ML12333A277
| ML12333A277 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/16/2012 |
| From: | Patel D Entergy Nuclear Operations |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML123330366 | List: |
| References | |
| W3F1-2012-0100 WF3-CS-12-00003 | |
| Download: ML12333A277 (76) | |
Text
ENCLOSURE to W3F1-2012-0100 WATERFORD 3 SEISMIC WALKDOWN REPORT
Engineering Report No.
\\VF3-CS-12-t)Ot)03 Rev 0
Page 1
of 35 ENTERGY NUCLEAR Engineering Report Cover Sheet Engineering Report
Title:
Waterford Steam Electric Station Unit 3 Seismic VaIkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic EC No. 40510 Engineering Report Type:
Cancelled E
Superseded Superseded by:
Applicable Site(s)
Report Origin:
Entergy Vendor Vendor Document No.:
N/A No Prepared by:
Reviewed by:
Re e ed b\\:
Approved by:
Approved by:
Dinesh Patel 7 - -
7 (
Brian Pace Peer Review Team Leader (Benamin Koshab)
Desien aanaeer Robert Porter>
Design Supervisor Mark Adarns Date:
11-16-2012 Date:
11-16-2012 Date:
I I162012 Date:
Date:
New Revision LI LI IP1 LI 1P2 LI 1P3 LI JAF Li PNPS LI vy LI wo LI ANO1 LI ANO2 LI ECH LI GGNS LI RBS LI WF3 PLP LI Quality-Related:
LI Yes
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 2 of 35 Waterford Steam Electric Station Unit 3 Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic TABLE OF CONTENTS Section Title Page 1.0 SCOPE AND OBJECTIVE......................................................................................................................... 3 2.0 SEISMIC LICENSING BASIS
SUMMARY
................................................................................................ 4 2.1 SAFE SHUTDOWN EARTHQUAKE (SSE)............................................................................................ 4 2.2 DESIGN CODES, STANDARDS, AND METHODS................................................................................ 4 3.0 SEISMIC WALKDOWN PROGRAM IMPLEMENTATION APPROACH.................................................. 8 4.0 PERSONNEL QUALIFICATIONS............................................................................................................. 9 4.1 EQUIPMENT SELECTION PERSONNEL............................................................................................ 12 4.2 SEISMIC WALKDOWN ENGINEERS................................................................................................... 12 4.3 LICENSING BASIS REVIEWERS......................................................................................................... 12 4.4 IPEEE REVIEWERS............................................................................................................................. 12 4.5 PEER REVIEW TEAM.......................................................................................................................... 13 5.0 IPEEE VULNERABILITIES REPORTING............................................................................................... 15 6.0 SEISMIC WALKDOWN EQUIPMENT LIST DEVELOPMENT............................................................... 16 6.1 SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY FUNCTIONS........................................... 16 6.2 SPENT FUEL POOL ITEMS................................................................................................................. 19 6.3 DEFERRED INACCESSIBLE ITEMS on SWEL................................................................................... 20 7.0 SEISMIC WALKDOWNS AND AREA WALK-BYS................................................................................ 23 7.1 SEISMIC WALKDOWNS....................................................................................................................... 23 7.2 AREA WALK-BYS................................................................................................................................. 24 8.0 LICENSING BASIS EVALUATIONS....................................................................................................... 26 CONDITON IDENTIFICATION......................................................................................................................... 26 CONDITION RESOLUTION............................................................................................................................. 26 8.1 Licensing Basis Evaluation.................................................................................................................... 27 8.2 Corrective Action Program Entries........................................................................................................ 27 8.3 Plant Changes....................................................................................................................................... 28 9.0 PEER REVIEW........................................................................................................................................ 29 9.1 PEER REVIEW PROCESS................................................................................................................... 29 9.2 PEER REVIEW RESULTS
SUMMARY
................................................................................................ 29
10.0 REFERENCES
......................................................................................................................................... 34 11.0 ATTACHMENTS...................................................................................................................................... 35 ATTACHMENT A - IPEEE VULNERABILITIES TABLE.................................................................................. 36 ATTACHMENT B - SEISMIC WALKDOWN EQUIPMENT LISTS................................................................... 38 ATTACHMENT C - SEISMIC WALKDOWN CHECKLISTS (SWCs)............................................................... 76 ATTACHMENT D - AREA WALK-BY CHECKLISTS (AWCs)....................................................................... 592 ATTACHMENT E - POTENTIALLY ADVERSE SEISMIC CONDITIONS..................................................... 802 ATTACHMENT F - LICENSING BASIS EVALUATION FORMS................................................................... 809 ATTACHMENT G - PEER REVIEW CHECKLIST FOR SWEL..................................................................... 817 ATTACHMENT H - PEER REVIEW COMMENT FORM............................................................................... 821 ATTACHMENT J - SEISMIC WALKDOWN ENGINEER TRAINING CERTIFICATES.................................. 835
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 3 of 35 1.0 SCOPE AND OBJECTIVE The Great Tohoku Earthquake of March 11, 2011 and the resulting tsunami caused an accident at the Fukushima Dai-ichi nuclear power plant in Japan. In response to this accident, the Nuclear Regulatory Commission (NRC) established the Near-Term Task Force (NTTF). The NTTF was tasked with conducting a systematic and methodical review of NRC processes and regulations and determining if the agency should make additional improvements to its regulatory system. On March 12, 2012 the NRC issued a 10CFR50.54(f)
Letter [Ref. 1], which requested information from all licensees to support the NRC staffs evaluation of several of the NTTF recommendations. To support NTTF Recommendation 2.3, Enclosure 3 to the 50.54(f) Letter requested that all licensees perform seismic walkdowns to gather and report information from the plant related to degraded, non-conforming, or unanalyzed conditions with respect to its current seismic licensing basis.
The Electric Power Research Institute (EPRI), with support and direction from the Nuclear Energy Institute (NEI), published industry guidance for conducting and documenting the seismic walkdowns which represented the results of extensive interaction between NRC, NEI, and other stakeholders. This industry guidance document, EPRI Report 1025286 [Ref. 2],
hereafter referred to as the Guidance, was formally endorsed by the NRC on May 31, 2012.
Entergy Waterford Steam Electric Station Unit 3 has committed to using this NRC-endorsed guidance as the basis for conducting and documenting seismic walkdowns for resolution of NTTF Recommendation 2.3: Seismic.
The objective of this report is to document the results of the seismic walkdown effort undertaken for resolution of NTTF Recommendation 2.3: Seismic in accordance with the Guidance, and provide the information necessary for responding to Enclosure 3 to the 50.54(f).
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 4 of 35 2.0 SEISMIC LICENSING BASIS
SUMMARY
Waterford Steam Electric Station Unit 3 (WSES-3) is located on the west (right descending) bank of the Mississippi River in St. Charles Parish, near the town of Taft, Louisiana. The Nuclear Steam Supply System (NSSS) is a pressurized water reactor (PWR) designed by Combustion Engineering Incorporated. The WSES-3 Facility Operating License was issued on March 16, 1985, and is currently rated at 3716 MWt power [Ref. 3]. This section summarizes the seismic licensing basis of structures, systems and components (SSCs) at WSES-3 which bound the context of the NTTF 2.3 Seismic Walkdown program.
2.1 SAFE SHUTDOWN EARTHQUAKE (SSE)
The selection of the SSE is based on a hypothetical earthquake with an epicentral intensity of VI MM occurring adjacent to the site. According to the most recent and acceptable intensity-acceleration relationship by Trifunac-Brady the intensity VI MM corresponds to a horizontal surface acceleration of 0.06g. In order to comply with the minimum accepted acceleration as stipulated by 10CFR100, Appendix A, WSES-3 was designed for a maximum horizontal ground surface acceleration of 0.10g. This very conservative surface acceleration is double the maximum acceleration appropriate for the maximum earthquake which has occurred in the sites tectonic province during the past 250 years. The peak vertical acceleration for the postulated SSE is 2/3 peak horizontal acceleration or 0.067g.
2.2 DESIGN CODES, STANDARDS, AND METHODS Principle structures, systems, and components (SSCs) which may either serve to prevent accidents or to mitigate their consequences are designed and are erected in accordance with applicable codes to withstand any deleterious natural phenomena which could be reasonably assumed to occur at the site during the lifetime of the plant. Redundancy is provided in the reactor protective and safety feature systems so that no single failure of an active component of the system would prevent action necessary to avoid an unsafe condition.
Seismic Category I defines SSCs as those components (1) whose failure could cause uncontrolled release of radioactivity, (2) that are essential for safe reactor shutdown and the immediate and long-term operation following a Design Basis Accident, or (3) that are essential for a safe and orderly shutdown of the Nuclear Steam Supply System.
Response Spectra The design response spectra used in the plant design differ from the design response spectra recommended in NRC Regulatory Guide 1.60, Design Response Spectra for Seismic Design of Nuclear Power Plants, Revision 1 December 1973. The regulatory guide response spectra have slightly higher values in general. Use of Regulatory Guide 1.60 permits utilization of
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 5 of 35 damping values indicated in Regulatory Guide 1.61, Damping Values for Seismic Design of Nuclear Power Plants, October 1973. These damping values are equal or greater than the values utilized for WSES-3 plant design. By utilizing lower damping values in the WSES-3 design, as compared to the damping values of Regulatory Guide 1.61, the analysis and design of WSES-3 compensates for any differences.
Structures The seismic Category I structures consist of the following:
a) Reactor Building (comprising a free standing steel containment vessel, a containment internal structure and a reinforced concrete Shield).
b) Reactor Auxiliary Building c) Fuel Handling Building d) Component Cooling Water System Structure Subsystems and Their Supports The following list comes from WSES-FSAR-UNIT-3 Table 3.2-1. All systems that have components classified as Seismic Category I will be listed here. For a more detailed version of specific components classified as Seismic Category I, see Table 3.2-1.
Reactor Coolant System Safety Injection System Shutdown Cooling System Refueling Water Level Indicating System Chemical and Volume Control System Containment Spray System Waste Management System Component Cooling Water System Sampling System Containment Cooling System Essential Services Chilled Water System Fuel Handling System Spent Fuel Pool System Main Steam and Feedwater System Emergency Feedwater System Compressed Air Systems Containment Isolation System Emergency Diesel Generator System Control Room Air Conditioning System RAB Cable Vault and Switchgear Areas Ventilation System
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 6 of 35 RAB H&V Equipment Room Ventilation System FHB Ventilation System Containment Atmospheric Release System Shield Building Ventilation System Controlled Ventilation Area System Reactor Cavity Cooling System Miscellaneous HVAC Equipment Combustible Gas Control Containment Vacuum Relief Actuation System Containment Pressure Indication System Containment Water Level Indication System Electrical Systems and Equipment Radiation Monitoring Accident Radiation Monitors Inadequate Core Cooling Instrumentation Miscellaneous Codes and Industry Standards Seismic Class I structures are generally proportioned to maintain elastic behavior when subjected to various combinations of dead loads, thermal loads, accident loads, seismic and tornado loads.
Safety-related structural steel is designed in accordance with American Institute of Steel Construction (AISC), Manual of Steel Construction, 7th Edition.
Safety-related concrete is designed in accordance with American Concrete Institute (ACI-308-63), Building Code Requirements for Reinforced Concrete with the exception that ACI 318-71 is used for design of reinforcing steel splices.
Safety-related welds are designed in accordance with American Welding Society (AWS)
D1.1-72, AWS Structural Welding Steel.
IEEE-323-1971, General Guide for Type Test of Class I Electric Equipment for Nuclear Power Generating Stations.
IEEE Standard 344-1971, IEEE Recommended Practice for Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations, was used in qualifying electrical equipment. Some equipment was qualified in accordance with IEEE 344-1975.
Piping systems, pumps, valves, heat exchangers and pressure vessels are designed to the following codes and industrial standards. Note that various pieces of equipment were
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 7 of 35 designed by different code years at WSES-3. Items were purchased to code years and addenda as specified in WSES-3 specifications ASME Boiler and Pressure Vessel Code,Section II, "Material Specifications, including the latest published addenda in force on the date of purchase and /or design.
ASME Boiler and Pressure Vessel Code,Section III, "Nuclear Vessels, including the latest published addenda in force on the date of purchase and/or design.
ASME Boiler and Pressure Vessel Code,Section VIII, "Unfired Pressure Vessels,"
including the latest published addenda in force on the date of purchase and/or design.
ASME Boiler and Pressure Vessel Code,Section IX, "Welding Qualifications ANSI B31.1.0-1967, Power Piping Code ANSI B31.7-1969, Nuclear Piping Code ASTM A36, Structural Steel
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 8 of 35 3.0 SEISMIC WALKDOWN PROGRAM IMPLEMENTATION APPROACH Entergy WSES-3 has committed to conduct and document seismic walkdowns for resolution of NTTF Recommendation 2.3: Seismic in accordance with the EPRI Seismic Walkdown Guidance [Ref. 2]. The approach provided in the Guidance for addressing the actions and information requested in Enclosure 3 to the 50.54(f) Letter includes the following activities, the results of which are presented in the sections shown in parenthesis:
Assignment of appropriately qualified personnel (Section 4.0)
Reporting of actions taken to reduce or eliminate the seismic vulnerabilities identified by the Individual Plant Examination of External Events (IPEEE) program (Section 5.0)
Selection of SSCs to be evaluated (Section 6.0)
Performance of the seismic walkdowns and area walk-bys (Section 7.0)
Evaluation and treatment of potentially adverse seismic conditions with respect to the seismic licensing basis of the plant (Section 8.0)
Performance of peer reviews (Section 9.0)
The coordination and conduct of these activities was initiated and tracked by Entergy corporate leadership, which provided guidance to each Entergy site throughout the seismic walkdown program, including WSES-3. Entergy contracted with an outside nuclear services company to provide engineering and project management resources to supplement and assist each individual site. Each site had dedicated engineering contractors, supported by their own project management and technical oversight, who worked closely with plant personnel.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 9 of 35 4.0 PERSONNEL QUALIFICATIONS The NTTF 2.3 Seismic Walkdown program involved the participation of numerous personnel with various responsibilities. This section identifies the project team members and their project responsibilities, and provides brief experience summaries for each. For organizational purposes, personnel are presented as being primarily involved with either the walkdown effort or the peer review. Training certificates of those qualified as Seismic Walkdown Engineers are included in Attachment H.
Table 4-1 summarizes the names and responsibilities of personnel used to conduct the seismic walkdowns. Experience summaries of each person follow.
Table 4-1 Name Equipment Selection Personnel Seismic Walkdown Engineer Licensing Basis Reviewer IPEEE Reviewer Greg Ferguson, DE-Civil X
X X
X Marc McCloskey, DE-Mechanical X
David Constance, Operations X2 Ricky Tran, DE-Electrical X
John Meibaum, SE-Electrical X
James Jamison, SE-Mechanical X
Bill Hardin, Licensing X
Stephen Picard, DE-Civil X
X J. McDonald, PSA Engineer X
Dinesh Patel (ENERCON)
X1 X
X Brian Pace (ENERCON)
X X
Natalie George (ENERCON)
X Chu-Chieh Jay Lin (SC Solutions)
X Notes:
- 1.
- 2.
Plant operations representative
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 10 of 35 Greg Ferguson, P.E Mr. Ferguson is a Registered Professional Engineer with over 35 years of experience currently assigned to Design Engineering Group (Civil) at Waterford 3. Mr. Ferguson has significant experience dealing with design and modification of seismic structures. Mr.
Ferguson was involved with the Waterford 3 IPEEE seismic walkdowns. Mr. Ferguson completed the NTTF 2.3 Seismic Walkdown Training Course in June of 2012.
Marc McCloskey Mr. McCloskey is a Mechanical engineer with over five years of experience currently assigned to Design Engineering Group (Mechanical) at Waterford 3 David Constance Mr. Constance is an Operations training instructor with over 30 years of experience currently assigned to Operations group at Waterford 3. He was also involved in operations group at Waterford 3. Mr. Constance also held a Senior Reactor Operator License from 2000 to 2008 and is also a Certified Shift Technical Advisor Ricky Tran Mr. Tran is an Electrical engineer with over 20 years of experience currently assigned to Design Engineering Group (Electrical) at Waterford 3. Mr. Tran was also involved with Procurement Engineering Group at Waterford 3 from 1992 to 1996 John Meibaum Mr. Meibaum is an Electrical engineer with over 23 years of experience currently assigned to Systems Engineering Group (Electrical) at Waterford 3 James Jamison Mr. Jamison is a Mechanical Engineer with over four years of experience currently assigned to Systems Engineering Group (Mechanical) at Waterford 3 William Hardin Mr. Hardin is a Senior Licensing Specialist with over 40 years of experience currently assigned to Licensing group at Waterford 3. Prior to this Mr. Hardin was a Senior Reactor Operator working as Control Room Supervisor and Senior Operations Training Instructor.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 11 of 35 Stephen Picard Mr. Picard is a Civil Engineer with three years of experience in Design Engineering (Civil). Mr.
Picard completed the NTTF 2.3 Seismic Walkdown Training Course in July of 2012.
J McDonald Mr. McDonald is an Electrical Engineer with ten years of experience in electrical, I&C, and PRA Design Engineering.
Dinesh Patel Mr. Patel is a Lead Engineer in ENERCON Services Kennesaw, GA Office in the Civil/Structural Engineering department. Mr. Patel has a BS degree in Civil/Architectural Engineering with over 30 years of experience. Mr. Patel has extensive concrete, building design, piping and pipe support design experience. Mr. Patel was also Lead/Responsible Engineer for Main and Auxiliary Transformer Replacements, Vacuum Pump Replacement, Diesel Governor Replacement, Power Uprate related modifications and Emergency Sump Strainers design and installations at various nuclear sites. Mr. Patel has significant seismic experience including the design and modification of nuclear structures and distribution system, selecting equipment, developing specifications, witnessing seismic testing, and equipment supports. Mr. Patel also has extensive experience performing security upgrades at Entergy Sites including Grand Gulf Nuclear Station, River Bend Station, Arkansas Nuclear One and Waterford 3 as well as at the Progress Energy sites (Crystal River, Brunswick, Harris, Robinson), Florida Power Sites (St. Lucie and Turkey Point) and the Southern Company Sites (Farley, Hatch and Vogtle). These upgrades included modifications to security buildings, ISFSI installations, VBS installations as well as protected area changes.
For the Entergy Sites, Mr. Patel supported the 2002 ICM Security upgrades, the 2004 Revised DBT Security upgrades, and the PA expansion associated with the ISFSI installation at GGNS. Mr. Patel completed the NTTF 2.3 Seismic Walkdown Training Course in July of 2012.
Brian Pace Mr. Pace is assigned to the Civil/Structural Engineering Group in ENERCONs office in Baton Rouge, LA. He is a degreed civil engineer from Louisiana State University with experience in several nuclear projects for Entergy. Mr. Pace was involved with Service Water System Modifications at Arkansas Nuclear One (ANO), where he helped design safety related tie-back restraints for Service Water piping at ANO. Mr. Pace has experience with Entergys Engineering Change and Work Management process. He has design experience for River Bend Station as well as ANO. Mr. Pace completed the NTTF 2.3 Seismic Walkdown Training Course in August of 2012.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 12 of 35 Natalie George Ms. George is a Structural Engineer in ENERCONs Kennesaw, GA office. She is responsible for piping design and analysis, support qualification, modification development, and various other mechanical/piping design tasks. Ms. George has approximately two years of support qualification and pipe stress analysis experience. She has performed ANSI B31.1 and ASME pipe stress analysis for safety related piping at several plants including Wolf Creek, Turkey Point, and Brunswick while assigned to the Kennesaw office. Her computer analysis code experience includes ME101, AUTOPIPE, and PipeStress2000. Ms. George completed the NTTF 2.3 Seismic Walkdown Training Course in August of 2012.
Chu-Chieh Jay Lin Dr. Lin is a Senior Engineer in SC Solutions Walnut Creek, CA office. He has over 15 years of experience in Seismic and Safety assessment of various structures, soil structural integration analyses and design evaluation, finite/discrete element simulation of different types of structures and materials, analyzing and designing industrial and urban steel and reinforced concrete structures, structural evaluation, field investigation, data acquisition, structural health monitoring of bridges and experimental modal analysis, performance analysis of vibration, and seismic design. Dr. Lin completed the NTTF 2.3 Seismic Walkdown Training Course in July of 2012.
4.1 EQUIPMENT SELECTION PERSONNEL A total of nine individuals served as Equipment Selection Personnel - see Table 4-1.
4.2 SEISMIC WALKDOWN ENGINEERS A total of six individuals served as Seismic Walkdown Engineers - see Table 4-1.
4.3 LICENSING BASIS REVIEWERS A total of three individuals served as Licensing Basis Reviewers - see Table 4-1.
4.4 IPEEE REVIEWERS A total of two individuals served as IPEEE Reviewers - see Table 4-1.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 13 of 35 4.5 PEER REVIEW TEAM Table 4-2 summarizes the names and responsibilities of personnel who conducted peer reviews of the seismic walkdown program. Experience summaries of each person follow.
Table 4-2: Peer Review Team Name SWEL Peer Reviewer Walkdown Peer Reviewer Licensing Basis Peer Reviewer Submittal Report Peer Reviewer Benjamin Kosbab (ENERCON)
X2 X2 X1,2 Heidi Graf (ENERCON)
X2 Sada Dhingra (ENERCON)
X Matthew Wilkinson (ENERCON)
X Greg Ferguson X
X Notes:
- 1.
Peer Review Team Leader
- 2.
Lead peer reviewer of particular activity Benjamin Kosbab Dr. Kosbab is a civil/structural engineer with ENERCON specializing in seismic engineering of nuclear power plant structures, systems, and components. He has earned Master of Science and Ph.D. degrees in civil/structural engineering from the Georgia Institute of Technology with a focus on probabilistic seismic response and fragility analysis of industrial structures. In the nuclear industry, Dr. Kosbab has been involved with seismic time-history and response spectra development, seismic equipment qualification, design of seismic supports, walkdowns, seismic fragility screening, dynamic structural analysis, seismic instrumentation analysis, and soil-structure interaction analysis for plant modifications at numerous nuclear facilities. Dr. Kosbab maintains active involvement with the Nuclear Energy Institute (NEI) Seismic Task Force, and completed the EPRI NTTF 2.3: Seismic Walkdown Training in July, 2012.
Heidi Graf Ms. Graf is a mechanical engineer in the Power Generation Group out of the Kennesaw, Georgia office of ENERCON. Ms. Graf has over 17 years of commercial nuclear power engineering experience including 7 years in Nuclear Plant Design and Support with the Southern Nuclear Company (SNC) Farley Nuclear Plant. Ms. Graf has completed multiple modification projects for various nuclear plants on numerous systems. She has knowledge of
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 14 of 35 plant documentation. Ms. Graf has completed several training courses on plant operations and has an understanding on many systems. She has spent many hours studying the IPEEE and the USI A-46 programs and their impacts on the industry Matthew Wilkinson Mr. Wilkinson is a Civil Engineer with over 5 years of experience. He has a B.S. in Civil Engineering. Mr. Wilkinson is currently assigned to the Civil/Structural Group at ENERCONs office in Kennesaw, GA. As a civil engineer, he is responsible for the development of engineering packages, calculations, analyses, drawings, and reports. Mr. Wilkinson has significant design experience with Florida Power and Light, primarily providing his services for Turkey Point Nuclear Station (PTN) on several modification packages and calculations. Mr.
Wilkinson has significant site support experience at PTN, McGuire Nuclear Station and River Bend Nuclear Station. Moreover, Mr. Wilkinson worked directly at PTN for the majority of 2010 to support the Independent Spent Fuel Storage Installation (ISFSI) construction and 2011 to 2012 to support the Extended Power Uprate (EPU) project design phase. Mr.
Wilkinson performed seismic walkdowns at Vogtle Nuclear Station.
Sada Dhingra Mr. Dhingra is currently assigned as an Engineer in ENERCONs Mechanical group. He has over 30 years of experience in the design, construction, start up and operation of HVAC and Mechanical Systems for nuclear power plants. Prior to joining ENERCON, Mr. Dhingra was a Senior Lead Consultant for D.P. Engineering and Senior Mechanical Engineer for Entergy Operations, Inc. providing engineering services to Entergy Nuclears Waterford and River Bend stations.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 15 of 35 5.0 IPEEE VULNERABILITIES REPORTING During the IPEEE program in response to NRC Generic Letter 88-20 [Ref. 4], plant-specific seismic vulnerabilities were identified at many plants. In this context, vulnerabilities refer to conditions found during the IPEEE program related to seismic anomalies, outliers, or other findings.
IPEEE Reviewers (see Section 4.4) reviewed the IPEEE final report [Ref. 5] and supporting documentation to identify items determined to present a seismic vulnerability by the IPEEE program. IPEEE Reviewers then reviewed additional plant documentation to identify the eventual resolutions to those seismic vulnerabilities not resolved via the completion of the IPEEE program.
The seismic vulnerabilities identified for WSES-3 during the IPEEE program are reported in Attachment A. A total of 2 seismic vulnerabilities were identified by the WSES-3 IPEEE program. For each identified seismic vulnerability, the table in Attachment A includes three pieces of information requested by Enclosure 3 of the 50.54(f) Letter:
a description of the action taken to eliminate or reduce the seismic vulnerability; whether the configuration management program has maintained the IPEEE action (including procedural changes) such that the vulnerability continues to be addressed; when the resolution actions were completed.
The list of IPEEE vulnerabilities provided in Attachment A was used to ensure that some equipment enhanced as a result of the IPEEE program were included in SWEL1 (see Section 6.1.2). Documents describing these equipment enhancements and other modifications initiated by identification of IPEEE vulnerabilities were available and provided to the Seismic Walkdown Engineers (SWEs) during the NTTF 2.3 Seismic Walkdowns.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 16 of 35 6.0 SEISMIC WALKDOWN EQUIPMENT LIST DEVELOPMENT This section summarizes the process used to select the SSCs that were included in the Seismic Walkdown Equipment List (SWEL) in accordance with Section 3 of the Guidance. A team of equipment selection personnel with extensive knowledge of plant systems and components was selected to develop the SWEL. The SWEL is comprised of two groups of items:
SWEL 1 consists of a sample of equipment required for safe shutdown of the reactor and to maintain containment integrity (i.e. supporting the five safety functions)
SWEL 2 consists of items related to the spent fuel pool The final SWEL is the combination of SWEL1 and SWEL2. The development of these two groups is described in the following sections.
6.1 SAMPLE OF REQUIRED ITEMS FOR THE FIVE SAFETY FUNCTIONS Safe shutdown of the reactor involves four safety functions:
Reactor reactivity control (RRC)
Reactor coolant pressure control (RCPC)
Reactor coolant inventory control (RCIC)
Maintaining containment integrity is the fifth safety function:
Containment function (CF)
The overall process for developing a sample of equipment to support these five safety functions is summarized in Figure 1-1 of the Guidance. Figure 1-1 of the Guidance provides a screening method for selecting SSCs, starting with all of the SSCs for the plant and reducing the number based on certain screening criteria referenced in Section 3 of the Guidance. The list of equipment coming out of Screen #3 and entering Screen #4 is defined as Base List 1. The list of equipment coming out of Screen #4 is the first Seismic Walkdown Equipment List, or SWEL 1. Development of these lists is described separately in the following sections.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 17 of 35 6.1.1 Base List 1 Based on Figure 1-1 and Section 3 of the Guidance, Base List 1 should represent a set of Seismic Category (SC) I equipment or systems that support the five safety functions. The IPEEE program was intended to address the seismic margin of SSCs associated with each of the five safety functions. At WSES-3, the EPRI Seismic Margin Assessment (EPRI SMA) method was used to complete the seismic IPEEE program, based on EPRI Report NP-6041 titled A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Ref. 6). As described in Section 3 of the WSES-3 IPEEE report [Ref. 5], an equipment list was developed representing the SSCs necessary for one preferred and one alternate success path capable of achieving and maintaining a safe shutdown condition for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> following a SSE event. This equipment list of SSCs on the success paths is consistent with the requirements of Screens #1 through #3 of the Guidance. Therefore, the IPEEE equipment list of SSCs on the success paths is used as the starting point for the NTTF 2.3 Seismic Walkdown Base List 1. Each component was then checked in the Entergy Electronic Database to verify its safety classification, preventative maintenance, environment, etc. Plant personnel were consulted to find any additional components that were added or replaced in the past 15 years (since the IPEEE report). The resulting list represents Base List 1.
Base List 1 is presented as Table 1 in Attachment B, and has 624 total items.
6.1.2 SWEL 1 Based on Figure 1-1 and Section 3 of the Guidance, SWEL 1 should represent a diverse population of items on Base List 1 including representative items from some of the variations within each of five sample selection attributes. Additionally, the selection of SWEL 1 items includes consideration of the importance of the contribution to risk for the SSCs. Equipment Selection Personnel (see Section 4.1) developed SWEL 1 using an iterative process. The following paragraphs describe how the equipment selected for inclusion on the final SWEL 1 are representative with respect to each of the five sample selection attributes while also considering risk significance.
In general, preference for inclusion on SWEL 1 was given to items that are accessible and have visible anchorage while still maintaining the sample selection attributes.
SWEL 1 is presented as Table 2 in Attachment B, and has 97 total items.
Variety of Types of Systems Items were selected from Base List 1 ensuring that each of the five safety functions was well represented. Additionally, components from a variety of frontline and support
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 18 of 35 systems, as listed in Appendix E of the Guidance, were selected. The system type of each item on SWEL 1 is listed on Table 2 of Attachment B.
Major New and Replacement Equipment With assistance from plant Operations and Engineering, Equipment Selection Personnel identified items on Base List 1 which are either major new or replacement equipment installed within the past 15 years or have been modified or upgraded recently. These items are designated as such on Base List 1 on Table 1 of Attachment B. A robust sampling of these items is represented on SWEL 1.
Variety of Equipment Types According to Appendix B of the Guidance, there are 22 classes of mechanical and electrical equipment. The items on Base List 1 were classified accordingly and the total number of items from each class was determined. Items were then selected from Base List 1 ensuring that each of the equipment classes there was also represented on SWEL 1 in approximately the same ratios. The equipment class of each item on SWEL 1 is listed in Table 2 of Attachment B. Note that SWEL 1 does not include components from Class 13. WSES-3 has no Seismic Class I components that are Class 13, and therefore would not be represented on Base List 1 or SWEL 1.
Variety of Environments Items were selected from Base List 1 located in a variety of buildings, rooms, and elevations. These item locations included environments that were both inside and outside, as well as having high temperature and/or elevated humidity and also within the containment building. Items that were part of borated systems were included as well. The location and environment of each item on SWEL 1 is listed on Table 2 of Attachment B.
IPEEE Enhancements With assistance from IPEEE Reviewers, Equipment Selection Personnel identified items on Base List 1 which were enhanced as a result of seismic vulnerabilities identified during the IPEEE program (see Section 5.0). These items are designated as such on Base List 1 on Table 1 of Attachment B. These items are represented on SWEL 1.
Risk Significance Information from the plant Probabilistic Risk Analysis (PRA) model was used to determine whether items were risk significant. Where otherwise comparable items could be chosen relative to the sample selection attributes, the item with higher risk significance was chosen.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 19 of 35 6.2 SPENT FUEL POOL ITEMS The overall process for developing a sample of SSCs associated with the spent fuel pool (SFP) is similar to that of the screening process for SWEL1 and is summarized in Figure 1-2 of the Guidance. The equipment coming out of Screen #2 and entering Screen #3 is defined as Base List 2. The equipment coming out of Screen #4 are the items that could potentially cause the SFP to drain rapidly. The items coming out of either Screen #3 or Screen #4 are the second Seismic Walkdown Equipment List, or SWEL 2. Development of these lists is described separately in the following sections.
6.2.1 Base List 2 Based on Figure 1-2 and Section 3 of the Guidance, Base List 2 should represent the Seismic Category I equipment or systems associated with the SFP. To develop Base List 2, Equipment Selection Personnel (see Section 4.1) reviewed plant design and licensing basis documentation and plant drawings for the SFP and its associated cooling system. Base List 2 is presented as Table 3 in Attachment B, and has 75 total items.
6.2.2 Rapid Drain-Down Rapid drain-down is defined as unintentionally lowering the water level to the top of the fuel assemblies within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after an earthquake. Consistent with the Guidance, the Equipment Selection Personnel (see Section 4.1) identified SSCs that could cause the SFP to drain rapidly by first reviewing the SFP documentation to identify penetrations below about 10 ft. above the top of the fuel assemblies.
This review assessed the hydraulic lines and connected equipment of each such penetration for potentially seismically-induced failure modes that could lead to rapid drain down. The list of SSCs that could cause rapid drain-down is presented as Table 4 in Attachment B which includes the specific basis for determining which SSCs could or could not cause rapid drain-down.
The rapid drain-down list is presented as Table 4 in Attachment B, and has a total of 5 items that could potentially cause rapid drain down.
6.2.3 SWEL 2 Based on Figure 1-2 and Section 3 of the Guidance, SWEL 2 is a broad population of items on Base List 2 including representative items from some of the variations within each of the four sample selection attributes (using a sample process similar to SWEL 1), as well as each item that could potentially cause rapid-drain down of the SFP. Due
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 20 of 35 to the population of items on Base List 2 being much smaller than Base List 1, the sampling attributes are satisfied differently for SWEL 2 than for SWEL 1. The following paragraphs describe how the equipment selected from Base List 2 for inclusion on SWEL 2 are representative with respect to each of the four sample selection attributes. SWEL 2 is presented as Table 5 in Attachment B, and has 26 total items; of these, 21 items are selected from Base List 2, and 5 are from the rapid drain-down list.
Variety of Types of Systems There are two systems associated with SFP cooling. Both of these systems are well-represented on SWEL 2.
Major New and Replacement Equipment There have been no major new or replacement equipment installations within the past 15 years associated with the SFP. Therefore, this sampling attribute is not applicable.
Variety of Equipment Types There are 6 different equipment classes represented on Base List 2: 0, 2, 5, 7, 8, 14, and 21. Each of these equipment classes is represented on SWEL 2.
Variety of Environments All SFP components are located nearby each other, but are in two different environments. The SFP equipment is inside, but some equipment is part of a borated system while the remainder is not. The location and environment of each item on SWEL 2 is listed on Table 5 of Attachment B.
6.3 DEFERRED INACCESSIBLE ITEMS on SWEL Each item on the SWEL shall be walked down as part of the NTTF 2.3 Seismic Walkdown program. In order to perform the seismic walkdowns of these items, it is necessary to have access to them and to be able to view their anchorage. In some cases, it was not feasible to gain access to the equipment or view its anchorage because WSES-3 was at power until October 17, 2012. For these cases, walkdowns of these items have been deferred until the next available refueling outage (RFO) and/or specific equipment outages. The inaccessible items and some items within cabinets that are available will be walked down during the current outage (RFO 18). The results of these walkdowns will be incorporated into the first updated submittal of the report. The walkdown of the remaining items will be completed during specific system outage windows or during the next scheduled RFO (19). A second update to the report will be submitted after RFO 19. WSES-3 will provide two updated submittal reports incorporating these deferred walkdowns. The first update will be provided two months after the end of Refuel Outage 18, and the second update will be provided two months after the end of Refuel Outage 19, tentatively scheduled for the Spring of 2014.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 21 of 35 Deferred items are summarized in the table below. The reason for deferral is identified as either ACC (indicating that the item is in an inaccessible item while the plant is at power or other work must be done for access), CAB (indicating that the item requires opening cabinet/panel doors which was not permitted by plant Operations personnel during the walkdown period, due to being energized or otherwise), or INS (indicated that insulation must be removed in order to complete the walkdown of that component). A total of 26 items are deferred. Of these, 12 were inaccessible at the time of the initial walkdowns, 13 are in cabinets/panels that have to be opened, and one needs insulation removed.
Table 6-1: Deferred Items SWEL#
Equipment ID Description Location Reason SWEL1-002 (AWC-018*)
SSDEMCC311B Motor Control Center 311B RAB +21, Switchgear B Room CAB SWEL1-004 (AWC-019)
CEDEBKR3918-B Reactor Trip Switchgear Breaker TCB-2 Compartment 2C RAB +21, Switchgear B Room CAB SWEL1-005 (AWC-026)
SSDESWGR31AB Switchgear 31AB RAB +21, Switchgear AB Room CAB SWEL1-006 (AWC-016*)
4KVESWGR3A Switchgear 3A RAB +21, Switchgear A Room CAB SWEL1-018 (AWC NOT ASSIGNED)
BM MVAAA109 Reactor Drain Tank Outlet Inside Containment Isolation RCB -11, COL. 14 ACC SWEL1-019 (AWC NOT ASSIGNED)
CAPMVAAA103 Containment Purge Inlet Inside Annulus ANN +21, PEN. P-10 ACC SWEL1-026 (AWC-031)
CVCMVAAA209 Charging Header Isolation RB +21 ACC SWEL1-029 (AWC-038*)
HVCMVAAA205-A Control Room Emergency Filtration A Inlet Damper RAB +46, 8A-L INS SWEL1-037 (AWC NOT ASSIGNED)
SI MVAAA307-A Safety Injection Tank 1A Fill/Drain RCB +35, COL. 17 ACC SWEL1-038 (AWC NOT ASSIGNED)
SI MVAAA405-B RC Loop 1 SDC Suction Inside Containment Isolation RCB +21, COL. 17 ACC SWEL1-047 (AWC NOT ASSIGNED)
RC ISV1014 Reactor Vessel Vent to Quench Tank Isolation RCB +46, AZM 196 ACC SWEL1-048 (AWC NOT ASSIGNED)
RC ISV3184 Pressurizer Vent to Quench Tank RCB +46, AZM 196 ACC
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 22 of 35 SWEL#
Equipment ID Description Location Reason SWEL1-059 (AWC NOT ASSIGNED)
ACCMFAN0002-B Wet Cooling Tower B Fan 2-SB CTB -35, 12A-Q1 ACC SWEL1-075 (AWC NOT ASSIGNED)
IC ICDC1-C Instrument Cabinet C-1C RCB +21, COL. 16 ACC SWEL1-077 (AWC NOT ASSIGNED)
IC ICDC9 Instrument Cabinet C-9 RCB +21, COL. 6 ACC SWEL1-079 (AWC NOT ASSIGNED)
SG ILT1115-A Steam Generator 1 Level IXMITR (Wide Range)
RCB -4, COL. 18 ACC SWEL1-080 (AWC NOT ASSIGNED)
RC ITE0122-HA1 Reactor Coolant Loop 2 Hot Leg Temperature RCB -4 ACC SWEL1-084 (AWC-032*)
IC ECP08 Engineered Safeguard Control Panel CP8 RAB +46, Control Room CAB SWEL1-097 (AWC-018*)
4KVESWGR3B Switchgear 3B RAB +21, Switchgear B Room CAB SWEL2-001 (AWC-054)
FS EBKR314A-5D Fuel Pool Purification Pump Circuit Breaker FHB +1, 1FH-V CAB SWEL2-002 (AWC-054)
FS EBKR314A-5M Fuel Pool Pump A Circuit Breaker FHB +1, 1FH-V CAB SWEL2-003 (AWC-054)
FS EBKR314B-6F Refueling Canal Drain Pump Circuit Breaker FHB +1, 2FH-W CAB SWEL2-006 (AWC-054)
FS EBKR314B-5M Fuel Pool Pump B Circuit Breaker FHB +1, 2FH-W CAB SWEL2-007 (AWC-054)
FS EOL314A-5M Fuel Pool Pump A TOL FHB +1, 1FH-V CAB SWEL2-008 (AWC-054)
FS EOL314B-5M Fuel Pool Pump B TOL FHB +1, 2FH-W CAB SWEL2-009 (AWC-054)
FS EOL314B-6F Refueling Canal Drain Pump TOL FHB +1, 2FH-W CAB
- Denotes that the AWC is submitted with this Final Report. Although its associated SWEL item has been deferred, the AWC was conducted due to other SWEL items being in the surrounding area.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 23 of 35 7.0 SEISMIC WALKDOWNS AND AREA WALK-BYS The NTTF 2.3 Seismic Walkdown program conducted in accordance with the Guidance involves two primary walkdown activities: Seismic Walkdowns and Area Walk-Bys. These activities were conducted at WSES-3 by teams of two trained and qualified Seismic Walkdown Engineers (SWEs) (see Section 4.2). Each team included one engineer with several years of experience in seismic design and the qualification of nuclear power plant SSCs. The second engineer had less experience, but sufficient experience to properly perform the tasks. A total of two SWE teams were used. In certain instances, the teams periodically shuffled personnel to cross-check consistency between the SWES and to ensure that lessons learned were being shared. SWE teams were periodically accompanied into the field by WSES-3 design engineering and operations personnel to open cabinets and answer questions.
The seismic walkdowns and area walk-bys were conducted over the course of 3 weeks during October of 2012. Each morning, a pre-job brief with all personnel involved was conducted. This pre-job brief was used to outline the components and areas that would be walked down that day, to ensure consistency between the teams, to reinforce expectations to identifying potential personal safety issues specific to that day, and to allow team members to ask questions and share lessons learned in the field. The SWE teams brought cameras (regular and pole mounted with remote monitor), tape measures, and flash lights into the field to assist with the seismic walkdowns and area walk-bys.
7.1 SEISMIC WALKDOWNS Seismic walkdowns were performed in accordance with Section 4 of the Guidance for all items on the SWEL (SWEL 1 plus SWEL 2), except for those determined to be inaccessible and deferred (see Section 6.3). To document the results of the walkdown, a separate Seismic Walkdown Checklist (SWC) with the same content as that included in Appendix C of the Guidance was created for each item. Additionally, photographs were taken of each item, and included on the corresponding SWC.
Prior to performance of the walkdowns, documentation packages were developed that contained the pre-filled SWC and other pertinent information including the location drawings, equipment drawings, response spectra information, previous IPEEE seismic walkdown documentation, current operability evaluations, and anchorage drawings where applicable.
These documentation packages were brought with the SWE teams into the plant during the seismic walkdowns.
Walkdown inspections focused not only on anchorage conditions and seismic spatial interactions, but also included inspections for other potentially adverse seismic conditions.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 24 of 35 Anchorage, in all cases, was considered to specifically mean anchorage of the component to the structure. This included anchor bolts to concrete walls or floors, structural bolts to structural steel and welds to structural steel or embedded plates. For welds, the walkdown team looked for cracks and corrosion in the weld and base metal. Other bolts or connections, such as flange bolts on in-line components were not considered as equipment anchorage.
These bolts and connections were evaluated by the SWEs and any potential adverse seismic concerns were documented under other adverse seismic conditions rather than under anchorage. Thus, components with no attachments to the structure are considered as not having anchorage. Nevertheless, the attachment of these components to other equipment was evaluated and inspected for potentially adverse seismic conditions.
Cabinets/panels on the SWEL that could be reasonably opened without presenting safety or operational hazards were opened during the walkdown. This allowed visual observation of internal anchorage to the structure (where present), as well as inspection for other adverse seismic conditions related to internal components (if it could be observed without breaking the plane of the equipment opening). Where opening the cabinet/panel exhibited undue safety or operational hazards, it was considered inaccessible and the completion of the walkdown of that item was deferred to a later time (see Section 6.3).
In addition to the general inspection requirements, at least 50% of the SWEL items having anchorage required confirmation that the anchorage configuration was consistent with plant documentation. Not considering deferred items, there were a total of 97 SWEL1 and SWEL2 items. Of the 97 SWEL items, 56 were considered to have anchorage (i.e., removing in-line/line-mounted components). Of these 56 anchored components, the walkdowns of 31 SWEL items included anchorage configuration verification, which is greater than 50%. When an anchorage configuration verification was conducted, the specific plant documentation used for comparison to the as-found conditions was referenced on the SWC.
All SWCs, whether status has been checked Y or N, have been included in Attachment C.
A total of 123 SWCs are attached, 97 with completion status marked Y and 26 with completion status marked N. SWCs considered and marked incomplete are those where a walkdown was initiated, but whose completion was ultimately deferred because the cabinet/panel could not be opened during the walkdown period. Therefore, the 97 completed SWCs represent the completed walkdowns of each SWEL item accessible during the walkdown period.
7.2 AREA WALK-BYS Seismic area walk-bys were performed in accordance with Section 4 of the Guidance for all plant areas containing items on the SWEL (SWEL 1 plus SWEL 2); except for those SWEL items located in plant areas inaccessible during the walkdown period (see Section 6.3). Area
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 25 of 35 walk-bys were not deferred where components were deferred simply to open cabinets/panels. A separate Area Walk-By Checklist (AWC) with the same content as that included in Appendix C of the Guidance was used to document the results of each area walk-by performed. Photographs were taken of each area, and included on the corresponding AWC.
Where possible, area walk-bys were conducted once for plant areas containing more than one SWEL item. In cases where the room or area containing a component was very large, the extent of the area encompassed by the area walk-by was limited to a radius of approximately 35 ft. around the subject equipment. The extent of the areas included in the area walk-bys is described on the AWC for that area. Because certain areas contained more than one SWEL item, there are fewer total area walk-bys conducted than seismic walkdowns.
A total of 46 area walk-bys was necessary to cover all plant areas containing at least one accessible SWEL item.
The AWC for each area walk-by completed is included in Attachment D. A total of 46 AWCs are attached, which represent all of the areas containing a SWEL item that were accessible during the walkdown period. Note that the AWCs number up to AWC-053, but some numbers were not used. These unused numbers may be used for AWCs for deferred items.
The walkdown team will select additional AWCs for walkdowns of SWEL items inside containment as well as other deferred items (see Section 6.3).
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 26 of 35 8.0 LICENSING BASIS EVALUATIONS During the course of the seismic walkdowns and area walk-bys, the objective of the SWE teams was to identify existing degraded, non-conforming, or unanalyzed plant conditions with respect to its current seismic licensing basis. This section summarizes the process used to handle conditions identified, what conditions were found, and how they were treated for eventual resolution.
CONDITON IDENTIFICATION When an unusual condition was observed by a SWE team in the field, the condition was noted on the SWC or AWC form and briefly discussed between the two SWEs to agree upon whether it was a potentially adverse seismic condition. These initial conclusions were based on conservative engineering judgment and the training required for SWE qualification.
For conditions that were reasonably judged as insignificant to seismic response, the disposition was included on the SWC or AWC checklist and the appropriate question was marked Y, indicating that no associated potentially adverse seismic condition was observed.
However, some unusual or uncertain conditions (i.e. mild surface corrosion) were reported to site personnel through the Corrective Action Program (CAP) for tracking purposes (see Section 8.2). Not all observations were reported through the CAP. Often times, only a Work Request (WR) was written, or the observation was deemed too insignificant to write a WR or report through the CAP. A total of 72 seismically insignificant conditions were identified and were either reported through the CAP or had a Work Request written for them. These conditions were generally related to either housekeeping (5), missing bolts or screws that posed no seismic concern (7) or mild surface corrosion (60).
For conditions that were judged as potentially significant to seismic response, then the condition was photographed and the appropriate question on the SWC or AWC was marked N indicating that a potentially adverse seismic condition was observed. The condition was then immediately reported to site personnel for further resolution (see Section 8.2) and documented for reporting in Attachment E. A total of 19 potentially adverse seismic conditions were identified. These conditions were generally related to missing or loose anchorage (5), seismically significant housekeeping issues (5), seismically significant corrosion (7), or concrete cracks (2).
CONDITION RESOLUTION Conditions observed during the seismic walkdowns and area walk-bys determined to be potentially adverse seismic conditions are summarized in Attachment E, including how each condition has been addressed and its current status. Each potentially adverse seismic condition is addressed either with a Licensing Basis Evaluation (LBE) to determine whether it
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 27 of 35 requires entry into the CAP, or by entering it into the CAP directly. The decision to conduct a LBE or enter the condition directly into the CAP was made on a case-by-case basis, based on the perceived efficiency of each process for eventual resolution of each specific condition.
Some unusual conditions that were not seismically significant were entered into the CAP directly. Other unusual observed conditions either had a WR written for them or were deemed insignificant to report. Further resolution of these conditions is not tracked or reported as part of the NTTF 2.3 Seismic Walkdown program, except by noting the CR and / or Work Request (WR) numbers generated on the applicable SWCs and AWCs.
8.1 Licensing Basis Evaluation Potentially adverse seismic conditions identified as part of the NTTF 2.3 Seismic Walkdown program may be evaluated by comparison to the current licensing basis of the plant as it relates to the seismic adequacy of the equipment in question, as is described in Section 5 of the Guidance. If the identified condition is consistent with existing seismic documentation associated with that item, then no further action is required. If the identified condition cannot easily be shown to be consistent with existing seismic documentation, or no seismic documentation exists, then the condition is entered into the CAP.
Of the 19 identified potentially adverse seismic conditions, 7 LBEs were performed.
Each LBE performed is documented consistently, and included in Attachment F. The results of these LBEs with respect to the associated potentially adverse seismic conditions are summarized in Attachment E. A total of 7 potentially adverse seismic conditions evaluated using a LBE were dispositioned and required no further action, whereas 0 required CAP entry.
8.2 Corrective Action Program Entries Conditions identified during the seismic walkdowns and area walk-bys that required further resolution were entered into the plants Corrective Action Program (CAP) in accordance with the plants existing processes and procedures for an eventual disposition. Conditions entered into the CAP included three types of unusual conditions identified:
Seismically insignificant unusual conditions Potentially adverse seismic condition that does not pass a LBE Potentially adverse seismic condition that bypasses a LBE A total of 34 Condition Reports (CRs) were generated in the CAP as a result of the NTTF 2.3 Seismic Walkdown program. A total of 14 identified conditions already had
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 28 of 35 CRs written for them. Of these, the majority (36) were from seismically insignificant unusual conditions. A total of 12 CRs were written relative to potentially adverse seismic conditions. The CR numbers, current status, and resolution (where applicable and available) are summarized for these potentially adverse seismic conditions in Attachment E.
8.3 Plant Changes The CAP entries (CRs) generated by the NTTF 2.3 Seismic Walkdown program are being resolved in accordance with the plant CAP process, including operability evaluations, extent of condition evaluations, and root cause analysis (where applicable).
There was one item that required immediate field work as a result of the NTTF 2.3 Seismic Walkdown program. A temporary enclosure was found to be installed in the B Switchgear room. This enclosure is used to provide a contamination barrier when the floor plug is removed from a contaminated pipe chase below the floor.
No calculation or drawings could be found for the enclosure. Since the enclosure is unanchored, there is a distinct possibility that it could move across the floor and strike two different safety related panels during a seismic event. One Local Control Panel (PAC LCP-63), and the Instrument Cabinet (C-3B).
CR-WF3-2012-05172 was initiated. As a result, the enclosure was braced at the top and bottom to existing structural members to ensure the rigidity of the enclosure. This bracing was installed using existing site procedures.
EC40448 was issued to document the acceptability of the modified enclosure.
Final and complete resolutions of the CRs for seismically insignificant unusual conditions and potentially adverse seismic conditions will determine if future modifications to the plant are required. Current status and resolutions (where applicable and available) for CRs related to potentially adverse seismic conditions are provided in Attachment E.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 29 of 35 9.0 PEER REVIEW 9.1 PEER REVIEW PROCESS The peer review for the Near Term Task Force (NTTF) Recommendation 2.3 Seismic Walkdowns was performed in accordance with Section 6 of the Guidance. The peer review included an evaluation of the following activities:
review of the selection of the structures, systems, and components (SSCs) that are included in the Seismic Walkdown Equipment List (SWEL);
review of a 25% sample of the checklists prepared for the Seismic Walkdowns and area walk-bys; review of licensing basis evaluations and decisions for entering the potentially adverse conditions into the plants Corrective Action Plan (CAP); and review of the final submittal report.
At least two members of the peer review team (see Section 4.5) were involved in the peer review of each activity. The team member with the most relevant knowledge and experience took the lead for that particular peer review activity. A designated overall Peer Review Team Leader provided oversight related to the process and technical aspects of the peer review, paying special attention to the interface between peer review activities involving different members of the peer review team.
9.2 PEER REVIEW RESULTS
SUMMARY
The following sections summarize the process and results of each peer review activity.
9.2.1 Seismic Walkdown Equipment List Development Peer review of the selection of SSCs for SWEL development was conducted by two peer reviewers. These peer reviewers both have extensive knowledge and experience related to nuclear power plant design, operations, documentation, and SSCs. The peer review was conducted prior to the seismic walkdowns occurring, and was performed as follows:
The draft of SWEL 1 and SWEL 2 were provided to the peer reviewers, along with the corresponding base lists (Base List 1, Base List 2, and SFP rapid drain-down list). the peer reviewers were also provided a written description from the equipment selection personnel of how the SWEL 1 and SWEL 2 were developed.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 30 of 35 Each peer reviewer independently reviewed the equipment selection process and the resulting SWEL in terms of the equipment selection process presented in Section 3 of the Guidance.
The peer reviewers discussed their findings and generated consolidated comments. General comments on the overall list and how it represents adequate diversity were documented on a peer review checklist based on Appendix F of the Guidance. Specific comments on documentation of the various lists and individual item selection decisions were documented on formal comment forms following utility procedure.
Comments were provided to the Equipment Selection Personnel (see Section 4.1).
Comment resolutions were provided to the peer reviewers to confirm acceptable resolution of all comments.
The peer review team reviewed the initial SWEL 1 and SWEL 2 and provided comments and suggestions for modification of the SWEL. Comments included suggesting to add components associated with IPEEE vulnerabilities identified at WSES-3 to SWEL1. All of the peer review comments were addressed by the Equipment Selection Personnel. The resolutions were reviewed by the peer review team and it was determined that all comments were adequately addressed.
Based on completion of the SWEL peer review activities described, the peer review team concludes that the Equipment Selection Personnel developed a SWEL that adequately reflects the selection and screening process outlined in the Guidance. The peer reviewers confirmed that all SSCs in the SWEL1 and SWEL2 are Seismic Category I components that do not undergo regular inspections and represent a diverse blend of different component types from critical systems and safety-related functions. The list contains major new and replacement items. Risk significance was considered in the component selection. Additionally, SFP items were appropriately addressed. Specific considerations for how the SWEL adequately represents the sample selection attributes described in Section 3 of the Guidance are provided on the peer review checklist of the SWEL.
The peer review checklist of the SWEL is provided in Attachment G.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 31 of 35 9.2.2 Seismic Walkdowns and Area Walk-Bys Peer review of the seismic walkdowns and area walk-bys was conducted by two peer reviewers, each of whom is a qualified SWE and has broad knowledge of seismic engineering applied to nuclear power plants. One of the peer reviewers participated in the seismic walkdown program for a different utility, and the other is engaged with the industry team which developed the Guidance (see Section 4.2). The peer reviews were conducted at the WSES-3 site concurrent with the walkdowns at approximately 50% completion. The peer review was performed as follows:
The peer review team reviewed the walkdown packages (including checklists, photos, drawings, etc.) for SWEL items already completed to ensure that the checklists were completed in accordance with the Guidance. A total of 27 SWC and 14 AWC forms were reviewed, each representing approximately 25% of their respective totals. In the context of the Guidance, the peer review team considered the number of walkdown packages reviewed to be appropriate. The packages reviewed represent a variety of equipment types in various plant areas. Specific SWC forms reviewed were SWEL1-003, 006, 007, 008, 010, 011, 012, 013, 016, 043, 044, 046, 051, 054, 056, 060, 066, 069, 070, 071, 072, 082, 087, 089, 090, 092, and 094. Specific AWC forms reviewed were AWC-001, 002, 004, 005, 006, 007, 010, 014, 016, 021, 023, 025, 028, and 042.
While reviewing the walkdown packages, the peer reviewers conducted informal interviews of the SWEs and asked clarifying questions to verify that they were conducting walkdowns and area walk-bys in accordance with the Guidance.
The peer review team held a meeting with the SWE teams to provide feedback on the walkdown and walk-by packages reviewed and the informal interviews, and discuss potential modifications to the documentation packages in the context of the Guidance.
Each peer reviewer accompanied each SWE team into the field and observed them perform a walkdown of a SWEL component and its associated area walk-by. During these observations, the peer reviewers asked clarifying questions to verify the walkdown and walk-by process being followed was in accordance with the Guidance. The items walked down under the observation of a peer reviewer were SWEL1-042, 061, 062, and 064. The associated area walk-bys performed under the observation of a peer reviewer are AWC-038 and -039.
The peer review team held a meeting with the SWE teams to provide feedback on the walkdown and walk-by observations, and discuss how lessons learned
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 32 of 35 from review of the walkdown packages had been incorporated into the walkdown process.
As a result of the peer review activities, the SWE teams modified their documentation process to include additional clarifying details, particularly related to checklist questions marked N/A and where conditions were observed but judged as insignificant. The peer review team felt these modifications would be of benefit for future reviews of checklists incorporated into the final report. These modifications were recommended following review of the walkdown and area walk-by packages, and the observation walkdowns and area walk-bys demonstrated that the SWEs understood the recommendations and were incorporating them into the walkdown and area walk-by process. Previously completed checklists were revised to reflect lessons learned from the peer review process.
Based on completion of the walkdown and walk-by peer review activities described, the peer review team concluded that the SWE teams are familiar with and followed the process for conducting seismic walkdowns and area walk-bys in accordance with the Guidance. The SWE teams adequately demonstrated their ability to identify potentially adverse seismic conditions such as adverse anchorage, adverse spatial interaction, and other adverse conditions related to anchorage, and perform anchorage configuration verifications, where applicable. The SWEs also demonstrated the ability to identify seismically-induced flooding interactions and seismically-induced fire interactions such as the examples described in Section 4 of the Guidance. The SWEs demonstrated appropriate use of self checks and peer checks. They discussed their observations with questioning attitude, and documented the results of the seismic walkdowns and area walk-bys on the appropriate checklists.
9.2.3 Licensing Basis Evaluations Licensing Basis Evaluations (LBEs) were developed by members of the walkdown engineering team to document the disposition of those potentially adverse seismic conditions identified which did not require entry into the CAP. Each LBE was independently reviewed for technical content and CAP entry decisions by the lead LBE peer reviewer. A second peer reviewer reviewed the set of all LBEs to ensure the process and decisions made were in compliance with Section 5 of the Guidance.
Based on these reviews, the peer review team concludes that the LBEs properly evaluate field conditions relative to the specific plant licensing basis documents and make appropriate decisions for entering the potentially adverse seismic conditions into the plants CAP. High-level peer review comments are documented in Attachment H.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 33 of 35 9.2.4 Submittal Report The peer review team was provided with an early draft of this submittal report for peer review. The peer review team verified that the submittal report met the objectives and requirements of Enclosure 3 to the 50.54(f) Letter, and documented the NTTF 2.3 Seismic Walkdown program performed was in accordance with the Guidance. The peer review team provided the results of review activities to the SWE team for consideration. The SWE team satisfactorily addressed all peer review comments in the final version of the submittal report. The signature of the Peer Review Team Leader provides documentation that all elements of the peer review as described in Section 6 of the Guidance were completed.
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 34 of 35
10.0 REFERENCES
- 1.
10CFR50.54(f) Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident, dated March 12, 2012
- 2.
EPRI 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, June 2012
- 3.
Waterford Steam Electric Station Unit 3, Final Safety Analysis Report (FSAR),
Revision 306
- 4.
Generic Letter No. 88-20, Supplement 4, Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities
- 5.
Waterford 3 Individual Plant Examination of External Events (IPEEE) Reduced Scope Seismic Margin Assessment (SMA). Report No. WF3-CS-12-00001, 02 2012/Revision, 0
- 6.
EPRI Report NP-6041-SLR1, A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1)
Engineering Report No.WF3-CS-12-00003 Rev.0 Page 35 of 35 11.0 ATTACHMENTS ATTACHMENT A - IPEEE VULNERABILITIES TABLE ATTACHMENT B - SEISMIC WALKDOWN EQUIPMENT LISTS ATTACHMENT C - SEISMIC WALKDOWN CHECKLISTS (SWCs)
ATTACHMENT D - AREA WALK-BY CHECKLISTS (AWCs)
ATTACHMENT E - POTENTIALLY ADVERSE SEISMIC CONDITIONS ATTACHMENT F - LICENSING BASIS EVALUATION FORMS ATTACHMENT G - PEER REVIEW CHECKLIST FOR SWEL ATTACHMENT H - PEER REVIEW COMMENT FORM ATTACHMENT J - SEISMIC WALKDOWN ENGINEER TRAINING CERTIFICATES
Attachment A IPEEE Vulnerability List Engineering Report No. WF3-CS-12-00003 Attachment A Rev. 0 Page 1 of 2
IPEEE VULNERABILITY COMMITMENT RESOLUTION CMP RESOLVED V01 Several Seismic interaction issues were found during IPEEE walkdown in the Control Room.
Panels not bolted together Personal storage lockers book cases, storage cabinets, lockers, copy machine were behind the panels and were not secured Breathing air cabinet can interact with CP-08 Resolve the Seismic interaction issue in the Control Room CR-94-1019 was issued to document loose items in the Control Room Modifications were implemented and all issues were resolved
-Panels were bolted together
-Personal storage lockers, book cases and storage cabinets were either bolted or relocated
-Breathing air cabinet was secured such that it would not interact with CP-08 Y
02-15-1995 V02 Station Air Pipe is close to Switchgear 4KVESWGR3B and can interact with the Switchgear Resolve the Seismic interaction issue with the Switchgear CR-94-1111 was issued to document the station air pipe which is adjacent to 4KVESWGR3B Station Air pipe was rerouted to provide adequate clearance between the switchgear and pipe.
Y Note 1 03-30-1995 Prepared by:
Dinesh Patel Date:
10/27/2012 Note 1: Plant documents were modified to incorporate vulnerability resolution.
Engineering Report No. WF3-CS-12-00003 Attachment A Rev. 0 Page 2 of 2
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 3
4KVESWGR3A PANEL SWITCHGEAR 3A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 3
4KVESWGR3AB PANEL SWITCHGEAR 3AB Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 3
4KVESWGR3B PANEL SWITCHGEAR 3B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 9
ACCMFAN0001 B
BLOWER WET COOLING TOWER B FAN 1-SB Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0001 A
BLOWER WET COOLING TOWER A FAN 1-SA Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0002 B
BLOWER WET COOLING TOWER B FAN 2-SB Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0002 A
BLOWER WET COOLING TOWER A FAN 2-SA Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0003 B
BLOWER WET COOLING TOWER B FAN 3-SB Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0003 A
BLOWER WET COOLING TOWER A FAN 3-SA Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0004 B
BLOWER WET COOLING TOWER B FAN 4-SB Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0004 A
BLOWER WET COOLING TOWER A FAN 4-SA Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0005 B
BLOWER WET COOLING TOWER B FAN 5-SB Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0005 A
BLOWER WET COOLING TOWER A FAN 5-SA Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0006 B
BLOWER WET COOLING TOWER B FAN 6-SB Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0006 A
BLOWER WET COOLING TOWER A FAN 6-SA Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0007 B
BLOWER WET COOLING TOWER B FAN 7-SB Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0007 A
BLOWER WET COOLING TOWER A FAN 7-SA Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0008 B
BLOWER WET COOLING TOWER B FAN 8-SB Yes No Yes No Yes O
H No Yes WF3 9
ACCMFAN0008 A
BLOWER WET COOLING TOWER A FAN 8-SA Yes No Yes No Yes O
H No Yes WF3 5
ACCMPMP0001 B
PUMP AUXILIARY COMPONENT COOLING WATER PUMP B
Yes No Yes No Yes I
No Yes WF3 5
ACCMPMP0001 A
PUMP AUXILIARY COMPONENT COOLING WATER PUMP A
Yes No Yes No Yes I
No Yes WF3 7
ACCMVAAA112 B
VALVE ACC HEADER B TO ESSENTIAL CHILLERS ISOL Yes No Yes No Yes I
No Yes WF3 7
ACCMVAAA112 A
VALVE ACC HEADER A TO ESSENTIAL CHILLERS ISOL Yes No Yes No Yes I
No Yes WF3 7
ACCMVAAA126 B
VALVE ACC HEADER B CCW HX OUTL TEMPERATURE CONTROL VALVE Yes No Yes No Yes I
No Yes WF3 7
ACCMVAAA126 A
VALVE ACC HEADER A CCW HX OUTL TEMPERATURE CONTROL Yes No Yes No Yes I
No Yes WF3 7
ACCMVAAA138 B
VALVE ACC WET COOLING TOWER B CROSS-CONNECT ISOLATION Yes No Yes No Yes O
H No Yes WF3 7
ACCMVAAA138 A
VALVE ACC WET COOLING TOWER A CROSS-CONNECT ISOLATION Yes No Yes No Yes O
H No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 2 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 7
ACCMVAAA139 B
VALVE ACC HEADER B RETURN FROM ESSENTIAL CHILLERS ISOL Yes No Yes No Yes I
No Yes WF3 7
ACCMVAAA139 A
VALVE ACC HEADER A RETURN FROM ESSENTIAL CHILLERS ISOL Yes No Yes No Yes I
No Yes WF3 8
ARMISV0109 VALVE CNTMT ATMOS RAD MONITOR SUCT HDR INSIDE ISOL Yes No Yes No Yes I
T / H No Yes WF3 5
BAMMPMP0001 B
PUMP BORIC ACID PUMP B Yes No Yes No Yes I
Yes Yes WF3 5
BAMMPMP0001 A
PUMP BORIC ACID PUMP A Yes No Yes No Yes I
Yes Yes WF3 21 BAMMTNK0001 B
ACCUMU BORIC ACID MAKEUP TANK B Yes No Yes No Yes I
Yes Yes WF3 21 BAMMTNK0001 A
ACCUMU BORIC ACID MAKEUP TANK A Yes No Yes No Yes I
Yes Yes WF3 8
BAMMVAAA113 B
VALVE BORIC ACID MAKEUP TANK B GRAVITY FEED VALVE Yes No Yes No Yes I
Yes Yes WF3 8
BAMMVAAA113 A
VALVE BORIC ACID MAKEUP TANK A GRAVITY FEED VALVE Yes No Yes No Yes I
Yes Yes WF3 7
BAMMVAAA126 B
VALVE BORIC ACID MAKEUP PUMP B RECIRC VALVE Yes No Yes No Yes I
Yes Yes WF3 7
BAMMVAAA126 A
VALVE BORIC ACID MAKEUP PUMP A RECIRC VALVE Yes No Yes No Yes I
Yes Yes WF3 8
BAMMVAAA133 VALVE EMERGENCY BORATION VALVE Yes No Yes No Yes I
Yes Yes WF3 7
BAMMVAAA141 VALVE BORIC ACID MAKEUP HEADER ACID FLOW CONTROL VALVE Yes No Yes No Yes I
Yes Yes WF3 7
BD MVAAA102 B
VALVE S/G 2 BLOWDOWN INSIDE CONTAINMENT ISOLATION Yes No Yes No Yes I
T / H No Yes WF3 7
BD MVAAA102 A
VALVE S/G 1 BLOWDOWN INSIDE CONTAINMENT ISOLATION Yes No Yes No Yes I
T / H No Yes WF3 7
BD MVAAA103 B
VALVE S/G 2 BLOWDOWN OUTSIDE CONTAINMENT ISOLATION Yes No Yes No Yes I
No Yes WF3 7
BD MVAAA103 A
VALVE S/G 1 BLOWDOWN OUTSIDE CONTAINMENT ISOLATION Yes No Yes No Yes I
No Yes WF3 7
BM MVAAA109 VALVE REACTOR DRAIN TANK OUTLET INSIDE CONTAINMENT ISOL Yes No Yes No Yes I
T / H Yes Yes WF3 20 CABINET C-90B SOUTH OF WALL IN CCW PUMP B Yes No Yes No Yes I
No Yes WF3 7
CAPMVAAA103 VALVE CONTAINMENT PURGE INLET INSIDE ANNULUS Yes No Yes No Yes I
T / H No Yes WF3 7
CAPMVAAA104 VALVE CONTAINMENT PURGE INLET INSIDE CONTAINMENT Yes No Yes No Yes I
T / H No Yes WF3 7
CAPMVAAA203 VALVE CONTAINMENT PURGE EXHAUST INSIDE CONTAINMENT Yes No Yes No Yes I
T / H No Yes WF3 7
CAPMVAAA204 VALVE CONTAINMENT PURGE EXHAUST INSIDE ANNULUS Yes No Yes No Yes I
T / H No Yes WF3 8
CARMVAAA201 B
VALVE CAR EXHAUST HEADER B INLET Yes No Yes No Yes I
T / H No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 3 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 8
CARMVAAA201 A
VALVE CAR EXHAUST HEADER A INLET Yes No Yes No Yes I
T / H No Yes WF3 8
CARMVAAA204 B
VALVE CAR EXHAUST HEADER B DISCHARGE Yes No Yes No Yes I
No Yes WF3 8
CARMVAAA204 A
VALVE CAR EXHAUST HEADER A DISCHARGE Yes No Yes No Yes I
IBISSW CCW SURGE TANK B SIDE LO/LO LEVEL SWITCH Yes No Yes No Yes I
IBISSW CCW SURGE TANK A SIDE LO/LO LEVEL SWITCH Yes No Yes No Yes I
No Yes WF3 8
CC ISV0835 B1 ICNTRL CNTMT FAN COOLERS HDR B CCW RTN TCV SOLENOID VLV Yes No Yes No Yes I
No Yes WF3 9
CC MFAN0001 B
BLOWER DRY COOLING TOWER B FAN 1-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0001 A
BLOWER DRY COOLING TOWER A FAN 1-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0002 B
BLOWER DRY COOLING TOWER B FAN 2-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0002 A
BLOWER DRY COOLING TOWER A FAN 2-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0003 B
BLOWER DRY COOLING TOWER B FAN 3-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0003 A
BLOWER DRY COOLING TOWER A FAN 3-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0004 B
BLOWER DRY COOLING TOWER B FAN 4-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0004 A
BLOWER DRY COOLING TOWER A FAN 4-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0005 B
BLOWER DRY COOLING TOWER B FAN 5-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0005 A
BLOWER DRY COOLING TOWER A FAN 5-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0006 B
BLOWER DRY COOLING TOWER B FAN 6-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0006 A
BLOWER DRY COOLING TOWER A FAN 6-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0007 B
BLOWER DRY COOLING TOWER B FAN 7-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0007 A
BLOWER DRY COOLING TOWER A FAN 7-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0008 B
BLOWER DRY COOLING TOWER B FAN 8-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0008 A
BLOWER DRY COOLING TOWER A FAN 8-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0009 B
BLOWER DRY COOLING TOWER B FAN 9-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0009 A
BLOWER DRY COOLING TOWER A FAN 9-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0010 B
BLOWER DRY COOLING TOWER B FAN 10-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0010 A
BLOWER DRY COOLING TOWER A FAN 10-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0011 B
BLOWER DRY COOLING TOWER B FAN 11-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0011 A
BLOWER DRY COOLING TOWER A FAN 11-SA Yes No Yes No Yes O
H No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 4 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 9
CC MFAN0012 B
BLOWER DRY COOLING TOWER B FAN 12-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0012 A
BLOWER DRY COOLING TOWER A FAN 12-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0013 B
BLOWER DRY COOLING TOWER B FAN 13-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0013 A
BLOWER DRY COOLING TOWER A FAN 13-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0014 B
BLOWER DRY COOLING TOWER B FAN 14-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0014 A
BLOWER DRY COOLING TOWER A FAN 14-SA Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0015 B
BLOWER DRY COOLING TOWER B FAN 15-SB Yes No Yes No Yes O
H No Yes WF3 9
CC MFAN0015 A
BLOWER DRY COOLING TOWER A FAN 15-SA Yes No Yes No Yes O
HTEXCH COMPONENT COOLING WATER HEAT EXCHANGER B Yes No Yes No Yes I
HTEXCH COMPONENT COOLING WATER HEAT EXCHANGER A Yes No Yes No Yes I
No Yes WF3 5
CC MPMP0001 B
PUMP COMPONENT COOLING WATER PUMP B Yes No Yes No Yes I
No Yes WF3 5
CC MPMP0001 A
PUMP COMPONENT COOLING WATER PUMP A Yes No Yes No Yes I
ACCUMU COMPONENT COOLING WATER SURGE TANK Yes No Yes No Yes O
H No Yes WF3 7
CC MVAAA114 B
VALVE CCW PUMP B TO AB SUCTION CROSSCONNECT Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA114 A
VALVE CCW PUMP A TO AB SUCTION CROSSCONNECT Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA115 B
VALVE CCW PUMP AB TO B SUCTION CROSSCONNECT Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA115 A
VALVE CCW PUMP AB TO A SUCTION CROSSCONNECT Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA126 B
VALVE CCW PUMP B TO AB DISCHARGE CROSSCONNECT Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA126 A
VALVE CCW PUMP A TO AB DISCHARGE CROSSCONNECT Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA127 B
VALVE CCW PUMP AB TO B DISCHARGE CROSSCONNECT Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA127 A
VALVE CCW PUMP AB TO A DISCHARGE CROSSCONNECT Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA134 B
VALVE DRY COOLING TOWER B CCW BYPASS Yes No Yes No Yes O
H No Yes WF3 7
CC MVAAA134 A
VALVE DRY COOLING TOWER A CCW BYPASS Yes No Yes No Yes O
H No Yes WF3 7
CC MVAAA135 B
VALVE DRY COOLING TOWER B CCW INLET ISOLATION Yes No Yes No Yes O
H No Yes WF3 7
CC MVAAA135 A
VALVE DRY COOLING TOWER A CCW INLET ISOLATION Yes No Yes No Yes O
H No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 5 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 7
CC MVAAA200 B
VALVE CCW HEADER B TO AB SUPPLY ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA200 A
VALVE CCW HEADER A TO AB SUPPLY ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA301 B
VALVE CCW HEADER B SUPPLY TO ESSENTIAL CHILLERS ISOL Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA301 A
VALVE CCW HEADER A SUPPLY TO ESSENTIAL CHILLERS ISOL Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA322 B
VALVE CCW HEADER B RETURN FROM ESSENTIAL CHILLERS ISOL Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA322 A
VALVE CCW HEADER A RETURN FROM ESSENTIAL CHILLERS ISOL Yes No Yes No Yes I
No Yes WF3 0
CC MVAAA323 B
VALVE CCW Header B Return from Essential Chillers Check Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA501 VALVE CCW NON SAFETY SUPPLY HDR ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA562 VALVE CCW NON SAFETY RETURN HDR ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA563 VALVE CCW HEADER AB TO B RETURN ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA641 VALVE CCW TO CONTAINMENT OUTSIDE CONTAINMENT ISOL Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA713 VALVE CNTMT CCW RETURN HEADER OUTSIDE CNTMT ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA727 VALVE CCW HEADER AB TO A RETURN ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA807 B
VALVE CONTAINMENT FAN COOLER B CCW INLET ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA807 A
VALVE CONTAINMENT FAN COOLER C CCW INLET ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA808 B
VALVE CONTAINMENT FAN COOLER D CCW INLET ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA808 A
VALVE CONTAINMENT FAN COOLER A CCW INLET ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA822 B
VALVE CONTAINMENT FAN COOLER D CCW OUTLET ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA822 A
VALVE CONTAINMENT FAN COOLER A CCW OUTLET ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA823 B
VALVE CONTAINMENT FAN COOLER B CCW OUTLET ISOLATION Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA823 A
VALVE CONTAINMENT FAN COOLER C CCW OUTLET ISOLATION Yes No Yes No Yes I
No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 6 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 7
CC MVAAA835 B
VALVE CNTMT FAN COOLERS TRAIN B TEMPERATURE CONTROL Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA835 A
VALVE CNTMT FAN COOLERS TRAIN A TEMPERATURE CONTROL Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA963 B
VALVE SHUTDOWN HEAT EXCHANGER B CCW FLOW CONTROL Yes No Yes No Yes I
No Yes WF3 7
CC MVAAA963 A
VALVE SHUTDOWN HEAT EXCHANGER A CCW FLOW CONTROL Yes No Yes No Yes I
No Yes WF3 9
CCSMFAN0003 D
BLOWER CONTAINMENT COOLING HVAC AH-1(3D-SB) FAN Yes No Yes No Yes I
T / H No Yes WF3 9
CCSMFAN0003 A
BLOWER CONTAINMENT COOLING HVAC AH-1(3A-SA) FAN Yes No Yes No Yes I
T / H No Yes WF3 7
CCSMVAAA102 B
VALVE CONTAINMENT COOLING HVAC SAFETY DISCHARGE DAMPER B Yes No Yes No Yes I
T / H No Yes WF3 7
CCSMVAAA102 A
VALVE CONTAINMENT COOLING HVAC SAFETY DISCHARGE DAMPER A Yes No Yes No Yes I
T / H No Yes WF3 2
CEDEBKR3917 B
CKTBRK REACTOR TRIP SWGR BREAKER TCB-1 COMPARTMENT 1D Yes No Yes No Yes I
No Yes WF3 2
CEDEBKR3917 A
CKTBRK REACTOR TRIP SWGR BREAKER TCB-5 COMPARTMENT 1B Yes No Yes No Yes I
No Yes WF3 2
CEDEBKR3918 B
CKTBRK REACTOR TRIP SWGR BREAKER TCB-2 COMPARTMENT 2C Yes No Yes No Yes I
No Yes WF3 2
CEDEBKR3918 A
CKTBRK REACTOR TRIP SWGR BREAKER TCB-6 COMPARTMENT 2B Yes No Yes No Yes I
No Yes WF3 2
CEDEBKR3919 CKTBRK REACTOR TRIP SWGR BREAKER TCB-9 COMPARTMENT 3C Yes No Yes No Yes I
No Yes WF3 2
CEDEBKR3920 B
CKTBRK REACTOR TRIP SWGR BREAKER TCB-7 COMPARTMENT 4C Yes No Yes No Yes I
No Yes WF3 2
CEDEBKR3920 A
CKTBRK REACTOR TRIP SWGR BREAKER TCB-3 COMPARTMENT 4B Yes No Yes No Yes I
No Yes WF3 2
CEDEBKR3921 B
CKTBRK REACTOR TRIP SWGR BREAKER TCB-8 COMPARTMENT 5D Yes No Yes No Yes I
No Yes WF3 2
CEDEBKR3921 A
CKTBRK REACTOR TRIP SWGR BREAKER TCB-4 COMPARTMENT 5B Yes No Yes No Yes I
No Yes WF3 5
CHWMPMP0001 B
PUMP CHILLED WATER PUMP B
Yes No Yes No Yes I
No Yes WF3 5
CHWMPMP0001 A
PUMP CHILLED WATER PUMP A
Yes No Yes No Yes I
No Yes WF3 7
CHWMVAAA578 VALVE SWGR AUX SVSMAHU0002-A CHW OUTLET FCV Yes No Yes No Yes I
No Yes WF3 7
CHWMVAAA591 VALVE SWGR MAIN SVSMAHU0001-A CHW OUTLET FCV Yes No Yes No Yes I
No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 7 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 7
CHWMVAAA603 VALVE CONTROL RM HVCMAHU0001-A CHW OUTLET FCV Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
CHWMVAAA900 VALVE SWGR MAIN SVSMAHU0001-B CHW OUTLET FCV Yes No Yes No Yes I
No Yes WF3 7
CHWMVAAA919 VALVE CONTROL RM HVCMAHU0001-B CHW OUTLET FCV Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
CMUISV0407 B
ICNTRL SV FOR CMU-407B Yes No Yes No Yes O
H No Yes WF3 8
CMUISV0407 A
ICNTRL SV FOR CMU-407A Yes No Yes No Yes O
H No Yes WF3 8
CMUISV0524 B
VALVE EGD B JACKET WATER AUTO MAKEUP VALVE Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
CMUISV0524 A
VALVE EDG A JACKET WATER AUTO MAKEUP VALVE Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 5
CMUMPMP0004 B
PUMP COMPONENT COOLING WATER MAKEUP PUMP B
Yes No Yes No Yes I
No Yes WF3 5
CMUMPMP0004 A
PUMP COMPONENT COOLING WATER MAKEUP PUMP A
Yes No Yes No Yes I
No Yes WF3 21 CMUMPOL0001 ACCUMU CONDENSATE STORAGE POOL Yes Yes Yes No Yes I
No Yes WF3 7
CMUMVAAA538 B
VALVE CCW RETURN HEADER B MAKEUP CONTROL VALVE Yes No Yes No Yes I
No Yes WF3 7
CMUMVAAA538 A
VALVE CCW RETURN HEADER A MAKEUP CONTROL VALVE Yes No Yes No Yes I
HTEXCH SHUTDOWN COOLING HEAT EXCHANGER B Yes No Yes No Yes I
HTEXCH SHUTDOWN COOLING HEAT EXCHANGER A Yes No Yes No Yes I
Yes Yes WF3 5
CS MPMP0001 B
PUMP COMPONENT COOLING WATER PUMP B Yes No Yes Y
Yes I
Yes Yes Yes WF3 5
CS MPMP0001 A
PUMP COMPONENT COOLING WATER PUMP AB Yes No Yes Y
Yes I
Yes Yes Yes WF3 7
CS MVAAA125 B
VALVE CONTAINMENT SPRAY HDR B ISOLATION Yes No Yes No Yes I
Yes Yes WF3 7
CS MVAAA125 A
VALVE CONTAINMENT SPRAY HDR A ISOLATION Yes No Yes No Yes I
Yes Yes WF3 8
CVCISV0216 B
VALVE PRESSURIZER AUX SPRAY VALVE B Yes No Yes Y
Yes I
T / H Yes Yes Yes WF3 8
CVCISV0216 A
VALVE PRESSURIZER AUX SPRAY VALVE A Yes No Yes Y
Yes I
T / H Yes Yes Yes WF3 8
CVCISV0218 B
VALVE CHARGING LINE TO RCS LOOP 2A ISOLATION Yes No Yes Y
Yes I
T / H Yes Yes Yes WF3 8
CVCISV0218 A
VALVE CHARGING LINE TO RCS LOOP 1A ISOLATION Yes No Yes Y
Yes I
T / H Yes Yes Yes WF3 21 CVCMHX0001 HTEXCH REGENATIVE HEAT EXCHANGER Yes No Yes No Yes I
T / H Yes Yes Yes WF3 5
CVCMPMP0001 B
PUMP CHEMICAL VOLUME CONTROL CHARGING PUMP B Yes No Yes No Yes I
Yes Yes Yes WF3 5
CVCMPMP0001 A
PUMP CHEMICAL VOLUME CONTROL CHARGING PUMP A Yes No Yes No Yes I
Yes Yes Yes WF3 21 CVCMTNK0002 ACCUMU VOLUME CONTROL TANK Yes No Yes No Yes I
Yes Yes Yes WF3 7
CVCMVAAA101 VALVE LETDOWN STOP VALVE Yes No Yes No Yes I
T / H Yes Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 8 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 7
CVCMVAAA103 VALVE LETDOWN INSIDE CONTAINMENT ISOLATION Yes No Yes No Yes I
T / H Yes Yes Yes Yes WF3 7
CVCMVAAA109 VALVE LETDOWN OUTSIDE CONTAINMENT ISOLATION Yes No Yes No Yes I
Yes Yes Yes Yes WF3 7
CVCMVAAA140 VALVE LETDOWN TO HEAT EXCHANGERS INLET/BYPASS Yes No Yes No Yes I
Yes Yes Yes WF3 8
CVCMVAAA183 VALVE VOLUME CONTROL TANK OUTLET ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 7
CVCMVAAA209 VALVE CHARGING HEADER ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 7
CVCMVAAA401 VALVE RCP CONTROL BLEEDOFF ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 8
CVCMVAAA507 VALVE RWSP TO CHARGING PUMPS SUCTION ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 8
CVRISV0400 VALVE CVR INST UPSTREAM CNTMT ISOL VLV - PEN 53 Yes No Yes Y
Yes I
No Yes WF3 8
CVRISV0401 VALVE CVR INST DOWNSTREAM CNTMT ISOL VLV - PEN 53 Yes No Yes Y
Yes I
No Yes WF3 15 DC EBATA BATTRY 125V BAT & RACK 125VDC BATTERY A-S 60 CELLS Yes No Yes Y
I No Yes Yes Yes Yes Yes WF3 15 DC EBATAB BATTRY 125V BAT & RACK 125VDC BATTERY AB-S 62 CELLS Yes No Yes Y
I No Yes Yes Yes Yes Yes WF3 15 DC EBATB BATTRY 125V BAT & RACK 125VDC BATTERY B-S 60 CELLS Yes No Yes Y
I No Yes Yes Yes Yes Yes WF3 16 DC EBC1A BATTRY BATTERY CHARGER A1 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 16 DC EBC1B BATTRY BATTERY CHARGER B1 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 16 DC EBC2A BATTRY BATTERY CHARGER A2 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 16 DC EBC2B BATTRY BATTERY CHARGER B2 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 14 DC EPDP1A DC PANEL PDP A1-DC Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 14 DC EPDP1B DC PANEL PDP B1-DC Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 14 DC EPDPA DC PANEL PDP A-DC Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 14 DC EPDPAB DC PANEL PDP AB-DC Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 14 DC EPDPB DC PANEL PDP B-DC Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 EDGB RTGB ISOL PNL EDGB RTGB ISOLATION PANEL Yes No Yes Yes I
No Yes Yes Yes Yes Yes WF3 18 EFWIFIS8330 B
IBISSW EMERGENCY FEEDWATER HDR B TO STEAM GENERATOR 2 FIS Yes No Yes No Yes I
No Yes WF3 18 EFWIFIS8330 A
IBISSW EMERGENCY FEEDWATER HDR A TO STEAM GENERATOR 1 FIS Yes No Yes No Yes I
No Yes WF3 18 EFWIFIS8331 B
IBISSW EMERGENCY FEEDWATER HDR A TO STEAM GENERATOR 1 FIS Yes No Yes No Yes I
No Yes WF3 18 EFWIFIS8331 A
IBISSW EMERGENCY FEEDWATER HDR B TO STEAM GENERATOR 2 FIS Yes No Yes No Yes I
No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 9 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 5
EFWMPMP0001 B
PUMP EMERGENCY FEEDWATER PMP B Yes No Yes No Yes I
No Yes WF3 5
EFWMPMP0001 AB PUMP EMERGENCY FEEDWATER PUMP AB Yes No Yes No Yes I
No Yes WF3 5
EFWMPMP0001 A
PUMP EMERGENCY FEEDWATER PMP A Yes No Yes No Yes I
No Yes WF3 7
EFWMVAAA223 B
VALVE EMERGENCY FEEDWATER HDR B TO SG2 BACKUP FLOW CNTRL Yes No Yes No Yes O
H No Yes WF3 7
EFWMVAAA223 A
VALVE EMERGENCY FEEDWATER HDR A TO SG1 BACKUP FLOW CNTRL Yes No Yes No Yes O
H No Yes WF3 7
EFWMVAAA224 B
VALVE EMERGENCY FEEDWATER HDR B TO SG2 PRIMARY FLOW CNTRL Yes No Yes No Yes O
H No Yes WF3 7
EFWMVAAA224 A
VALVE EMERGENCY FEEDWATER HDR A TO SG1 PRIMARY FLOW CNTRL Yes No Yes No Yes O
H No Yes WF3 7
EFWMVAAA228 B
VALVE EMERGENCY FEEDWATER TO SG2 PRIMARY ISOLATION Yes No Yes No Yes O
H No Yes WF3 7
EFWMVAAA228 A
VALVE EMERGENCY FEEDWATER TO SG1 PRIMARY ISOLATION Yes No Yes No Yes O
H No Yes WF3 7
EFWMVAAA229 B
VALVE EMERGENCY FEEDWATER TO SG2 BACKUP ISOLATION Yes No Yes No Yes O
H No Yes WF3 7
EFWMVAAA229 A
VALVE EMERGENCY FEEDWATER TO SG1 BACKUP ISOLATION Yes No Yes No Yes O
H No Yes WF3 20 EG ECP6850 B
PANEL DIESEL GEN B ENGINE CONTROL PANEL Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 EG ECP6850 A
PANEL DIESEL GEN A ENGINE CONTROL PANEL Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 EG ECP6852 B
PANEL DIESEL GEN B CONTROL PANEL Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 EG ECP6852 A
PANEL DIESEL GEN A CONTROL PANEL Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 17 EG MDSG0001 B
GENERA EMERGENCY DIESEL GENERATOR B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 17 EG MDSG0001 A
GENERA EMERGENCY DIESEL GENERATOR A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
EGAISV0411 B
VALVE EG B EMERGENCY MODE FUEL CONTROL
- 2 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
EGAISV0412 B
VALVE EG B EMERGENCY MODE FUEL CONTROL
- 1 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 12 EGAMCMP0001 B
BLOWER EG B AIR COMPRESSOR B1 Yes No Yes No I
No Yes Yes Yes Yes Yes WF3 12 EGAMCMP0001 A
BLOWER EG A AIR COMPRESSOR A1 Yes No Yes No I
No Yes Yes Yes Yes Yes WF3 12 EGAMCMP0002 B
BLOWER EG B AIR COMPRESSOR B2 Yes No Yes No I
No Yes Yes Yes Yes Yes WF3 12 EGAMCMP0002 A
BLOWER EG A AIR COMPRESSOR A2 Yes No Yes No I
No Yes Yes Yes Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 10 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 21 EGAMRCR0001 B
ACCUMU (AIR RECEIVER) EGA AIR RECEIVER B1 Yes No Yes No I
No Yes Yes Yes Yes Yes WF3 21 EGAMRCR0001 A
ACCUMU (AIRECEIVER) EGA AIR RCVR A1 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 21 EGAMRCR0001 A
ACCUMU (AIRECEIVER) EGA AIR RCVR A1 Yes No Yes No I
No Yes Yes Yes Yes Yes WF3 21 EGAMRCR0002 B
ACCUMU (AIR RECEIVER) EGA AIR RECEIVER B2 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 21 EGAMRCR0002 A
ACCUMU (AIR RECEIVER) EGA AIR RECEIVER A2 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 18 EGCILS1980 B
IBISSW EG SEAL WATER STANDPIPE LEVEL Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 18 EGFILT6903 B
IXMITR DIESEL OIL FEED TNK B LVL TRANSMITTER Yes No Yes No Yes O
H No Yes Yes Yes Yes Yes WF3 18 EGFILT6903 A
IXMITR DIESEL OIL FEED TNK A LVL TRANSMITTER Yes No Yes No Yes O
H No Yes Yes Yes Yes Yes WF3 5
EGFMPMP0001 B
PUMP DIESEL OIL TRANSFER PUMP B Yes No Yes No Yes O
H No Yes Yes Yes Yes Yes WF3 5
EGFMPMP0001 A
PUMP DIESEL OIL TRANSFER PUMP A Yes No Yes No Yes O
H No Yes Yes Yes Yes Yes WF3 21 EGFMTNK0001 B
ACCUMU FUEL OIL STORAGE TANK B Yes No Yes No Yes O
H No Yes Yes Yes Yes Yes WF3 21 EGFMTNK0001 A
ACCUMU FUEL OIL STORAGE TANK A Yes No Yes No Yes O
H No Yes Yes Yes Yes Yes WF3 21 EGFMTNK0002 B
ACCUMU EDG B FUEL OIL FEED TANK Yes No Yes No Yes O
H No Yes Yes Yes Yes Yes WF3 21 EGFMTNK0002 A
ACCUMU EDG A FUEL OIL FEED TANK Yes No Yes No Yes O
H No Yes Yes Yes Yes Yes WF3 20 ESFECP0001 B
PANEL ESFAS CABINETS Yes No Yes No Yes I
No Yes WF3 20 ESFECP0001 A
PANEL ESFAS CABINETS Yes No Yes No Yes I
No Yes WF3 0
FW MVAAA1763 B
VALVE FEEDWATER TO EFW HEADER B PRESSURIZING CHECK VALVE Yes No Yes No Yes O
H No Yes WF3 8
FW MVAAA179 B
VALVE FEEDWATER LINE 2 TO BLOWDOWN ISOLATION Yes No Yes No Yes O
H No Yes WF3 8
FW MVAAA179 A
VALVE FEEDWATER LINE 1 TO BLOWDOWN ISOLATION Yes No Yes No Yes O
H No Yes WF3 7
FW MVAAA184 B
VALVE SG 2 MAIN FEEDWATER ISOLATION Yes No Yes Y
Yes O
H No Yes WF3 7
FW MVAAA184 A
VALVE SG 1 MAIN FEEDWATER ISOLATION Yes No Yes Y
Yes O
H No Yes WF3 7
GWMMVAAA104 VALVE CONTAINMENT VENT HEADER INSIDE CONTAINMENT ISOL Yes No Yes No Yes I
T / H No Yes WF3 8
HRAISV0101 B
VALVE CONTAINMENT DOME AREA HRA B SAMPLE ISOLATION Yes No Yes No Yes I
T / H No Yes WF3 8
HRAISV0101 A
VALVE CONTAINMENT DOME AREA HRA A SAMPLE ISOLATION Yes No Yes No Yes I
T / H No Yes WF3 8
HRAISV0109 B
VALVE HRA CNTMT SAMPLE HEADER B INSIDE CONTAINMENT ISOL Yes No Yes No Yes I
T / H No Yes WF3 8
HRAISV0109 A
VALVE HRA CNTMT SAMPLE HEADER A INSIDE CONTAINMENT ISOL Yes No Yes No Yes I
T / H No Yes WF3 8
HRAISV0110 B
VALVE HRA CNTMT SAMPLE HEADER B OUTSIDE CONTAINMENT ISOL Yes No Yes No Yes I
No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 11 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 8
HRAISV0110 A
VALVE HRA CNTMT SAMPLE HEADER A OUTSIDE CONTAINMENT Yes No Yes No Yes I
No Yes WF3 8
HRAISV0126 B
VALVE HRA CONTAINMENT SAMPLE RETURN HEADER B ISOLATION Yes No Yes No Yes I
No Yes WF3 8
HRAISV0126 A
VALVE HRA CONTAINMENT SAMPLE RETURN HEADER A ISOLATION Yes No Yes No Yes I
No Yes WF3 8
HRAISV0201 B
VALVE ANNULUS DOME AREA HRA B SAMPLE ISOLATION Yes No Yes No Yes I
No Yes WF3 8
HRAISV0201 A
VALVE ANNULUS DOME AREA HRA A SAMPLE ISOLATION Yes No Yes No Yes I
No Yes WF3 8
HRAISV0202 B
VALVE HRA ANNULUS SAMPLE RETURN HEADER B ISOLATION Yes No Yes No Yes I
No Yes WF3 8
HRAISV0202 A
VALVE HRA ANNULUS SAMPLE RETURN HEADER A ISOLATION Yes No Yes No Yes I
No Yes WF3 8
HRAISV2011 VALVE CNTMT ATMOS GRAB SAMPLER TO HRA SAMPLE HDR B STOP Yes No Yes No Yes I
No Yes WF3 8
HRAISV20121 VALVE HRA SAMPLE HDR B TO CNTMT ATMOS GRAB SAMPLER STOP Yes No Yes No Yes I
No Yes WF3 9
HVCMAHU0001 A
BLOWER CONTROL ROOM AIR HANDLING UNIT AH-12A Yes No Yes Yes I
No Yes Yes Yes Yes Yes WF3 10 HVCMAHU0009 A
BLOWER CONTROL ROOM EMER FILTRATION UNIT A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 10 HVCMAHU0013 B
BLOWER CONTROL ROOM HVAC ROOM AIR HANDLING UNIT AH-26B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 10 HVCMAHU0013 A
BLOWER CONTROL ROOM HVAC ROOM AIR HANDLING UNIT AH-26A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 9
HVCMFAN0002 B
BLOWER CONTROL ROOM AIR HANDLING UNIT B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 9
HVCMFAN0010 B
BLOWER CONTROL ROOM EMER FILTRATION UNIT B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA101 VALVE CONTROL ROOM NORMAL OAI DOWNSTREAM ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA102 VALVE CONTROL ROOM NORMAL OAI UPSTREAM ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA103 B
VALVE CONTROL ROOM AIR HANDLING UNIT B INLET ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA103 A
VALVE CONTROL ROOM AIR HANDLING UNIT A INLET ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA105 B
VALVE CONTROL ROOM AIR HANDLING UNIT B RECIRC DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA105 A
VALVE CONTROL ROOM AIR HANDLING UNIT A RECIRC DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 12 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 8
HVCMVAAA201 B
VALVE CR EMERG FLTR UNIT NORTH OAI UPSTREAM ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
HVCMVAAA201 A
VALVE CR EMERG FLTR UNIT NORTH OAI UPSTREAM ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
HVCMVAAA202 B
VALVE CR EMERG FLTR UNIT NORTH OAI DOWNSTREAM ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
HVCMVAAA202 A
VALVE CR EMERG FLTR UNIT NORTH OAI DOWNSTREAM ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
HVCMVAAA203 A
VALVE CR EMERG FLTR UNIT SOUTH OAI UPSTREAM ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
HVCMVAAA204 A
VALVE CR EMERG FLTR UNIT SOUTH OAI DOWNSTREAM ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA205 B
VALVE CONTROL ROOM EMERG FLTR B INLET DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA205 A
VALVE CONTROL ROOM EMERG FLTR A INLET DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA304 B
VALVE CONTROL RM TOILET EXH FAN BYPASS DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA304 A
VALVE CONTROL RM TOILET EXH FAN BYPASS DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA306 VALVE CONTROL RM TOILET EXH FAN UPSTREAM EXHAUST DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA307 VALVE CONTROL RM TOILET EXH FAN DNSTREAM EXHAUST DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA313 VALVE KITCHEN/CONFERENCE RM EXH FAN UPSTREAM ISOL Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVCMVAAA314 VALVE KITCHEN/CONFERENCE RM EXH FAN DOWNSTREAM ISOL Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
HVRISV0501 B
ICNTRL DIESEL GENERATOR ROOM B INTK DAMPER SOLENOID VLV Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
HVRISV0501 A4 ICNTRL SV FOR HVR-501A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
HVRISV0501 A3 ICNTRL SV FOR HVR-501A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
HVRISV0501 A2 ICNTRL SV FOR HVR-501A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
HVRISV0501 A1 ICNTRL SV FOR HVR-501A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 10 HVRMAHU0020 A
BLOWER CONTROLLED VENT AREA EXH FAN A Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0022 B
BLOWER RAB+46 HVAC RM AIR HDLNG UNIT AH-13B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 10 HVRMAHU0022 A
BLOWER RAB+46 HVAC RM AIR HNDLG UNIT AH-13A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 10 HVRMAHU0026 B
BLOWER CCW HX ROOM B AIR HANDLING UNIT AH-24B Yes No Yes No Yes I
No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 13 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 10 HVRMAHU0026 A
BLOWER CCW HX ROOM A AIR HANDLING UNIT AH-24A Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0028 B
BLOWER CCW PUMP ROOM B AIR HANDLING UNIT AH-10B Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0028 A
BLOWER CCW PUMP ROOM A AIR HANDLING UNIT AH-10A Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0032 B
BLOWER SHUTDOWN COOLING HX B AIR HANDLING UNIT AH-3B Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0032 A
BLOWER SHUTDOWN COOLING HX A AIR HANDLING UNIT AH-3A Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0034 B
BLOWER SAFEGUARDS ROOM B AIR HANDLING UNIT AH-2B Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0034 A
BLOWER SAFEGUARDS ROOM A AIR HANDLING UNIT AH-2A Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0036 B
BLOWER SAFEGUARDS ROOM B AIR HANDLING UNIT AH-2D Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0036 A
BLOWER SAFEGUARDS ROOM A AIR HANDLING UNIT AH-2C Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0038 B
BLOWER EFW PUMP ROOM B AIR HANDLING UNIT AH-17B Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0038 A
BLOWER EFW PUMP ROOM A AIR HANDLING UNIT AH-17A Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0040 B
BLOWER CHARGING PUMP ROOM B AIR HANDLING UNIT AH-18B Yes No Yes No Yes I
No Yes WF3 10 HVRMAHU0040 A
BLOWER CHARGING PUMP ROOM A AIR HANDLING UNIT AH-18A Yes No Yes No Yes I
No Yes WF3 9
HVRMFAN0021 B
BLOWER CONTROLLED VENT AREA SYS B EXHAUST FAN E-23(3B-SB)
Yes No Yes No Yes I
No Yes WF3 9
HVRMFAN0024 B
BLOWER RAB+46 HVAC ROOM EXHAUST FAN E-41B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 9
HVRMFAN0024 A
BLOWER RAB+46 HVAC ROOM EXHAUST FAN E-41A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 9
HVRMFAN0025 B
BLOWER EDG ROOM B EXHAUST FAN E-28B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 9
HVRMFAN0025 A
BLOWER EDG ROOM A EXHAUST FAN E-28A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVRMVAAA104 VALVE RAB NORMAL SUPPLY TO RB-4 UPSTREAM ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVRMVAAA105 VALVE RAB NORMAL SUPPLY TO RB-4 DOWNSTREAM ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVRMVAAA106 VALVE RAB NORMAL SUPPLY TO CVAS UPSTREAM ISOLATION Yes No Yes No Yes I
No Yes WF3 7
HVRMVAAA107 VALVE RAB NORMAL SUPPLY TO CVAS DOWNSTREAM ISOLATION Yes No Yes No Yes I
No Yes WF3 7
HVRMVAAA108 VALVE CVAS AREAS TO RAB NORMAL EXHAUST UPSTREAM ISOL Yes No Yes No Yes I
No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 14 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 7
HVRMVAAA109 VALVE CVAS AREAS TO RAB NORMAL EXHAUST DOWNSTREAM ISOL Yes No Yes No Yes I
No Yes WF3 7
HVRMVAAA110 VALVE CCW HX RM A PIPE CHASE TO RAB NORM EXH UPSTRM ISOL Yes No Yes No Yes I
No Yes WF3 7
HVRMVAAA111 VALVE CCW HX RM A PIPE CHASE TO RAB NORM EXH DNSTRM ISOL Yes No Yes No Yes I
No Yes WF3 7
HVRMVAAA301 VALVE CVAS AREAS EXHAUST TO CVAS FILTER TRAIN B
Yes No Yes No Yes I
No Yes WF3 7
HVRMVAAA302 VALVE CVAS AREAS EXHAUST TO CVAS FILTER TRAIN A
Yes No Yes No Yes I
No Yes WF3 7
HVRMVAAA303 B
VALVE CVAS FILTER TRAIN B MINIMUM FLOW INLET Yes No Yes No Yes I
No Yes WF3 7
HVRMVAAA303 A
VALVE CVAS FILTER TRAIN A MINIMUM FLOW INLET Yes No Yes No Yes I
No Yes WF3 8
HVRMVAAA304 B
VALVE CVAS FILTER TRAIN B INLET Yes No Yes No Yes I
No Yes WF3 8
HVRMVAAA304 A
VALVE CVAS FILTER TRAIN A INLET Yes No Yes No Yes I
No Yes WF3 8
HVRMVAAA313 B
VALVE CVAS EXHAUST FAN B SUCTION Yes No Yes No Yes I
No Yes WF3 8
HVRMVAAA313 A
VALVE CVAS EXHAUST FAN A SUCTION Yes No Yes No Yes I
No Yes WF3 7
HVRMVAAA403 B
VALVE RCA HVAC ROOM AHU B RECIRC Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVRMVAAA403 A
VALVE RCA HVAC ROOM AHU A RECIRC Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVRMVAAA501 B
VALVE EG B ROOM OUTSIDE AIR INTAKE DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVRMVAAA501 A
VALVE EG A ROOM OUTSIDE AIR INTAKE DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVRMVAAA502 B
VALVE EG B ROOM EXHAUST FAN VARIABLE PITCH BLADE Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
HVRMVAAA502 A
VALVE EG A ROOM EXHAUST FAN VARIABLE PITCH BLADE Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
IA MVAAA909 VALVE IA ISOL TO CONTAINMENT @ PEN
- 9 Yes No Yes No Yes I
No Yes WF3 20 IC EAUX1 PANEL AUXILIARY PANEL 1(SA)
Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC EAUX2 PANEL AUXILIARY PANEL 2(SB)
Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ECP01 PANEL TURBINE CONTROL PANEL Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ECP02 PANEL REACTOR CONTROL PANEL CP2 Yes No Yes No Yes I
No Yes Yes Yes WF3 20 IC ECP04 PANEL CHEMICAL & VOLUME CONTROL PANEL Yes No Yes No Yes I
No Yes Yes WF3 20 IC ECP06 PANEL COMPUTER DISPLAY PANEL Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ECP07 PANEL REACTOR PROTECTION ENGINEERED SAFETY FEATURE Yes No Yes No Yes I
No Yes Yes Yes Yes WF3 20 IC ECP08 PANEL ENGINEERED SAFEGUARD CONTRL PANEL CP8 Yes No Yes No Yes I
No Yes Yes Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 15 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 20 IC ECP10 PANEL PLANT PROTECTION SYSTEM CONTROL PANEL Yes No Yes No Yes I
No Yes WF3 20 IC ECP18 PANEL HVAC, CONTAINMENT ISOLATION CONTROL PANEL Yes No Yes No Yes I
No Yes WF3 20 IC ECP22 PANEL CORE PROTECTION CALCULATORS Yes No Yes No Yes I
No Yes WF3 20 IC ECP25 PANEL PROCESS ANALOG CONTROL PROTECTIVE CHANNEL A Yes No Yes No Yes I
No Yes WF3 20 IC ECP26 PANEL PROCESS ANALOG CONTROL PROTECTIVE CHANNEL B Yes No Yes No Yes I
No Yes WF3 20 IC ECP27 PANEL PROCESS ANALOG CONTROL PROTECTIVE CHANNEL C Yes No Yes No Yes I
No Yes WF3 20 IC ECP28 PANEL PROCESS ANALOG CONTROL PROTECTIVE CHANNEL D Yes No Yes No Yes I
No Yes WF3 20 IC ECP33 PANEL COOLING TOWERS CONTROL PANEL Yes No Yes No Yes I
No Yes WF3 20 IC ECP41 PANEL PROCESS ANALOG CONTROL TRAIN A BOP Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ECP42 PANEL PROCESS ANALOG CONTROL TRAIN A BOP Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ECP43 PANEL PROCESS ANALOG CONTROL TRAIN A/B BOP Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ECP44 PANEL PROCESS ANALOG CONTROL TRAIN B BOP Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ECP45 PANEL PROCESS ANALOG CONTROL TRAIN B BOP Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ECP48 PANEL PROCESS ANALOG CONTROL TRAIN A BOP Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ECP49 PANEL PROCESS ANALOG CONTROL TRAIN B BOP Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ELCP61 PANEL LOCAL CONTROL PANEL PAC LCP-61 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC ELCP62 PANEL LOCAL CONTROL PANEL PAC LCP-62 Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 20 IC EPNLISOL 1
PANEL ISOLATION PANEL Yes No Yes No Yes I
PANEL INSTRUMENT CABINET C-1D Yes No Yes No Yes I
T / H No Yes Yes WF3 18 IC ICDC1 C
PANEL INSTRUMENT CABINET C-1C Yes No Yes No Yes I
T / H No Yes Yes WF3 18 IC ICDC10 PANEL INSTRUMENT CABINET C-10 Yes No Yes No Yes I
T / H No Yes WF3 18 IC ICDC11 B
PANEL INSTRUMENT CABINET C-11B Yes No Yes No Yes I
PANEL INSTRUMENT CABINET C-11A Yes No Yes No Yes I
No Yes Yes WF3 18 IC ICDC12 PANEL INSTRUMENT CABINET C-12 Yes No Yes No Yes I
PANEL INSTRUMENT CABINET C-2B Yes No Yes No Yes I
T / H No Yes WF3 18 IC ICDC2 A
PANEL INSTRUMENT CABINET C-2A Yes No Yes No Yes I
T / H No Yes WF3 18 IC ICDC23 PANEL INSTRUMENT CABINET C-23 Yes No Yes No Yes I
No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 16 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
PANEL INSTRUMENT CABINET C-26B Yes No Yes No Yes I
PANEL INSTRUMENT CABINET C-26A Yes No Yes No Yes I
No Yes Yes WF3 18 IC ICDC31 PANEL INSTRUMENT CABINET C-31 Yes No Yes No Yes I
PANEL INSTRUMENT CABINET C-35A Yes No Yes No Yes I
No Yes WF3 18 IC ICDC39 PANEL INSTRUMENT CABINET C-39 Yes No Yes No Yes No Yes WF3 18 IC ICDC40 PANEL INSTRUMENT CABINET C-40 Yes No Yes No Yes I
No Yes WF3 18 IC ICDC7 PANEL INSTRUMENT CABINET C-7 Yes No Yes No Yes I
T / H No Yes WF3 18 IC ICDC8 PANEL INSTRUMENT CABINET C-8 Yes No Yes No Yes I
T / H No Yes WF3 18 IC ICDC9 PANEL INSTRUMENT CABINET C-9 Yes No Yes No Yes I
T / H No Yes WF3 4
ID EMTA TRANSF BYPASS TRANSFORMER ISOLIMITER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 4
ID EMTB TRANSF BYPASS TRANSFORMER ISOLIMITER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 4
ID EMTMA B
TRANSF SUPS INVERTER MA AC INPUT MAIN TRANSFORMER Yes No Yes No Yes I
No Yes WF3 4
ID EMTMB B
TRANSF SUPS INVERTER MB AC INPUT MAIN TRANSFORMER Yes No Yes No Yes I
No Yes WF3 4
ID EMTMC B
TRANSF SUPS INVERTER MC AC INPUT MAIN TRANSFORMER Yes No Yes No Yes I
No Yes WF3 4
ID EMTMD B
TRANSF SUPS INVERTER MD AC INPUT MAIN TRANSFORMER Yes No Yes No Yes I
No Yes WF3 14 ID EPDP90A PANEL PDP 90A SUPS A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 14 ID EPDP91B PANEL PDP 91B SUPS B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 14 ID EPDPMA PANEL PDP MA NUCLEAR INST CHANNEL A Yes No Yes No Yes I
No Yes WF3 14 ID EPDPMB PANEL PDP MB NUCLEAR INST CHANNEL B Yes No Yes No Yes I
No Yes WF3 14 ID EPDPMC PANEL PDP MC NUCLEAR INST CHANNEL C Yes No Yes No Yes I
No Yes WF3 14 ID EPDPMD PANEL PDP MD NUCLEAR INST CHANNEL D Yes No Yes No Yes I
No Yes WF3 20 LCP-82A FOR 2MS-V602A, MS ISOL VALVE Yes No Yes Yes O
H No Yes Yes WF3 20 LCP-83A,B LCP-83A FOR 2MS-V604B Yes No Yes Yes O
H No Yes Yes WF3 20 LCS E-41(3A-SA)
Yes No Yes Yes I
Yes No Yes Yes O
H No WF3 20 LOC CNTL STA for AH-25(3B-SB)
Yes No Yes Yes I
No WF3 20 LOCAL STR for 2MS-V604B LOCAL STR for 2MS-V604B Yes No Yes Yes O
H No Yes Yes WF3 14 LVDEPDP94A PANEL PDP 94A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 14 LVDEPDP95B PANEL PDP 95B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 0
MS MVAAA106 B
VALVE MAIN STEAM LINE 2 SAFETY #1 Yes No Yes No Yes O
H No Yes WF3 0
MS MVAAA106 A
VALVE MAIN STEAM LINE 1 SAFETY #1 Yes No Yes No Yes O
H No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 17 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 0
MS MVAAA108 B
VALVE MAIN STEAM LINE 2 SAFETY #2 Yes No Yes No Yes O
H No Yes WF3 0
MS MVAAA108 A
VALVE MAIN STEAM LINE 1 SAFETY #2 Yes No Yes No Yes O
H No Yes WF3 7
MS MVAAA110 B
VALVE MAIN STEAM LINE 2 SAFETY #3 Yes No Yes No Yes O
H No Yes WF3 7
MS MVAAA110 A
VALVE MAIN STEAM LINE 1 SAFETY #3 Yes No Yes No Yes O
H No Yes WF3 7
MS MVAAA112 B
VALVE MAIN STEAM LINE 2 SAFETY #4 Yes No Yes No Yes O
H No Yes WF3 7
MS MVAAA112 A
VALVE MAIN STEAM LINE 1 SAFETY #4 Yes No Yes No Yes O
H No Yes WF3 7
MS MVAAA113 B
VALVE MAIN STEAM LINE 2 SAFETY #5 Yes No Yes No Yes O
H No Yes WF3 7
MS MVAAA113 A
VALVE MAIN STEAM LINE 1 SAFETY #5 Yes No Yes No Yes O
H No Yes WF3 7
MS MVAAA114 B
VALVE MAIN STEAM LINE 2 SAFETY #6 Yes No Yes No Yes O
H No Yes WF3 7
MS MVAAA114 A
VALVE MAIN STEAM LINE 1 SAFETY #6 Yes No Yes No Yes O
H No Yes WF3 7
MS MVAAA116 B
VALVE STEAM GENERATOR 2 ATMOSPHERE DUMP VALVE Yes No Yes Yes Yes O
H No Yes WF3 7
MS MVAAA116 A
VALVE STEAM GENERATOR 1 ATMOSPHERE DUMP VALVE Yes No Yes Yes Yes O
H No Yes WF3 8
MS MVAAA119 B
VALVE MSIV 2 UPSTREAM DRIP POT STARTUP DRAIN Yes No Yes No Yes O
H No Yes WF3 8
MS MVAAA119 A
VALVE MSIV 1 UPSTREAM DRIP POT STARTUP DRAIN Yes No Yes No Yes O
H No Yes WF3 8
MS MVAAA120 B
VALVE MSIV 2 UPSTREAM DRIP POT NORMAL DRAIN Yes No Yes No Yes O
H No Yes WF3 8
MS MVAAA120 A
VALVE MSIV 1 UPSTREAM DRIP POT NORMAL DRAIN Yes No Yes No Yes O
H No Yes WF3 7
MS MVAAA124 B
VALVE MAIN STEAM ISOLATION VALVE 2 Yes No Yes No Yes O
H No Yes Yes WF3 7
MS MVAAA124 A
VALVE MAIN STEAM ISOLATION VALVE 1 Yes No Yes No Yes O
H No Yes Yes WF3 8
MS MVAAA401 B
VALVE EFW PUMP AB TURBINE STEAM SUPPLY FROM S/G 2 Yes No Yes No Yes O
H No Yes Yes Yes WF3 8
MS MVAAA401 A
VALVE EFW PUMP AB TURBINE STEAM SUPPLY FROM S/G 1 Yes No Yes No Yes O
H No Yes Yes Yes WF3 18 NG IPIS0940 A
IBISSW NITROGEN HEADER 1 PRESS INDICATING SWITCH Yes No Yes No Yes I
No Yes WF3 18 NG IPIS0941 B
IBISSW NITROGEN HEADER 2 PRESS INDICATING SWITCH Yes No Yes No Yes I
No Yes WF3 18 NG IPIS0942 A
IBISSW NITROGEN HEADER 3 PRESS INDICATING SWITCH Yes No Yes No Yes I
No Yes WF3 18 NG IPIS0943 B
IBISSW NITROGEN HEADER 4 PRESS INDICATING SWITCH Yes No Yes No Yes I
No Yes WF3 18 NG IPIS0944 A
IBISSW NITROGEN HEADER 5 PRESS INDICATING SWITCH Yes No Yes No Yes O
H No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 18 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 18 NG IPIS0945 B
IBISSW NITROGEN HEADER 6 PRESS INDICATING SWITCH Yes No Yes No Yes O
H No Yes WF3 18 NG IPIS0947 B
IBISSW NITROGEN HEADER 8 PRESS INDICATING SWITCH Yes No Yes No Yes O
H No Yes WF3 8
NG ISV0609 VALVE NITROGEN ACCUMULATOR #1 OUTLET STOP Yes No Yes No Yes I
No Yes WF3 8
NG ISV0610 VALVE NITROGEN ACCUMULATOR #2 OUTLET STOP Yes No Yes No Yes I
No Yes WF3 8
NG ISV0709 VALVE NITROGEN ACCUMULATOR #3 OUTLET STOP Yes No Yes No Yes I
No Yes WF3 8
NG ISV0710 VALVE NITROGEN ACCUMULATOR #4 OUTLET STOP Yes No Yes No Yes I
No Yes WF3 8
NG ISV0809 VALVE NITROGEN ACCUMULATOR #5 OUTLET STOP Yes No Yes No Yes O
H No Yes WF3 8
NG ISV0810 VALVE NITROGEN ACCUMULATOR #6 OUTLET STOP Yes No Yes No Yes O
H No Yes WF3 8
NG ISV0909 VALVE NITROGEN ACCUMULATOR #7 OUTLET STOP Yes No Yes No Yes O
H No Yes WF3 8
NG ISV0910 VALVE NITROGEN ACCUMULATOR #8 OUTLET STOP Yes No Yes No Yes O
H No Yes WF3 21 NG MACC0001 ACCUMU NITROGEN ACCUMULATOR #1 Yes No Yes No Yes I
No Yes WF3 21 NG MACC0002 ACCUMU NITROGEN ACCUMULATOR #2 Yes No Yes No Yes I
No Yes WF3 21 NG MACC0003 ACCUMU NITROGEN ACCUMULATOR #3 Yes No Yes No Yes I
No Yes WF3 21 NG MACC0004 ACCUMU NITROGEN ACCUMULATOR #4 Yes No Yes No Yes I
No Yes WF3 21 NG MACC0005 ACCUMU NITROGEN ACCUMULATOR #5 Yes No Yes No Yes O
H No Yes WF3 21 NG MACC0006 ACCUMU NITROGEN ACCUMULATOR #6 Yes No Yes No Yes O
H No Yes WF3 21 NG MACC0007 ACCUMU NITROGEN ACCUMULATOR #7 Yes No Yes No Yes O
H No Yes WF3 21 NG MACC0008 ACCUMU NITROGEN ACCUMULATOR #8 Yes No Yes No Yes O
H No Yes WF3 7
NG MVAAA157 VALVE CONTAINMENT NG SUPPLY OUTSIDE ISOLATION Yes No Yes No Yes I
PANEL PROCESS ANALOG CONTROL POWER ISOLATION PANEL Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
PSLMVAAA105 VALVE RCS HOT LEG #1 SAMPLE INSIDE CONTAINMENT ISOL Yes No Yes No Yes I
T / H Yes Yes WF3 7
PSLMVAAA107 VALVE RCS HOT LEG #1 SAMPLE OUTSIDE CONTAINMENT ISOL Yes No Yes No Yes I
Yes Yes WF3 7
PSLMVAAA203 VALVE PZR SURGE LINE SAMPLE INSIDE CONTAINMENT ISOL Yes No Yes No Yes I
T / H Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 19 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 7
PSLMVAAA204 VALVE PZR SURGE LINE SAMPLE OUTSIDE CONTAINMENT ISOL Yes No Yes No Yes I
Yes Yes WF3 7
PSLMVAAA303 VALVE PZR STEAM SPACE SAMPLE INSIDE CONTAINMENT ISOL Yes No Yes No Yes I
T / H Yes Yes WF3 7
PSLMVAAA304 VALVE PZR STEAM SPACE SAMPLE OUTSIDE CONTAINMENT ISOL Yes No Yes No Yes I
IXMITR REACTOR COOLANT LOOP 2 HOT LEG PRESSURE IXMITR Yes No Yes No Yes I
T / H No Yes WF3 18 RC IPT0106 A
IXMITR REACTOR COOLANT LOOP 1 HOT LEG PRESSURE IXMITR Yes No Yes No Yes I
T / H No Yes WF3 18 RC IPT9120 B
IXMITR PRESSURIZER PRESSURE WIDE RANGE RCS PRESSURE Yes No Yes No Yes I
T / H No Yes WF3 18 RC IPT9120 A
IXMITR PRESSURIZER PRESSURE WIDE RANGE RCS PRESSURE Yes No Yes No Yes I
T / H No Yes WF3 8
RC ISV1014 VALVE REACTOR VESSEL VENT TO QUENCH TANK ISOLATION Yes No Yes No Yes I
T / H Yes Yes WF3 8
RC ISV1015 VALVE REACTOR VESSEL VENT TO QUENCH TANK ISOLATION Yes No Yes No Yes I
T / H Yes Yes WF3 8
RC ISV1017 VALVE REACTOR/PRESSURIZE R VENTS TO QUENCH TANK HDR ISOL Yes No Yes No Yes I
T / H Yes Yes WF3 8
RC ISV3183 VALVE PRESSURIZER VENT TO QUENCH TANK Yes No Yes No Yes I
T / H Yes Yes WF3 8
RC ISV3184 VALVE PRESSURIZER VENT TO QUENCH TANK Yes No Yes No Yes I
T / H Yes Yes WF3 8
RC ISV3186 VALVE REACTOR/PRESSURIZE R VENT TO QUENCH TANK ISOLATION Yes No Yes No Yes I
T / H Yes Yes WF3 19 RC ITE0112 HB1 IXMITR REACTOR COOLANT LOOP 1 HOT LEG TEMPERATURE Yes No Yes No Yes I
T / H No Yes WF3 19 RC ITE0112 HA1 IXMITR REACTOR COOLANT LOOP 1 HOT LEG TEMPERATURE Yes No Yes No Yes I
T / H No Yes WF3 18 RC ITE0112 CB1 IXMITR REACTOR COOLANT LOOP 1B COLD LEG TEMPERATURE Yes No Yes No Yes I
T / H No Yes WF3 19 RC ITE0122 HB1 IXMITR REACTOR COOLANT LOOP 2 HOT LEG TEMPERATURE Yes No Yes Yes Yes I
T / H No Yes WF3 19 RC ITE0122 HA1 IXMITR REACTOR COOLANT LOOP 2 HOT LEG TEMPERATURE Yes No Yes Yes Yes I
T / H No Yes WF3 19 RC ITE0122 CA1 IXMITR REACTOR COOLANT LOOP 2A COLD LEG TEMPERATURE Yes No Yes No Yes I
T / H No Yes WF3 7
RC MVAAA606 VALVE RCP CONTROL BLEEDOFF INSIDE CONTAINMENT ISOL Yes No Yes Yes Yes I
T / H Yes Yes WF3 20 RFRECP3311 3B PANEL WATER CHILLER COMPRESSOR CONTROL PANEL 3B Yes No Yes No Yes I
No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 20 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 20 RFRECP3311 3A PANEL WATER CHILLER COMPRESSOR CONTROL PANEL 3A Yes No Yes No Yes I
No Yes WF3 11 RFRMCHL0001 B
HTEXCH ESSENTIAL CHILLER B Yes No Yes No Yes I
No Yes WF3 11 RFRMCHL0001 A
HTEXCH ESSENTIAL CHILLER A Yes No Yes No Yes I
No Yes WF3 20 SBVEEHC313B 5BL HEATER SBV FILTER TRAIN B ELECTRIC HEATING COIL Yes No Yes Yes I
No Yes Yes Yes Yes Yes WF3 9
SBVMFAN0001 B
BLOWER SBV EXH FAN B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 9
SBVMFAN0001 A
BLOWER SBV EXH FAN A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
SBVMVAAA101 B
VALVE SBV FILTER TRAIN B INLET ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
SBVMVAAA101 A
VALVE SBV FILTER TRAIN A INLET ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
SBVMVAAA110 B
VALVE SBV EXHAUST FAN B SUCTION ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
SBVMVAAA110 A
VALVE SBV EXHAUST FAN A SUCTION ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
SBVMVAAA113 B
VALVE SBV EXHAUST FAN B RECIRC ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
SBVMVAAA113 A
VALVE SBV EXHAUST FAN A RECIRC ISOLATION Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
SBVMVAAA114 B
VALVE SBV EXHAUST FAN B EXHAUST TO PLANT STACK Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 8
SBVMVAAA114 A
VALVE SBV EXHAUST FAN A EXHAUST TO PLANT STACK Yes No Yes No No I
No Yes Yes Yes Yes Yes WF3 18 SG ILT1115 B
IXMITR STEAM GENERATOR 1 LEVEL IXMITR (WIDE RANGE)
Yes No Yes No Yes I
T / H No Yes WF3 18 SG ILT1115 A
IXMITR STEAM GENERATOR 1 LEVEL IXMITR (WIDE RANGE)
Yes No Yes No Yes I
T / H No Yes WF3 18 SG ILT1125 B
IXMITR STEAM GENERATOR 2 LEVEL IXMITR (WIDE RANGE)
Yes No Yes No Yes I
T / H No Yes WF3 18 SG ILT1125 A
IXMITR STEAM GENERATOR 2 LEVEL IXMITR (WIDE RANGE)
Yes No Yes No Yes I
T / H No Yes WF3 18 SG IPT1115 A
IXMITR STEAM GENERATOR 1 PRESSURE TRANSMITTER Yes No Yes No Yes I
T / H No Yes WF3 18 SG IPT1125 B
IXMITR STEAM GENERATOR 2 PRESSURE TRANSMITTER Yes No Yes No Yes I
T / H No Yes WF3 18 SI IFT1306 B
IXMITR RCS LOOP 1 SHDN LINE FLOW LOOP Yes No Yes No Yes I
No Yes Yes WF3 18 SI IFT1307 A
IXMITR RCS LOOP 2 SHDN LINE FLOW TRANSMITTER Yes No Yes No Yes I
No Yes Yes WF3 20 SI IHIS0225 B
IBISSW LCL CNTRL SW FOR CNTRL VLV SI MVAAA225-B Yes No Yes No Yes I
No Yes Yes WF3 20 SI IHIS0225 A
IBISSW LCL CNTRL SW FOR CNTRL VLV SI MVAAA225-A Yes No Yes No Yes I
No Yes Yes WF3 20 SI IHIS0226 B
IBISSW LCL CNTRL SW FOR CNTRL VLV SI MVAAA226-B Yes No Yes No Yes I
No Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 21 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
IBISSW LCL CNTRL SW FOR CNTRL VLV SI MVAAA226-A Yes No Yes No Yes I
No Yes Yes WF3 20 SI IHIS0227 B
IBISSW LCL CNTRL SW FOR CNTRL VLV SI MVAAA227-B Yes No Yes No Yes I
No Yes Yes WF3 20 SI IHIS0227 A
IBISSW LCL CNTRL SW FOR CNTRL VLV SI MVAAA227-A Yes No Yes No Yes I
No Yes Yes WF3 20 SI IHIS0228 B
IBISSW LCL CNTRL SW FOR CNTRL VLV SI MVAAA228-B Yes No Yes No Yes I
No Yes Yes WF3 20 SI IHIS0228 A
IBISSW LCL CNTRL SW FOR CNTRL VLV SI MVAAA228-A Yes No Yes No Yes I
No Yes Yes WF3 18 SI IPS0405 B
IBISSW RCS LOOP 1 SHDN COOL RTN ISOL VLV HYDRLC PRESS SW PMP SHUT-OFF/RE Yes No Yes Yes Yes I
T / H No Yes Yes WF3 18 SI IPS0405 A
IBISSW RCS LOOP 2 SHDN COOL RTN ISOL VLV HYDRLC PRESS SW PMP SHUT-OFF/RE Yes No Yes No Yes I
T / H No Yes Yes WF3 8
SI ISV0307 B
ICNTRL SAFETY INJECTION TANK 1B FILL/DRAIN VALVE SOLENOID Yes No Yes No Yes I
T / H No Yes Yes WF3 8
SI ISV0307 A
ICNTRL SAFETY INJECTION TANK 1A FILL/DRAIN VALVE SOLENOID Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI ISV0323 B
VALVE SAFETY INJECTION TANK 1B VENT Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI ISV0323 A
VALVE SAFETY INJECTION TANK 1A VENT Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI ISV0324 B
VALVE SAFETY INJECTION TANK 2B VENT Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI ISV0324 A
VALVE SAFETY INJECTION TANK 2A VENT Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI ISV0325 B
VALVE SAFETY INJECTION TANK 1B VENT Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI ISV0325 A
VALVE SAFETY INJECTION TANK 1A VENT Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI ISV0326 B
VALVE SAFETY INJECTION TANK 2B VENT Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI ISV0326 A
VALVE SAFETY INJECTION TANK 2A VENT Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI ISV0405 B4 ICNTRL RC LOOP 1 SHDN COOLING ISOLATION VALVE SOLENOID Yes No Yes Yes No I
T / H No Yes Yes WF3 8
SI ISV0405 B3 ICNTRL RC LOOP 1 SHDN COOLING ISOLATION VALVE SOLENOID Yes No Yes Yes No I
T / H No Yes Yes WF3 8
SI ISV0405 B2 ICNTRL RC LOOP 1 SHDN COOLING ISOLATION VALVE SOLENOID Yes No Yes Yes No I
T / H No Yes Yes WF3 8
SI ISV1161 B
VALVE LPSI PUMP B MINIMUM FLOW RECIRC Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI ISV1161 A
VALVE LPSI PUMP A MINIMUM FLOW RECIRC Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI ISV6011 VALVE LPSI A TO RC LOOP 2B UPSTR AUTO VENT ISOL Yes No Yes No Yes I
Yes Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 22 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 8
SI ISV6012 VALVE LPSI A TO RC LOOP 2B DWNSTR AUTO VENT ISOL Yes No Yes No Yes I
Yes Yes Yes WF3 6
SI MPMP0001 B
PUMP LOW PRESSURE SAFETY INJECTION PUMP B Yes No Yes No Yes I
Yes Yes Yes WF3 6
SI MPMP0001 A
PUMP LOW PRESSURE SAFETY INJECTION PUMP A Yes No Yes No Yes I
Yes Yes Yes WF3 5
SI MPMP0002 B
PUMP HIGH PRESSURE SAFETY INJECTION PUMP B Yes No Yes No Yes I
Yes Yes Yes WF3 5
SI MPMP0002 A
PUMP HIGH PRESSURE SAFETY INJECTION PUMP A Yes No Yes No Yes I
Yes Yes Yes WF3 21 SI MPOL0001 ACCUMU REFUELING WATER STRG POOL Yes Yes Yes No Yes I
Yes Yes Yes WF3 7
SI MVAAA106 B
VALVE REFUELING WATER STRG POOL OUTLET HEADER B ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 7
SI MVAAA106 A
VALVE REFUELING WATER STRG POOL OUTLET HEADER A ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 0
SI MVAAA107 B
VALVE REFUELING WATER STRG POOL OUTLET HEADER B CHECK Yes No Yes No Yes I
Yes Yes Yes WF3 0
SI MVAAA1071 B
VALVE LPSI PUMP B SUCTION CHECK Yes No Yes No Yes I
Yes Yes Yes WF3 0
SI MVAAA108 B
VALVE LPSI PUMP B SUCTION CHECK Yes No Yes No Yes I
Yes Yes Yes WF3 0
SI MVAAA116 B
VALVE LPSI PUMP B MINIMUM FLOW RECIRC STOP CHECK Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA120 B
VALVE SI RECIRCULATING HDR B TO RWSP UPSTREAM ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA120 A
VALVE SI RECIRCULATING HDR A TO RWSP UPSTREAM ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA121 B
VALVE SI RECIRCULATING HDR B TO RWSP DOWNSTREAM ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA121 A
VALVE SI RECIRCULATING HDR A TO RWSP DOWNSTREAM ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 0
SI MVAAA122 B
VALVE LPSI PUMP B DISCHARGE CHECK Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA125 B
VALVE SHUTDOWN COOLING HX B INLET Yes No Yes Yes Yes I
Yes Yes Yes WF3 8
SI MVAAA125 A
VALVE SHUTDOWN COOLING HX A INLET Yes No Yes No Yes I
Yes Yes Yes WF3 7
SI MVAAA129 B
VALVE LPSI PUMP B DISCHARGE FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 7
SI MVAAA129 A
VALVE LPSI PUMP A DISCHARGE FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA135 B
VALVE RC LOOP 1 SHDN COOLING WARM-UP Yes No Yes No Yes I
Yes Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 23 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 8
SI MVAAA135 A
VALVE RC LOOP 2 SHDN COOLING WARM-UP Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA138 B
VALVE LPSI HEADER TO RC LOOP 1B FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA138 A
VALVE LPSI HEADER TO RC LOOP 2B FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA139 B
VALVE LPSI HEADER TO RC LOOP 1A FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA139 A
VALVE LPSI HEADER TO RC LOOP 2A FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 0
SI MVAAA201 B
VALVE HPSI PUMP B SUCTION CHECK Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA219 B
VALVE HPSI DISCHARGE HEADER B ORIFICE BYPASS Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA219 A
VALVE HPSI DISCHARGE HEADER A ORIFICE BYPASS Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA225 B
VALVE HPSI HDR B TO RC LOOP 1A FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA225 A
VALVE HPSI HDR A TO RC LOOP 1A FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA226 B
VALVE HPSI HDR B TO RC LOOP 1B FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA226 A
VALVE HPSI HDR A TO RC LOOP 1B FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA227 B
VALVE HPSI HDR B TO RC LOOP 2A FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA227 A
VALVE HPSI HDR A TO RC LOOP 2A FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA228 B
VALVE HPSI HDR B TO RC LOOP 2B FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA228 A
VALVE HPSI HDR A TO RC LOOP 2B FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 7
SI MVAAA301 VALVE RC LOOP 1 HOT LEG INJ LEAKAGE DRAIN Yes No Yes No Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA302 VALVE RC LOOP 2 HOT LEG INJ LEAKAGE DRAIN Yes No Yes No Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA303 B
VALVE SAFETY INJECTION TANK 1B LEAKAGE DRAIN Yes No Yes No Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA303 A
VALVE SAFETY INJECTION TANK 1A LEAKAGE DRAIN Yes No Yes No Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA304 B
VALVE SAFETY INJECTION TANK 2B LEAKAGE DRAIN Yes No Yes No Yes I
T / H Yes Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 24 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 7
SI MVAAA304 A
VALVE SAFETY INJECTION TANK 2A LEAKAGE DRAIN Yes No Yes No Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA307 B
VALVE SAFETY INJECTION TANK 1B FILL/DRAIN Yes No Yes No Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA307 A
VALVE SAFETY INJECTION TANK 1A FILL/DRAIN Yes No Yes No Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA308 B
VALVE SAFETY INJECTION TANK 2B FILL/DRAIN Yes No Yes No Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA308 A
VALVE SAFETY INJECTION TANK 2A FILL/DRAIN Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI MVAAA331 B
VALVE SAFETY INJECTION TANK 1B OUTLET ISOLATION Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI MVAAA331 A
VALVE SAFETY INJECTION TANK 1A OUTLET ISOLATION Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI MVAAA332 B
VALVE SAFETY INJECTINO TANK 2B OUTLET ISOLATION Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI MVAAA332 A
VALVE SAFETY INJECTION TANK 2A OUTLET ISOLATION Yes No Yes No Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA343 VALVE SI TANK DRAIN HEADER TO RWSP ISOLATION Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI MVAAA401 B
VALVE RC LOOP 1 SHDN COOLING UPSTREAM SUCTION ISOL Yes No Yes No Yes I
T / H Yes Yes Yes WF3 8
SI MVAAA401 A
VALVE RC LOOP 2 SHDN COOLING UPSTREAM SUCTION ISOL Yes No Yes No Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA405 B
VALVE RC LOOP 1 SDC SUCTION INSIDE CONTAINMENT ISOL Yes No Yes Yes Yes I
T / H Yes Yes Yes WF3 7
SI MVAAA405 A
VALVE RC LOOP 2 SDC SUCTION INSIDE CONTAINMENT ISOL Yes No Yes Yes Yes I
T / H Yes Yes Yes WF3 8
SI MVAAA407 B
VALVE RC LOOP 1 SDC SUCTION OUTSIDE CONTAINMENT ISOL Yes No Yes Yes Yes I
Yes Yes Yes WF3 8
SI MVAAA407 A
VALVE RC LOOP 2 SDC SUCTION OUTSIDE CONTAINMENT ISOL Yes No Yes Yes Yes I
Yes Yes Yes WF3 8
SI MVAAA412 B
VALVE SHUTDOWN COOLING HX B OUTLET ISOLATION Yes No Yes Yes Yes I
Yes Yes Yes WF3 8
SI MVAAA412 A
VALVE SHUTDOWN COOLING HX A OUTLET ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA415 B
VALVE SHUTDOWN COOLING HX B TEMPERATURE CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA415 A
VALVE SHUTDOWN COOLING HX A TEMPERATURE CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA502 B
VALVE RC LOOP 2 HOT LEG INJ ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA502 A
VALVE RC LOOP 1 HOT LEG INJ ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA506 B
VALVE RC LOOP 2 HOT LEG INJ FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 25 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 8
SI MVAAA506 A
VALVE RC LOOP 1 HOT LEG INJ FLOW CONTROL Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA602 B
VALVE SAFETY INJECTINO SUMP OUTLET HEADER B ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 8
SI MVAAA602 A
VALVE SAFETY INJECTION SUMP OUTLET HEADER A ISOLATION Yes No Yes No Yes I
Yes Yes Yes WF3 0
SI MVAAA604 B
VALVE SAFETY INJECTION SUMP OUTLET HEADER B CHECK Yes No Yes No Yes I
Yes Yes Yes WF3 7
SP MVAAA105 VALVE CONTAINMENT SUMP HEADER INSIDE CNTMT ISOLATION Yes No Yes No Yes I
T / H Yes Yes WF3 7
SP MVAAA106 VALVE CONTAINMENT SUMP HEADER OUTSIDE CNTMT ISOLATION Yes No Yes No Yes I
No Yes WF3 1
SSDEMCC311A PANEL MOTOR CONTROL CENTER 311A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 1
SSDEMCC311AB PANEL MOTOR CONTROL CENTER 311AB Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 1
SSDEMCC311B PANEL MOTOR CONTROL CENTER 311B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 1
SSDEMCC312A PANEL MOTOR CONTROL CENTER 312A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 1
SSDEMCC312B PANEL MOTOR CONTROL CENTER 312B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 1
SSDEMCC313A PANEL MOTOR CONTROL CENTER 313A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 1
SSDEMCC313B PANEL MOTOR CONTROL CENTER 313B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 1
SSDEMCC315A PANEL MOTOR CONTROL CENTER 315A Yes No Yes No Yes O
H No Yes WF3 1
SSDEMCC315B PANEL MOTOR CONTROL CENTER 315B Yes No Yes No Yes O
H No Yes WF3 1
SSDEMCC317 B
PANEL MOTOR CONTROL CENTER 317B Yes No Yes No Yes I
No Yes WF3 1
SSDEMCC317 A
PANEL MOTOR CONTROL CENTER 317A Yes No Yes No Yes I
No Yes WF3 4
SSDEMT315A TRANSF (4160-480/277V XFMR)
STA SERVICE XFMR-3A315S Yes No Yes No Yes O
H No Yes WF3 4
SSDEMT315B TRANSF (4160-480/277V XFMR)
STA SERVICE XFMR-3B315-S Yes No Yes No Yes O
H No Yes WF3 4
SSDEMT31A TRANSF STATION SERVICE 3A31 DISTRIBUTION TRANSFORMER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 4
SSDEMT31B TRANSF (4160-480/277V XFMR)
STA SERVICE XFMR-3B31-S Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 2
SSDESWGR31A PANEL SWITCHGEAR 31A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 2
SSDESWGR31A B
PANEL SWITCHGEAR 31AB Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 2
SSDESWGR31B PANEL SWITCHGEAR 31B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
SSLMVAAA8004 B
VALVE STEAM GEN 2 BLOWDOWN SAMPLE INSIDE CNTMT ISOL Yes No Yes Yes Yes I
T / H No Yes WF3 7
SSLMVAAA8004 A
VALVE STEAM GEN 1 BLOWDOWN SAMPLE INSIDE CNTMT ISOL Yes No Yes Yes Yes I
T / H No Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 26 of 38
Table 1 - Base List 1 (BL 1)
Unit SQUG Equip Type Current Equipment ID SSEL Equipment ID Equipment Description Screen 1 Screen 2 Screen 3 Screen 4 Five Safety Functions Seismic Undergoes Regular Configuration Inspections?
Maintains at least one of the 5 Safety Functions Replaced?
IPEEE Environment?
Reactor Reactivity Control Reactor Coolant Pressure Control Reactor Coolant Inventory Control Decay Heat Removal Containment Function Inside
/
Outside
( I / O )
High Temp
/
Humidity?
( T / H )
Borated System?
WF3 7
SSLMVAAA8006 B
VALVE STEAM GEN 2 BLOWDOWN SAMPLE OUTSIDE CNTMT ISOL Yes No Yes No Yes I
No Yes WF3 7
SSLMVAAA8006 A
VALVE STEAM GEN 1 BLOWDOWN SAMPLE OUTSIDE CNTMT ISOL Yes No Yes No Yes I
No Yes WF3 10 SVSMAHU0001 B
BLOWER SWGR MAIN VENTILATION AIR HANDLING UNIT AH-25B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 10 SVSMAHU0001 A
BLOWER SWGR MAIN VENTILATION AIR HANDLING UNIT AH-25A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 10 SVSMAHU0002 B
BLOWER SWGR AUX VENTILATION AIR HANDLING UNIT AH-30B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 10 SVSMAHU0002 A
BLOWER SWGR AUX VENTILATION AIR HANDLING UNIT AH-30A Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 9
SVSMFAN0003 B
BLOWER COMPUTER BATTERY ROOM EXHAUST FAN B Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 9
SVSMFAN0003 A
BLOWER COMP BATT RM EXHST FAN A E-46(3A-SA)
Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
SVSMVAAA101 VALVE SVS UPSTREAM MAKEUP DAMPER D-65(A)
Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
SVSMVAAA102 VALVE SVS DOWNSTREAM MAKEUP DAMPER D-65(SB)
Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
SVSMVAAA103 B
VALVE SVSMAHU0001B AH-25(3B-SB) INLET DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
SVSMVAAA103 A
VALVE SVSMAHU0001A AH-25(3A-SA) INLET DAMPER Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
SVSMVAAA201 B
VALVE AH-30 SB INLET DAMPER D-50(SB)
Yes No Yes No Yes I
No Yes Yes Yes Yes Yes WF3 7
SVSMVAAA201 A
VALVE AH-30 SA INLET DAMPER D-50(SA)
Yes No Yes No No I
No Yes Yes Yes Yes Yes WF3 8
SBVMVAAA112 B
VALVE SBV EXHAUST FAN B RECIRC CHECK Yes No Yes No No I
No Yes Yes Yes Yes Yes Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 27 of 38
Table 2 - Seismic Walkdown Equipment List 1 (SWEL 1)
SWEL1 #
EQUIPMENT ID DESCRIPTION BLDG.
ELEV.
ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT ANC DWG SWEL1-001 MS MVAAA106 A
VALVE MAIN STEAM LINE 1 SAFETY
- 1 RB
+46 R1 MS 0
O, H N
5817-4718 SWEL1-002 SSDEMCC311B PANEL MOTOR CONTROL CENTER 311B RAB
+21 212 SSD 1
I N
SQ-E-2 SWEL1-003 SSDEMCC315B PANEL MOTOR CONTROL CENTER 315B CTB
-35 B59A SSD 1
O, H N
1564-2118 1564-2119 SWEL1-004 CEDEBKR3918 B
CKTBRK REACTOR TRIP SWGR BREAKER TCB-2 COMPARTMENT 2C RAB
+21 212 CED 2
I N
SQ-NSSS-ICE-3 SWEL1-005 SSDESWGR31AB PANEL SWITCHGEAR 31AB RAB
+21 212B SSD 2
I N
SQ-E-8 SWEL1-006 4KVESWGR3A PANEL SWITCHGEAR 3A RAB
+21 212A 4KV 3
I N
1564-4017 1564-4018 1564-4019 SWEL1-007 ID EMTMD B
TRANSF SUPS INVERTER MD AC INPUT MAIN TRANSFORMER RAB
+21 212A B
ID 4
I Y
1564-1829 SWEL1-008 SSDEMT315B TRANSF (4160-480/277V XFMR) STA SERVICE XFMR-3B315-S RAB
+21 B59A SSD 4
O, H Y
5817-117 SWEL1-009 CC MPMP0001 B
PUMP COMPONENT COOLING WATER PUMP B RAB
+21 233 B
CC 5
I Y
1564-1347 SWEL1-010 EFWMPMP0001 AB PUMP EMERGENCY FEEDWTR PUMP AB RAB
I Y
1564-1493 SWEL1-011 EGFMPMP0001 A
PUMP DIESEL OIL TRANSFER PUMP A RB
-35 B52 A
EGF 5
O, H Y
1564-1224 SWEL1-012 SI MPMP0002 B
PUMP HIGH PRESSURE SAFETY INJECTION PUMP B RAB
-35 B16 B
SI 5
I, B Y
1564-72 SWEL1-013 SI MPMP0001 A
PUMP LOW PRESSURE SAFETY INJECTION PUMP A RAB
-35 B15 A
SI 6
I, B N
1564-85 1564-86 1564-87 SWEL1-014 ACCMVAAA126 B
VALVE ACC HEADER B CCW HX OUTL TEMPERATURE CONTROL VALVE RAB
+21 236 B
ACC 7
I N
5817-2158 5817-2159 SWEL1-015 ACCMVAAA138 A
VALVE ACC WET COOLING TOWER A CROSS-CONNECT ISOLATION CTA
-35 A
ACC 7
O, H N
1564-9924 1564-9925 SWEL1-016 BAMMVAAA126 A
VALVE BORIC ACID MAKEUP PUMP A RECIRC VALVE RAB
-35 B38 A
BAM 7
I, B N
1564-150 SWEL1-017 BD MVAAA103 A
VALVE S/G 1 BLOWDOWN OUTSIDE CONTAINMENT ISOLATION RB
-4 B100 A
BD 7
I N
5817-11962 Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 28 of 38
Table 2 - Seismic Walkdown Equipment List 1 (SWEL 1)
SWEL1 #
EQUIPMENT ID DESCRIPTION BLDG.
ELEV.
ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT ANC DWG SWEL1-018 BM MVAAA109 VALVE REACTOR DRAIN TANK OUTLET INSIDE CONTAINMENT ISOL RCB
-11 421 BM 7
I, T, H, B N
1564-4667 SWEL1-019 CAPMVAAA103 VALVE CONTAINMENT PURGE INLET INSIDE ANNULUS ANN
+21 420 CAP 7
I, T, H N
1564-4379 SWEL1-020 CC MVAAA135 B
VALVE DRY COOLING TOWER B CCW INLET ISOLATION CTB
-35 B60A B
CC 7
O, H N
1564-8424 1564-8431 SWEL1-021 CC MVAAA322 B
VALVE CCW HEADER B RETURN FROM ESSENTIAL CHILLERS ISOL RAB
+21 236 B
CC 7
I N
1564-4045 SWEL1-022 CC MVAAA835 A
VALVE CNTMT FAN COOLERS TRAIN A TEMPERATURE CONTROL RB
-4 B100 A
CC 7
I N
1564-2514 1564-4390 SWEL1-023 CC MVAAA963 A
VALVE SHUTDOWN HEAT EXCHANGER A CCW FLOW CONTROL RAB
-35 B17 A
CC 7
I N
1564-4628 1564-4629 SWEL1-024 CMUISV0407 B
ICNTRL SV FOR CMU-407B CTB
-35 B59A B
CMU 7
O, H N
5817-4614 SWEL1-025 CS MVAAA125 B
VALVE CONTAINMENT SPRAY HDR B ISOLATION RB
-35 B53 B
CS 7
I, B N
1564-3133 SWEL1-026 CVCMVAAA209 VALVE CHARGING HEADER ISOLATION RB
+21 225B CVC 7
I, B N
5817-1776 SWEL1-027 EFWMVAAA223 B
VALVE EMERGENCY FEEDWATER HDR B TO SG2 BACKUP FLOW CNTRL RB
+46 R2 B
EFW 7
O, H N
5817-3745 SWEL1-028 EFWMVAAA229 B
VALVE EMERGENCY FEEDWATER TO SG2 BACKUP ISOLATION RB
+46 R2 A
EFW 7
O, H N
5817-3571 5817-3744 SWEL1-029 HVCMVAAA205 A
VALVE CONTROL ROOM EMERG FLTR A INLET DAMPER RAB
+46 314 A
HVC 7
I N
1564-6628 SWEL1-030 HVRMVAAA107 VALVE RAB NORMAL SUPPLY TO CVAS DOWNSTREAM ISOLATION RAB
-35 B17 HVR 7
I N
1564-8744 5817-3595 SWEL1-031 HVRMVAAA303 A
VALVE CVAS FILTER TRAIN A MINIMUM FLOW INLET RAB
+46 299 A
HVR 7
I N
SQ-HV-42 SWEL1-032 HVRMVAAA502 A
VALVE EG A ROOM EXHAUST FAN VARIABLE PITCH BLADE RAB
+46 304 A
HVR 7
I N
SQ-HV-11 SWEL1-033 IA MVAAA909 VALVE IA ISOL TO CONTAINMENT @
-4 B100 IA 7
I N
1564-3559 Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 29 of 38
Table 2 - Seismic Walkdown Equipment List 1 (SWEL 1)
SWEL1 #
EQUIPMENT ID DESCRIPTION BLDG.
ELEV.
ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT ANC DWG SWEL1-034 MS MVAAA116 A
VALVE STEAM GENERATOR 1 ATMOSPHERE DUMP VALVE RB
+46 R1 A
MS 7
O, H N
5817-232 5817-423 5817-6268 5817-12128 SWEL1-035 MS MVAAA124 B
VALVE MAIN STEAM ISOLATION VALVE 2 RB
+46 R2 B
MS 7
O, H N
1564-3707 SWEL1-036 SI MVAAA129 B
VALVE LPSI PUMP B DISCHARGE FLOW CONTROL RAB
-35 B16 B
SI 7
I, B N
1564-284 SWEL1-037 SI MVAAA307 A
VALVE SAFETY INJECTION TANK 1A FILL/DRAIN RCB
+35 421 A
SI 7
I, T, H, B N
1564-145 SWEL1-038 SI MVAAA405 B
VALVE RC LOOP 1 SDC SUCTION INSIDE CONTAINMENT ISOL RCB
+21 421 B
SI 7
I, T, H, B N
1564-1269 SWEL1-039 SVSMVAAA201 B
VALVE AH-30 SB INLET DAMPER D-50(SB)
+7 B
SVS 7
I, B N
1564-5763 1564-6028 1564-6628 SWEL1-040 BAMMVAAA113 A
VALVE BORIC ACID MAKEUP TANK A GRAVITY FEED VALVE RAB
-35 B38 A
BAM 8
I, B N
SQ-NSSS-PE-24 SWEL1-041 CARMVAAA204 A
VALVE CAR EXHAUST HEADER A DISCHARGE RAB
+46 299 A
CAR 8
I N
1564-4386 SWEL1-042 CHWMVAAA900 VALVE SWGR MAIN SVSMAHU0001-B CHW OUTLET FCV RAB
+46 323 B
CHW 8
I N
5817-2710 SWEL1-043 EGAISV0411 B
VALVE EG B EMERGENCY MODE FUEL CONTROL #2 RAB
+21 222 EGA 8
I N
1564-2080 1564-2081 1564-2082 SWEL1-044 MS MVAAA120 A
VALVE MSIV 1 UPSTREAM DRIP POT NORMAL DRAIN RB
+46 R1 A
MS 8
O, H N
1564-1548 SWEL1-045 MS MVAAA401 A
VALVE EFW PUMP AB TURBINE STEAM SUPPLY FROM S/G 1 RB
+46 300 A
MS 8
O, H N
5817-5815 5817-6914 5817-7250 5817-8170 SWEL1-046 NG ISV0809 VALVE NITROGEN ACCUMULATOR
- 5 OUTLET STOP RB
+46 R1 NG 8
O, H N
5817-5363 5817-5366 5817-5367 5817-6400 SWEL1-047 RC ISV1014 VALVE REACTOR VESSEL VENT TO QUENCH TANK ISOLATION RCB
+46 421 B
RC 8
I, T, H, B N
5817-5362 5817-5369 SWEL1-048 RC ISV3184 VALVE PRESSURIZER VENT TO QUENCH TANK RCB
+46 421 RC 8
I, T, H, B N
5817-5362 5817-5369 SWEL1-049 SBVMVAAA110 A
VALVE SBV EXHAUST FAN A SUCTION ISOLATION RAB
+46 299 A
SBV 8
I N
1564-4384 Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 30 of 38
Table 2 - Seismic Walkdown Equipment List 1 (SWEL 1)
SWEL1 #
EQUIPMENT ID DESCRIPTION BLDG.
ELEV.
ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT ANC DWG SWEL1-050 SBVMVAAA112 B
VALVE SBV EXHAUST FAN B RECIRC CHECK RAB
+46 B
SBV 8
I N
1564-4084 SWEL1-051 SI ISV1161 A
VALVE LPSI PUMP A MINIMUM FLOW RECIRC RAB
-35 B15 SI 8
I, B N
5817-6401 SWEL1-052 SI MVAAA121 A
VALVE SI RECIRCULATING HDR A TO RWSP DOWNSTREAM ISOLATION RB
-35 B53 A
SI 8
I, B N
1564-6618 SWEL1-053 SI MVAAA138 B
VALVE LPSI HEADER TO RC LOOP 1B FLOW CONTROL RB
-35 B53 SI 8
I, B N
1564-142 SWEL1-054 SI MVAAA219 A
VALVE HPSI DISCHARGE HEADER A ORIFICE BYPASS RB
-35 B53 A
SI 8
I, B N
1564-6615 SWEL1-055 SI MVAAA227 B
VALVE HPSI HDR B TO RC LOOP 2A FLOW CONTROL RB
-35 B53 B
SI 8
I, B N
5817-11904 5817-11905 SWEL1-056 SI MVAAA415 B
VALVE SHUTDOWN COOLING HX B TEMPERATURE CONTROL RAB
-35 B16 B
SI 8
I, B N
5817-1419 5817-3594 SWEL1-057 SI MVAAA502 A
VALVE RC LOOP 1 HOT LEG INJ ISOLATION RB
-35 B53 SI 8
I, B N
1564-6617 SWEL1-058 SI MVAAA602 B
VALVE SAFETY INJECTINO SUMP OUTLET HEADER B ISOLATION RB
-35 B53 B
SI 8
I, B N
5817-10933 SWEL1-059 ACCMFAN0002 B
BLOWER WET COOLING TOWER B FAN 2-SB CTB
-35 B60A ACC 9
O, H N
SQ-MN-203 SWEL1-060 CC MFAN0003 A
BLOWER DRY COOLING TOWER A FAN 3-SA CTA
-35 B59A A
CC 9
O, H N
1564-1435 5817-11268 SWEL1-061 HVCMAHU0001 A
BLOWER CONTROL ROOM AIR HANDLING UNIT AH-12A RAB
+46 A
HVC 9
I N
1564-7545 1564-9361 1564-9362 1564-9363 SWEL1-062 HVCMFAN0010 B
BLOWER CONTROL ROOM EMER FILTRATION UNIT B RAB
+46 314 B
HVC 9
I N
1564-5052 SWEL1-063 HVRMFAN0025 A
BLOWER EDG ROOM A EXHAUST FAN E-28A RAB
+46 299 A
HVR 9
I N
1564-4560 SWEL1-064 HVCMAHU0009 A
BLOWER CONTROL ROOM EMER FILTRATION UNIT A RAB
+46 A
HVC 10 I
Y 1564-5051 SWEL1-065 HVRMAHU0028 A
BLOWER CCW PUMP ROOM A AIR HANDLING UNIT AH-10A RAB
+21 235 A
HVR 10 I
N 1564-4586 1564-8953 SWEL1-066 HVRMAHU0032 B
BLOWER SHUTDOWN COOLING HX B AIR HANDLING UNIT AH-3B RAB
-35 B20 B
HVR 10 I
N 1564-4585 SWEL1-067 RFRMCHL0001 B
HTEXCH ESSENTIAL CHILLER B RAB
+46 299 B
RFR 11 I
Y 5817-10990 Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 31 of 38
Table 2 - Seismic Walkdown Equipment List 1 (SWEL 1)
SWEL1 #
EQUIPMENT ID DESCRIPTION BLDG.
ELEV.
ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT ANC DWG SWEL1-068 DC EPDPB DC PANEL PDP B-DC RAB
+21 212B B
DC 14 I
Y SQ-E-1 SWEL1-069 ID EPDPMD PANEL PDP MD NUCLEAR INST CHANNEL D RAB
+21 212 ID 14 I
Y 5817-4678 SWEL1-070 DC EBATB BATTRY 125V BAT & RACK 125VDC BATTERY B-S 60 CELLS RAB
+21 213 B
DC 15 I
Y SQ-E-5 SWEL1-071 DC EBC1A BATTRY BATTERY CHARGER A1 RAB
+21 212 A
DC 16 I
Y 1564-1146 1564-1157 SWEL1-072 EG MDSG0001 B
GENERA EMERGENCY DIESEL GENERATOR B RAB
+21 222 B
EG 17 I
Y 1564-1999 1564-2040 1564-2041 1564-2042 1564-2043 1564-2055 1564-2057 1564-2058 SWEL1-073 CC ILS7011 B
IBISSW CCW SURGE TANK B SIDE LO/LO LEVEL SWITCH RAB
+91 417 B
CC 18 I
N 1564-1489 SWEL1-074 EGFILT6903 A
IXMITR DIESEL OIL FEED TNK A LVL TRANSMITTER RAB
+46 328B EGF 18 O, H Y
1564-7973 SWEL1-075 IC ICDC1 C
PANEL INSTRUMENT CABINET C-1C RCB
+21 421 IC 18 I, T, H N
1564-9155 SWEL1-076 IC ICDC12 PANEL INSTRUMENT CABINET C-12 RB
-4 B145 IC 18 I
N 1564-9210 SWEL1-077 IC ICDC9 PANEL INSTRUMENT CABINET C-9 RCB
+21 421 IC 18 I, T, H N
1564-9158 SWEL1-078 NG IPIS0945 B
IBISSW NITROGEN HEADER 6 PRESS INDICATING SWITCH RB
+46 NG 18 O, H N
5817-5815 5817-7250 5817-8270 SWEL1-079 SG ILT1115 A
IXMITR STEAM GENERATOR 1 LEVEL IXMITR (WIDE RANGE)
RCB
-4 421 SG 18 I, T, H N
5817-5727 SWEL1-080 RC ITE0122 HA1 IXMITR REACTOR COOLANT LOOP 2 HOT LEG TEMPERATURE RCB
-4 423 RC 19 I, T, H N
SQ-IC-6 SWEL1-081 EG ECP6850 B
PANEL DIESEL GEN B ENGINE CONTROL PANEL RAB
+21 222 B
EG 20 I
N 1564-2169 SWEL1-082 ESFECP0001 A
+21 212A ESF 20 I
Y 1564-6395 SWEL1-083 IC EAUX2 PANEL AUXILIARY PANEL 2(SB)
+35 262 B
IC 20 I
N SQ-IC-36 Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 32 of 38
Table 2 - Seismic Walkdown Equipment List 1 (SWEL 1)
SWEL1 #
EQUIPMENT ID DESCRIPTION BLDG.
ELEV.
ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT ANC DWG SWEL1-084 IC ECP08 PANEL ENGINEERED SAFEGUARD CONTRL PANEL CP8 RAB
+46 304 ESF 20 I
N 1564-9337 SWEL1-085 IC ECP22 PANEL CORE PROTECTION CALCULATORS RAB
+46 304 CPC 20 I
N 1564-5421 1564-5422 1564-5423 1564-5424 SWEL1-086 IC ECP26 PANEL PROCESS ANALOG CONTROL PROTECTIVE CHANNEL B RAB
+46 304 PAC 20 I
N 1564-2554 SWEL1-087 IC ELCP61 PANEL LOCAL CONTROL PANEL PAC LCP-61 RAB
+21 212A PAC 20 I
Y 5817-5884 SWEL1-088 RFRECP3311 3B PANEL WATER CHILLER COMPRESSOR CONTROL PANEL 3B RAB
+46 299 B
RFR 20 I
Y SQ-HV-6A SWEL1-089 BAMMTNK0001 A
ACCUMU BORIC ACID MAKEUP TANK A RAB
-35 A
BAM 21 I, B N
1564-427 SWEL1-090 CC MHX0001 A
HTEXCH COMPONENT COOLING WATER HEAT EXCHANGER A RAB
+21 220 A
CC 21 I
Y 1564-1466 SWEL1-091 CC MTNK0001 C
ACCUMU COMPONENT COOLING WATER SURGE TANK RAB
+91 417 CC 21 O, H Y
1564-4554 SWEL1-092 CS MHX0001 A
HTEXCH SHUTDOWN COOLING HEAT EXCHANGER A RAB
-35 B48 A
CS 21 I, B Y
SQ-NSSS-PE-39 SWEL1-093 EGFMTNK0001 A
ACCUMU FUEL OIL STORAGE TANK A RB
-35 A
EGF 21 O, H Y
1564-2525 1564-2526 1564-2527 SWEL1-094 NG MACC0003 ACCUMU NITROGEN ACCUMULATOR
- 3 RAB
+21 NG 21 I
Y SQ-MN-245 SWEL1-095 EGAMCMP0002 A
BLOWER EG A AIR COMPRESSOR A2 RAB
+21 221 A
EGA 12 I
N 1564-2060 5817-9388 SWEL1-096 EGAMRCR0002 A
ACCUMU (AIR RECEIVER) EGA AIR RECEIVER A2 RAB
+21 221 EGA 12 I
Y 1564-2060 5817-9388 SWEL1-097 4KVESWGR3B PANEL SWITCHGEAR 3B RAB
+21 212 B
4KV 3
I N
1564-4013 1564-4014 1564-4331 Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 33 of 38
Table 3 - Base List 2 (BL 2)
BL2#
Equipment ID Description BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R 2001 FS EBKR312A 10F CKTBRK RWSP PURIFICATION PUMP RAB
+21 212A A
FS 2
I 2002 FS EBKR314A 5D CKTBRK FUEL POOL PURIFICATION PUMP FHB
+1 B151 A
FS 2
I 2003 FS EBKR314A 5M CKTBRK FUEL POOL PUMP A FHB
+1 B151 A
FS 2
I 2004 FS EBKR314B 5M CKTBRK FUEL POOL PUMP B FHB
+1 B151 B
FS 2
I 2005 FS EBKR314B 6F CKTBRK REFUELING CANAL DRAIN PUMP FHB
+1 B151 B
FS 2
I 2006 FS EOL312A 10F RELAY RFLG WTR POOL PURIF PUMP TOL RAB
+21 212A FS 2
I 2007 FS EOL314A 5D RELAY FUEL POOL PURIF PUMP TOL FHB
+1 B151 FS 2
I 2008 FS EOL314A 5M RELAY FUEL POOL PUMP A TOL FHB
+1 B151 A
FS 2
I 2009 FS EOL314B 5M RELAY FUEL POOL PUMP B TOL FHB
+1 B152 B
FS 2
I 2010 FS EOL314B 6F RELAY REFUELING CANAL DRAIN PUMP TOL FHB
+1 B152 FS 2
I 2011 FS ITE2010 PIPE FP WATER TO FP PUMPS TEMP ELEMENT THERMOWELL FHB
+1 FS 0
I, B 2012 FS ITE2020 PIPE FUEL POOL HX OUTLET HDR TEMP ELEMENT THERMOWELL FHB
+1 FS 0
I, B 2013 FS MHX0001 HTEXCH FUEL POOL HEAT EXCHANGER TUBE SIDE FHB
+1 FS 21 I, B 2014 FS MHX0002 HTEXCH BACK-UP FUEL POOL HX PO#J11-100014 FHB
-35 FS 21 I, B 2015 FS MPMP0001 A
PUMP FUEL POOL PUMP A FHB
+1 B157 A
FS 5
I, B 2016 FS MPMP0001 B
PUMP FUEL POOL PUMP B FHB
+1 B157 B
FS 5
I, B 2017 FS MSTRN0001 FILTER REFUEL WTR STORAGE POOL OUTLT TO REFUEL WTR PUMP FHB
+1 FS 0
I, B 2018 FS MSTRN0002 FILTER FUEL POOL INLET STRAINER FHB
+1 FS 0
I, B 2019 FS MVAAA101 A
VALVE FUEL POOL PUMP A SUCTION ISOLATION FHB
+1 FS Manual I, B 2020 FS MVAAA101 B
VALVE FUEL POOL PUMP B SUCTION ISOLATION FHB
+1 FS Manual I, B 2021 FS MVAAA102 A
VALVE FUEL POOL PUMP A SUCTION DRAIN FHB
+1 FS Manual I, B 2022 FS MVAAA102 B
VALVE FUEL POOL PUMP B SUCTION DRAIN FHB
+1 FS Manual I, B 2023 FS MVAAA103 A
VALVE FUEL POOL PUMP A DISCH LINE FS IPI0401 RT FHB
+1 FS Manual I, B 2024 FS MVAAA103 B
VALVE FUEL POOL PUMP B DISCH LINE FS IPI0402 RT FHB
+1 FS Manual I, B 2025 FS MVAAA104 A
VALVE FUEL POOL PUMP A DISCHARGE CHECK FHB
+1 B156 FS Check I, B 2026 FS MVAAA104 B
VALVE FUEL POOL PUMP B DISCHARGE CHECK FHB
+1 B157 FS Check I, B 2027 FS MVAAA105 A
VALVE FUEL POOL PUMP A DISCHARGE DRAIN FHB
+1 FS Manual I, B 2028 FS MVAAA105 B
VALVE FUEL POOL PUMP B DISCHARGE DRAIN FHB
+1 FS Manual I, B 2029 FS MVAAA106 A
VALVE FUEL POOL PUMP A DISCHARGE ISOLATION FHB
+1 FS Manual I, B 2030 FS MVAAA106 B
VALVE FUEL POOL PUMP B DISCHARGE ISOLATION FHB
+1 FS Manual I, B 2031 FS MVAAA107 VALVE FUEL POOL PUMPS DISCHARGE HEADER FS IPS0403 ROOT FHB
+1 FS Manual I, B 2032 FS MVAAA108 VALVE FUEL POOL PUMPS DISCHARGE HEADER VENT FHB
+1 FS Manual I, B 2033 FS MVAAA1081 VALVE FUEL POOL HEAT EXCHANGER TUBE SIDE VENT FHB
+1 FS Manual I, B 2034 FS MVAAA10811 VALVE FUEL POOL HEAT EXCHANGER INLET ISOLATION FHB
+1 FS Manual I, B 2035 FS MVAAA1082 VALVE FUEL POOL HEAT EXCHANGER TUBE SIDE DRAIN FHB
+1 FS Manual I, B 2036 FS MVAAA109 VALVE FUEL POOL HEAT EXCHANGER OUTLET LINE DRAIN FHB
+1 FS Manual I, B 2037 FS MVAAA110 VALVE FUEL POOL HEAT EXCHANGER OUTLET ISOLATION FHB
+1 FS Manual I, B 2038 FS MVAAA111 VALVE FUEL POOL HEAT EXCHANGERS OUTLET HEADER VENT FHB
+1 FS Manual I, B 2039 FS MVAAA404 VALVE FUEL POOL ION EXCHANGER TO RWSP ISOLATION RB
-4 B100 FS Manual I, B 2040 FS MVAAA405 VALVE FP IX TO REFUELING CAVITY OUTSIDE CONTAINMENT ISOL RB
-4 FS Manual I, B 2041 FS MVAAA406 VALVE FP IX TO REFUELING CAVITY INSIDE CONTAINMENT ISOL RCB
-4 FS Manual I, B 2042 FS MVAAA415 VALVE REFUELING CAVITY DRN PUMP INSIDE CONTAINMENT ISOL RCB
-4 FS Manual I, B 2043 FS MVAAA416 VALVE REFUELING CAVITY DRN PUMP OUTSIDE CONTAINMENT ISOL RB
-4 FS Manual I, B 2044 FS MVAAA422 VALVOP REFUELING CAVITY DRN PUMP TO RWSP ISOLATION R
-4 FS Manual I, B 2045 FS MVAAA422 VALVE REFUELING CAVITY DRN PUMP TO RWSP ISOLATION RB
-4 FS Manual I, B 2046 FS MVAAA423 VALVE RWSP PURIFICATION PUMP SUCTION ISOL FROM RWSP RB
-35 FS Manual I, B 2047 FS MVAAA423 VALVOP RWSP PURIFICATION PUMP SUCTION ISOL FROM RWSP RB
-4 FS Manual I, B Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 34 of 38
Table 3 - Base List 2 (BL 2)
BL2#
Equipment ID Description BLDG. ELEV. ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R 2048 FS MVAAA601 VALVE BACK-UP FUEL POOL HX INLET ISOLATION FHB
-35 FS Manual I, B 2049 FS MVAAA602 VALVE BACK-UP FUEL POOL HX INLET DRAIN FHB
-35 FS Manual I, B 2050 FS MVAAA603 VALVE BACK-UP FUEL POOL HX INLET TUBE SIDE DRAIN FHB
-35 FS Manual I, B 2051 FS MVAAA604 VALVE BACK-UP FUEL POOL HX U-TUBE SIDE DRAIN FHB
-35 FS Manual I, B 2052 FS MVAAA605 VALVE BACK-UP FUEL POOL HX OUTLET TUBE SIDE VENT FHB
-35 FS Manual I, B 2053 FS MVAAA606 VALVE BACK-UP FUEL POOL HX U-TUBE SIDE VENT FHB
-35 FS Manual I, B 2054 FS MVAAA607 VALVE BACK-UP FUEL POOL HX OUTLET LINE VENT FHB
-35 FS Manual I, B 2055 FS MVAAA608 VALVE BACK-UP FUEL POOL HX OUTLET ISOLATION FHB
-35 FS Manual I, B 2056 FS EBKR45AB 16 CKTBRK FUEL POOL LEVEL ALARM HORN RAB
+35 262 FS 14 I
2057 FS ILS2000 IBISSW FUEL POOL WATER HIGH LEVEL SWITCH FHB
+46 F361 FS 0
I, B 2058 FS ILS2000 A1 IBISSW FUEL POOL WATER LOW LEVEL SWITCH FHB
+46 F361 FS 0
I, B 2059 FS ILS2000 A2 IBISSW FUEL POOL WATER LOW LEVEL SWITCH FHB
+46 F361 FS 0
I, B 2060 FS EREL0631 A
RELAY FUEL POOL LOW LEVEL ALARM RL1 RELAY FHB
+46 F361 FS 0
I 2061 FS EREL0631 B
RELAY FUEL POOL LOW-LOW LEVEL TRIP RLL1 RELAY FHB
+46 F361 FS 0
I 2062 CC MVAAA620 VALVE FUEL POOL HEAT EXCH'S TEMPERATURE CONTROL FHB
+1 B161 FS, CCW 7
I 2063 CC EBKR90A 21 CKTBRK MAIN FUEL POOL HX TCV CHANNEL A SOL (CC-620)
+35 262 A
FS, CCW 14 I
2064 CC EBKR91B 21 CKTBRK MAIN FUEL POOL HX TCV CHANNEL B SOL (CC-620)
+35 262 B
FS, CCW 14 I
2065 CC ISV0620 1
ICNTRL SV FOR CC-620 FHB
+1 B161 FS, CCW 8
I 2066 CC ISV0620 2
ICNTRL SV FOR CC-620 FHB
+1 B161 FS, CCW 8
I 2067 CC MPMP0001 A
PUMP COMPONENT COOLING WATER PUMP A RAB
+21 235 A
FS, CCW 5
I 2068 CC MPMP0001 AB PUMP COMPONENT COOLING WATER PUMP AB RAB
I 2069 CC MPMP0001 B
PUMP COMPONENT COOLING WATER PUMP B RAB
+21 233 B
FS, CCW 5
I 2070 CC EMTR3A 2
MOTOR COMPONENT COOLING WATER PUMP A RAB
+21 235 A
FS, CCW 5
I 2071 CC EMTR3AB 4
MOTOR COMPONENT COOLING WATER PUMP AB RAB
I 2072 CC EMTR3B 81 MOTOR COMPONENT COOLING WATER PUMP B RAB
+21 233 B
FS, CCW 5
I 2073 FS EMTR314A 5M MOTOR FUEL POOL PUMP A MOTOR FHB
+1 B156 A
FS 5
I 2074 FS EMTR314B 5M MOTOR FUEL POOL PUMP B MOTOR FHB
+1 B157 B
FS 5
I 2075 FS EMTR314B 6F MOTOR REFUELING CANAL DRAIN PMP MOTOR FHB
-35 B58 B
FS 5
I Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 35 of 38
Table 4 - Rapid Drain-Down List (RDD)
RDD#
DESCRIPTION BASIS FOR INCLUSION/EXCLUSION RDD R-01 3FS1-35 PIPE FUEL POOL COOLING PIPING VENTS AND INST.
TAPS These small lines are not attached to the spent fuel pool or to larger lines that can drain the fuel pool. See drawings 4305-4425 and 4305-4433.
N R-02 3FS1-55 PIPE FUEL POOL CLG. LOOP DRAIN AND LOC SAMPLES These small lines are not attached to the spent fuel pool or to larger lines that can drain the fuel pool. See drawing 4305-4425.
N R-03 3FS10-2 A
PIPE FUEL POOL PUMP A SUCTION Connected to 3FS12-1A/B header. Plain end of header in spent fuel pool at elevation 40- 6 will prevent drain down of the pool. See drawings 4305-4423 and 4305-4424.
N R-04 3FS10-3 B
PIPE FUEL POOL PUMP B SUCTION Connected to 3FS12-1A/B header. Plain end of header in spent fuel pool at elevation 40 - 6 will prevent drain down of the pool. See drawings 4305-4423 and 4305-4424.
N R-05 3FS10-4 A
PIPE FUEL POOL PUMP A DISCH TO FUEL POOL HT EXCH Line not attached to pool where it could cause drain down. See drawing 4305-4425.
N R-06 3FS10-5 B
PIPE FUEL POOL PUMP B DISCH TO FUEL POOL HT EXCH Line not attached to pool where it could cause drain down. See drawing 4305-4425.
N R-07 3FS10-76 A/B PIPE TO SUPPLEMENTAL FUEL POOL HEAT EXCH.
Line not attached to pool where it can cause drain down. Runs between line 3FS12-6A/B and FS MHX0002 (BACKUP HEAT EXCHANGER). See drawing G169 and 4305-4425.
N R-08 3FS12-1 A/B PIPE FUEL POOL PUMPS SUCTION HDR FROM SPENT FUEL POOL Plain end at elevation 40-6 where it enters the pool. This line cannot drain down the pool. See drawings 4305-4423, 4305-4424, and G169.
N.
R-09 3FS12-6 A/B PIPE FUEL POOL PMPS COMB DISCH HDR UPST.F.P.
HEAT EXCH Line not attached to pool where it could cause drain down. See drawing 4305-4425.
N R-10 3FS12-7 A/B PIPE FUEL POOL PMPS DISCH HDR DWSTM.F.P.HEAT EXCH.
Holes in pipe at elevation 40'-6" inside the fuel pool will prevent drain down. See drawings 4305-4433 and G169. Also, see EC 5000083767.
N R-11 3FS12-51 A/B PIPE DELETED PER DC-3465 Line is removed by DC 3465. See drawing 4305-4433 and EC 5000083767.
N R-12 7FS0 3/4-72 PIPE REFUEL CANAL DR PUMP STRN DRAIN LINE Connected to fuel pool through line 7FS4-45, which can cause rapid drain down. Therefore, this line is included in RDD list. See drawing V8.4-1001-11.
Y R-13 7FS1-36 PIPE F.P.PURIF. LOOP VENTS AND INSTRUMENT TAPS This line is not connected to the spent fuel pool. Also, it is not attached to lines 7FS4-45, 7FS4-46, 7FS4-47, or 7FS0 3/4-72. See drawings 4305-4431 and 4305-4445.
N R-14 7FS1-56 PIPE FUEL POOL PURIF.LOOP DR AND LOC. SAMPLES.
This line is not connected to the spent fuel pool. Also, it is not attached to lines 7FS4-45, 7FS4-46, 7FS4-47, or 7FS0 3/4-72. See drawing 4305-4445.
N R-15 7FS1-57 PIPE FUEL POOL SYS DR. LOC SAMPLES VENTS & INST TAPS This line is not connected to the spent fuel pool. Also, it is not attached to lines 7FS4-45, 7FS4-46, 7FS4-47, or 7FS0 3/4-72. See drawings 4305-4431 and V8.4-1001-16.
N R-16 7FS2-21 PIPE FUEL POOL SKIMMER LINE Plain end on pipe at elevation 43' -0 7/8" inside the spent fuel pool will prevent drain down. See drawings V8.4-1001-13, 4305-4428, G169, EC 5000083763, and EC 5000083770.
N R-17 7FS2-50 PIPE SPENT FUEL CASK DECON PIT TO FHB SUMP This line is not connected to the spent fuel pool. Also, it is not attached to lines 7FS4-45, 7FS4-46, 7FS4-47, or 7FS0 3/4-72. See drawing V8.4-1001-12.
N R-18 7FS3-8 PIPE FUEL POOL PURIF. PUMP SUCT FROM FUEL POOL Plain end on pipe at elevation 40'-6" inside the spent fuel pool will prevent drain down. See drawings G169, 4305-4428, and EC 5000083763.
N R-19 7FS3-13 PIPE FUEL POOL ION EXCH OUTLET DOWNSTREAM OF STRAINER Plain end on pipe at elevation 42'-6" inside the spent fuel pool will prevent drain down. See drawings G169 and 4305-4431.
N R-20 7FS3-19 PIPE SPENT FUEL POOL M.U. FROM R.W.A. VIA CCW M.U.
PUMP Plain end on pipe at elevation 42'-6" inside the spent fuel pool will prevent drain down. See drawings G169 AND 4305-4435.
N R-21 7FS3-20 PIPE FUEL POOL PURIF. PUMP PRIMING LINE DOWNSTREAM This line is not connected to the spent fuel pool. Also, it is not attached to lines 7FS4-45, 7FS4-46, 7FS4-47, or 7FS0 3/4-72. See drawings 4305-4435 and G169.
N R-22 7FS3-22 PIPE DELETED PER DC-3465 Line is removed by DC 3465. See drawing 4305-4428 and EC 5000083763.
N R-23 7FS3-23 PIPE DELETED PER DC-3465 Line is removed by DC 3465. See drawing 4305-4428 and EC 5000083763.
N R-24 7FS3-44 PIPE REFUEL CANAL & SPT. FUEL CASK STOR DR. PUMP DISCH.
Bottom of pipe at elevation 42'-6" inside fuel pool will prevent drain down of the pool. See drawings 4305-4445 and G169.
N R-25 7FS4-45 PIPE REFUEL CANAL DRAIN PUMP SUCTION This is attached to a drain in the bottom of the refuel canal. This can result in a drain down of the pool to near the top of the fuel bundles. See drawings 4305-4446, G874 S02, and EC 5000084044.
Y Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 36 of 38
Table 4 - Rapid Drain-Down List (RDD)
RDD#
DESCRIPTION BASIS FOR INCLUSION/EXCLUSION RDD R-26 7FS4-46 PIPE SPENT FUEL CASK STORAGE TO DRAIN PUMP SUCTION The drain in the Cask Storage Area is covered with a welded plate. However, this line is connected directly to line 7FS4-45 which can cause a drain down of the pool. See drawings 4305-4446, G874 S02, and EC 5000084044.
Y R-27 7FS4-47 PIPE SPEN FUEL CASK DECONTAM. PIT This line is connected to 7FS4-46 which does have the capability to cause rapid drain down of the pool. See drawing 4305-4446.
Y R-28 FS MPMP0002 PUMP REFUELING CANAL DRAIN PUMP Line 7FS4-45, which can cause a rapid drain of the pool, is attached to the suction on this pump.
See drawing 4305-4446.
Y Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 37 of 38
Table 5 - Seismic Walkdown Equipment List 2 (SWEL 2)
SWEL2#
EQUIPMENT ID DESCRIPTION BLDG. ELEV ROOM TRAIN SYSTEM TYPE CLASS ENVIRONMENT N/R RDD SWEL2-001 FS EBKR314A 5D CKTBRK FUEL POOL PURIFICATION PUMP FHB
+1 B151 A
FS 1
I N/A SWEL2-002 FS EBKR314A 5M CKTBRK FUEL POOL PUMP A FHB
+1 B151 A
FS 1
I N/A SWEL2-003 FS EBKR314B 6F CKTBRK REFUELING CANAL DRAIN PUMP FHB
+1 B151 B
FS 1
I N/A SWEL2-004 CC EBKR90A 21 CKTBRK MAIN FUEL POOL HX TCV CHANNEL A SOL (CC-620)
+35 262 A
CC 14 I
N/A SWEL2-005 CC EBKR91B 21 CKTBRK MAIN FUEL POOL HX TCV CHANNEL B SOL (CC-620)
+35 262 B
CC 14 I
N/A SWEL2-006 FS EBKR314B 5M CKTBRK FUEL POOL PUMP B FHB
+1 B151 B
FS 1
I N/A SWEL2-007 FS EOL314A 5M RELAY FUEL POOL PUMP A TOL FHB
+1 B151 A
FS 1
I N/A SWEL2-008 FS EOL314B 5M RELAY FUEL POOL PUMP B TOL FHB
+1 B152 B
FS 1
I N/A SWEL2-009 FS EOL314B 6F RELAY REFUELING CANAL DRAIN PUMP TOL FHB
+1 B152 FS 1
I N/A SWEL2-010 CC EMTR3A 2
MOTOR COMPONENT COOLING WATER PUMP A RAB
+21 235 A
CC 5
I N/A SWEL2-011 CC MPMP0001 A
PUMP COMPONENT COOLING WATER PUMP A RAB
+21 235 A
CC 5
I N/A SWEL2-012 FS EMTR314A 5M MOTOR FUEL POOL PUMP A MOTOR FHB
+1 B156 A
FS 5
I N/A SWEL2-013 FS EMTR314B 5M MOTOR FUEL POOL PUMP B MOTOR FHB
+1 B157 B
FS 5
I N/A SWEL2-014 FS EMTR314B 6F MOTOR REFUELING CANAL DRAIN PMP MOTOR FHB
-35 B58 B
FS 5
I N/A SWEL2-015 FS MPMP0001 A
PUMP FUEL POOL PUMP A FHB
+1 B157 A
FS 5
I / B N/A SWEL2-016 FS MPMP0001 B
PUMP FUEL POOL PUMP B FHB
+1 B157 B
FS 5
I / B N/A SWEL2-017 CC MVAAA620 VALVE FUEL POOL HEAT EXCH'S TEMPERATURE CONTROL FHB
+1 B161 CC 7
I N/A SWEL2-018 CC ISV0620 1
ICNTRL SV FOR CC-620 FHB
+1 B161 CC 8
I N/A SWEL2-019 CC ISV0620 2
ICNTRL SV FOR CC-620 FHB
+1 B161 CC 8
I N/A SWEL2-020 FS MHX0001 HTEXCH FUEL POOL HEAT EXCHANGER TUBE SIDE FHB
+1 FS 21 I / B N/A SWEL2-021 FS MHX0002 HTEXCH BACK-UP FUEL POOL HX PO#J11-100014 FHB
-35 FS 21 I / B N/A SWEL2-022 7FS0 3/4-72 PIPE REFUEL CANAL DR PUMP STRN DRAIN LINE FHB FS 0
I / B R-12 SWEL2-023 7FS4-45 PIPE REFUEL CANAL DRAIN PUMP SUCTION FHB FS 0
I / B R-25 SWEL2-024 7FS4-46 PIPE SPENT FUEL CASK STORAGE TO DRAIN PUMP SUCTION FHB FS 0
I / B R-26 SWEL2-025 7FS4-47 PIPE SPENT FUEL CASK DECONTAM PIT FHB FS 0
I / B R-27 SWEL2-026 FS MPMP0002 PUMP REFUELING CANAL DRAIN PUMP FHB
-35 B58 FS 5
I / B R-28 Engineering Report No. WF3-CS-12-00003 Attachment B Rev. 0 Page 38 of 38