522 Rm GG 55 Yes 5 1NSPUB B C S 103 522 Rm 01.01 CN-1NSlB NS PMP B SUCT FROM CONT SUMP NS 8 Aux GG 54 Yes 5 103 ,

Catawba Unit I Swel-1 Equipment Walkdown Scope CNC-1206.03-00-0203 Rev 0 Attachment 2A Page 5 of 8.

Prior 5 Safety.

Equipment Description ......- Svs Class BLDG Elev/Room Column

- Listed

-I on PEE Function Tam tern Grid IPEEE List Replace Equip Disc/ DwFs Enhan S KC 21 Aux 522 Rm GG 53 Yes 1,3,4 CN-1573-1KCHX0050 ND Pump 1B Motor Cooler (Cooler Integral to Housing 104 02.00 CN-522 Rm CN-1200-1NDPUB 1BRHRPump ND 6 Aux 105 HH 54 Yes 1,3,4 01.01 CN-1_ 1561-01.01 543 Rm CN-1492-1NV202B NV PMPS A & B RECIRC ISOL NV 8 Aux 231 HH 54 Yes EC108310 1,3,4 NV.00-040 CN-1554-1NVPUBCC 1B NV PUMP NV 5 Aux 43-1 HH-55 Yes EC100680 1.3,4 05.0 -

____________231 105.02 ON-SEAL WATER INJECTION FLOW 543 Rm CN-1738-1NV309 ONTROLNV 7 Aux 23 Yes E77871 1,3 03.03 CN-NI MINIFLOW HDR TO FWST ISOL NI 8 Aux 543 Rm HH 53 Yes 1,3,4 0N-1562-1NI147B

____________234 ___ 01.02 NI 5 Aux 543 Rm HH 54 Yes EC61493 1,3,4 ON-i200-INIPUB 1B Med-Head NI Pump (SAFETY ON-INJECTION PUMP) 234 05.02 KG 21 Aux 543 Rm HH 53 Yes 1,3,4 ON-i573 1KCHX0052 NI Pump 1 B Motor Cooler (Cooler Integral to Housing) 234 1 02.01 CN-543 Rm ON-i1562-01.02 Med-Head 1B NI Pump Minflow Isolation NI 8 Aux 23 HH 53 Yes 1,3,4 1NI144A 234012 543 Rm CN-1492-1NI136B ND SUPPLY TO NI PUMP 1B NI 8 Aux 234 HH53 Yes 1,3,4 43.01-01 CN-234 _1562-01.02 543 Rm CN-1492-1NV253B NV PUMPS SUCT FROM FWST NV 8 Aux 234 HH 53 Yes 1,3,4 NV.00-013 234 CN-1 554-543 Rm CN-1492-1CA18B CA PUMP 1B SUCT FRM RN ISOL CA Aux 250R BB 51 Yes 2,4 43.10-00 CN-8 1592.01-00 543 Rm ON-i1592-CA 8 Aux 251 CC 53 Yes EC65608 2,4 01.00 1CA174 RC TO CA SUCTION ISOL 543 Rm EC 54583 EC CN-1592-lGAPUB 18 CA PUMP GA 5 Aux 255 AA5O Yes 332,4 01.00 1CAPUTD TDCAP #1 GA 5 Aux 543 254Rm AA51 AA_5_Ye Yes 2,4 CN-1200-2,4_0504_CN 254________ 05.04 ON-AUX BLDG NON-ESSENTIAL RETURN 580 Rm CN-1492-1KC2B AESSENIAL KC 8 Aux 560 HH 57 Yes EC36266 1,3,4 60.02-00 CN-HEADER ISOL 300 1573-01.00

Catawba Unit 1 Swel-1 Equipment Walkdown Scope CNC-1206.03-00-0203 Rev 0 Attachment 2A Page 6 of 8.

. ..... .. . ~Prior 5S ft Equipment Description Sys Class BLD ElevlRoor Column Listed on - aMNewt IPEEE Reference Taq tern Grid IPEEE List Replace Equip Disc! Function Dwqs Enhan S 560 Rm CN-1492-RX BLDG NON-ESSENTIAL RETURN HH 57 1KC18B KC 8 Aux Yes EC62769 5 60.02-00 CN-HEADER ISOL 300 1573-01.00 CN-1200-560 Rm 1NDHXB 1B RHR HtX ND 21 Aux KK51 Yes 1,3,4 08.02 CN-435 1561-01.01 1EID 120 VAC Vital Power Inverter EPG 16 Aux 554 Rm BB 54 Yes EC 74964 1,2,3,4,5 350 1EIF 120 VAC Vital Swing Inverter EPG 16 Aux 554 Rm BB 55 Yes EC 75104 1,2,3,4,5 350 1EIB Vital Battery Inverter EPG 16 Aux 554 Rm 0054 Yes EC 74964 1,2,3,4,5 1__ 350 _ __

560 Rm CN-1876-01 600 VAC ESSENTIAL MOTOR CONTROL 1EMXL EPE 1 Aux BB 47 Yes 1,2,3,4,5 CNWT-1752-CENTER 372 01.11 CN-1876-01 560 Rm 1EMXD 600 VAC ESS MCC EPE 1 Aux 372 BB 50 Yes 1,2,3,4,5 CNWT-1752-01.04 1EADB Auctioneering Diode Assembly EPL 14______Aux 560 372Rm BB 51

______ NO ____ 1,2,3,4,5 1KC53B Aux Bldg Non-Essential Header Isolation KC 8 Aux 577 Rm HH 55 Yes 1,3,4 400 ____ _____

577 Rm 1KC81B KC TO ND HX 1B SUP ISOL KC 8 Aux 577 KK 52 1,3,4 57400R 1RN351 1B KC HX OUTLET THROTTLE RN 7 Aux 577 Rm LL 57 Yes EC 104015 1,2,3,4 400 577 RmCN-1 574-8 Aux 577 Rm PP 60 Yes 1,2,3,4,5 01.05 1RN58B RN Header B Return to SNSWP (SHARED RN 577 Rm CN-1492-1B NS HX INLET ISOL RN 8 Aux NN 53 Yes 5 77.07-00 1RN225B 400 77.07-00 574 Rm 1ELCP0275 TRAIN A & B Damper Control Panel VE 20 Aux 41 DD 54 NO 5 1KCTKB 1B KC SURGE TANK KC 21 Aux 5CN00 MM 59 Yes 1,2,3,4 10.3 C0-

__ _ __ _ _ _ __ _ _ _ __ _ __ _ _ _ _500 ____ _ _10.03 CN-1SV7 1C S/G POWER OPERATED RELIEF SV 7 DH1 Inner FF- FF 52 Yes EC102396 2,4

___VALVE Inner _ -_ _ I_ I _ _ _ _ _ _ _ _

DH 1 CN-I1593-01.00 1C S/G PORV ISOL SV 8 DH1 Inner FF- FE 52 Yes 2,4,5 1SV26B

Catawba Unit 1 Swel-1 Equipment Walkdown Scope CNC-1206.03-00-0203 Rev 0 Attachment 2A Page 7 of 8.

-Prior 5 Safety Equipmentlass ElevlRoom Column Listed on - Mai New/ IPEEE nReference

_ter Grid IPEEE List Replace__ Disc/

Enhan a Dwqs DH1 1SA5 1B S/G MAIN STEAM SUPPLY TO CAPT SA 7 DH1 FF 63 Yes 4 I_ I Inner FF-1VC5B CRA FILT INLET VC 8 Aux 594Rm Yes 1,2,3,4,5 CN-1491-1CA66B CA PMP 1 DISCH TO S/G 1A ISOL CA DH1 Rm 591 DD 44 Yes 2,4 CA.00-019 CN-8 1592.01-00 lB COOERCN-1609-DG EN JAKET ATE 1 B DG ENG JACKET WATER COOLER KD 21 DIB 556 CC 39 Yes 1,2,3,4,5 01.00 1KDHXB (1KDHX14)10.0 1ELCP0329 1 B Diesel Annex Panel EQC 20 D1B 556 BB 41 Yes 1,2,3,4,5 18 D1B 556 BB 4O Yes 1,2,3,4,5 CN-1499-01.08-00 1LDPT5174 1B DG ENG LUBE OIL INLET PRESSURE LD 1VGTKB1 181 EDG Starting Air Tank VG 21 D18 556 BB 38 Yes 1,2,3,4,5 1VGTKB2 1 B2 EDG Starting Air Tank VG 21 D18 556 BB 38 Yes 1,2,3,4,5 1VGCPB1 181 EDG Starting Air Compressor (NON VG 12 DIB 556 AA 38 NO None CN-1200-14.02 QA - KEEP ON LIST) I 1DGCB 1B Diesel Generator Batt Charger EPQ 16 D1B 556 CC 40 Yes EC100375 1,2,3,4,5 1B D/G ENG FUEL OIL DAY TANK 1 BBCN-1609-1FD62 FILL FD 8 DlB 556 BB 38 Yes 1,2,3,4,5 03.01 CN-1RN849B 1B D/G HX RETURN TO SNSWP RN 8 D1B 556 Stair AA 38 Yes EC 93045 1,2,3,4,5 1RN848B 1B D/G HX RETURN TO SNSWP RN 8 D01 556 Stair AA 38 Yes EC 93045 1,2,3,4,5 Outer 1SM1 Main Steam Isolation Valve 1D SG SM 7 DHI Outer DD 44 Yes EC 76333 2,5

_________ _____~ ~~~~

Rm 591 _ _ _ ___ __________

IRNPUB 1B NUCLEAR SERVICE WATER PUMP RN 6 RNB 600 BTrain 52X 71Y Yes 1,2,3,4,5 UNIT 1 REFUELING WATER STORAGE Ul Yrd CN-1571-1FWTK01 TANK FW 21 YRD 594 Basin Yes 1,3,4 01.00 Ul Yrd CN-1571-01.00 1FWLT5010 FWST WR LEVEL CH 2 FW 18 YRD 594 Basin - Yes EC65578 1,3,4 U1 Yrd ON-1571-1FWLT5000 FWST WR LEVEL CH 1 FW 18 YRD U1 Bas 50X 46Y Yes EC65578 1,3,4 01.00

___594 Basin ____________ 01.00 IEPB / PNLB PNL BOARD (125VDC VITAL I&C PWR S EPL 20 AUX 554 350Rm CC 55 Yes 1,2,3,4,5 1EMXB VAC ESSENTIAL MOTOR CONTROL CEN EPE 3 AUX 560 Rr FF 60 Yes 1,2,3,4,5 330 1FWLT5130 FWST WR Level CH 4 FW 18 YRD 18594 U1BYrd Basin __

Yes 1,3,4

Catawba Unit 1 Swel-1 Equipment Walkdown Scope CNC-1206.03-00-0203 Rev 0 Attachment 2A Page 8 of 8.

_a _EQ New Pro.5* _Safety eeec Equipment Description -SYs Class BLDG Ee- -oo Column Listed-on - Mal Ne IPE afet Reference -

Taq tees Grid IPEEE List Replace Equip Disc/ Function Dwqs Enhan S 1DGBNGC 3 Diesel Generator Neutral Grounding Cubi EQC 3 D1B 556 AA 40 Yes 1,2,3,4,5 1DECPB 1B Diesel Engine Control Panel EQC 20 D1B 556 AA 41 Yes 1,2,3,4,5 1DGCPB 1B Diesel Generator Control Panel EQC 20 D1B 556 AA 41 Yes 1,2,3,4,5 1MC1 MAIN CONTROL BOARD 1MC1 EOQ 20 Aux MCR594 AA56 No 1,2 1MC2 MAIN CONTROL BOARD 1MC2 EOQ 20 Aux MCR 594 AA 56594 No RmCN-1578-2 Control Room AHU-1(2CRA-FAN) VC 10 Aux 594 Rm FF 69 YES 1,2,3,4,5 02.05 2CRA-AHU-1 560025 1SSPSA SOLID STATE PROTECTION SYSTEM TRAIN A IPE 18 Aux 594 CC 55 Yes 1,2,3,4,5 CN-1491-1NV52A 1A NC PUMP SEAL RETURN NV 7 CV1 557 58/40 R Yes 3 03.00-02 CN-1554-CN-1491-1N154A C-LEG ACCUM A DISCH ISOL NI 8 CV1 569 46/47 R Yes 3,4 02.00-01 CN-1562-01.01 1N1438A EMER N2 FROM CLA TO INC-34A NI 8 CV1 562 40/53 R Yes 2 CN-1562-01.01 CN-1491-1ND2A ND PUMP 1A SUCT FRM LOOP B ND 8 CV1 567 176/50 R Yes 1,3,4 07.00-009 CN-1561-01.00 IND1B ND PUMP 1A SUCT FRM LOOP B ND 8 CVl 568 176/25 R Yes 1,3,4 CN-1561-CN-1491-1NC34A UNIT 1 PZR PORV NC 7 CV1 635 105/37 R Yes 2 06.00-01 CN-1553-01.01 CN-1491-1NC32B UNIT 1 PZR PORV NC 7 CV1 635 107/38 R Yes 2 06.00-01 CN-

_1553-01.01 CN-1491-1NC36B UNIT 1 PZR PORV NC 7 CV1 635 101/37 R Yes 2 06.00-01 CN-1 __ 1553-01.01

CNC-1206.03-00-0203 Rev 0 Attachment 3A Page J of 2 Catawba Unit I SWEL-2 Base-List and Rapid Drain Down List Unit 1 SWEL-2 "Base List" Descrintlon System J Euin I Eley Room#

CNC-1206.03-00-0203 Rev 0.

Attachment 3A.

Page? of 2.

Unit I SWEL-2 "Rapid Draindown List" SBMUP SFP &

1NV865A Suction frm NV 8-MOV Rx 578 Annul 266/61 R Refueling Cavity xfer tube Inventory 1FW8, -9, - SFP &

25,-26,-461- Refueling FW 0-Other Rx N/A CV1 N/A Refueling 47,-71,-79 47, -71, Cavity Drain Cavity I7 Inventory SBMUP SFP &

1NVPD0041 Discharge NV 0-Other Rx 557 Annul 278/60 R Refueling Pulsation Cavity Dampener Inventory SBMUP SFP &

1NVPDO042 Discharge NV 0-Other Rx 558 Annul 278/58 R Refueling Pulsation Cavity Dampener Inventory SBMUP SFP &

1NVFLY-45 Discharge NV 0-Other Rx 561 Annul 274/61 R Refueling Cavity Strainer Strainer__Inventory SBMUP SFP &

1NV868 Discharge NV 08- MOV Rx 561 Annul 274/61 R Refueling Cavity Isolation Inventory I

Reaztor Refueling SFP &

rReactor FW 0-Other Rx n/a CV1 n/a Refueling Cavity Seal Cavity Cavity Seal Inventory Fuel Transfer Fuel Transfer SFP &

Tube Blind Tube Blind KF 0-Other Rx n/a CV2 n/a Refueling Flange Flange Cavity Inventory Fuel Transfer Fuel Transfer SFP &

Tube Weir Tube Weir KF 0-Other Rx n/a CV3 n/a Refueling Gate Gate Gate GateInventory Cavity

CNC-1206.03-00-0203 Rev 0 Attachment 4A Page 1 of 1 Catawba Unit I SWEL-2 Equipment Walkdown Scope Malor NewI/ aeyD~IG Equipment # Description System ECquip ColunndGr rew/ Function Class qld Elev Roomn# id _______Fncio Equipment SBMUP Suction frm xfer tube NV 8-MOV Rx 578 Annul 266/61 R SFP & Refueling 1NV865A Cavity Inventory Refueling Cavity Drain FW 0-Other Rx 563 CV1 300/33 R SEP & Refueling CN-1491-FW.00-007 1FW8 Cavity Inventory CN-1571-01.01 10FW46 Refueling Cavity Drain FW ,-Other Rx 568 CV1 244/48 R SFP & Refueling CN-1 491-FW.00-004 Cavity Inventory CN-1571-01.00 1NVPDO042 SBMUP Discharge Pulsation Dampener NV 0-Other Rx 558 Annul 278/58 R EC102855 N/A 1KFPUA 1A KF Pump KF 5-Pump Aux 579 418 QQ/52 SFP Cooling CN-1570-01.00 CN-

____ ___ _ __ _ ___1200-01.01 1NVPUSB Standby Makeup Pump (NV) NV 5-Pump Rx 577 n/a 280/60 R SFP Cooling 1KF181 ALT Makeup Isol KF 0-Other Aux 586 400 NN-51 SFP Inventory 1KF62 KF Drain Header Isolation KF 0-Other Aux 586 400 MM-51 SFP Inventory 1KFHXA 1A FUEL POOL COOLING HtX KF 21-Htx Aux 577 418 NN-62 SFP Cooling