ML13190A272: Difference between revisions

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-WITHHOLD UNDER 10 CFR 2.390(d)(1)
-WITHHOLD UNDER 10 CFR 2.390(d)(1)
UPON REMOVAL OF ATTACHMENT 5 and 7 of ENCLOSURE 1, THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission June 20, 2013 Page 5 ENCLOSURE 1: McGuire Nuclear Station Unit I Seismic Walkdown Report Revision I Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 1 of 15 Rev. 1 Revision Log: Rev. 0 Initial NRC submittal dated November 26, 2012 Rev. 1 Supplemental NRC submittal to address "initially" inaccessible components.
UPON REMOVAL OF ATTACHMENT 5 and 7 of ENCLOSURE 1, THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission June 20, 2013 Page 5 ENCLOSURE 1: McGuire Nuclear Station Unit I Seismic Walkdown Report Revision I Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 1 of 15 Rev. 1 Revision Log: Rev. 0 Initial NRC submittal dated November 26, 2012 Rev. 1 Supplemental NRC submittal to address "initially" inaccessible components.
Revised pages 1-15, Added ATTACHMENTS 7 & 8.Executive Summary The results of the McGuire Unit 1 Fukushima Dai-ichi Near-Term Task Force (NTTF)Recommendation  
Revised pages 1-15, Added ATTACHMENTS 7 & 8.Executive Summary The results of the McGuire Unit 1 Fukushima Dai-ichi Near-Term Task Force (NTTF)Recommendation 2.3 Seismic Walkdowns are provided here-in. 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 (issued June 2012). The performance of the seismic walkdowns is required in response to the Nuclear Regulatory Commission's (NRC) 10CFR50.54(f) letter regarding NTTF Recommendation 2.3: Seismic. The EPRI guidance outlined requirements for personnel qualifications, selection of walkdown components, the conduct of the walkdowns, evaluation of potentially adverse conditions against the plant seismic licensing basis, and reporting requirements.
 
===2.3 Seismic===
Walkdowns are provided here-in. 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 (issued June 2012). The performance of the seismic walkdowns is required in response to the Nuclear Regulatory Commission's (NRC) 10CFR50.54(f) letter regarding NTTF Recommendation 2.3: Seismic. The EPRI guidance outlined requirements for personnel qualifications, selection of walkdown components, the conduct of the walkdowns, evaluation of potentially adverse conditions against the plant seismic licensing basis, and reporting requirements.
The guidance further provided check lists to document the performance of the seismic walkdowns and walk-bys.Revision 0 of the submittal report documented the walkdown results for the accessible components as of November 2012. Revision 1 of the submittal report added the walkdown results for the previously in-accessible components.
The guidance further provided check lists to document the performance of the seismic walkdowns and walk-bys.Revision 0 of the submittal report documented the walkdown results for the accessible components as of November 2012. Revision 1 of the submittal report added the walkdown results for the previously in-accessible components.
 
1.0 Seismic Licensing Basis Site Characteristics:
===1.0 Seismic===
Licensing Basis Site Characteristics:
Major Category I structures are supported on sound rock (UFSAR Sections 3.7.1.4, 3.7.1.5, 3.7.1.6, 3.8.4, 3.8.5, 3.8.5.4.1).
Major Category I structures are supported on sound rock (UFSAR Sections 3.7.1.4, 3.7.1.5, 3.7.1.6, 3.8.4, 3.8.5, 3.8.5.4.1).
Where zones of irregular weathering of bedrock occurred, the weathered material was excavated and fill concrete was used under foundation structures, or piles were driven to suitable rock bearing for Category I structure (UFSAR Section 2.5.1.2).Response Spectra: The Safe Shutdown Earthquake (SSE) for McGuire is conservatively specified to have a peak ground acceleration of 0.15g horizontally and 0.10 g vertically.
Where zones of irregular weathering of bedrock occurred, the weathered material was excavated and fill concrete was used under foundation structures, or piles were driven to suitable rock bearing for Category I structure (UFSAR Section 2.5.1.2).Response Spectra: The Safe Shutdown Earthquake (SSE) for McGuire is conservatively specified to have a peak ground acceleration of 0.15g horizontally and 0.10 g vertically.
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Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 2 of 15 Rev. 1 System, Structure, 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 1 (UFSAR 3.2.1). The McGuire design complies with Regulatory Guide 1.29 for SSC seismic design requirements.
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 2 of 15 Rev. 1 System, Structure, 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 1 (UFSAR 3.2.1). The McGuire design complies with Regulatory Guide 1.29 for SSC seismic design requirements.
Seismic Category I SSCs are designed to maintain their functional capability in-the event of a SSE. The seismic design of Category I SSCs is outlined in UFSAR Section 3.2 and Tables 3-1, 3-2, 3-4 & 3-7. Seismic Category I SSCs are also designed to withstand the effects of the Operating Basis Earthquake without loss of capability to perform their safety functions.
Seismic Category I SSCs are designed to maintain their functional capability in-the event of a SSE. The seismic design of Category I SSCs is outlined in UFSAR Section 3.2 and Tables 3-1, 3-2, 3-4 & 3-7. Seismic Category I SSCs are also designed to withstand the effects of the Operating Basis Earthquake without loss of capability to perform their safety functions.
Applicable seismic design codes and standards include (MCS-1465.00-00-0009, Section 3.2, UFSAR section 3.2 and Tables 3-1 through 3-7): " 10CFR50, Appendix A, General Design Criteria 2 -Design Bases for Protection Against Natural Phenomena* Duke Class A, B, C piping per ASME Section III, 1971, except for the Nuclear Service Water piping which was designed per ANSIB31.7, Class III (Reference UFSAR Table 3-5)" Duke Class A, B, C valves per ASME Section III, 1971 (Reference UFSAR Table 3-6)* Duke Class F valves per ANSI B31.1.0 (1967), Class III (Reference UFSAR Table 3-6)* Regulatory Guide 1.29, "Seismic Design Classification," Revision 3, September 1978.* 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 IE Equipment for Nuclear Power Generating Stations.  
Applicable seismic design codes and standards include (MCS-1465.00-00-0009, Section 3.2, UFSAR section 3.2 and Tables 3-1 through 3-7): " 10CFR50, Appendix A, General Design Criteria 2 -Design Bases for Protection Against Natural Phenomena* Duke Class A, B, C piping per ASME Section III, 1971, except for the Nuclear Service Water piping which was designed per ANSIB31.7, Class III (Reference UFSAR Table 3-5)" Duke Class A, B, C valves per ASME Section III, 1971 (Reference UFSAR Table 3-6)* Duke Class F valves per ANSI B31.1.0 (1967), Class III (Reference UFSAR Table 3-6)* Regulatory Guide 1.29, "Seismic Design Classification," Revision 3, September 1978.* 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 IE Equipment for Nuclear Power Generating Stations.
 
2.0 Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 3 of 15 Rev. 1 Personnel Qualifications The personnel involved in the McGuire NTTF Recommendation 2.3 Seismic Walkdown effort satisfactorily met the qualification requirements of EPRI 1025286. The personnel responsibilities and qualifications are outlined in TABLE 2-1 below. Additional Peer Review Team experience is outlined within the Peer Review Report (ATTACHMENT 6).TABLE 2-1 Walkdown Personnel Experience and Training a)) 3 = C l 0 C .2 a) = 0- (S G(1) CU L: _ Wu CL d)o a)a, 3- -0 a, W)>- > -a Qa 0 Q >Mark Eli, P.E. (Ares) BS/Civil Engineering 32 SWE (2)(3) X Charles M. Conselman, BS/Civil Engineering 28 SWE (2)(3) X P.E. (ARES) BCinn n2 S ()3X Bryan Hanna, P.E. BS/Civil Engineering 12 SWE (2)(3) X (ARES)Kevin Rubright (ARES) BS/Civil Engineering 30 SWE74z' X Harpreet Ghuman BS/Civil Engineering 4 SWE (2) X (ARES)Paul Baughman, P.E. SQUG X(3)PArl BS/Civil Engineering  
===2.0 Fukushima===
 
Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 3 of 15 Rev. 1 Personnel Qualifications The personnel involved in the McGuire NTTF Recommendation  
 
===2.3 Seismic===
Walkdown effort satisfactorily met the qualification requirements of EPRI 1025286. The personnel responsibilities and qualifications are outlined in TABLE 2-1 below. Additional Peer Review Team experience is outlined within the Peer Review Report (ATTACHMENT 6).TABLE 2-1 Walkdown Personnel Experience and Training a)) 3 = C l 0 C .2 a) = 0- (S G(1) CU L: _ Wu CL d)o a)a, 3- -0 a, W)>- > -a Qa 0 Q >Mark Eli, P.E. (Ares) BS/Civil Engineering 32 SWE (2)(3) X Charles M. Conselman, BS/Civil Engineering 28 SWE (2)(3) X P.E. (ARES) BCinn n2 S ()3X Bryan Hanna, P.E. BS/Civil Engineering 12 SWE (2)(3) X (ARES)Kevin Rubright (ARES) BS/Civil Engineering 30 SWE74z' X Harpreet Ghuman BS/Civil Engineering 4 SWE (2) X (ARES)Paul Baughman, P.E. SQUG X(3)PArl BS/Civil Engineering  
>40 SWE (2) (3)(Ares) SWE_______________
>40 SWE (2) (3)(Ares) SWE_______________
___George Bushnell, P.E. S§QUG (P (HV)BS/Mechanical Engineering  
___George Bushnell, P.E. S§QUG (P (HV)BS/Mechanical Engineering  
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The EPRI guidance provided a definition for SFP uncontrolled drain-down, which was seismic induced leakage which could drain SFP to within 10'of the top of the fuel within 72 hours. Unlike the prior screening criteria, screen #4 does not exclude non-seismic equipment.
The EPRI guidance provided a definition for SFP uncontrolled drain-down, which was seismic induced leakage which could drain SFP to within 10'of the top of the fuel within 72 hours. Unlike the prior screening criteria, screen #4 does not exclude non-seismic equipment.
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 6 of 15 Rev. 1 The McGuire Unit 1 & 2 SFP relies on passive design features to limit the amount of inventory which could be inadvertently drained. In general, the mechanical piping interfaces below the SFP normal water level are either equipped with siphon breakers, and/or the pipe elevation does not extend more than 2-4' below normal SFP water level. The McGuire SFP is normally aligned to the fuel transfer canal to support the Safe Shutdown Facility Standby Make-up Pump (SBMUP).The SBMUP is periodically aligned to the spent fuel pool for testing and was considered to be a potential rapid drain-down pathway, thus some of the associated components in the flow-path were included in the SWEL-2 Rapid Drain Down list (ATTACHMENT 3). The SWEL-2 Rapid Drain Down List also included some components which could pose a rapid drain down risk during refueling operations (e.g. reactor cavity seal, refueling canal drains, etc.). The final SWEL-2 list was selected based on a sampling of appropriate equipment types from the Base-2 and Rapid Drain Down Lists. The SWEL-2 list is provided in ATTACHMENT 4 and was comprised of 8 components.
Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 6 of 15 Rev. 1 The McGuire Unit 1 & 2 SFP relies on passive design features to limit the amount of inventory which could be inadvertently drained. In general, the mechanical piping interfaces below the SFP normal water level are either equipped with siphon breakers, and/or the pipe elevation does not extend more than 2-4' below normal SFP water level. The McGuire SFP is normally aligned to the fuel transfer canal to support the Safe Shutdown Facility Standby Make-up Pump (SBMUP).The SBMUP is periodically aligned to the spent fuel pool for testing and was considered to be a potential rapid drain-down pathway, thus some of the associated components in the flow-path were included in the SWEL-2 Rapid Drain Down list (ATTACHMENT 3). The SWEL-2 Rapid Drain Down List also included some components which could pose a rapid drain down risk during refueling operations (e.g. reactor cavity seal, refueling canal drains, etc.). The final SWEL-2 list was selected based on a sampling of appropriate equipment types from the Base-2 and Rapid Drain Down Lists. The SWEL-2 list is provided in ATTACHMENT 4 and was comprised of 8 components.
 
4.0 Seismic Walkdowns and Area Walk-Bys Duke Energy contracted the Shaw Group / ARES Corporation team to perform the NTTF 2.3 seismic walkdowns at McGuire Nuclear Station. The McGuire Unit 1 walkdown summary report, the component Seismic Walkdown Checklists (SWC), and the Area Walk-By Checklists (AWC)are provided in ATTACHMENT
===4.0 Seismic===
Walkdowns and Area Walk-Bys Duke Energy contracted the Shaw Group / ARES Corporation team to perform the NTTF 2.3 seismic walkdowns at McGuire Nuclear Station. The McGuire Unit 1 walkdown summary report, the component Seismic Walkdown Checklists (SWC), and the Area Walk-By Checklists (AWC)are provided in ATTACHMENT
: 5. Duke Energy personnel subsequently completed the walkdown checklists for the initially inaccessible components, and these are provided in ATTACHMENT 7.The Seismic Walkdowns and Area Walk-bys were conducted in accordance with the EPRI guidance outlined in EPRI Technical Report #1025286 (Reference MCC-1612.00-00-0001, Rev.0). The EPRI guidance Seismic Walkdown Check-lists (SWC)s were completed for each item on the SWEL. The EPRI guidance Area Walk-by Check-lists (AWC)s were also completed for areas/rooms associated with SWEL equipment.
: 5. Duke Energy personnel subsequently completed the walkdown checklists for the initially inaccessible components, and these are provided in ATTACHMENT 7.The Seismic Walkdowns and Area Walk-bys were conducted in accordance with the EPRI guidance outlined in EPRI Technical Report #1025286 (Reference MCC-1612.00-00-0001, Rev.0). The EPRI guidance Seismic Walkdown Check-lists (SWC)s were completed for each item on the SWEL. The EPRI guidance Area Walk-by Check-lists (AWC)s were also completed for areas/rooms associated with SWEL equipment.
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 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.
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The AWC was previously completed for 1 ETB and was not re-performed.
The AWC was previously completed for 1 ETB and was not re-performed.
Table 4-1 was updated based on the results of these recent walk-downs.
Table 4-1 was updated based on the results of these recent walk-downs.
TABLE 4-2 Walkdown Inspections Deferred to Next Refueling Outage ,nt LocationT ibEq 1 Reactor Bldg. 1NC-32B Reactor Coolant System Pressurizer PORV Reactor Coolant System Pressurizer 1 Reactor Bldg. 1 NC-34A PORV 1 Reactor Bldg. 1 NI-430A N2 Assured Supply to 1NC-34A 1 Reactor Bldg. 1 NI-431 B N2 Assured Supply to 1 NC-32B 1 Reactor Bldg. 1ND-1B RHR Pump Hotleg Suction Isolation 1 Reactor Bldg. 1ND-2AC RHR Pump Hotleg Suction Isolation Completed during 2013 Spring Refueling outage 1 1 Auxiliary Bldg. 1ETB 4Kv Essential Switchgear
TABLE 4-2 Walkdown Inspections Deferred to Next Refueling Outage ,nt LocationT ibEq 1 Reactor Bldg. 1NC-32B Reactor Coolant System Pressurizer PORV Reactor Coolant System Pressurizer 1 Reactor Bldg. 1 NC-34A PORV 1 Reactor Bldg. 1 NI-430A N2 Assured Supply to 1NC-34A 1 Reactor Bldg. 1 NI-431 B N2 Assured Supply to 1 NC-32B 1 Reactor Bldg. 1ND-1B RHR Pump Hotleg Suction Isolation 1 Reactor Bldg. 1ND-2AC RHR Pump Hotleg Suction Isolation Completed during 2013 Spring Refueling outage 1 1 Auxiliary Bldg. 1ETB 4Kv Essential Switchgear 5.0 Licensing Basis Evaluations As outlined in section 4.0 TABLE 4-1, a total of 32 Potentially Adverse Seismic Conditions (PASC) were identified by the Seismic Walkdowns and the Area walkby's.
 
===5.0 Licensing===
 
Basis Evaluations As outlined in section 4.0 TABLE 4-1, a total of 32 Potentially Adverse Seismic Conditions (PASC) were identified by the Seismic Walkdowns and the Area walkby's.
The potentially adverse seismic conditions were entered into the Corrective Action Program (CAP). Engineering evaluation was performed as warranted for the potentially adverse seismic condition, and in all cases the engineering evaluation concluded that the condition was in conformance with the current licensing bases. In some cases work requests or CAP ACTIONS were initiated to resolve minor issues (e.g. loose fastener, add grout, etc.), update design documents, and/or to enhance field equipment clearances.
The potentially adverse seismic conditions were entered into the Corrective Action Program (CAP). Engineering evaluation was performed as warranted for the potentially adverse seismic condition, and in all cases the engineering evaluation concluded that the condition was in conformance with the current licensing bases. In some cases work requests or CAP ACTIONS were initiated to resolve minor issues (e.g. loose fastener, add grout, etc.), update design documents, and/or to enhance field equipment clearances.
The potential adverse conditions and their individual Problem Investigation process (PIP) tracking numbers are listed in the Unit 1 NTTF 2.3 Seismic Walkdown Reports (ATTACHMENTs 5 and 7).6.0 IPEEE Vulnerabilities The McGuire IPEEE NRC submittal of 6/1/94 (Reference
The potential adverse conditions and their individual Problem Investigation process (PIP) tracking numbers are listed in the Unit 1 NTTF 2.3 Seismic Walkdown Reports (ATTACHMENTs 5 and 7).6.0 IPEEE Vulnerabilities The McGuire IPEEE NRC submittal of 6/1/94 (Reference

Revision as of 20:49, 11 May 2019

Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Seismic Aspects of Recommendation 2.3 of the Near Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML13190A272
Person / Time
Site: McGuire Duke Energy icon.png
Issue date: 06/20/2013
From: Capps S D
Duke Energy Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13190A272 (78)
v • d • e


Text

Steven D. Capps DUKE Vice President ENERGY. McGuire Nuclear Station Duke Energy MG01VP I 12700 Hagers Ferry Road Huntersville, NC 28078 o: 980.875.4805 f: 980.875.4809 Steven.Capps@duke-energy.com SECURITY-SENSITIVE INFORMATION -WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5 and 7 of ENCLOSURE 1, THIS LETTER IS UNCONTROLLED June 20, 2013 10 CFR 50.54(f)U. S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

SUBJECT:

Duke Energy Carolinas, LLC (Duke Energy)McGuire Nuclear Station (MNS), Unit 1 Docket Nos. 50-369 Renewed License Nos. NPF-9 Response to NRC Request for Information Pursuant to Title 10 Code of Federal Regulations 50.54(f) Regarding Seismic Aspects of Recommendation 2.3 of the Near Term Task Force Review of Insights from the Fukushima Dai-lchi Accident.

REFERENCES:

1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident, dated March 12, 2012, Accession No. ML12053A340
2. EPRI Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, dated June 20, 2012 3. NRC Letter, Endorsement of Electric Power Research Institute (EPRI) Draft Report 1025286, "Seismic Walkdown Guidance", dated May 31, 2012, Accession No. ML12145A529
4. Duke Energy's 180-Day Response to March 12, 2012, Request for Information Regarding Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights for the Fukushima Dai-Ichi Accident, dated July 9, 2012, Accession No. ML12194A028
5. Duke Energy's November 26, 2012 Seismic 2.3 response to Information Requested by NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(o) Regarding Recommendations 2.1, 2.3.and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchiAccident, dated March 12, 2012, Accession No. ML12361A006 A- oom www.duke-energy.com SECURITY-SENSITIVE INFORMATION

-WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5 and 7 of ENCLOSURE 1, THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission June 20, 2013 Page 2 On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to Duke Energy. On November 26, 2012, Duke Energy responded to the request and submitted the Unit 1 and Unit 2 Seismic Walkdown Reports for the accessible areas of the plant. In the response, Duke Energy also committed to provide an updated report for those inaccessible areas of Unit 1 by September 1, 2013. There were no inaccessible areas for Unit 2. A copy of the Unit 1 report is attached which documents the inspection results in Enclosure

1. Attachments 1 through 6 of the report are unchanged, but are included for completeness.

Attachments 7 and 8 of the report are new and reflect the inaccessible area inspection results for Unit 1.Attachment 5 and 7 of the report contain information that Duke Energy is requesting the NRC withhold from public disclosure in accordance with the requirements of 10CFR 2.390(d)(1).

In accordance with NRC Regulatory Issue Summary 2005-26, an affidavit is not required for the security-sensitive information withheld under 10 CFR 2.390(d)(1).

This letter contains no new regulatory commitments.

If you have any questions or require additional information, please contact George Murphy at (980) 875-5715.I declare under the penalty of perjury that the foregoing is true and correct. Executed on June 20, 2013.Sincerely,ýSteven D. Ca p Enclosure SECURITY-SENSITIVE INFORMATION

-WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5 and 7 of ENCLOSURE 1, THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission June 20, 2013 Page 3 xc: V.M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, Georgia 30303-1257 Eric J. Leeds, Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 0-8C2A 11555 Rockville Pike Rockville, MD 20852-2738 J.S. Kim, Project Manager (MNS and CNS)U.S. Nuclear Regulatory Commission One White Flint North, Mailstop 8 G9A 11555 Rockville Pike Rockville, MD 20852-2738 J. Zeiler NRC Senior Resident Inspector McGuire Nuclear Station Justin Folkwein American Nuclear Insurers 95 Glastonbury Blvd., Suite 300 Glastonbury, CT 06033-4453 SECURITY-SENSITIVE INFORMATION

-WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5 and 7 of ENCLOSURE 1, THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission June 20, 2013 Page 4 bxc: (w/o enclosure)

R.J. Duncan (EC07H)B.C. Waldrep (EC07H)C.J. Thomas (EC05P)D.H. Llewellyn (EC09E)G.D. Robison (EC09E)M.C. Nolan (EC05P)S.D. Capps (MG01VP)C.J. Morris (MG01VP)S.M. Snider (MG01VP)H.D. Brewer ((MG01VP)J.N. Robertson (MG02MO)G.M. Murphy (MG01RC)RGC Date File, (MG01RC)MNS Master File (MG01DM, File MC 801.01)ELL (EC05P)

SECURITY-SENSITIVE INFORMATION

-WITHHOLD UNDER 10 CFR 2.390(d)(1)

UPON REMOVAL OF ATTACHMENT 5 and 7 of ENCLOSURE 1, THIS LETTER IS UNCONTROLLED United States Nuclear Regulatory Commission June 20, 2013 Page 5 ENCLOSURE 1: McGuire Nuclear Station Unit I Seismic Walkdown Report Revision I Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 1 of 15 Rev. 1 Revision Log: Rev. 0 Initial NRC submittal dated November 26, 2012 Rev. 1 Supplemental NRC submittal to address "initially" inaccessible components.

Revised pages 1-15, Added ATTACHMENTS 7 & 8.Executive Summary The results of the McGuire Unit 1 Fukushima Dai-ichi Near-Term Task Force (NTTF)Recommendation 2.3 Seismic Walkdowns are provided here-in. 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 (issued June 2012). The performance of the seismic walkdowns is required in response to the Nuclear Regulatory Commission's (NRC) 10CFR50.54(f) letter regarding NTTF Recommendation 2.3: Seismic. The EPRI guidance outlined requirements for personnel qualifications, selection of walkdown components, the conduct of the walkdowns, evaluation of potentially adverse conditions against the plant seismic licensing basis, and reporting requirements.

The guidance further provided check lists to document the performance of the seismic walkdowns and walk-bys.Revision 0 of the submittal report documented the walkdown results for the accessible components as of November 2012. Revision 1 of the submittal report added the walkdown results for the previously in-accessible components.

1.0 Seismic Licensing Basis Site Characteristics:

Major Category I structures are supported on sound rock (UFSAR Sections 3.7.1.4, 3.7.1.5, 3.7.1.6, 3.8.4, 3.8.5, 3.8.5.4.1).

Where zones of irregular weathering of bedrock occurred, the weathered material was excavated and fill concrete was used under foundation structures, or piles were driven to suitable rock bearing for Category I structure (UFSAR Section 2.5.1.2).Response Spectra: The Safe Shutdown Earthquake (SSE) for McGuire 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 2.5.2.6, 2.5.2.11, 3.1, and MCS-1465.00 0009, section 3.3).The ground response spectra curves are enveloped for analysis and design of all Category 1 building foundations on closely joined rock and slightly weathered rock and for all building elevations where the floor slab rests on rock or fill concrete (MCS-1465.00-00-0009, section 3.3).

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 2 of 15 Rev. 1 System, Structure, 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 1 (UFSAR 3.2.1). The McGuire design complies with Regulatory Guide 1.29 for SSC seismic design requirements.

Seismic Category I SSCs are designed to maintain their functional capability in-the event of a SSE. The seismic design of Category I SSCs is outlined in UFSAR Section 3.2 and Tables 3-1, 3-2, 3-4 & 3-7. Seismic Category I SSCs are also designed to withstand the effects of the Operating Basis Earthquake without loss of capability to perform their safety functions.

Applicable seismic design codes and standards include (MCS-1465.00-00-0009, Section 3.2, UFSAR section 3.2 and Tables 3-1 through 3-7): " 10CFR50, Appendix A, General Design Criteria 2 -Design Bases for Protection Against Natural Phenomena* Duke Class A, B, C piping per ASME Section III, 1971, except for the Nuclear Service Water piping which was designed per ANSIB31.7, Class III (Reference UFSAR Table 3-5)" Duke Class A, B, C valves per ASME Section III, 1971 (Reference UFSAR Table 3-6)* Duke Class F valves per ANSI B31.1.0 (1967), Class III (Reference UFSAR Table 3-6)* Regulatory Guide 1.29, "Seismic Design Classification," Revision 3, September 1978.* 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 IE Equipment for Nuclear Power Generating Stations.

2.0 Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 3 of 15 Rev. 1 Personnel Qualifications The personnel involved in the McGuire NTTF Recommendation 2.3 Seismic Walkdown effort satisfactorily met the qualification requirements of EPRI 1025286. The personnel responsibilities and qualifications are outlined in TABLE 2-1 below. Additional Peer Review Team experience is outlined within the Peer Review Report (ATTACHMENT 6).TABLE 2-1 Walkdown Personnel Experience and Training a)) 3 = C l 0 C .2 a) = 0- (S G(1) CU L: _ Wu CL d)o a)a, 3- -0 a, W)>- > -a Qa 0 Q >Mark Eli, P.E. (Ares) BS/Civil Engineering 32 SWE (2)(3) X Charles M. Conselman, BS/Civil Engineering 28 SWE (2)(3) X P.E. (ARES) BCinn n2 S ()3X Bryan Hanna, P.E. BS/Civil Engineering 12 SWE (2)(3) X (ARES)Kevin Rubright (ARES) BS/Civil Engineering 30 SWE74z' X Harpreet Ghuman BS/Civil Engineering 4 SWE (2) X (ARES)Paul Baughman, P.E. SQUG X(3)PArl BS/Civil Engineering

>40 SWE (2) (3)(Ares) SWE_______________

___George Bushnell, P.E. S§QUG (P (HV)BS/Mechanical Engineering

>40 SE(2) X George Hermann BS/Mechanical Engineering 17 SWE (2) X (SHAW) Technology Thomas Tonden, P.E. MS Energy Engineering

>35 SWE (2) X (SHAWV) ____Karen Kuhn (SHAW) BS/Nuclear Engineering 11 SWE (' X Robert L. Keiser, P.E. BS/Civil Engineering SQUG-T1T (Duke) MS/Civil Engineering

>20 SWE (2) X Breece C. Nesbitt, P.E. BS/Civil Engineering

>40 SWE (2) X (Duke)Mike F. Langel, P.E. BS/Civil Engineering

>35 SWE (2) X X (Duke) ME/Civil Engineering I Charles N. BS/Civil Engineering 4 SWE X X Cunningham, (Duke) MS/Civil Engineering Harry E. Vanpelt, P.E. BS/Nuclear Engineering, MS/Mechanical 36 X X (Duke) Engineering Phil A. Thompson N/A 37 SRO-4) X (Duke) (25 yr-)Bryan D. Meyer (Duke) BS/Mechanical Engineering

>28 SWE X X X X Drew Lyerly (Duke) BS/Civil Engineering 6 X NOTES: 1)2)3)4)SQUG Seismic Capability Engineers (SCEs) have successfully completed SQUG training.Seismic Walkdown Engineers (SWEs) have successfully completed EPRI 1025286 2 day walkdown training course.Senior Team Member.Prior Senior Reactor Operator (SRO).

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 4 of 15 Rev. 1 3.0 Selection of Equipment for the SWEL-1 and SWEL-2 Lists The McGuire Unit 1 SWEL-1 and SWEL-2 equipment selection was performed in accordance with the EPRI guidance outlined in EPRI Technical Report #1025286 (Reference MCC-1612.00-00-0001, Rev. 0).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 McGuire IPEEE Seismic Walkdown list (MCC-1535.00-00-0004, Rev. 0, ATTACHMENT

24) was used as an initial "Base-1 List" of potential SWEL-1 walkdown components.

This list includes shared, Unit 1 and Unit 2 components; however, only the shared and Unit 1 components are considered part of the Unit 1 SWEL-1 Base-1 list. Additionally, the IPEEE list included some non-safety/non-seismic equipment, which were not considered to be part of the Unit 1 SWEL-1 Base-1 list. The prior IPEEE list effectively represents the output of EPRI guidance equipment Screening criteria's

  1. 1, #2 and #3. The SWEL-1 "Base-1 List" is provided in ATTACHMENT 1.EPRI Screening criteria #4 was then used to select equipment from this "Base List." EPRI screening criteria #4 requires a representative cross-section of the following sample selection attributes:
  • include a variety of systems,* Include variety of types of equipment,* Include a variety of equipment environments,* Include major new/replacement equipment* Include equipment enhancements implemented in response to prior IPEEE walkdown identified discrepancies The McGuire Unit I SWEL-1 equipment list (ATTACHMENT
2) comprised 99 components in -22 different systems. Safety and PRA significant systems are well represented within the SWEL-1 equipment selection, such as Auxiliary Feedwater (CA, SA), Emergency Service Water (RN), Essential AC Power (EDG, EPC, EPE), Vital DC Power (EPQ, EPG, EPL), Solid State Protection System (IPE), Residual Heat Removal (ND), Safety-Injection (ND, NI, NV), Closed Cooling Water System (KC), control room ventilation (VC, YC), Main Steam (SM, SV), Reactor Coolant (NC), and containment spray (NS) systems. The systems and components selected for SWEL-1 support the EPRI screen #3 safety functions, which are necessary to achieve safe reactor shutdown, andlor containment isolation.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 5 of 15 Rev. 1 The SWEL-1 list represented equipment from each of the EPRI guidance equipment classes, with the exception of air compressors and motor-generator sets. McGuire does not have any Seismic Cat I equipment within these two equipment classes. The SWEL-1 lists included equipment located in -44 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

>20% of the SWEL-1 list. Similarly, the SWEL-1 list included some equipment which was enhanced in response to the prior IPEEE walkdown 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.The McGuire 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 OR 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

3) 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, pump motor air handling units, 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 SFP mechanical connections were further reviewed to ascertain whether they could present the potential for rapid drain-down of the SFP in-the-event of postulated seismic event. Rapid drain-down is considered to be an uncontrolled and unlimited drain-down due to a postulated leakage from a mechanical piping/component interface.

The EPRI guidance provided a definition for SFP uncontrolled drain-down, which was seismic induced leakage which could drain SFP to within 10'of the top of the fuel within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Unlike the prior screening criteria, screen #4 does not exclude non-seismic equipment.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 6 of 15 Rev. 1 The McGuire Unit 1 & 2 SFP relies on passive design features to limit the amount of inventory which could be inadvertently drained. In general, the mechanical piping interfaces below the SFP normal water level are either equipped with siphon breakers, and/or the pipe elevation does not extend more than 2-4' below normal SFP water level. The McGuire SFP is normally aligned to the fuel transfer canal to support the Safe Shutdown Facility Standby Make-up Pump (SBMUP).The SBMUP is periodically aligned to the spent fuel pool for testing and was considered to be a potential rapid drain-down pathway, thus some of the associated components in the flow-path were included in the SWEL-2 Rapid Drain Down list (ATTACHMENT 3). The SWEL-2 Rapid Drain Down List also included some components which could pose a rapid drain down risk during refueling operations (e.g. reactor cavity seal, refueling canal drains, etc.). The final SWEL-2 list was selected based on a sampling of appropriate equipment types from the Base-2 and Rapid Drain Down Lists. The SWEL-2 list is provided in ATTACHMENT 4 and was comprised of 8 components.

4.0 Seismic Walkdowns and Area Walk-Bys Duke Energy contracted the Shaw Group / ARES Corporation team to perform the NTTF 2.3 seismic walkdowns at McGuire Nuclear Station. The McGuire Unit 1 walkdown summary report, the component Seismic Walkdown Checklists (SWC), and the Area Walk-By Checklists (AWC)are provided in ATTACHMENT

5. Duke Energy personnel subsequently completed the walkdown checklists for the initially inaccessible components, and these are provided in ATTACHMENT 7.The Seismic Walkdowns and Area Walk-bys were conducted in accordance with the EPRI guidance outlined in EPRI Technical Report #1025286 (Reference MCC-1612.00-00-0001, Rev.0). The EPRI guidance Seismic Walkdown Check-lists (SWC)s were completed for each item on the SWEL. The EPRI guidance Area Walk-by Check-lists (AWC)s were also completed for areas/rooms associated with SWEL equipment.

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 -35' radius around SWEL component or the room containing the SWEL component) had potentially degraded anchorage, or whether the potential for adverse seismic interactions were present.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 7 of 15 Rev. 1 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 107 Seismic Walkdown Checklists (SWC) were completed for the components listed on the SWEL. This total was comprised of 99 SWEL-1 components, and 8 SWEL-2 components.

The originally accessible component walkdowns were performed by Shaw Group / ARES personnel.

Duke Energy personnel completed the remaining walkdowns for the "inaccessible" components which required a unit outage to complete (Refer to section 4.0). For the non-line mounted SWEL equipment, an anchorage as-built verification was completed for 57% of the equipment with anchorage.

Additionally, a total of 53 (48 by Shaw/ARES personnel, and balance by Duke personnel)

Area Walk-by Checklists (AWC) were completed for the SWEL-1 scope, and 2 AWC were completed for the SWEL-2 scope.The seismic walkdowns and walk-bys identified 32 "Potentially Adverse Seismic Conditions" which are outlined in TABLE 4-1. Refer to the respective TABLE NOTE(s) for the "CAP Resolution" designation.

The potentially adverse seismic conditions were entered into the Corrective Action Program (CAP). Engineering evaluation was performed as warranted for the potentially adverse seismic condition, and in all cases the engineering evaluation 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 (e.g. loose fastener, add grout, etc.), and/or to enhance field equipment clearances.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 8 of 15 Rev. 1 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Disposition Walkdown Item Potentially Adverse Condition (See notes)1) 1EPQ-BC-EDGA:

1A EDG Battery Elevated shim height not depicted by drawing. 3 Charger 2) 1-EPE-TF-ELXB:

The concrete slab adjacent to two vertical supports of the KV/600 VAC equipment contains cracks.i) Cracks in the concrete floor in the vicinity of bolts i) 1 for units: 1 ETB-17, 1 ETB-16, 1ETB-13, 1 ETB-11, 1 ETB-6, and 1 ETB-9. HN 3440 anchors (observed) are consistent with MC-1906-04, Rev. 8 3) 1 ETB: 4.16 kV and calculations MCC-1535.00-00.0004.

However, Essential Power -"diameter Phillips Red Anchors are concealed Essentialwr (inaccessible) by the base C-channel by design.Switchgear ii) Spalling at corner of grout pad at end of unit ii) 1 (1ETB-1).

Also grout pad height is in excess of 2" resulting in less than design overlap of angle and channel at this location (1ETB-1, MC-1906-04, Rev. 8).4) 1-EPE-TF-ELXA:

Cracks in concrete floor near 2 of 4 anchor groups. Cracks 4.16 kV Essential were within 10 x (anchor diameter) of anchor bolts. 1 Power Transformer Concrete cracks: Cracks in concrete floor between R6D 5) 1 EMXA: 600 VAC and R5D. Floor was coated with epoxy; therefore unable to measure crack width. Anchor bolt location was unable to be 1 determined (see above); therefore, unable to determine distance between anchor bolt and crack in concrete floor.6) 1VGTKO062:

Wl Interaction effect: Relief valve (1VG-33) on top of tank is EDG Starting Air within 1/2" of cable tray.Tank 7) 1VGTKO063:

1IA2 Interaction effect: Relief valve 1VG-34 is approximately 1" EDG Starting Air from cable tray.Tank 8) 1KCTKO009:

U1 KC Interaction effect: Bottom of ladders are welded to access SurgeCTnk K platform (independent of tank) and top of ladder is lashed to 1 tank nozzles. Potential for "event caused" flooding.Interactions effect: Cable tray tie rod support hanger is Suction 1ND-4B: RHRF nearly tom off of the tray which reduces support of 2 cantilevered portion of tray carrying actuator cables.10)1CA-56A:

MDCAP to Interaction effect: Cable tray feeding ICAPNAFPB panel 1 1B SG has cables resting against valve operator air manifold CAP DISPOSITION NOTE(sl: 1)2)3)4)Field configuration meets Current Licensing Bases (CLB) requirements, and no field work required.Field configuration meets CLB requirements; however, work request/work order/ACTION initiated to resolve minor issue, verify unknown condition, or enhance/correct field configuration.

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

CLB not met, and required field modification.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 9 of 15 Rev. 1 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Disposition Walkdown Item Potentially Adverse Condition (See notes)11)Room 600, MDCAP Interaction effect: Approximately 3/4" air supply pipe to valve 1 Room: AWC for has 3+ elbows and approx. 15' of pipe with no support.1 CA-56A Interaction effect: i) Valve 1 CA-36AB air connection to (black) air regulator does not have adequate clearance from i) 2 vertical support member (see photo).12) Room 600, U1 ii) Discharge line from floor drain sump tank impinges MDCA Pump Room: on valve 1 WL-359 and rests on another line ii) 1 Area Walk-By for approximately 5 ft. downstream.

This line also 1CAPNAFPA; passes over Unit 1 Aux. shutdown panel.lCAPU0001; and iii) 1-V520 handwheel has inadequate clearance to Ul iii) 1 1W CAP ; ndline. Not significant.

iv) Approx. 3" pipe directly over enclosure has threaded connections and is hung with threaded iv) 1 rods. Pipe is touching stanchion (but not attached)directly above cabinet. Pipe may deflect and hit vertical Unistrut.Interaction effect: Could not verify whether 1 EVDA and 1 31 EVDA: Vital Panel EVKA are bolted together.

Based on MCM-1314.01-34, 13) DC a 1 EVDA appears to be a discrete enclosure from 1 EVKA. 2 Unclear whether interactions between enclosures was considered in IPEEE review.14)701- Vital Battery Interaction effect: Abandoned eyewash supply pipe is Area A: Area Walk- buckled and kinked. It is supported by rod hangers. Pipe is 1 By for 0-EPL-BC-located over various enclosures and equipment throughout EVCA: I EVDA, etc. vital battery room.15)701- Vital Battery Interaction effect: Abandoned eyewash supply pipe is Area B AWC for 0- buckled and kinked. It is supported by rod hangers. Pipe is 1 EPL-BC-EVCB;1 located over various enclosures and equipment throughout EVDB; EVDB; etc. vital battery room.16)701- Vital Battery Interaction effect: Abandoned eyewash supply pipe is Area C AWC for 0- buckled and kinked. It is supported by rod hangers. Pipe is 1 EPL-BC-EVCC; located over various enclosures and equipment throughout EVDC, etc. vital battery room.17) 1EVDD: 125VDC Vital Batter Break Interaction effect: Shims were located between block wall Vital Battery Breaker adcbnt Paneland cabinet.Panel 18)701- Vital Battery Interaction effect: Abandoned eyewash supply pipe is Area D AWC for buckled and kinked. It is supported by rod hangers. Pipe is 1 1EVDD; 1EPG-BI- located over various enclosures and equipment throughout EVID, etc. vital battery room.19)Room 705- Electrical Penetration Room: Interaction effect: Rigid ducts span between 1 EFE-LX- 1 AWC for 1ETB & 1- ELXB and similar units in the room.EPE-TF-ELXB CAP DISPOSITION NOTEsW: 1)2)3)4)Field configuration meets Current Ucensing Bases (CLB) requirements, and no field work required.Field configuration meets CLB requirements; however, work request/work order/ACTION initiated to resolve minor issue, verify unknown condition, or enhance/correct field configuration.

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

CLB not met, and required field modification.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 10 of 15 Rev. 1 TABLE 4-1 Potentially Adverse Seismic Conditions CAP Disposition Walkdown Item Potentially Adverse Condition (See notes)20) Room 730: AWC for Interaction effect: 1 KC-325 valve actuator within 1/4" of 10" 1NI-178B.

diameter pipe that is suspended in a hanger that is not 1 restrained vertically.

21)Room 730: VCT Interaction effect: Directly below 1NV-146 -3 feet, there is a Hallway: AWC for loose piece of pipe and a small tool that could fall during a 1 1NV-141A.

seismic event.Interaction effect: 22)Room 730: VCT i) Valve actuator, 1NVG-137A, conduit connections are i) 2 Hallway: AWC for resting on a fixed support.1NV-141A.

ii) 6" pipe at ceiling has slipped off center of support held ii) 1 by 2 spring cans, one spring can is fully-compressed, other appears loose. Valve 1 FW23 is in this line.23)1KCPU0002:

1A2 Interaction effect: Fire sprinkler line over pump in contact 1 KC Pump with wire-way to pump motor.24)Room 601, U2 Interaction effect: Sump drain pipe is attached to the ceiling MDCA Pump Room: with threaded rod and could displace into pressurized tubing 1 AWC for ORN7A for auxiliary feedwater pump 2CAMR0002/2BETB6 25)1 NSHX0004:

1B Notched column flanges: Anchors are complete; however, Containment Spray multiple wide flange columns have notches in the flange I Heat Exchanger near base plate.26)1 NSHX0003:

1A Notched column flanges: Anchors are complete; however, Containment Spray multiple wide flange columns have notches in the flange 1 Heat Exchanger near base plate.27)Unit 1, Room 926- House-keeping:

Trash can was not secured / constrained.

1 AWC for 1VC-IA 28)1 NVPU0046:

Interaction effect: Valve 1 NV-937 has contact with pump Standby Make-up discharge pipe, which could adversely affect the function of 1 Pump the pump in a seismic event.29)1KFPU0001:

1A KF Interaction effect: end of valve stem (1 KF-2) on pump 1 Pump suction valve is within -1/8" of a structural (HSS) support.30)Room 816: AWC for Interaction effect: One end of 4" cable tray that supports a 1KFPU0001&2; flexible conduit to 1 MRNSV2400 (Fuel Pool Cool Pump Air 2 1 KFHX0003&4; Cooler B) solenoid was supported/"anchored" by something 1VAAH0031 resembling duct tape (only).31) 1B Cold Leg Instrument impulse tubing track L-bracket support not tightly Accumulator Room: secured for 1NIIV5060.

AWC for 1NI-431B 32) 1 ETB 4kV Essential Fluorescent light fixture adjacent to front of 1 EPC-BK-Switchgear SWC ETB14 had a single unsecured rod-hanger.

CAP DISPOSITION NOTE(s): 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 configuration.
4) CLB not met, and required field modification.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 11 of 15 Rev. 1 Additionally, there were 11 SWCs which documented that portions of internal electrical cabinet anchorage was concealed in-part or entirely, and the SWCs were designated to be "unknown." The SWC for 1ETB (4 kV Essential Switchgear) was initially specified to be "unknown" due to personnel safety concerns, thus this component internal anchorage inspection was deferred (refer to the inaccessible component section below). The remaining 10 SWCs which were designated "unknown" are as follows:* 6 SWCs were associated with 125 VDC vital battery distribution centers (EVDA, EVDB)and 600 VAC Essential MCCs (1 EMXA, I EMXA-1, 1 EMXB, 1 EMXB-1) in which portions of anchors were not accessible because they were covered by structural members or the embedded "C"-channel.

Some physical equipment demolition would be required to visually access all the anchorage.

  • 3 SWCs (EMXE 600 VAC MCC, 1A EDG Battery, 1A CA pump control panel) only a portion of the internal anchorage was visible, due to concealment by wires, wire-ways, or other structure.

A significant portion of the cabinet anchorage was visibly inspected (16 of 18 bolts for EMXE, 10 of 12 fasteners for 1A EDG battery, 8 of 12 anchors for the 1A CA Pump Control Panel). The anchors which could not be visually inspected are judged to be in acceptable condition based on the satisfactory condition of the visually inspected anchorage.

0 The SWC for the Turbine Driven Auxiliary Feedwater Pump (TDCAP) control panel the internal anchorage was concealed by a sheet metal shroud. Therefore, it was not included in the 50% anchorage check. This component inspection was limited to the visual of internal cabinet components to ensure they were secure, exterior perimeter inspection of the cabinet concrete, and for local seismic interaction concerns.This equipment was retained on the SWEL to satisfy various sample selection attributes; however, some physical equipment demolition would be required to visually access all the anchorage.

This equipment is located in a dry, mild environment and not exposed to any physical degradation mechanisms.

The SWCs and associated inspections are deemed to satisfactorily meet the intent of the published EPRI walkdown guidance.

Based on the aggregate results of the seismic walkdowns, there were no significant anchorage deficiencies, nor licensing bases issues identified.

Based on the foregoing discussion, no further equipment walkdowns are planned for these components.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 12 of 15 Rev. 1 INACCESSIBLE COMPONENTS:

The Unit 1 components initially deemed to be inaccessible, which required a unit shutdown in order to complete the walk-downs are listed in TABLE 4-2. These outstanding SWC and associated AWC were completed during the McGuire Unit 1 spring 2013 refueling outage. A SWC for 1ETB was initially partially completed in the fall of 2012, and 1ETB was re-inspected to verify internal anchorage condition and configuration.

The AWC was previously completed for 1 ETB and was not re-performed.

Table 4-1 was updated based on the results of these recent walk-downs.

TABLE 4-2 Walkdown Inspections Deferred to Next Refueling Outage ,nt LocationT ibEq 1 Reactor Bldg. 1NC-32B Reactor Coolant System Pressurizer PORV Reactor Coolant System Pressurizer 1 Reactor Bldg. 1 NC-34A PORV 1 Reactor Bldg. 1 NI-430A N2 Assured Supply to 1NC-34A 1 Reactor Bldg. 1 NI-431 B N2 Assured Supply to 1 NC-32B 1 Reactor Bldg. 1ND-1B RHR Pump Hotleg Suction Isolation 1 Reactor Bldg. 1ND-2AC RHR Pump Hotleg Suction Isolation Completed during 2013 Spring Refueling outage 1 1 Auxiliary Bldg. 1ETB 4Kv Essential Switchgear 5.0 Licensing Basis Evaluations As outlined in section 4.0 TABLE 4-1, a total of 32 Potentially Adverse Seismic Conditions (PASC) were identified by the Seismic Walkdowns and the Area walkby's.

The potentially adverse seismic conditions were entered into the Corrective Action Program (CAP). Engineering evaluation was performed as warranted for the potentially adverse seismic condition, and in all cases the engineering evaluation concluded that the condition was in conformance with the current licensing bases. In some cases work requests or CAP ACTIONS were initiated to resolve minor issues (e.g. loose fastener, add grout, etc.), update design documents, and/or to enhance field equipment clearances.

The potential adverse conditions and their individual Problem Investigation process (PIP) tracking numbers are listed in the Unit 1 NTTF 2.3 Seismic Walkdown Reports (ATTACHMENTs 5 and 7).6.0 IPEEE Vulnerabilities The McGuire IPEEE NRC submittal of 6/1/94 (Reference

8) concluded that there were no vulnerabilities from external events. Thus, there were no identified plant changes which would significantly reduce the risk from external events.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 13 of 15 Rev. 1 Table 3-3 of the 1PEEE NRC Submittal identified several enhancements to resolve minor field walkdown issues (References 6, 8, ATTACHMENT 3). These enhancements are listed in TABLE 6-1.TABLE 6-1 IPEEE Enhancements Equipment Deficiency Identified Resolution Date Resolved* 1EDGA Complete Unit 1 EDG battery racks were missing WO 94050272 & 94050263 12/29/94 spacers. installed missing spacers.

  • 1EDGA Complete (NAS WOs# 00326062 & 00326059) 11/21/94 PIP M94-1003 Unit 2 Upper Surge Tank anchor bolts Replaced bolts per WR 93034428. (Reference 7.4)missing. documented complete prior to 1/25/96.MCCs were noted to be in contact with
  • WO # 00316559 complete prior to each other at a corner (Re. Attach. 1 of MGMM-3870 mechanically 10/5/95 Reference 7.3): fastened the MCCs together to e WO # 00316580* 1EMXB and 1EMXB-1 prevent interaction, complete prior to 0 2EMXB and 2EMXB-1 10/4/95 WO 94030900 cleaned and re- PIP M94-1003 Auxiliary Feedwater CST anchor bolts coated fasteners. (Reference 7.4)and nuts exhibited corrosion.

documented complete prior to 1/25/96.Various movable equipment where Guidelines were incorporated PIP M94-1003 noted to be unsecured and could pose within NSD-104 for station house- (Reference 7.4)documented complete a seismic interaction concern. keeping. prior to 1/25/96.Turbine Driven Auxiliary Feedwater MM-6664/WO 94095550 trimmed PIP M94-1003 Pump control cabinet in contact with panel corner to eliminate contact (Reference 7.4)documented complete'CA' piping. and resealed cabinet, prior to 1/25/96.MM-4118 eliminated pipe PIP M94-1003 KC Heat exchanger saddle bases and interference and add grout. W/O"s (Reference 7.4)concrete curbs require grouting.

94064720, 94053337, 94065089, documented complete and 94065092 prior to 1/25/96.PIP M94-1003 Grating in contact with steam vent Grating trimmed per WR 93034096 (Reference 7.4)valves in exterior doghouses.

& 93034099.

documented complete prior to 1/25/96.PIP M94-1003 Arc barrier connections were not secure WO 94010441 & 94010379 (Reference 7.4)within main control boards. secured the connections.

documented complete prior to 1/25/96.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 14 of 15 Rev. 1 7.0 Peer Review: Duke Energy contracted with the Shaw Group (Shaw) / ARES Corporation (ARES) Team to perform the NTTF 2.3 peer review for the McGuire Nuclear Station (MNS). The Peer Review Report for the initially accessible components is contained in ATTACHMENT

6. A supplemental Peer Review Report (ATTACHMENT
8) was performed for the initially inaccessible components, which were completed during McGuire Unit 1 spring 2013 refueling outage.The Peer Review Team consisted of three individuals (refer to Table 2-2), 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 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.* Conducting an in-process review at the plant site, including interviews with the personnel performing the activity and reviewing in-process documentation.
  • 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 McGuire Design Engineering for licensing review. The peer review of the licensing basis evaluations resulted in some open issues;however, those issues were addressed by updating the licensing basis evaluations documented in the CAP.The conclusion of the peer review is that the MNS 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.

In-process comments on the final walkdown reports, the licensing basis reviews, and the submittal have also been resolved.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal Report for Seismic Walkdowns McGuire Unit 1 Page 15 of 15 Rev. 1

REFERENCES:

1) MCS-1465.00-00-0009, Rev. 1, Seismic Design Bases Document 2) UFSAR Sections 3.1, 3.2.1, 3.8.4, 3.8.5, Tables 3-1 through 3-7 3) UFSAR Section 2.5.1.2, 2.5.2 Site Geology 4) UFSAR Sections 2.5.2.10, 2.5.2.11 SSE/OBE 5) UFSAR Section 3.7 Seismic Design 6) MCC-1612.00-00-0001, Rev.1 7) EPRI Report 1025286, Dated May 2012, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force (NTTF) Recommendation 2.3 (ATTACHMENT 1).8) McGuire NRC Response to GL 88-20, Individual Plant Examination of External Events (IPEEE)Submittal, dated June 1, 1994, T.C. McMeekin to NRC.9) SHAW/ARES Summary Report, Seismic Walkdown Report for Duke Energy's McGuire Nuclear Station Unit 1 1457690101-R-M-00001-1, Rev. 1 (November 5, 2012).10) SHAW/ARES Summary Report, Seismic Walkdown Report for Duke Energy's McGuire Nuclear Station Unit 2 1457690101-R-M-00002-1, Rev. 1 (November 5, 2\012).11) SHAW/ARES Peer Review Summary Report, "NTTF 2.3 Seismic Peer Review Report McGuire Nuclear Station Units 1 and 2 1457690101-R-M-00003-0.
12) MCC-1535.00-00-0003, Rev. 0, Seismic Hazard Curve Sensitivity for the McGuire IPEEE.13) MCC-1535.00-00-0004, Rev. 0, Seismic PRA/IPEEE Back-up Calculation.
14) PIP M94-1003, 'Equipment Deficiencies Identified During the 1994 IPEEE Seismic Walkdowns.
15) MCS-1108.00-00-0002, Rev. 9, "Specification for the Response Spectra and Seismic Displacements for Category I Structure 16) 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" 17) MCS-1108.02-00-0001, Rev. 5, "McGuire Structural Design Specification.

ATTACHMENTS:

1) SWEL-1 Base-1 List (*see note below)2) McGuire Unit 1 SWEL-1 (*see note below)3) McGuire Unit 1 SWEL-2 Base-2 List and Rapid Drain Down List (*see note below)4) McGuire Unit 1 SWEL-2 (*see note below)5) Seismic Walkdown Summary Report and Checklists

(*see note below)6) PEER Review Summary Reports (*see note below)7) Seismic Walkdown Checklists (SWCs) and Area Walkby Checklists (AWCs) for Initially Inaccessible Components

8) Supplemental PEER Review Summary Reports for Initially Inaccessible Components
  • NOTE: Attachments 1-6 were originally transmitted in submittal dated 11/26/12, and are not included here-in.

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal report for Seismic Walk-downs McGuire Unit 1 ATTACHMENT 1 Rev. 1 SWEL-1 Base-1 List Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal report for Seismic Walk-downs McGuire Unit 1 ATTACHMENT 2 McGuire Unit 1 SWEL-1 Rev. 1 Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal report for Seismic Walk-downs McGuire Unit 1 Rev. 1 ATTACHMENT 3 -McGuire Unit 1 SWEL-2 Base-2 List and Rapid Drain Down List Unit 1 SWEL-2 "Base List".: Class of Column-Equipment#

Description System C o Bldg Elev. Room # CGrid Function Equipment Grid 05-Horizontal 1KFPU0001 1A KF Pump KF Pump Aux Bldg 750 816 PP-52 SFP Cooling IKFPU0002 1B KF Pump KF 05-Horiontal Aux Bldg 750 816 PP-52 SFP Cooling Pump II 1KFHX003 1A KF HtX KF 21-Tanks/HtXs Aux Bldg 750 816 PP-52 SFP Cooling 1KFHX004 1B KF HtX KF 21-Tanks/HtXs Aux Bldg 750 816 PP-52 SFP Cooling 1VAAH0030 1A KF Pump AHU VA 10-AHU Aux Bldg 750 816 PP-52 SFP Cooling 1VAAH0031 1B KF Pump AHU VA l0-AHU Aux Bldg 750 816 PP-52 SFP Cooling 03-Med Voltage 1ETA-13 1A KF Pump Breaker EPC Metal Clad Aux Bldg 750 803 AA-50 SFP Cooling SWGR 03-Med Voltage 1ETB-13 1B KF Pump Breaker EPC Metal Clad Aux Bldg 733 705 AA-50 SFP Cooling SWGR I I 1RN-140A A KF Pump Ess AHU Sup RN 07-AOV Aux Bldg 750 816 PP-52 SFP Cooling Isol 01-Motor Control 1EMXA-F3D 1A KF Pump Motor AHU EPE Centers/Wall Aux Bldg 750 808 FF-55 SFP Cooling lv DMotor Mounted Contactors 01-Motor Control 1ENvXB-4C 16 KF Pump Motor AHU EPE Centers/Wall Aux Bldg 750 722 FF-55 SFP Cooling Motor Mounted I_ Contactors 1RN-240B 1B KF Pump Ess AHU Sup RN 07-AOV Aux Bldg 750 816 PP-52 SFP Cooling Isol Unit I SWEL-2 "Rapid Draindown List" Class of Column.Equipment

  1. Description Syste Eass o Elev. Room # Grid Function EaulSmen R Grid 1NV-842AC SBMUP Suction Isolation NV 08-MOV/SOV Rx Bldg 725 Annulus 273°/61 R SFP & Refueling Cavity Inventory SBMUP Suction Pulsation 00-Other-1 NVAC0048 Dampener (non-seismic NV (pulsation Rx Bldg 725 Annulus 320*/61 R N/A SSC) dampener)INVPU0046 SBMUP (non-seismic SSC) NV 05-Horizontal Rx Bldg 725 Annulus 320°161 R N/A Pump SBMUP Discharge Pulsation 00-Other-1NVAC0049 Dampener (non-seismic NV (pulsaton Rx Bldg 725 Annulus 320'/61 R N/A SSC) dampener)I NVFL0047 SBMUP Discharge Filter NV 00- Other Rx Bldg 725 Annulus 320°/61 R N/A (non-seismic SSC)1 NV-849AC SBMUP Discharge Isolation NV 08-MOV/SOV Rx Bldg 725 Annulus 273*/61 R N/A Reactor Cavity Seal Refueling Reactor Cavity FW 00- Othe R B n/a n/A n/a SFP & Refueling Seal __ 00 Cavity Inventory 1 FW-8, -10, -25, -26, -46, Refuling Cavity Manual Drain FW 00 -Other Rx Bldg n/a n/A n/a SFP & Refueling-47, -76, -75 Valves Cavity Inventory Fuel Transfer Tube blind Fuel Transfer Tube Blind KE 00I- Oer Rx Bldg n/a n/A n/a SFP & Refueling flange Flange __ 00 -Other Cavity Inventory Fuel Transfer Tube Weir Fuel Transfer Tube Weir KF 00 -Other RF Bldg n/a n/A n/a SFP & Refueling Gate Gate T Cavity Inventory Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal report for Seismic Walk-downs McGuire Unit 1 Rev. 1 ATTACHMENT 4 McGuire Unit 1 SWEL-2 Class of Column- Major New/Equipment
  1. Description System Bld Elev. Room # Grid Replacement Function-Equipment X -actuator SFP &INV-842AC SBMUP Suction Isolation NV 08-MOVISOV Rx Bldg 725 Annulus 273*/61 R replacement ueling EC-9992) Cavity (EC-99992)

Inventory SBMUP Suction Pulsation Dampener 00-Other-X -replaced 1 NVAC0048 (non-seismic SSC) NV (pulsation Rx Bldg 725 Annulus 320°161 R MGMM11916 N/A ( dampener) (EC 37849)05-Horizontal 1 NVPU0046 SBMUP (non-seismic SSC) NV Pump Rx Bldg 725 Annulus 320°/61 R N/A 05-Horizontal X -replaced 1KFPU0001 1A KF Pump KF Pump Aux Bldg 750 816 PP-52 motor SFP Cooling EC105550 05-Horizontal 1KFPU0002 1B KF Pump KF Pump Aux Bldg 750 816 PP-52 SFP Cooling 1KFHX0003 1A KF HtX KF 21-Tanks/HtXs Aux Bldg 750 816 PP-52 SFP Cooling 1KFHX0004 1B KF HtX KF 21-Tanks/HtXs Aux Bldg 750 816 PP-52 SFP Cooling 1VAAH0031 1B KF Pump AHU VA 10-AHU Aux Bldg 750 816 QQ-52 SFP Cooling Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal report for Seismic Walk-downs McGuire Unit 1 Rev. 1 ATTACHMENT 6 PEER Review Summary Report Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal report for Seismic Walk-downs McGuire Unit 1 ATTACHMENT 8 Supplemental PEER Review Summary Reports for Initially Inaccessible Components Rev. 1 Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal report for Seismic Walk-downs McGuire Unit 1 ATTACHMENT 1 Rev. 1 SWEL-1 Base-1 List 053 TABLE 2 MECHANICAL EQUIPMENT LIST FOR MCGUIRE UNIT I IPEEE WALKDOWN 0 II II I I II CB troin components are shown In parentheses.

A detalled walkdown of these components Is not necessary If the "B train configuration Is similar to the 'A' train.)_ _If CA SiSMM COMPONENTSUI Lbne Included In -Press. bndry...CA SYSTEM COMPONENTS Size (n.) Seismic PRA -Integrity only Non-Safet-AOV ICA20AB 6 AOV I CA27A (328) 4 AOV ICA36AB 4 AOV ICA48AB 4 AOV 1CA52AB 4 AOV ICAS6A (44B) .4 AOV )CA60A (40B) 4 AOV ICA64AB 4 MOV ICA7AC 8 MOV ICAIIA (98) 8 MOV 1CA15A (18B) 6 MOV ICA38B 4 MOV ICA50B 4 MOV 1CA54AC 4 MOV ICA58A (468) 4 MOV 1CA62A (42B) 4 MOV 1CA66AC 4 MOV ICA86A (116B) 8 TURBINE DRIVEN PUMP I (INCLUDING X CONDENSATE EDUCTOR)TURBINE DRIVEN PUMP LUBE OIL HX MOTOR DRIVEN PUMP IA (IB) X WZ SUMP PUMP A (B) FROM GROUNDWATER DRAINAGE SUMP A (A)DIESEL GENERATOR AND SUPPORTING Line Included In -Press. bndry._COMPONENTS Size (in.)- Seismic PRA Integ~rity only -Non-Safety DIG IA (01) X FUEL OIL DAY TANK IA (I1B) x FUEL OIL STORAGE TANK IA (1) B_FUEL OIL BOOSTER PUMP ]A (113) X FUEL OIL FUEL TRANSFER FILTERS IA1, 1A2 X (IBI. IB2)FUEL OIL TRANSFER PUMP )A (113) _I~R-OPERATED REGULA1N(VALVE lKD9 4 ( IKD29)--J-.~ £-~ _______________ .L.L _______________

Pftgel-/

054 TABLE 2 -.0 DIESEL GENERATOR AND SUPPORTING 11 1in Included In Press. bndry.COMPONENTS (oant.) Size (In.) I Seismic PRA IInterihonly I Non-Safety 4. 4--; 4--I.KD D/G COOUNGWATER-HXIA (18)'U KD INTERCOOLER PUMP 1A (01)KD JACKET WATER PUMP ]A (IB)KD SURGE TANK IA (15)D/G INTERCOOLER IA 0IB)MOV ILDI08 (113) 4 X LUBE OIL INTAKE STRAINER 1A (1 B) x LUBE OIL FILTER IA (IS) X LUBE OILCOOLER IA (IB) x VD D/G BLDG. VENTILATION FANS DSF-1A. IC (1B. ID)SOLENOID VALVE IVG61 (65) 2 _ _" SOLENOID VALVE 1VG62 (66) 2.2.SOLENOID VALVE 1VG63 (6?) -2 1 SOLENOID VALVE IVG64 (68) 2 VG STARTING AJR TANKS A. 1,A2 (151. IB2) -_ .... X VG INTAKE AIR AFTERCOOLERS AND DRYERS 1A1. 1A2 X (OBI. 182)VG CONTROL AIR VOLUME TANK )A (18) B VG AIR COMPRESSORS A. 1A2 (113. 182) X a-VG UNE PURIFIERS IIAI. 1A2 01311. 182B__ ____ ___GCONTROL AIR FILTER IA (IB) ., _VN AIR INTAKE SILENCER IA (1B) _ _ X VN AIR EXHAUSTSILENCER IA (1B) X WN D/G SUMP PUMPS A2. IA3 (112,1183)

X ZD VACUUM BLOWER PACKAGE IA (1B) --X I Lne Included In Press. bndry.FW SYSTEM COMPONENTS Size (in.) -Sefsmlc PRA Inteardty only Non-Safety MOV IFW1A 8 -MOV IFW27A 14 _MOV IFW32B 8 MOV IFW33A 2 .._MOV 1FW49B 2 -REFUELING WATER STORAGE TANK (FWSI X ,~J. ___________

1~.I. J~L Page" /5-TABLE 2 -U Line Included In Press. bndr.KC SYSTEM COMPONENTS I1 Size (In.) Seismic PRA Integity only Non-Sofety

--t-I -- F-f I-f AOV IKC-57A (82)12 MOV IKCIA (2B) 20 L MOV IKC3A (08D) 10 MOV IKC5QA (53D) 20 MOV IKC51A (54B) 4 x MOV IKC66A (818) 16 MOV 1KC230A (228B) 8 KC HX IA (18) X KC PUMPS WAI. IA2 (131, .12) X UNIT I KC SURGE TANK .....RHR PUMP MECH. SEAL HX IA (13)Line Included in Press. bidry. I NC SYSTEM COMPONENTS

._Size (In.) Seismic PRA on Non-Sfet PZR PORV INC32B 3 X PZR PORV INC34A 3 X PZR PORV INC36B 3 -x SAFETY RELIEF VLV INC 1 6 SAFETY REUEF VLV INC2 6Y REUEF VLV INC3 6 MOV INC31B .3 MOV 1NC33A 3 MOV INC35B 3 Une Included in Press. bndry.ND -SYSTEM COMPONENTS Size (!D.) Seismic PRA intearily only Non-Safety AOV IND29 (14) 8 " x.. f AOV IND34 8 X #MOV INDIB 14 #MOV 1ND2AC 14 X #MOV INDI9A (413) 14 MOV IND30A (15B) 8 MOV IND32 (17) 2 X MOV IND33 (18) 8 X MOV IND58A 8-~ .1 4-~ 4-4 I,# -reaulred to function durkmcolc shutdown I.L'-I 056 TABLE 2 -S Adi I Line I Included In I IPress. bnd,. I"-ND'SYSTEM COMPONENTS (cont.) Size (in.) I Seismic PRA integlily only I Nor-Safety-F WIqMOV IND68A (67B)2 I ND (1S) X __ND HX )A (IB) X _Line Included in Press. bndry.NI SYSTEM COMPONENTS

-Size (in.) Selsmic PRA Intearily only Non-Safety AOV 1NI I1 X AOV 1N156 I X AOV IN157 0.75 X AOV1N.S .0.75 X AOV IN61l I X AOV IN167 -x AOV IN168 0.75 X AOV IN169 0.75 X AOV IN172 I X AOV IN178 I x AOV IN179 0.75 X AOV NI o o 0.75 x ,AOV 1N190 1 X AOV 1N191 0.75 X AOV IN192 ..0.75 X AOV NII63 0.75 X AOV IN1174 (179) 0.75 X MOV IN19A (108) 4 #MOV IN154A 10 X #MOV IN165B 10 X #p MOV IN176A 10 1 1 MOV 1Ni88B 10 #MOV 1NI100 Ba I X MOV INI0O3A (135B) 6 X MOV NIN15B (14413) 1.5 X MOV INII18A (15013) 4 X MOV 1N1121A (1528) 4 1 X MOV IN1136B 6 MOV 1N0147A 2 X MOV IN1162A 4 1 X MOV 1NIN73A (1788) 8 MOV 1NI183B 12 X MOV INI185A (18413) 18 MOV 1N1332A 6 ARM" A'# .- required to function during Cold shutdown Poge-4. 1~7 057 TABLE 2 S I I _ _Une I Included In Press, bndry. L i NI SYSTEM COMPONENTS (cont.) ! Size (in,) Seismic PRA fntegrity only J Non-Sofety ,WMOV IN1334B 6 X i 1 INM1430A (NITROGEN BACKUP TO PZR PORVS) 0.75 x INT3RIB OMGrAENBACKUPTOPZRPORVS)f

_ 0.75 X NIPUMP JA (18) I I.,x, _, (not needed for Invento. control f01 V SBLOCA)COLD LEG ACCUMULATORS

-X (not needed for ' SB.OCA) ...._ _Une Included In Press. bndyy. -NS SYSTEM COMPONENTS Size On.)- Seismic PRA Integrity only -Non-Sofety MOV 1NS43A (38B) 8 _SPRAY NOZZLES DOWNSTREAM OF 1NS47 (42)Line Included In Press. bndry. -WV SYSTEM COMPONENTS Size Oin.) Seismic PRA integjrity only -Non-Safety AOV 1 NV238 3 X AOV INV241 3 X MOV 1NV94AC 4 MOV INV95B 4 MOV INVI41A 4 X MOV 1NV1428 4' X MOV INV150B 2 X MOV 1NVI5IA 2 X MOV 1NV221A 8 MOV 1NV222B 8 MOV 1NV244A 3 MOV INV2458 3 CENTRIFUGAL CHARGING PUMP IA Q1B) X SEAL WATER HX I X I SEAL WATER INJECTION FILTER )A (18) X SEAL WATER RETURN FILTER 1 X _VOLUME CONTROL TANK I X x _(not needed for inventory control for I' SBLOCA) I REGENERATIVE HEAT EXCHANGER I ,.x X x (not needed for inventory control for I SBLOCA) .__k I I i pI.F I I pages, (1' TABLE 2 -I I Line Included in Press. bndry. I I_ _RN YSTEM, COMPONENTS l, Size (In.) Seismic PRA integr ty In I Non-Safety I- 1-~ I-I-w AOV IRN21A (2581 6 4 AOV IRN22A (268) 6 _ _AOV 1RN68A (161B) 1.5 " ._AOV IRN89A (1908) 20 AOV IRN103A (204B) 3? --AOV IRN112A (213B) 2 AOV IRN114A (215B) 2 x -" AOV 1RNI17A (218B) 2 AOV IRNI26A (227B) 2 X AOV IRNI30A C231D) 2 AOV IRN140A (240B) 4 -x AOV IRNI66A (1708) 2 AOV )RN2528 6 X -AOV IRN277B 6 X AOV IRN442 (445) 4 X MOV IRNI 42 X MOV ORN2B 36.. X MOV ORN3A 36 -x MOV ORN4AC 36 X MOV RN5B -36 x b Y MOVL0RN7A (98) -36 MOV -.OP1AC 36 MOV ORNI I8 36 MOV ORN12AC 36 MOV 0RN13A 36 MOVORN14A (15B) 36 -X MOV IRN16A (OBB) 36 1 x MOV 1RN40A 10 X MOV IRN41B (43A) 10 MOV 1RN42A ..10 MOV IRN63B 10 X MOV 1RN64A 10 X MOV 1RN69A (1628) _ 8 MOV IRN70A (171B) 8 MOV 1RN73A 0174B) B X MOV IRNB6A (187B) 20 MOV IRN134A (235B) 18 X MOV IRN137A (2388) 18 X _MOV ORN147AC (283AC) 36 ,., MOV ORN148AC (284B) 36 MOV ORN149A (1528) 36 MOV ORNISOA (1518) 36 x MOV IRN253A 6 X MOV 1RN276A 6 X MOV 1RN279B 6 x SV RN296A (2978) A316- x _MOV IRN299A 6 x Poge,6. / q TABLE 2 -AM NEI J Line I Included In I Press. bndry. I I.Sicont)ze (In.)- fSelsmic.PRA Inteori![

only JNon-Safety I-i -W9MOV ORN3OJAC 24 x 4 MOV ORN302B 24 X RN PUMP IA (1B) X RNSTRAINERIA (0B)STANDBY NUCLEAR SERVICE WATER POND X-"Line Included In Press. bndtry.SA, SM. SV COMPONENTS

.Size (in.) Seismic PRA I Integrity only i Non-Safety AOV ISA49AB (48AB) 6 STEAM STOP VALVE TO TDP -ISA3 3 STEAM CONTROL VALVE TO TDP -1SA4 -3 MSIV ISMIAB 34 MSIV ISM3AB 34 MSIV ISMSAB 34 MSIV ISM7AB 34 " MSI BYPASS .V ISMWAB 3 MSIBYPASSVLV ISMIOAB 3 MSI BYPASS VLV ISMI IAB 3 MSI BYPASS VLV ISMI2AB 3 AOV ISM78 2' _ _,2, x __AOV ISMB3 2 AOV ISM84 2 X AOV ISM89 2 AOV ISM90 2 X AOV ISM95 2 AOV ISM96 2 X AOV ISMIO .2 SG lOV ISVIAB 6 X X SG PORV ISVAB 6 X X SGPORV ISV13AB 6 X X SG PORV ISVI9AB 6 X X SG SWV ISV2.1 1 X SG SRV ISV3 6 X" SG SRV ISV4 6 X SG SRV ISV5 6 X ISG SRV ISV6 6 X GSRV ISV8 L 61 ______L x_____rsc sRv ISV9 6 X-s 1J. I Z.\.9 6 Poge I a'o 060 " TABLE 2 -I I Line Included in " Press. bndcy. I I SA. SM. SV COMPONENI3 (cont.) I I Size (n.). Seismic PRA Ijinteglrlonly.I I Non-Satety; I 4-4 4 L-J 4.-I -SG SRV ISVIO 6 x q SGSRV 1SVI1 6_ ' X SG SRV 1SVM2 6 X SG SRV 1SV114 6 x SGSRV ISVIS .6 -x SG SRV 1SV16 6 X SGSRV ISV17 6 X SG SRV ISVI8 6 X SGSRV 1SV20 6 X SGSRV ISV21. 6 ._. X SG SRV 1SV22 6 X SGSRV ISV23 6 X SG SRV 1SV24 6 X MOV ISV25 6 _X MOV ISV26 6 X MOV ISV27 -6 , X _MOV ISV28 .6 X- i _Une Included In Press. bndry. -VA SYSTEM COMPONENTS

-f Size (in.) Seismic PRA _Integrity only/- Nco-Safety AIR-OP DAMPER 1-ABF-D-1

_ X AIR-OP DAMPER I-ABF-D-2 x AIR-OP DAMPER I-ABF-D-3

__' _ _x AIR-OP DAMPER I-ABF-D-4A (SA) _ _ _,, X AIR-OP DAMPER I-ABF-D-4B (513) _ X AUX. BLDG. FILTERED EXHAUST FAN ABFXF-1A (18) --X AUX. BLDG. RLTER UNIT ABFU-1 (2) X X RHR PUMP MOTORAHU RHR-AHU-1A (18) -_-Line Included In PRom -ndry.VC SYSTEM COMPONENTS

-# Size (in.) Seismic PRA integrity only Non-Sofety MOV lVCIA (9A) 18 MOV IVC2A (10A) 18 MOV JVC3B (JIB) 18 -MOV IVC4B (128) 18 AIR-OP DAMPER CR-OAD-, (5)AIR-OP DAMPER CR-OAD-3 (7) _ 'AIR-OP DAMPER CRA~OAD-3 II I- -I-J- __ I1.. I~L-only cursory review of these components reaured 1L LJ.Page 8. p-/

061 TABLE 2 -J I Une" Included In Press. bndry.VC SYSTEM COMPONENTS Wcont.) -_ _ Sze (in.)_ -Seismic PRA Intery on Non-Satety

  • wAIR-OP DAMPER CRA-OAD-4 MOTOR-OP DAMPER CR-D-1. (2) 1 1 MOTOR-OP DAMPER CR-D-4 (3)MOTOR-OP DAMPER CR-D-5 _ ___MOTOR-OP DAMPER CRA-D-i (3)MOTOR-OP DAMPER CRA-D-2 (4) _MOTOR-OP DAMPER CRA-D-5 (6) X MOTOR-OP DAMPER CRA-D-11 (7) x MOTOR-OP DAMPER CRA-D-12 (8) X MOTOR-OP DAMPER CRA-D-13 (9) I _X MOTOR-OP DAMPER CRA-D-14 (10) _ _X MOTOR-OP DAMPER CRA-D-16 (22)MOTOR-OP DAMPER CRA-D-17 (20) "_ _-MOTOR-OP DAMPER CRA-D-19 (18)MOTOR-OP DAMPER CRA-D-21 (15) " _MOTOR-OP DAMPER CRA-D-24 (30) i MOTOR-OP DAMPER CRA-D-26 (28)MOTOR-OP DAMPER CRA-D-27 (25) il MOTOR-OP DAMPER CRA-D-29 (23)MOTOR-OP DAMPER CRA-D-34 (33) __I MOTOR-OP DAMPER CRA-D-35 (36) ___ I___ __-LMOTOR-OP DAMPER CRA-D-35 (36)--MOTOR-OP DAMPER SGR-D-1 (2),OTOR-OP DAMPER SGR-D-3 (4) .... _MOTOR-OP DAMPER SGR-D-5 (6) _MOTOR-OP DAMPER SGR-D-7 (8) ___TRAIN A (B) CONTROL ROOM FILTER PACKAGE CRA-OAPFT-1 (2)TRAIN A (B) CONTROL ROOM FILTER PACKAGE FAN A-(B) I I TRAIN A (B) CONTROL ROOM AIR HANDUNG UNIT CR-AHU-1 (2)TRAIN A (B) CONTROL ROOM AREA AIR HANDUNG UNIT CRA-AHU-I (2)FAN UNiT BR-XF-l (2)I. I I sWIrCHGEAR ROOM AIR HANDLING UNIT SGR-AHU-IA c(1)SWITCHGEAR ROOM AIR HANDLING UNIT SGR-AHU-IC (ID)SWITCHGEAR ROOM AIR HANDLING UNIT SGR-AHU-2A (2B)SWITCHGEAR ROOM AIR HANDUNG UNIT SGR-AHU-2C (2D)_HEATER CRA-H-1 .x HEATER CRA-H-2
  • _ _ _x HEATER CRA-H-3 X HEATER CRA-H-4 .x HEATER CRA-H-5 _ _x HEATER CRA-I-I-6 (8) __X HEATER CRA-H-7 (9) X HEATER CRA-H-1 1 (10) X HEATER CRA-H-13 (12)I-x HEATER CRA-H-15 (14)X--~4-I---- 4-4 1-I -only Cursonr review of these components recuired Page\, ;?-?.

062 TABLE 2 -I I.I Une I Included In I Press.bbndry.

I I I VC SYSTEM COMPONENTS (cont.) -# ISize (in.) I Seismic PRA Integrity only Non-Safety HEATER CRA-H-19 (18)x HEATER CRA-H-20 (17) X HEATER CRA-H-21 (16) .X HEATER CRA-H-23 (27) X HEATER CRA-H-24 (28) X HEATER CRA-H-25 (29) X HEATER CRA-H-26 (30) X Line Included In Press bndn.YC SYSTEM COMPONENTS

--Size (in.) Seismic PRA inltearity only Non-Safety MOV iYC2A (83B) 1.25 MOV IYC39B (38A) 8 X 3-WAYVALVE IYC54 (113) 4 X 3-WAYVALVE IYC76 (135) 5 X , 3-WAYVALVE 1YC148 (204) 2.5 3-WAY VALVE IYC162 (218) -2.5 3-WAY VALVE IYC176 (232) 2.5 3-WAY VALVE lVC190 (246) 2.5 CONTROL ROOM AREA CHILLED WATER PUMP CRA-P-1 (2)CONTROL ROOM AREA CHILLER CRA-C- I (2Z COMPRESSION TANK CRA-T-1 (2)I 1~ ~ ~ ~ I -4 ~ 4-4/ -only cUrSory review of these components reauired Page Hr2X-3 063 TABLE 3 -MECHANICAL EQUIPMENT LIST FOR MCGUIRE UNIT 2 IPEEE WALKDOWN I I I I I-I I I CB' train components are shown in oarentheses.

A detailed woikdown of these components Is not necessary if the '8 train conflf wation is similar to the 'A' train.)4_lne_ Included In Press. bndry.CA SYSTEM COMPONENTS Size O.n.) Seismic PRA Integrity only Non-Safety AOV 2CA2DAB 6 AOV 2CA27A (32B) 4 AOV 2CA36AB 4 AOV 2CA48AB 4 AOV 2CA52AB 4 AOV 2CA56A (44B) 4 AOV 2CA60A (40B) 4 -AOV 2CA64AB 4 MOV 2CA7AC 8 MOV 2CA1 )A (9B) 8 MOV 2CAI5A (188) 6 MOV 2CA38B 4 MOV 2CA50B 4 MOV 2CA54AC .4 -.MOV 2CA58A (468) 4 MOV 2CA62A (42B) 4 MOV 2CA66AC 4 MOV 2CA86A (1168) 8 MOV 2CA161C 8 , TURBINE DRIVEN PUMP 2 (INCLUDING X CONDENSATE EDUCTOR)TURBINE DRIVEN PUMP LUBE OIL HX " MOTOR DRIVEN PUMP 2A C2B) _ _X _WZ SUMP PUMP A (B) FROM GROUNDWATER DRAINAGE SUMP B (B)DIESEL GENERATOR AND SUPPORTING

'Line I Included In Press. bndry.COMPONENTS Size (in.) Seismic PRA -integrity on, Non-Satety D/G 2A (2B) X FUEL OIL DAY TANK 2A (2B) "x FUEL OIL STORAGE TANK 2A (2B) _FUEL OIL BOOSTER PUMP 2A (2B) X FUEL OIL FUEL TRANSFER FILTERS 2A1.2A2 x (2B1. 212)FUEL OIL TRANSFER PUMP 2A (2B)--1-4 4-4 '1.-I 4-4-I 4-4 4-4. 5.-I I-I.a --J -.4 .4 -a a -I Pager p2.1-0641 TABLE 3 DIESEL GENERATOR AND SUPPORTING Line Included In Press. bndry. I COMPONENTS (cont.) Size (In.) Seismic PRA i t o -NOn-Sotety w AIR-OPERATED REGULATING VALVE 21(D9 4 I (2KD29)KD D.G COOLING WATER HX2A (2B)KD INTERCOOLER PUMP 2A (28)KD JACKET WATER PUMP 2A (2B)KD SURGE TANK 2A (23)D OG INTERCOOLER 2A (2B)MOV 2LD108 (113) 4 .x LUBE OlL*INTAKE STRAINER 2A M28) x LUBE OIL FILTER 2A (28) x LUBE OIL COOLER 2A (2B) X VD DIG BLDG. VENTRIATION FANS DSF-2A. 2C (2B,2D).SOLENOID VALVE 2VG61 (65) 2 ' -SOLENOID VALVE 2VG62 (66) -2 SOLENOID VALVE 2VG63 (67) 2 SOLENOID VALVE 2VG64 (68) 2 ......VG STARTING AIR TANKS 2A). 2A2 (2B]. 2B2) L___X VG INTAKE AIR AFTERCOOLERS AND DRYERS 2A1, 2A2 X (281.262)VG CONTROL AIR VOLUME TANK 2A (28)VG AIR COMPRESSORS 2AI. 2A2 (2B, 282) X VG UNE PURIFIERS 2A1,2A2 (2B1,282)VG CONTROL AIR FILTER 2A (28) .VN AIR INTAKE SILENCER 2A (28) X VN AIR EXHAUST SILENCER 2A (28) X WN D/G SUMP PUMPS 2A2, 2A3 (2B2.2B3)

X ZD VACUUM BLOWER PACKAGE 2A (2B) X Line i Included in Press. bndry, FW SYSTEM COMPONENTS Size (in.) SelsmIc PRA integrity only Non-Safety MOV 2FW1A 8 _MOV 2FW27A 14 MOV 2FW32B 8 MOV 2FW33A 2 MOV 2FW49B 2 REFUEUNG WATER STORAGE TANK (FWST) X w Page/ X5-TABLE 3 -I _IILine Included in Press. bndry.KC SYSTEM COMPONENTS I Size On.) Seismic PRA inteciy only Non-Safety I-I. Z--I.w AOV 2KC57A (82B)12_____________________________________

--~-4. ~-4 MOV 2KCIA (21) 20 MOV 2KC3A (189) 10 MOV 2KC50A (53B) 20 MOV 2KC51A (54B) 4 X MOV 2KC56A (818) 16 MOV 2KC230A (228B) 8 XC HX2A (2B) x KC PUMPS2AI.2A2 (21311.22Z X UNIT 2 KC SURGE TANK RHR PUMP MECH. SEAL HX 2A (28),= Line Included in Press. bndry.NC SYSTEM COMPONENTS Size (in.) Seismic PRA Integrity onfy Non-Safety PZR PORV 2NC32B 3 X PZR PORV 2NC34A 3 x PZR PORV 2NC36B 3 X'SAFETY REUEF VLV 2NCI 6 urn ____________________________________ I 4-4 SAFETY REUEF VIV 2NC2 6 SAFELY REUEF VLV 2NC3 6 MOV 2NC31B -3 MOV 2NC33A 3 MOV 2NC35B 3 Line Included in Press. bndry.ND SYSTEM COMPONENTS Size (In.) Seismic PRA Integrity only Non-Safety AOV 2ND29 (14) 8 X f .....AOV 2ND34 8 X #MOV 2ND1B 14 #MOV 2NDAC 14 X #MOV 2ND19A (4B) 14 MOV 2ND30A (15B) ... 8 MOV 2ND32 (17) 2 1 X MOV 2ND33 (18) 8 1 -X MOV 2ND58A 8 -___ I I&I- IQOUWOd to Ifunctiof inG dwcold sfltdw 1.-I Page 7-G~

001 TABLE 3 -0 Anb II Line II Included In I Press. bndry. I ND SYSTEM COMPONENTS (cont.) Size (in.) I Seismic PRA I Lotegrt onI- Non-Safety MOV 2ND68A (671)2 ND PUMP 2A (20) .X #ND HX 2A (2B) X _U Line Included In Press. bndry.NI SYSTEM COMPONENTS Size (in.) Seismic PRA interty on-y 1 No-Sofety AOV 2N150 I X AOV 2NI56 1 X AOV 2N157 0.75 X AOV 2N158 0.75 X AOV 2NI61 I 1 X AOV 2N167 1 X AOV 2N168 0.75 X AO 2N169. 075 X AOV 2N172 I x AOV 2N178 I X AOV 2N179- 0.75 1 X AOV 2NI80 0.75 X AOV 2NI84 I x AOV 2NI90 I X AOV 2NI91 0.75 X AOV 2NI92 0.75 X AOV 2NI163 0.75 X AOV 2N1174 (179) 0.75 X MOV 2N19A (101) 4 #MOV 2NI54A 10 X #MOV 2NI65B 10 X #MOV 2N176A 10 #MOV 2NI88B 10 -MOV 2NI100B 8 X MOV 2NI1O3A (135B) -6 X MOV 2NI115B (1448) is. X MOV 2NI118A (150B) 4 X MOV 2NI121A (152B) 4_ X MOV 2NI136B 6 -MOV 2NI147A 2 X MOV 2NI62A 4 X MOV 2NM173A (178B) 8 MOV 2NI183B 1 12 -X MOV 2NI185A (184B) 1 18 MOV 2NI332A 6 4-4 4-1 4-4 MOV 2N1333B 6~ -i-.~ I-I io -reouired to funfctkf durifla cold shLiudown 11 1L P0g9/

TABLE 3 -I IUne I Included in Rem bndry. I I NI SYSTEM COMPONENTS (cont.) I I Size (in.) I SeWsmic PRA Integrity only I I-Non-Safety

',MOV 2NI334B 6 X 2NI430A (NITROGEN BACKUP TO PZA PORVa) 0.75 X 2NI431B (NITROGEN BACKUP TO PZR PORVs) 0.75 X NI PUMP 2A C2B) 1 X (not needed for Inventory control for I' SBLOCA)COLD LEG ACCUMULATORS X (not needed for " SBLOCA)aLie Included In Press. bndry.NS SYSTEM COMPONENTS Size (Vn.) Seismic PRA Integrity only Non-Safety MOV 2NS43A (38B) 8, SPRAY NOZZLES DOWNSTREAM OF 2NS47 (42)...ne .. Included In I Press. bndry.B-NV SYSTEM COMPONNF"S 517A ~

PlQA Iflt=flrltv nnlv Nnn-Snffntv Siz an. Se.d PR Inaryol AOV 2NV238 3 x AOV 2NV241 3 X MOV 2NV94AC 4 MOV 2NV95B 4 _MOV 2NVI41A 4 X MOV 2NV142B 4 X MOV 2NVISOB 2 X MOV 2NV151A .2 x MOV 2NV221A 8 MOV 2NV2228 8 " MOV 2NV244A 3 MOV 2NV245B 3 CENTRIFUGAL CHARGING PUMP2A (2B) " X " -SEAL WATER HX 2 x SEAL WATER INJECTION FILTER 2A (28) X _SEAL WATER RETURN RLTER 2 x VOLUME CONTROL TANK 2 x x (not needed for Inventory control for I' SBLOCA) -REGENERATIVE HEAT EXCHANGER

_I E- x x (not needed for Inventory control for I' SBLOCA] -r----II-i -- -- 4_1 1- 4-1 I I.1 1.1 L....J L..L Page/ aw 003 TABLE 3 -0 Ine I[ IIncluded in j.Press. bndry.RN SYSTEM COMPONENTS Size (In.)j SeIsmic PRA Integrity onyj Non-Safety 14AOV 2RN21A (25B 4 AOV 2RN22A (268) 6 AOV 2RN68A (1610) 1.5 AOV 2RN89A (190B) 20 AOV 2RNI03A (2048) 3 ?AOV 2RNI12A (2135) 2 AOV 2RNI14A (2158) 2 X AOV 2RN117A (218B) .2 AOV 2RN126A (227B) 2 X AOV 2RN130A (231B) 2-AOV 2RN140A (2408) 4 X AOV 2RN166A (170B) 2 1 AOV 2RN252B 6 X AOV 2RN277B 6 X MOV 2RNI 42 x MOV 2RN16A (18B) 36 .X MOV 2RN40A 10 X MOV 2RN4IB (43A) 10 MOV 2RN42A ..10 -MOV 2RN63B ,,10 X MOV 2RN64A 10 X MOV 2RN69A (162B) 8 .......MOV 2RN7OA (1718) 8 MOV 2RN73A (174B) a 8X MOV 2RN86A (187B) .20 MOV 2RN)34A (235B) 18 X MOV 2RN137A (238B) 18 X MOV 2RN253A 6 X MOV 2RN276A 6 X MOV 2RN279B 6 x MOV 2RN296A (2978) 36 X MOV 2RN299A 6 X RN PUMP 2A (2B) x RN STRAINER 2A (2B) ,,__,, STANDBY NUCLEAR SERVICE WATER POND X Une Included In Press. bndry.SA, SM. SV COMPONENTS Size (in.) Seismic PRA Infeglity only No-SafetV AOV 2WA49AB (48AB) 6 STEAM STOP VALVE TOTDP -2SA3 3 3 L~FAM CC~N1PflL VAI VF Tfl TflP. 9~AA 2 rr -.m VALVE TO MP- -.. ________ ____MSIV 2SMIAB a34 Pagej 2-TABLE 3 -IL i Une Included in IPress. bndf, I SA, SM. SV COMPONENTS (cont.) I Size (In.) Seismic PRA Intety ony I I Non-Sofety WMS1V 2SM3AB 34_IVV 2SM5A_ 34 MSIV 2SM7AB 34 MSI BYPASS VLV 2SM9AB 3 MSI BYPASS VLV 2SM IOAB 3 MSI BYPASS VLV 2SM I IAB 3 ____ ___MSI BYPASS VLV 2SMI2AB 3 AOV 2SM78 2 X AOV 2SM83 2 AOV 2SM84 2 X AOV 2SM89_ 2 AOV 2SM90 2 X -AOV 2SM95 2 Aov 2SM96 2 x AOV 2SMI01 2 SG PORV 2SV7AB 6 X X SGPORV 2SV7,ABC 6 X X SG PORVI2SV13AB 6 x x SGPORV 2SV19AB 6 -X X SGSRV 2SV2 6 X_" SG SRV 2SV3 6 X SG SRV 2SV4 6 X SG SRV 2SV5 6 X SGSRV 2SV6 6 X SG SRV 2SV8 6 X SG SRV 2SV9 6 X SG SRV 2SVI0 6 X SG SRV 2SVII1 6 X SG SRV 2SV 12 6 X SG SRV 2SV14 6 x SG SRV 2SWS. , 6 X SG SRV 2SV 1 6 X SG SRV 2SV17 6 X SGSWV 2SVI8 6 X SG SRV 2SV20 6 X SG SRV 2SV21 6 X.S.G.SRV 2SV22 6 ...x SG SRV 2SV23 6 X SG.S.RV 2SV24 6 X MOV 2SV25 6x MOV 2SV26 6 X IMOV 2SV27 t&X 6- x- ____ --MCJV 2SV28 6 X_________________6___

-x L.ZJ Page 1 3 6 0L4 TABLE 4 -LELECTRICAL EQUIPMENT LIST FOR MCGUIRE UNIT 1 IPEEE WALKDOWN_Included In AREA TERMINATION CABINETS -' Seismic PRA Non-Sofet_included in AUXILIARY SHUTDOWN PANEL ____Seismic PRA Non-Sot ety___Included in _SUPPORT FOR CA SYSTEM _ Seismic PRA Non-Safety 4160V AC SWITCHGEAR

]ETA (IETB) -X 600V AC MCC IEMXA (IEMXB) (IEMXB-2)

I X 600V AC MCC IEMXA-4 X 600V AC MCC 1EMXA-5 _ X 125V DC DISTRIBUTION CENTER IEVDA (ILEVDB) X 125V DC PANELBOARD IEVDA (IEVDB) IX I*120V AC PANELBOARD 1EVKA (1EVKB) & MANUAL TRANSFER SWITCH X LOCAL MOTOR-DRIVEN PUMP CONTROL PANEL X LOCAL TURBINE-DRIVEN PUMP CONTROL PANEL X ESFAS TRAIN A (B) 48V DC POWER SUPPLIES -'BATTR'Y EVCA (EVC:.B) I!BATTERY CHARGE:R EVCA (EVCB)II DC CIRCUIT BREAKER FOR MDP1A (MDPIB) AUTOSTART

"=INVERTER IEVIA (lEVIB) _ _ -TD PUMP RELAY HF I _I_-MFW PUMP RELAY BBA)W (BB[(B) )_I I MFW PUMP RELAY .R/IT FPTCA) (R/Tf(FPTCB))

__....MFW PUMP RELAY RWITT. (FPTCA) (R/T-I [FPTCB))RELAY R25C(A) (R25C(B))RELAY K609A (K6098)RELAY LRA6 (LRB6)LOAD SHED RELAY LSAI (LSB1)TEST RELAY TSA2 C(SB2)ESFAS SLAVE RELAY K633A (K633B)ESFAS SLAVE RELAY K634A (K634B)ESFAS MASTER RELAY K516A (K516B)ESFAS INPUT RELAY K113A (K113B)ESFAS INPUT RELAY K114A (K(148)ESFAS INPUT RELAY K121A (KI21B)ESFAS INPUT RELAY K150A 0(150B)ESFAS INPUT RELAY X23)A (K230B), ESFAS INPUT RELAY K231A (K231B) _WE ESFAS INPUT RELAY K25DA (K25MB)W5AS INPUT RELAY X255A (K(2558) -I I Ifi 1____ 1-1 1-__ _ t PageI 3/

006 TABLE 4 -" Included In SUPPORT FOR CA SYSTEM (cont.) -Selsmic PRA Non-Safet, t-.t 1--.~MW)ESFAS INPUT RELAY K331A (K331B)ESFAS INPUT RELAY K332A (1<3328) !ESFAS INPUT RELAY K333A (K3338) _ESFAS INPUT RELAY K334A (K334B)ESFAS INPUT RELAY K407A (K407B)ESFAS INPUT RELAY K408A (K408B)ESFAS INPUT RELAY K409A (K409B)ESEAS INPUT RELAY K410A (K410B)ESFAS LOGIC MODULEA317A (A317B)D/G LOAD SEQUENCER (LOAD ACTUATE) RELAY 2JA(RAB8 (2JA(R8S))

D/G LOAD SEQUENCER RELAY A3 (83) 1 1 I SG A LO-LO WATER LEVEL CHANNEL 1 BISTABLE ..SG A LO-LO WATER LEVEL CHANNEL I LEVEL TRANSMITTER SG A LO-LO WATER LEVEL CHANNEL 2 BISTABLE -_ _ I SG A LO-LO WATER LEVEL CHANNEL 2 LEVEL TRANSMITTER SG A LO-LO WATER LEVEL CHANNEL 3 BISTABLE I I SG A LO-LO WATER LEVEL CHANNEL 3 LEVEL TRANSMITTER SG A LO-LO WATER LEVEL CHANNEL 4 BISTABLE I 'I SG A LO-LO WATER LEVEL CHANNEL 4 LEVEL TRANSMITTER SG B LO-LO WATER LEVEL CHANNEL 1 BISTABLE I SG B LO-LO WATER LEVEL CHANNEL 1 LEVEL TRANSMITTER_

SG B LO-LO WATER LEVEL CHANNEL 2 BISTABLE I_ _SG B LO-LO WATER LEVEL CHANNEL 2 LEVEL TRANSMITTERI.

iýSG B LOWL WATER LEVEL CHANNEL 3 BISTABLE _______SG B LO-LO WATER LEVEL CHANNEL 3 LEVEL TRANSMITTER R '_ " _SG B LO-LO WATER LEVEL CHANNEL 4 BISTABLE _ __i SG B LO-LO WATER LEVEL CHANNEL 4 LEVEL TRANSMITTER_

SG C LO-LO WATER LEVEL CHANNEL I BISTABLE I I SG C LO-LO WATER LEVEL CHANNEL I LEVEL TRANSMrTTER SG C LO-LO WATER LEVEL CHANNEL 2 BISTABLE I I _ _--SG C LO-LO WATER LEVEL CHANNEL 2 LEVEL TRANSMITTER

_SG C LO-LO WATER LEVEL CHANNEL 3 BISTABLE I' I__SG C LO-LO WATER LEVEL CHANNEL 3 LEVEL TRANSMITTER SG C 1O-LO WATER LEVEL CHANNEL 4 BISTABLE I I SG C LO-LO WATER LEVEL CHANNEL 4 LEVEL TRANSMITTER

_SG D LO-LO WATER LEVEL CHANNEL I BISTABLE I I_SG D LO-LO WATER LEVEL CHANNEL I LEVEL TRANSMITTER SG D LO-LO WATER LEVEL CHANNEL 2 BISTABLE I I SG D LO-LO WATER LEVEL CHANNEL 2 LEVEL TRANSMITTER SG D LO-LO WATER LEVEL CHANNEL 3 BISTABLE I I_"_SG D LO-LO WATER LEVEL CHANNEL 3 LEVEL TRANSMITTER SG D LO-LO WATER LEVEL CHANNEL 4 BISTABLE I I SG D LO-LO WATER LEVEL CHANNEL 4 LEVEL TRANSMITTER INSTR. LOOP CONTAINING ICASV/MV0200, SV0201. & SV0202 INSTR. LOOP CONTAINING CASV/MV270 (0320) & SVO27) (0321)INSTR. LOOP ICALL/P ./SVML05_2 (0480) 11 -1 1 -I INSIR. LOOP CONTAINJNG ICALL/P/SV/ML056O (0440)I I INSTPL LOOP CONTAINING ICALL/P /SVML0600 (0400)I I Page A 3 1')-

007 TABLE 4 -0 I I ...._I I _I IIncluded In I _I SUPPORT FOR CA SYSTEM (cont.) IH 1i I Seismic PRA Non-Salety I I I I w INSTR. LOOP CONTAINING ICALLIP ISVIML0640 (0360) I I.I INSTR. LOOP CONTAINING ICAFEtPS/Fr/P 5000 (5010), PS5001 (501 1). & P55002 (5012)INSTR. LOOP CONTAINING ICAPS/PT/P 020 (5030) II INSTR. LOOP CONTAINING ICAFE/PS/FT/P 5040. PS504,. & PS5044 .INSTR. LOOP CONTAINING ICAPSIPT/PG/P W5050 ] W INSTR. LOOP CONTAINING ICAPS/PT/P 5070 (5080)_INSTR. LOOP CONTAINING ICAFE/Fr/P 500 (5110) & FT5091 (5111)INSTR. LOOP CONTAINING ICAFEII'/P 5100 C5120) & FT5101 (5121) i INSTR. LOOP CONTAINING ICAPSMPT/P 5160 INSTR. LOOP CONTAINING ICFT/P,5490

--INSTR. LOOP CONTAINING ICFLT/P 5500 INSTR. LOOP CONTAINING ICFLT/P 5510 ,, i , -INSTR. LOOP CONTAINING ICFLTIP 5520 INSTR. LOOP CONTAINING 1CFLT/P 5530 .... J INSTR. LOOP CONTAINING ICFLT/P5540

_ _INSTR. LOOP CONTAINING ICFLT/P 55,50 SSW INSTR. LOOP CONTAINING ICFLT/P 5560 5 INSTR. LOOP CONTAINING ICFLT/P 5570 I INSTR. LOOP CONTAINING ICFLT P 5580 -INSMR. LOOP CONTAINING ICFLT/P 5590 _INSTR. LOOP CONTAINING ICFLT/P 5600-]-INSTR. LOOP CONTAINING ICFLT/P 6000 M I INSrR. LOOP CONTAINING ICFLTIP6010

_ !INSIR. LOOP CONTAINING ICFLT/P6020 6 M INSTR. LOOP CONTAINING ICFLT/P 6030 -_ -Included In SUPPORT FOR DIESEL GENERATORS

_ Seismic PRA Non-Safet 4160V AC SWITCHGEAR 1ETA (IEIB- f _ _ X 600V AC LOAD CENTER lELXA (IELXB) -X 600V AC LOAD CENTER IELXC (QELXD) -X 600V AC LOAD CENTER IELXE (IELXF) -X 600V AC MCC IEMXA (IEMXB) X 600V AC MCC IEMXE x 120V AC PANELBOARD IDGIA (IDGIB) X 125V DC PANELBOARD IEVDA (JEVDD) x 125V DC BATTERY/RACK X INVERTER X I D/G CONTROL PANELS X BATTERY IEDGA (IEDGB) AND CHARGERS -x BATTERY IEDGA (I EDGB) INPUT & OUTPUT BREAKERS _600/ 120V AC TRANSFORMER TO PANELBOARD IDGIA ()DG1B) I_ BREAKERDGIA-2 (DGIB-2) I I I I ARESET RELAY ED(TRA3) (ED(rRB3))

If_______________

.1-I rBLACKOUT RELAY DC(BOA) (DC(B08))I I pagey 3 0G8 TABLE 4 -I I I I Included In I]SUPPORT FOR DIESEL GENERATORS (Cont.) 4 Seismic PRA Non-Sofety DEETTS=EA BDS)(BDS))

___ ____ ____f-I BWLACKOUT LOGIC RELAY EDAILRA2I (DA!lRE2I)

DEFEAT TEST RELAY FB(DTSA] (FB(DTSB))

!.DIG START RELAY 2TRA(A) (OTRA(B))

___D/G START RELAY 2TRAI(A) (2TRAI(B))

_DIG START RELAY 2TRB(A) (2TRB(B))

_ _ _D/G START RELAY 2TRC(A) (2TRC(B))___

DIESEL STARTING AIR RELAY RVGI(A) (RVGI(B))DIESEL STARTING AIR RELAY RVG2(A) (RVG2(B))DIESEL STARTING AIR RELAY RVG3(A) (RVG3(B))DIG AUTOSTART RELAY DASR(A] (DASR(B))

l -.LOAD SHED RELAY AB(LSAI) (AB(LSB1))

I)LOAD SHED RELAY AAMLSA2) (AA(LSSB2)

J _LOAD SHED TIMER RELAY GC(LSAT) (GCC.SBT))

LOGIC TIMER RELAY FD(LTMA) (FD(LTIB))

.-LOGIC TIMER RELAY FD(.T2A) (FD(LT2B))

RELAY AC(127ZBX)

RELAY AE(127XBX)

RELAY 3CR(A) (3CR(B))RELAY ART(A) (ART(]))RELAY DGIFRA (DGIFRB)RELAY ESX(A) (ESX(B))RELAY 2TRA(A) (2TRA(B)RELAY FCORA1I (FCLTRBII)

RELAY FC(TRAI) (FC(Ml))RELAY HRAAA) (HRBIB8))1 1-4-RELAY RTD(A) (RTD(B))RELAY SIAIXEA Y (SAAIX(B))

4-RELAY SIA2XGA) (SDA2X(B))

RELAY SIA4X(A] (SIA4X(l))

RELAY TSA3 (SB3)RESET RELAY EB[RRA] (EB[RRB])RESTART RELAY FA[RGA) (FA[RGB])UNDERVOLTAGE RELAY 4CA[A] (:CA(B))UNDERVOLTAGE RELAY 4DA(A) M4AOB)UNDERVOLTAGE RELAY AC(127ZAX) (AC(127ZBX))

_..UNDERVOLTAGE RELAY AD(127YAX) (AD(127YBX))

UNDERVOLTAGE RELAY AE(127XAX) (AE(127XBX))

RESET SWITCH 4CC(A) (4CC(B]) ._., -,_.RESET-SWITCH EG135 SPEED SWITCH SIM (SIBI) ._.SPEED SWITCH S1A2 (SIB2)INSMR. LOOP CONTAINING IFDLS5040

& LS5041 (5050 & 5051)INSTR. LOOP CONTAINING ILDPG/PS5120

& PS5121/5122/5123 (5130 & 5131/5132/5133)

INSTR. LOOP CONTAINING )LDPT/PG536 (5370)1 , ,1___INSTR. LOOP CONTAINING I VGPG/PS5040

& PG/PS5050 (5060 & 5070)INSTR. LOOP CONTAINING I VGPG/PS5080 (5090) 1 I1*-INSTR. LOOP CONTAINING 1VGPG/PSSI20

& PG/PS5i22 (5140&5142) 1 1 NSTR. LOOP CONTAINING IVGPGIPS5130

& PG/PS5132 (5150 & 5152)I I-t-i..I I I I£~J. ___________

1~,J.Pogea 34 TABLE 4 -S O Oi Sncluded AIn SUPPORT FOR FW' SYSTEM I tSeismic-PRA1 l Non-Safel-4-4 -I 4-4 w INSIR. LOOP CONTAINING I FWLT/P 5000 M- -..- M- M___ ___INSTR. LOOP CONTAINING IFWLT/PSOIO I INSTR. LOOP CONTAINING IFWLT/P 5020 !Included In SUPPORT FOR KC SYSTEM -Seismic PRA I Non-Sofel 4160V AC SWITCHGEAR IETA (IETB) I .__X 600V AC MCC IEMXA (IEMXB) X 125V DC PANELBOARD 1EVDA (IEVDD) -x D/G ACCELRATED SEQUENCE RELAY 2DB[AA2) (2DB[AB2])

D/G AUTO RESET AUXIUARY RELAY CC(TRA3X) (CC(TRB3)I)

DIG LOAD ACTUATE RELAY 2HA(RA6) (2HA(RB6))

_DIG LOAD SEQUENCER RELAY LSA2 (LSB2) _____, DIG LOAD SEQUENCER RELAY RA6 (RB6) I DIG LOADING TRANSIENr ADVANCE TIMER RELAY 2AD(ATAI)

(2AD(ATBI))

DIG LOADING TRANSIENT ADVANCE TIMER RELAY 2BD(ATA2)

(2BD(ATB2))

D/G LOADING TRANSIENT ADVANCE TIMER RELAY 2CD(ATA3)

(2CD(ATB3))

-_DIG LOADING TRANSIENT ADVANCE TIMER RELAY 2DD(ATA4)

(2DD(ATB4))

D/G SEQUENCE TIMER RELAY GA(ST4A) (GA(ST4B))

D/G SEQUENCE TIMER RELAY GB(ST2A) (GB(ST2B))

vl D/G SEQUENCE TIMER RELAY HB(ST6A) (HB(ST6B))

DIG SEQUENCE TIMER RELAY HC(STSA] (HC(ST58))

_DIG TEST RELAY 2FB(FSA4)

('2FB[TSB4))I ESFAS SLAVE RELAY K610A CK610B)' I TEST RELAY TSAI (TSBI)-I INSTR. LOOP CONTAINING IKCPT/P 5490 (6500) S .-INSTR. LOOP CONTAINING IKCFE/FT/P 5530 (5540)I INSTR. LOOP CONTAINING IKCFE/FT/FS/SV/P 5670 (5680) 1"- -Included In MAIN CONTROL BOARDS --Seismic PRA Non-Safety

_____ _____ _____ ____ _____ ______________

Included In _ _ _ _SUPPORT FOR NC SYSTEM _______ Seismic PRA No 4160V AC SWITCHGEAR IETA (IETB) x_' _ _X 600V AC LOAD CENTER )ELXA (1ELXB) _ _X -6WV AC LOAD CENTR lLXC (ELXD) .__ __ X I fTIV AC~ M~ ~FMXC (1PM)Cfl'~

V A"110" AC MC I- EIVIX QEI--k v __125V DC PANELBOARD lEVDA (OEVDD)x h-s Page $:..5" TABLE 4 -0 An S T FR NI SM I) I Included In I -SUPPORT FOR NC SYTMN (cont.) I~~ I j Seismic PRA I ANori-Satety~

I IW ACCELERATED SEQUENCE RELAY 2CB(AAI) (2CB(ABI))

e ESFAS SLAVE RELAY K6aA (K608B)ESG AUXIUARY RELAY BD(ESGAXI) (BD(ESGBXI))

LOAD SHED RELAY AB{LSAI] (AB[LSBI])

I I-_." MAXIMUM SEQUENCE TIMER RELAY BEILT3A) (BEILT3B))

RELAY 2ABSLRA4)

(2AB(LRB4))

RELAY TDC(BOA) (DCBOB))RELAY DA(LRA2) (DA[LRB2))

RELAY FCOTRAI) (FCNING I SEQUENCER LOAD RELAY 2CA1RA C ) (2CA(RBI)SEQUENCER LOAD RELAY 2DA[RA2) (S2DASRB2))

SEQUENCER TIMER RELAY JASTRIA] (EV )X _IB))IGT LUA ACT1 RELAY 2F AIRAA) A- B(TSB4))RELAY 2GB(TSA5)

(.2GBETSB5, )UNDERVOLTAGE RELAY CB{127AX)R (CB(127B0)(INSTR. LOOP CONTAINING INNCSVO320

& SVD321 INSTR. LOOP CONTAINING INCSV0340

& SVO341 INSTR. LOOP CONTAINING INCSVT360

& SV-3 I Included In SUPPORT FOR NI SYSTEM Seismic PRA o-4160V AC SWMTCHGEAR IETA (IETB) X 600V AC MCC IEMXA (IEMXB-I)

X 125V DC DISTRIBUTON CENTER I EVDA Q1EVDD) X -DIG LOAD ACiUATE RELAY 2FAIRA4) (2FA(RB4)).

-RELAY DGTSA6 (DGTSB6)IRELAY LSAI (LSBI) -IINSTR, LOOP CONTAINING 1NDRD/P50030 (5120) & INDRD/P/CR56 (5070)I INSTR. LOOP CONTAINING 1NDFE/FS5040 (5050)INSTR. LOOP CONTAINING 1NDPT/PS09 (5080)INSTR. LOOP CONTAINING 1NDFE/FT5250 (5260)Included In , SUPPORT FOR NI SYSTEM Seismic PRA No-fe 4160V AC SWITCHGEAR

]ETA (IETB) X 600V AC MCC I EMXA X 600V AC MCC IEMXA-I X 600V AC MCC IEMXB-1 X 125V DC PANELBOARD 1EVDA (ED X_D/G LOAD ACTUATE RELAY 2EA(RA3) (2EA[RB3])LOAD SEQUENCER RELAY RA3 (RB3} I l" Am-I LOA SEUECE REA ii()II OICG RELAY ISAI (LSBI)II---- -Li i~L Pagex 3(o 011 TABLE 4 -0 Am S F I S I I Included in I SUPPORT FOR N1 SYSTEM (cont.) I I Seismic PRA I _INot-Sofet 4--I 4--I w DIG TEST RELAY DGTSA6 (DGTSB6)LIMIT SWITCH TO MOV INfl47A _ _LIMIT SWITCH TO MOV 1NI1M5A (ON1184B)

_INSTR. LOOP CONTAINING INILT/P 5260 D INSTR. LOOP CONTAINING INILT/P 5270 -_Included in SUPPORT FOR NV SYSTEM -Seismic PRA No 4160V AC SWITCHGEAR

]ETA (1ETB) X 600V AC MCC IEMXA X 600V AC MCC )EMXB-l x 600V AC MCC lEMXB-2 I -X 125V DC PANELBOARD IEVDA (IEVDD) _ X D/G AUTO RESET RELAY ED(TRA3) (ED(TRB3))

DIG LOAD ACTUATE RELAY 2DA(RA2) (2DA(RB2))

DIG TEST RELAY TSA2 WSAB) I I ....CONTAINMENT HIGH PRESS. CHANNEL 2 BISTABLE (ESFAS)CONTAINMENT HIGH PRESS. CHANNEL 2 TRANSMITTER (ESFAS)CONTAINMENT HIGH PRESS. CHANNEL 3 BISTABLE IESFAS) -CONTAINMENT HIGH PRESS. CHANNEL 3 TRANSMITTER (ESFAS)CONTAINMENT HIGH PRESS. CHANNEL 4 BISTABLE (ESFAS) ]-CONTAINMENT HIGH PRESS. CHANNEL 4 TRANSMITTER (ESFAS)ESFAS INPUT RELAY K131A (KI31B)ESFAS INPUT RELAY K133A (K133B)ESFAS INPUT RELAY K201A (K201B)ESFAS INPUT RELAY K217A (K271B)ESFAS INPUT RELAY K247A (K247B)ESFAS INPUT RELAY K330A (K330B)ESFAS INPUT RELAY K344A (K344B)ESFAS INPUT RELAY K417A (K4178)ESFAS INPUT WEAY K430A .(K430B)ESFAS INPUT RELAY K444A (K44,4D)ESFAS LOGIC MODULE A213A (A210B)ESFAS LOGIC MODULE A213A (A213B)WFAS LOGIC MODULE A30]8A (A308B) *ESFAS LOGI4C MODULE A313A (A313B)ESFAS LOGIC MODULE A411A (A411I1B)ESFAS LOGIC MODULE A416A (A4168) -, ESFAS MASTER RELAY K501A (K501B) -ESFAS SLAVE RELAY K603A (K6038) _ESFAS SLAVE RELAY K607A (K6078)LOW STEAMUNE PRESSURE CHANNEL 1 BISTABLE (ESFAS) _LOW STEAMLINE PRESSURE CHANNEL I TRANSMITTER (ESFAS) _STEAMLINE PRESSURE CHANNEL 2 BISTABLE (ESFASI I M IO -TAMN PRSSR CHANNELZ 2 BITAL (E-IS I-LOW STEAMLINE PRESSURE CHANNEL 2 TRANSMITTER (ESFAS)Pcigek ~7 TABLE 4 -I I I I Included in I I SUPPORT FOR NV SYSTEM (cont.) I I J SeIsrnic PRA .I Non-Safe I I I~1* ___________

LOW STEAMLINE PRESSURE CHANNEL 4 BISTABLE (ESFASI I'-4. 4.-*LOW STEAMUNE PRESSURE CHANNEL 4 1RANSMITTER (ESFAS)I PRESSURIZER LOW PRESSURE CHANNEL I BWABLE (ESFAS) I "I _PRESSURIZER LOW PRESSURE CHANNEL ) TRANSMIITER (ESFAS)PRESSURIZER LOW PRESSURE CHANNEL 2 BISTABLE (ESFAS) I I PRESSURIZER LOW PRESSURE CHANNEL 2 TRANSMITTER (ESFAS)PRESSURIZER LOW PRESSURE CHANNEL 3 BISTABLE (ESFAS] I I I PRESSURIZER LOW PRESSURE CHANNEL 3 TRANSMITTER (ESFAS)INSTR. LOOP CONTAINING INVFEFT//P 562D & 1NVFT/P 5621 i INSTR. LOOP CONTAINING INVFE/Fr/SS/P 5630 & INVFT/P 5631 -____ "-Included in _I PROCESS CONTROL CABINETS -" Seismic PRA -Non-Sofe SUPR:O Included In SUPPORT FOR RN SYSTEM '_-_ Seismic PRA Non-Safet 4160V AC SWITCHGEAR IETA (IETB) X 600V AC MCC IEMXA _ ___X 600V AC MCC 1EMXB-2 ____-._X 600V AC MCC 1EMXE X 600V AC MCC 1EMXH X 600V AC MCC 1EMXH-1 X 600V AC MCC 2EMXH X 125V DC DISTRIBUTION CENTER 1EVDA (IEVDD) X X D/G LOAD SEQUENCER RELAY 21A(RA7J (21A(RB7])

._D/G LOAD SEQUENCER RELAY LSAI (LSB1) _____D/G LOADING TRANSIENT ADVANCE TIMER RELAY 2ED(ATA5)

(2EDfATB5))

_D/G SEQUENCE TIMER RELAY HA(ST7A) (HA(ST7B))

_____D/G TEST RELAY 2FB(TSA4)

(2FB(SB4))

... L__INSTR. LOOP CONTAINING 1 RNPG/PS 0 & SVO2 10. 0211.0220.

0221 !(5010 & 0250.0251.0260.0261)

_I_ __I INSTR. LOOP CONTAINING I RNPT/PS/P 5020 (5030)INSTR. LOOP CONTAINING' )RNFE/FT/P 5040 & T5041 (5050 & 5051) I INSTR. LOOP CONTAINING I RNFE/FT/P 5220 (5230) 1 1 _INSTR. LOOP CONTAINING 1 RNFE/FT/P 5360 & P/P 5361 (5370 & 5371) _REACTOR PROTECTION SYSTEM -Non-Safetv REACTOR TRIP BREAKER A (B) -_ ___-____.U=AfrMD TiID WPM qlDA WrDAlelD A Mi I................1 I. I LIII Poge 3?

013 TABLE 4 -ISUI Included In FOI IY SUPPORT FOR SM. SV SYSTEMS _:___I_ I_ I Seismic PRA I Non-Sote II II--~w&JOV AC MCC IFMXA-2 I I II'C 4 600V AC MCC IEMXB-4 __ _ _x -_ _INSTR. LOOPCONTAINING ISMSVOOl1(001 I). (0013)& LLOO10,0011

_INSTR. LOOPCONTAINNG ISMSVO30 (0031). (0033) & LL0030,0031 INSTR. LOOP CONTAINING ISMSV0O50 (005)0W3)

& w,) .005)INSTR. LOOP CONTAINING 1MSVO070 (0071)1(0073)

& LL0070, 0071 _..INSTR. LOOP CONTAINING ISMSV/LL/MLOO90 (SV/0101)INSTR. LOOP CONTAINING ISMSV/SL./MLO]10 (SVO1O1)INSTR. LOOP CONTAINING ISMSILL/Mt.0120 (SV0121) -INSTR. LOOP CONTAINING 1SMFE/Fr/P 5000. RCPS. FWCS .(FE/Fr/P 5010, RCPS, FWCS)INSTR. LOOP CONTAINING 1SMFE/FT/P

50. RCPS, FWCS (FE/FT/P 500, RCPS, FWCS)INSTR. LOOP CONTAINING 1SMFE/FT/P 5040. RCPS. FWCS (FE/FT/P 5050. RCPS. FWCS)INSTR: LOOP CONTAINING 1SMFE/FT/P50w.

RCPS. FWCS (FE/FT/P 5070, RCPS. FWCS)INSTR. LOOP CONTAINING ISMPT/P 5080 & RCPS INSTR. LOOP CONTAINING ISMPT/P 5090 & RCPS INSTR. LOOP CONTAINING ISMP'/P5100

& RCPS INSTR. LOOP CONTAINING 1SMPT/P 5110 & RCPS INSTR. LOOP CONTAINING 1SMPT/P 5120 & RCPS INSTR. LOOP CONTAINING ISMKI7PP5130

& RCPS INSTR. LOOP CONTAINING ISMPr/P 5140 & RCPS INSITR. LOOP CONTAINING 1SMPT/P51,50

& RCPS INUSR. LOOP CONTAINING ISMPT/P5160

& RCPS INSTR. LOOP CONTAINING ISVPT/P 5170 & RCPS INSTR. LOOP CONWAINING ISMPT/P5180

& RCPS _INSTR. LOOP CONTAINING 1SPTIP519O

& RCPS Included In Seismic PRA Non-Sofety SOLID STATE PROTECTION SYSTEM X I Included In SUPPORT FOR VA SYSTEM -f Seismic PRA Non-Safety POWER SUPPLY FOR VA SYSMEM X_ __ InCluded In, SUPPORT FOR VC SYSIEM ---Seismic PRA -Non-Safety 600V AC MCC 1EMXH I I i -. 1 .1 1.4 f -ontv cursorv iev~ew. of ttme corn gonents reaukred Poge W 3q O.i, TABLE 4 -0 InluedI SUPPORT FOR YC SYSTEM -T SePsAi onSft 4--I _________w 4160V AC SWITCHGEAR IETA (IEBIB 4160V AC 2ETA (2ETB)600V AC MCC IEMXG.600V AC MCC 2E1:MXG 600V AC MCC IEMXH 600V AC MCC 2EMXH .i2oV AC PANELBOARD EKA (EKB)120V AC PANELBOARD KXA-only cursory review of these components re qured Poge~ 19.0 TABLE 5 -ELECTRICAL EQUIPMENT LIST FOR MCGUIRE UNIT 2 IPEEE WALKDOWN-4-4. 4.-I Included In AREA TERMINATION CABINETS Seismic PRA Non-Safety Included in AUXILIARY SHUIDOWN PANEL SeLmnlc PRA Noq-Safet x Included in SUPPORT FOR CA SYSTEM Seismic PRA _Non-Satetr 4160V AC SWITCHGEAR 2ETA (2ETB) X 600V AC MCC 2EMXA (2EMXB) (2EMXB-2 _ X _' __600V AC MCC 2EMXA-4 X 600V AC MCC 2EMXA-5 X _125V DC DISTRIBUTION CENTER2EVDA (2EVDB) X 125V DC PANELBOARD 2EVDA (2EVDB) I x 120V AC PANELBOARD 2EVKA (2EVKB)& MANUAL TRANSFER SWITCH X -LOCAL MOTOR-DRIVEN PUMP CONTROL PANEL X , _ _LOCAL TURBINE-DRIVEN PUMP CONTROL PANEL X ESFAS TRAIN A (8)48V DC POWER SUPPLIES--- -I BATTERY"CHARGER EVCA (EVC13) I.DC CIRCUIT BREAKER FOR MDP2A (MDP2B) START -,NVERfER 2EVIA (2EVIs)!II T-D PUMP RELAY HFII'MFW PUMP RELAY BB(A)'(8B(B))

,(.,.'W,,@)

I '..MFW PUMP RELAY R/TT(FPTCA) (R/T'(FPTCB))

-'-MFW PUMP RELAY R/T'-I (FPTCA) (RITT- i (FPTCB)) _RELAY R25CCA] (R25C[B))RELAY K609A K(6095)RELAY LRA6 (1-986)LOAD- SHED RELAY LSAI (LSBD).TEST RELAY TSA2 (I"SB2)ESFAS SLAVE RELAY K633A (K633B) _ESFAS SLAVE RELAY K634A (K634B)056)

ES.A MASTER RELAY K516A051B!ESFAS INPUT RELAY K113A (KI13B)ESFAS INPUT RELAY K1I14A 0(KI 14B)i ESFAS INPUT RELAY K121A (K1218)IESFAS INPUT RELAY K150A 0(K150B)0 ESFAS INPUT RELAY K230A 0(1230B)ESFAS INPUT RELAY K231A (K231B) _ESFAS INPUT RELAY K250A (0(250B) _ _ELSFAS INPUT RELAY K255A _ESFAS INPUT RELAY K331A (K331B)---____________

___________________

~Pagoe% -/

016_________________TABL 5 InlddInL _SUPPORT FOR CA SYSTEM (cont.). _ _ SeIsmIc PRA Non-Safety WIESFAS INPUT RELAY K332A W(332B)ESFAS INPUT RELAY K333A 0(333B)ESFAD INPUT RELAY S 334A A=3UAT) A R ESFAS, INPUT RELAY K407A 0(4078) , E.SFAS INPUT RELAY K408A (1(408B)I ESFAS INPUT RELAY K409A (K4098)i ESFAS INPUT RELAY K410A OU,1013)i ESFAS LOGIC MODULEEA317A (A317B) L T E D/G LOAO SEQUENCER (LOAD ACTUATEL R2LAY 2JALA_ _ (__A(RB8))

_D./G LOAD SEQUENCER RELAY A3 (133) 1 I_1 SG A LO-LO WATER LEVEL CHANNEL I BISTAB..E SG A LO-LO WATER LEVEL CHANNEL I LEVEL TRANSMITTER SG A LO-LO WATER LEVEL CHANNEL 2 BISTABLE I I SG A LO-LO WATER LEVEL CHANNEL 2 LEVEL TRANSMITTER_

SG A LO-LO WATER LEVEL CHANNEL 3 BISTABLE I I SG A LO-LO WATER LEVEL CHANNEL 3 LEVEL TRANSMITTER SG A LO-LO WATER LEVEL CHANNEL 4 BISTABLE I I SG A LO-LO WATER LEVEL CHANNEL 4 LEVEL TRANSMITTER SG B LO-LO WATER LEVEL CHANNEL I BISTABLE N I SG B LO-.O WATER LEVEL CHANNEL 3 LEVEL TRANSMITTER_

SG B LO-LO WATER LEVEL CHANNEL 2 BISTABLE, I, SG B LO-LO WATER LEVEL CHANNEL 2 LEVEL TRANSMITTER_

SG C LO-LO WATER LEVEL CHANNEL 3 I i[,ABLE_ _" SG B LO-LO WATER LEVEL CHANNEL 3 LEVEL TRANSMITR_

_SG B LO-LO WATER LEVEL CHANNEL 4 BISTABLE _SG B LO-LO WATER LEVEL CHANNEL 4 LEVEL TRANSMITTER_

SG C LO-LO WATER LEVEL CHANNEL 3 BISTABLE I I SG C LO-LO WATER LEVEL CHANNEL 3 LEVEL TRANSMITTER SG C LO-LO WATER LEVEL CHANNEL 2 BISTABLE T7 SG C LO-LO WATER LEVEL CHANNEL 2 LEVEL TRANSMITTER SG C LO-LO WATER LEVEL CHANNEL 3 BISTABLE I I SG C LO-.O WATER LEVEL CHANNEL 3 LEVEL TRANSMITTER SG C LO-LO WATER LEVEL CHANNEL 4 BISTABLE I _1 SG C LO-LO WATER LEVEL CHANNEL 4 LEVEL TRANSMITTER SG D LO-LO WATER LEVEL CHANNEL I BISTABLE I I SG D LO-LO WATER LEVEL CHANNEL I LEVEL TRANSMITTER SG D LO-LO WATER LEVEL CHANNEL 2 BISTABLE I I SG D LO-LO WATER LEVEL CHANNEL 2 LEVEL TRANSIMITER SG 0 LO-LO WATER LEVEL CHANNEL 3 BISTABLE I I" SG D LO-IO WATER LEVEL CHANNEL 3 LEVEL TRANSMITTER SG D LO-.O WATER LEVEL CHANNEL 4 BISTABLE I.I SG D LO-LO WATER LEVEL CHANNEL 4 LEVEL TRANSMITTER INS , LOOP CONTAINING 2CASV/MV020D.

SVo2. & SV202 INSTR. LOOP CONTAINING 2CASV/MV0270 (0320) & SV0271 (0321)INSTR. LOOP CONTAINING 2CALL/P /SV/ML0520 (0480) jJ_.INSTR. LOOP CONTAINING 2CALL/P/SV/ML0560 (0440 Im lNSTR. LOOP CONTAINING 2CALLIP ISV/ML0600 (0401) I I I IFW.INSMR. LOOP CONTAINING 2CALL/P ISVIMLO06O (0360) I I Pagey 4-L2 TABLE 5 -0 I I I I I I I ncludd in SUPPORT FOR CA SYSTEM (Cont.) I-_ __ _ Seismic PRA I Nlo-Sofety I I I-in. .LJ...............L...I

_________________

t..i WIIjNSTR.

LOOP CONTAINING 2CAFE/PSIFT/PSO00 (5010). PS5001 (5rn11). & PS5002 r'5012)INSTR. LOOP CONTAINING 2CAPS/PT/P50 (5030) 1- 1 1.INST. LOOP CONTAINING 2CAFErPS/F,/P5040.

P5041, P5042. &P .INSTR. LOOP CONTAINING 2CAPS/PTIPGP5D05 INSTR. LOOP CONTAINING 2CAPL/PTP 5070 (50)INSTR. LOOP CONTAINING 2CAFET/,,P 5090 (5110) & FT.91 (5l)INSTR. LOOP CONTAINNG 2CAFERFT/P 5500 (5120) & FT5. 1 (5121)INSTR. LOOP CONTAINING 2CAPSIP 51600 INSTR. LOOP CONTAINING 2CRLT/P5490

.,.INSIR. LOOP CONTAINING 2CFLTIP 5500-M_ ___INSTR. LOOP CONTAINING 2CFLT/P5510 INSTR. LOOP CONTAINING 2CFLT/P5520 INST2. LOOP CONTAINING 2CMT/P 5530 -_ __-____-___

INSI-. LOOP CONTAINING 2CR.T/P 5540 -_. 'INSTR. LOOP CONTAINING 2CFLT/P 5550 -__ ____-____-

INSTR. LOOP CONTAINING 2CRT/P 56 -____- ___INSTR. LOOP CONTAINING 2CFT/P 5570 INSTR. LOOP CONTAINING 2CfLT/PS58M

__ ____-___iNSTR. LOOP CONTAINING

-2CFLT/P 5590 --____ ____-___INSTR. LOOP CONTAINING 2CRTJP 5600 -__ __INSTR. LOOP CONTAINING ZCAT/P 6000 D__ ___MNSR. LOOP CONTAINING 2CFLT/P 6010 __ ____ -____-.___

INSIR. LOOP CONTAINING 2CFLT/P 6020 ___ ____-____

___INSTR. LOOP CONTAINING 2CRT/P 603 __- ___Included In SUPPORT FOR DIESEL GENERATORS

"'"Seismic PRA Non-Sofety 4160V AC SWTCHGEAR 2ETA (2ETB) X 600V AC LOAD CENTER 2ELXA (2ELXB) X 600V AC LOAD CENTER 2ELXC (2EIXD) X 600V AC LOAD CENTER 2ELXE (2ELXF) X 600V AC MCC 2EMXA (2EMX)B) X 600V AC MCC 2EMXE X 120V AC PANELBOARD 2DG2A (20G2B) X 125V DC PANELBOARD 2EVDA (2EVDD) X 125V DC BATTERY./RACK

  • _. X INVERTER X DIG CONTROL PANELS X BATTERY 2EDGA (2EDGB) AND CHARGERS I X BATTERY 2EDGA (2EDGB) INPUT & OUTPUT BREAKERS 600/12Uv AC TRANSFORMER TO 2DG2A M20G2BM.,AUTO RESET RELAY ED('RA3) (ED(TRB3)) )i'BLACKOUT RELAY DC(BOA) CDC(BOBI)I BLACKOUT RELAY DC(BOA) (DC(BOBI)

-'-4 4.-I 1-1 1-4 lwmw BLACKOUT LOGIC RELAY DA(LRA2) (DA(LRB2fl" I P099eX -f3 Q I a TABLE 5 -__P __I _ FI I_ I__ I I I Included In I Ion-__e SUPPORT FOR DIESEL GENERATORS (cant.) Ij___ I_____ SeI IR I ~ Nonýr--Sofet 4-4 4-4 4-4 MWIDEFEAT TEST RELAY FB(DISA) (FB(DT])v DIG START RELAY 2TRAIA (2TRA(B))

'DIG START RELAY 2TRA1(A) (2TRA1(8)

_____ ___DIG START RELAY Z"RB(A) (2"RB(B))D/G START RELAY 2TRC(A) (2TRC(B))DIESEL STARTING AIR RELAY RVGI(A) (RVGI(B))DIESEL STARTING AIR RELAY RVG2(A) (RVG2(8))DIESEL STARTING AIR RELAY RVG3(A) (RVG3(B))D.GAUTOSTART RELAY DASR(A) CDASR(B)) ) -LOAD SHED RELAY ABISAI) (AB[LSBI))

LOAD SHED RELAY AA(LSA2) (AA[LSB2))

....LOAD SHED TIMER RELAY GC(LSA') (GC(L..T)LOGIC TIMER RELAY FD(LTIA) (FD(LTIB))

LOGIC TIMER RELAY FD(LT2A) (FD(LT2B))

RELAY AC(127ZBX)

RELAY AE[ 27XBX)RELAY 3CR(A E (3CR(BA)RELAY D (ATRA] (A)RT)B )RELAY DGIFRA (DGIFRB)RELAY ESX{A] (ESX(}))RELAY 21RA[A (2TRA(B])ERELAY FC(CRAI] (FC2'IRBI))

IRELAY HRA(AA) (HRB(BB))RELAY RTD(AG (REDLB)A .A Y RELAY S RAIXEA Y (S1AIX(BA)

Q I RELAY SIA2XTA 2 (SIA2X{B2)

RELAY SIA4XTA) (SIA4X2B)

_ _I RELAY TSA3 (TINN) (RESEr RELAY EB[RRA) (EB[RRB])RESTART RELAY FA[RGA) (FA{RGB))UNDERVOLTAGE RELAY 4CA[A) (5A37))UNDERVOLTAGE RELAY 4DA(A) (4DA( P0))UNDERVOLTAGE RELAY AC[127ZAX) (AC0927ZBX))

UNDERVOLTAGE RELAY AD&127YAXG (AD(127YBX()

UNDERVOLTAGE RELAY AE[127XAG ) (AE3527X02))

RESET SWITCH EG135 SPEED SWITCH $2 A2 (S282 )SPEED SWICH $2 A2 (S32 B2) ...INSTR. LOOP CONTAINING 2FDLS5040

& LS 504 0 & 351)INSTR. LOOP CONTAINING 2LDPG/PS5120

& PS,5..121/512215123 (5130 & 51311F5132t 5133)INSTR. LOOP CONTAINING 2VGPG/PS(4

& PG/P55 (5060 & 5070)INSTR. LOOP CONTAINING 2VGPG/PSM~

(5M I- I INSTR, LOOP CONTAINING 2VGPGIPM120

&{ PG/PS5122 (5140 & 5142)__INSTR. LOOP CONTAINING 2VGPGIPS5130

& PG/.PS5132 (5150.& 5152) ..I I I I I I I I I 4.-I 4.-I w--II I I Pogqý 4 019 TABLE 5 -0 1 Included in I _I SUPPORT FOR FW SYSTEM II_1 Seismic PRA I Non-Sofety w INSTR. LOOP CON INWG 2FWLTIP 5000 INSTR. LOOP CONTAININC 2FWLTIP 5000 --- ---- ---- .4.-I 4-I J-4-- .1-.I.INSTR. LOOP CONTAINING 2FWLTIP 5010 INSTR. LOOP CONTAINING 2FWLT/P 5020 =--__ included in SUPPORT FOR KC SYSTEM -Seismic PRA Non-Safet 4160V AC SWITCHGEAR 2ErA (2ETB) I I _x 600V AC MCC 2EMXA (2EMXB) X 125V DC PANELBOARD 2EVDA (2EVDD) -X D/G ACCELRATED SEQUENCE RELAY 2DB(AA2) (2DB(AB2])

DIG AUTO RESET ALU)UARY RELAY CCMRA3X) (CC )IRB.)DIG LOAD ACTUATE RELAY 2HA(RA6) (2HA(RB6)) " -D/G LOAD SEQUENCER RELAY LSA2 (LS ,I I__DIG LOAD SEQUENCER RELAY RA6 (RB6) II___.D/G LOADING TRANSIENT ADVANCE TIMER RELAY 2AD(ATAI)

(2AD(ATBI)

_D/G LOADING TRANSIENT ADVANCE TIMER RELAY 28D(ATA2J (2BO(ATB2))

D/G LOADING TRANSIENT ADVANCE TIMER RELAY 2CD(ATA3)

(2CD(ATB3))

_D/G LOADING TRANSIENT ADVANCE TIMER RELAY 2DD(ATA4]

(2DD(ATB4))

-D/G SEQUENCE TIMER RELAY GA(ST4A) (GA(ST4B))

D/G SEQUENCE TIMER RELAY GB(ST2A) (GB(Si2B])

-D/G SEQUENCE TIMER RELAY HB(ST6A) (HB(ST6B))

-D/G SEQUENCE TIMER RELAY HC(ST5A) (1HC(STSB))

, D/G TEST' RELAY 2FB(TSA4)

(2FB(TSB4I))

L ___ESFAS SLAVE RELAY K61OA (K610B)TEST RELAY TSAI CTSBI) ._, INSITR. LOOP CONTAINING 2KCPT/P 5490 (550)INSTR. LOOP CONTAINING 2KCFE/FT/P 5530 (5540) --INSTR. LOOP CONTAINING 2KCFE/FT/FS/SVJP 5670 (5680)I- Included in MAIN CONTROL BOARDS Seismic PRA -Non-Safea X-Included In -_SUPPORT FOR NC SYSTEM _ __ Seismic PRA _.Non-Safety 4160V AC SWITCHGEAR 2ETA (2ETB) X _600V AC LOAD CENTER 2ELXA (2ELXB) -X _600V AC LOAD CENTER 2ELXC (2ELXD) -m -I_ X 600V AC MCC 2EMXC (2EMXD) X~I95V flC PANFI ROARfl 9FVflA (9FVflfl~y PANEBO-4 2ED-(.)VO ACCELERATED SEQUENCE RELAY 2CB(AAI) (2CB(AB1))

Page% 457 020 TABLE 5 -SUPPORT FOR NC SYSTEM (cont.) .Seln PRA I jNon-Soeto I'W9ESFAS SLAVE RELAY K608A (K608B)I Im ESG AUXILIARY RELAY BDIESGAX2) (BD(ESG BX2)) -LOAD SHED RELAY AB(LSA2) (AB. SB2)) I I MAXIMUM SEQUENCE TIMER RELAY BE(LT3A) (BE(LT3B))

RELAY 2AB(LRA4)

(2AB(.RB4))

_., RELAY DC(BOA) (DC(BOB])RELAY DA(LRA2) (DA(LRB2))

RELAY FCalRA2) (FC(TRB2))

....._.SEQUENCER LOAD RELAY 2CA(RA2) (2CA(RB2)).

SEQUENCER LOAD RELAY 2DA(RA2) (2DACRB2])

SEQUENCER TIMER RELAY JA(ST2A) (JA(ST28))

TEST RELAY 2FBITSA4)

(2FBCrSB4))

TEST RELAY 2GB(rSA5)

(2GB(TSB5))

UNDERVOLTAGE RELAY C8B127AX) (CB(127BX))

INSTR. LOOP CONTAINING 2NCSVO320

& SV0321 INSTR. LOOP CONTAINING 2NCSV0340

& SV0341 INSTR. LOOP CONTAINING 2NCSVO360

& SV0361_ __I -Included in , SUPPORT FOR ND SYSTEM ,-Seismic PRA -Non-Sofeft 4160V AC SWITCHGEAR 2ETA (2ElB) x 600V AC MCC 2EMXA (2EMXB-1)

X _125V DC DISTRIBUTION CENTER 2EVDA (2EVDD)_ X DIG LOAD ACTUATE RELAY 2FA(RA4) (2FA(RB4))

, RELAY DGTSA6 (DGTSB6) ___RELAY LSAI (LS82)INSTR. LOOP CONTAINING 2NDRD/P 5=00 (5120) & 2NDR/P CR5060 (5070)INSTR. LOOP CONTAINING 2NDFEIFS5040 (5050)INSTR. LOOP CONTAINING 2NDPT/P 5090 (5080)INSTR. LOOP CONTAINING 2NDFE/FT5250 (5260)___Included in SUPPORT FOR NI SYSTEM Seismic PRA Non-Safety 4160V AC SWITCHGEAR 2ETA (2ETB) .X 600V AC MCC 2EMXA _ x 600V AC MCC 2EMXA-1 .I_ X 600V AC MCC 2EMXB-1 _ X 125V DC PANELBOARD 2EVDA (2EVDD) --X D/G LOAD ACTUATE RELAY 2EA(RA3) (2EA(RB3))

-_IDIG LOAD SEQUENCER RELAY RA3 CRB3) U-I _DIG RELAY LSA2 (LSB2)-- --- tt f-+ 1-4 lqwp DG TEST RELAY DGTSA6 .(DGTSB6)Page 04-4 021I TABLE 5 --T I V --~nInuJded In~~~-Inlue In_______SUPPORT FOR NI SYSTEM (cont.)Seismlc PRA Non-Sofetv Se-isi PR-o Sf--~ -~ ~-4 +-*w UMIT SWITCH TO MOV 2NI147A LIMIT SWITCH TO MOV 2N1185A (2NI184B) r iT INSTR. LOOP CONTAINING 2NILT/P 5260 INSTR. LOOP CONTAINING 2NILT/P 5270 Included In SUPPORT FOR NV SYSTEM Seismic PRA Non-Safety 4160V AC SWITCHGEAR 2ETA (2ETB) x 600V AC MCC 2EMXA X 600V AC MCC 2EMXB-) X 600V AC MCC 2EMXB-2 X)25V DC PANELBOARD 2EVDA (2EVDD) -... X DIG AUTO RESET RELAY EDUTRA3) (ED([RB3))

D/G LOAD ACTUATE RELAY 2DA(RA2) (2DA(RB2))

DIG TEST RELAY TSA2 (FSAB) I I CONTAINMENT HIGH PRESS. CHANNEL 2 BISTABLE (ESFAS)CONTAINMENT HIGH PRESS. CHANNEL 2 TRANSMITTER (ESFAS)CONTAINMENTHI-GH PRESS. CHANNEL 3 BISTABLE (ESFAS) I CONTAINMENT HIGH PRESS, CHANNEL 3 TRANSMITTER (ESFAS)CONTAINMENT HIGH PRESS. CHANNEL 4 BISTABLE [ESFAS) I CONTAINMENT HIGH PRESS. CHANNEL 4 TRANSMITTER (ESFAS)..ESFAS INPUT RELAY KI34A (K331B)ESFAS INPUT RELAY 'Kl33A (KI33B)ESFAS INPUT RELAY K201A (K201B)ESFAS INPUT RELAY K217A (02718)ESFAS INPUT RELAY K247A (K247B)ESFAS INPUT RELAY K33DA (K330B)ESFAS INPUT RELAY K344A 0(3448)ESFAS INPUT RELAY K417A 0041713)ESFAS INPUT RELAY K430A (10308)ESFAS INPUT RELAY K444A 0(44413)ESFAS LOGIC MODULE A210A (A2101M ESFAS LOGIC MODULEA213A (A21313)ESFAS LOGIC MODULE A308A (A308B)ESFAS LOGIC MODULEA313A (A313B)ESFAS LOGIC MODULEA411A (A4110)ESFAS LOGIC MODULEA416A (A416B)ESFAS MASTER RELAY K501A (K5O1B)ESFAS SLAVE RELAY K603A (K60313) _ESWAS SLAVE RELAY K607A (K607B)LOW STEAMLINE PRESSURE CHANNEL 1 BISTABLE (ESFAS)LOW STEAMUNE PRESSURE CHANNEL 1 TRANSMITTER (ESFAS).._

-,LOW STEAMUNE PRESSURE CHANNEL 2 BISTABLE (ESFAS) _i I III-MLOW STEAMUNE PRESSURE CHANNEL 2 TRANSMITTER (ESFAS)I W LLOW STEAMUNE PRESSURE CHANNEL 4 BISTABLE (ESFAS)I POge+ 1- 7 TABLE 5 -0 II_[_I Included In=SUPPORT FOR NV SYSTEM (cont.) I I Seismic PRA I Non-Saret 1 I I I I LOW STELAMUNE PRESSURE CHANNEL 4 TRANSMITIER (ESFAS) j PRESSURIZER LOW PRESSURE CHANNEL I BISTABLE (ESFAS] II PRESSURIZER LOW PRESSURE CHANNEL I TRANSMITTER (ESFAS)PRESSURIZER LOW PRESSURE CHANNEL 2 BISTABLE (ESFAS) 1 1 PRESSURIZER LOW PRESSURE CHANNEL 2 TRANSMITTER (ESFAS)PRESSURIZER LOW PRESSURE CHANNEL 3 BISTABLE (ESFAS) I I .- I...PRESSURIZER LOW PRESSURE CHANNEL 3 TRANSMITTER (ESFASI.INSTR. LOOP CONTAINING 2NVFE/FTISS/P 5620 & 2NVFT/P 5621 INSTR. LOOP CONTAINING 2NVFE/FTISS P 5630 & 2NVFT/P 5631-Included In PROCESS CONTROL BOARDS .Seismic PRA Non-Safety Included In SUPPORT FOR RN SYSTEM -Seismic PRA Non-Sofety 4160V AC SWITCHGEAR2ETA C2ETB) X 600V AC MCC 2EMXA X 600V AC MCC 2EMX(B-2 ...X aýAC MCC 2EMXE ,'X 60VAC MCC 2EMXH X 600)V AC MCC 2EMXH-1 X 600V AC MCC 2EMXH X 125V DC DISTRIBUTION CENTER 2EVDA (2EVDD) .X DIG LOAD SEQUENCER RELAY 21A(RA7] (21A[RB7])

D/G; LOAD SEQUENCER RELAY LSA2 (Ms2) I F-D/G LOADING TRANSIENT ADVANCE171MER RELAY 2ED(ATA5]

(2ED[AB]DIG SEQUENCE TIMER RELAY HA[ST7A)

),D/G TEST RELAY 2FB[TS4] (2FB(SB4)) -II INSTR. LOOP CONTAINING 2RNPG/P:SS=X

& SV0210. 021,l, 2]20, 0221 (5010 &0250,

_ I I -- 'II INSTR. LOOP CONXTAMNIG 2MIIPTIPS/P

=02 (SM I I)INSTR. LOOP CONTAINING 2MMFFT/P 5040 & R5041 (0505D& 6051)INSTR. LOOP CONTAINING 2RfLH:/FT/P 5220 (5230) _ .I I.INSTR. LOOP CONTAINING 2R"E/FTIP

&W6 & PTPSI(53.7,0

&.53.7 1)Mncluded in REACTOR PROTECTION SYSTEM Seismic PRA Non-SoferTRIP BREAKER A (B)REACTOR TRIP BYPASS BREAKER A (B),mad _____________________x____

wp____________________________________________________________________

~ i~-.... £ -J. L -1 ____________________

J. -Page) LI-'

623 TABLE 5 -U OTFO SVSSTM .I .Included In SUPPORT" FOR SM. svSV I II PRA I Non-Safety I I I-5 4 4--I *I.-~4."WlI60V AC MCC 2EMXA-2 I I I I x 600V AC MCC 2EMX"-4 i i__ x_INSTR. LOOPCONTAIMNG 2SMSV[J10 (0011).(0013)&LL0010,0011

_INSTR. LOOP CONTAINING 2SMSV0030(0031).(0033)

& LL0030.0031 INSTR. LOOP CONTAINING 2SMSVO050 (0051) (0053) & 100650. 0051 ,_INSTR. LOOP CONTAINING 2SMSVO070 (0071)1(0073)

& LL0070. 0071 _ ..INSTR. LOOP CONTAINING 2SMSV/LL/MLOO0 (SVO091) _ _INSTR. LOOP CONTAINING 2SMSV/LL/ML0110 (SV0101)INSTR. LOOP CONTAINING 2SMSV/LL/MLOI 10 (SV0 11) .INSTR. LOOP CONTAINING 2SMSV/LL/ML0120 (5V0121) jJ_ ___INSTR. LOOP CONTAINING 2SMFE/FT/P 5000. RCPS. FWCS (FE/FT/P 5010. RCPS. FWCS)iNSTR. LOOP CONTAINING 2SMFE/FTLP 50M,0 IRCPS, FWCS (FE/F'/P 5030, RCPS, FWCS)INSTR. LOOP CONTAINING 2SMFE/FT/P 5040. RCPS. FWCS (FE/FT/P 5050. RCPS. FWCS)INSTR. LOOP CONTAINING 2SMFE/FT/P 6060. RCPS. FWCS (FE/FT/P 5070. RCPS. FWCS)INSTR. LOOP CONTAINING 2SMPT/P 5080 & RCPS _INSTR. LOOP CONTAINING 2SMPTjP 5090 & RCPS ...INSMR. LOOP CONTAINING 2SMPT/P6100

& RCPS INSTR. LOOP CONTAINING 2SMPT/P5110

& RCPS INSTR. LOOP CONTAINING 2SMPT/P5120

& RCPS INSTR. LOOP CONTAINING 2SMPI/P 5130 & RCPS INSR. LOOP COTAINING 2SMPr/P 5140 & RCPS -INSTR. LOOP CONTAINING 2SMPTb P 5150 & RCPS INSTR. LOOP CONTAINING 2SMPT/P5160

& RCPS INSIR. LOOP CONTAINING 2SMPTIP65170

& RCPS_INSTR. LOOP CONTAINING 2SMPT/P5180

& RCPS -__INSTR. LOOP CONTAINING 2SMPT/P5190

& RCPS 1Included In SOLID STATE PROTECTION SYSTEM ... .,_ Seismic PRA N -r__ _x I 0e PogeX 4ij opa1 TABLE 6 -Ah CONTAINMENT PERFORMANCE COMPONENT UST FOR MCGUIRE UNIT I IPEEE WALKDOWN , CONTAINMENT ISOLATION VALVES Penet. alve Posit.on AND PENETRATIONS No. Valve No.. Line Size (in.) Norm] Fal Acc.UPPER COMPARTMENT PURGE INLEt I M367 I lVPIB 24 C C C UPPER COMPARTMENT PURGE INLET M367 I IVP2A 24 C C C UPPER COMPARTMENT PURGE INLET 1VP3B 24 C C C UPPER COMPARTMENT PURGE INLET M454 IVP4A 24 C C C LOWER COMPARTMENT PURGE INLET M357 1VP6B 24 C C C LOWER COMPARTMENT PURGE INLET IM357 VP7A -24 C C C QOWER COMPARTMENT PURGE INLET M456 -VP8B 24 C C C LOWER COMPARTMENT PURGE INLET M456 IVP9A 24 C C C CONTAINMENT PURGE EXHAUST M368 IVPIOA 24 C C C CONTAINMENT PURGE EXHAUST M368 IVPIIB 24 C C C CONTAINMENT PURGE EXHAUST M455 IVP12A 24 C C C CONTAINMENT PURGE EXHAUST M455 IVP13B 24 C C C CONTAINMENT PURGE M119 )VP15A -24 C C C CONTAINMEN PURGE M M19 IVP16B -24 C C C INCORE INSTR. ROOM PURGE IN M213 IVPI7A -12 C C C ORE INSTR. ROOM PURGE IN 1M213 VP18B 12 C C C.ORE INSTR ROOM PURGE OUr M138 IVP19A _ 24 C C C REINSITR.

ROOM PURGE OUT M138 IVP20B 1 24 C C C CONTAINMENT AIR RELEASE M243 IVQIA _ 6 C C C CONTAINMENT AIR RELEASE I43 lVQ2B -6 C C C CONTAINMENT AIR ADDIIlON M384 IVQ5B -6 C C C CONTAINMENT AIR ADDmON M384 )VQ6A 6 C C C CONT. VENT UNITS COND. DRAINS TO DRN. TK. M221. IWL321A -6 0 A] C CONT. VENT UNITS COND. DRAINS TO DRN. TK M221 IWL322B 6 0 Al C EQUIPMENT HATCH .......UPPER CONTAINMENT PERSONNEL HATCH.. C392...LOWER CONTAINMENT PERSONNEL HATCH .C152 .......PERSONNEL AIR LOCK INFLATABLE DOOR SEALS OINCLUDING AIR SUPPLY SYSTEM)PERSONNEL AIR LOCK 208 V UNEAR ACTUATOR DOOR LATCHES 600V AC MCC IEMXA 600V AC MCC IEMXB I 125V DC PANELBOARD 1EVDA _125V DC PANELBOARD 1EVDB 125V DC PANELBOARD lEVOD _120V AC PANELBOARD IEKVA _120V AC PANELBOARD IEKVD -I Pageg 5c OF,,: TABLE 6 -al-train components ore shown in parentheses.

A detailed wolkdown of these components Is not essary if the WB train configuration is similar to the 'A' train.)HWDROGEN MIIIGATION SYSTEM GLOW PLUG IGNITERS 600V AC MCC IEMXA (EMX) " TRANSFORMER HMTA (HMTB)TRANSFORMER IEMXA (IEMXB)ICE BASKETS & DOORS ....Une Included In NS SYSTEM ..Size (in.) Seismic PRA NS PUMP IA (1.8) -'__ X NS HX ]A (1B) " h"4160V AC,.SWTCHGEAR IIETA (IETB)w. 60aV AC MCC IEMXA (IEMXB).V DC PANELBOARD 1EVDA (1EVDD)Line Included In VX SYSTEM Size (in.) Seismic PRA AIR-OP DAMPER IRAF-D-5 (-8) , AIR-OP DAMPER IRAF-D-6 (-9)_AIR-OP DAMPER IRAF-D-7 (-10)MOTOR-OP ISONAI(O DAMPER IRAF-D-2 (-4) _CONTAINMENT AIR RETURN FAN IA (IB) ..... X , 600V AC MCC IlEMXA (IEMXB) .........600VAC MCC IEMXC (IEMXD).120V AC PANELBOARD IEKVA (I1KVD) _ .PRESSURE TRANSMITER I VXPT5390 (I-ci ossoc. breaker, alarm module,.&

48 dc power supply)(PRESSURE "RANSMIT"ER IVXPT5380 toncL assoc breaker, alarm module. & 48 dc power supply))PRESSURE TRANSMOrTER IVXPT5500 Uncl. assoc. breaker, alarm module. & 48 dc power supply)(PRESSURE TRANSMITTER IVXPT5490 (Mc. assoc breaker, alarm module. & 48 dc power supply))Page~ ý '

026 TABLE 7 -Ah CONTAINMENT PERFORMANCE COMPONENT USLT FOR MCGUIRE UNIT 21 IPEEE WALKDOWN____

CONTAINMENT ISOLATION VALVES , Peneti. ' Volve Position AND PENETRATIONS No. Valve No. Line She (in.) Norm FoR Ac.UPPER COMPARTMENT PURGE INLET " M367 2VPIB 24 " -_UPPER COMPARTMENT PURGE INLET I M3.7 2VP2A 24 C C C UPPER COMPARTMENT PURGE INLET 2VP3B 24 C C C UPPER COMPARTMENT PURGE INLET M454 2VP4A 24 C C C LOWER COMPARTMENT PURGE INLET M357 2VP6B 24 C C C LOWER COMPARTMENT PURGE INLET M357 2VP7A 24 C C C LOWER COMPARTMENT PURGE INLET M456 2VP8B 24 c C C LOWER COMPARTMENT PURGE INLET M456 2VP9A 24 C C C CONTAINMENT PURGE EXHAUST M368 2VP1OA 24 C C C CONTAINMENT PURGE EXHAUST M368 2VPlIB 24 C C C CONTAINMENT PURGE EXHAUST M455 I2VP2A 24 C C C CONTAINMENT PURGE EXHAUST M455 _ 2VP132 24 C C C CONTAINMENTPURGE.

M119 2VP15A 24 C C C CONTAINMENT PURGE M119 -2VP168 1 24 C C C INCORE INSTR. ROOM PURGE IN " M213 -2VPI7A 12- C C C CORE INSTR. ROOM PURGE IN M213 2VP18B 12 C C C OE INSTR. ROOM PURGE OUT 1 M138 2VP19A 24 C C C INSTR. ROOM PURGE OUT .M138 2VP209 24 C C C CONTAINMENT AIR RELEASE M243 , 2VQ1A 6 C C C CONTAINMENT AIR RELEASE M243 2VQ2B 6 c , CONTAINMENT AIR ADDITON M384 __2VQ_ B 6 C c__CONTAINMENT AIR ADDITION M384 _ 2VQ6A 6 C C C CONT. VENT UNITS COND. DRAINS TO DRN. TI. M221 2WL321A 6 O A C CONT. VENT UNITS COND. DRAINS TO DRN. "K. M221 2WL322B 6 0 Al- C EQUIPMENT HATCH ........ I......UPPER CONTAINMENT PERSONNEL HATCH , C392 _ ... ..._ _LOWER CONTAINMENT PERSONNEL HATCH C152 PERSONNEL AIR LOCK INFLATABLE DOOR SEALS (INCLUDING AIR SUPPLY SYSTEM) I-PERSONNEL AIR LOCK 208 V LINEAR ACTUATOR DOOR LATCHES____

600V AC MCC 2EMXA _ _ ,_600V AC MCC 2EMXB 125V DC PANELBOARD 2EVDA I'_I 125V DC PANELBOARD 2EVDB __ .:___,I 126V DC PANELBOARD 2EVDD _ _ _ _, 120V AC PANELBOARD 2EKVA _____120V AC PANELBOARD 2EKVD _l_"___Paget 5 7 TABLE 7 -Ah B train components ore shown in parentheses.

A detailed wolkdown of these components Is not essary if the '0' train con!lguration Is smilar to the A train.)HYDROGEN MITIGATION SYSTEM GLOW PLUG IGNITERS 600V AC MCC 2EMXA (2EM.B) -_" TRANSFORMER HMTA (HMTB)TRANSFORMER 2EMXA (2EMXB)ICE BASKETS & DOORS Line Included in ISNS SYSTEM Size (In. Seismic PRA NS PUMP 2A (2B) X NS HX 2A (28) X S4160V AC sWI.TCHGEAR 2ETA (2ETB), 600V AC MCC 2EMXA (2EMXB),- 5V DC PA.,NE.BOARD 2EVDA (2EVDD)Line Included in VX SYSTEM Size (In -Seismic PRA AIR-OP DAMPER 2RAF-D-5 (-8)AIR-OP DAMPER 2RAF-D-6 (-9) _._...._ _AIR-OP DAMPER 2RAF-D-7 (-10)MOTOR-OP ISOLATION DAMPER 2RAF-D-2 (4)_CONTAINMENT AIR RETURN FAN 2A (2B) "" X 600V AC MCC 2EMXA (2EMXB) , , R5O]V AC MCC 2EMXC (2EMXD) ...._120V AC PANELBOARD 2EKVA (2EKVD)PRESSURE TRANSMITTER 2VXPT5390 (ncL ossoc. breaker, alarm module, & 48 dc power supply)(PRESSURE TRANSMUlTER 2VXPT5380 incl. ossoc, breaker. alarm module, & 48 dc power supply])PRESSURE TRANSMITTER 2VXPT600 (inc. ossoc. breaker, alarm module, & 48 dc p.ower supply)(PRESSURE TRANSMITTER 2VXPT5490 (IncL ossoc, breaker, alarm module, & 48 dc power supply))Pogey 53 Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal report for Seismic Walk-downs McGuire Unit 1 ATTACHMENT 2 McGuire Unit 1 SWEL-1 Rev. 1 McGuire Unit I SWEL. Equipment Walkdown Scope ATTACHMENT 2 1 of 6 Eqimn ytm Class of Bids El. Roma oin Lisedon Malor Now/ Prior IPEBEE___________

Building_

____, Rom Coun EEE Replacement Discreilancy/

Safe',Fntiy Eqipen 1 Dsoloio ~Eauismerri Grid lin unctionEhaceen 05-Horlzonata.OltO~

ICAPU0001 IA MDCAP CA Pump Aux Bldg 716 O/MDCAPmX NC-Press, DH ICA-PN-AFPA MOCAP 1A Control Panel CA 20-Instrument and Aux Bldg 716 eS0/MDCAP CC-61 X NC-Press, DH Control Panel Rm 1CA-PN-AFTP TDCAP Control Panel CA 20.Instrument and Wu ~g 76 60TDCA XN-PaD Control Panel Puup Blg 7 Rm CPrs.ICAPUD003 TDCAP CA Aua Bldg 710 600oTOCA X NC-Press, DH_ AP_ _T__APC Puma Pump Rm ICAHX0003 TDCAP Bearing Oil Cooler CA 21.Tanks/HtXs Aux Bldg 716 600iTDCA X NC-Press, DH PPump Rm ICA-56A MDCAP Flow Controt to 1 B SG CA 07-AOV Aus Bldg 716+8 6500/MDCAP x NC-Press, DH Rm 1SA-4aABC TDCAP steam supply from 1C SG SA 07-AOV Inner 76+0 Inner Doghouse X NC-Preas, DH Inner Inner 1SA-4gAB TDCAP steam supply from IB SG SA 07-AOV I Doohouse 767+11 Doohouse X, NC-Press.

DH 1VGTKO062 1A1 EDG Starting Air Tank VG 21-TanksitMs BEG Bldg 736.5 IA OG Ar X Various 1VGTK0063 1A2 EDG Starting Air Tank VG 21-Tanks/HtXs EDG Bldg 736.5 IB EDG Rm X Various 1VGTK0064 1 B 1 EDG Starting Air Tank VG 21-Tanks/HtXs EDG Bldg 736.5 IA EDG Rm X Various 1VGTKO065 1B2 EDG Staering Air Tank VG 21-Tanks/HtXs EDG Bldg 736.5 lB EDG Rm X Various 1VG-61 EDG Serting Alr Solenoid VG 08-MOVWSOV EOG Bldg 736.5 1A EDG Rm X Various 1VG-66 EDG Sartting Air Solenoid VG 08-MOV/SOV EDG Bldg 736.5 1B BDG Rm X Various lB EDG 16 Emergency Diesel Generator Set EDG 17-Engine BOG Bldg 736 Generator

.5 lB BOG Am X Various 1KCTKO009 KC Surge Tank KC 21-Tanks/HtXs Aux Bldg 767 9 JJ-57 X Various IKCHXO005 IA KC HiX KC 21-Tanks/Htxa Arx Bldg 750 KC HLXArea JJ-56 x Various X -missingogou 1KCHX0006 1B KC HtX KC 21-Tanks/HtXs Aux Bldg 750 KC HNX Area JJ-S6 6or saddle base Various and curbr 1KCPUO0OI lA1 KC Pump KC 05-Horizontal Aum Bllg 733 UI KC GG-55 XVarious Pump Pump Area McGuire Unit 1 SWEL-1 Equipment WalkdOwn Scope ATTACHMENT 2 2 of 6 Euoet eritcSytm Class Rf Bulig Ee. Ro o iste on Major New/ Prior IPEEE S Ss---------m-B .Room# Column- IPFEE Retacernet iscrepnyl Safety Function Oddnen List Equipment Enhancemen 1KCPU.002 1A2 KC Pump KC 05-Horizontal Aun Bldg 733 U1 KC Pump Pump Area GG-5 X Veaious Open 1 KC-50A KC Aux Bldg Non-ESS Return Isot KC 0n-M.OVISOV Au" Bidg 750 General GG-57 X X (EC-75450, Various Area replace valve)3 Aux Bldg Non-Essential Header Open 1KC-53I Nolation KC 08-MOV/SOV Aux Bldg 750 General KK-55 X Various Isolation__

Area I NC-32B NC System Pressurizer PORV NC 07-AOV Rx Bldg Przr Cavity X NC-Press, NC Inventory 1 NC-34A NC System Pressurizer PORV NC 07-AOV Rx Bldg Przr Cavity X NC-Press, NC Inventory 1NDRl5060 1A ND pump dsch temp NO 1S-Temperature Amn Bldg 750+9 732 LL-51 Containment Sensor Integrity INDRD5120 1B ND HtX dischargeTemperature to ND 19-Temperature Aux Bldg 750+9 733 LL-51 Containment NC CL Sensor Integrity 1ND-1B RHR Pump Hotleg Suction Isolation ND 08-MOV/SoV Rx Bldg 745 B-C Lower Between Containment B & CSG D 1ND-2AC RHR Pump Hotleg Suction Isolation ND 08-MOV/SOV Rx Bldg 745 B-C VL Fan B-C VL X Rm Fan Rm DH, NC 1 ND-4B RHR FWST Suction Isolation ND 08-MOV/SOV Ann Bldg 695 P 5pechase FF-53 X Inventory.

P___e__a__

_Reactivity IND-15B ND -tX Discharge X-tie nsot ND 08-MOVISOV Aux Bldg 733+8 733 LL-52 X X ReaC__________

80-997)Reactivitv X OH. NC 1ND-14 ND 1 B HtX Discharge Flow Control ND 07-AOV Aux Bldg 733+6 733 LL-52 X X Inventory.

_(EC-77860)

Reactivity X Dii, NC IND-29 ND 1A HitX Discharge Flow Control ND 07-AOV Aux Bldg 733+4 732 LL-52 X X Inventory.-Reactivity 1NV-222B UNIT 1 NV PUMP SUCTION FROM NOH NC FWST ISOL NI t t-MOVSOV Auxo1do 7"6+2 603 JJ-52 X Inventry.Reactivity OH, NC 1NDI-X0003 1A RHR HtX ND 21.Tanks/HtXs Aux Bldg 750 732 LL-52 X Inventory, Reactivity OH, NC iNDHX0004 18 RHR HtX ND 21-TankslHtXs Aux Bldg 750 733 LL-52 X Inventory, Reactivity McGuire Unit 1 SWEL-1 Equipment Walkdown Scope ATTACHMENT 2 3 of 6 Class of Lie on Malor Newt gioIEEE Equipment Bidn 51vSystem Eaulpml Ceuo Gri IP Replacement Dlecrepan" a----Odd IBI Egulloment Entrancemen iNPOO lA ,II Pum ND..eta upAnBd 65 51 G5 CPes NC-Press, DH, 1NDPUOOO1 1A RHR Pump ND e6-Vedlcat Pump Aux Bldg 695 501 GG-54 X NC Inventory.

Reatt.1iy 1NDPU0002 IB RHR Pump ND 06-Vertcal Pump Aux Bldg 695 Sao FF-54 X NC Inventory, I I IReacWN~INIPU009 1A Med-Head NI Pump NI 05-Horizonta A.l B 7 628 G54 X NC Inventory, Pump A Reactivity 1NIPU0010 18 Me(I-Head NI Pump NI 05-Horizontal .Bd 1 2 G5 NC Inventory.

Pum Au Blg 76 .626 GG-4 XReactivty 1NI-115B.

Med-Head NI Pump Minflow Isolation NI 08-MOVISOV Aux Bldg 716 e28 HH-54 X RH, NC X DH, NC 628 H-5 X (C-996)Inventory.

1NI-1448-Med-Head NI Pump Minflow Isolation NI 08-MOVISOV Aux Bldg 716 626 GG-54 X I nHetoNy.(EC-9994)

Ivnoy NC-Press Dt.INI-178B B train ND to Coldleg Isol. NI O-tMOV/SOV Aux Bldg 733+7 730 H14-52 X NC Iventory, Reactivty ND/NS Pump Containment Sump NI oB-MOVISOV Am Bldg 716 62IE 1NI-185A , Supply sot Rathole FF-53 X Various 1 NI-430A N2 Assured Supply to 1 NC-34A NI 08-MOVISOV Rx Bldg 760 1A CLA X NC-Prea3 PORV Room INI-431B N2 Assured Supply to 1NC-32B -OVSOV Bldg 760 CLA X NC-Press PORV Room INSHX0003 1A NS HtX NS 21-Tanks/HtXs Aux Bldg 733 732 LL-50 X Iontarinet Integrity 1NSHXO004 18 NS HtX NS 21-TanksIHtXs Aux Bldg 733 733 LL-50 X Cotament Integrty INSPU0001 1A Containment Spray Pump NS 06-Vertical Pump Aux Bldg 733 502 GG-54 X Containment lNVTKOO1 i CVCS Volume Control Tank NV 21-Tanks/tXs Ann Bldg 733 723 KK-50 x NC Inventory, INV-141A HI-Head NV pump VCT Suction NV (16-MOVISOV Aux Bldg 733 730 JI-50 X NC tnvtort.isolation Reactivity INV-238 Charging flow control NV 07-AOV Aux Bldg 716 629 JJ-54 X NC tivnityot, 1NVPUO0015 1A HI-Head NV Pump NV 05-Horizontal AC Bn71n2H-4 X Pump Ann Bldg 716 627 HH-54 X ReaCtivety 1RNPU0007 1A RN STRAINER BACKWASH PUMP RN 05-HOrMDntN Aux Bldg 716 1 Pump I 600eRN Slualner RAn BB-52 X -new I(EC102477)

.Various McGuire Unit 1 SWEL-1 Equipment Walkdown Scope ATTACHMENT 2 4 of 6 Class of u Major New Prior IPEE.Eouipment Dscriton Sysm Building Elaev Room# IPEEE Rsgiuement Qaioancn lla lon List Esaome Rnhancemet 1RNPUOO 1B RN STRAINER BACKWASH 05-Horizontal Aux Bldg 716 St01/RN VaBXous PUMP Pump rainer Rm (EC102478)

X -replaced StranerRm AA-50 X (MD102029, Various IRNST0002 1A RN Pump Suction Strainer RN 00-other AtuxBldg 716 St1rane XRrelae Strainer Rm ~ EC 997291 _____X -replaced StrainrRm AA-60 X (MD101864, Various 1RNSTOO02 1B RN Pump Suction Strainer RN 00-oter Au Bldg 716 StriRne Rm -0 X MD19.Vris EC 99729)X -oew 1R-1 A RN Strainer Asuto Backwash 600RN BEX5 x nalewatar 1RN-21A 1 Valve RN 07-AOV Amx Bldg 716+4 Strainer Rm BB-52 X controls Various 0RN-7A, 1J2A RN Pump SNSWP Suction various ECs ORN-7A IA2A RN Pump SNSWP Suction RN 08-MOV/SOV Aux Bldg 716+3 601 BM-63 X Various 1A/2A RN Essential Header SNSWP 647W 0RN-149A Return RN 0m-MOV/SOV Ann Bldg 7164-4 /Rathole FF-59 X Various~ ~~X -Controls Nrsue 1SM-1AB Main Steam Isolation Valve ID SG SM 07-AOV e 807+3 Outer FF-43 NSpg d NC presaure, Doghouse Doghouse UNS-g56)aeatiit 1SM-3AB Main Steam Isolation Valve IC SG SM 07-AOV laser 767+30 inner dX -conrols NC pressure.oghouse D Doghouse F253 Reactivity 1SV-19 1A SG Main Steam PORV SM 07-AOV Outer 807+3 Outer FF-43 X NC pressure.nDoMuhouse Doghouse Reactivity 1SV-13 1nB S Main Steam PORV SM 57-AOV Iner FF5 x X -grating In NC presaure, 1 1B MnR07 Doohouse 6730 e F-3 contact whrawse Rea(1VC-1A VC Otsd Air Intake Isol from Unit I VC 08-MOV/SOV Ama Bldg 767 926 BB-50 X Various IVIAG-11 RN StraineracashAssedA X -new 1Vt-AC-1 R r rB sA d VI 21-Tanks/HtXs Ann Bldg 733 701C CC-52 component Various p (EC-101543) 1WL-322B Containment Venltilation Otiod CIV to WL 08-MOV/SOV Aux Bldg 716+11 B00iMOCAP CC-S2 C VUCDT Rm Integrity OVC-DO-0001 (CR Control Room Outside Press Fan Control Rm OAD-1) Supply VC 07-AOV Aux Bldg 767 Venliatiaon FF-56 X Various OAD-1)_ _ Supp_ yRm Control Rm OVCFL001)1 Control Room Filter Package Fan A VC 09-Fan Ann Bldg 767 Ventilation DD-54 XVarious OAPFT-1) Rm Control Rm X -controls 0YC-CH-00O5 Control Room Area Chiller-1 VC/YC 11,-Chilrr Ann Bldg 767 Ventilation FF-56 X upgrade Various (CRA-C-1)

Rm tMD5007391 0VCAHO001 Control Rm (CRA-AHU-1)

A TrainControl Room AHU-1 VC i0-AHU Aun Blg 767 Ventiltion EE-54 XVarious Rm McGuire Unit I SWEL.1 Equipment Walkdown Scope ATTACHMENT 2 5 of 6 ElClose of E Column. Listed an uor New( Prior IPEE.Equipment Decipin yte uldtna g y. Ro Grid IPEEE Replacement Discrepancy/

Safe~ty untion0-qipe LMI Eotulament Enhancssman CX -replaced 1EPO-BC-EDGA 1A EDG Battery Charger EPO l-Batte EDGBldg 736.5 IA DG R X (NSM-12482/

Varous (1EPQBCEDGA)

Charger/inverten EC75135)1EPO-BA-EDGA 1A EDG Battery (IEPQBAO24)

EPO 15-Batteny Rack EDG Bldg 736.5 IA EDG Rm x Various 1 -B ED- Battery Charger 1-Battery X -replaced I(EPQ-BE-EDBB EPO Chargerfinverter EDG Bldg 736.5 IB EDO Rm X (NSM-124821 Various (1EPBCEDGB)

C eEC75136)1EPO-BA-EDGB 1B EDG Battery (1EPQBA024)

EPO 15-Battery Rack EDG Bldg 736.5 16 EDG Rm X X -mrssing Vadous spacers 01-Motor Control IEPE-M[X-EMXE IDGIA 600 VAC MCC (IEMXE) EDG Centers/Wall EDG Bldg 736.5 IAEDORo c Various Mounted Co.ntactors 1ETB 4.16 kV Essential Power for EPC Metal Ctad SWgR Aux Bldg 733 706 AA-50 X Various 1ELX A4.10 KV/600 VAC 1-EPE-TF-ELXA TransforVer EPE 04-Tfansforrie Aux Bldg 750 803 AA-50 X Various 1 -EPE-TF-ELXC 4 1a nsfor VAC EPE 04-Transformer Aum Bldg 750 803 AA-50 X Various 1-EPE-TP-ELXB IELXB 4.16 KV/600 VAC EPE 04-Traisaormer Aux Bldg 733 705 AA-50 X Various P -T Transformer 01-Moor Control 1EMXA 600 VAC Essential MCC EPE Centers/Wat Mounted Aux Bldg 760 808 FF-55 X Varos Contactors 01-Motor Control 1EMXA-1 600 VAC Essential MCC EPE Centers/Wall Ass Bldg 750 W0 FF-55 I various Mounted Contactors 01-,Molor Control 1EMXB 600 VAC Essential MCC EPE Centers/Was Aux Bldg 733 722 FF-55 X X -contactC Mounted w/adjacent MCC Vaou Contactors 01-Motar Control 1EMXB-1 600 VAC Essential MCC EPE CentersWad Ass Bldg 733 722 FF-55 X X -contact Mounted wladjacent MCC Varous Contactors McGuire Unit 1 SWEL-1 Equipment Walkdown Scope ATTACHMENT 2 6 of 6 Class of Listed on t Mator New/ Prior IPEE Eoipe- e~rilinSystem Buidin Elov. Room# CoI"'n IPgE Relacement.

Discrepancy/

Safety Function Eaaomst# Declotn Gride JW EIlmtinm EnthancemnentI 1-IPE-CA-9010 SSPS Cabinet 'A' Output & Logic IIE 18-tnstrurnent conrol 767 Control Rm CC-54 X Various cabinet Rack Complex 1 -IPE-CA-9020 SSPS CablineV"'

Output & Logic IPE 1B-tnstnument Control 767 Conol Rot CC-54 X Varous cabinet R ck Complex 6EPt-BI-EVIA Vital Battery inverter EPG -Battery Control 733 701 CC-56 X X -reptaced Various____-______A_____taBattery

__verter ___ Cha er/inverter Complex IMG-12522) 1EPG-BI-EVIB Vital Battery Inverter EPG Chage-Bary Coptrol 733 701 CC-56 X XG-rp532) various 1EPG-BI-EVIC Vital Battery Inverter EPG 1 -Battery Cowo 733 701 CC-56 X XV- repied ChargerfInverter Complex (MG-22522)

Various EV-Batteia C Inot 733 701 CC-S6 X X -replaced Vaous 1EPG-BI-EVID Vital Battery Inverter EPG Charger/inverter Complerx (MG-22522) 02-Low Voltage 1EVDA Vital Panel 125VDC Breaker Panel EPG SWGR and Cotro] 733 701 CC-56 X Various Breaker Panels Compleex 024-ow Voltage 1EVDB vital Panel 125VDC Breaker Panel EPG SWGR and Control 733 701 CC-5S X Various Breaker Panels Complex 02-Low Voltage Control IEVDC Vital Panel 125VOC Breaker Panel EPG SWGR and Col 733 701 CC-56 X Various___________________________________________

Breaker Panels Complea 02-Low Voltage Contro 1 EVDD Vital Panel 125VDC Breaker Panel EPG SWGR and conpl 733 701 CC-56 X Various Breaker Panels plex 14-Distribulion EVDA 12o"VDC Distribution Center EPL Panels and Control 733 701 CC-66 X Vltous Automatic Complex Transfer Switches 14-Distribution EVDB 125VDC Distribution Center EPL Panels and Control 733 701 CC-56 X Various Automatic Complex Transler Switches X -replaced 0-EPL-BA-EVCA Vital Battery EPL 15-Battery Rack Control 733 707 CC-56 X (NSM-52483

/ Various Comptex EC._47__)X -replaced O-EPL-BA-EVCB Vital Battery EPL 16-Battery Rack Control 733 700 CC-56 X (NSM-52484/

Various Complex ____-____O

_____X -replaced O-EPL-BC-EVCA Vital Battery Charger EPL 16-Battery Control 733 70- CC-Spa X tNdM-524a81 Varous Charger/inverter Complex ,,_ 70 , EC-66972t

__S5281 __X. replaced 0-EPL-BC-EVCB Vital Battery Charger EPL 18-Bettap/

Control 733 701 CC-58 X (NSM-524891 Various Chargentlnvertar Complex IEC-66301)

Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal report for Seismic Walk-downs McGuire Unit 1 Rev. 1 ATTACHMENT 3 -McGuire Unit 1 SWEL-2 Base-2 List and Rapid Drain Down List Unit 1 SWEL-2 "Base List".: Class of Column.Equipment Description System C Elev. Room # C Function Equipmen Grid 05-Horizontal 1KFPU0001 1A KF Pump KF Pump Aux Bldg 750 816 PP-52 SFP Cooling 1KFPU0002 1B KF Pump KF 05-Horizontal Aux Bldg 750 816 PP-52 SFP Cooling Pump 1KFHX003 1A KF HtX KF 21-Tanks/HtXs Aux Bldg 750 816 PP-52 SFP Cooling 1KFHX004 lB KF HtX KF 21-Tanks/HtXs Aux Bldg 750 816 PP-52 SFP Cooling 1VAAH0030 1A KF Pump AHU VA 10-AHU Aux Bldg 750 816 PP-52 SFP Cooling 1VAAH0031 1B KF Pump AHU VA 10-AHU Aux Bldg 750 816 PP-52 SFP Cooling 03-Med Voltage 1ETA-13 1A KF Pump Breaker EPC Metal Clad Aux Bldg 750 803 AA-50 SFP Cooling SWGR I 03-Med Voltage 1ETB-13 1B KF Pump Breaker EPC Metal Clad Aux Bldg 733 705 AA-50 SFP Cooling SWGR 1RN-140A Asol RN 07-AOV Aux Bldg 750 816 PP-52 SFP Cooling 01-Motor Control 1 EMXA-F3D 1A KF Pump Motor AHU EPE Centers/Wall Aux Bldg 750 808 FF-55 SFP Cooling Motor Mounted Contactors 01-Motor Control 1EMXB-4C 1B KF Pump Motor AHU EPE Centers/Wall Aux Bldg 750 722 FF-55 SFP Cooling Motor Mounted Contactors 1 RN-240B 1B KF Pump Ess AHU Sup RN 07-AOV Aux Bldg 750 816 PP-52 SFP Cooling Isol Unit I SWEL-2 "Rapid Draindown List" Class of Column-Equipment

  1. Description System Bldg Elev. Room .u Function Eauipmen Grid SFP & Refueling 1 NV-842AC SBMUP Suction Isolation NV o8-MoviSov Rx Bldg 725 Annulus 273*/61 R C nent Cavity Inventory SBMUP Suction Pulsation 00-Other-1NVAC0048 Dampener (non-seismic NV (pulsation Rx Bldg 725 Annulus 320-/61 R N/A SSC) dampener)1 NVPU0046 SBMUP (non-seismic SSC) NV 05-Horizontal Rx Bldg 725 Annulus 320°/61 R N/A Pump SBMUP Discharge Pulsation 00-Other-1NVAC0049 Dampener (non-seismic NV (pulsation Rx Bldg 725 Annulus 320°/61 R N/A SSC) dampener)

I 1 NVFLOO47 SBMUP Discharge Filter NV 00- Other Rx Bldg 725 Annulus 320/61 R N/A (non-seismic SSC) I 1NV-849AC SBMUP Discharge Isolation NV 08-MOV/SOV Rx Bldg 725 Annulus 273°/61 R N/A Reactor Cavity Seal Refueling Reactor Cavity FW 00 -Other Rx Bldg n/a n/A n/a SFP & Refueling Seal Cavity Inventory 1 FW-8, -10, -25, -26, -46, Refuling Cavity Manual Drain FW 00 -Other RxBldg n/a n/A n/a SFP & Refueling-47,-76, -75 Valves II_ _ _Cavity Inventory Fuel Transfer Tube blind Fuel Transfer Tube Blind KF 00 -Other Rx Bldg nla n/A n/a SFP & Refueling flange Flange Cavity Inventory Fuel Transfer Tube Weir Fuel Transfer Tube Weir KF 00 -Other Rx Bldg nla n/A n/a SFP & Refueling Gate Gate Cavity Inventory Fukushima Near-Term Task Force (NTTF) Recommendation 2.3: NRC Submittal report for Seismic Walk-downs McGuire Unit 1 ATTACHMENT 4 McGuire Unit 1 SWEL-2 Rev. I Class of Column- Major New/Eguinment

  1. Description System BId Elev. Room Grid Replacement Function-Equipment SEP &X -actuator Rful 1NV-842AC SBMUP Suction Isolation NV 08-MOV/SOV Rx Bldg 725 Annulus 273°/61 R replacement Refueling Cavity (EC-99992)

Inventory SBMUP Suction Pulsation Dampener 00-Other-X -replaced 1NVAC0048 (non-seismic SSC) NV (pulsation Rx Bldg 725 Annulus 320°/61 R MGMM11916 N/A dampener) (EC 37849)05-Horizontal 1NVPU0046 SBMUP (non-seismic SSC) NV Pump Rx Bldg 725 Annulus 320°/61 R N/A Pump 05-Horizontal X -replaced 1 KFPU0001 1A KF Pump KF Pump Aux Bldg 750 816 PP-52 motor SFP Cooling EC105550 05-Horizontal 1KFPUO0O2 1B KF Pump KF Pump Aux Bldg 750 816 PP-52 SFP Cooling 1KFHX00O3 1A KF HtX KF 21-Tanks/HtXs Aux Bldg 750 816 PP-52 SFP Cooling 1KFHX0004 1B KF HtX KF 21-Tanks/HtXs Aux Bldg 750 816 PP-52 SFP Cooling 1VAAH0031 1B KF PumpAAHU VA 10-AHU AuxBldg 750 816 QQ-52 SFP Cooling

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