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{{Adams
{{Adams
| number = ML18012A594
| number = ML18194A902
| issue date = 01/12/2018
| issue date = 07/10/2018
| title = Braidwood Station, Units 1 and 2 - Notification of NRC Triennial Fire Protection Baseline Inspection and Request for Information; Inspection Report 05000456/2018013; 05000457/2018013 (Drs-A.Shaikh)
| title = NRC Triennial Fire Protection Inspection Report 05000456/2018013; 05000457/2018013 (DRS-A. Shaikh)
| author name = Shaikh A A
| author name = Daley R
| author affiliation = NRC/RGN-III/DRS
| author affiliation = NRC/RGN-III/DRS/EB3
| addressee name = Hanson B C
| addressee name = Hanson B
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear
| docket = 05000456, 05000457
| docket = 05000456, 05000457
Line 12: Line 12:
| document report number = IR 2018013
| document report number = IR 2018013
| document type = Inspection Report, Letter
| document type = Inspection Report, Letter
| page count = 9
| page count = 7
}}
}}


Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:
{{#Wiki_filter:uly 10, 2018
[[Issue date::January 12, 2018]]


Mr. Bryan Senior VP, Exelon Generation Company, LLC President and CNO, Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
==SUBJECT:==
BRAIDWOOD NUCLEAR GENERATING STATION, UNITS 1 AND 2NRC TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000456/2018013; 05000457/2018013


SUBJECT: BRAIDWOOD STATION, UNITS 1 AND 2NOTIFICATION OF NRC TRIENNIAL FIRE PROTECTION BASELINE INSPECTION AND REQUEST FOR INFORMATION; INSPECTION REPORT 05000456/2018013; 05000457/2018013
==Dear Mr. Hanson:==
On June 8, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a Triennial Fire Protection inspection at your Braidwood Nuclear Generating Station, Units 1 and 2. The NRC inspectors discussed the results of this inspection with Mrs. A. Ferko and other members of your staff. The results of this inspection are documented in the enclosed report.
 
Based on the results of this inspection, NRC inspectors did not identify any findings or violations of more than minor significance.
 
This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
 
Sincerely,
/RA/
Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Enclosure:
IR 05000456/2018013; 05000457/2018013 cc: Distribution via LISTSERV
 
Letter to Bryan
 
=SUMMARY=
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a Triennial Fire Protection at Braidwood Nuclear Generating Station in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC and self-revealed findings, violations, and additional items are summarized in the table below.
 
Licensee-identified non-cited violations are documented under inspection results.
 
List of Findings and Violations No findings or violations were identified Additional Tracking Items None
 
=INSPECTION SCOPES=
 
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2515, Light-Water Reactor Inspection Program -
Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.
 
==REACTOR SAFETY==
 
===71111.05TFire Protection(Triennial)
The inspectors evaluated the following from May 7, 2018, through June 8, 2018.
 
Fire Protection Inspection Requirements ===
{{IP sample|IP=IP 71111.05|count=3}}
The inspectors evaluated Fire Protection Program implementation in the following selected areas:
: (1) Fire Area 11.4C-0, Radwaste and Remote Shutdown Control Panel Room
: (2) Fire Area 5.2-1, Division 11 Engineered Safety Feature Switchgear Room
: (3) Fire Area 5.2-2, Division 21 Engineered Safety Feature Switchgear Room
 
===B.5.b Inspection Activities (2 Samples)===
The inspectors evaluated feasibility of the following B.5.b Mitigating Strategies:
: (1) Makeup to Refueling Water Storage Tank
: (2) Spent Fuel Pool SprayExternal Strategy
 
==INSPECTION RESULTS==
71111.05TFire Protection(Triennial) No findings or violations were identified


==Dear Mr. Hanson:==
==EXIT MEETINGS AND DEBRIEFS==
On May 7, 2018, the U.S. Nuclear Regulatory Commission (NRC) will begin a Triennial Fire Protection Baseline Inspection at your Braidwood Station, Units 1 and 2. This inspection will be performed in accordance with Inspection Procedure (IP) 71111.05T Baseline Fire Protection IP. Changes were made to the IP 71111.05T which now requires the fire protection inspection to review your actions to mitigate postulated events that could potentially cause loss of large areas of power reactor facilities due to explosions or fires. This requirement was implemented by the issuance of the Interim Compensatory Measures Order EA-02-026, Section B.5.b, and the subsequent requirements of Title 10 of the Code of Federal Regulations (CFR), Part 50.54(hh)(2), which are collectively referred to as B.5.b requirements. During this inspection, the B.5.b requirements review will be performed during the first onsite week of the inspection starting on March 5, 2018. The schedule for the onsite inspection activity is as follows: Information Gathering Visit: May 78, 2018; B.5.b Requirements: May 911, 2018; and Fire Protection Inspection: May 2125, 2018; and June 48, 2018 The purpose of the information gathering visit is: (1) to obtain information and documentation needed to support the inspection; (2) to become familiar with the Braidwood Station Fire Protection Programs, fire protection features, post-fire safe shutdown capabilities, and plant layout; and (3) to arrange administrative details, such as office space, availability of knowledgeable office personnel and to ensure unescorted site access privileges. Experience has shown that the Baseline Fire Protection Inspections are extremely resource intensive both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both organizations, we have enclosed a request for documents needed for the inspection. These documents have been divided into four groups. The first group lists information necessary to aid the inspection team in choosing specific focus areas for the inspection. It is requested that this information be provided to the lead inspector via mail or electronically no later than March 30, 2018. The second group also lists information and areas for discussion necessary to aid the inspection team in choosing specific fire protection focus areas for the inspection and to ensure that the inspection team is adequately prepared for the inspection. It is requested this information be available during the information gathering visit on May 7, 2018. The third group of requested documents consists of those items that the team will review, or need access to, during the inspection. Please have this information available by the first day of the second onsite inspection week beginning May 21, 2018. The fourth group lists the information necessary to aid the inspection team in tracking issues identified as a result of the inspection. It is requested that this information be provided to the lead inspector as the information is generated during the inspection. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection. The lead inspector for this inspection is Mr. Atif Shaikh. We understand that our regulatory contact for this inspection is Mr. Richard Schliessmann of your organization. If there are any questions about the inspection or the material requested, please contact the lead inspector at 630-829-9824 or via e-mail at Atif.Shaikh@nrc.gov. This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, Control Number 3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid Office of Management and Budget Control Number. This letter and its enclosure will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR
The inspectors confirmed that proprietary information was controlled to protect from public disclosure. No proprietary information was documented in this report.
* On June 8, 2018 the inspectors presented the Triennial Fire Protection inspection results to Mrs. A. Ferko and other members of the licensee staff.


Sincerely,/RA/ Atif A. Shaikh, Senior Reactor Inspector Engineering Branch 3 Division of Reactor Safety Docket Nos. 50456; 50457 License Nos. NPF72; NPF77
=DOCUMENTS REVIEWED=


===Enclosure:===
- BRW-97-0339-M; Braidwood Control Room Heat Up Evaluation; Revision 3
Document Request for Fire Protection Inspection cc: Distribution via LISTSERV
- BRW-11-0119E; Multiple Spurious Operation Technical Evaluation; Revision 1
- IR 04140755; 2018 NRC FP Triennial InspectionFPR References Update; 05/24/2018
- IR 00235431; Consider Testing of Remote Shutdown Panel Switches; 07/12/2004
- IR 00241151; Need ECR for Reset Point for 1/2PSL-IA009; 08/03/2004
- IR 02597947; NOS ID: Implementation of Testing for RSP Components; 12/09/2015
- IR 04038523; Box 8 On 2PMO5J Will Not Test; 08/02/2017
- AR 02499179; The Installed Relay has the Wrong Coil Voltage Rating; 05/11/2015
- AR 02512046; FP Zone 2D-36 Locked in Alarm; 06/09/2015
- AR 02548227; Recurrence of Spurious Alarm in Zone 1D-67; 08/29/2015
- 0BwOA PRI-5; Control Room Inaccessibility Unit 0; Revision 101
- 0BwOS PL-R2; Remote Shutdown Panel Control Switch Functional Check (PW Pumps);
Revision 0
- 1BwOA PRI-5; Control Room Inaccessibility Unit 1; Revision 109
- 1BwOS PL-R2-AB; Remote Shutdown Panel Control Switch Functional Check (AB XFER
Pump); Revision 0
- 1BwOS PL-R2-CC; Remote Shutdown Panel Control Switch Functional Check (CC Pumps);
Revision 0
- 1BwOS PL-R2-CV.1; Remote Shutdown Panel Control Switch Functional Check (CV Pumps);
Revision 1
- 1BwOS PL-R2-MS.2; Remote Shutdown Panel Control Switch Functional Check (PORVs);
Revision 0
- 1BwOS PL-R2-RY; Remote Shutdown Panel Control Switch Functional Check (RY Heaters);
Revision 0
- 1BwOS PL-R2-SX; Remote Shutdown Panel Control Switch Functional Check (SX Pumps);
Revision 0
- 1BwOSR 5.5.8.AF-2A; Unit One Train A Auxiliary Feedwater Valves Indication Test
Surveillance; Revision 17
- 2BwOA PRI-5; Control Room Inaccessibility Unit 2; Revision 106
- 2BwOS PL-R2-AB; Remote Shutdown Panel Control Switch Functional Check (AB XFER
Pump); Revision 0
- 2BwOS PL-R2-CC; Remote Shutdown Panel Control Switch Functional Check (CC Pumps);
Revision 0
- 2BwOS PL-R2-CV.1; Remote Shutdown Panel Control Switch Functional Check (CV Pumps);
Revision 0
- 2BwOS PL-R2-MS.2; Remote Shutdown Panel Control Switch Functional Check (PORVs);
Revision 0
- 2BwOS PL-R2-RY; Remote Shutdown Panel Control Switch Functional Check (RY Heaters);
Revision 0
- 2BwOS PL-R2-SX; Remote Shutdown Panel Control Switch Functional Check (SX Pumps);
Revision 0
- 2BwOSR 5.5.8.AF-2B; Unit Two Train B Auxiliary Feedwater Valves Indication Test
Surveillance; Revision 17
- BwOP VC-1; Shutdown of Control Room HVAC System; Revision 11
- BwOP VC-2; Startup of Control Room HVAC System; Revision 14
- BwOP VP-5; Reactor Containment Fan Cooler Start-Up; Revision 58
- BwOP VP-6; Reactor Containment Fan Cooler Shutdown; Revision 57
- BwAR 0-37-A4; Alarm No: 0-37-A4; Revision 16
- EDMG 4; External Spent Fuel Pool Spray Strategy; Revision 3
- EDMG 1; Extensive Damage Mitigation Guideline; Revision 8
- 00455864 01; Unit 1 1PSL-IA009 Remote Shutdown Control Panel IA Header Pressure
Switch; 08/23/2004
- 01044558 01; Unit 1 1PSL-IA009 Remote Shutdown Control Panel IA Header Pressure
Switch; 01/09/2009
- 01504332 01; Unit 1 1PSL-IA009 Remote Shutdown Control Panel IA Header Pressure
Switch; 08/06/2014
- 01741169 01; Unit 2 Remote Shutdown Panel Control Power Check; 10/21/2015
- 01824974 01; Unit 1 Remote Shutdown Panel Control Power Check; 10/24/2016
- 01872317 01; Unit 2 Remote Shutdown Panel Control Power Check; 05/18/2017
- 04680419; Unit 2 Remote Shutdown Panel Control Power Check (PMID/RQ 54750-01; Partial
Performance To Verify Box 8 Annunciator Window Lights); 08/02/2017
- 04711799 01; Unit 0 Operations Abnormal Procedures Local Equipment Check Quarterly
Surveillance; 02/09/2018
- 04756762 01; Unit 1 Remote Shutdown Instrumentation Monthly Surveillance; 04/06/2018
- 04756766 01; Unit 2 Remote Shutdown Instrumentation Monthly Surveillance; 04/13/2018
- 20E-0-3672; Cable Pans Routing Aux Building; Revision K
- 20E-0-3361 CT1; Conduit Tabulation Aux Building; Revision AD
- 20E-0-3361; Electrical Installation Aux. Building; Revision DK
- 20E-1-4111D; External Wiring Diagram, Process I & C Rack Channel 4; Revision Y
- 20E-1-4108E; Internal/External Wiring Diagram, Safety Valve Room; Revision 1
- 20E-1-4086; Elevation, Remote Shutdown Panel; Revision W
- 20E-1-4006A; Key Diagram, 4160V ESF SWGR Bus 141; Revision 1
- 20E-1-4610A; Elevation, 4160V SWGR Bus 141; Revision 1
- 20E-1-4007A; Key Diagram, 480V ESF Substation Bus 131X; Revision M
- 20E-2-4006A; Key Diagram, 4160V ESF SWGR Bus 241; Revision F
- 20E-2-4610A; Elevation, 4160V SWGR Bus 241; Revision G
- 20E-2-4007A; Key Diagram 480V ESF Substation Bus 231X; Revision K
5
}}
}}

Latest revision as of 19:52, 18 December 2019

NRC Triennial Fire Protection Inspection Report 05000456/2018013; 05000457/2018013 (DRS-A. Shaikh)
ML18194A902
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 07/10/2018
From: Robert Daley
Engineering Branch 3
To: Bryan Hanson
Exelon Generation Co, Exelon Nuclear
References
IR 2018013
Download: ML18194A902 (7)
v • d • e


Text

uly 10, 2018

SUBJECT:

BRAIDWOOD NUCLEAR GENERATING STATION, UNITS 1 AND 2NRC TRIENNIAL FIRE PROTECTION INSPECTION REPORT 05000456/2018013; 05000457/2018013

Dear Mr. Hanson:

On June 8, 2018, the U.S. Nuclear Regulatory Commission (NRC) completed a Triennial Fire Protection inspection at your Braidwood Nuclear Generating Station, Units 1 and 2. The NRC inspectors discussed the results of this inspection with Mrs. A. Ferko and other members of your staff. The results of this inspection are documented in the enclosed report.

Based on the results of this inspection, NRC inspectors did not identify any findings or violations of more than minor significance.

This letter, its enclosure, and your response (if any) will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely,

/RA/

Robert C. Daley, Chief Engineering Branch 3 Division of Reactor Safety Docket Nos. 50-456; 50-457 License Nos. NPF-72; NPF-77 Enclosure:

IR 05000456/2018013; 05000457/2018013 cc: Distribution via LISTSERV

Letter to Bryan

SUMMARY

The U.S. Nuclear Regulatory Commission (NRC) continued monitoring licensees performance by conducting a Triennial Fire Protection at Braidwood Nuclear Generating Station in accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs program for overseeing the safe operation of commercial nuclear power reactors. Refer to https://www.nrc.gov/reactors/operating/oversight.html for more information. NRC and self-revealed findings, violations, and additional items are summarized in the table below.

Licensee-identified non-cited violations are documented under inspection results.

List of Findings and Violations No findings or violations were identified Additional Tracking Items None

INSPECTION SCOPES

Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with their attached revision histories are located on the public website at http://www.nrc.gov/reading-rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared complete when the IP requirements most appropriate to the inspection activity were met consistent with Inspection Manual Chapter 2515, Light-Water Reactor Inspection Program -

Operations Phase. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel to assess licensee performance and compliance with Commission rules and regulations, license conditions, site procedures, and standards.

REACTOR SAFETY

===71111.05TFire Protection(Triennial)

The inspectors evaluated the following from May 7, 2018, through June 8, 2018.

Fire Protection Inspection Requirements ===

Main article: IP 71111.05

The inspectors evaluated Fire Protection Program implementation in the following selected areas:

(1) Fire Area 11.4C-0, Radwaste and Remote Shutdown Control Panel Room
(2) Fire Area 5.2-1, Division 11 Engineered Safety Feature Switchgear Room
(3) Fire Area 5.2-2, Division 21 Engineered Safety Feature Switchgear Room

B.5.b Inspection Activities (2 Samples)

The inspectors evaluated feasibility of the following B.5.b Mitigating Strategies:

(1) Makeup to Refueling Water Storage Tank
(2) Spent Fuel Pool SprayExternal Strategy

INSPECTION RESULTS

71111.05TFire Protection(Triennial) No findings or violations were identified

EXIT MEETINGS AND DEBRIEFS

The inspectors confirmed that proprietary information was controlled to protect from public disclosure. No proprietary information was documented in this report.

  • On June 8, 2018 the inspectors presented the Triennial Fire Protection inspection results to Mrs. A. Ferko and other members of the licensee staff.

DOCUMENTS REVIEWED

- BRW-97-0339-M; Braidwood Control Room Heat Up Evaluation; Revision 3

- BRW-11-0119E; Multiple Spurious Operation Technical Evaluation; Revision 1

- IR 04140755; 2018 NRC FP Triennial InspectionFPR References Update; 05/24/2018

- IR 00235431; Consider Testing of Remote Shutdown Panel Switches; 07/12/2004

- IR 00241151; Need ECR for Reset Point for 1/2PSL-IA009; 08/03/2004

- IR 02597947; NOS ID: Implementation of Testing for RSP Components; 12/09/2015

- IR 04038523; Box 8 On 2PMO5J Will Not Test; 08/02/2017

- AR 02499179; The Installed Relay has the Wrong Coil Voltage Rating; 05/11/2015

- AR 02512046; FP Zone 2D-36 Locked in Alarm; 06/09/2015

- AR 02548227; Recurrence of Spurious Alarm in Zone 1D-67; 08/29/2015

- 0BwOA PRI-5; Control Room Inaccessibility Unit 0; Revision 101

- 0BwOS PL-R2; Remote Shutdown Panel Control Switch Functional Check (PW Pumps);

Revision 0

- 1BwOA PRI-5; Control Room Inaccessibility Unit 1; Revision 109

- 1BwOS PL-R2-AB; Remote Shutdown Panel Control Switch Functional Check (AB XFER

Pump); Revision 0

- 1BwOS PL-R2-CC; Remote Shutdown Panel Control Switch Functional Check (CC Pumps);

Revision 0

- 1BwOS PL-R2-CV.1; Remote Shutdown Panel Control Switch Functional Check (CV Pumps);

Revision 1

- 1BwOS PL-R2-MS.2; Remote Shutdown Panel Control Switch Functional Check (PORVs);

Revision 0

- 1BwOS PL-R2-RY; Remote Shutdown Panel Control Switch Functional Check (RY Heaters);

Revision 0

- 1BwOS PL-R2-SX; Remote Shutdown Panel Control Switch Functional Check (SX Pumps);

Revision 0

- 1BwOSR 5.5.8.AF-2A; Unit One Train A Auxiliary Feedwater Valves Indication Test

Surveillance; Revision 17

- 2BwOA PRI-5; Control Room Inaccessibility Unit 2; Revision 106

- 2BwOS PL-R2-AB; Remote Shutdown Panel Control Switch Functional Check (AB XFER

Pump); Revision 0

- 2BwOS PL-R2-CC; Remote Shutdown Panel Control Switch Functional Check (CC Pumps);

Revision 0

- 2BwOS PL-R2-CV.1; Remote Shutdown Panel Control Switch Functional Check (CV Pumps);

Revision 0

- 2BwOS PL-R2-MS.2; Remote Shutdown Panel Control Switch Functional Check (PORVs);

Revision 0

- 2BwOS PL-R2-RY; Remote Shutdown Panel Control Switch Functional Check (RY Heaters);

Revision 0

- 2BwOS PL-R2-SX; Remote Shutdown Panel Control Switch Functional Check (SX Pumps);

Revision 0

- 2BwOSR 5.5.8.AF-2B; Unit Two Train B Auxiliary Feedwater Valves Indication Test

Surveillance; Revision 17

- BwOP VC-1; Shutdown of Control Room HVAC System; Revision 11

- BwOP VC-2; Startup of Control Room HVAC System; Revision 14

- BwOP VP-5; Reactor Containment Fan Cooler Start-Up; Revision 58

- BwOP VP-6; Reactor Containment Fan Cooler Shutdown; Revision 57

- BwAR 0-37-A4; Alarm No: 0-37-A4; Revision 16

- EDMG 4; External Spent Fuel Pool Spray Strategy; Revision 3

- EDMG 1; Extensive Damage Mitigation Guideline; Revision 8

- 00455864 01; Unit 1 1PSL-IA009 Remote Shutdown Control Panel IA Header Pressure

Switch; 08/23/2004

- 01044558 01; Unit 1 1PSL-IA009 Remote Shutdown Control Panel IA Header Pressure

Switch; 01/09/2009

- 01504332 01; Unit 1 1PSL-IA009 Remote Shutdown Control Panel IA Header Pressure

Switch; 08/06/2014

- 01741169 01; Unit 2 Remote Shutdown Panel Control Power Check; 10/21/2015

- 01824974 01; Unit 1 Remote Shutdown Panel Control Power Check; 10/24/2016

- 01872317 01; Unit 2 Remote Shutdown Panel Control Power Check; 05/18/2017

- 04680419; Unit 2 Remote Shutdown Panel Control Power Check (PMID/RQ 54750-01; Partial

Performance To Verify Box 8 Annunciator Window Lights); 08/02/2017

- 04711799 01; Unit 0 Operations Abnormal Procedures Local Equipment Check Quarterly

Surveillance; 02/09/2018

- 04756762 01; Unit 1 Remote Shutdown Instrumentation Monthly Surveillance; 04/06/2018

- 04756766 01; Unit 2 Remote Shutdown Instrumentation Monthly Surveillance; 04/13/2018

- 20E-0-3672; Cable Pans Routing Aux Building; Revision K

- 20E-0-3361 CT1; Conduit Tabulation Aux Building; Revision AD

- 20E-0-3361; Electrical Installation Aux. Building; Revision DK

- 20E-1-4111D; External Wiring Diagram, Process I & C Rack Channel 4; Revision Y

- 20E-1-4108E; Internal/External Wiring Diagram, Safety Valve Room; Revision 1

- 20E-1-4086; Elevation, Remote Shutdown Panel; Revision W

- 20E-1-4006A; Key Diagram, 4160V ESF SWGR Bus 141; Revision 1

- 20E-1-4610A; Elevation, 4160V SWGR Bus 141; Revision 1

- 20E-1-4007A; Key Diagram, 480V ESF Substation Bus 131X; Revision M

- 20E-2-4006A; Key Diagram, 4160V ESF SWGR Bus 241; Revision F

- 20E-2-4610A; Elevation, 4160V SWGR Bus 241; Revision G

- 20E-2-4007A; Key Diagram 480V ESF Substation Bus 231X; Revision K

5

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