ML042890080

TVA/BFN-01-R-004, Rev 0, Browns Ferry Nuclear Plant Unit 1, USI-46 Seismic Evaluation Report

ML042890080
Person / Time
Site:	Browns Ferry
Issue date:	09/23/2004
From:	Dizon J, Eder S Facility Risk Consultants
To:	Office of Nuclear Reactor Regulation, Tennessee Valley Authority
References
TVA/BFN-01, USI A-46 TVA/BFN-01-R-004, Rev 0
Download: ML042890080 (179)

Text

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TVA/BFN-01 -R-004 Revision 0 September 23, 2004 BROWNS FERRY NUCLEAR PLANT UNIT 1 USI A-46 SEISMIC EVALAUTION REPORT Prepared for:

BROWNS FERRY UNIT 1 RESTART PROJECT Prepared by:

FACILITY RISK CONSULTANTS, INC.

Page i FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 APPROVAL COVER SHEET

Title:

Browns Ferry Nuclear Plant Unit 1 USI A-46 Seismic Evaluation Report Report Number:

TVA/BFN-01-R-004 Client:

Browns Ferry Unit 1 Restart Project Project Number:

TVA/BFN-01 Or~~~~~....eion.

R v'ision:

Number Date Prepared Reviewed 0

9/23/04 O

Stephen J. Eder John 0. Dizon Richard D. cutsinger Page ii FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01-R-004 Revision 0 September 23, 2004 TABLE OF REVISIONS A--s--- ; -.ac

........... -.............XXX--

Revision No.

De scriptionofRevision Date

'1:::::-::.:':.:

0 ORIGINAL ISSUE 9123104 This report contains 178 pages total Page iii FACILIMY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 EXECUTIVE

SUMMARY

The Browns Ferry Nuclear Plant Unit 1 (BFN-1) seismic evaluation for Unresolved Safety Issue (USI) A-46 was performed in accordance with the appropriate industry guidance documents developed by the Seismic Qualification Utility Group (SQUG) and the Electric Power Research Institute (EPRI), and approved by the Nuclear Regulatory Commission (NRC). The evaluation was performed in a manner similar to that performed for resolution of USI A-46 for BFN-2 and BFN-3. The evaluation utilized the BFN design basis earthquake and design basis in-structure acceleration response spectra for seismic demand definition.

In summary, the evaluation results and findings are as follows:

Mechanical and Electrical Equipment The composite safe shutdown equipment list contains 900 items of mechanical and electrical equipment. The composite safe shutdown equipment list will be reviewed by the BFN-1 operations group for consistency with BFN-1 plant operating procedures.

The seismic review safe shutdown equipment list contains 523 items of electrical and mechanical equipment. The seismic review safe shutdown equipment list includes the items from the composite safe shutdown equipment list, excluding the 128 items that are inherently rugged (such as check valves) and 18 items associated with the LPCI M-G sets that are being elirminated by DCN 51216; and excluding the 234 items of equipment that were previously evaluated in the BFN-2 and BFN-3 program which are not located in the BFN-1 Reactor Building, Control Bay, and Turbine Building.

A total of 53 individual Outlier Seismic Verification Sheet (OSVS) forms were written, documenting a total of 84 individual items of mechanical and electrical equipment on the SSEL as outliers.

• These outliers were resolved as follows:

21 outliers were determined to be acceptable based on more detailed evaluation. This included the CRD/Hydraulic Control Units which were evaluated as an outlier as Equipment Class 0 ("Other").

Page iv FACILITY RISK CONSULTANTS, INC.

TVANBFN-01-R-004 Revision 0 September 23, 2004 27 outliers will be resolved by procedural change (restraint of crane hoist and chains during plant operation to eliminate seismic interaction concerns) 30 outliers will be resolved by plant modification under the Design Change Notice process.

6 outliers will be resolved through plant maintenance activity initiated by work orders.

No outliers will be left unresolved. The modifications will be completed prior to October 2006.

A total of 81 items of equipment were found to be acceptable by taking special exception to enveloping of seismic demand spectrum. In all cases this involved determining the lowest natural frequency of the items of equipment because their seismic demand spectrum was not fully enveloped by the seismic capacity spectrum.

Tanks and Heat Exchangers A total of 16 tanks and heat exchangers were identified for evaluation in the USI A-46 program. None of these items are explicitly covered by the GIP, which only addresses large, flat-bottom vertical tanks and horizontal heat exchangers.

A total of 6 outliers were identified for tanks and heat exchangers. All 6 outliers were resolved by mor6 detailed evaluation.

The remaining 10 tanks and heat exchangers were accepted as-is based on engineering judgment (small sizes; adequate attachment; and/or "rule-of-the-box" considerations).

Cable and Conduit Raceways The BFN-1 program addressed all cable trays and conduit located in the BFN-1 Rector Building. Note that cable trays and conduit in the BFN-1 Control Bay were previously evaluated in the BFN-2 and BFN-3 USI A-46 program.

A total of 9 bounding support configurations were selected for Limited Analytical Reviews (LAR's).

Page v FACILITY RISK CONSULTANTS, IC

TVANBFN-01-R-004 Revision 0 September 23, 2004 A total of 14 outliers were identified and documented.

These outliers were resolved as follows:

Six (6) outliers were determined to be acceptable based on more detailed evaluation.

Three (3) outliers will be resolved by plant modification under the Design Change Notice process.

Five (5) outliers will be resolved through plant maintenance activity and work orders.

No outliers will be left unresolved. The modifications will be completed prior to October 2006.

Functional Screening of Relays Inherent ruggedness of contact devices, chatter acceptability, and seismic adequacy were sufficient to resolve the seismic acceptability of contact devices affecting the safe shutdown equipment list components.

No outliers were identified in the relay evaluation.

Mo low ruggedness (bad actor) relays were found to be essential relays.

No operator actions are necessary.

No significant or programmatic deviations from the SQUG GIP were taken in the BEFN-1 USI A-46 resolution program. The qual.fization of the scismic capability engineer3 and the lead relay reviewer meet or exceed all requirements of the SQUG GIP.

Page vi FACILITY RISK CONSULTANTS, INC.

TVANBFN-01-R-004 Revision 0 September 23, 2004 TABLE OF CONTENTS Page Approval Cover Sheet.......................

ii Table of Revisions.............................................................

iii Executive Summary iv

1. INTRODUCTION..............................................................................

1-1

2.

SAFE SHUTDOWN EQUIPMENT LIST.

2-1 2.1 Description of the Safe Shutdown Paths Chosen for the Resolution of USI A-46 2-1 2.2 Systems Beyond A-46 Scope....................................................

2-4 2.3 Plant Operations Department Review of SSEL............

2-4

3.

SAFE SHUTDOWN EARTHQUAKE.

3-1 3.1 Design Basis Earthquake Ground Response Spectrum.......

3-1 3.2 In-structure Response Spectra...................................................

3-1

4.

EXCEPTIONS TO THE GIP.............................................................

4-1 4.1 Capacity Versus Demand..........................................................

4-1 4.2 Caveats 4-1 4.3 Anchorage 4-1 4.4 Interaction 4-1 4.5 l anks and Heat Exchangers 4

4-4.6 Cable and Conduit Raceways 4-1 4.7 Relay Functionality Review..............

................ 4-2

5. OUTLIERS......................................................................................

5-1 5.1 Mechanical and Electrical Safe Shutdown Equipment...................... 5-1 5.2 Tanks and Heat Exchangers..................

..................... 5-1 5.3 Cable and Conduit Raceways..................

..................... 5-2 5.4 Relay Functionality Review

..................... 5-2 5.5 Resolution of Outliers

..................... 5-2 5.6 Plan and Schedule for Resolution of Outliers.................................

5-2 Page vii FACILay RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September 23, 2004 TABLE OF CONTENTS, CONTINUED PaEfe

6.

INDEPENDENT PEER REVIEW.........................................................

6.1 Safe Shutdown Equipment Selection Peer Review Report...............

6.2 Cable Tray and Conduit Raceway Peer Review Report...................

6.3 Mechanical and Electrical Equipment Peer Review Report..............

7.

REFERENCES................................................................................

6-1 6-2 6-6 6-10 7-1 Appendix A:

Appendix B:

Appendix C:

Appendix D:

Appendix E:

Appendix F:

Appendix G:

Appendix H:

Lead Relay Reviewer and Seismic Review Team Qualifications...

Composite SSEL................................................................

Seismic Review SSEL.........................................................

Screening Verification Data Sheets........................................

Results of the Cable and Conduit Raceway Review...................

Operations Department Review of SSEL.................................

Independent Peer Reviewer Resume.....................................

Area Turnover Walkdown Punch List......................................

A-1 B-1 C-1 D-1 E-1 F-1 G-1 H-1 Page viii FACILiTy RIsK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 TABLES Page 4-1 Instances of Special Exception for Capacity versus Demand........

4-3 5-1 Summary of Outliers and Resolution Methods: Mechanical and Electrical Equipment.....................................................................................

5-3 FIGURES Page 2-1 BFN Safe Shutdown for Reactor Reactivity Control...........

2-5 2-2 BFN Safe Shutdown for Reactor Coolant Pressure Control.........

2-6 2-3 BFN Safe Shutdown for Reactor Coolant Inventory Control.........

2-7 2-4 BFN Safe Shutdown for Decay Heat Removal...............

2-8 3-1 Comparison of BFN DBE Ground Motion Response Spectrum with the SQUG Bounding Spectrum.............................................................

3-2 3-3 Comparison of BFN DBE In-structure Response Spectrum with the SQUG Reference Spectrum....................

3-3 Page ix FACLITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23,2004 Page 1-1

1. INTRODUCTION This report provides supporting documentation for the resolution of Unresolved Safety Issue (USI)

A-46 for Browns Ferry Nuclear Plant Unit 1 (BFN-1). The evaluations were performed in accordance with the Seismic Qualification Utility Group (SQUG) Generic Implementation Procedure (GIP) Revision 2A (Reference 1). The evaluations were performed consistent with the USI A-46 resolution programs for BFN-2 and BFN-3, and with the TVA and NRC agreed upon resolution process for USI A-46 at BFN (References 2 to 7). There were no significant or programmatic deviations from the SQUG GIP.

Chapter 2 of this report provides a summary description of the safe shutdown equipment list (SSEL) selection process for BFN-1. SSEL selection was generally consistent with and based largely on the BFN-2 and BFN-3 USI A-46 programs.

Chapter 3 of this report describes the safe shutdown earthquake (SSE) used in the USI A-46 program.

Chapter 4 of this report described the instances in which special exception to enveloping of seismic demand spectrum were used in the seismic screening evaluations of equipment and components.

Chapter 5 of this report describes the outliers that were identified and the planned outlier resolution process. 1 me plan calls for all outliers to be resolved, without exception.

An independent peer review was performed for the BFN-1 USI A-46 program in accordance with the SQUG GIP. The review is confirmatory. It is summarized in Chapter 6.

References are listed in Chapter 7.

This report is issued with a companion report that contains the USI A-46 relay functionality review:

"USI A-46 / Seismic IPEEE Relay Evaluation Browns Ferry Nuclear Plant Unit 1,"

Facility Risk Consultants, Inc., Report No. TVANBFN-01-R-001, Revision 0, 23 January 2004.

FACUTy RISK CONSULTANTS INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 1-2 Additional supporting documentation is provided in the Appendices of this report:

Appendix A:

Appendix B:

Appendix C:

Appendix D:

Appendix E:

Appendix F:

Appendix G:

Appendix H:

Lead Relay Reviewer and Seismic Review Team Qualifications Composite SSEL Seismic Review SSEL Screening Verification Data Sheets Results of the Cable and Conduit Raceway Review Operations Department Review of SSEL Independent Peer Reviewer Resume Area Turnover Walkdown Punch List This report, its Appendices, and the above-listed companion relay review report comprise the entire documentation for TVA's resolution of USI A-46 for BFN-1.

FAcaLy RiSK CONSULTANTS: INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 2-1

2. SAFE SHUTDOWN EQUIPMENT LIST 2.1 Description of the Safe Shutdown Paths Chosen for the Resolution of USI A-46 The following sections describe the safe shutdown paths chosen to mitigate a postulated DBE.

Specifically, it describes what systems are selected for performing the following four functions during shutdown:

Reactivity Control Reactor Coolant System Pressure Control Reactor Coolant System Inventory Control Decay Heat Removal Figures 2-1 through 2-4 illustrate the BFN-1 systems available to perform the above four functions. The systems selected for performing the functions are described below. More detailed descriptions of these safe shutdown systems are provided in TVA Calculation CDQ1-999-2003-0654, Revision 2 (Reference 8).

The primary path used for safe shutdown at BFN-1 is insertion of the control rods and depressurization of the reactor coolant system using the safety relief valves (SRVs) for pressure control. The Core Spray (CS) or Residual Heat Removal (RHR) system is then used to maintain reactor coolant inventory. The RHR system is also used for decay heat removal.

2.1.1 Reactivity Control The first plant challenge in response to a seismic event is to control reactivity, thus reducing core power to decay heat levels. This function is accomplished by a reactor scram and the rapid insertion of the control rods into the core. The scram function will be provided by the Reactor Protection System (RPS) upon execution of a manual reactor trip by the operators. A primary and an alternate path of components are defined to provide the reactor trip function and subsequent insertion of the control rods. The paths are independent except for the Hydraulic Control Units (HCUs) and the Control Rod Drives (CRDs), which are included in both paths. The control rods provide adequate shutdown margin to allow for the control rod of the highest worth FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 2-2 to fail to insert. The inherent redundancy of this system therefore provides protection against a single active failure.

The function of reactivity control is achieved by interaction between the Reactor Protection System (RPS) and the Control Rod Drive Hydraulic Control Unit (CRD/HCU) system. The RPS contains the actuation circuitry, alarms, active equipment, and passive equipment required to trip the reactor, and the CRD system provides the mechanical means to insert the control rods.

Interaction between these two systems will provide for reactivity control. Note that both systems are designed to be fail-safe systems.

Browns Ferry has a Standby Liquid Control System (SLCS) as a backup to the control rods for reactivity control. However, SLCS was not considered a viable altemative for reactivity control for the purpose of this evaluation because of the time and operator actions required for initiation.

2.1.2 Reactor Coolant Pressure Control Following a seismic event, if plant conditions cause or require a plant trip, the main steam isolation valves may close, increasing the Reactor Coolant System (RCS) pressure to the point that RCS pressure relief is required. The plant response to control RCS pressure is the lifting of the SRVs at their respective set points. Thereafter, the SRVs are manually operated by the control room operators to lower reactor pressure and allow low pressure injection for vessel makeup. The redundancy against a single active failure is provided by primary and alternate path designations of the multipic SRV capabilities and the redundancy of their pneumatic col Itrol source. Additionally, a number of the SRVs are provided with pneumatic accumulators for the storage of control pressure to facilitate a number of operations upon total loss of their pneumatic source.

The system is comprised of 13 valves, which are dependent on a pneumatic source for their motive force. Success is defined by the proper functioning of at least four SRVs to control and reduce reactor pressure. Although an alternate means to reduce reactor pressure is included in the Emergency Operating Instructions (EOIs) for emergency depressurization, this alternate path was not selected because of the redundancy of the SRVs and their support systems. This automatic depressurization system (ADS) is also inhibited by the control room operators in accordance with EOIs, so no credit for ADS is taken in this evaluation.

FACILIaY RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September 23,2004 Page 2-3 2.1.3 Reactor Coolant Inventory Control The inventory of the RCS is controlled by injecting water and minimizing the loss of water from the various openings in the system. High pressure makeup is typically provided by the High Pressure Coolant Injection (HPCI) system for the Browns Ferry plant. However, industry experience has indicated that the system is only moderately reliable and for primary path shutdown at BFN, high pressure makeup is not necessary to achieve a safe shutdown condition.

As such, reactor coolant inventory control can be achieved by manually depressurizing the SRVs and utilizing one loop of the CS or RHR systems for makeup.

2.1.3.1 RCS InventorV Sunnlv Core Spray- (RCS Pressure < 450 psig)

The primary path for providing makeup to the RCS is provided by one loop of the CS system (in conjunction with manual depressurization to < 450 psig). For resolution of USI A-46, loop 1 is chosen as the primary path, with loop 2 as the secondary path. Each loop of CS pumps takes suction from the pressure suppression pool Emergency Core Cooling System (ECCS) header and injects into the RPV.

Residual Heat Removal- (RCS Pressure < 450 psig)

Additional alternate paths for providing makeup to the RCS are provided by each loop of the RHR system (in conjunction with manual depressurization to < 450 psig). For resolution of USI A-46, either loop will provide makeup via the Low Pressure Coolant Injection (LPCI) mode, taking suction from the pressure suppression pool and injecting into the RCS via a reactor recirculation loop.

2.1.3.2 RCS Inventory DischarQe The discharge from the RCS is controlled by minimizing the loss of inventory through various paths. Loss of inventory is limited to that necessary in utilization of the SRVs for depressurization to enable the low pressure ECCS systems to inject water into the RPV.

FACILtflY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 2-4 2.1.4 Decay Heat Removal The final function required to meet safe shutdown is decay heat removal. Since safe shutdown for BFN is defined as hot shutdown, the primary means of decay heat removal following a seismic event is accomplished by placing one loop of the RHR system into operation in the suppression pool cooling mode. One RHR pump and heat exchanger combination will be operated taking suction from the suppression pool where decay heat is being deposited through the SRVs, and transferring sensible heat to the Residual Heat Removal Service Water (RHRSW) system before recirculation back to the suppression pool. For the resolution of USI A-46, Loop I is chosen as the primary path, although either loop could be used. The redundancy against a single active failure is provided by the multiple loops of the RHR system.

2.2 Systems Beyond A-46 Scope The USI A-46 SSEL was expanded to include the additional items of equipment that are evaluated for Seismic IPEEE. This followed the same equipment selection process that was used in the BFN-2 and BFN-3 USI A-46 and Seismic IPEEE programs. The USI A-46 SSEL expansion for Seismic IPEEE facilitates the seismic IPEEE review of these components.

2.3 Plant Operations Department Review of SSEL The BFN-1 Plant Operations Department will review the USI A-46 SSEL for BFN-1 for consistency with plant operating procedures for shutdown. This review will be performed after the plant operating procedures are complete. The review will be performed prior to plant start-up. The plan and schedule for the operations department review of the SSEL are summarized in Appendix F of this report.

A preliminary review of the SSEL was performed by the BFN-1 Plant Operations Department, and minor changes were made to the SSEL based on their comments. The preliminary review comments are also summarized in Appendix F.

FACIfrn' RiSK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 2-5 Reactor Reactivity Control I

Manual

[t RPS Trip 1

(Path 1)

TI,'

_ I Manual R

RPS Trip (Path 2)

`

S~~s~~z.X^.X.

ImB I

i CRD IX (Control Rod Insertion)

Figure 2-1: BFN Safe Shutdown for Reactor Reactivity Control FACILI1Y RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 2-6 Reactor Coolant Pressure Control Safety Relief Valves (Actuation at Setpoint) 0,

&M
M, 777"'

M

I I

Safety Relief Valves Path 1 (Manual Activation of at Least 4 Valves)

I Safety Relief Valves Path 2 (Manual Activation of at Least 4 Valves)

.iS

",K
-Ii

i11 ii;isa;~a

<>vasaX"X]~ e

~

g~iij; Figure 2-2: BFN Safe Shutdown for Reactor Coolant Pressure Control FACILITY RISK CONSULTANTSt INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 2-7 Reactor Coolant Inventory Control Safety Relief Valves (Manual Activation) t I

I.

CS (Loop 1)

Pressure <450 psig a*ss~a.;aws~>;ma;;

SE;;A~owGE;'1oY CS (Loop 2)

R Pressure <450 psig I.

RHR (Loop 1/2)

Pressure <450 psig

-I

~~~~~~,,,........

I Figure 2-3: BFN Safe Shutdown for Reactor Coolant Inventory Control FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 2-8 Decay Heat Removal (SPC Mode) p RHR (Loop 1)

'i

~I RHR (Loop 2) j a

S Figure 2-4: BFN Safe Shutdown for Decay Heat Removal FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 3-1

3. SAFE SHUTDOWN EARTHQUAKE 3.1 Design Basis Earthquake Ground Response Spectrum The BFN licensing-basis design basis earthquake (DBE) ground motion acceleration response spectrum is defined in Sections 2.5.4 and 12.2 of the BFN Final Safety Analysis Report (FSAR, Reference 3). The horizontal peak ground acceleration (PGA) corresponding to the DBE is 0.20g, defined at the top of sound rock. Vertical ground motion is two-thirds of the horizontal motion. The site DBE design ground motion is that of a Housner-shaped spectrum anchored to 0.20g PGA.

BFN-1 SSEL equipment are located in the Reactor Building and in the Turbine Building.

Effective grade elevations for these structures were determined in accordance with Part II, Section 4.2 of the SQUG GIP, as follows:

Building1 E

G

.Elevation"'.

Reactor Building 561' Turbine Building 565' The 5% damped BFN DBE ground motion response spectrum is fully enveloped by the SQUG Bounding Spectrum. See Figure 3-1.

3.2 In-structure Response Spectra The 5% damped BFN Reactor Building DBE horizontal in-structure response spectra are compared with the SQUG Reference Spectrum in Figure 3-2. In summary:

.Floor'Elevation:.

'. -Comparison with SQUG:.R eference Spectrum:-;.

~~~~~~~~~~~~~~~~~....;

519' Fully enveloped (same as ground motion) 565' Fully enveloped 593' Partially enveloped (exceeds from about 5.5 to 6.2 Hz.)

621.25' Partially enveloped (exceeds from about 5.0 to 7.0 Hz.)

639' Partially enveloped (exceeds from about 4.8 to 7.3 Hz.)

664' N/A - No SSEL items at El. 664' FAcIUTY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 3-2 I

0.8 z0 Ui C.)

C.)

0.6 0.4 0.2 0

0 5

10 15 20 25 30 35 FREQUENCY (HZ)

Figure 3-1: Comparison of BFN DBE ground motion response spectrum with the SQUG Bounding Spectrum FALiTy RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September23, 2004 Page 3-3 2.5 2

a 0P

-j U'O.

1.5 1

0.5 0

0 5

10 15 20 25 30 35 FREQUENCY (HZ)

Figure 3-2: Comparison of BFN DBE in-structure response spectrum with the SQUG Reference Spectrum FACIVLTY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September23, 2004 Page 4-1

4. EXCEPTIONS TO THE GIP 4.1 CapacitV Versus Demand In 81 instances, the seismic demand in-structure response spectrum for the floor elevation for SSEL items was not fully enveloped by the capacity spectrum that was used to define the seismic capacity of the item of equipment. In each of these 81 cases, the evaluation utilizing the estimated lowest natural frequency of the equipment component to verify that the seismic capacity of the item exceeds its seismic demand. These cases are listed in Table 4-1.

4.2 Caveats In all cases where the item of equipment was determined to be acceptable, the specific wording of the applicable SQUG GIP caveat rule was met.

4.3 Anchorage In all cases where the item of equipment was determined to be acceptable, the specific wording of the applicable SQUG GIP anchorage rule was met.

4.4 Interaction In all cases where the item of equipment was determined to be acceptable, the specific wording of the applicable SQUG GIP seismic interaction rule was met.

4.5 Tank and Heat Exchangers In all cases where the item of equipment was determined to be acceptable, the specific wording of the applicable SQUG GIP tank and /or heat exchanger rule was met.

4.6 Cable and Conduit Raceways In the BFN-1 Reactor Building, a unique anchorage device termed as "loop insert" is used as a typical anchorage for overhead cable tray supports. The loop insert is a cast-in-place device, with reinforcing steel passing through the embedded loop. Engineering evaluations of manufacturers data determined that the pullout resistance and shear capacity of the loop FACIVLTY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 4-2 insert is significantly larger than that of a comparable size expansion anchor. The BFN-1 USI A-46 cable and conduit raceway reviews used the expansion anchor capacities from the SQUG GIP to verify seismic adequacy. This was conservative.

4.7 Relay Functionality Review In all cases where the relay was determined to be acceptable, the specific wording of the applicable SQUG GIP relay review rule was met.

FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 4-3 Table 4-1: Instances of Special Exception for Capacity versus Demand SSEL...

CLASS E QOUIPMENT 1 I' 10016 20 1-HS-99-5ANSlA RPSIREACTOR MANUAL SCRAM CHANNEL AB Ul CB 617' 10017 20 1 -HS-99-5A/S1lB RPS/REACTOR MANUAL SCRAM CHANNEL B1 U1 CB 617' 10018 20 1-HS-99-5A-S1 RPS/REACTOR MODE SWITCH Ul CB 617' 11018 20 1-FI-74-50 RHRtLOOP I FLOW INDICATOR Ul CB 617" 11019 20 1-FI-74-56 RHPlLOOP I FLOW INDICATOR Ul CB 617" 11026 08A 1-FCV-78461 FPC/SPENT FUEL POOL COOLING X-TIE TO RHR Ul RB 621'-3" 11043 20 1-FI-74-64 RHR/LOOP II FLOW INDICATOR Ul CB 617' 11044 20 1-FI-74-70 RHR/LOOP II FLOW INDICATOR Ul CB 617' 13016 07 1-FCV-64-30 CONTAINMENT VENTILATION ISOLATION VALVE U1 RB 621'-3" 13051 20 1-LI-3-58A RPV LEVEL INSTRUMENT Ul CB 617' 13052 20 1-LI-3-58B RPV LEVEL INSTRUMENT Ul CB 617' 13053 20 1-PI-3-74A RPV PRESSURE INSTRUMENT Ul CB 617' 13054 20 1-PI-3-74B RPV PRESSURE INSTRUMENT Ul CB 617' 13055 20 1-XR-64-159 TORUS LEVEL AND DRYWELL PRESSURE INSTRUMENT Ul CB 617" 13056 20 1-LI-64-159A TORUS LEVEL INSTRUMENT Ul CB 617" 13057 20 1-TI-64-161 TORUS TEMPERATURE INSTRUMENT Ul CB 617" 13058 20 1-TI-64-162 TORUS TEMPERATURE INSTRUMENT U1 CB 617" 13059 20 1-PI-64-67 DRYWELL PRESSURE INSTRUMENT U1 CB 617" 13060 20 1-PI 160A DRYWELL PRESSURE INSTRUMENT Ul CB 617" 13061 20 1-TI[64-52A DRYWELL TEMPERATURE INSTRUMENT Ul CB 617" 13062 20 1-XR-64-50 DRYWELL TEMP. AND PRESSURE INSTRUMENT Ul CB 617" 15011 20 1 -FI-75-21 CS/PUMPS 1A & 1 G FLOW INDICATOR U1 CB 61/'

15025 20 1-FI-75-49 CS/PUMPS 1B & 1D FLOW INDICATOR Ul CB 617' 18009 20 1 -FI-23-36 RHRSW HX A FLOW INDICATOR Ul CB 617' 18010 20 1-FI-2342 RHRSW HX C FLOW INDICATOR Ul CB 617' 18011 20 1-FI-2348 RHRSW HX B FLOW INDICATOR Ul CB 617' 18012 20 1-FI-23-54 RHRSW HX D FLOW INDICATOR Ul CB 617' 19001 20 1-PNLA-009-0023/1 ELECTRICAL CONTROL PANEL 1-9-23-1 Ul CB 617' 19002 20 1-PNLA-009-0023/2 ELECTRICAL CONTROL PANEL 1-9-23-2 Ul CB 617' 19003 20 1-PNLA-009-0023/3 ELECTRICAL CONTROL PANEL 1-9-23-3 Ul CB 617' 19004 20 1-PNLA-009-0023/4 ELECTRICAL CONTROL PANEL 1-9-23-4 Ul CB 617' 19005 20 1-PNLA-009-002315 ELECTRICAL CONTROL PANEL 1-9-23-5 Ul CB 617' 19006 20 1-PNLA-009-0023/6 ELECTRICAL CONTROL PANEL 1-9-23-6 Ul CB 617' 19007 20 1 -PNLA-009-002317 ELECTRICAL CONTROL PANEL 1-9-23-7 Ul CB 617' 19008 20 1-PNLA-009-0023/8 ELECTRICAL CONTROL PANEL 1-9-23-8 Ul CB 617' 19039 14 1-JBOX-253-6455 I&C BUS 1ADISCSWITCH lAl Ul RB 621'-3" FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September23, 2004 Page 4-4 Table 4-1: Instances of Special Exception for Capacity versus Demand, Continued

.SEL CLASS EQUIPME I.i

.... IDESCRPT1ON$~:......ULD.N.

19040 04 1-XFA-253-OOO1A1 I&C BUS 1A 480/208-120V TRANSFORMER Ul RB 621'-3 19043 14 1 -JBOX-253-6456 I&C BUS 1A DISC SWITCHES 1 A3, 1A4, 1A5, 1A6 Ul RB 621'-3" 19044 14 1.JBOX-253-8862 I&C BUS 1A DISC SWITCH Ul RB 621'-3" 19045 20 1-PNLA-009-0009 I&C BUS 1A (CAB 2 OF PNL 1-9-9)

Ul CB 617' 19054 20 1-PNLA-009-0009 I&C BUS 1B (CAB 3 OF PNL.1-9-9)

Ul CB 617' 19073 20 1 -PX-64-50 POWER SUPPLY (PNL 1-25-31: XR-64-50 [DEV BA TERM 11/1 2])

U1 RB 621'-3' 19088 20 1-LPNL-925-044A/11 COMMON BD LOGIC RELAY PANEL 25-44-All U' RB 621 37 19089 20 1-LPNL-925-044A/12 COMMON BD LOGIC RELAY PANEL 25-44-A12 Ul RB 621'-3" 19090 20 1-LPNL-925-04483/11 COMMON BD LOGIC RELAY PANEL 25-44-Bl1 Ul RB 621'-3" 19091 20 1-LPNL-925-044B/12 COMMON BD LOGIC RELAY PANEL 25-44-B12 Ul RB 621'-3" 19114 20 1-PNLA-009-0003A REACTOR SD & CONT. COOLING PNL Ul CB 617' 19115 20 1-PNLA-009-0003B REACTOR SD & CONT. COOLING PNL Ul CB 617' 19116 20 1-PNLA-0090004 CLEANUP & RECIRC PNL Ul CB 617' 19117 20 1-PNLA-009-ooo5 REACTORCONTROLPNL Ul CB 617' 19118 20 1-PNLA-oos-0006 FW& COND. PNL Ul CB 617' 19125 20 1-PNLA-009-0021 TEMP RECORDING PNL Ul CB 617' 19133 20 1-PNLA-009-0054 CONTAINMENT ATM. DILUTION PNL U1 CB 617' 19134 20 1-PNLA-009-0055 CONTAINMENT ATM. DILUTION PNL Ut CB 617' 19197 18 1 -LPNL-925-005D LOCAL PANEL 25-5-001 Ul RB 593' 19199 18 1-LPNL-925M-06D LOCAL PANEL 25-6-001 Ul RB 593' 19204 20 1-PNLA-925-O031 LOCAL PANEL25-31 Ul RB 621'-3" 19205 20 1-PNLA-925-0032 LOCAL PANEL 25-32 Ul RP 621'-3 19226 18 1-LPNL-925-247A LOCAL PANEL 1-25-247A (CAD DRYWELL & SUPP. CHAMB. V.)

U1 RB 621'-3" 19229 18 1-LPNL-925-0247B LOCAL PANEL 1-25-247B (CAD N2 SUPPLY PANEL B)

U1 RB 621'-3" 19268 14 1-HS-78-61B HANDSWITCH FOR 1-FCV-78-61 (11026)

Ul RB 621'-3" 19300 20 1-NM-92-7/41A CHANNEL"A IRM INDICATOR Ul CB 617' 19301 20 1-NM-92-7/41B CHANNEL1B IRM INDICATOR Ul CB 617' 19302 20 1-NM-92-7/41C CHANNELCV IRM INDICATOR Ul CB 617' 19303 20 1-NM-92-7/41D CHANNEL D' IRM INDICATOR Ul CB 617' 19304 20 1-PNLA-009-012 PANEL 1-9-12 CB 617' 19313 20 1-HS-1 -56A HANDSWITCH FOR 1 -FCV-1 -56 (13075)

Ul CB 617' 19316 20 1-HS-77-2A HANDSWITCH FOR 1-FCV-77-2A (13080)

Ul CB 617' 19317 20 1-HS-77-15A HANDSWITCH FOR 1 -FCV-77-15A (13081)

U1 CB 617' 19318 20 1-HS-64-18 HANDSWITCH FOR 1-FCV-64-18 (13082)

Ul CB 617' 19319 20 1-HS-64-19 HANDSWITCH FOR 1-FCV-64-19 (13083)

Ul CB 617' 19320 20 1-HS-76-18 HANDSWITCH FOR 1-FCV-76-18 (13084)

Ul CB 617' 19321 20 1-HS-76-19 HANDSWITCH FOR 2-FCV-76-19 (13085)

Ul CB 617' FACILITY RisK CONSULTANTSt INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 4-5 Table 4-1: Instances of Special Exception for Capacity versus Demand, Continued SSEL CLAS FLOORX 19412 03 O-BDM-211-OOOOA 4KV SHDN BD A U1 RB 621'-3X 19418 02 1-BDBB-231-001A 480V SHDN BD 1A Ul RB 621'-3" 19419 02 1-BDBB-231-0001B 480V SHDN BD 1B U1 RB 621'-3" 19492 20 O-LPNL-925-0045A PANEL 25-45A U1 RB 621 X 19594 04 1-XFA-231-TS1A 4KV/480V TRANSFORMER TS1A U1 RB 621-3" 19595 04 1-XFA-231-TS1B 4KVW480V TRANSFORMER TS1B Ul RB 621'-3" 19709 20 X-PNLAO09-0020 PANEL 1-9-20 Ul CB-617' 19791 20 1-PNLA-009-0008 PANEL1-9-8 U1 CB 617" FACIL!TY RiSK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 5-1

5. OUTLIERS 5.1 Mechanical and Electrical Safe Shutdown Equipment A total of 53 individual Outlier Seismic Verification Sheet (OSVS) forms were written, documenting a total of 84 individual items of mechanical and electrical equipment on the SSEL as outliers. The outliers are summarized in Table 5-1.

The types of outliers are as follows:

Ma.jor ConcernNumber of

<..;.¢.:

Outliers Capacity Versus Demand 8

Anchorage 15 Caveats 8

Seismic Interactions 52 Others - Outside of GIP screening criteria 8

applicability Equipment Class 0 (CRD/HCUs) 1 Affected by cable and conduit raceway 2

(see Section 5.3).

TOTAL 84 5.2 Tanks and Heat Exchangers A total of six (6) outliers were identified, affecting four heat exchangers and two tanks:

• The four RHR heat exchangers were designated as outliers because their vertical configuration falls outside of the applicability of the SQUG GIP screening criteria.

• The two CRD Scram Instrument Volume Tanks were designated as outliers because their vertical configuration falls outside of the applicability of the SQUG GIP screening criteria.

FACILITY RISK CONSULTANTS. INc.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 5-2 5.3 Cable and Conduit Raceways A total of 14 outliers were identified in the cable and conduit raceway seismic evaluation program. See Appendix E.

5.4 Relay FunctionalitV Review No outliers were identified in the relay functionality review. See Reference 9.

5.5 Resolution of Outliers All outliers will be resolved prior to restart of BFN-1. See-Table 5-1 for mechanical and -

electrical equipment; and tanks and heat exchangers. See Appendix E for cable and conduit raceways. In general, the resolution of outliers is accomplished as follows:

eso lution.Methd Outliers Further evaluation 21 Procedural revision (to require that crane hoists and chains are restrained during 27 plant operation, to eliminate seismic interaction concerns)

Plant modification implemented by issue 30 of Design Change Notice Maintenance item resolved by issue of 6

Work Order TOTAL 84 5.6 Plan and Schedule for Resolution of Outliers All of the USI A-46 outliers will be resolved before 12/30/06, prior to restart of BFN-1. Designs have been are completed for all modifications. Construction work has begun, and some of the modifications have already been constructed. Follow-up verification of each outlier that is resolved by work order or design change will be performed during plant area turnover walkdowns (see Appendix H punchlist).

FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 5-3 TABLE 5-1

SUMMARY

OF OUTLIERS AND RESOLUTION METHODS:

MECHANICAL AND ELECTRICAL EQUIPMENT OUTLIERINFORMATION.

-:.AFFECTEDEOIUIPMENT.::.:-.-.

EQIPEN DESCRIPTION..

OSVS NO. OUTLIER CONDITION AND PROPOSED RESOLUTION SSEL EQUIP EQUIPMENT I.D.

EQUIPMENT DESCRIPTION RESOLU T ION METHOD:

.:..... NOC: CLASS 10001-01 Equipment configuration falls outside of GIP Resolved - Acceptable As-s by further evaluation. 10001 00 1-HCU-85, 1185 CRD/HYDRAULIC CONTROL UNITS screening criteria applicability. Perform (Calculation CDOQ 085 2004 0153).

further evaluation.

10007-01 Interaction hazard - Sharp end of cut-off Resolved - Work Order WO No. 04-715782-000 10007 07 1-FCV-85-83 CRD/EASTSDVVENTVALVE beam section is in contact with actuator was issued to address the condition. Final diaphragm housing. Cope out beam.

configuration to be verified during area turnover walkdowns.

10010-01 Vertical orientation falls outside of GIP Resolved - Acceptable As-Is by further evaluation. 10010 21 1-TNK-85-901 CRD'WEST SCRAM INSTRUMENT VOLUME screening criteria applicability (Calculation CD0 1 085 2004 0153).

10011-01 Vertical orientation falls outside of GIP Resolved - Acceptable As-Is by furtherevatuation. 10011 21 1-TNK-85-902 CRD/EAST SCRAM INSTRUMENT VOLUME screening criteria applicability (Calculation CDQI 085 2004 0153).

11009-01 Vertical orientation falls outside of GIP Resolved-Acceptable As-Is by further evaluation. 11009 21 1-HEX-74-900A RHRIHEAT EXCHANGER 1A screening criteria applicability. Perform (Calculation CDQI 074 2003 2583).

further evaluation.

11017-01 Vertical orientation falls outside of GIP Resolvel - Acceptable As-s by further evaluation. 11017 21 1-HEX-74-900C RHR/HEAT EXCHANGER 1C screening criteria applicability. Perform (Calculafon CDQ1 074 2003 2583).

further evaluation.

11036-01 Vertical orientation falls outside of GIP Resolved-Acceptable As-s by further evaluation. 11036 21 1-HEX-74-900B RHR/HEAT EXCHANGER lB screening criteria applicability. Perform (Calculation CDOl 074 2003 2583).

further evaluation.

11042-01 Vertical orientation falls outside of GIP Resolved - Acceptable As-Is by further evaluation. 11042 21 1-HEX-74-900D RHR/HEAT EXCHANGER ID screening criteria applicability. Perform (Calculaticn CD01 074 2003 2583).

further evaluation.

FACILITY RISK CONSULTANTS? INQ I.I

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 5-4 TABLE 5-1 Summary of Outliers and Resolution Methods: Mechanical and Electrical Equipment, Continued

-UT E.

rOlMA:OX AFFETED E

-PNT OSVS NO.1: OULIER CONDION AND PROPOSED

-........ : RESOLONSL U

E I NN D

.:RS NEHD:.........

LS

':::RESOLUTION METO NO CAS 12001-01 Interaction hazard -Hoistchains from Resolved - PER No. 64133 was issued to address 12001 07 1-PCV-1-4 MS/MAIN STEAM SAFETY RELIEF VALVE overhead jib crane. Procedure revision is the condition. Final configuration to be verified 12003 07 1-PCV-1-18 MS/MAIN STEAM SAFETY RELIEF VALVE 120ra 07 1-PCV-1-1o MS/MAIN STEAM SAFETY RELIEF VALVE 12006 07 1-PCV-1-22 MS/MAIN STEAM SAFETY RELIEF VALVE 12010 07 1-PCV-1-19 MS/MAIN STEAM SAFETY RELIEF VALVE 12012 07 1-PCV-1-17 MS/MAIN STEAM SAFETY RELIEF VALVE 12021 07 1-PCV-1-30 MS/MAIN STEAM SAFETY RELIEF VALVE 12021 07 1-PCV-1-31 MS/MAIN STEAM SAFETY RELIEF VALVE 12021 07 1-PCV-1-34 MS/MAIN STEAM SAFETY RELIEF VALVE 12032 07 1-PCV-1-41 MS/MAIN STEAM SAFETY RELIEF VALVE 12030 07 l-PCV-1-410 MS/MAIN STEAM SAFETY RELIEF VALVE 16010 08B I-PSV-1-19 MSISOLENOAD VALVE FOR PCV-1-19 16013 08B I-PSV-1-22 MS/SOLENOID VALVE FOR PCV-1-22 16016 08B 1-PSV-I-5 MS/SOLENOID VALVE FOR PCV-1-5 16017 08B l-PSV-1-23 MS/SOLENOID VALVE FOR PCV-1-23 16018 08B 1-PSV-1-179 MS/SOLENOID VALVE FOR PCV-1-179 16019 08B 1-PSV-1-4 MS/SOLENOIDVALVE FOR PCV-1-4 16021 088 1-PSV-1-18 MS/SOLENOID VALVE FOR PCV-1-178 I

FACILITY RISK CONSULTANTS, IN.

TVAIBFN-01 -R-004 Revision 0 September 23, 2004 Page 5-5 TABLE 5-1 Summary of Outliers and Resolution Methods: Mechanical and Electrical Equipment, Continued

.:.O

.IRo AO.

AF

OUTLIER lNI5OMA110N AFFECTED EQUIPMENT::'"

OSVS NO..

LIER CONDITION AND E

-L E I E

N QIE DESC:IPT:O:

-RESOLUTMON METHOD

'NO,`:CLAS

. E ~

12001-01 (Contnued) 16030 08B 1-PSV-1-30 MS/SOLENOID VALVE FOR PCV-1-30 16033 08B 1-PSV-1-31 MS/SOLENOID VALVE FOR PCV-1-31 16036 08B 1-PSV-1-34 MS/SOLENOID VALVE FOR PCV-1-34 16038 08B 1-PSV-1-41 MS/SOLENOID VALVE FOR PCV-1-41 16040 08B 1 -PSV-1-42 MS/SOLENOID VALVE FOR PCV-1-42 16041 08B 1lPSV-1-180 MS/SOLENOID VALVE FOR PCV-1-180 12001-02 Interaction Hazard -The ring duct is a Resolved - Acceptable As-Is by further evaluation. 12001 07 1-PCV-1-4 MSIMAIN STEAM SAFETY RELIEF VALVE polenlial falling interacton hazard lo fragile (Calculation CDQ1 080 2003 1196).

components if the listed equipment items.

12003 07 1+PCV.15 MS/MAIN STEAM SAFETY RELIEF VALVE Perform further evaluation.

12012 07 1-PCV-1-22 MS/MAIN STEAM SAFETY RELIEF VALVE 12018 07 1-PCV-1-179 MS/MAIN STEAM SAFETY RELIEF VALVE 12030 07 1-PCV-1-41 MS/MAIN STEAM SAFETY RELIEF VALVE 12033 07 1.PCV-1-42 MS/MAIN STEAM SAFETY RELIEF VALVE 12036 07 1-PCV-1-180 MSIMAIN STEAM SAFETY RELIEF VALVE 16013 086 I-PSV-1-22 MS/SOLENOID VALVE FOR PCV-1-22 16016 08B 1-PSV-1-5 MS/SOLENOID VALVE FOR PCV-1-5 16018 086 1-PSV-1-179 MS/SOLENOID VALVE FOR PCV-1-179 16019 08B 1-PSV-1-4 MS/SOLENOID VALVE FOR PCV-1-4 16038 08B 1-PSV-1-41 MS/SOLENOID VALVE FOR PCV-1-41 16040 08B 1:PSV-1.42 MS/SOLENOID VALVE FOR PCV-1-42 16041 08B 1-PSV-1-180 MS/SOLENOID VALVE FOR PCV-1-180 FACILITY RISK CONSULTANTS, INa

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 5-6 Table 5-1 Summary of Outliers and Resolution Methods: Mechanical and Electrical Equipment, Continued OUT.E.IFORA.ONAFFECTED EQUIMN

~~~~.

........... :.WIR OMBCn:

l OSVSNO: OUTLIERCONDITIONAND PROPOSED RESOLUTION SE

-LEQUIP i E UIPMENT DESCRIPTION::

RESLUTNN M

E T HOD:.J NO. CL AS RSLONMTD:.:

13001-01 The inboard and outboard MSIVs are not Resolved - Acceptable As-Is by further evaluation. 13001 07 1-FCV-1-14 MSIV A INBOARD ISOLATION VALVE explicitly represented in the seismic (Calculation CDO1 001 2004 0143).

experience database. In addition, the length 13002 07 1-FCV-1-15 MSIV 'Al OUTBOARD ISOLATION VALVE from the centerline of 24'0 MS pipe to the top of the valve operator is about 103 which 13003 07 I-FCV-1-26 MSIV B INBOARD ISOLATION VALVE exceeds the GIP limitation per Figure B.7-2 13004 07 1-FCV-1-27 MSIV B OUTBOARD ISOLATION VALVE of the GIP for 18"P or larger pipes. Perform 13004 07_______27________UTBORDSOLAION

_ALV further evaluabon.

13005 07 1-FCV-1-37 MSIV C INBOARD ISOLATION VALVE 13006 07 1-FCV-1-38 MSIV C OUTBOARD ISOLATION VALVE 13007 07 1-FCV-1-51 MSIV D' INBOARD ISOLATION VALVE 13008 07 1-FCV-1-52 MSIV'D'OUTBOARD ISOLATION VALVE 13047-01 Caveat: Operator CG height not covered by Resolved - DCN. Valve and operators replaced 13047 07 1-FCV-77-2B DRYWELL FLOOR DRAIN SUMP DISCHARGE GIP inclusion rules. Perform further with seisnically qualified valve under DCN 51202.

evaluation.

Final configuration to be verified during area turnover walkdowns.

13048-01 Caveat: Operator CG height not covered by Resolved - DCN. Valve and operators replaced 13048 07 1-FCV-77-15B DRYWELL EQUIP. DRAIN SUMP DISCHARGE GIP inclusion rules. Perform further with seisrically qualified valve under DCN 51202.

evaluation.

Final configuration to be verified during area turnover walkdowns.

13049-01 Seismic Cap < Demand. Perform further Resolved - Acceptable As-Is by further evaluation. 13049 07 1-FCV-84-19 CAD ISOLATION VALVE evaluation.

(Calculation CDOQ1 084 2003 2584).

13050-01 Seismic Cap < Demand. Perform further Resolved - Acceptable As-Is by further evaluation. 13050 07 1-FCI'-84-20 CAD ISOLATION VALVE evaluation.

(Calculaton CDQ1 084 2003 2584).

13075-01 Caveat: OperatorCG height notcovered per Resolved-Acceptable As-Is by furtherevaluaton. 13075 08A 1-FCV-1-56 MAIN STEAM LINE DRAIN ISOLATION VALVE GIP inclusion rules. Perform further (Calculation CDN1 999 2004 0037).

evaluation.

FACILITY RISK CONSULTANTS, /iN

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 5-7 Table 5-1 Summary of Outliers and Resolution Methods: Mechanical and-Electrical Equipment, Continued UTItER INFOMATION

..AFFECTED EQU.PMENT.

OSVS NO. OUTLIER CONDITION AND PROPOSED RESOLUTION

E E 1 EQUIPMENT N.:.

EQUIPMENT DESCRIPTION

.:.RESOLUTlON METH OD NO C AS J__

__I

.::'.'"'EOWNEHD'"

...C::;:.'..

13080-01 Caveat: Operator CG height not covered per Resolved - DCN. Valve and operators replaced 13080 07 1-FCV-77-2A DRYWELL FLOOR DRAIN SUMP DISCHARGE GIP inclusion rules. Modification is with seisnically qualified valve under DCN 51202.

recommended Final configuration to be verified during area turnover walkdowns.

13081-01 Caveat: Operator CG height not covered per Resolved - DCN. Valve and operators replaced 13081 07 1-FCV-77-15A DRYWELL EQUIP. DRAIN SUMP DISCHARGE GIP inclusion rules. Modification is with seisrrically qualified valve under DCN 51202.

recommended Final configuration to be verified during area turnover walkdowns.

14014-01 Caveat: Flex conduit connection loose.

Resolved - Work Order was issued under DCN 14014 10 1-CLR-67-920 EECW/CS PUMP lB ROOM COOLER Issue work order for repair of coupling.

51190 to repair coupling (WO # 02-016198-019).

Final configuration to be verified during area turnover walkdowns.

RB519-03 Interaction: Overhead conduits have span Resolved - DCN. Support added under DCN 51521 15007 06 1-PMP-75-14 CS/PUMP IC exceeding GIP raceway screening

& DCA 1-48B800-3639. Final configuration to be guidelines limit Add new support to verified during area turnover walkdowns.

conduit.

Note - see Appendix E for raceway seismic evaluation program.

RB519-01 Interaction: Overhead conduits have span Resolved - DCN. Supports added under DCN 15021 06 1-PMP-75-42 CS/PUMP ID exceeding GIP raceway screening 51521 & DCA 1-488800-3638. Final configuration guidelines limit Add new supports to to be verified during area turnover walkdowns.

conduit.

RB519-02 Note - see Appendix E for raceway seismic evaluation program.

19030-01 Seismic Capacity < Demand. Further Resolved - Acceptable As-s.

19030 01 1-BDBB-281-O00A 250V DC RMOV BOARD IA evaluation is recommended (Calculation CDQO 999 96 0096 for BFN-2 & -3 documen's a comparison of shake table test results for GE model 7700 MCC to appropriate BFN demand levels).

FACILITY RISK CONSULTANTS, INS

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 5-8 Table 5-1 Summary of Outliers and Resolution Methods: Mechanical and Electrical Equipment, Continued OUTLIER INFORMATION..

AFFECTED EQUIPMENT OSVS'NO.

OUTLIER CONDITION AND"PROPOSED RESOLUTION SSEL 1EQUIP. IEQUIPMENT.D. 1.:. EQUIPMENTDESCRIPTION..

OL M O M

....:....i.

19030-02 Caveat: Screws are missing on lower left Resolved - Work Order was issued under DON cover panel. Modification is recommended 51521 to install screws (WO # 03-015216-000).

Final configuration to be verified during area turnover walkdowns.

19030-03 Anchorage: Capacity < Demand.

Resolved - DCN. Top brace added to MCC per Modification is recommended.

DCA 51521-001 under DCN 51521 (see Calculation CD01 999 2003 1499). Final configuration to be verified during area turnover walkdowns.

19031-01 Seismic Cap < Demand. Further evaluation Resolved - Acceptable As-Is.

19031 01 1-BDBB-281-OOOIB 250V DC RMOV BOARD lB is recommended.

(Calculation CD00 999 96 0096 for BFN-2 & -3 documents a comparison of shake table test results for GE model 7700 MCC to appropriate BFN demand levels),

19031-02 Caveat: Screws are missing on lower left Resolve, - Work Order WO No. 04-715780-000 cover panel. Modification is recommended was issued to install the missing screws.

19042-01 Anchorage: Toggle bolts into block wall.

Resolved - See mini-calculation documented 19042 14 1-JBOX-253-6457 I&C BUS 1A DISC SW 1A2 Further evaluation is recommended.

directly on the 19042-01 OSVS form.

19042-02 Caveat: Anchor in oversized hole.

Further evaluation is recommended.

19070-01 Seismic Cap < Demand Resolved - DCN. Inverter is to be replaced by a 19070 16 1-INVT-256-0001 DIV I ECCS ATU INVERTER Caveat: Configuration not covered by new seismically qualified unit under DCN 51085.

inclusion rules Anchorage: Details could not be confirmed 19075-01 Seismic Cap < Demand Resolved - DCN. Inverter is to be replaced by a 19075 16 1-INVT-256-0002 DIV 11 ECCS ATU INVERTER Caveat: Configuration not covered by new seismically qualified unit under DCN 51085.

inclusion rules Anchorage: Details could not be confirmed FACILITY RISK CONSULTANTS, IN:

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 5-9 Table 5-1 Summary of Outliers and Resolution Methods: Mechanical and Electrical Equipment, Continued

'OUTLIER INFORMATION AFF OSVSNO. C T'IER"CONDITIONANDPROPOSED:l::.

RESOL ON SSE EUIP EUiPM UiEN DESCRIPT METHOD N:: CLSS 19088-01 Anchorage: Gap at anchor.

Resolved - DCN. Shim plate(s) provided per 19088 20 1-LPNL-925-044A/11 COMMON B LOGIC RELAY PANEL 25-44-All Interaction: Impactwith wall.

Drawing 1-48B900-3085 under DCN 51521.

Modification is recommended.

19120-01 Caveat: Impact with block wall Resolved - DCN. Gap filled with sealant under 19120 20 1-PNLA-009-0015 RPS CH A (DIV I)

Interac6on: Impact with wall DCN 51085.

Modification is recommended.

19121 20 I-PNLA-009-0016 RPS CHA, B, C, D 19122 20 1-PNLA-009-0017 RPS CH B (DIV 11) 19128 20 1-PNLA-009-0032 RHR, CS, & HPCI (CH A) PNL 19130-01 Caveat: Impact with adjacent panel Resolved - DCN. Panels -39 and -82 attached 19129 20 1-PNLA-009-0033 RHR, CS, & HPCI (CH B) PNL Interaction: Impact with adjacent panel.

together per DCA 51085-202 under DCN 51085 Modification is recommended.

(Calculation CDQ1 999 2003 1491).

19130 20 1-PNLA-009-0039 HPCI RELAY AUX PNL 19132 20 1-PNLA-009-0043 MSIV (OUTBOARD) DIV II PNL 1913601 19136 20 1-PNLA-009-0082 DIV It ECCS ATU CABINET (9-82) 19131-01 Caveat: Impact with adjacent panel Resolved - DCN. Panels -42 and -81 attached 19131 20 1-PNLA-009-0042 MSIV (INBOARD) DIV ii PNL Interaction: Impact with adjacent panel.

together per DCA 51085-202 under DCN 51085 19135-01 Modification is recommended.

(Calculation CDOQ 999 2003 1491).

19135 20 1-PNLA-009-0081 DIV I ECCS ATU CABINET (9-81) 19137-01 Caveat: Impact with adjacent panel Resolved - DCN. Panels -83, -84, -85, and -86 19137 20 1-PNLA-009-0083 RPS ATU CAB Interaction: Impact with adjacent panel.

attached together per DCA 51085-202 under DCN 19138-01 Modification is recommended.

51085 (Calculation CDQ1 999 2003 1491) 19138 20 1-PNLA-009-0084 RPS ATU CAB 19139-01 19139 20 1-PNLA-094085 RPS ATU CAB 19140-01 19140 20 1-PNLA-009-0086 RPS ATU CAB 19154-01 Anchorage: Missing bolts to unistrut. Repair Resolved - PER No. 64136 was issued to address 19153 18 1-HS-74-52B LOCAL HS STATION is recommended.

the cond tion. Final configuration to be verified during area tumover walkdowns.

19154 14 1-JB-1079 JUNCT. BOX (TERM BLOCK) - SEALED BOX 19155 18 1-HS-74-53B LOCAL HS STATION FACILITY RISK CONSULTANTS, INQ

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 5-1 0 Table 5-1 Summary of Outliers and Resolution Methods: Mechanical and Electrical Equipment, Continued LIER INFORMATIO AFFECTED EQUIP ENT OSVSNO OTLIERCONDITION AND PROPOSED lE

SOLUTON SSEL EQUIP EQUIPME ZD1.:.

UIPMENT DESCRIPTION 19195.01 Caveat: Missing bolt to floor kicker. Repair Resolved -Work Order WO No. 04-715781-000 19195 18 1-LPNL-925-005A LOCAL PANEL 2-S5A is recommended, was issued to install bolts.

19198.01 Anchorage: Gap under base anchorage.

Resolved - PER No. 64139 was issued to address 19198 18 1-LPNL-925-006A LOCAL PANEL 25-6A Further evaluation is reconmmended. Work the condition. Final configuration to be verified with OSYS 19792-01.

during area turnover walkdowns._

19223-01 Anchorage: Fourolsix anchor bolts railed Resolved -Bolts were properly torqued under bolt 19223 20 1-PROT-099-0001B2 RPS CIRCUIT PROTECTOR CABINET 1B2 tightness check, tightness check, WO 03-0113284000. Operability was demonstrated for the case with only two bolts; see calculation 0001099 2003 2582_

19287-01 Seismic Cap < Demand. Further evaluation Resolved - Acceptable As-Is. Capacity data in 19287 18 1-TS-54A MAIN STEAM TUNNEL TEMPERATURE is recommended.

GERS report used to substantiate higher capacity.

SWITCH Resolved on OSVS form._

19288-01 Seismic Cap < Demand. Further evaluation Resolved - Acceptable As-Is. Capacity data in 19288 18 1-TS-54B MAIN STEAM TUNNEL TEMPERATURE is recommended.

GERS report used to substantiate higher capacity.

SWITCH Resolved on OSVS form._

19289-01 Seismic Cap < Demand. Further evaluation Resolved - Acceptable As-s. Capacity data in 19289 18 1-TS-54 C

M AI N STEAM TUNNEL TEMPERATURE is recommended.

GERS reiort used to substantiate higher capacity.

SWITCH Resolveo on OSVS form._

1929-01 Seismic Cap <Demand. Further evaluation Resolved - Acceptable As-Is. Capacity data in 19290 18 1-TS-54D MAIN STEAM TNNEL TEMPERATURE is recommended.

GERS report used to substantiate higher capacity.

SWITCH Resolved on OSVS formn.

19307-01 Anchorage: Anchored to block wal without Resolved - DoN. New support system installed per 19307 18 1-CHPOT-283-AI-1 24V NEUTRON BATTERY CHARGERS A1-i through bolts. Modification is iCA 51085-201 under DN 51085 (Calculation recommended.

see1 a99 2003 1491) 19308-01 Anchorage: Anchored to block wal without Resolved - DON. New support system installed per 19308 16 1-CHGD-2835A2-1 24V NEUTRON BATTERY CHARGERS A2-1 through bolts. Modification is oCA 5v0e5-201 under D CN 51085 (Calculation recommended.

COER r99 2003 1491)

FACILITY RISK CONSULTANTS, INC

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 5-11 Table 5-1 Summary of Outliers and Resolution Methods: Mechanical and Electrical Equipment, Continued OUTL1ER INfoRMATION AFFECTED AFF ECTED-OSVS NO.l OUTiER CONDITiON1AND PROPOSED i RESOL rON ~. -:

.:SSEL: EQUIP EQUiPMENT I.D.

EQUPMEN DESCRIPTION : ;

S E-t

~ _________________

IL~~O M~HOO.NOCLASS t L SS s

?::

recommended.

I 1 999-2003 1491) 19310-01 Anchorage: Anchored to block wall without Resolved - DCN. New support system installed per 19310 16 1-CHGD-283-B2-1 24V NEUTRON BATTERY CHARGERS B2-1 through bolts. Modification is DCA 51085-201 under DCN 51085 (Calculation recommended.

0CD1 999 2003 1491) 19418-01 Seismic Interaction: Breaker lifting device Resolved - PER No. 64141 was issued to address 19418 02 1-BDBB-231-0001A 480V SHDN BD 1A not restrained. Review then enhance the condition. Final configuration to be verified procedures as required.

during area tumover walkdowns.

19792-01 Anchorage: Gap under base anchorage.

Resolved - PER No. 64139 was issued to address 19792 18 1-LPNL-925-006B LOCAL PANEL 25-68 Further evaluation is recommended. Work the condition. Final configuration to be verified with OSVS 19198-01.

during area tumover walkdowns.

19794-01 Caveat: Weak way bending on support Resolved - DCN. Anchorage detail modified under 19794 04 1-XFA-099-0010 RPS REGULATING TRANSFORMER TRP-l base DCN 51085 (Calculation CDQ1 999 2003 1491).

Modification is recommended.

19794-02 Anchorage: Anchor bolts missing from the rear.

Modification is recorrmnended.

19797-01 Anchorage: Anchored to block wall with Resolved - See mini-calculation documented 19797 14 1-FUDS-099-O0OICB RPS BUS XFMR DISC SW toggle bolts.

directly on the 19794-01 OSVS form.

Further evaluation is recommended 19797-02 Anchorage: One anchor bolt is loose. Work with OSVS 19797-01.

FACILITY RISK CONSULTANTS, IN.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 6-1

6. INDEPENDENT PEER REVIEW An independent, third-party peer review of the BFN-1 USI A-46 resolution program was performed by Dr. James J. Johnson. He was not a part of the walkdown team. This evaluation provided an assessment of the walkdown and analysis by audit and sampling.

Dr. James J. Johnson meets the qualification requirements for a Seismic Capability Engineer; see resume in Appendix G. These reports include the following:

Safe shutdown equipment selection Cable trays and conduit raceways Mechanical and electrical equipment FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 6-2 6.1 SAFE SHUTDOWN EQUIPMENT SELECTION PEER REVIEW REPORT FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 6-3 JAMES J. JOHNSON, PH.D., P.E.

James J. Johnson and Associates 7 Essex Court, Alamo, CA 94507 Phone: (925) 837.4749 - Fax: (925) 838-9227 17 March 2003 Mr. Richard D. Cutsinger Tennessee Valley Authority Browns Ferzy Nuclear Plant, RSBI-7/BFN P.O. Box 2000 Decatur, AL 35609-2000

Subject:

Independent Peer Review Browns Ferry Unit I (BFN-1) Safe Shutdown Equipment List (SSEL) for Resolution of NRC Unresolved Safety Issue (USI) A-46 and Addressing Independent Plant Examination for External Events (IPEEE)

Dear Mr. Cutsinger:

During the period of 27 February 2003 to 17 March 2003, 1 performed an Independent Peer Review of the subject Safe Shutdown Equipment List (Ref. 1).

The approach and result appear to be consistent with the GIP (Ref. 2) and EPRI NP-6041 (Ref. 3) methodologies.

Importantly, the approach and result are consistent with that used for BFN Units 2 and 3. This latter point is particularly important since operators for the Browns Ferry Nuclear Plant are trained to operate all three units. Hence, consistency in the definition of the safe shutdown paths and the safe shutdown equipment lists for the three units should be maintained to the extent possible.

Also, shared systems are assumed in a number of areas, which further requires this consistency...

Two areas of emphasis for this review are:

Plant Operations Department Review The GIP (Ref. 2) and EPRI NP-6041 (Ref. 3) require Plant Operations Department review of a number of elements and concurrence of their acceptance:

• The plant procedures for shutting down the reactor should be reviewed by the Operations Department to verify that the plant procedures are compatible with the identified method of safe shutdown, and that they do not preclude the use of the safe shutdown equipment, if some other method of shutting down the reactor is first attempted. For BFN-I, one area where this question should be addressed is initial use of HPCI and RCIC systems, not on the safe shutdown path, but likely to be called upon first during plant shutdown. The method of verification by the Operations Department should be documented.

Leter. James J. Johnson to Richard D. Cutsinger, Pate I of 3 FACILTY RisK CONSULTANTS, luc.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 6-4

• Permitted operator actions that are identified as initial or back-up procedures should be verified for feasibility, i.e., required time frame can be met, physical path to achieve action is unrestricted, access to components is not hampered by high temperature, humidity, or other environmental effects, etc.

• Shared systems of the multiple units have the capacity to meet the demand of the multiple units when simultaneously subjected to the event of interest - the design basis earthquake for US] A-46 and the review level earthquake for IPEEE.

Shared Systems Reviewed Reference I and its predecessors for Units 2 and 3 identified systems that are shared between Units 1, 2, and 3 or Units I and 2.' These shared systems were evaluated previously with respect to Units 2 and 3 capacity to meet safe shutdown requirements for USI A-46 and seismic IPEEE and verified as being adequate. For Unit I evaluation, the following should be noted:

• For conpleteness, the Unit I SSEL should include the safe shutdown equipment items contained in shared systems that are relied upon by Unit I for safe shutdown.

This permits a complete and adequate review.by Plant Operations and other parties.

• Detailed calculations need not be repeated to verify the seismic capacity of these shared system components. However, it is the responsibility of the Seisrnmic'Review Team (SRT) to validate that the field conditions of the equipment have not changed in.

a manner that would invalidate the previously determined capacity of the equipment.

In particular, that adverse seismic spatial interaction issues have not been introduced that would preclude the equipment from performing its designated function. Tlus validation could be accomplished through a number of approaches, e.g., review of configuration control procedures to verify that effective configuration control is in place, brief area or equipment specific walk-bys to verify no adverse seismic system interactions exist, etc.

References

1. BFN - I, "Composite Safe Shutdown Equipment List (SSEL) for USI A-46 and Seismic IPEEE Programs," Cal. No. CDQI-999-2003-0654, Rev. 0.

2. Seismic Qualification Utility Group (SQUG), "Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment," Rev. 2A, March 1993.

3. Electric Power Research Institute (EPRI), "A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision I)," EPRI NP-6041-SL, Rev. 1, August 1991.

Letter, James J. Johnson to Richiard D. Culsin=er, Page 2 of 3 FACILITY RIsx CONSULTANTS, INC.

TVAtBFN-01 -R-004 Revision 0 September 23, 2004 Page 6-5 If questions arise as to the substance of this review, please feel free to contact me. it is my pleasure to continue to support the efforts of TVA to bring BFN Unit I on-line to support the energy demands of the United States.

Sincerely, James J. Johnson President cc: John 0. Dizon, Facility Risk Consultants Letter, James J. Johnson to Richard D. Cutsin-er, Pace 3 of 3 FACILITY RIsK CONSULTrAT INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 6-6 6.2 CABLE TRAYS AND CONDUIT RACEWAYS PEER REVIEW REPORT FACILITY RISK CONSULTANTSE INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 6-7 JAMfES J. JOHNSON2, PH.D., P.E.

James J. Johnson and Associates 7 Essex Court, Alamo, CA 94507 Phone: (925) 837-4749 - Fax: (925) 838-9227 13 August 2003 Mr. Richard D. Cutsinger Tennessee \\'alley Authority Browns Ferry Nuclear Plant, RSB I-7/BFN P. O. Box 2000 Decatur, AL 35609-2000

Subject:

Independent Peer Review Browns Ferry Unit I (BFN-1) Seismic Verification of Cable Tray and Conduit Raceway Systems for Resolution of NTRC Unresolved Safety Issue (USI) A-46

Dear Mr. Cutsinger:

During the period of 4 August 2003 to the current date, I performed an Independent Peer Review of the subject program US] A-46 Seismic Verification of Cable Tray and Conduit Raceway Systems (Ref. 1). The scope of this program covers all electrical raceway systems (cable tray and conduit systems) at BFN-I not previously evaluated during the USI !A-46 programs for BFN Units 2 and 3. Hehce, the present program covers the Unit I Re'actor Building, below elevation 664'; including the drywell.

The approach and result are consistent with the GIP (Ref. 2) and acceptable to meet the requirements for resolution of USI A-46 for BFN Unit l.

W'alldown Observations The walkdown pa:kagcs (Rcjs. 3-8) were reviewed. In general, the walkdown packages were very well documented with easy to foliow highlights identified. Discussions were conducted with available Seismic Review Team members. The identified outliers were discussed in detail to understand the reasoning for identifying them so. It was observed that the Seismic Review Team performed a complete in-plant walkdown of the program scope raceways, and conducted several close-up inspections of select details.

The Seismic Review Team was thorough and managed the program by use of designated plant areas at the various elevations..

I participated in an in-plant wvalkby cof'ering Reactor Building elevations within the scope of the program. The identified outliers were viewed in the plant. A selected group of cases identified for Limited Analytical Review were also viewed. I concur with the outlier identification and the selected cases for Limited Analytical Review.

The approach used for the wvalkdown adheres to the guidance in the GIP (Ref. 2).

Letter, James J. Johnson to Richard D. Cutsinger, Page 1 of 3 FACILUTY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 6-8 Outlier Resolution and Limited Analytical Review The outlier resolutions and limited analytical reviews contained in Ref. I were reviewed for approach and adherence to the guidelines provided in the GIP (Ref. 2). They were found to meet the guidelines and approach.

Attachment A of Ref. I presents the Checker's perspective on areas of excess conservatism in the outlier resolution and limited analytical review calculations. I concur with these observations.

Configuration Control Most of the cable trays inside drywell are supported from overhead drywell platform steel and have been temporarily disconnected during the replacement of platform steel. These supports are intended to be re-welded to the new platforin steel in the same, or close to the same, configuration as originally installed. A wvalkby to verify the re-installation after its completion should be performned.

New systems or modifications to existing systems, which will be installed over the next one or two years to complete BFN Unit 1, should be verified to not invalidate the assessments performed herein.

Verification of no new hazards may be accomplished

• through an office evaluation and/or in-plant wallkdown. This may be accomplished at the final walkdown stage prior to area turnover.

References

1. BFN -

1, "USI A-46 Seismic Verification of Cable Tray and Conduit Raceway Systems," Cal. No. CDQ1-000-2003-2203, Rev. 0.

2. Seismic Qualification Utility Group (SQUG), "Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment," Rev. 2A, March 1993.

3. "Walkdownm Data Packages for Cable Tray and Conduit Raceway Review for US] A-46 and Seismic IPEEE - Documentation for-BFN Unit I Drywell," WDP No. B1Ni-CEB-RC'WY-DW, 7/31/03.

4. "Walkdown Data Packages for Cable Tray and Conduit Raceway Review for USI A-46 and Seismic IPEEE - Documentation for BFN Unit I Reactor Building El. 519',"

NVDP No. BFN I -CEB-RCWY-519, 7/31/03.

5. "Walkdown Data Packages for Cable Tray and Conduit Raceway Review for USI A-46 and Seismic IPEEE - Documentation for BFN Unit I Reactor Building El. 565',"

WVDP No. BFN 1-CEB-RCWY-565, 7/31/03.

6. "Walkdown Data Packages for Cable Tray and Conduit Raceway Review for USI A-46 and Seismic IPEEE - Documentation for BFN Unit I Reactor Building El. 593',"

\\VDP No. BFNI -CEB-RCWY-593,7/31/03.

Letter, James 3. Johnson to Richard D. Cutsinger, Page 2 of 3 FACIL TY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September23, 2004 Page 6-9

7. "Walkdown Data Packages for Cable Tray and Conduit Raceway Review for USI A-46 and Seismic IPEEE - Documentation for BFN Unit I Reactor Building El. 621',"

NVDP No. BFN I -CEB-RCWY-621, 7/31/03.

8. "Walkdown Data Packages for Cable Tray and Conduit Raceway Review for USI A-46 and Seismic IPEEE - Documentation for BEN Unit I Reactor Building El. 639',"

WDP No. BFNI-CEB-RCWY-639, 7/31/03.

If questions arise as to the substance of this review, please my pleasure to continue to support the efforts of TVA to support the energy demands of the United States.

Sincerely, feel free to contact me. It is bring BFN Unit I on-line to James J. Johnson President cc. John 0. Dizon, Facility Risk Consultants Letter, James 3. Johnson to Richard D. Cutsinger, Page 3 of 3 FACILWTY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 6-1 0 6.3 MECHANICAL AND ELECTRICAL EQUIPMENT PEER REVIEW REPORT FACILTY RISK CONSULTANTSt INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 6-11 JAMES J. JOHNSON, PN.D., P.E.

James J. Johnson and Associates 7 Essex Court, Alamo, CA 94507 Phone: (925) 837-4749 - Fax: (925) 838-9227 30 June 2004 Mr. Richard D. Cutsinger Tennessee Valley Authority Browns Ferry Nuclear Plant, RSB 1 -7/BFN P. 0. Box 2000 Decatur, AL 35609-2000

Subject:

Independent Peer Review Browns Ferry Unit I (BFN-1) Seismic Verification of Mechanical and Electrical Components for Resolution of NRC Unresolved Safety Issue' (USI)A Dear Mr. Cutsinger.

During the period of 10 June 2004 to the current date, I performed an Independent Peer Review of the seismic verification of mechanical and electrical components of the Seismic Verification of Nuclear Plant Equipment Program (Resolution of USI A-46).

The complete program is documented in Ref. 1. Its implementation was separated into four phases: Safe Shutdown Equipment List, Cable Tray and Conduit Raceway Sysiems, Mechanical and Electrical Components, and Relay Review. I previously performed the Independent Peer Review of the Safe Shutdown Equipment List (Ref. 2) and the Cable Tray and Conduit Raceway Systems (Ref. 3). The scope of this portion of the program covers all mechanical and electrical components at BFN-I on the Safe Shutdown Equipment Lisi (SSEL) (Ref. 5) and not previously evaluated during the USI A-46 programs for BFN Units 2 and 3.

This Independent Peer Review completes the Independent Peer Review of the implementation.

The approach and result are consistent with the GIP (Ref. 4) and acceptable to meet the requirements for resolution of USI A-46 for BFN Unit 1.

Mechanical and Electrical Components on the BFN-1 SSEL The composite safe shutdown equipment list for BFN-I contains 906 items. A total of 525 components were identified on the BFN-I SSEL for detailed evaluation. This list excludes items evaluated in the seismic verification of safe shutdown components for BFN-2 and BFN-3, which are part of shared systems. It, also, excludes items that are deemed inherently rugged, such as check valves, and items associated with the LPCI M-G sets, since these M-G sets are being eliminated. Table I summarizes the components by GIP equipment class.

Letter, James 1. Johnson to Richard D. Cutsinger, Page I of 4 FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September23, 2004 Page 6-12 A representative set of Screening Evaluation Work Sheets (SENVS) was reviewed. A general observation is that the SEWS are very clear and well document the in-field condition of the components and their in-office evaluation, supported by calculations as necessary. Extensive use of photographs documents important aspects of the components and the surrounding areas.

A particular focus of my review was on the components identified to have outlier conditions. The number of mechanical and electrical components with outlier conditions was 84, Table 5-] (Ref. 1). Fifty-three individual Outlier Seismic Verification Sheets (OSVS) were rTitten, which affected the 84 components.

Obviously, an individual OSVS can affect a number of components and a component may have more than one OSVS. The details are well documented in Ref. 1. An additional six outliers were identified for tanks and heat exchangers.

I reviewed representative components identified to be outliers in more detail, including in-plant walkbys where accessible. Some examples are:

"Outlier Evaluation of Main Steam Isolation Valves for USI A-46 Resolution,"

CDQ1 001 2004 0143.

Four inboard and four outboard valves were evaluated following the approach taken for BFN-2 and BFN-3. Reviewed in-office.

"Seismic II/I Evaluation of HVAC Ducts and Supports Inside Unit l Drywell,"

CDQI 080-2003-1196.

Seven Main Steam Relief Valves (MSRVs) and seven associated solenoid valves for the MSRVs were resolved for seismic interaction IL1/

issues inside the drywell. Reviewed in office.

• Motor Control Centers 19030 and 19031 reviewed in-office and in-plant.

• Junction box 19042 reviewed in-office and in-piant.

• Instrument panel 19088 reviewed in-office and in-plant.

• RPS panels 19120, 19121, 19122, and 19128 reviewed in-office and in-plant.

• Instrument panels 19129, 19130, 19132, and 19136 reviewed in-office and in-plant.

• Instruments on rack 19128 reviewed in-office and in-plant.

• RPS panel 19223 reviewed in-office and in-plant.

• Battery chargers 19307, 19308, 19309, and 19310 reviewed in-office and in-plant.

• Shutdown board 19418 reviewed in-office and in-plant.

• Transformer 19794 reviewed in-office and in-plant.

Letter, James J. Johnson to Richard D. Cutsinger, Page 2 of 4 FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 6-13 Intent Versus Specific Wording of the GIP In addition to the outliers identified above, there were 78 instances of the seismic demand response spectrum at the support locations of the components (floor level) exceeding the capacity spectrum in a limited frequency range. Elevations in the reactor building where this situation could exist are floor elevations 593', 621.25', and 639'. Table 4-1 (Ref. 1) identifies tfhese situations. Each of these situations at'as evaluated individually and the estimated lowest frequency of the component was verified to be in a frequency range where the capacity spectrum exceeded the demand spectrum.

A representative sample of these cases was reviewed.

Configuration Control Resolution of a number of outliers was through modification, maintenance, or replacement of equipment components. This is appropriate. However, new systems or modifications to existing systems, which will be installed over the next one or two years to complete BFN Unit 1, should be verified to not invalidate the assessments performed herein.

Verification of no new hazards may be accomplished through an office evaluation and/or in-plant walkdowvn. This may be accomplished at the final walkdown stage prior to area turnover. Along this vane, Ref. I contains Appendix H Area Turnover Walkdown Punch List, which documents actions to be taken to verify the seismic adequacy of components before plant startup.

This is an excellent approach to verifying that no new hazards are introduced and that appropriate outlier resolutions have been made before plant startup.

References

1. Facility Risk Consultants, "Browrns Ferry Nuclear Plant Unit 1 USI A-46 Seismic Evaluation Report," Report No. TVA/BFN-01-R-004, Rev. 0, Draft, 30 June 2004.

2. "Independent Peer Reviewv ro'wns Ferry Unit I (BFN-1) Safe Shutdown Equipment List (SSEL) for Resolution of NRC Unresolved Safety Issue (IJSI) A-46 and Addressing Individual Plant Examination for External Events (IPEEE)," Letter, James J. Johnson and Associates to RDCutsinger, 17 March 2003.

3. "Independent Peer Review Browns Ferry Unit I (BFN-1) Seismic Verification of Cable Tray and Conduit Raceway Systems for Resolution of NRC Unresolved Safety Issue (USI) A-46," Letter, James 3. Johnson and Associates to RDCutsinger, 13 August 2003.

4. Seismic Qualification Utility Group (SQUG), "Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment," Rev. 2A, March 1993.

5. BFN - 1, "Composite Safe Shutdown Equipment List (SSEL) for USI A-46 and Seismic IPEEE Programs," Cal. No. CDQI-999-2003-0654, Rev. 002.

Letter, James J. Johnson to Richard D. Cutsinger, Page 3 of 4 FACILITY RIsK CONSULTANTS, INC.

TVN/BFN-01 -R-004 Revision 0 September23, 2004 Page 6-14 Table I Equipment Class Description Class No. on No. of Identification BFN-1 Components No.

SSEL with Outliers Motor Control Centers 1

7 2

Low Voltage Switch Gear 2

2 1

Medium Voltage Switch Gear 3

2 0

Transformers 4

8 1

Horizontal Pumps 5.

0 0

Vertical Pumps 6

8 2

Fluid-Operated Valves 7

70 28 Motor Operated Valves 8a 60 1

Solenoid Operated Valves 8b 27 13 Fans 9

0

° 0

Air Handlers 10 6

1 Chillers 11 0.

0 Air Compressors 12 0

0 Motor Generators 13 0

0 Distribution Panels 14 86 3

Batteries on Racks 15 5

0 Battery Chargers and Inverters 16 9

6 Engine Generators 17 0

0 Instruments on Racks 18

88.

9 Temperature Sensors 19 16 0

Instrument and Control Panels 20 110 16 Tanks and Heat Exchangers 21 16 6

Other 0

. 5 1

If questions arise as to the substance of this review, please feel free to contact me. It is my pleasure to continue to support the efforts of TVA to bring BFN Unit I on-line to support the energy demands of the United States.

Sincerely, James J. Johnson President cc. John 0. Dizon, Facility Risk Consultants Letter, James J. Johnson to Richard D. Cutsinger, Page 4 of 4 FACILITY RISK CONSULTANTSt INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page 7-1

7. REFERENCES

1. "Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment." C) Seismic Qualification Utility Group (SQUG). Revision 2A. March 1993.

2. "Supplement No. 1 to Generic Letter (GL) 87-02 that Transmits Supplemental Safety Evaluation Report No. 2 (SSER No. 2) on the SQUG Generic Implementation Procedure, Revision 2, as Corrected on February 14,1992 (GIP-2)." May22,1992.

3. "Browns Ferry Nuclear Plant Final Safety Analysis Report." Tennessee Valley Authority.

-4. Letter from TVA (O.J. Zeringue) to NRC describing approach for-the resolution of USI A_46 and the implementation of seismic IPEEE (Initial 120-day response to Supplement 1 of GL 87-02). R08 920921 671. September 21,1992.

5. Letter from NRC (F.J. Hebdon) to TVA (M.O. Medford) requesting clarification and additional information on TVA's 120-day response to Supplement 1 of GL 87-02.

November 19,1992.

6. Letter from TVA (O.J. Zeringue) to NRC providing additional information on the approach for the resolution of USI A-46 and the implementation of seismic IPEE. R08 930119 958. January 19,1993.

7. Letter from NRC (F.J. Hebdon) to TVA (M.O. Medford) accepting TVS's approach for the resolution of USI A-46 at BFN. March 19, 1993.

8. TVA Calculation no. CDQ1-999-2003-0654, "Composite Safe Shutdown Equipment List (SSEL) for USI A-46 and Seismic IPEEE Programs." Revision 3.

9. FRC Report no. TVA/3FN-01 -R-001, "USI A-46 / Seisrnic IPEEE Relay Evaluation Browns Ferry Nuclear Plant Unit 1." Revision 0, 23 January 2004.

FACILI1Y RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-1 APPENDIX A LEAD RELAY REVIEWER AND SEISMIC REVIEW TEAM QUALIFICATIONS FACcLIIY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-2 RESUME - Lead Relay Reviewer Performed Relay Functionality Review Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Name:

Jess 0. Betlack Bachelors Degree:

B.S. Electrical Engineering,i1966 Institution:

University of Kansas Advanced Degree:

M.S. Electrical Engineering, 1967 Graduate Studies in Electrical Engineering and Computer Science Institution:

University of Kansas and University of New Mexico Date and location of Seismic Adequacy Verification Training Courses:

USI A-46 Course:

SQUG Relay Seismic Functionality Evaluation Date:

1988-1996 Location:

SQUG Subject Matter Expert and Course Instructor Seismic Course:

IPEEEE Date:

Location:

Earthquake engineering experience applicable to nuclear power plants and in structural or mechanical engineering:

30 years (see attached resume)

Licensed Professional Engineer: Yes 0 No 03 State of Maryland FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-3 RESUME - Seismic Capability Engineer Member of a Seismic Review Team Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Name:

John O. Dizon Bachelors Degree:

B.S. Civil Engineering, 1973 Institution:

Mapua Institute of Technology Advanced Degree:

M.S. Structural Engineering, 1975 Engineer Degree, 1977 Institution:

Stanford University Date and location of Seismic Adequacy Verification Training Courses:

USI A-46 Course:

SOUG Walkdown Screening & Seismic Evaluation Training Course Date:

January 13-19, 1993 Location:

San Francisco, CA (EQE)

Seismic Course:

Seismic IPE Add-on Training Course IPEEEE Date:

October 13-15, 1992 Location:

Chicago, IL Earthquake engineering experience applicable to nuclear power plants and in structural or mechanical engineering:

27 years (see attached resume)

Licensed Professional Engineer: Yes 0 No 0 State of California FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-4 RESUME - Seismic Capability Engineer Member of a Seismic Review Team Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Name:

Stephen J. Eder Bachelors Degree:

B.S. Civil and Environmental Engineering, 1980 Institution:

Clarkson College of Technology Advanced Degree:

M.Eng. Structural Engineering & Structural Mechanics, 1982 Institution:

University of California, Berkeley Date and location of Seismic Adequacy Verification Training Courses:

USI A-46 Course:

SQUG Walkdown Screening & Seismic Evaluation Training Course Date:

1988-1994 Location:

SQUG Subject Matter Expert and Course Instructor Seismic Course:

Seismic IPE Ad-on training IPEEEE Date:

1992 - 1994 Location:

Reviewer of EPRI seismic margins training course as SQUG Subject Matter Expert Earthquake engineering experience applicable to nuclear power plants and in structural or mechanical engineering:

22 years (see attached resume)

Licensed Professional Engineer: Yes El No al States of Alabama & California FACILInY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-5 RESUME - Seismic Capability Engineer Member of a Seismic Review Team Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Name:

Farid Elsabee.

Bachelors Degree:

B.S. Engineering, 1973 Institution:

State University of New York at Stony Brook Advanced Degree:

M.S. Civil Engineering (Structures), 1975 Institution:

Massachusetts Institute of Technology Date and location of Seismic Adequacy Verification Training Courses:

USI A-46 Course:

SQUG Walkdown Screening & Seismic Evaluation Training Course Date:

August 10-14,1992 Location:

Millstone Nuclear Station Seismic Course:

Seismic PE Ad-on training IPEEEE Date:

November 2 - 4, 1992 Location:

Millstone Nuclear Station Earthquake engineering experience applicable to nuclear power plants and in structural or mechanical engineering:

27 years (see attached resume)

Licensed Professional Engineer: Yes 0 No El RACWLTY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page A-6 RESUME - Seismic Capability Engineer Member of a Seismic Review Team Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Name:

Robert D. Hookway Bachelors Degree:

B.S. Mechanical Engineering, 1963 Institution:

Lowell Technological Institute Advanced Degree:

M.S. Mechanical Engineering, 1970 Institution:

Northeastern University Date and location of Seismic Adequacy Verification Training Courses:

USI A-46 Course:

SQUG Walkdown Screening & Seismic Evaluation Training Course Date:

January 13-19, 1993 Location:

San Francisco, CA (EQE)

Seismic Course:

IPEEEE Date:

Location:

Earthquake engineering experience applicable to nuclear power plants and in structural or mechanical engineering:

30 years (see attached resume)

Licensed Professional Engineer: Yes El No 0 l States of Massachusetts & Virginia FCILY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page A-7 RESUME - Relay Reviewer Performed Relay Functionality Review Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Name:

Marc D. Quilici Bachelors Degree:

B.S. Engineering, 1977 Institution:

Idaho State University Advanced Degree:

Institution:

Date and location of Seismic Adequacy Verification Training Courses:

USI A-46 Course:

Equipment Selection and Relay Evaluation Training Course Date:

March 22 - 24,1993 Location:

Rockville, MD Seismic Course:

IPEEEE Date:

Location:

Earthquake engineering experience applicable to nuclear power plants and in structural or mechanical engineering:

27 years: 24 years experience in systems engineering; and 10 years experience in seismic relay evaluation and SSEL work Licensed Professional Engineer: Yes 0 No E0

-r FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-8 RESUME - Seismic Capability Engineer Member of a Seismic Review Team Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Name:

Richard L. Tiong Bachelors Degree:

B.S. Civil Engineering, 1978 Institution:

University of London, England Advanced Degree:

M.S. Structural Engineering and Structural Mechanics, 1981 Institution:

University of California, Berkeley Date and location of Seismic Adequacy Verification Training Courses:

USI A-46 Course:

SQUG Walkdown Screening & Seismic Evaluation Training Course Date:

January 15 - 20, 1993 Location:

Irvine, CA (EQE)

Seismic Course:

IPEEEE Date:

Location:

Earthquake engineering experience applicable to nuclear power plants and in structural or mechanical engineering:

22 years (see attached resume)

Licensed Professional Engineer: Yes 1 No 0 State of California FACLITY RtsK CONSULTANTS NC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-9 JESS BETLACK, P.E.

EDUCATION University of Kansas and University of New Mexico, Graduate Studies in Electrical Engineering and Computer Science University of Kansas, M.S. Electrical Engineering, 1967 University of Kansas, B.S. Electrical Engineering, 1966 (With Distinction)

PROFESSIONAL HISTORY 1964 - 1968 University of Kansas 1968 - 1973 Sandia Laboratories 1973 - present MPR Associates, Inc.(currently as a special assignment employee)

EXPERIENCE Mr. Betlack has worked in the fields of electrical engineering and computer science since 1964.

Specific activities have included the design, analysis, development and testing of computer systems and components (both hardware and software), electrical and electro-mechanical systems and components, and instrumentation and controls.

Projects have involved data acquisition, processing, monitoring, simulation and control computer systems, database systems, test facility and power plant instrumentation and controls, and modeling and simulation of power plants and power plant equipment including steam generators, turbines, pumps, instrumentation, controls and electrical equipment. The design and analysis activities, including troubleshooting and plant life extension evaluations, have involved extensive in-plant experience. Projects have also included seismic functionality evaluations of relays and other electrical equipment, and vibration monitoring and testing of such equipment.

Specific examples of Mr. Betlack's experience include:

Design, Development, and Evaluation of Computer Systems Designed, developed, implemented and tested on-line and real-time computer systems used in support of flight, environmental, and full-scale testing.

Specific activities have included feasibility studies, systems analysis and design, software development, preparation of functional specifications, component and system specifications, component and system procurement, data acquisition and reduction, acceptance and benchmark tests, and system and component evaluations.

Participated as a committee member and writer of several Electric Power Research Institute (EPRI) guidelines for design, development, licensing, and dedication of digital l&C system upgrades for the nuclear industry.

Evaluated the design and standards compliance of several power plant instrumentation, control, and protection digital systems.

FACIuTY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page A-1 0 Design and development of a networked environmental monitoring system.

Design and Development of Instrumentation and Controls (I&C)

Designed and coordinated the development and check-out of power plant I&C equipment including a reactor coolant pump seal leakage flowmeter, an ultrasonic level sensing system controller, and a nuclear plant steam generator cleaning system controller.

Specified, reviewed and provided oversight of the design, development, installation and testing of a five-instrument two-phase flowmeter and other advanced instruments used in international reactor safety test facilities.

Developed instrumentation and monitoring capabilities for the evaluation of equipment problems including fan vibration and pump seal rubbing.

Technical lead for implementation of U.S. Nuclear Regulatory Commnission (USNRC)

Regulatory Guide (R.G.) 1.97 design requirements at a nuclear power station.

Life Extension Evaluations Performed life extension evaluations of electrical equipment, instrumentation and controls in over 15 fossil and nuclear plants.

Relay/Control Seismic Functionality Evaluations Developed relay seismic functionality evaluation procedure for application in resolving USNRC Unresolved Safety Issue (USI A-46) and Individual Plant Examination of External Events (IPEEE). Coordinated and evaluated seismic testing of over 150 relays in support of the nuclear power industry resolution of USI A-46.

Performed and reviewed relay seismic functionality evaluations for several nuclear plants.

Training and Teaching Taught over 20 industry training courses on USI A-46 relay seismic functionality evaluation and courses on computer-based I&C systems. Teaching assistant in logic design and laboratory instructor for computer science and programming at the University of Kansas.

MEMBERSHIPS Tau Beta Pi - National Engineering Eta Kappa Nu - National Electrical Engineering Instrument Society of America (ISA)-Senior Member Registered Professional Engineer - Maryland FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September23, 2004 Page A-1 1 PUBLI CATI ONS Publications have consisted of many reports, software documents and internal design and evaluation documents at MPR, Sandia Laboratories, and CRES (University of Kansas Research Center). These have included:

• Master's Thesis -- "A Preprocessor for Multi-Spectral Images."

• SC-DR-21-0419 -- "Area III Automated Data Processing System."

• SC-TM-69-509 -- "Operations and Maintenance Documents for Program FIXCAM."

• EPRI NP-7148 -- "Procedure for Evaluating Nuclear Power Plant Relay Seismic Functionality." (Primary author).

• EPRI TR-107980, "I&C Upgrades for Nuclear Plants -- Desk Reference 1997," December 1997.

• EPRI TR-107339, "Evaluating Commercial Digital Equipment for High Integrity Applications," December 1997 (Co-writer).

EPRI TR-106436, "Guidance on Evaluation and Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Applications," October 1996 (Co-writer).

EPRI TR-102348, "Guideline on Licensing Digital Upgrades," December 1993 (Co-writer).

Presentations on digital I&C, database systems, and relay seismic functionality evaluation and testing have been made at national and international conferences including:

EPRI International I&C Conference (December, 1997).

ANS 1994 Winter iviecting EPRI Workshop on Licensing Issues Concerning Digital I&C Upgrades for Nuclear Power Plants (March, 1992).

10th International Conference on Structural Mechanics in Reactor Technology (SMIRT).

3rd Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment and Piping.

6th Water Reactor Safety Information Meeting of the U.S. Nuclear Regulatory Commission.

FACILITY RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September 23, 2004 Page A-1 2 JOHN 0. DIZON, P.E.

PROFESSIONAL IRSTORY Facility Risk Consultants, Inc., Fremont, Callifornia & Huntsville, Alabama, President, 2002-present ABS Consulting (foyrmerly EQE International), Oakland, California, Director and VP of Facility Risk, 2000-2002 EQE International, Oakland, California, Vice President, 1998-2000; Associate, 1991-1998; Senior Engineer, 1986-1991 Engineering Decision Analysis Company, Cupertino, California, Senior Engineer, 1984-1986 General Electric Company, San Jose, California, Senior Engineer, 1984 URSIJohn A. Blume & Associates, San Francisco, California, Senior Engineer, 1982-1984; Associate Engineer, 1977-1980 Structural Systems Engineering, Inc., Lafayette, California, Senior Engineer, 1980-1982 Stanford University, John A. Blume Earthquake Engineering Center, Palo Alto, California, Teaching and Research Assistant, 1975-1977 PROFESSIONAL EXPERIENCE Mr. Dizon has over 25 years of experience in the field of civil and structural engineering, earthquake engineering, risk assessment and project management. He has extensive knowledge in the areas of seismic analyses and design assessments of primary structures and piping systems, seismic upgrade and retrofit design, seismic qualification of mechanical and electrical systems and components, and technical development of seismic evaluation criteria and programs for various industries, including power, oil and gas, petrochemical, and high tech process and manufacturing facilities. Mr. Dizon has undertaken and managed a wide variety of seismic projects, ranging from traditional structural engineering design and seismic retrofits to complex nuclear power plant and DOE facilities' seismic verification projects.

As President of Facility Risk Consultants, Mr. Dizon is currently managing all associated tasks under a subcontract with Bechtel Power Corporation for all seismic-related issues associated with Browns Ferry Unit 1 Restart Project for Tennessee Valley Authority. The seismic works include USI A-46/lPEEE implementation programs, seismic 11/1 spray hazard evaluations, new cable routing utilizing the SQUG/GIP methodology, MSIV seismic ruggedness verification, among others. Currently, he is also actively involved in the development of seismic II/I design criteria for distribution systems and equipment for DOE's PDCF project, under a subcontract with the Washington Group, Inc. In addition, Mr. Dizon is participating as a subject matter expert witness in a litigation project for a large foreign company in the area of seismic performance of structures, piping systems and associated equipment associated with earthquake damges in a coal-fired power plant located in South America.

As EQE Project Manager for various seismic programs associated with the restart of Browns Ferry Units 2 and 3, Mr. Dizon was responsible for all engineering activities associated with USI A-46 FACLuTY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page A-1 3 resolution and seismic IPEEE implementation; seismic proximity and 11/1 spray interaction evaluations; MSIV seismic ruggedness verification; cable tray and conduit raceway and supports; and HVAC support evaluation programs.

These activities consisted of seismic criteria development, seismic walkdown assessments and mitigation of findings, including retrofit designs and plant upgrades. He was also responsible for the A-46 seismic evaluation program for major equipment items at Davis-Besse, Duane Arnold and H.B. Robinson power plants. Mr. Dizon also served as Project Manager for the HVAC seismic verification program at Salem Nuclear Plant, MSIV seismic projects at Hope Creek and Brunswick plants, and participated in a number of related seismic evaluation projects at Sequoyah, Watts Bar, Bellefonte, Pickering A, Bruce A, Forsmark, Liebstadt, among others.

As Managing Director of EQE's Hsinchu, Taiwan project office following the 1999 Chi-Chi earthquake, he was in charge of the region's business development and project management. Mr.

Dizon managed a number of seismic risk assessment and structural upgrade projects for the high tech industry, including seismic consultation on a number of projects for Taiwan Semiconductor Manufacturing Co., seismic strengthening projects for United Microelectronics, Applied Materials, Winbond Electronics and Macronix International in Taiwan. In addition, he also managed the seismic upgrades for the Cypress Semiconductor and Anruor facilities and seismic design review project for IBM in the Philippines, seismic risk assessment for AMP facilities in Japan, and seismic assessment of structural and non-structural components of several Intel fab plants in the Northwest region in U.S., among others.

As Group Manager for EQE at the US Department of Energy Savannah River Site, Mr. Dizon was responsible for the seismic verification program of safety-related mechanical and electrical systems and components.

His tasks included developing seismic evaluation criteria and procedures for restart and long-term seismic programs; managing the seismic walkdown and evaluation efforts; providing technical support in resolving seismic issues; and serving as an interface with the client.

Mr. Dizon was also responsible for the seismic walkdown and evaluation of various distribution systems at the Pantex Facilities, including developing the walkdown screening criteria and evaluation acceptance criteria. Mr. Dizon has participated in the seismic evaluation of the High Flux Isotope Reactor at Oak Ridge National Laboratory. This project involved performing seismic analyses and upgrades for the primary coolant piping system and related equipment, and the reactor and control buildings.

Other DOE facilities he has involvement with included Los Alamov, Livermore and Hanford sites. Mr. Dizon has also been involved in a number of risk assessment programs for petrochemical plants and refineries, including seismic walkdowns at the Imperial West Chemical plants in Pittsburg and Antioch, CA; Tosco Refinery in Avon, CA; and Dupont Chemical plant in Antioch, CA, among others.

At EDAC, Mr. Dizon was responsible for the development and verification of a pipe support optimization program (OPTPIPE) and was involved in a number of snubber reduction pilot projects. Other areas of his involvement consisted of finite element analyses of the MX-missile launch tube components and systems for thermal and pressure loads, equipment qualification of major mechanical and electrical components, and seismic evaluation of cooling towers.

With General Electric Company, Mr. Dizon was responsible for stress analysis and code conformation of main steam and recirculation piping systems for generic BWR plants. He was also involved in the developmental phase of an in-house pipe support optimization program FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-1 4 At URS/Blume & Associates, Mr. Dizon was responsible for the development and maintenance of in-house computer programs for both linear and nonlinear analyses of structural and piping systems.

He was also involved in the linear and nonlinear dynamic analyses, finite element modeling, and generation of floor response spectra for several nuclear power plants. He helped develop a soil-structure interaction computer program using a three-dimensional finite element technique to evaluate the dynamic response of structures due to arbitrary plane body and surface wave excitations. He performed a research study involving soil-structure interaction analysis using the finite element FLUSH program to investigate the dynamic response of typical containment structures due to underground blast excitations.

Mr. Dizon worked as a consultant to Bechtel Power Corporation with Structural Systems Engineering, Inc.

He performed structural analyses and design assessments of the primary containment structure and the reactor/control buildings of several BWR plants for the various types of hydrodynamic loads. He was involved in a BWR in-plant test procedures, data reduction and correlation study to determine the dynamic response, including soil-structure interaction of the reactor/control buildings during GE Mark II reactor hydrodynamic load actuation in the primary containment.

At Stanford University, Mr. Dizon performed statistical analyses of earthquake accelerograms and various response parameters, as part of his research work under Professor Haresh Shah. He also conducted seismic risk analyses and formulated seismic design criteria for Nicaragua. In addition, he was involved in the dynamic testing of structural models and equipment.

EDUCATION STANFORD UNIVERSITY, Palo Alto, California: Engineer Degree, 1977 STANFORD UNIVERSITY, Palo Alto, California: M.S. Structural Engineering, 1975 MAPUA INSTITUTE OFTECHNOLOGY, Manila, Philippines: B.S. Civil Engineering, 1973 AFFILIATIONS AND AWARDS Earthquake Engineering Research Institute, Member Philippine Board Examination for Civil Engineers, Fifth Place, 1973 Philippine Association of Civil Engineers, Certificate of Merit, 1974 REGISTRATION California: Civil Engineer Philippines: Civil Engineer SELECTED PUBLICATIONS With S. J. Eder, and R. D. Cutsinger. 2003. " Browns Ferry Cable Tray Evaluations." Presented to the SQUG/SEQUAL Annual Meeting, San Antonio, TX, December 10-12, 2003.

With S. J. Eder. 2003. " Technical Position Paper for Seismic lI/I Design of Cable Tray Raceway Systems at PDCF." Presented to Washington Group, Inc., December 2003.

FACcLarw RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-1 5 With S. J. Eder, W. H. Tong, and E. H. Wong, 1999. "Chichi, Taiwan Earthquake of September 21, 1999 (M7.6). An EQE Briefing. Oakland, CA. October, 1999.

With S. J. Eder. 1998. "Risk Management for Power and Industrial Facilities -- Focus on Business Interruption".

Second Biennial Federation of Asian Pacific & African Risk Management Organization. Manila, Philippines. October, 1998.

With F. R. Beigi. 1995. "Application of Seismic Experience Based Criteria for Safety Related HVAC Duct System Evaluation." Fifth DOE Natural Phenomena Hazards Mitigation Symposium, Denver, Colorado, November 13-14, 1995.

With S. J. Eder, J. F. Glova, and R. L. Koch. 1994. "Seismic Adequacy Verification of HVAC Duct Systems and Supports for an USI A-46 Nuclear Power Plant." Fifth Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment and Piping, Orlando, Florida, December 14-16, 1994.

With E. J. Frevold and P. D. Osborne. 1993. "Seismic Qualification of Safety-related HVAC Duct Systems and Supports."

ASME Pressure Vessel and Piping Division Coniference, Denver, Colorado, July 1993.

With S. J. Eder.

1991.

"Advancement in Design Standards for Raceway Supports and Its Applicability to Piping Systems." ASME Pressure Vessel and Piping Division Conference, San Diego, California, June 1991.

With R. D. Campbell and L. W. Tiong. 1990. "Response Predictions for Piping Systems W'hich Have Experienced Strong Motion Earthquakes." ASME Pressure Vessel and Piping Conference, Nashville, Tennessee, June 17-21, 1990.

With S. P. Harris, R. S. Hashimoto, and R. L. Stover.

1989.

"Seismic, High Wind, and Probabilistic Risk Assessments of the High Flux Isotope Reactor."

Second DOE Natural Phenomena Hazards Mitigation Conference.

With D. Ray and A. Kabir. 1979. "A 3-D Seismic Analysis for Arbitrary Plane Body and Surface Wave Excitations." American Society of Civil Engineers Nuclear Specialty Conference, Boston, Massachusetts..

With D. Ray and A. Zebarjadian.

1978. "Dynamic Response of Surface and Embedded Disk Foundations for SH, SV, P and Rayleigh Wave Excitations."

Sixth Indian Symposium on Earthquake Engineering, Roorkee, India.

"A Statistical Analysis of Earthquake Acclerograms and Response Parameters."

1977. Thesis, Stanford University, Palo Alto, California, With H. Shah, T. Zsutty, H. Krawinkler, and L. Padilla. 1977. "A Seismic Design Procedure for Nicaragua."

Paper presented at the Sixth World Conference on Earthquake Engineering, New Delhi, India.

With H. Shah, T. Zsutty, H. Krawinkler, C. P. Mortgat, and A. Kiremidjian. 1976. "A Study of Seismic Risk for Nicaragua, Part II, Summary and Commentary." John A. Blume Earthquake Engineering Center, Report No. 12A and 12B. Stanford University, Palo Alto, California.

FAC LCTY RisK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-1 6 STEPHEN J. EDER, P.E.

PROFESSIONAL HISTORY Facility Risk Consultants, Fremont, California, Chief Executive Officer, 2003-present ABS Consulting, Houston, Texas, Vice President, North Asia Pacific Region, 2001-2003 EQE Internaiional, San Francisco, California, Senior Vice President, 1985-2001 (ABS Purchased EQE in 2000).

URS/Johln A. Blane & Associates, Engineers, San Francisco, California, 1982-1985 J. G. Bomvkanip, Inc., Snructural Engineers, Berkeley, California, 1981-1982 PROFESSIONAL EXPERIENCE Mr. Stephen J. Eder provides senior engineering and management consultant services, licensing support, and expert testimony in the fields of natural hazards risk assessment, seismic analysis, structural performance evaluation, and retrofit design.

His background includes project management, engineering, risk management, and planning for domestic and multinational corporations, insurance and financial institutions, construction companies, utilities, and the government. Mr. Eder is based in Madison, Alabama.

Prior to Facility Risk Consultants, Mr. Eder was stationed in Tokyo, Japan for 8 years and led all operations for ABS Consulting Inc. (formerly EQE International, Inc.) in Japan, China, Korea and Taiwan -- including risk consulting, structural engineering and design, probabilistic financial loss estimation, and the development and maintenance of management systems.

Mr. Eder has performed many post-earthquake reconnaissance studies -- most notably he led investigations of the M8.4 earthquake in Arequipa, Peru of June 2001; the M7.6 earthquake in Chichi, Taiwan of September 1999; and lie was lead investigator of the MS.] earthquake in Mexico of September 1985, for the US Electrical Power Research Institute (EPRI).

Prior to his assignment in Japan, Mr. Eder focused primarily in the seismic risk evaluation and seismic retrofit design of critical equipment and systems. Mr. Eder pioneered the development of many seismic risk evaluation procedures and criteria for the US and European nuclear power industry, the Seismic Qualification Utilities Group (SQUG), and the US Department of Energy (DOE). This included conducting a series of week-long seismic evaluation training courses for a total of about 500 engineers, and serving as subject matter expert and technical liason for industry groups.

Mr. Eder served as project manager or project consultant for the seismic risk surveys of critical equipment and systems at about 60 nuclear power plants in the US and Europe, and many DOE facilities.

He has developed unique, cost-effective structural designs for new installations and seismic strengthening of structures, equipment, and distribution systems including raceways, piping, and HVAC ducting. He performed research for and supported many U.S. industry and professional groups, to advance the state-of-the-art of seismic risk assessment techniques and seismic design guidelines.

FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page A-1 7 EDUCATI ON UNIVERSI OF CALIFORNIA, Berkeley: M.Eng., Structural Engineering and Structural Mechanics, 1982 CLARKSON COLLEGE OF TECHNOLOGY, Potsdam, New York: B.S., Magna Cum Laude, Civil and Environmental Engineering, 1980 REGISTRATION California: Civil Engineer, 1985 Alabama: Civil Engineer, 2003 PROFESSIONAL AND BUSINESS AFFILIATIONS American Society of Civil Engineers Earthquake Engineering Research Institute Structural Engineers Association of Northern California Applied Technology Council Tau Beta Pi National Engineering Honor Society Phi Kappa Phi National Honor Society American and British Chambers of Commerce in Japan COMMITTEES -- PAST EXPERIENCE Electric Power Research Institute - Post Earthquake Investigation Team - Leader U.S. Department of Energy - Tiger Team Member - Natural Hazards Risk Analysis U.S. Department of Energy - Steering Committee on Natural Hazards - Technical Liason -

Mechanical and Eletrical Equipment Evaluation and Design Seismic Qualification Utility Group - Equipment Seismic Evaluation Training - Lead Instructor and Subject Matter Expert Joint American Society of Mechanical Engineers and Institute of Electrical and Electronics Engineers - Special Seismic Qualification Working Group - CoChairman National Cenlerfor Earhquake Engineering Research - Critical Equipment Seismic Risk Analysis - Chief Researcher National Fire Protection Association (NFPA) - Seismic Technical Committee Member, NFPA-13.

Building Seismic Safety Council - Seismic Rehabilitation Advisory Panel Member -

Mechanical Equipment. NEHRP, FEMA 273.

American Society of Civil Engineers - Electrical Raceway and HVAC Duct Seismic Design -

Working Groups Structural Engineers Association of California - Seismology Subcommittee - Non-Building Structures and Equipment FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-1 8 SELECTED PUBLICATIONS & PRESENTATIONS "Analysis of 11o2 Plant Components Affected by the June 23, 2001 Mw 8.4 Arequipa, Peru Earthquake". Prepared for Hitachi Corporation. December 2002. Presented in London, U.K.

"The Use of Modeling and Natural Risk Analysis for Power Plants".

Presented at Second International Conference on Mitigating Your Risks in Energy. February 2002. Singapore.

"Using Risk Based Inspection Techniques to Assess Maintenance of Power Plants".

2002.

Presented at Second International Conference on Mitigating Your Risks in Energy. February 2002.

Singapore.

"Preparing Your Properties for Major Earthquakes".

2001.

Prepared for Architecture, Construction, and Engineering Subcomittee, American Chamber of Commerce in Japan. December 2001. Tokyo.

"Earthquake Hazards and Earthquake Risks in Tokyo".

2001.

TELS-Setagaya, Earthquake Disaster Information and Preparedness Seminar. October 2001. Tokyo.

"Geographic Information Systems".

2000.

Prepared for Non-Life Insurance Institute, ISJ Advanced Course 2000 Program, Natural Hazards and Underwriting Capacity. November 2000.

Tokyo.

With J. 0. Dizon, W. H. Tong, and E. R. Wong, 1999. "Chichi, Taiwan Earthquake of September 21, 1999 (M7.6). An EQE Briefing. Oakland, CA. October, 1999.

With G.S. Johnson, R.E. Sheppard, M.D. Quilici, and C.R. Scawvthorn, 1999. "Seismic Reliability Assessment of Critical Facilities:

A Handbook, Supporting Documentation, and Model Code Provisions."

Technical Report MCEER-99-0008.

Multidisciplinary Center for Earthquake Engineering Research, Buffalo, NY.

"Earthquake Risk of Independent Power Producer Stations", 1999. Prepared for Lloyd's Japan Power Seminar. June 1999. Tokyo.

With J. 0. Dizon. "Risk Management for Power and Industrial Facilities -- Focus on Business Interruption".

Second Biennial Federation of Asian Pacific & African Risk Management Organization. Manilla, Philippines. October, 1998.

"3 Years After the Hanshin-Kobe Earthquake, Earthquake Risk Management, Damage Assessment and Mitigation". 1998. High Pressure Gase Safety Association of Japan. Vol. 35, No. 2 (1998).

Tokyo.

With G. S. Johnson, R.E. Sheppard, and S.P. Harris. 1998. "A Method to Assess and Improve the Operational Reliability of Critical Systems Following Earthquakes."

Presented at the 6ih U.S.

National Conference on Earthquake Engineering, Seattle, WA, June 1998.

With G. S. Johnson, R.E. Sheppard, and S.P. Harris. 1998. "The Development of Model Code Provisions to Address System Reliability Following Earthquakes."

Presented at the ATC-29-1 Seminar on Seismic Design, Retrofit, and Performance of Nonstructural Components, San Francisco, CA, January 1998.

FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0

-September 23, 2004 Page A-1 9 With D. W. Jones, M. K. Ravindra, C. R. Scawthorn, and K. Iida.

1996.

"Earthquake Risk Management for Process Industries". High Pressure Gas Safety Institute of Japan. Vol. 35, No. 5 (1996). Tokyo.

With G. A. Antaki.

1994.

"Recommended Provisions for Equipment Seismic Qualification Consistent with IEEE and ASME Criteria for Use of Experience." ASME 1994, PVP-Vol. 275-2, Seismic Engineering, Volume 2.

With P. J. Butler and R. P. Kassawara.

1994.

"Application of the Generic Implementation Procedure Methodology to Demonstrate Seismic Adequacy of New and Replacement Equipment and Parts in USI A-46 Plants." ASME 1994, PVP-Vol. 275-2, Seismic Engineering - Volume 2.

Proceedings American Power Conference, Illinois Institute of Technology, April 1994, Chicago, Illinois.

With N. P. Smith and R. P. Kassawara.

1994.

"Future Direction for the Use of Earthquake Experience Data." Proceedings American Power Conference, Illinois Institute of Technology, April 1994, Chicago, Illinois.

With M. W. Eli and M. W. Salmon. November 1993. "Walk-through Screening Evaluation Field Guide, Natural Phenomena Hazards at Department of Energy Facilities."

UCRL-ID-115714, Revision 2. Lawrence Livermore National Laboratory.

"Seismic Design of Important Systems and Components--Functionality Considerations."

1993.

Structural Engineers Association of Northern California, 1993 Fall Seminar, Nonstructural Components: Design and Detailing. San Francisco, California.

With C. Scawthorn, M. Zadeh, and G. Johnson. 1993. "Economic Impacts of Earthquake Damage to Nonstructural Components."

40th North American Meetings of the Regional Sciences Association International, Houston, Texas.

With M. W. Barlow, R. J. Budnitz, and M. W. Eli.

1993.

"Use of Experience Data for DOE Seismic Evaluations."

4th DOE Natural Phenomena Hazards Mitigation Conference, Atlanta, Georgia.

With K. Porter, G. S. Jchnson, M. M. Zaden, and C. Scawthorn. 1993. "Seismic Vulnerability of Equipment in Critical Facilities: Life-safety and Operational Consequences." Technical; Report NCEER-93-0022. National Center for Earthquake Engineering Research.

With J. K. Arros. 1993. "Applications of Experience-based Methods for Seismic Qualification of Distribution Systems."

Prepared for Advanced Reactor Corporation FOAKE ALXVR Seismic Qualification Project.

With MPR Associates and Winston and Strawn. 1993. "Verifying the Seismic Adequacy of New and Replacement Equipment and Parts."

Prepared for the SQUG Management Guidelines Document.

With Lawrence Livermore National Laboratory.

1992.

"Program Plan for the Evaluation of Systems and Components in Existing DOE Facilities Subject to Nataral Phenonema Hazards."

Prepared for the U.S. Department of Energy.

FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page A-20 With J. 0. Dizon, P. D. Baughman, and G. S. Johnson. 1992. "Peer Review of the Watts Bar Nuclear Plant Integrated Interaction Program Suspended Systemns Proximity Task." Prepared for Tennessee Valley Authority.

With G. S. Hardy, G. S. Johnson, and R. W. Cushing of EQE; MPR; S&A; and URS.

1992.

"Walkdown Screening and Seismic Evaluation Training Course."

Prepared for Seismic Qualification Utility Group.

With M. W. Salmon. 1992. "Technical Safety Appraisal of the Idaho Chemical Processing Plant, NPH Discipline." Prepared for the U.S. Department of Energy.

With M. W. Eli.

1992.

"NPH Walkdown Evaluation Summary Report - Paducah Gaseous Diffusion Plant." Prepared for the U.S. Department of Energy.

With G. S. Johnson, R. H. Kincaid, and G. S. Hardy.

1992.

"High-rise Building Critical Equipment Study." Prepared for National Centerfor Earthquake Engineering Research.

With K. E. Smith.

1992.

"Seismic Performance of Standby and Emergency Power Engine Generator Systems." Prepared for National Center for Earthquake Engineering Research.

With M. W. Eli.

1991.

"Use of Earthquake Experience Data."

Prepared for the Third DOE Natural Phenomena Hazards Mitigation Conference, St. Louis, Missouri.

With J. 0. Dizon.

1991.

"Advancement in Design Standards for Raceway Supports and Its Applicability to Piping systems." PVP-Volume 210-1, Codes and Standards and Applications for Design and Analysis of Pressure Vessel and Piping Components. ASME 1991.

"Cable Tray and Conduit System Seismic Evaluation Guidelines." March 1991. EPRI Report NP-7151. Prepared for the Electric Power Research Institute. San Francisco, CA: EQE International.

With G. S. Johnson. March 1991.

"The Performance of Raceway Systems in Strong-motion Earthquakes." EPRI Report NP-7150. Prepared for the Electric Power Research Institute. San Francisco, CA: EQE International.

With G. S. Johnson. March 1991.

"Longitudinal Load Resistance in Seismic Experience Data Base Raceway Systems."

EPRI Report NP-7153.

Prepared for the Electric Power Research Institute. San Francisco, CA: EQE International.

With J. P. Conoscente and B. N. Sumodobila. March 1991. "Seismic Evaluation of Rod Hanger Supports for Electrical Raceway Systems." EPRI Report NP-7152. Prepared for the Electric Power Research Institute. San Francisco, CA: EQE International.

With Winston & Strawn, MPR Associates, Inc., etal.

June 1991.

"Generic Implementation Procedure (GIP) for Seismic Verification of Nuclear Plant Equipment." Revision 2. Prepared for the Seismic Qualification Utility Group.

With M. W. Eli and L. J. Bragagnolo. 1991. "Walkthrough Screening Evaluation Field Guide, Natural Phenomena Hazards at Department of Energy Facilities." Special Release for 3rd DOE Natural Phenomena Hazard Mitigation Conference, October 1991, St. Louis, Missouri.

FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-21 With L. J. Bragagnolo and J. P. Conoscente. 1990. "A Proposed Methodology for the Seismic Design of Rectangular Duct Systems." Applied Technology Center (ATC) Seminar on Seismic Design and Performance of Equipment and Nonstructural Elements in Building and Industrial Structures, Irvine, California. ATC-29.

With J. J. Johnson and N. P. Smith. 1990. "Developments of the Seismic Qualification Utility Group."

Applied Technology Center (ATC) Seminar on Seismic Design and Performance of Equipment and Nonstructural Elements in Building and Industrial Structures, Irvine, California.

ATC-29.

With W. Djordjevic, J. Eidinger, and F. Hettinger. 1990. "American Society of Civil Engineers Activities on Seismic Design of Electrical Raceways." Current Issues Related of Nuclear Power Plant Structures, Equipment, and Piping. Proceedings of the Third Symposium, Orlando, Florida, December 1990.

With H. L. Williams.

1990. "Qualification of Cable Tray Supports by Earthquake Experience Data:

Application at H. B. Robinson Plant" Current Issues Related of Nuclear Power Plant Structures, Equipment, and Piping.

Proceedings of the Third Symposium, Orlando, Florida, December 1990.

With R. P. Kennedy, J. D. Stevenson, J. J. Johnson, W. R. Schmnidt, and K. Collins. June 1990.

"Watts Bar Civil Program Review." Prepared for Tennessee Valley Authority.

With J. P. Conoscente, B. N. Sumodobila, and S. P. Harris. 1989. "Seismic Fatigue Evaluation of Rod Hung Systems."

Prepared for the Tenth Conference on Structural Mechanics in Reactor Technology, (SMiRT).

With P. D. Smith and J. P. Conoscente.

December 1988.

"SQUG Cable Tray and Conduit Evaluation Procedure." Paper presented at the Second Symposium on Current Issues Related to Nuclear Power Plant Structures, Equipment and Piping, Orlando, FL.

With P. 1. Yanev.

1988. "Evaluation of Cable Tray and Conduit Systems Using the Seismic Experience Data Base." Nuclear Engineering and Design (North-Holland, Amsterdam) 107: 149-153.

With S. P. Harris, P. D. Smith, and J. E. Hoekendijk. October 1988. "Performance of Condensers and Main Steam Piping in Past Earthquakes." Report prepared for General Electric Nuclear Energy Boiling Water Reactor Owners Group. San Francisco: EQE Engineering.

With J. J. Johnson, G. S. Hardy, N. G. Horstman, G. Rigamonti, M. R. Reyne, and D. R. Ketcham.

August 1988.

"Technical Basis, Procedures and Guidelines for Seismic Characterization of Savannah River Plant Reactors." E. I. Dupont De Nemours & Co, Aiken, South Carolina.

With S. P. Harris, P. S. Hashimoto, J. 0. Dizon, B. Sumodobila, G. M. Zaharoff, and L. J.

Bragagnolo.

March 1988.

"Seismic Evaluation of the High Flux Isotope Reactor Primary Containment System." Report prepared for Martin Marietta Energy Systems, Inc. San Francisco:

EQE Engineering.

FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-22 With S. W. Swan, "Summary of the Effects-of the 1985 Mexico Earthquake to Power and Industrial Facilities." Proceedings of the American Society of Civil Engineers International Conference on the 1985 Mexico Earthquake, Factors Involved and Lessons Learned, Mexico City, Mexico, September 1986.

With A. F. Kabir and S. Bolourchi, "Seismic Response of Pipes Supported on Complex Framing Systems."

Proceedings of the American Society of Civil Engineers Structures Congress, New Orleans, Louisiana, September 1986.

With S. W. Swan, "The Mexico Earthquake of September 19, 1985; Performance of Power and Industrial Facilities," Proceedings of the Third U. S. National Conference on Earthquake Engineering, Charleston, South Carolina, August 1986.

"Performance of Industrial Facilities in the Mexican Earthquake of September 19, 1985," Electric Power Research Institute Report No. NP-4605, Project 1707-30 Final Report, Palo Alto, California, June 1986, also presented at the IEEE Power Engineering Society Summer Meeting, Mexico City, --

Mexico, July 1986.

"Earthquake Response Analysis of a Braced Offshore Platform," University of California, Berkeley (June 1982), also American Petroleum Institute, October 1982, San Francisco, California.

FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-23 FARID ELSABEE

SUMMARY

Engineering: Analysis, Design, Inspection / Audit, and Management Over twenty five years of extensive experience in the nuclear power industry undertaking and managing retrofit and analysis projects. Experience includes linear and non-linear analysis of static and dynamic structural and mechanical systems where compliance with codes, standards, and specifications is required. The methods used include detailed finite element analyses. Expertise was acquired at both Architect / Engineer and consulting firms using and developing state-of-the-art analysis techniques for nuclear power plants.

Experience includes plant walkdowns at DOE facilities (Rocky Flats and Hanford) and numerous nuclear power plants (including SEP and USI A-46 related walkdowns) for review of seismic adequacy of various types of equipment. Attended EPRI sponsored training programs and certification for:

• CHEC Farnily of Codes, for Erosion Corrosion

• Walkdown Screening and Seismic Evaluation for USI A-46 (as a Seismic Capability Engineer)

• Add-on Seismic IPE, Seismic PRA and SMA for Seismic IPE Reviews EDUCATION MS Civil Engineering (Structures), Massachusetts Institute of Technology, 1975 BS Engineering, SUNY at Stony Brook, 1973 EXPERIENCE APPLIED ENGINEERING ASSOCIATES (1990 - present)

Principal with responsibilities in client development, applied mechanics projects, technical reviews and development and verification of CAE/CAD/FEM and data base management applications.

Consulting projects consisted of:

>> Providing Analysis and Field Support at TVA Browns Ferry Unit I (Through Facility Risk Consultants and Bechtel Corporation) for the following projects:

• Seismic evaluation and field walkdowns of plant Equipment in support of the resolution of USI A-46 requirements as a Seismic Capability Engineer. The work included plant mechanical and electrical equipment required for safe shutdown, including all plant cable tray and conduit systems. Evaluation of seismic II over I interactions, of piping and other support systems, was also performed to insure adequate non seismic supports in the vicinity of the safety related equipment.

All work was performed per the requirements of the SQUG GIP.

Recommendations for resolution of outliers were also prepared.

FACILITY RISK CONSULTANS, INC.

TVAIBFN-01-R-004 Revision 0 September 23, 2004 Page A-24

• Development of a generic design for the installation of new cable tray and conduit systems following the guidelines used in the USI A-46 evaluations. The designs were prepared and presented in a procedure format which is extremely easy to follow and implement by field electricians and engineers.

Providing Stress analysis support at ABS Consulting for the following projects:

• Seismic analysis of the refueling machine at the Bruce Nuclear Power Plant using a finite element model of the machine and the entire supporting structure. The dynamic analysis was performed using a linear elastic model of the machine head and suspension assemblies as well as the supporting frames, columns, elevators, bridge and carriage. The analysis of the detailed model, using the SAP 2000 software, resulted in the elimination of numerous modifications planned for implementation prior to the restart of the unit.

A three dimensional non-linear analysis of various Main Steam pipe clamps at snubber locations at the Pilgrim Nuclear power station. The clamp stresses were determined using staitic analyses of the non-linear models, which accounted for friction, gaps and interface loads at the pipe to clamp interface, using the ANSYS finite element program. The stress evaluations, performed for the mechanical loads applied by the snubbers to the pipe, were per the ASME Section III requirements.

>> Providing Project Engineering support at Altran Corporation for several projects including:

• Analysis, testing, project engineering and coordination for the evaluation and analysis of Steam Generator internals at Indian Point Unit 2. The project was in support of the restart effort associated with the tube leak resulting from Primary Water Stress Corrosion Cracking at a Row 2 U-bend tube. The project consisted of FEA of tube support plates and U-bend tubes; crack initiation and growth studies; experimental testing of U-bends; development of degradation assessments, condition monitoring and operational assessment of the secondary side components.

• Analysis, design and implementation of a large bore snubber reduction project for the steam generator support structures at Indian Point Unit 2.

• Inspection of roof structures and supporting decks, including development of repair specifications, for Con Edison's 59th Street fossil station.

• Assessment, evaluation and closure of condition reports and preparation of structural, mechanical and piping calculation revisions for Indian Point Unit 2.

Supporting Millstone Unit 2 (MP2) Design Engineering staff in day to day activities for a duration of six years, including their major recovery effort. Responsibilities included:

• Responsible engineer for seismic qualification and heavy load drop issues;

• Supporting the Configuration Management Project and Independent Corrective Action Verification Project (ICAVP) in investigating and addressing design basis issues and discrepancies in the areas of seismic equipment qualification, seismic structural analysis and design, heavy load drop analyses, and fuel rack design issues. This work was in support of the 50.54(f) effort and included interfacing with the NRC and the ICAVP contractor; FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page A-25

• Design Basis reconstitution of the reactor coolant loop system and the major NSSS components.

• Investigations of noted adverse conditions (Condition Reports) for design basis reviews of plant configurations;

• Review and preparation of FSAR changes and license amendments;

• Preparation of reportability and operability determinations, corrective actions and Licensee Event Reports;

• Preparation and review of plant modification packages for structural and equipment modifications;

• Preparation and review of calculations, DCN's, Technical Evaluations, Specifications and Procedures;

• Providing support for the reconstitution of the High Energy Line Break (HELB) program.

• Review and close out of administrative department items such as Assignment Requests, Engineering Work Requests, Project Files, etc.. and

• Providing vendor interface.

>> USI A-46 and IPEEE related consulting services at Northeast Utilities for three plants (CY, MPl and MP2). Work included development of a detailed project description, outline and plan, a program manual/instruction for the implementation phase, and a specification for new and replacement parts/components based on the EPRI/ STERI process to be used for plant end of life.

The project also included specific support for MP2 associated with plant walkdowns per the GIP (for USI A-46) and EPRI NP6041 (for IPEEE); interface with and managing other consulting companies; coordination of efforts between the appropriate Engineering and plant operations departments within the utility; preparing modification packages to correct identified outliers; providing response to NRC requests for additional information and justification of methods used (MP2's response on GIP Method A issues was identified by NRC as a good model to be used in other utilities responses); providing interface with the NRC and SQUG steering group on generic responses to NRC questions; and preparing and updating final reports.

>> Responsible for the structural aspects of an Appendix R fire protection modification which improved on the existing oil collection system to the RCP motors of a PWR unit.

>> Seismic equipment qualification consulting services related to the MOV Generic Letter 89-10 (CY, MP1, MP2, MP3), USI A-46 & IPEEE (MP2) and numerous plant design changes (CY, MPI, MP2); including test plan development, seismic qualification (in accordance with IEEE 344-1975) and development of replacement part requirements for a complete hydraulic power unit and it's controls by shake table testing (CY). The GL 89-10 work included review and update of MOV seismic qualification (weak link) reports, for Northeast Utilities and New York Power Authority, covering six nuclear plants, to maximize the valve structural thrust capacity by eliminating conservatisms found in existing qualification reports and previously used criteria. Prepared, managed and implemented two associated modification packages.

FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-26

>> Development of a Seismic Equipment Qualification Manual, for Northeast Utilities, which is applicable to four nuclear units spanning in design basis history from the SEP plants to a recently designed plant which is in full conformance with the SRP.

> Development of a specification for the seismic evaluation of existing rod hung electrical raceway systems to allow addition of new cables as well as for the design of new systems.

Evaluation of an Erosion / Corrosion inspection program for MP3 using EPRI's recommended practices. Supported the overall E/C program and the structural evaluation of the measured data at two plants (MPI & MP2).

>> Technical audits of the design and installation of piping, cable tray and conduit supports on the Philippines Nuclear Power Plant as part of an independent assessment of the design of the plant.

CYGNA ENERGY SERVICES (1985 - 1990)

Senior Project Manager Teclmical Specialist Division Manager Responsibilities included development and verification of CAEICAD/FEM applications, analysis and design, bid preparation, client development, project management and technical review for a number of diversified projects related to structural, equipment qualification, configuration management, licensing reviews, and Safety System Functional Inspections. Major specific projects included:

>> Specialized evaluation of non-conformance's associated with wind, tornado and seismic events for mechanical and electrical components using finite element analysis and simplified calculations.

>> Development and implementation of an asbestos survey program which included the identification, gathering and assimilation of the data into a computerized asbestos tracking system.

>> Gathering, assimilation and compilation of data into a Data Base Management System (DBMS) for several inspection programs which are part of a major fossil plant life extension program

>> Independent review of a major drawing discrepancy resolution and update project. This effort which is part of the utility's configuration management program includes instrumentation, electrical, mechanical, and piping systems.

>> Participated in the Safety System Functional Inspections (SSFI) of the pneumatic systems at a nuclear power plant. Responsibilities included preparations, inspections and reviews for structural and seismic related topics.

FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-27

)> Seismic and tornado evaluation of two existing structures against possible collapse using realistic structural characteristics and inelastic responses.

Supervised and coordinated projects in the area of erosion/corrosion of carbon steel piping and microbe induced corrosion in buried lined pipes.

STONE & WEBSTER ENGINEERING CORPORATION (1973 - 1977 & 1984 - 1985)

Engineer Project Management Responsible for several specialized projects in the area of seismic equipment qualification and large bore snubber elimination. Also participated in the development of the state-of-the-art procedures.

for soil structure interaction analysis. A few of the more noteworthy projects include:

)> Responsible for the analysis, design, and plant change packages for the elimination of large bore snubbers supporting steam generators and reactor coolant pumps on the primary coolant loop piping of three PWR's.

Development of generic seismic acceptance criteria of non-safety related equipment and review of numerous seismic equipment qualification vendor reports; including performing a seismic re-qualification of a 125 ton crane while accounting for its flexible girder support system.

)> Evaluation and resolution of safety related hazards resulting from postulated internally generated missiles.

> Performed seismic analyses of various structures, including both detailed and simplified soil-structure interaction procedures and developed structural design forces and in-structure response spectra.

)> Performed dynamic analyses of a BWR Mark 11 containment structure for hydro-dynamic loads.

URS/JOHN A BLUME AND ASSOCIATES (1979 - 1984)

Equipment Qualification Project Manager Developed specialized expertise in the area of seismic equipment qualification. Experience includes the development and implementation of full-scale seismic shaking-table testing programs; in-situ low-level excitation modal testing programs; innovative, state of the art techniques in seismic qualification by combined testing and analysis procedures; and field investigations / plant walkdowns consisting of "Expert Earthquake Engineers" to evaluate the seismic ruggedness of existing equipment.

Attended and participated in early SQUG meetings where development of seismic equipment evaluation methods using experience gained from performance of equipment during strong motion earthquakes was being formulated. Some of the projects undertaken include:

a> Development of realistic anchorage guidelines for EPRI and SQUG to be used in the SQUG-GIP for the resolution of generic issue A-46.

FACILITY RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September 23, 2004 Page A-28

>> Seismic evaluation of various types of mechanical and electrical equipment at nuclear power plants using finite element and simplified analyses, in-situ testing, shake-table testing and combined techniques. Some of the more significant equipment have included existing laterally flexible cable trays and conduits at the SEP plants (this work was subsequently used by the SQUG in the development of the GIP guidelines), control room panels and boards, motor control centers, switchgears and diesel generators.

> Evaluation of more than 60 items of mechanical and electrical equipment for seismic and tornado loads at the DOE Rocky Flats Facility. Structural integrity and operability evaluations for the seismic effects were performed using analytical techniques, in-situ modal testing, and full-scale shaking-table testing.

>> Evaluation of the seismic ruggedness of existing equipment at the DOE Hanford facility and the Nine Mile Point Unit I nuclear power plant as a member of a team of "Expert Earthquake Engineers".

INIPELL CORPORATION (EDS Nuclear) (1977 - 1979)

Supervisor Senior Engineer Responsible for the technical and administrative management of specialized projects such as pipe ruptures, finite element analysis and soil structure interaction. Analysis and development of pipe restraint design loads due to pipe whip and jet impingement effects resulting from postulated pipe breaks at several nuclear power plants.

Analysis procedures included both simplified energy balance techniques and detailed non-linear analysis.

Responsible for the structural design evaluation of miscellaneous structural steel frames for pipe support and pipe rupture loads.

Performed the seismic analysis of all Category I structures at a BW'R plant including soil structure interaction and generation of design forces as well as arnplified floor response spectra.

Performed static and dynamic analysis of a BWR Mark I suppression pool torus for hydrodynamic loads.

Responsible for finite element stress analysis of various piping components such as sweepolets, reducers, and anchoring devices.

PUBLICATIONS "Seismic Investigation of Electrical Raceway Components," with L. Serdar, Jr. and D. Williams, ASME paper 84-PVP-43, PVP Conference and Exhibition, San Antonio, Texas (June 1984)

"A Seismic Evaluation Study of Mechanical and Electrical Equipment at an Existing Nuclear Handling Facility," with L. Serdar, Jr., et al., 7th International Conference on Structural Mechanics In Reactor Technology, Chicago, Illinois (August 1983)

FACIuTY RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September23, 2004 Page A-29 "Seismic Evaluation of Electrical Raceway Systems," with S. Anagnostis and W. Djordjevic, ASME paper 83-PVP-18, 4th National Congress on Pressure Vessel and Piping Technology, Portland, Oregon (June 1983)

"A Survey and Assessment of Major Mechanical Equipment Capability During Seismic Events,"

with W. Djordjevic, ASME Pressure Vessel and Piping Conference and Exhibit, Orlando, Florida (June 1982)

"The Spring Method For Embedded Foundations," with E. Kausel, et al., Nuclear Engineering and Design Journal, Volume 48 (August 1978)

"Dynamic Analysis of Embedded Structures," with E. Kausel, et al., 4th international Conference on Structural Mechanics In Reactor Technology, San Francisco, California (August 1977)

"Dynamic Stiffness of Embedded Foundations," with E. Kausel, and J. M. Roesset, ASCE 2nd Annual Engineering Mechanics Division Speciality Conference, North Carolina (May 1977)

"Static Stiffness Coefficients For Circular Foundations Embedded In An Elastic Medium,"

M. S. Thesis, Massachusetts Institute of Technology, Cambridge, Massachusetts (June 1975)

FACLITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-30 ROBERT D. HOOKWAY, P.E.

PROFESSIONAL HISTORY Hookway E ngineering, Consulting Engineer, 1996-present EQE International, Stratham, New Hampshire, Technical Manager, 1990-1996 Teledyne Engineering Services, Waltham, Massachusetts, Manager, 1967-1990 PROFESSIONAL EXPERIENCE Mr. Hookway has over 35 years of professional engineering and project management experience.

Specific background experience includes project management for design, analysis and evaluation of piping system and pressure vessels, supports and structures in power generation stations (fossil and Nuclear), petrochemical facilities, and Navy nuclear installations considering weight, thermal, seismic and dynamic loadings.

As a member of the ASME Section III Working Group on Piping Design, ASME B31.3 Main Piping Committee, and a past member of the ASME Section III Special Working Group on Seismic Design Rules, he is familiar with the requirements of and is involved in the development of these design codes for piping. Past projects include: litigation support for fossil plant piping failure, seismic evaluation of piping, mechanical, electrical and I & C equipment at the Paks Nuclear Plant in Hungary, seismic upgrade of piping at various U.S. Nuclear facilities, anchor bolt study to investigate the dynamic capacities of concrete expansion bolts, seismic margins evaluation of critical piping at the Haddam Neck Nuclear Plant, various piping design and evaluation projects at nuclear and fossil generation stations, petrochemical and cryogenic plants.

Mr. Hookway has completed the Seismic Qualification Utility Group (SQUG), Seismic Capacity Engineer (SCE) training required by the USNRC for A-46 evaluations. He has been involved with A-46 and other similar projects at numerous nuclear facilities in the U.S. and Internationally.

Project management responsibilities include a variety of piping, mechanical, and civil/structural consulting engineering projects. Tasks include project planning, teclmical direction, manpower assignment, cost and schedule control, client intcrfacc, and writing of technical procedures.

Some of Mr. Hookway's specific projects include the following:

Design Review support for General Electric HRSG' projects. The scope includes a detailed review of the design process for all Balance of Plant high energy piping systems and pipe supports provided by the G.E selected Architect Engineer. Services also include general consulting to GE on an as-needed basis regarding ASME code compliance and piping desien.

Design Analysis & Evaluation for numerous LNG facility upgrade projects.

Expert witness and engineering support for litigation of feedwater piping flow accelerated corrosion (erosion/corrosion) failure at a midwest fossil powered electric generation plant.

Engineering support for this project included complete documentation search and reviews, plant operations and maintenance reviews, detailed system flow evaluations, white paper preparation for various associated issues, depositions, deposition reviews and technical FACtITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-31 guidance for the legal staff. Discipline expertise for this project included pipe stress and design, failure evaluation, metallurgical, fluid mechanics, non-destructive examination and water chemistry.

Millstone II Nuclear Power Plant 9/97-present: Design Engineering support for resolution of piping design issues considering weight, thermal expansion, seismic and other dynamic loadings to satisfy US Nuclear Regulatory Commission concerns relative to configuration control of the plant. In addition, provided support for the corrective action department performing Condition Report investigations, Root Cause analyses, Corrective action prescription, Operability Determinations, and Licensee Evaluation Reports (LER) preparation.

0 Millstone III Nuclear Power Plant - 11/96-8/97 50.54f Restart Oversiht Group -

participated in the assessment of numerous systems (SSFl/vertical slice) in addition to the assessment of selected engineering programs such as erosion/corrosion, stress data packages, Seismic Design, Active Valves and Components, P&ID Upgrades, and Component Labeling.

Connecticut Yankee Nuclear Plant - 6/96-11/97 Configuration Management Program (CMP) responsible for all structural tasks within the CMP. Tasks included Graded System Reviews and Topical Reports for selected Engineering Programs (e.g. Seismic Design, Piping Design and Structural Design)

Task manager for the recently completed seismic qualification task for the Category l(L) piping at Tennessee Valley Authority's Watts Bar Nuclear Plant. This task included the walkthrough and bounding case evaluations for all piping interaction issues (proximity, shakespace flexibility and 11/1).

Lead engineer for the seismic upgrade of equipment at the Paks Nuclear Power Plant in Hungary.

The plant is a four unit VVER type 213 Russian design plant. The project included walkdown screening evaluation for all equipment, seismic capacity evaluations and preparation of modification designs.

Project manager for the expansion anchor bolt study to remove conservatism in design criteria for nuclear power plants, including dynamic anchor bolt testing as part of the EPRI study of Improved Guidelines and Criteria for Nuclear Piping and System Evaluation and Design. Scope of work included test plan preparation, supervision of anchor bolt testing, interpretation of test data, final report preparation, and EPRI interface.

Project manager for anchor bolt testing in cracked concrete. The purpose of this project was to develop capacities for epoxy anchor bolts and to assist in the development of epoxy anchor bolts use for the power industry.

Design, analysis, and evaluation of nuclear Class 1, 2, and 3 piping systems. Plants include Nine Mile 1, Vermont Yankee, Millstone l, Hatch 1, Hatch 2, North Anna 1, North Anna II, Davis Besse, DC Cook, Millstone 2, Millstone 3, Pilgrim, Fitzpatrick Hope Creek, and Monticello.

Preparation of design specifications for Class I piping systems.

FACILIY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page A-32 Project management for various failure evaluation, plant modification, and new system design projects.

Lead engineer for the evaluation of various pressure vessels, heat exchangers and valves for navy nuclear, commercial nuclear and process plant facilities.

Direct interface with the NRC and provided technical management services. As project manager for "The Study to Determine the Effects of Hydrodynamic Loads on the Control Rod Drive Piping System for BWR Plant Designs," he managed the technical investigation and provided a communication link between the BWR Owner's Group (which included 11 utilit4ies and I plants) and the NRC.

Participated in design reviews for the Millstone I, Vermont Yankee, Nine Mile Point I, LaSalle, and Comanche Peak (which was under contract to the NRC).

A study to "Deterrnine the Effects of Postulated Events Devices on Normal Operation of Piping systems in Nuclear Power Plants" the NRC. The results of this work contributed to the refinement of code criteria and NRC regulatory guides for seismic pipe whip restraint design. Plants included in the study included Farley Unit 2, Diablo Canyon and Zimmer.

A study to upgrade the design criteria for submarine sea connected piping using high strength thin-walled piping material. This work was performed for the David Taylor Naval Research Center.

EDUCATION NORTHEASTERN UNIVERSITY, Boston, MA: M.S. Mechanical Engineering, 1970 LOWELLTECHNOLOGICAL INSTITUe: B.S. Mechanical Engineering, 1963 AFFILIATIONS Member, ASME Section III Working Group Piping Design Member, ASME B31.3 Chemical Plant and Petroleum Piping Committee Member, Past Vice Chair, Pressure Vessel and Piping Subcommittee of the ASME NED Past Member ASME Section III Special Working Group Seismic Design Rules American Society of Mechanical Engineers REGISTRATION Professional Engineer: Massachusetts Professional Engineer: Virginia FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-33 PUBLICATIONS "Effects of Postulated Events Devices on Normal Operation of Piping Systems in Nuclear Power Plants." 1981. NUREG/CR-2136. U.S. Nuclear Regulatory Study.

With S. J. Eder and T. R. Kipp.

1991.

"Commodity Clearance Requirements."

Engineering Specification N3C-941. Prepared for Tennessee Valley Authority.

With S. J. Eder and T. R. Kipp. 1991. "Seismic Qualification of Category I(L) Fluid System Components and Electrical or Mechanical Equipment."

Design Criteria WB-DC-40-31.13.

Prepared for Tennessee Valley Authority.

With S. J. Eder and T. R. Kipp. 1991. "Seismic Design Specification for Category I (L) Piping, Pipe Supports, and In-line Components."

Engineering Specification N3C-943.

Prepared for Tennessee Valley Authority.

With R.D. Campbell, T.R. Roche, P.D. Baughman, S.J. Eder 1995 "Use of Seismic Experience Data for Seismic Verification of VVER Reactors" International Atomic Energy Agency Coordinated Research Program.

FAC.LlTY RtsK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-34 RICHARD L. W. TIONG, P.E.

PROFESSIONAL HISTORY Independent Consultant, 2000 - present EQE International (S) Pie. Ltd, Singapore, Senior Consultant, 1995 - 2000 EQE Intemational, Irvine, California, Project Engineer to Technical Manager and Associate, 1986 - 1995 Structural Mechanics Associates, San Ramon, California, Staff Engineer, 1982 - 1985 PROFESSIONAL EXPERIENCE Mr. Tiong has over twenty years of experience in the technical execution of projects requiring the design, construction, and integrity evaluation of civil structures. He started his consulting practice in California in 1982 after graduation from the Master's program at UC Berkerley, California, wvhere hle specialized in structural engineering and structural mechanics with emphasis on the seismic aspects. He has been involved in a wide variety of projects such as seismic risk assessment, structural and equipment fragilities quantification, soil-structure interaction analyses of nuclear facilities, earthquake protection of structures and critical equipment against seismic-induced damage, risk-based inspection (RBI) of offshore platforms, among others.

He has performed numerous post-earthquake investigations in California, Japan, Taiwan and Indonesia. Some salient aspects of his previous work experiences are summarized in the following.

Mr. Tiong was exposed to detailed finite element analysis work in the early 80's while working for Structural Mechanics Associates, California. He is also well-versed in performing seismic response analyses including the effects of dynamic soil-structure interaction. He has also participated in research projects aimed at calibrating analytical methods for estimating structural response using actual recorded data obtained during strong motion earthquakes.

These projects involved the Lotung scalb model containment structures located in Taiwan, and the Pacific Bell telephone building at Watsonville.

Mr. Tiong is conversant with Seismic Probabilistic Risk Assessment (PRA) and Seismic Margins methodology as practiced in the US for nuclear facilities, having direct involvement in over 10 such studies in the U.S., Japan and Korea. This type of study focuses on realistic failure modes of structures and components, to determine realistic factors of safety under seismic conditions.

Since joining EQE in 1986, Mr. Tiong participated in numerous seismic projects utilizing both the conventional structural dynamics as well as experience-based methodologies. These included the Seabrook cable tray seismic evaluation project, Browns Ferry Unit 2 cable tray and conduit seismic verification, and Comanche Peak Il/I evaluation for non-safety, non-seismic large and small bore piping. He had contributed significantly in the early development work on the limited analytical review guidelines for SQUG conduit and cable tray raceway supports. Mr. Tiong completed the SQUG-sponsored walkdown screening and seismic evaluation training course as Seismic Capability Engineer in January 1993, and was actively involved in numerous seismic verification walkdowns of nuclear power plant equipment to support USI A-46 resolution for many U.S. plants.

FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page A-35 In late 1995, Mr. Tiong transferred to EQE's Singapore office where his interests expanded to areas such as infrastructure design, structural integrity/damage assessment and rehabilitation activities.

The type of structures included commercial buildings, manufacturing facilities, bridges, marine terminals and offshore structures. In December 1998, he was engaged by insurance interests to perform earthquake damage assessment at a large timber processing facility in Indonesia.

He formulated and directed the field investigation program and retrofit design for a building owned by Unocal in Indonesia. The building suffered from under-strength concrete and required retrofit strengthening to meet ACI code. He has also performed integrity assessment of a jetty, including load test to address short-term operability concerns. He has also performed seismic evaluation walkdowns of mechanical and electrical equipment on an-offshore platform located in Baku, Azerbaijan.

Practicing as an independent consultant since 2000, Mr. Tiong has been actively involved in the seismic strengthening of semiconductor manufacturing equipment and distribution systems in several wafer fabrication plants, and seismic consultation and design review for new fab construction in Hsin-Chu and Tainan Science-Based Parks in Taiwan. He is also involved in the seismic risk assessment of several oil refineries for Mitsubishi in Japan, RBI projects for BP/Amoco in Indonesia and Thailand. Currently, Mr. Tiong is actively involved in the Browns Ferry Unit I restart project EDUCATION UNIVERSITY OF CALIFORNIA, Berkeley: M.S. Structural Engineering and Structural Mechanics, 1981 UNIVERSITY OF LONDON, England: B.Sc (Engineering) 1st Class Honors, Civil Engineering, 1978 REGISTRATION California:

Civil Engineer since 1984 PUBLI CATI ONS A selection of technical reports and journal articles for which Mr. Tiong is a principal contributor are lised below:

With A.P. Asfura, et. al., "Seismic Analysis of Multiple Supported Bridges," Conference Proceeding, Bridge into the 21st Century, Hong Kong, 2-5 October, 1995.

With R.D. Campbell and J.O. Dizon, "Response Predictions for Piping Systems Which Have Experienced Strong Motion Earthquakes," ASME Pressure Vessel and Piping Conference, Nashville, Tennessee, June 17-21, 1990.

With M.K. Ravindra, "Comparison of Methods for Seismic Risk Quantification." Proceedings of 10th SMiRT Conference, Anaheim, California, August 14-18, 1989.

FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page A-36 With O.R. Maslenikov, J.J. Johnson, and M.J. Mraz, "Seismic Analysis of the MFI`F Facility." In Proceeding of 81h SMiRT Conference, Brussels, Belgium, August 19-23, 1985.

With 0. R. Maslenikov, J.J. Johnson, M. J. Mraz, S. Bumpus, and M.A. Gerhard. "SMACS - A System of Computer Programs for Probabilistic Seismic Analysis of Structures and Subsystems, Volume I User's Manual, Volume 11 Example Problem." SMA 12211.31.01/12211.31.02. Prepared for Lawrence Liver7nore National Laboratory, 1984 With J.J. Johnson and B.J. Benda. "Stress Analysis of the Neutral Beam Pivot Point Bellows for Tokamak Fusion Test Reactor."

In Proceeding of the 10th Symposium on Fusion Engineering, Philadelphia, PA, 1983.

FiACILIY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-1 APPENDIX B COMPOSITE SSEL FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-2 APPENDIX B COMPOSITE SSEL sSEL 1

NUMBER C S

EQUiPENT 1.

DESCRIPTIO:

I l

O IUE 10001 00 t-HCU-85,1-185 CR/HYDRAULIC CONTROL UNIT U1 RB 565 R2& R6/P-S Al 1.2 10002 07 1-FCV-85-82A CRD/WEST SDV VENT VALVE Ul RB 565 R2/S Al 1

10003 07 1-FCV*85-82 CRD/WEST SDV VENT VALVE U1 RB 565 R2/S Al 2

10004 07 1-FCV-85-37C CRD/WEST SDV DRAIN VALVE Ul RB 565 R2R P

Al 1

10005 07 1-FCV-85-37D CRD/WEST SDV DRAIN VALVE U1 RB 565 R2/P Al 2

10006 07 1-FCV-85-83A CRD/EAST SDV VENT VALVE U1 RB 565 P6/S Al 1

10007 07 1-FCV.85.83 CRD/EAST SDV VENT VALVE U1 RB 565 R6/S Al 2

10008 07 1-FCV*85-37E CR0/EAST SOV DRAIN VALVE U1 RB 565 R6/P Al 1

10009 07 1-FCV-85-37F CRD/EAST SDV DRAIN VALVE U1 RB 565 R6/P Al 2

10010 21 1-TNK-85-901 CRD/WEST SCRAM INSTRUMENT VOLUME U1 RB 565 R2/P Al 1.2 10011 21 1-TNK-85-902 CRD/EAST SCRAM INSTRUMENT VOLUME U1 RB 565 R6/P Al 1.2 10012 08B 1-FSV-85-37A CRD/SCRAM DUMP VALVE Ul RB 565 R5/N Al I

10013 08B

.-FSV-85-37B CRD/SCRAM DUMP VALVE Ul RB 565 R5/N Al 1

10014 08B 1-FSV-85-35A CRD/BACKUP SCRAM VALVE U1 RB 565 R5/N Al 2

10015 086 1-FSV-85-35B CRO/BACKUPSCRAM VALVE U1 RB 565 PR/N Al 2

10016 20 1-HS-99-SA/S1A RPS/REACTOR MANUAL SCRAM CHANNEL Al Ut CB 617 Ul MCR Al 1

10017 20 1-HS-99-5AIS1B RPSREACTOR MANUALSCRAM CHANNELB1 Ul CB 617 U1 MCR Al 1

10018 20 1-HS-99-SA-S1 RPS/REACTOR MODE SWITCH U1 CB 617 U1 MCR Al 2

10019 8B 1-FSV-85-70A CRD/BACKUP PILOT SCRAM VALVE A' U1 RB 565 R5/N Al 10020 BB 1-FSV-85.70B CRD/ BACKUP PILOT SCRAM VALVE 'B' Ul RB 565 R5/N Al 10021 R

1-CKV-85-330 CR0/ISOLATION CHECK VALVE U_ RB 565 Al 10022 R

1-CKV-85-576 CPD/ISOLATION CHECK VALVE UU RB 565 Al 10023 8B 1-FSV-85-39A CR0/ISOLATION VALVE U1 RB 565 CR0 RACKS Al 10024 8B 1-FSV-85.39B CR0/ISOLATION VALVE U1 RB 565 CRD RACKS Al 10025 18 1.PI-85-88 PRESSURE INDICATOR U1 RB 565 R6/S Al 10026 16 1-PI-85-89 PRESSURE INDICATOR U1 RB 565 R2/P Al 10027 18 1-PI-85-90 PRESSURE INDICATOR U1 RB 565 R2/P Al 10028 R

1-CKV-85-597 CRD/ISOLATION CHECK VALVE U1 RB 565 Al APPENDIX B FACLITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-3 S S EL NUMBER A

EQUiENT l:I

[

DESCRIPTION BUILDING ELEV ROOM ISSUE 10029 R

1-CKV-85-616 CROtlSOLATION CHECK VALVE U1 RB 565 Al 11001 08A 1-FCV-74-1 RHRPPUMP IA SUCTION VALVE FROM SUPRESSION POOL Ul RB 519 SW CORNER Al 1

11002 08A 1-FCV-74-2 RHRtPUMP IASUCTION VALVE FROM SHUTDOWN COOLING U1 RB 541 SW CORNER Al 1

11003

• 08A 2-FCV-74-96

• RHRtU2TO U1 RHR X-TIE ISOLATION VALVE U2 RB 519 SW CORNER Al 1

11004 06 1-PMP-74-5 RHRtPUMP IA U1 RB 519 SW CORNER Al 1

11005 R

1-CKV-74-560A RHRPPUMP IA MINIMUM FLOW CHECK VALVE U1 RB 519 Al 1

11006 08A 1-FCV-74-7 RHRIPUMP 1A& 1C MINIMUM FLOW VALVE U1 RB 541 SW CORNER Al 1

11007 R

1-CKV-171-547 RCIC/RCIC MINIMUM FLOW CHECK VALVE U1 RB 519 Al 1

11008 R

1-CKV-74-559A RHR/PUMP IA DISCHARGE CHECK VALVE Ut RB 519 Al 1

11009 21 1-HEX-74-900A RHRIHEAT EXCHANGER 1A U1 RB 565 SW HX Al I

11010

• 08A 2-FCV-74-100

• RHRIU2 TO Ut RHR DISCHARGE X-TIE ISOLATION VALVE (A,C)

U2 RB 565 R8fT Al 1

11011 08A 1-FCV-74-12 RHRIPUMP IC SUCTION VALVE FROM SUPRESSION POOL U1 RB 519 SW CORNER Al IA 11012 08A 1-FCV-74-13 RHRIPUMP IC SUCTION VALVE FROM SHUTDOWN COOLING Ut RB 541 SW CORNER Al IA 11013-08A 2-FCV-74-97 RHRtU2TO U1 RHR X-TIE ISOLATION VALVE U2 RB 519 SW CORNER Al IA 11014 06 1-PMP-74-16 RHRPPUMP IC U1 RB 519 SW CORNER Al IA 11015 R

1-CKV-74-560C RHRtPUMP iC MINIMUM FLOW CHECK VALVE U1 RB 519 Al IA 11016 R

1-CKV-74-559C RHRtPUMP IC DISCHARGE CHECK VALVE Ut RB 519 Al IA 11017 21 1-HEX-74-900C RHRtHEAT EXCHANGER IC U1 RB 565 SW HX Al 1A 11018 20 1-FI-74-50 RHRILOOP I FLOW INDICATOR U1 CB 617 U1 MCR Al 1

11019 20 1-FI-74-56 RHRILOOP I FLOW INDICATOR U1 CB 617 Ul MCR Al 1

11020 08A 1-FCV-74 57 RHRILOOP I TORUS CONTAINMENT COOLING/SPRAY VALVE Ul RB 551 TORUS Al 1

11021 08A 1-FCV-74-59 RHR/LOOP I SUPRESSION POOL COOLING VALVE Ut RB 551 TORUS Al 1

11022 08A 1-FCV-74-58 RHRILOOP I SUPRESSION POOL SPRAY VALVE Ut RB 551 TORUS I

1 11023 08A 1-FCV-74-52 RHRILOOP I OUTBOARD INJECTION VALVE Ut RB 565 R4tT Al 1

11024 08A 1-FCV-74-53 RHRPLOOP I INBOARD INJECTION VALVE Ut RB 565 R4/T Al 1

11025 R

1-FCV-74-54 RHR/LOOPI rESTABLE CHECK VALVE Ut DW Al 1

11026 08A 1-FCV-78-61 FPC/SPENT FUEL POOL COOLING X-TIE TO RHR Ut RB 621 R5/S Al 1

11027 08A t-FCV-74-60 RHR/LOOP I OUTBOARD DRYWELL SPRAY VALVE Ut RB 593 R3/S Al 1

11028 08A t-FCV-74-61 RHR/LOOP I INBOARD DRYWELL SPRAY VALVE Ut RB 593 R3/S I

1 11029 08A t-FCV-74-24 RHRIPUMP 1B SUCTION VALVE FROM SUPRESSION POOL Ut RB 519 SE CORNER Al 2

11030 08A 1-FCV-74-25 RHR/PUMP 1B SUCTION VALVE FROM SHUTDOWN COOLING Ut RB 541 SE CORNER Al 2

11031 06 1-PMP-74-28 RHR/PUMP 1B U1RB 519 SE CORNER Al 2

APPENDIX B FACLITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-4

.SSEL BD ELEV.

lO-NUMBER CLASS EQUIPMENT.DESCRIPTION MU.L.I.G.

S TIN 11032 R

1-CKV-74-560B RHR/PUMP lB MINIMUM FLOW CHECK VALVE Ul RB 519 Al 2

11033 08A 1-FCV-74*30 RHR/PUMP 1B & ID MINIMUM FLOW VALVE U1 RB 541 SE CORNER Al 2

11034 R

1-CKV-73-559 HPCVHPCI PUMP MINIMUM FLOW CHECK VALVE U1 RB Al 2

11035 R

1-CKV-74-559B RHR/PUMP 1B DISCHARGE CHECK VALVE U1 RB 519 Al 2

11036 21 1-HEX-74-900B RHR/HEAT EXCHANGER 1B U1 RB 565 SEHX Al 2

11037 08A 1-FCV-74-35 RHR/PUMP 1D SUCTION VALVE FROM SUPRESSION POOL U1 RB 519 SE CORNER Al 2A 11038 08A 1-FCV-74-36 RHRPPUMP 1D SUCTION VALVE FROM SHUTDOWN COOLING U1 RB 541 SE CORNER Al 2A 11039 06 l-PMP-74-39 RHR/PUMP ID Ul RB 519 SE CORNER Al 2A 11040 R

1-CKV-74-560D RHRPPUMP 1D MINIMUM FLOW CHECK VALVE U1 RB 519 Al 2A 11041 R

1-CKV-74-559D RHR/PUMP 10 DISCHARGE CHECK VALVE U1 RB 519 Al 2A 11042 21 1-HEX-74-900D RHR/HEAT EXCHANGER ID UI RB 565 SE HX Al 2A 11043 20 1-FI-74-64 RHRILOOP 11 FLOW INDICATOR U1 CB 617 UI MCR Al 2

11044 20 1-FI-74-70 RHR/LOOP II FLOW INDICATOR U1 CB 617 U1 MCR Al 2

11045 08A 1-FCV-74-71 RHR/LOOP II TORUS CONTAINMENT COOLING/SPRAY VALVE U1 RB 551 TORUS Al 2

11046 08A 1-FCV-74-73 RHR/LOOP 11 SUPRESSION POOL COOLING VALVE U1 RB 551 TORUS Al 2

11047 08A 1-FCV-74-72 RHR/LOOP It SUPRESSION POOL SPRAY VALVE Ul RB 551 TORUS I

2 11048 08A 1-FCV-74-66 RHR/LOOP I! OUTBOARD INJECTION VALVE Ul RB 565 R5tT Al 2

11049 08A 1-FCV-74-67 RHR/LOOP II INBOARD INJECTION VALVE U1 RB 565 R5/T Al 2

11050 R

1-FCV-74-68 RHR/LOOP 11 TESTABLE CHECK VALVE U1 DW.

Al 2

11051 08A 1-FCV-74-74 RHR/LOOP 11 OUTBOARD DRYWELL SPRAY VALVE U1 RB 565 R5/S Al 2

11052 08A 1-FCV-74-75 RHIPJLOOP II INBOARD DRYWELL SPRAY VALVE Ul RB 565 R6/S I

2 11053 08A 1-FCV-74-101 RHR/U2TO Ul RHR DISCHARGE X-TIE ISOLATIONVALVE(B,D)

U1 RB 565 R6/T Al 1

12001 07 1-PCV-1-4 MS/MAIN STEAM SAFETY RELIEF VALVE Ul DW 584 DW Al 1

12002 R

1-CKV-10-521 RVVD/MSRV 1-4 DISCHARGE LINE VACUUM BKR U1 OW Al 1

12003 07 1-PCV-1-5 MS/MAIN STEAM SAFETY RELIEF VALVE Ul DW 584 DW Al 1

12004 R

I-CKV-10-507 RVD/MSRV 1-5 DISCHARGE LINE VACUUM BKR Ul OW Al 12005 R

1-CKV-10-522 RVVD/MSRV 1-5 DISCHARGE LINE VACUUM BKR U1 DW Al 1

12006 07 1-PCV-1-18 MS/MAIN STEAM SAFETY RELIEF VALVE Ul DW 584 DW Al 1

12007 R l-CKV-10-508 RWDIMSRV 1.18 DISCHARGE LINE VACUUM BKR U1 DW.

Al 1

12008 R

1-CKV-10-523 RWD/MSRV 1-18 DISCHARGE LINE VACUUM BKR U1 DW Al I

12009 07 1-PCV-1-19 MS/MAIN STEAM SAFETY RELIEF VALVE U1 DW 584 DW Al I

12010 R

1-CKV-tO-509 RVVD/MSRV 1-19 DISCHARGE LINE VACUUM BKR JUl DW Al 1

APPENDIX B FACtlTY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-5 SSEL: 1 1

NUMBER JCLASS[ --

EBUILDING ISSUE 12011 R

1-CKV-10-524 RVVD/MSRV 1-19 DISCHARGE LINE VACUUM BKR U1 DW Al 1

12012 07 1-PCV-1-22 MS/MAIN STEAM SAFETY RELIEF VALVE U1 DW 584 DW Al 1

12013 R

1-CKV-10-510 RWD/MSRV 1-22 DISCHARGE LINE VACUUM BKR U1 DW Al 1

12014 R

1-CKV-t0-525 RWD/MSRV 1-22 DISCHARGE LINE VACUUM BKR Ul DW Al 1

12015 07 1-PCV-1-23 MS/MAIN STEAM SAFETY RELIEF VALVE U1 DW 584 DW Al 1

12016 R

1-CKV-10-511 RWD/MSRV 1-23 DISCHARGE LINE VACUUM BKR U1 DW Al 1

12017 R

1-CKV-10-526 RWD/MSRV 1-23 DISCHARGE LINE VACUUM BKR U1 DW Al 1

12018 07 1-PCV-1-179 MS/MAIN STEAM SAFETY RELIEF VALVE UL DW 584 DW Al 1

12019 R

l-CKV-10-519 RWD/MSRV 1-179 DISCHARGE LINE VACUUM BKR U1 DW Al 1

12020 R

1-CKV-10-532 RWD/MSRV 1-179 DISCHARGE LINE VACUUM BKR U1 DW Al 1

12021 07 1-PCV-1-30 MS/MAIN STEAM SAFETY RELIEF VALVE U1 DW 584 DW Al 2

12022 R

1-CKV-10-512 RVVD/MSRV 1-30 DISCHARGE LINE VACUUM BKR Ut DW Al 2

12023 R

1-CKV-10-527 RVVD/MSRV 1-30 DISCHARGE LINE VACUUM BKR UL DW Al 2

12024 07 1-PCV-1-31 MS/MAIN STEAM SAFETY RELIEF VALVE U1 DW 584 DW Al 2

12025 R

1-CKV-10-513 RVVD/MSRV 1-31 DISCHARGE LINE VACUUM BKR U1 DW Al 2

12026 R

1-CKV-10-528 RWD/MSRV 1-31 DISCHARGE LINE VACUUM BKR U1 DW Al 2

12027 07 1-PCV-1-34 MS/MAIN STEAM SAFETY RELIEF VALVE Ut DW 584 DW Al 2

12028 R

t-CKV-10-514 RVVD/MSRV 1-34 DISCHARGE LINE VACUUM BKR UL1 DW.

Al 2

12029 R

1-CKV-10-529 RVVD/MSRV 1-34 DISCHARGE LINE VACUUM BKR U1 DW Al 2

12030 07 1-PCV-1-41 MS/MAIN STEAM SAFETY RELIEF VALVE Ul DW 584 DW Al 2

12031 R

1-CKV-10-515 RVVD/MSRV 1-41 DISCHARGE LINE VACUUM BKR U1 DW Al 2

12032 R

1-CKV-10-530 RWD/MSRV 1-41 DISCHARGE LINE VACUUM BKR U1 DW Al 2

12033 07 1-PCV-1-42 MS/MAIN STEAM SAFETY RELIEF VALVE UL1 DW 584 DW Al 2

12034 R

1-CKV-10-516 RVVD/MSRV 1-42 DISCHARGE LINE VACUUM BKR U1 DW Al 2

12035 R

1-CKV-10-531 RWD/MSRV 1-42 DISCHARGE LINE VACUUM BKR U1 DW Al 2

12036 07 1-PCV-1-180 MS/MAIN STEAM SAFETY REUEF VALVE Ul DW 584 DW Al 2

12037 R

1-CKV-10-520 RWD/MSRV 1-180 DISCHARGE LINE VACUUM BKR Ut DW Al 2

12038 R

1-CKV-10-506 RWD/MSRV 1-4 DISCHARGE LINE VACUUM BKR U1 DW Al 1

12039 R

1-CKV-10.533 RWD/MSRV 1-180 DISCHARGE LINE VACUUM BKR U1 DW Al 2

13001 07 t-FCV-1-14 MSIV A' INBOARD ISOLATION VALVE U1 DW 563 DW Al 1

13002 07 1-FCV-1-15 MSIV A' OUTBOARD ISOLATION VALVE U1 RB 565 MSIV VAULT Al 2

13003 07 1-FCV-1-26 MSIV 'B INBOARD ISOLATION VALVE Ut DW 563 DW Al 1

APPENDIX B FACtLf RISK CONSULTANTS, INC.

TVAJBFN-01 -R-004 Revision 0 September 23, 2004 Page B-6 SSEL' l '

l NUMBERCLAI EQUIPMENT ID.

DESCRIPTIO SUE RAIN 13004 07 1-FCV-1-27 MSIV 'B OUTBOARD ISOLATION VALVE U1 RB 565 MSIV VAULT Al 2

13005 07 1-FCV-1-37 MSIV 'C INBOARD ISOLATION VALVE U1 DW 563 DW Al 1

13006 07 1-FCV-1-38 MSIV C OUTBOARD ISOLATION VALVE U1 RB 565 MSIV VAULT Al 2

13007 07 1-FCV-1-51 MSIV D INBOARD ISOLATION VALVE Ul DW 563 DW Al 1

13008 07 1-FCV-1-52 MSIV 'D OUTBOARD ISOLATION VALVE U1 RB 565 MSIV VAULT Al 2

13009 08A 1-FCV-1-55 MAIN STEAM LINE DRAIN ISOLATION VALVE Ul DW 563 DW Al 1

13010 R

1-CKV-3-558 FEEDWATER A INBOARD ISOLATION VALVE Ul DW Al 1

13011 R

1-CKV-3-554 FEEDWATER A OUTBOARD ISOLATION VALVE U1 RB Al 2

13012 R

1-CKV-3-572 FEEDWATER B INBOARD ISOLATION VALVE Ul DW Al I

13013 R

1-CKV-3-568 FEEDWATER B OUTBOARD ISOLATION VALVE U1 RB Al 2

13015 07 1-FCV-64-17 CONTAINMENT VENTILATION ISOLATION VALVE U1 RB 565 R3/U I

1,2 13016 07 1-FCV-64-30 CONTAINMENT VENTILATION ISOLATION VALVE U1 RB 621 R3/Q I

1,2 13017 07 1-FCV-64-33 CONTAINMENT VENTILATION ISOLATION VALVE U1 RB 565 R21P I

1,2 13018 07 1-FCV-64-139 CONTAINMENT DW DP ISOLATION VALVE U1 RB 565 R2/P I

1,2 13019 07 1-FCV-64-140 CONTAINMENT DW DP ISOLATION VALVE U1 RB 565 R2/P I

1,2 13020 07 1-FCV-64-28A SUPPRESSION CHAMBERPDRYWELL VACUUM BREAKERS Ul DW

<550 IN TORUS I

1,2 13021 07 1-FCV-64-28B SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ul DW.

<550 INTORUS I

1,2 13022 07 1-FCV-64-28C SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW

<550 IN TORUS I

1,2 13023 07 1-FCV-64-28D SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW

<550 IN TORUS I

1,2 13024 07 1-FCV-64-28E SUPPRESSION CHAMBERtDRYWELL VACUUM BREAKERS Ul DW

<550 IN TORUS I

1,2 13025 07 1-FCV-64-28F SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW

<550 INTORUS I

1,2 13026 07 1-FCV-64-28G SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ul DW

<550 IN TORUS I

1,2 13027 07 1-FCV-64-28H SUPPRESSION CHAMBERIDRYWELL VACUUM BREAKERS Ul DW

<550 IN TORUS I

1,2 13028 07 1-FCV-64-28J SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS UI DW

<550 IN TORUS I

1,2 13029 07 1-FCV-64-28K SUPPRESSION CHAMBERJDRYWELL VACUUM BREAKERS Ul DW

<550 IN TORUS I

1,2 13030 07 1-FCV-64-28L SUPPRESSION CHAMBERIDRYWELL VACUUM BREAKERS U1 DW

<550 IN TORUS I

1,2 13031 07 1-FCV-64-28M SUPPRESSION CHAMBERtDRYWELL VACUUM BREAKERS U1 DW

<550 INTORUS I

1,2 13032 08A 1-FCV-69-1 RWCU INBOARD ISOLATION VALVE Ul DW 584 DW Al 1

13033 08A 1-FCV-69-2 RWCU OUTrOARD ISOLATION VALVE U1 RB 593 R5tS Al 2

13034 R

1-CKV-69-579 RWCU SYSTEM RETURN CHECK VALVE Ul RB Al 2

13035 08A 1-FCV-70-47 RBCCW DRYWELL RETURN VALVE U1 RB 551 TORUS I

1,2 13036 R

1-CKV-70-506 RBCCW DR'YWELL SUPPLY CHECK VALVE Ul RB I

1,2 APPENDIX B FACILITY RIsK CONSULTANTS. INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-7 SSEL NUMBER EOUIPMENTDB ISSUEl TRAN 13037 08A t-FCV-71-2 RCIC INBOARD ISOLATION VALVE U1 DW 584 DW Al 1

13038 08A 1-FCV-71-3 RCIC OUTBOARD ISOLATION VALVE U1 RB 565 MSIV VAULT Al 2

13039 08A 1-FCV-71-18 RCIC OUTBOARD SUCTION VALVE U1 RB 519 NW CORNER I

1,2 13040 08A 1-FCV-73-2 HPCI STEAM SUPPLY ISOLATION VALVE U1 DW 563 DW Al 1

13041 08A 1-FCV-73-3 HPCI STEAM SUPPLY ISOLATION VALVE U1 RB 551 TORUS Al 2

13042

_8A 1-FCV-73-81 HPCI STEAM SUPPLY ISOLATION BYPASS VALVE U1 RB 551 TORUS Al 2

13043 08A 1-FCV-73-27 HPCI OUTBOARD SUCTION VALVE U1 RB 519 HPCI ROOM I

1,2 13044 07 1-FCV-75-57 PSC PUMP SUCTION ISOLATION VALVE U1 RB 519 NW CORNER Al 1

13045 07 1-FCV-75-58 PSC PUMP SUCTION ISOLATION VALVE U1 RB 519 NW CORNER Al 2

13046 07 1-FCV-76-24 PRIMARY CONTAINMENT ISOLATION VALVE U1 RB 565 R31U 1

1,2 13047 07 1-FCV-77-2B DRYWELL FLOOR DRAIN SUMP DISCHARGE U1 RB 551 TORUS I

1,2 13048 07 1-FCV-77-15B DRYWELL EQUIPMENT DRAIN SUMP DISCHARGE Ul RB 551 TORUS I

1,2 13049 07 1-FCV-84-19 CAD ISOLATION VALVE Ul RB 621 R130 I

1,2 13050 07 1-FCV-84-20 CAD ISOLATION VALVE U1 RB 621 R3/O I

1,2 13051 20 1-LI-3-58AA RPV LEVEL INSTRUMENTATION U1 RB 617 UlMOR Al 1

13052 20 1-LI-3-588B RPV LEVEL INSTRUMENTATION U1 RB 617 U1 MCR Al 2

13053 20 1-PL-3-74A RPV PRESSURE INSTRUMENT U1 CB 617 U1 MCR Al 1

13054 20 1-PI-3-74B RPV PRESSURE INSTRUMENT U1 CB 617 U1 MCR Al 2

13055 20 1-XR-64-159 TORUS LEVEL AND DRYWELL PRESSURE INSTRUMENT U1 CB 617 Ul MCR Al 1

13056 20 1-LI-64-159A TORUS LEVEL INSTRUMENT U1 CB 617 U1 MCR Al 2

13057 20 l-TI-64-161 TORUS TEMPERATURE INSTRUMENT U1 CB 617 Ul MCR Al 1

13058 20 1-TI-64-162 TORUS TEMPERATURE INSTRUMENT U1 CB 617 U1 MCR Al 2

13059 20 1-PI-64-67 DRYWELL PRESSURE INSTRUMENT U1 CB 617 U1 MCR I

1 13060 20 1-PI-64-160A DRYWELL PRESSURE INSTRUMENT Ul CB 617 U1 MCR I

2 13061 20 1-TI-64-52A DRYWELLTEMPERATURE INSTRUMENT U1 CB 617 U1 MCR I

I 13062 20 1-XR-64-50 DRYWELLT.!MPERATURE AND PRESSURE INSTRUMENT U1 CB 617 Ul MCR I

2 13063 07 1-FCV-76-17 CONTAINMENT INERTING N2 MAKEUP U1 RB 565 RS/T I

1,2 13064 07 1-FCV-64-222 HARDENED WETWELL VENT U1 RB 565 R3/T I

1,2 13067 R

1-CKV-63-525 PRIMARY CONTAINMENT ISOLATION CHECK VALVE U1 RB 565 Al 13068 R

1-CKV-63-526 PRIMARY CONTAINMENT ISOLATION CHECK VALVE U1 RB 565 Al 13069 08A 1-FCV-71-40 PRIMARY CONTAINMENT ISOLATION VALVE Ut RB 565 R4/P Al 13070 R

1-CKV-71-580 PRIMARY CONTAINMENT ISOLATION CHECK VALVE UI RB 565 Al APPENDIX B APDBFACILfTnRISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-8

."SSEL':

.E': ' D- :

BU_

_LI NUMBER C DEQUIPMENT l.D.

DESCRIPTION BUILDING ELEVI ROOM IS 13071 R

1-CKV-71-592 PRIMARY CONTAINMENT ISOLATION CHECK VALVE Ul RB 565 Al 13072 R 1-CKV-73-603 PRIMARY CONTAINMENT ISOLATION CHECK VALVE U1 RB 565 Al 13073 R

1-CKV-73-609 PRIMARY CONTAINMENT ISOLATION CHECK VALVE Ul RB 565 Al 13074 08A 1-FCV-71-17 RCIC INBOARD SUCTION VALVE Ul RB 519 NW CORNER I

1,2 13075 08A 1-FCV-1-56 MAIN STEAM LINE DRAIN ISOLATION VALVE U1 RB 565 MSIV VAULT?

Al 13076 08A 1-FCV-73-26 HPCI INBOARD SUCTION VALVE U1 RB 519 SW CORNER I

1,2 13077 R

1-CKV-73-517 HPCI CHECK VALVE Ut RB 519 A

____Al 13079 07 1-FCV-32-62 DRYWELL CONTROL AIR SUCTION VALVE U1 RB 565 CLEAN RM I

1,2 13080 07 1-FCV-77-2A DRYWELL FLOOR DRAIN SUMP DISCHARGE U1 RB 551 TORUS I

1,2 13081 07 1-FCV-77-ISA DRYWELL EQUIPMENT DRAIN SUMP DISCHARGE U1 RB 551 TORUS I

1,2 13082 07 1-FCV-64-18 COOLING/PURGE AIR TO DRYWELL Ul RB 565 RS/T I

1,2 13083 07 1-FCV-64-19 COOLING/PURGE AIR TO SUPPRESSION CHAMBER Ut RB 565 R3/T I

1.2 13084 07 1-FCV-76-18 CONTAINMENT INERTING DRYWELL N2 MAKEUP VALVE Ut RB 565 R5/T -

I 1,2 13085 07 1-FCV-76-19 CONTAINMENT INERTING - PSC N2 MAKEUP VALVE Ut RB 565 R3tT I

1,2 13101 18 1-LT-64-159A TORUS LEVEL TRANSMITTER Ut RB 519 TORUS 13102 18 1-LT-64-159B TORUS LEVELTRANSMITTER U1 RB 519 TORUS 13111 19 1-TE-64-161A TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13112 19 1-TE-64-161B TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13113 19 1-TE-64-161C TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13114 19 1-TE-64-161D TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13115 19 1-TE-64-161E TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13116 19 1-TE-64-161F TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13117 19 1-TE-64-161G TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13118 19 1-TE-64-161H TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13211 19 1-TE-64-162A TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13212 19 1-TE-64-162B TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13213 19 1-TE-64-162C TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13214 19 1-TE-64-162D TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13215 19 1-TE-64-162E TORUS TEMPERATURE ELEMENT UI RB 519 TORUS 13216 19 1-TE-64-162F TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13217 19 1-TE-64-162G TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13218 19 1-TE-64-162H TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS APPENDIX B FACILiTY RISK CONSULTANTS,, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-9 NUMBER.

LSI.:.:EQUIPMENT ID.:

DECIPINBUILlJING Ej:LEV, RO ISSUE: '.TSAIN 14001 10 1-CLR-67-917 EECW/RHR PUMP IA ROOM COOLER U1 RB 519 SW CORNER Al 1

14002 10 1-CLR-67-919 EECW/CS PUMP IA ROOM COOLER UI RB 519 NW CORNER Al 1

14003 10 1-CLR-67-921 EECW/RHR PUMP IC ROOM COOLER Ul RB 519 SW CORNER Al 1

14004 21 1-HEX-67.915 EECW/RHRSEALHX IA U1RB 519 SW CORNER Al 1

14005 R

1-CKV-67-638 EECW NORTH HEADER SUPPLY CHECK VALVE TO A & C RHR Ul RB 565 Al 1

14006 R

1-CKV-67-639 EECW NORTH HEADER SUPPLY CHECK VALVE TO A & C RHR U1 RB 565 Al 1

14007 R

1-CKV-67-648 EECW NORTHHEADERSUPPLYCHECKVALVETOACS Ut RB 565 Al I

14008 R

1-CKV-67_649 EECW NORTH HEADER SUPPLY CHECK VALVE TO A CS Ut RB 565 Al 1

14009 R

1-CKV-67-659 EECW NORTH HEADER SUPPLY CHECK VALVE TO B&D RHR U1 RB 565 Al 1

14010 R

1-CKV-67-660 EECW NORTH HEADER SUPPLY CHECK VALVE TO B&D RHR U1 RB 565 Al 1

14011 R

1-CKV-67-656 EECW NORTH HEADER SUPPLY CHECK VALVE TO B CS Ul RB 565 Al 1

14012 R

1-CKV-67-657 EECW NORTH HEADER SUPPLY CHECK VALVE TO B CS Ul RB 565 Al 1

14013 10 1-CLR*67-918 EECWIRHR PUMP IB ROOM COOLER Ul RB 519 SE CORNER Al 2

14014 10 1-CLR-67-920 EECW/CS PUMP IB ROOM COOLER Ul RB 519 NECORNER Al 2

14015 10 1CLR-67-922 EECW/RHRFPUMP 1DROOM COOLER UIRB 519 SECORNER Al 2

14016 21 1-HEX-67-923 EECW/RHR SEAL HX 1B UlRB 519 SECORNER Al 2

14017 R

l-CKV-67-558 EECW SOUTH HEADER SUPPLY CHECK VALVE TO A & C RHR U1 RB 593 Al 2

14018 R

1-CKV-67-559 EECW SOUTH HEADER SUPPLY CHECK VALVE TO A & C RHR UiRB 593 Al 2

14019 R

1-CKV-67-541 EECW SOUTH HEADER SUPPLY CHECK VALVE TO A CS UIRB 593 Al 2

14020 R

1.CKV*67*542 EECW SOUTH HEADER SUPPLY CHECK VALVE TO A CS U1 RB 593 Al 2

14021 R

1-CKV-67-600 EECW SOUTH HEADER SUPPLY CHECK VALVE TO B & D RHR UIRB 593 Al 2

14022 R

1-CKV-67-601 EECW SOUTH HEADER SUPPLY CHECK VALVE TO B & D RHR UIRB 593 Al 2

14023 R

1-CKV-67-584 EECW SOUTH HEADER SUPPLY CHECK VALVE TO B CS URB 593 Al 2

14024 R

1-CKV-67-585 EECW SOUTH HEADER SUPPLY CHECK VALVETOBCS U1RB 593 Al 2

14025 21 1-HEX-67-916 EECW/RHR SEAL HX IC UIRB 519 SW CORNER Al I

14026 21 1-HEX-67-924 EECW/RHR SEAL HX 1D U1RB 519 SE CORNER Al 2

14027 R

1-CKV-67-598 EECW SEAL DISCHARGE CHECK VALVE UI RB 593 Al 2

14028 R

1-CKV-67-554 EECW CHECK VALVE U1RB 593 Al 2

14031*

06 0-PMP-23-85 RHRSW PUMPA3 INTAKE 565 A

Al 1

14032-R 0-CKV-23-588 RHRSW PMP A3 DISCHARGE CHECK VALVE INTAKE 565 Al 1

14033-00 0-STN-67.925 A EECW PUMP DISCHARGE STRAINER INTAKE 565 A

Al I

14034

• 08A 0-FCV-67-1 A EECW PUNP DISCHARGE STRAINER DRAIN VALVE INTAKE 565 A

Al 1

APPENDIX B A DFACTY RISK CoNSuTAmS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-1 0 SSEL f:'

""j:"'

NUMBER CLASS' EQUI ENT-:'I.D.

,D-BUILDIN LE R

I

'RAIN

=_.

14035

• R O-CKV-67-622 EECW SYSTEM NORTH HEADER CHECK VALVE U1/2 DG 565 Al 1

14040

• R 0-CKV-67-671 EECW SYSTEM NORTH HEADER CHECK VALVE RB 565 Al 1

14041 '

06 0-PMP-23-91 RHRSW PUMP C3 INTAKE 565 C

Al 14042 '

R 0-CKV-23-594 RHRSW PMF C3 DISCHARGE CHECK VALVE INTAKE 565 Al 1

14043

• 00 0-STN-67-927 C EECW PUMP DISCHARGE STRAINER INTAKE 565 C

Al 1

14044

• 08A 0-FCV-67-8 C EECW PUMP DISCHARGE STRAINER DRAIN VALVE INTAKE 565 C

Al 1

14045

• 08A 0-FCV-67-49 RHRSW PUMP C1 TO EECW SYSTEM CROSS-CONNECT INTAKE 565 C

Al 1

14046 07 1-FCV-67-50 EECW NORTH HEADER BACKUP TO RBCCW U1 RB 593 R3/P Al 1

14049 07 D-FCV-67-53 EECW NORTH HEADER BACKUP TO THE AIR COMPRESSORS U1 RB 565 R3/N Al 1

14058.

R 0-CKV-67-634 EECW NORTH HEADER SUPPLY CHECK VALVE TO THE A DG U112 DO 565 Al 14059 -

R 0-CKV-67-635 EECW NORTH HEADER SUPPLY CHECK VALVE TO THE A DG U1/2 DG 565 Al 1

14060

• R 0-CKV-67-630 EECW NORTH HEADER SUPPLY CHECK VALVE TO THE B DG U112 DG 565 Al 1

14061

_ R 0-CKV-67-631 EECW NORTH HEADER SUPPLY CHECK VALVE TO THE B DG U1/2 DO 565 Al 14062

• R 0-CKV-67-624 EECW NORTH HEADER SUPPLY CHECK VALVE TO THE C DG U1/2 DO 565 Al 1

14063

• R 0-CKV-67-625 EECW NORTH HEADER SUPPLY CHECK VALVE TO THE C DG U1/2 DO 565 Al 1

14064 -

R 0-CKV-67-627 EECW NORTH HEADER SUPPLY CHECK VALVE TO THE C DO U1/2 DO 565 Al 1

14065 -

R 0-CKV-67-628 EECW NORTH HEADER SUPPLY CHECK VALVE TO THE D DOG U112 DO 565 Al I

14072 -

20 O-E1-23-91/3 EECW PUMP C3 AMPERAGE INDICATION N/A N/A N/A Al I

14074*

06 0-PMP-23-88 RHRSW PUMP B3 INTAKE 565 B

Al 2

14075

• R 0-CKV-23-591 RHRSW PMP B3 DISCHARGE CHECK VALVE INTAKE 565 Al 2

14076

• 00 0-STN-67-926 B EECW PUMP DISCHARGE STRAINER INTAKE 565 B

Al 2

14077 -

08A 0-FCV-67-5 B EECW PUMP DISCHARGE STRAINER DRAIN VALVE INTAKE 565 B

Al 2

14078

• R 0-CKV-67-502 EECW SYSTEM SOUTH HEADER CHECK VALVE U1/2 DO 565 Al 2

14083 -

R 0-CKV-67-619 EECW SYSTEM SOUTH HEADER CHECK VALVE RB 565 Al 2

14084 -

06 O-PMP-23-94 RHRSW PUMP D3 INTAKE 565 D

Al 2

14085

• R 0-CKV-23-597 RHRSW PMP D3 DISCHARGE CHECK VALVE INTAKE 565 Al 2

14086 -

00 0-STN-67*928 D EECW PUMP DISCHARGE STRAINER INTAKE 565 D

Al 2

14087

• 08A 0-FCV-67-11 D EECW PUMIP DISCHARGE STRAINER DRAIN VALVE INTAKE 565 D

Al 2

14088 -

08A 0-FCV-67-48 RHRSW PUMP D1 TO EECW SYSTEM CROSS-CONNECT INTAKE 565 D

Al 2

14089 07 1-FCV-67-51 EECW SYST'-M SOUTH HEADER BACKUP TO RBCCW U1 RB 565 R3/T Al 2

14090

• R 0-CKV-67-528 EECW SOUTH HEADER SUPPLY CHECK VALVE TO THE A DO U112 DO 565 Al 2

14091

• R 0-CKV-67-529 EECW SOUTH HEADER SUPPLY CHECK VALVE TO THE A DO U1/2 DO 565 Al 2

APPENDIX B FACILITY RISK CONSULTAMTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-1 1 iS S E L l _ _ _ _ _ _

NUMBER ICLASS : EOUIPMENT-.D;-

DESCRiPTION

BUILDIN ISSE TRAI 14092 '

R 0-CKV-67-514 EECW SOUTH HEADER SUPPLY CHECK VALVE TO THE C DG U1/2 DG 565 Al 2

14093

• R 0-CKV-67-515 EECW SOUTH HEADER SUPPLY CHECK VALVE TO THE C DG U1/2 DG 565 Al 2

14094*

R 0-CKV-67-521 EECW SOUTH HEADER SUPPLY CHECK VALVE TO THE B DG U1/2 DG 565 Al 2

14095*

R O-CKV-67-522 EECW SOUTH HEADER SUPPLY CHECK VALVE TO THE B DG U1/2 DG 565 Al 2

14096-R 0-CKV-67-507 EECW SOUTH HEADER SUPPLY CHECK VALVE TO THE D DG U1/2 DG 565 Al 2

14097 R

0-CKV-67-508 EECW SOUTH HEADER SUPPLY CHECK VALVE TO THE D DG U1/2 DG 565 Al 2

15001 08A 1-FCV-75-2 CS/PUMP IA SUCTION ISOLATION VALVE Ul RB 519 NW CORNER Al 1

15002 06 1-PMP-75-5 CS/PUMP 1A U1 RB 519 NW CORNER Al 1

15003 R

l-CKV-75-537A CS/PUMP 1A DISCHARGE CHECK VALVE U1 RB Al 1

15004 R

1-CKV-75-5170A CS/PUMP 1A MINI-FLOW CHECK VALVE Ul RB Al 1

15005 08A 1-FCV-75-9 CS/PUMPS IA & IC MINI-FLOW VALVE U1 RB 541 NW CORNER Al 1

15006 08A 1-FCV-75-11 CS/PUMP IC SUCTION ISOLATION VALVE U1 RB 519 NW CORNER Al 1

15007 06 1-PMP-75-14 CS/PUMP IC Ul RB 519 NW CORNER Al 1

15008 R

l-CKV-75-537C CSIPUMP iC DISCHARGE CHECK VALVE U1 RB Al 1

15009 R

1-CKV-75-5170C CS/PUMP IC MINI-FLOW CHECK VALVE U1 RB Al 1

15010 08A 1-FCV-75-22 CS/PUMPS 1A & IC TEST ISOLATION VALVE Ul RB 541 NW CORNER Al I

15011 20 1-FI-75-21 CS/PUMPS 1A & IC FLOW INDICATOR Ul CB 617 MCR Al 1

15012 08A 1-FCV-75-23 CS/DIV I OUTBOARD INJECTION VALVE U1 RB 593 R4/P Al 1

15013 08A 1-FCV-75-25 CS/DIV I INBOARD INJECTION VALVE U1 RB 593 R4/P Al 1

15014 R

1-FCV-75-26 CS/DIV I TESTABLE CHECK VALVE U1 DW Al 1

15015 08A 1-FCV-75-30 CS/PUMP lB SUCTION ISOLATION VALVE U1 RB 519 NECORNER Al 2

15016 06 1-PMP-75-33 CS/PUMP 1E U1 RB 519 NECORNER Al 2

15017 R

1-CKV-75-537B CS/PUMP 1B DISCHARGE CHECK VALVE U1 RB Al 2

15018 R

1-CKV-75-5170B CS/PUMP lB MINI-FLOW CHECK VALVE U1 RB Al 2

15019 08A 1-FCV-75-37 CS/PUMPS 1B & ID MINI-FLOW VALVE UI RB 541 NE CORNER Al 2

15020 08A 1-FCV-75-39 CS/PUMP 1D SUCTION ISOLATION VALVE U1 RB 519 NECORNER Al 2

15021 06 1-PMP-75-42 CS/PUMP ID U1 RB 519 NECORNER Al 2

15022 R

1-CKV-75-537D CS/PUMP ID DISCHARGE CHECK VALVE U1 RB Al 2

15023 R

1-CKV-75-5170D CS/PUMP ID MINI-FLOW CHECK VALVE U1 RB Al 2

15024 08A 1-FCV-75-50 CS/PUMPS 16 & ID TEST ISOLATION VALVE Ul RB 541 NECORNER Al 2

15025 20 1-FI-75-49 CS/PUMPS lB & ID FLOW INDICATOR Ul CB 617 MCR Al 2

15026 08A 1-FCV-75-51 CS/DIV II OUTBOARD DISCHARGE VALVE U1 RB 593 R4/P Al 2

APPENDIX B FAC[LITfy RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September 23, 2004 Page B-12 SSEL

_ _-L;i-

-j NUMBER DCFSS.

BUIL;EQUIPMENG I...

R U

-E TDESCRIPTIO I

15027 08A 1-FCV-75-53 CS/DIV II INBOARD DISCHARGE VALVE U1 RB 593 R4/P Al 2

15028 R

1-FCV-75-54 CS/DIV II TESTABLE CHECK VALVE U1 DW Al 2

16001 08B 1-FSV-84-8A CAD/CAD TO DW (1-FCV-64-18) SOLENOID VALVE U1 RB 565 R5/T Al 1

16002 08B 1-FSV-84-8B CAD/CAD TO DW (1.FCV.64-19) SOLENOID VALVE Ul RB 565 R3IT Al 1

16003 07 1-PREG-84-52 CAD/CAD SYSTEM-A-TO UNIT 1 DRYWELLCONTROLAIR U1 RB 565 R4/U Al 1

16004 08B 1-FSV-84-48 CAD/CAD SYSTEM A TO UNIT 1 DRYWELL CONTROL AIR U1 RB 565 R3/T Al 1

16005 R

1-CKV-32-2521 CA/CHECK VALVE FROM DWCA CMPRSSR TO DRYWELL-PATH 1 U1 RB Al 1

16006 R

1-CKV-32-915 CA/CHECK JALVE FROM DWCA CMPRSSR TO DRYWELL-PATH 2 U1 DW Al 2

16007 R

1-CKV-32-2516 CA/CHECK VALVE FROM DWCA CMPRSSR TO DRYWELL-PATH 1 U1 DW Al I

16008 R

1-CKV-32-872 CAVDRYWELLCONTROLAIRTO PSV-1-19 U1 DW Al I

16009 21 1-ACC-32-6105 CAIACCUMULATOR FOR PSV-1-19 Ul DW.

584 DW Al 1

16010 08B 1-PSV-1.19 MS/SOLENOID VALVE FOR PCV.1-19 Ut DW 584 DW Al 1

16011 R

1-CKV-32-826 CA/DRYWELL CONTROL AIR TO PSV-1-22 Ul DW Al 1

16012 21 1-ACC-32-6107 CAIACCUMULATOR FOR PSV-1-22 U1 DW 584 DW Al 1

16013 08B 1-PSV-1-22 MS/SOLENO!D VALVE FOR PCV.1-22 U1 DW 584 DW Al 1

16014 R

1-CKV-32-869 CA/DRYWEJFLL CONTROL AIR TO PSV.1-5 Ul DW Al 1

16015 21 1-ACC-32-6106 CAACCUMULATOR FOR PSV-1-5 Ut DW 584 DW Al 1

16016 08B I-PSV-1-5 MS/SOLENOID VALVE FOR PCV-1-5 U1 DW 584 DW Al 1

16017 08B 1-PSV-1-23 MS/SOLENOID VALVE FOR PCV.1-23 U1 DW 584 DW Al 1

16018 08B 1-PSV-1-179 MS/SOLENOID VALVE FOR PCV-1-179 U1 DW 584 DW Al I

16019 08B 1-PSV-1-4 MS/SOLENOID VALVE FOR PCV-1-4 U1 DW 584 DW Al 1

16021 08B 1-PSV-1-18 MS/SOLENOID VALVE FOR PCV-1-18 U1 DW 584 DW Al 2

16023 08B 1-FSV-84-8C CAD/CAD TO DW (1-FCV-64-19) SOLENOID VALVE U1 RB 565 R3/T Al 2

16024 088 1-FSV-84-8D CAD/CAD TO DW (1-FCV-64-18) SOLENOID VALVE Ut RB 565 R5/T Al 2

16025 07 1-PREG-84-54 CAD/CAD SYSTEM B TO UNIT 1 DRYWELL CONTROL AIR U1 RB 565 R4/U Al 2

16026 088 1-FSV-84-49 CAD/CAD SYSTEM B TO UNIT 1 DRYWELL CONTROL AIR Ul RB 565 R3/T Al 2

16027 R

1-CKV-32-336 CA/CHECK VALVE FROM DWCA CMPRSSR TO DRYWELL-PATH 2 U1 RB Al 2

16028 R

1-CKV-32-919 CADRYWELL*,ONTROLAIRTO PSV-1-30 Ut DW Al 2

16029 21 1-ACC-32-6111 CAACCUMULATOR FOR PSV-1-30 Ut DW 584 DW Al 2

16030 088 1-PSV-1-30 MS/SOLENOID VALVE FOR PCV-1-30 Ut DW 584 DW Al 2

16031 R

l-CKV-32-894 CA/DRYWELLCONTROL AIR TO PSV-1-31 Ut DW 584 Al 2

16032 21

!-ACC-32-6108 CAVACCUMUI.ATOR FOR PSV-1-31 U1 DW 584 DW Al 2

APPENDIX B FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-1 3 NUMBER CLSS EaUI ENI.

DESCRIPTION:.

BUILDING: '

I TA 16033 08B 1-PSV-1-31 MS/SOLENOID VALVE FOR PCV-1-31 Ul OW 584 DW Al 2

16034 R l-CKV*32-895 CDRYWELLCONTROLAIRTO PSV-1-34 Ul DW Al 2

16035 21 1-ACC-32.6109 CACCUMULATOR FOR PSV-1-34 U_ DW 584 DW Al 2

16036 08B 1-PSV-1-34 MS/SOLENOID VALVE FOR PCV-1-34 U_ OW 584 OW Al 2

16038 08B 1-PSV-1-41 MS/SOLENOID VALVE FOR PCV-1-41 Ul DW 584 DW Al 2

16040 08B 1-PSV-1-42 MS/SOLENOID VALVE FOR PCV-1-42 U1 OW 584 DW Al 2

16041 08B 1-PSV-1-180 MS/SOLENOID VALVE FOR PCV-1-180 U1 DW 584 DW Al 2

16042 R

1-CKV-32-3749 CAD/CONTROL AIR/CAD CHECK VALVE U1 RB Al 1

16043 07 l-FCV-64-20 CONTAINMENT VENTILATION ISOLATION VALVE Ul RB 565 R3/T Al 16044 07 1-FCV-64.21 CONTAINMENT VENTILATION ISOLATION VALVE Ul RB 565 R3/T Al 16045 R

l-CKV-64.800 CONTAINMENT VENTILATION ISOLATION CHECK VALVE Ul RB 565 Al 16046 R

1-CKV-64-801 CONTAINMENT VENTILATION ISOLATION CHECK VALVE Ul RB 565 Al 16051

• 21 0-TNK-84-635 CAD/NITROGEN STORAGE TANK'A-YARD 565 YARD Al I

16052

• 07 0-FCV-84-5 CAD/N2 TANK A ISOLATION VALVE YARD 565 YARD Al 1

16053

• 08B 0-FSV-84-5 CAD/N2 TANK A ISOLATION SOLENOID VALVE YARD 565 YARD Al 1

16054

• 00 O-VPR-84-639 CAD/N2 TANK A-VAPORIZER YARD 565 YARD Al 1

16055 -

00 0-HTR-84-5 CAD/N2TANK A ELECTRIC HEATER YARD 565 YARD Al 1

16061

• 21 0-TNK-84-636 CAD/NITROG EN STORAGE TANK *B' YARD 565 YARD Al 2

16062-07 0-FCV-84-16 CAD/N2 TANK 'B' ISOLATION VALVE YARD 565 YARD Al 2

16063 -

08B 0-FSV-84-16 CAD/N2TANK 'B ISOLATION SOLENOID VALVE YARD 565 YARD Al 2

16064

• 00 0-VPR-84-640 VAD/N2 TANK 8 VAPORIZER YARD 565 YARD Al 2

16065 00 0-HTR-84-16 CADN2TANKB ELECTRIC HEATER YARD 565 YARD Al 2

17001

• 17 0-GEN-82-A UNIT I & 2 DIESEL GENERATOR A UI/2 DG 565 DG A Al 1

17002

• 21 0-TNK-18-45/1 G A7 DAY FUEL OIL TANK U1/2 DG 565 DG A Al I

17003

• 21 0-TNK-18-45/2 DO A 7 DAY FUEL OILTANK U1/2 DG 565 DG A Al 1

17004

• 21 0-TNK-18-45/3 DG 'A' 7 DAYFUEL OIL TANK U1/2 DG 565 DG A Al 1

17005

• 21 G-TNK-86-650A DG A LEFT BANK STARTING AIR RECIEVERS U1/2 DG 565 DG A Al 1

17006 -

21 0-TNK-86-651A DG A LEFT BANK STARTING AIR RECIEVERS U1/2 DG 565 DG A Al 1

17007

• 21 0-TNK-86-652A DG A LEFT BANK STARTING AIR RECIEVERS U1/2 DG 565 DG A Al 1

17008 -

21 0-TNK-86.653A DG A LEFT BANK STARTING AIR RECIEVERS U1/2 DG 565 DG A Al 1

17009

• 21 0-TNK-86-654A DO A LEFT BANK STARTING AIR RECIEVERS U1/2 DG 565 DG A Al 1

17010

• 21 0-TNK-86-655A DG A RIGHT BANK STARTING AIR RECIEVERS U1/2 DG 565 DG A Al I

APPENDIX B FACILITYRISK CONSULTANTS, INC.

TVA/BFN-01-R-004 Revision 0 September 23, 2004 Page B-1 4 SSE F

r NUMBER CLASS EQUIPENT I.D.

DESCRIPTION BUILDINGl ELEV ROIS TRAIN:

1701t*

21 0-TNK-86-656A DO A RIGHT BANK STARTING AIR RECIEVERS U1/2 DO 565 D-A Al 1

17012

• 21 0-TNK-86-657A DO A RIGHT BANK STARTING AIR RECIEVERS U1/2 DG 565 DG A Al 17013

• 21 0-TNK-86-658A DO A RIGHT BANK STARTING AIR RECIEVERS U1/2 DG 565 DG A Al 1

17014

• 21 0-TNK-86-659A DG A RIGHT BANK STARTING AIR RECIEVERS U1/2 DG 565 DG A Al 17015 '

09 0-FAN-30-64 DO ROOM A EXHAUST FAN *AR U1/2 DG 583 DG A Al 1

17016

• 09 0-FAN-30-65 DO ROOM A EXHAUST FAN AB U1/2 DG 583 DG A Al 1

17017

• 10 0-FCO-30-64A OUTLET DAMPER FOR FAN*A-IN DO ROOM 'A' U1/2 DG 583 DG A Al 1

17018 -

10 0-FCO.30-64B INLET DAMPER FOR FAN A IN DO ROOM A

U1/2 DO 583 DO A Al 1

17019

• 10 0-FCO.30-64C INLET DAMPER FOR FAN A IN DO ROOM

• U1/2 DG 583 DG A Al 1

17020 -

10 0-FCO-30-65A OUTLET DAMPER FOR FAN *B IN DO ROOM A U112 DO 583 DG A Al 1

17021 0 10 0-FCO-30-65A INLET DAMPER FOR FAN B IN DO ROOM A

U1/2 DO 583 DG A Al 1

17022

• 10 0-FCO-30-65C INLET DAMPER FOR FAN B IN DO ROOM A U1/2 DO 583 DG A Al 1

17023

• 17 0-GEN-82-B UNIT I & 2 DIESEL GENERATOR B' U1/2 DO 565 DG B Al I

17024 -

21 0-TNK-18-46/1 DG*B-7 DAY FUEL OILTANK U1/2 DO 565 DO B Al 1

17025 -

21 0-TNK-18*46/2 DG B 7 DAY FUELOILTANK U1/2 DO 565 DO B Al 17026

• 21 0-TNK-18-46/3 DO *B-7 DAY FUELOILTANK U1/2 DO 565 DOG B Al 1

17027

• 21 0-TNK-86-650B DO *B-LEFT BANK STARTING AIR RECEIVERS U1/2 DO 565 DO B Al 1

17028 21 0-TNK-86-651B DO B'LEFT BANKSTARTING AIR RECEIVERS U1/2 DO 565 DGB Al 1

17029

• 21 0-TNK-86-652B DG B LEFT BANK STARTING AIR RECEIVERS U1/2 DO 565 DO B Al 1

17030 -

21 0-TNK-86-653B DO *B-LEFT BANK STARTING AIR RECEIVERS U1/2 DO 565 DG B Al 1

17031 21 0-TNK-86-654B DO B LEFT BANK STARTING AIR RECEIVERS U1/2 DO 565 DO B Al 1

17032

• 21 0-TNK-86-655B DG B RIGHT BANK STARTING AIR RECEIVER U1/2 DO 565 DO B Al 1

17033

• 21 0-TNK-86-656B DO *B RIGHT BANK STARTING AIR RECEIVER U1/2 DO 565 DO B Al 1

17034.

21 0-TNK-86-657B DO B RIGHT BANK STARTING AIR RECEIVER

_1/2 DO 565 DO B Al 1

17035 -

21 0-TNK-86-658B DG B-RIGHT BANK STARTING AIR RECEIVER U1/2 DO 565 DO B Al 1

17036

• 21 0-TNK-86-659B DO *B-RIGHT BANK STARTING AIR RECEIVER U1/2 DO 565 DO B Al 1

17037

• 09 0-FAN-30-66 DG ROOM B EXHAUSTAN AIRR U1/2 DO 583 DG B Al 1

17038

• 09 0-FAN-30-67 DO ROOM B EXHAUST FAN *-B U1/2 DO 583 DG B Al 1

17039

• 10 0-FCO-30-66A OUTLET DAMPER FOR FAN A IN DO ROOM'B U1/2 DO 583 DO B Al 1

170403 10 0-FCO-30-66B IONLET DAMPER FOR FAN A-IN DO ROOM B' U1/2 DO 583 DO B Al 1

17041

• 10 0-FCO-30-66C INLET DAMPER FOR FAN A IN DO ROOM B' U1/2 DO 583 DO B Al I

17042

• 10 0-FCO-30-67A OUTLET DAMPER FOR FAN *B-IN DO ROOM *B' U1/2 DO 583 DG B Al 1

APPENDIX B FACILITY RISK CONSULTANTS, INC.

TVAtBFN-01 -R-004 Revision 0 September 23, 2004 Page B-1 5

-SSEL l -1

-l NUMBER CLASS EQUIPMENT l.D.

DESCRIPTION BUILDING

_ELE..

ROOM ISSUE TRAIN 17043 1IRO.

0 B A.

17043 ^

10 0-FCO.30-67B INLET DAMPER FOR FAN B IN OG ROOM B U1/2 DG 583 DOG B

Al I

17044

• 10 0-FCO.30-67C INLET DAMPER FOR FAN B IN DG ROOM'B' U1/2 DO 583 DO B Al 1

17045

• 17 0-GEN-82-C UNIT 1 & 2 DIESEL GENERATOR C U1/2 DG 565 DOG C

Al 2

17046

• 21 0-TNK-18-47/1 DO C 7 DAY FUELOILTANK U1/2 DO 565 DG C Al 2

17047 21 0-TNK-18-47/2 DO.C 7 DAY FUELOILTANK U112 O 565 DO C Al 2

17048

• 21 0-TNK-18-47/3 DG C 7 DAY FUEL OILTANK U1/2 DO 565 DG C Al 2

17049

• 21 0-TNK-86-650C OG C LEFT BANK STARTING AIR RECEIVERS U1/2 DG 565 DO C Al 2

17050 21 0-TNK-86-651C DG 'C LEFT BANK STARTING AIR RECEIVERS U1/2 DG 565 DO C Al 2

17051

• 21 0-TNK-86-652C DOG C LEFT BANK STARTING AIR RECEIVERS U1/2 DG 565 DG C Al 2

17052 21 0-TNK-86-653C DO C LEFT BANK STARTING AIR RECEIVERS UI/2 DG 565 DGC Al 2

17053

• 21 0-TNK-86-654C OG C-LEFT BANK STARTING AIR RECEIVERS U1/2 DG 565 DG C Al 2

17054

• 21 0-TNK-86-655C DOG C RIGHT BANK STARTING AIR RECEIVERS U1/2 DG 565 DOG C

Al 2

17055

• 21 0-TNK-86-656C DOG C RIGHT BANK STARTING AIR RECEIVERS U1/2 DO 565 DG C Al 2

17056 21 0-TNK-86-657C O C RIGHT BANK STARTING AIR RECEIVERS U112 DG 565 DO C Al 2

170574 21 0-TNK.86-658C DG C RIGHT BANK STARTING AIR RECEIVERS U1/2 DG 565 DO C Al 2

17058

• 21 0-TNK-86-659C DOG C RIGHT BANK STARTING AIR RECEIVERS U1/2 DG 565 DO C Al 2

17059

• 09 0-FAN-30-68 DG ROOM C EXHAUST FANN A U1/2 DG 583 DO C Al 2

17060 09 0-FAN-30-69 DO ROOM C EXHAUST FAN -B U1/2 DG 583 DOGC Al 2

17061

• 10 0-FCO-30-68A OUTLET DAMPER FOR FANS A IN DO ROOMECE U1/2 DG 583 DO C Al 2

17062

• 1 0 0-FCO*30-68B INLET DAMPER FOR FANWAIN DG ROOM'C' Ut/2 DO 583 DO C Al 2

17063

• I1 0-FCO-30-68C INLET DAMPER FOR FAN A IN DG ROOM CE UI/2 DG 583 DG C Al 2

17064

• 10 0-FCO-30-69A OUTLET DAMPER FOR FAN B IN DO ROOM C U112 DG 583 DG C Al 2

17065

• 10 0-FCO-30-69B INLET DAMPER FOR FAN B IN DO ROOM C' U1/2 DG 583 DO C Al 2

17066

• 10 0-FCO-30-69C INLET DAMPER FOR FAN B IN DO ROOM C U1/2 DG 583 DO C Al 2

17067' 17 D-GEN-82-D UNITI& 2 DIESEL GENERATOR'D UI/2 DO 565 DO D Al 2

17068

• 21 0-TNK-18-4861 DOUDL7 DAY FUELOIL TANK UI/2 DO 565 DG D Al 2

17069 21 0-TNK*18-4812 DO 'D'7DAY FUELOI1L TANK U1/2 DO 565 DOD Al 2

17070

• 21 0-TNK-18-48/3 DO -D 7DAY FUEL OIL TANK U1/2 DO 565 DOD Al 2

17071

• 21 0-TNK-36-650D DONDLLEFT BANK STARTING AIR RECEIVERS UI/2 DO 565 DO D Al 2

17072

• 21 0-TNK-86-651D DO D-LEFT BANK STARTING AIR RECEIVERS U1/2 DO 565 DO D Al 2

17073

• 21 0-TNK-86-652D DG D LEFT BANK STARTING AIR RECEIVERS UI/2 DO 565 DDOD Al 2

17074

• 21 0-TNK-86-653D DG D-LEFT BANK STARTING AIR RECEIVERS U1/2 DO 565 DG D Al 2

APPENDIX B FACLuTYRISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-1 6 S S E L-NUMBER CLASS EQUIPMENT

.PTION BUILDING ELEV.

ROOM ISSUE TRAIN 17075

• 21 0-TNK-86-654D DG D LEFT BANK STARTING AIR RECEIVERS U1/2 DG 565 DG D Al 2

17076

• 21 0-TNK-86-655D DG D-RIGHT BANK STARTING AIR RECEIVERS U1/2 DG 565 DG D Al 2

17077 21 0-TNK-86-656D DG *D-RIGHT BANK STARTING AIR RECEIVERS U1/2 DG 565 DG D Al 2

17078 ^

21 0-TNK-86-657D DG D RIGHr BANK STARTING AIR RECEIVERS U1/2 DG 565 DG 0 Al 2

17079

• 21 0-TNK-86-658D DOG

• D RIGHT BANK STARTING AIR RECEIVERS U1/2 DG 565 DG D Al 2

17080

• 21 0-TNK-86-659D DG D' RIGHT BANK STARTING AIR RECEIVERS U112 DG 565 OG D Al 2

17081

• 09 0FAN-30-170 DG ROOM D EXHAUST FAN 'A' U1/2 DG 583 DG D Al 2

17082' 09 0-FAN-30-171 DG ROOM D EXHAUST FAN *8-UI/2 DG 583 DG D Al 2

17083

• 10 0-FCO 30-170A OUTLET DAMPER FOR FAN A-IN DG ROOM D_

U1/2 DG 583 DG D Al 2

17084

• 10 0-FCO-30-170B INLET DAMPER FOR FAN A IN DG ROOM *D U1/2 DG 583 DG D Al 2

17085

• 10 0-FCO-30-170C INLET DAMPER FOR FAN A IN DG ROOM *D U1/2 DG 583 DG D Al 2

17086

• 10 0-FCO-30-171A OUTLET DAMPER FOR FAN B IN DG ROOM *D' U1/2 DG 583 DG D Al 2

17087

• 10 0-FCO-30-171B INLET DAMPER FOR FAN '*B IN DG ROOM D-U1/2 DG 583 DG D Al 2

17088

• 10 0-FCO-30-171C INLET DAMPER FOR FAN 'B-IN DG ROOM *D-U1t2 DG 583 DG D Al 2

18001 R

1-CKV-23-510 RHRSW TO HXA INLET CHECK VALVE Ul RB 565 Al 1

18002 08A 1-FCV-23-034 RHR/RHRSW HXA OUTLET VALVE Ul RB 565 R2/U Al 1

18003 R

1-CKV-23-550 RHRSW TO HXC INLET CHECK VALVE U1 RB 565 Al 1

18004 08A 1.FCV-23-040 RHR/RHRSW HX C OUTLET VALVE Ul RB 565 R2/U Al 1

18005 R

1-CKV-23-530 RHRSW TO HX B INLET CHECK VALVE Ul RB 565 Al 2

18006 08A 1-FCV-23-046 RHRJRHRSW HX B OUTLET VALVE U1 RB 565 RS/T Al 2

18007 R

1-CKV-23-569 RHRSW TO HX D INLET CHECK VALVE Ul RB 565 Al 2

18008 08A 1-FCV-23-052 RHR/RHRSW HX D OUTLET VALVE U1 RB 565 RS/T Al 2

18009 20.-

FI-23-36 RHRSW HX A FLOW INDICATOR U.OB 617 MCR Al 1

18010 20 1-FI-23-42 RHRSW HX C FLOW INDICATOR U1 CB 617 MCR Al 1

18011 20 1-FI-23-48 RHRSW HX B FLOW INDICATOR U1 CB 617 MCR Al 2

18012 20 1-FI-23-54 RHRSW HX D FLOW INDICATOR Ul CB 617 MCR Al 2

18021

• 06 0-PMP-23-005 RHRSW PUMP A2 INTAKE 565 A

Al 1

18022

• R 0-CKV.23-506 RHRSW PMP A2 DISCHARGE CHECK VALVE INTAKE 565 Al 1

18024

• 06 0.PMP-23-012 RHRSW PUMP C2 INTAKE 565 C

Al I

18025

• R 0-CKV-23-542 RHRSW PMAP C2 DISCHARGE CHECK VALVE INTAKE 565 Al 1

18027

• 06 0-PMP 19 RHRSW PUMP B2 INTAKE 565 B

Al 2

18028

• R 0-CKV-23-526 RHRSW PMP B2 DISCHARGE CHECK VALVE INTAKE 565 Al 2

APPENDIX B FACLITY RISK CONsuANmS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-1 7 NUMBER EUPN D

DESCRIPTION:'IDLASE:RO ISSUE TRAIN.

18029 08A 1-FCV-23-046 RHR/RHRSW HX B OUTLET VALVE Ut RB 565 R5/T Al 2

18030 06 O-PMP-23-027 RHRSW PUMP D2 INTAKE 565 D

Al 2

18031 R

0-CKV-23-561 RHRSW PMP D2 DISCHARGE CHECK VALVE INTAKE 565 Al 2

18032 08A 1-FCV-23-052 RHRPRHRSW HX D OUTLET VALVE U1 RB 565 RS/T Al 2

18033 08A 1-FCV-23-57 RHR/RHRSW CROSS CONNECT VALVE Ut RB 565 R6/S Al 2

19001 20 1-PNLA-009-0023/1 ELECTRICAL CONTROL PANEL 1-9-23-1 Ul CB 617 Ut MCR Al 19002 20 1-PNLA-009-002312 ELECTRICAL CONTROL PANEL 1-9-23-2 U1 CB 617 Ut MCR Al 19003 20 1-PNLA-009-002313 ELECTRICALCONTROL PANEL 1-9-23-3 U1 CB 617 Ut MCR Al 19004 20 1-PNLA-009-0023/4 ELECTRICALCONTROL PANEL 1-9-23-4 Ul CB 617 Ut MCR Al 19005 20 1-PNLA-009-0023/5 ELECTRICALCONTROL PANEL 1-9-23-5 Ut CB 617 Ut MCR Al 19006 20 1-PNLA-009-0023/6 ELECTRICAL CONTROL PANEL 1-9-23-6 Ut CB 617 Ut MCR Al 19007 20 1-PNLA-009-0023/7 ELECTRICAL CONTROL PANEL 1-9-23-7 Ut CB 617 Ut MCR Al 19008 20 i-PNLA-009-0023/8 ELECTRICAL CONTROL PANEL 1-9-23-8 U1 CB 617 Ut MCR Al 190101 14 1-JBOX-268-5986 MG SET ION CONTROL STATION (1 -HS-268-0001 DN)

U1 RB 621 U/R2 Al I

19011..

14 1-JBOX-268-5988 MG SET EN CONTROL STATION (1-HS-268-0O OEN)

U1 RB 639 S/R7 Al it 19012-14 1-JBOX-268-5947 MG SET IDN CONTROL BOX (RELAYS) -SEALED BOX Ut RB 621 U/R2 Al I

19013 S

14 V.R. Box IDN MG SET 1DN VOLTAGE REGULATOR BOX Ul RB 621 S/R1 Al I

19014" 14 1-JBOX-268-5949 MG SET 1EN CONTROL BOX (RELAYS) - SEALED BOX Ut RB 639 S/R7 Al II 19015-13 1-MGEN-268-OOO1DN LPCI MG SET 1DN U1 RB 621 U/R2 Al I

19016" 01 1-BDBB-268-0001D 480V RMOV BOARD 1D Ut RB 593 U/R4 Al I

19017" 13 1-MGEN-268-O0OIEN LPCI MG SEr 1EN Ut RB 639 S/R7 Al 190181 01 1-BDBB-268-OOOIE 480V RMOV BOARD tE U1 RB 621 S/R3 Al 11 190191 14 VR Box 1EN MG SET tEN VOLTAGE REGULATOR BOX Ut RB 621 S/R2 Al II 19030 01 1-BDBB-281-0001A 250V DC RMOV BOARD 1A U1 RB 621 0/RI Al 11 19031 01 1-BDBB-281-0001B 250V DC RMOV BOARD IB Ut RB 593 0/R1 Al I

19033 01 1-BDBB-281-OOO1C 250V DC RMOV BOARD IC U1 RB 565 O/R1 Al I

19039 14 1-JBOX-253-6455 I&C BUS IA DISC SWITCH tA1 U1 RB 621 R/R1 Al I

19040 04 1-XFA-253-OOOIA1 I&C BUS 1A480/208-120VTRANSFORMER U1 RB 621 fR/Ri Al I

19041 04 1-XFA-253-0001A I&C BUS IA REGULATING TRANSFORMER U1 RB 621 R/R1 Al 19042 14 1-JBOX-253-6457 I&C BUS 1A DISC SW 1A2 U1 CB 593 BATT BD I Al I

19043 14 t-JBOX-253-6456 I&C BUS 1A DISC SWITCHES 1A3, 1A4, 1A5, 1A6 UI RB 621 fl/RI Al I

19044 14 1-JBOX-253-8862 I&C BUS IA DISC SWITCH Ut RB 621 R/R1 Al I

APPENDIX B FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-1 8 NUMBER C S

EU N

BUILDINGl 0I 19045 20 1-PNLA-009-0009 I&C BUS IA (CAB 2 OF PNL 1-9-9)

U1 CB 617 Ul MCR Al I

19046 20 1-PX-64-160B POWER SUPPLY (PNL 1-9-19: 1-LI-64-159B,160B)

U1 CB 593 U1 AIR Al I

19047 20 1-PXMC-23-1 14 POWER SUPPLY (PNL 1-9-18: FI-23-36,42: Fl-74-50)

Ul CB 593 U1 AIR Al 19048 20 1-PXMC-23-115 A&B POWER SUPPLY (PNL 1-9-19: Fl-23-48,54; FI-74-64)

U1 CB 593 U1 AIR Al 11 19049 04 1-XFA-253-OOO1BI I&C BUS IB 480/208-120V TRANSFORMER U1 RB 593 R/R1 Al II 19050 04 1-XFA-253-0001B2 I&C BUS IB REGULATING TRANSFORMER U1 RB 593 R/R1 Al II 19051 14 1-JBOX-253-6460 I&C BUS 1B DISC SW 1B2 U1 CB 593 BATT BD I Al

_I 19052 14 1-JBOX-253-8865 I&C BUS 1B DISC SWITCH U1 RB 593 R/R1 Al 11 19053 14 1-JBOX-253-6459 I&C BUS lB DISC SWITCHES 1B3, 1B4, 1B5, 1B6 Ut RB 593 RPR1 Al ll 19054 20 1-PNLA-009-0009 I&C BUS 1B (CAB 3 OF PNL 1-9-9)

U1 CB 617 U1 MCR Al it 19055 20 1-PX-64-159B POWER SUPPLY (PNL 1-9-19)

U1 CB 593 U1 AIR Al 11 19068 14 1-JBOX-253-7160 I&C BUS IB DISC SWITCH 1B1 U1 RB 593 R/R1 Al 11 19070 16 1-INVT-256-0001 DIV I ECCS ATU INVERTER U1 RB 593 0/R1 Al I

19071 20 1-PX-71-60-1 ECCS ATU CAB 1-9-81 POWER SUPPLY U1 CB 593 U1 AIR Al I

19072 20 1-PX-71-60-IA ECCS ATU CAB 1-9-81 POWER SUPPLY U1 CB 593 U1 AIR Al I

19073 20 1-PX-64-50 POWER SUPPLY (PNL 1-25-31: XR-64-50 IDEV BATERM 11/12])

Ut RB 621 0/R2 Al I

19074 20 1-PX-74-56 POWER SUPPLY (PNL 1-9-18: FI-74-56)

U1 CB 593 U1 AIR Al I

19075 16 1-INVT-256-0002 DIV 11 ECCS ATU INVERTER Ul RB 621 P/R1 Al II 19076 20 1-PX-71-60-2 ECCS ATU CAB 1-9-82 POWER SUPPLY Ut CB 593 U1 AIR Al 11 19077 20 1-PX-71-60-2A ECCS ATU CAB 1-9-82 POWER SUPPLY U1 CB 593 U1 AIR Al 11 19078 20 1-PX-74-70 POWER SUPPLY (PNL 1-9-19: Fl-74-70)

U1 CB 593 Ut AIR Al II 19079 20 1-PX-64-159A POWER SUPPLY (1-9-18)

Ut CB 593 Ut AIR Al I

19080 20 1-PX-64-160A POWER SUPPLY (1-9-18)

U1 CB 593 Ut AIR Al I

19081 20 1-PX-64-67B POWER SUPPLY (1-9-19)

U1 CB 593 UI AIR Al 11 19082 20 1-PX-64-161 POWER SUPPLY (PNL 9-87)

U1 CB 593 Ut AIR Al 19083 20 t-PX-64-162 POWER SUPPLY (PNL 9-88)

U1 CB 593 U1 AIR Al 11 19084 lS 1-PS-67-50 PRESSURE SWITCH FOR 1-FCV-67-50 (14046)

Ut RB 593 P/R3 Al 19085 18 1-PS-67-51 PRESSURE SWITCH FOR 1-FCV-67-51 (14047)

Ut RB 565 T/R3 Al 19088 20 1-LPNL-925-044A/1 I COMMON BD LOGIC RELAY PANEL 25-44-All Ut RB 621 S/Ri Al 19089 20 1-LPNL-925-044AV12 COMMON BD LOGIC RELAY PANEL 25-44-A12 Ut RB 621 S/R2 Al 19090 20 1-LPNL-925-044B/11 COMMON BD LOGIC RELAY PANEL 25-44-B I1 Ut RB 621 S/R1 Al 19091 20 1-LPNL-925-044B112 COMMON BD LOGIC RELAY PANEL 25-44-B12 Ut RB 621 S/R2 Al APPENDIX B FACILIY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-19

.SSEL I.....

DESCRITION BUILDING ELEV S

19100l 14 3-ECAB-231-OOIA 250V DC CONT PWR TRANSFER SW -480V SD BD 1A U3 RB 593 S/R1 Al I

19101 14 3-ECAB-231-001B 250V DC CONT PWR TRANSFER SW -480V SD BD 1B U3 RB 593 S/R2 Al II 19114 20 1-PNLA-009-0003A REACTOR SD & CONT. COOLING PNL U1 CB 617 U1 MCR Al 19115 20 1-PNLA.009-0003B REACTOR SD & CONT. COOLING PNL Ul CB 617 U1 MCR Al 19116 20 1-PNLA-009.0004 CLEANUP & RECIRC PNL Ul CB 617 Ul MCR Al 19117 20 1-PNLA-009-0005 REACTOR CONTROL PNL U1 CB 617 U1 MCR Al 19118 20 1.PNLA-009-0006 FW & COND PNL U1 CB 617 U1 MCR Al 19120 20 1.PNLA.009-0015 RPS CH A (DIV I)

U1 CB 593 Ul AIR Al I

19121 20 1-PNLA-009-0016 RPS CH A, B, C, D Ul CB 593 U1 AIR Al 19122 20 1-PNLA-009-0017 RPS CH B (DIV Il)

U1 CB 593 U1 AIR Al II 19123 20 1-PNLA.009-0018 FW & RECIRC PNL U1 CB 593 U1 AIR Al 19124 20 1-PNLA-009-0019 PROCESS INSTR PNL U1 CB 593 U1 AIR Al 19125 20 1-PNLA-009.0021 TEMP RECORDING PNL U1 CB 617 Ul MCR Al 19126 20 1-PNLA-009-0028 CRD SELECT RELAY AUX PNL U1 CB 593 Ul AIR Al 19127 20 1-PNLA-009-0030 AUTO BLOWNDOWN AUX PNL U1 CB 593 U1 AIR Al 19128 20 1-PNLA.009-0032 RHR, CS, & HPCI (CH A) PNL U1 RB 593 Ul AIR Al 19129 20 1-PNLA-009-0033 RHR, CS, & HPCI (CH B) PNL U1 CB 593 U1 AIR Al 19130 20 1-PNLA-009-0039 HPCI RELAY AUX PNL U1 CB 593 U1 AIR Al 19131 20 1-PNLA-009-0042 MSIV (INBOARD) DIV II PNL UICB 593 UIAIR Al 19132 20 1-PNLA-009-0043 MSIV (OUTBOARD) DIV II PNL U1 CB 593 U1 AIR Al 19133 20 1-PNLA-009-0054 CONTAINMENT ATM. DILUTION PNL Ul CB 617 U1 MCR Al 19134 20 1-PNLA-009-0055 CONTAINMENT ATM. DILUTION PNL Ul CB 617 U1 MCR Al 19135 20 1-PNLA-009-0081 DIVCI ECCS ATU CABINET U1 CB 593 U1 AIR Al 19136 20 1-PNLA-009-0082 DIV II ECCS ATU CABINET U1 CB 593 Ul AIR Al II 19137 20 1-PNLA-009-0083 RPS ATU CAB U1 CB 593 U1 AIR Al I

19138 20 1-PNLA-009-0084 RPS ATU CAB U1 CB 593 Ul AIR Al I

19139 20 1-PNLA-009-0085 RPS ATU CAB U1 CB 593 U1 AIR Al II 19140 20 1-PNLA-009-0086 RPS ATU CAB U1 CB 593 Ul AIR Al if 19141 20 1-PNLA-009-0087 DIV I TORUS TEMP MONITORING U1 CB 593 U1 AIR Al I

19142 20 1-PNLA-009-0088 DIV II TORUS TEMP MONITORING U1 CB 593 U1 AIR Al I

19145 20 1-PNLA-009-0093 NEW PNL (INSTALLED BY DCN W19433)

U1 CB 593 U1 AIR Al 19146 18 1-HS-74-7B LOCAL HS STATION U1 RB 541 SW CORNER Al APPENDIX B AFACtLnY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-20 NuMBER ICLASSI EQ6IPMENT 1-.0.'::

.E.C.PTIONBU.LIN........OOM SSUE TAI 19147 14 1-JB-668 JUNCTION BOX (TERM BLOCK) - SEALED BOX Ul RB 541 SW CORNER Al 19148 18 1-HS-74-57B LOCAL HS STATION Ul RB 551 TORUS Al 19149 14 1-JB-654 JUNCTION BOX (TERM BLOCK) - SEALED BOX Ul RB 551 TORUS Al I

19150 18 1-HS-74-59B LOCAL HS STATION UI RB 551 TORUS Al I

19151 18 1-HS-74-58B LOCAL HS STATION U1 RB 551 TORUS 19153 18 1-HS-74-52B LOCAL HS STATION U1 RB 565 T/R3 Al 11 19154 14 1-JB-1079 JUNCTION BOX (TERM BLOCK) - SEALED BOX Ut RB 583 T/R3 Al II 19155 18 1-HS-74-53B LOCAL HS STATION U1 RB 565 T/R3 Al I

19156 18 1-HS-74-60B LOCAL HS STATION U1 RB 593 S/R3 Al I

19158 18 1-HS-74-61B LOCAL HS STATION U1 RB 593 SIR3 I

I 19160 18 1-HS-74-30B LOCAL HS STATION Ut RB 541 SE CORNER Al II 19162 18 1-HS-74-71B LOCAL HS STATION U1 RB 551 TORUS Al II 19163 14 1-JB-665 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 551 TORUS Al 11 19164 18 1-HS-74-72B LOCALHSSTATION Ut RB 551 TORUS I

if 19165 18 1-HS-74-66B LOCAL HS STATION U1 RB 583 T/R4 Al 11 19166 14 l-JB-1080 JUNCTION BOX (TERM BLOCK) - SEALED BOX Ut RB 583 T/R4 Al 11 19167 18 1-HS-74-67B LOCAL HS STATION U1 RB 583 T/R4 Al 11 19170 18 1-HS-74-75B LOCAL HS STATION Ut RB 565 S/R6 I

11 19171 18 1-HS-70-47B LOCAL HS S-ATION U1 RB 551 TORUS I

if 19172 14 1-JB-1204 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 551 TORUS Al 11 19173 18 1-HS-75-09B LOCAL HS STATION Ut RB 519 NW CORNER Al I

19175 18 1-HS-75-25B LOCAL HS STATION Ut RB 593 P/R4 Al I

19176 14 1-JBOX-1064 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 593 P/R4 Al I

19177 18 1-HS-75-37B LOCAL HS STATION Ul RB 519 NECORNER Al 11 19179 18 1-HS-75-53B LOCAL HS STATION (TERM BLOCK) - SEALED BOX U1 RB 593 P/R4 Al 11 19180 14 1-JBOX-1067 LOCAL HS STATION (TERM BLOCK) - SEALED BOX Ut RB 593 P/R4 Al II 19181 18 1-HS-23-34B LOCAL HS STATION (TERM BLOCK) - SEALED BOX Ut RB 565 U/R2 Al I

19182 14 1-JBOX-1077 JUNCTION BOX (TERM BLOCK) - SEALED BOX Ut RB 565 U/R2 Al I

19183 18 1-HS-23-40B LOCAL HS STATION (TERM BLOCK) - SEALED BOX Ut RB 565 U/R2 Al I

19184 18 1-HS-23-46B LOCAL HS STATION U1 RB 565 T/R4 Al 11 19185 14 1-JB-1087 JUNCTION BOX (TERM BLOCK) SEALED BOX U1 RB 565 T/R4 Al 11 19186 18 1-HS-23-52B LOCAL HS STATION Ut RB 565 T/R4 Al I11I APPENDIX B FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page B-21 q

I-!

MSSEL -

NUMBER ICLASSIEQUIPMENT. I.D..

DESCRIPTION L..N.

.V

........... O A....-

PUMP IA 19187 18 1-HS-74-0028B LOCAL HS STATION-RHR PUMP IA UI RB 519 SW CORNER Al 19188 18 1-HS-74-0028B LOCAL HS STATION - RHR PUMP IB U1 RB 519 SE CORNER Al 19189 18 1-HS-74-0016B LOCAL HS STATION - RHR PUMP IC UI RB 519 SW CORNER Al I

19190 18 1-HS-74-0039B LOCAL HS STATION - RHR PUMP ID U1RB 519 SE CORNER Al 19191 18 1-HS-75-0005B LOCAL HS STATION -CS PUMP IA U1 RB 519 NW CORNER Al 19192 18 1-HS-75-0033B LOCAL HS STATION -CS PUMP 1B UI RB 519 NE CORNER Al 19193 18 1-HS-75-0014B LOCAL HS STATION -CS PUMP 1C UI RB 519 NW CORNER Al 19194 18 1-HS-75-0042B LOCAL HS STATION-CS PUMP 1D U1 RB 519 NE CORNER Al 19195 18 1-LPNL-925-005A LOCAL PANEL 25-5A U1 RB 593 S/R3 Al 19196 18 1-LPNL-925-005B LOCAL PANEL 25-5B U1 RB 593 SMR3 Al 19197 18 1-LPNL-925-005D LOCAL PANEL 25-5A001 U1 RB 593 S/R3 Al 19198 18 1-LPNL-925-006A LOCAL PANEL 25-6A U1 RB 593 PIR5 Al 19199 18 1-LPNL-925-006D LOCAL PANEL 25-6-001 U1 RB 593 Q/R5 Al 19200 18 1-LPNL-925-0059 LOCAL PANEL 25-59 U.RB 519 SW CORNER Al 19201 18 1-LPNL-925-0062 LOCAL PANEL 25-62 U1 RB 519 SE CORNER Al 19204 20 1-PNLA-925-0031 LOCAL PANEL 25-31 U1 RB 621 COR2 Al 19205 20 1-PNLA-925-0032 LOCAL PANEL 25-32 U1 RB 621 Q/R2 Al 19206 18 1-LPNL-925-0001 LOCAL PANEL 25-1 UI RB 519 NW CORNER Al 19207 18 1-LPNL-925-0060 LOCAL PANEL 25-60 U1RB 519 N/E CORNER Al 19208-13 1-MG EN-268-0001DA LPCI MG SET 1DA UI RB 621 U/R4 Al 19209-14 VRBOX iDA MG SET IDA VOLTAGE REGULATOR BOX U1 RB 621 S/R2 Al 19210" 14 1-JBOX-268-5987 MG SET IDA CONTROL STATION (1-HS-268-OOOIDA)

UI RB 621 U/R4 Al 19211-20 1-JBOX-268-5948 MG SET IDA CONTROL BOX (RELAYS)

U1 RB 621 U/R4 Al 19212**

13 1-MGEN-268-OOOIEA LPCI MG SET lEA Ut RB 639 U/R5 Al 19213' 14 VRBOX1EA MG SET 1EA VOLTAGE REGULATOR BOX UIRB 621 S/RI Al 19214-14 1-JBOX-268-5989 MG SET I EA CONTROL STATION (1-HS-268-0001 EA)

U1 RB 621 S/R6 Al 19215*'

20 1-JBOX-268-5950 MG SET lEA CONTROL BOX (RELAYS)

U1 RB 639 U/R4 Al 19220 20 1-PROT-099-000AIA RPS CIRCUIT PROTECTOR CABINET

_Al UIRB 593 BATT BD 1 Al 19221 20 1-PROT-099-0001A2 RPS CIRCUIT PROTECTOR CABINET 1A2 U1 RB 593 BATT BD 1 Al 19222 20 1-PROT-099-OOOB1A RPS CIRCUIT PROTECTOR CABINET iBI Ut RB 593 BATT BD 1 Al 19223 20 1-PROT-099-0001B2 RPS CIRCUIT PROTECTOR CABINET 1B2 Ut RB 593 BATT BD 1 Al 19224 20 1-PROT-099-OOOIC1 RPS CIRCUIT PROTECTOR CABINET IC1 U1 RB 593 BATT BD I Al APPENDIX B FACLTY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-22 MB A

EQUIENT t.D.DILDING ROOM S

19225 20 1-PROT-099-0001C2 RPS CIRCUIT PROTECTOR CABINET 1C2 U1 RB 593 BATT BD 1 Al 19226 18 1-LPNL-925-247A LOCAL PANEL 1-25-247A (CAD DRYWELL & SUPP. CHAMB. V.)

Ul RB 621 O/R4 Al 19227 01 1-BDBB-265-0001B 480V RB VENT BD lB Ul RB 565 U/R4 Al 19228 20 1-PNLA-009-0036A PANEL 1-9-36A U1 CB 593 U1 AIR Al 19229 18 1-LPNL-925-0247B LOCAL PANEL 1-25-247B (CAD N2 SUPPLY PANEL B)

U1 RB 621 O/R4 Al 19230 18 1-LPNL-925-0007A LOCAL PANEL 125-7A U1 RB 541 SW CORNER Al 19231 18 1-LPNL-925-0007B LOCAL PANEL 1*25-7B U1 RB 541 SW CORNER Al 19232 14 1-HS-74-101B HANDSWITCH FOR 1-FCV-74*101 (11055)

U1 RB 565 T/R6 Al 19239 18 1-TS-64-68 HANDSWITCH FOR 1-CLR-67-917 (14001)

Ul RB 541 SW CORNER Al 19240 18 1-HS-64-69 HANDSWITCH FOR 1-CLR-67-918 (14013)

U1 RB 541 SE CORNER Al 19241 18 1-TS-64-70 HANDSWITCH FOR 1-CLR-67-921 (14003)

U1 RB 541 SW CORNER Al 19242 18 1-HS-64-71 HANDSWITCH FOR 1-CLR-67-922 (14015)

U1 RB 541 SE CORNER Al 19243 14 1-HS-69-2B HANDSWITCH FOR 1-FCV-69-2 (13033)

U1 RB 593 R5/S Al 19244 14 1-HS-71-18B HANDSWITCH FOR 1-FCV-71-18 (13039)

UI RB 519 NW CORNER I

19245 01 1-HS-71-2B HANDSWITCH FOR 1-FCV-71-2 (13037)

U1 RB 593 R/R1 Al 19246 14 1-HS-73-27 HANDSWITCH FOR 1-FCV-73-27 (13043)

UI RB 519 HPCI I

19247 18 1-HS-73-3B HANDSWITCH FOR 1-FCV-73.3 (13041)

Ul RB 551 TORUS Al 19248 18 1-HS-73-81B HANDSWITCH FOR 1-FCV-73 81 (13042)

Ut RB 551 TORUS Al 19249 14 2-HS-74-IOOB HANDSWITCH FOR 2-FCV-74 100 (11010)

U21RB 565 T/R8 Al 19250 14 1-HS-74-12B HANDSWITCH FOR 1-FCV-74-12 (11011)

U1 RB 519 SW CORNER Al 19251 14 1-HS-74-13B HANDSWITCH FOR 1-FCV-74-13 (11012)

U1 RB 541 SW CORNER Al 19252 14 1-HS-74-1B HANDSWITCH FOR 1-FCV-74-1 (11001)

U1 RB 519 SW CORNER Al 19253 14 1-HS-74-24B HANDSWITCH FOR 1-FCV-74-24 (11029)

UI RB 519 SE CORNER Al 19254 14 1-HS-74-25B HANDSWITCH FOR 1-FCV-74-25 (11030)

UI RB 541 SE CORNER Al 19255 14 1-HS-74-2B HANDSWITCH FOR 1-FCV-74-2 (11002)

U1 RB 541 SW CORNER Al 19256 14 1-HS-74-35B HANDSWITCH FOR 1-FCV-74-35 (11037)

U1 RB 519 SE CORNER Al 19257 14 1-HS-74-36B HANDSWITCH FOR 1-FCV-74-36 (11038)

Ut RB 541 SE CORNER Al 19258 18 1-HS-74-73B HANDSWITCH FOR 1-FCV-74-73 (11046)

UI RB 551 TORUS Al 19259

• 14 2-HS-74-97B HANDSWITCH FOR 2-FCV-74-97 (11013)

U2 RB 519 SW CORNER Al 19260 18 1-HS-75-11B HANDSWITCH FOR 1-FCV-75-11 (15006)

U 1RB 519 NW CORNER Al 19261 14 1-HS-75-22B HANDSWITCH FOR 1-FCV-75-22 (15010)

Ut RB 541 NW CORNER Al 19262 18 1-HS-75-23B HANDSWITCH FOR 1.FCV-75-23 (15012)

UI RB 593 P/R4 Al APPENDIXB AP XFACILY RISK CONSULTANrs INC.

TVANBFN-01-R-004 Revision 0 September 23, 2004 Page B-23 DESCUIPMENT-.-

.1.... 1SSUE_::TRAIN NUMBER f BCL SE N

R I

TRAIN 19263 18 1 HS-75-2B HANDSWITCH FOR 1-FCV-75-2

_1S001)

JS RB 519 NW CORNER Al 19264 18 1-HS-75-30B HANDSWITCH FOR 1-FCV-75-30 (15015)

U RB 519 NE CORNER Al 19265 18 1-HS-75-39B HANDSWITCH FOR 1-FCV-75-39 (15020)

UI RB 519 NE CORNER Al 19266 14 1-HS-75-50B HANDSWITCH FOR 1-FCV-75-50 (15024)

U1 RB 541 NE CORNER Al 19267 18 1-HS-75-51B HANDSWITCH FOR 1-FCV-75-51 (15026)

U1 RB 593 NP/R4 Al 19268 14 1-HS-78-61B HANDSWITCH FOR 1-FCV-78-61 (11026)

U1 RB 621 R5/S Al 19269 14 1-HS-64-72 HANDSWITCH FOR 1-CLR-67-919 (14002)

U RB 541 NW CORNER Al 19270 14 1-HS-64-73 HANDSWITCH FOR 1-CLR-67-920 (14014)

UI RB 541 NE CORNER Al 19271 18 1-TS-64-68 TEMPERATURE SWITCH FOR 1-CLR-67-917 (14001)

U1 RB 519 SW CORNER Al 19272 18 1-TS-64-69 TEMPERATURESWITCH FOR 1-CLR-67-918 (14013)

U1 RB 519 SECORNER Al 19273 18 1-TS-64-70 TEMPERATURE SWITCH FOR 1-CLR-67-921 (14003)

U RB 519 SW CORNER Al 19274 18 1-TS-64-71 TEMPERATURE SWITCH FOR 1-CLR-67-922 (14015)

U 1RB 519 SE CORNER Al 19275 18 1-TS-1-17A MAIN STEAM VAULT TEMPERATURE SWITCH U1 RB 565 MSVLT NIT3 Al 19276 18 1-TS-1-17B MAIN STEAM VAULT TEMPERATURE SWITCH U RB 565 MSVLT NJT3 Al 19277 18 1_TS-1-17C MAIN STEAM VAULT TEMPERATURE SWITCH URB 565 MSVLT NT3 Al 19278 18 1-TS-1-17D MAIN STEAM VAULT TEMPERATURE SWITCH U1 RB 565 MSVLT N1T3 Al 19279 18 1-TS-1-29A MAIN STEAM TUNNEL TEMPERATURE SWITCH Ut TB 565 MSTNL KNT3 Al 19280 18 1-TS-1-29B MAIN STEAM TUNNELTEMPERATURE SWITCH U TB 565 MSTNL K/T3 Al 19281 18 1-TS-1-29C MAIN STEAM TUNNEL TEMPERATURE SWITCH U1TB 565 MSTNL K/T3 Al 19282 18 1-TS-1-29D MAIN STEAM TUNNEL TEMPERATURE SWITCH U1 TB 565 MSTNL KtT3 Al 19283 1 8 1-TS-1-40A MAIN STEAM, TUNNEL TEMPERATURE SWITCH U TB 586 MSTNLKT3 Al 19284 18 1-TS-1-40B MAIN STEAM TUNNEL TEMPERATURE SWITCH U1 TB 586 MSTNL KWT3 Al 19285 18 1-TS-1-40C MAIN STEAM TUNNEL TEMPERATURE SWITCH Ut TB 586 MSTNL KT3 Al 19286 18.-

TS-1-40D MAIN STEAM TUNNEL.TEMPERATURE SWITCH IJTB 586 MSTNLK/T3 Al 19287 18 1-TS-1-54A MAIN STEAM TUNNEL TEMPERATURE SWITCH Ut TB 586 MSTNL KPT3 Al 19288 18 1-TS-1-54B MAIN STEAM TUNNEL TEMPERATURE SWITCH U1 TB 586 MSTNL K/T3 Al 19289 18 1-TS-1-54C MAIN STEAM TUNNEL TEMPERATURE SWITCH U1 TB 586 MSTNL KT3 Al 19290 18 1-TS-1-54D MAIN STEAM TUNNELTEMPERATURE SWITCH U TB 586 MSTNL KWT3 Al 19291 18 1-TS-64-72 TEMPERATURESWITCH FOR t-CLR-67-919(14002)

Ut RB 519 NW CORNER Al 19292 18 1-TS-64-73 TEMPERATURE SWITCH FOR 1-CLR-67-920 (14014)

U1 RB 519 NE CORNER Al 19293-14 2-HS-74-96B HAND SWITCH FOR 2-FCV-74-96 (11003)

RB 519 SW CORNER Al 19294 00 1-AMP-092-0007/41A IRM CH. 'A' VOLTAGE PREAMPLIFIER 7-34A RB 565 S/R3 Al APPENDIX B FACtLTY RISK CONSULTANTS, INC.

II

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-24 NUMBERP cLASSj.

EQJIPMENT [

I I

ROM l

TR 19295 00 I-AMP-092-0007/41B IRM OH. '8' VOLTAGE PREAMPLIFIER 7-34B RB 565 S/R3 Al 19296 14 1-LPNL-925-0027 PANEL 1-25-27 IRM PREAMP. RPS I RB 565 S/R3 Al 19297 00 1-AMP-092-0007/41C IRM CH. 'C' VOLTAGE PREAMPLIFIER 7-34C RB 577 O/RS Al 19298 00 l-AMP-092-0007/41D IRM CH. 'D' VOLTAGE PREAMPLIFIER 7-34D RB 577 O/R5 Al 19299 14 1-LPNL-925-0061 PANEL 1-25-01 IRM PREAMP. RPS 11 RB 577 OIRS Al 19300 20

_-NM-92-7/41A CHANNEL'A'IRM INDICATOR CB 617 UlMCR Al 19301 20 1-NM-92-7/41B CHANNEL 'A' IRM INDICATOR CB 617 U1 MCR Al 19302 20 1-NM-92-7/41C CHANNEL 'C' IRM INDICATOR CB 617 U1 MCR Al 19303 20 1-NM-92-7/41D CHANNEL 'C' IRM INDICATOR CB 617 U1 MCR Al 19304 20 1-PNLA-009-012 PANEL 1-9-12 CB 617 U1 MCR Al 19305 15 1-BATD-283-OOOA1 24V NEUTRON MONITORING BATTERY, UL1 CHANNELA CB 593 BAT RM 1 Al 19306 15 1-BATD-283-OOOB1 24V NEUTRON MONITORING BATTERY, U1 CHANNEL B CB 593 BAT RM 1 Al 19307 16 1-CHGD-283-A1-1 24V NEUTRON BATTERY CHARGERS A1-1 CB 593 BAT BD RM I Al 19308 16 1-CHGD-283-A2-1 24V NEUTRON BATTERY CHARGERS A2-1 CB 593 BAT BD RM 1 Al 19309 16 1-CHGD-283-B1-1 24V NEUTRON BATTERY CHARGERS B1-1 CB 593 BAT B RM 1 Al 19310 16 1-CHGD-283-B2-1 24V NEUTRON BATTERY CHARGERS 82-1 CB 593 BAT BD RM 1 Al 19312 14 1-HS-71-17B HANDSWITCH FOR 1-FCV-71-17 (13074)

U1 RB 519 NW CORNER Al 19313 20 1-HS-1-56A HANDSWITCH FOR 1TFCV-1-56 (13075)

Ul CB 617 U1 MCR Al 19314 14 1-HS-73-26B HANDSWITCH FOR 1-FCV-73-26 (13076)

U1 RB 519 SW CORNER Al 19316 20 1-HS-77-2A HANDSWITCH FOR 1-FCV-77-2A (13080)

Ut CB 617 U1 MCR Al 19317 20 1-HS-77-15A HANDSWITCH FOR FCV-77-I5A (13081)

UIOB 617 lMCR Al 19318 20 1-HS-64-18 HANDSWITCH FOR 1-FCV-64-18 (13082)

U1 CB 617 U1 MCR Al 19319 20 1-HS-64-19 HANDSWITCH FOR 1-FCV-64-19 (13083)

U1 CB 617 U1 MCR Al 19320 20 1-HS-76-18 HANDSWITCH FOR 1-FCV-76-18 (13084)

U1 CB 617 U1 MCR Al 19321 20 1-HS-76-19 HANDSWITCH FOR 1-FCV*76-19 (13085)

Ut CB 617 U1 MCR Al 19323 14 1-JB-0375 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 519 SE CORNER Al 19324 14 1-JB-0662 JUNCTION BOX (TERM BLOCK) - SEALED BOX Ut RB 541 SE CORNER Al 19325 14 1-JB-0658 JUNCTION BOX (TERM BLOCK) -SEALED BOX Ul RB 541 SE CORNER Al 19326 14 1-JB-1032 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 593 S/R3 Al 19327 14 1-JB-1095 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 565 S/R6 Al 19328 14 1-JB-1559 JUNCTION BOX (TERM BLOCK) - SEALED BOX UI RB 565 T/R6 Al 19329 14 1-JB-0670 JUNCTION BOX (TERM BLOCK) -SEALED BOX Ut RB 541 NECORNER Al APPENDIX B FACILiTY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-25 NUMBER: lCI

Eaul EOUIP ENT

II.....N.

JEL 1 J ROOM:

ISUE

TRAIN, I

..I...........

19330 14 1-JB-0791 JUNCTION eox(TERM BLOCK)-SEALED BOX Ut RB 519 NW CORNER Al 19331 14 1-JB-0681 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 541 NW CORNER Al 19332 14 1-CSJ75-9B CONTROL STATION FOR 1BHS 75-9B U1 RB 519 NW CORNER Al 19333 14 1-CS-75-37B CONTROL STATION FOR 1 HS-75-37B U1 RB 519 NE CORNER Al 19334 14 1-JB-1231 JUNCTION BOX(TERM BLOCK) - SEALED BOX U1 RB 565 SIR6 Al 19351 14 1-JB-3828 JUNCTION BOX FOR 1-TS-1-29A Ut RB 565 IMSTNLK/T3 Al 19352 14 1-JB-3829 JUNCTION BOX FOR 1-TS-1-29B U1 RB 565 MSTNL K/T3 Al 19353 14 1-JB-3830 JUNCTION BOX FOR 1-TS-1-29C U1 RB 565 MSTNL KIT3 Al 19354 14 1-JB-3831 JUNCTION BOX FOR 1-TS-1-29D U1 RB 565 MSTNL KIT3 Al 19355 14 1-JB-3801 JUNCTION BOX FOR 1-TS-1-40A U1 RB 586 MSTNL KtT3 Al 19356 14 1-JB-3802 JUNCTION BOX FOR 1-TS-1-40B U1 RB 586 MSTNL K/T3 Al 19357 14 1-JB-3803 JUNCTION BOX FOR 1-TS-1-40C U1 RB 586 MSTNL K/T3 Al 19358 14 1-JB-3804 JUNCTION BOX FOR 1-TS-1-40D Ut RB 586 MSTNL KT3 Al 19359 14 1-JB-3813 JUNCTION BOX FOR 1-TS-1-54A UI RB 586 MSTNL KfT3 Al 19360 14 1-JB-3814 JUNCTION BOX FOR 1-TS-1-54B Ut RB 586 MSTNL K/T3 Al 19361 14 1-JB-3815 JUNCTION BOX FOR 1-TS-1-54C Ut RB 586 MSTNL KIT3 Al 19362 14 1-JB-3816 JUNCTION BOX FOR 1-TS-1-54D U1 RB 586 MSTNL K/T3 Al 19404 04 0-OXF-219-TDA 4KV/480V XFMR TDA U1/2 D0 583 T/R1 Al IA 19405

• 04 0-OXF-219-TDB 4KV/480V XFMRTDB UI/2 DO 583 P/R1 Al IID 19412 03 0-BDM-2110000A 4KV SHDN BD A Ut RB 621 R/R2 Al IA 19413 03 0-BDAA-211-OOOOB_ 4KV SHDN BD B UI RB 593 0/R2 Al IB 19414*

03 0-BDAA-211-0000C 4KV SHDN BD C U2RB 621 RtR13 Al IIC 19415*

03 0-BDAAM211-OOOOD 4KV SHDN BD D U2 RB 593 OIR13 Al IID 19418 02 1 BDBB-231-0001A 480V SHDN BD lA U1 RB 621 S/RI Al 19419 02 1-BDBB-231-OOO1B 480VSHDNBD 1B U1 RB 621 S/R2 Al II 19423 01 1-BDBB-268-OOO1A 480V RMOV BD IA Ul RB 621 R/R1 Al 19424 01 1-BDBB-268-0001B 480V RMOV rD 1B Ut RB 593 RJR1 Al II 19431.

01 0-BDBB-219-OOOOA 48_OSLAUXBDA U1/2 DO 583 480V AUX BD Al 19432

• 01 0-BDBB-219-OOOOB 480V DSL AUX BD B U1/2 DG 583 480V AUX BD Al 19437 1 14 0-BDBD-280-0001 250V BATTERY BD 1 Ul RB 593 P/R4 Al 19438 1 14 0-BDDD-280-0002 250V BATTERY BD 2 U2 RB 593 P/RIO Al 19439

• 14 0-BDDD 280-0003 250V BATTERY BD 3 U3RB 593 PIR18 Al APPENDIX B FACILITy RtSK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-26 I

A_

_S U

E '.__

NUBE A EOUIPMENT 10.

DESCRIPTION.:

BULIN LV.

OM SE TRIN1 NUM1 ER C 20SS NLE 0

PANE 0927

.2CB 617

2C A.E 194512 20 0-PNLA-009-0023/7 PANEL 0-9-23-7 U2CB 617 U2 MCR Al 19452

• 20 0-PNLA-009-0023/8 PANEL 0-9-23-8 U2 CB 617 U2 MCR Al 19457-20 0-PNLA-009-0028 PANEL29-28 U2 CB 593 U2 AIR Al 19476-20 0-LPNL-925-0041A PANEL25-41A U1/2 DG 583 NORTH END Al 194778-20 0-LPNL-925-0041B PANEL25-41B U1/2 DO 583 NORTH END Al 194789 20 0-LPNL-925-0041C PANEL 25-410 U1/2 DG 583 NORTH END Al 19479

• 20 0-LPNL-925-0041D PANEL25-41D U112BD 583 NORTH END Al 194801 20 0-LPNL-925-0042A1 PANEL 25-42A1 U2RB 621 R/RI4 Al 194812 20 0-LPNL-925-0042A2 PANEL 25-42A2 U2RB 621 P/R14 Al 194823 20 0-LPNL-925-0042B1 PANEL 25-4213 U2RB 621 O/R14 Al 194834 20 0-LPNL-925-0042B2 PANEL 25-4Z23 U2 RB 621 H/Rl4 Al 19484

• 20 0-LPNL-925-0043A1 PANEL 25-43A1 U112 DO 583 HALLWAY Al 194856 20 0-LPNL-925-0043A2 PANEL 25-43A2 U1/2DG 583 HALLWAY Al 194867 20 0-LPNL-925-0043B1 PANEL 25-438 U11/2DG 583 HALLWAY Al 19487' 20 0-LPNL-925-0043B2 PANEL 25-43B32 U112 DG 583 HALLWAY Al 19492 20 0-LPNL-925-0045A PANEL 25-45A U_ RB 621 R/R2 Al 19493 20 0-LPNL-925-0045B PANEL 25-45B U1 RB 593 R/R2 Al 19494-20 0-LPNL-925-0045C PANEL 25-45C U2RB 621 R/R13 Al 19495-20 0-LPNL-925-0045D PANEL 25-45[)

U2RB 593

/RIR3 Al 19496' 20 0-LPNL-925-0046A PANEL 25-46A U1/2DO 565 DGA Al 19497 -

20 0-LPNL-925-0046B PANEL 25-469 U112 DG 565 DG B Al 19498 -

20 0-LPNL-925-0046C PANEL 25-46C U11/2 DG 565 DG C Al 19499*

20 0-LPNL-925-0046D PANEL 25-467 U1/2 DG 565 DG D Al 19500*

20 O-LPNL-925-0047A PANEL 0-25-47A U112 DG 565 DG A Al 19501 20 0-LPNL-925-0047B PANEL 0-25-47B ULI2DG 565 DG B Al 19502*

20 0-LPNL-925-0047C PANEL 0-25-"7C U1/2 DG 565 DG C Al 19503*

20 0-LPNL-925-0047D PANEL 0-25-47D U1/2 DG 565 DG D Al 19508 20 PNLA-082-OOOOA DG A ELECTRICAL CONTROL CABINET U_/2 DG 565 DGA Al 19509*

20 0-PNLA-082-OOOOA DGB ELECTRICAL CONTROL CABINET U1/2 DG 565 DG A Al 19510 -

20 0-PNLA-082-OOOOC DG C ELECTRICALCONTROL CABINET U1/2 DG 565 DG C Al 19511 -

20 0-PNLA-082-OOOOD DOG D ELECTRICALCONTROL CABINET U11/2 DO 565 DOG Al 19516 14 O-XSW-248-0001 250V MAIN BATT CHGR OUTPUT XFR SW 1 Ul RB 593 P/R4 Al APPENDIX B FACILTY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-27

_cA~

NUMBEREQUIPMENTI1.D0:.

DESCRIPTION BIDING, ELE 1I.. SSUE: :TRAIN' 19517

• 14 o-XSW-248-0002A 250V MAIN BATT CHGR OUTPUT XFR SW 2A U2 RB 593 PIR9 Al 19518' 14 o-XSW-248-0003 2SOV MAIN BATT CHGR OUTPUT XFR SW 3 U3 RB 593 P/R16 Al 19519 15 o-BATA-248-OOOOA 250V BATTERY SB-A Ul RB 621 S/R2 Al IA 19520 14 o-PNLA-248-A 250V DISTRIBUTION PANEL SB-A Ul RB 621 S/R2 Al IA 19521 16 o-CHGA-248-OOOOA 250V BATTERY CHARGER SB-A U1 RB 621 S/R2 Al IA 19522 15 o-BATA-248-OOOOB 250V BATTERY SB-B Ul RB 621 R/R2 Al lB 19523 14 o-PNLA-248sB 250V DISTRIBUTION PANEL SB-B U1 RB 621 R/R2 Al lB 19524 16 o-CHGA-248-OOooB 250V BATTERY CHARGER SB-B Ul RB 621 RIR2 Al lB 19525 15 o-BATA-248-OOOOC 250V BATTERY SB-C U2 RB 621 S/R13 Al tIC 19526

• 14 o-PNLA-248-OOOOC 250V DISTRIEUTION PANEL SB-C U2 RB 621 S/R13 Al 1ic 19527

• 16 o-CHGA-248-OOOOC 250V BATTERY CHARGER SB-C U2 RB 621 S/R13 Al

]IC 19528*

15 o-BATA-248-oOOD 2SOV BATTERY SB-D U2 RB 621 S/R13 Al lID 19529-14 o-PNLA-248-OOOOD 250V DISTRIBUTION PANEL SB-D U2 RB 621 S/R13 Al III 19530

• 16 o-CHGA-248-COOOD 250V BATTERY CHARGER SB-D U2 RB 621 S/R13 Al IID 19534 16 o-CHGA-248-0001 250V BATTERY CHARGER 1 Ut RB 593 P/R4 Al 19535

• 16 o-CHGA-248-0002A 250V BATTER1Y CHARGER 2A U2 RB 593 PIR9 Al 19536-16 o-CHGA-248-0003 250V BATTERY CHARGER 3 U3 RB 593 P/R18 Al 19537 15 o-BATA-248-0001 250V MAIN BATTERY 1 U1 RB 593 P/R4 Al 19538 -

15 o-BATA-248-0002 2soV MAIN BATTERY 2 U2 RB 593 PIR9 Al 19539

• 15 O-BATA-248-0003 250V MAIN BATTERY 3 U3 RB 593 P/R18 Al 19542 -

15 o-BATB-254-OOOOA 125V DC DSL BATT A UI/2 DG 565 DGA Al IA 19543*

15 o-BATB-254-OOOOB 125V DC DSL BATT B U1/2 DG 565 DG B Al IB 19544

• 15 o-BATB-254-OOOOC 125V DC DSL BATT C U1/2 DG 565 DOG C

Al 11C 19545

• 15 o-BATB-254-OOOOD 125V DC DSL BATT D U1/2 DG 565 DG D Al lID 19546

• 14 0-BDGG-254-OOOOA 125V DC DSL BATT BD A U1/2 DG 565 DGA Al IA 19547

• 14 O-BODGG-254-OOOoB 125V DC DSL BATT BD B U1/2 DG 565 DO B Al IB 19548

• 14 o-BDGG-254-OOOOC 125V DC DSL BATT BO C UI/2 DG 565 DG C Al IIC 19549

• 14 o-BDGG-254 OOOOD 125V DC DSL BATT 0D D UI/2 DG 565 DG D Al 110 19550

• 16 o-CHGB-254-OOOOAA 125V DSL GEN A BATT CHGR A U1/2 DG 565 DG A Al I

19551

• 16 o-CHGB-254-OOOOBA 125V DSL GEN B BATT CHGR A U1/2 DG 565 DG B Al I

19552

• 16 o-CHGB-254-OOOOCB 125V DSL GEN C BATT CHGR B UI/2 DG 565 OG C Al II 19553

• 16 o-CHGB-254-ooooDB 125V DSL GEN D BATT CHGR B U1/2 OG 565 DO D Al 1I APPENDIX B FACLITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-28 SSEL I I

NUMBER ICLASSl EQUIPMENT LD.:

DESCRIPTION BUILDING ELEV. [

ROOM

[ISSUE TRAIN 19560 04 0-XFA-082-OO0AA DG-A NEUTRAL GRN XFMR DGB 1/2 565 DG - A Al 19561 04 0-XFA-082-OO0BA DG-B NEUTRAL GRN XFMR DGB 112 565 DG - B Al 19562' 04 0-XFA-082-000CA DG-C NEUTRAL GRN XFMR DGB 1/2 565 DG - C Al 19563' 04 0-XFA-082-OOODA DG-D NEUTRAL GRN XFMR DGB 1/2 565 DG. D Al 19594 04 1-XFA-231-TS1A 4KV/480V TRANSFORMER TS1A Ul RB 621 TIR1 Al I

19595 04 1-XFA-231 -TS1 B 4KV/480V TRANSFORMER TS I B U1 RB 621 S/R7 Al 11 19643

• 18 0-HS-23-5B LOCAL HS STATION. RHRSW PUMP A2 INTAKE 565 A

Al I

19644 18 0-HS-23-85B LOCAL HS STATION. RHRSW PUMP A3 INTAKE 565 A

Al I

196454 18 0-HS-23-19B LOCAL HS STATION - RHRSW PUMP B2 INTAKE 565 B

Al II 19646 18 0-HS-23-88B LOCAL HS STATION - RHRSW PUMP B3 INTAKE 565 B

Al II 196476 18 0-HS-23-12B LOCAL HS STATION - RHRSW PUMP C2 INTAKE 565 C

Al I

19648 18 0-HS-23-91B LOCAL HS STATION-RHRSW PUMP C3 INTAKE 565 C

Al I

19649 7

18 0-HS-23-27B LOCAL HS STATION - RHRSW PUMP 02 INTAKE 565 C

Al tI 19650 18 0-HS-23-94B LOCAL HS STATION-RHRSW PUMP 03 INTAKE 565 0

Al

[10 196554 14 0-JBOX-30-0640 JUNCTION BOX (TERM BLOCK)

UI2ADG 583 FAN RM Al I

19656 18 0-HS-30-64 LOCAL HS STATION-DG A EXH FAN A U1/2 DO 583 ELEC BD A Al I

196575 14 0-JBOX-30-1817 JUNCTION BOX (TERM BLOCK)

U1/2 DG 583 FAN RM A Al II 19658 6 18 0-HS-30-65 LOCAL HS STATION - DOG A EXH FAN B U1/2 DG 583 ELEC BD A Al II 196597 14 0-JBOX-30-1825 JUNCTION BOX (TERM BLOCK)

U1/2 DG 583 FAN RM B Al I

19660 18 0-HS-30-66 LOCAL HS STATION - DG B EXH FAN A U1/2 DG 583 ELEC BD A Al I

19661 14 0-JBOX-30-1826 JUNCTION BOX (TERM BLOCK)

U1/2 DG 583 FAN RM B Al II 196620 18 0-HS-30-67 LOCAL HS STATION - DOG B EXH FAN B U1/2 DG 583 ELEC BD A Al II 196631 14 0-JBOX-30-1828 JUNCTION BOX (TERM BLOCK)

U1/2 D0 583 FAN RM C Al I

19664

• 18 0-HS-30-69 LOCAL HS STATION - DOG C EXH FAN B U11/2 DG 583 ELEC BD B Al 1

19665 14 0-JBOX-30-1827 JUNCTION BOX (TERM BLOCK)

U1/2 DG 583 FAN RM C Al II 19666

• 18 0-HS-30-68 LOCAL HS STATION - DOG C EXH FAN A UI/2 DG 583 ELEC BO B Al II 196675 14 W-JBOX-30-1830 JUNCTION BOX (TERM BLOCK)

U1/2 DG 583 FAN RM C Al I

19668 18 0-HS.30-71 LOCAL HS STATION - DOG EXH FAN B U1/2 DG 583 ELEC BD B Al 19669 14 0-JBOX-30-1829 JUNCTION BOX (TERM BLOCK)

U1/2 DG 583 FAN RM D Al I

19670 18 0-HS-30-70 LOCAL HS STATION - DG D EXH FAN A U1/2 DG 583 ELEC BD B Al 1I 19691 20 0-ECAB-067-0925 EECW PUMP DISCHARGE STRAINER A CONTROL PANEL INTAKE 565 A

Al 19692 20 0-ECAB-067-0926 EECW PUMP DISCHARGE STRAINER B CONTROL PANEL INTAKE 565 B

Al APPENDIX B FACILITY RISK CONSULTANTS INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-29 SSEL NUMBER CLS'I DESCRIPTION BUI LDI NG ELEV.'

RO ISSUjETRN NMECLSS E

E OU IP M E N T 'ID

l E C I T O,'..

B U I L D I N G E L E V,

R [OM

_ I S S U E

_T R

A I N

19.693

_20 0.ECAB-0.7-.927_EECW PUMP DISCHARGE.STRAINER.C.CONTROL PANEL IN.A.E.

565.C

.A.._.....

19693 4

20 0-ECAB-067-0927 EECW PUMP DISCHARGE STRAINER C CONTROL PANEL INTAKE 565 D

Al 19694 '

20 0-ECAB-067 0928 EECW PUMP DISCHARGE STRAINER D CONTROL PANEL INTAKE 565

.D Al 19703 '

20 0-LPNL-925-0246A PANEL 25-246A (CAD N2 SUPPLY PNL A)

YARD 565 YARD Al 19704

• 20 0-LPNL-925-0246B PANEL 25-246B (CAD N2 SUPPLY PNL B)

YARD 565 YARD Al 19709 20 1-PNLA-009-0020 PANEL 1-9-20 UICB 617 UIMCR Al 19711 '

20 NONE C02 RELAY PNL FOR 39-10 U1/2 DG 565 DG D Al 19712

• 20 NONE C02RELAYPNLFOR39-7 U112 DG 565 DGA Al 19713 '

20 NONE C02 RELAY PNL FOR 39-8 U1/2 DG 565 DG B Al 19714' 20 NONE C02 RELAY PNL FOR 39-9 U1/2 DG 565 DG C Al 19716 18 1-LPNL-925-0223 LOCAL PANEL 1-25-223 - RAW COOLING WATER PANEL Ul RB 593 O/R2 Al 19717' 20 2-PNLA-009-0008 PANEL 2-9-8 U2CB 617 U2 MCR Al 19719 '

18 2-LPNL-925-0223 LOCAL PANEL 2-25-223 U2 RB 593 O/R12 Al 19720

• 18 2-LPNL-925-0007A LOCAL PANEL 2-25-7A U2RB 541 SW CORNER Al 19721 '

18 2-LPNL-925-0007B LOCAL PANEL 2-25-7B U2 RB 541 SW CORNER Al 19722 '

18 0-HS-67-48B HANDSWITCH FOR 0-FCV-67-48 INTAKE 565 D

Al 19723 '

18 0-HS-67-49B HANDSWITCH FOR O-FCV-67-49 INTAKE 565 C

Al 19724 '

18 2-HS-73-81B HANDSWITCH FOR 2-FCV-73-81 U2 RB 519 TORUS Al 19729 14 1-HS-23-57B HANDSWITCH FOR 1-FCV-23-57 UI RB 565 R6/S Al 19791 20 1-PNLA-009-0008 PANEL 1-9-8 U1 CB 617 U1 MCR Al 19792 18 1-LPNL-925-006B LOCAL PANEL 25-6B U1 RB 593 RS5P Al 19794 04 1-XFA-099-0010 RPS REGULATING TRANSFORMER TRP-1 Ut CB 593 BATT BD I Al 19795 14 1-FUDS-099-OOO1CA RPS REG XFMR DISC SW FROM 480 V RMOV BD 1B U1 CB 593 BATT BD I Al 19796 04 TUPI UNIT PREFERRED XFMR U1 CB 593 BATT BD 1 Al 19797 14 1-FUDS-099-OOO1CB RPS BUS XFMR DISC SW U1CB 593 BATT BD 1 Al 19801 14 1-JB-6439 JUNCTION BOX SERVING 1-TE-161A Ut RB 519 TORUS 19802 14 1-JB-6440 JUNCTION BOX SERVING 1-TE-161B U1 RB 519 TORUS 19803 14 1-JB-6441 JUNCTION BOXSERVING 1-TE-161C U1 RB 519 TORUS 19804 14 1-JB-6442 JUNCTION BOX SERVING 1-TE-161D UI RB 519 TORUS 19805 14 1-JB-6443 JUNCTION BOX SERVING 1-TE-161E U1 RB 519 TORUS 19806 14 1-JB-6444 JUNCTION BOX SERVING 1-TE-161F Ut RB 519 TORUS 19807 14 1-JB-6445 JUNCTION BOX SERVING 1-TE-161G Ul RB 519 TORUS 19808 14 1-JB-6446 JUNCTION BOX SERVING 1-TE-161H Ut RB 519 TORUS APPENDIX B FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page B-30 SSEL NUM..

.> S

.. QI N I.D

.DSRPIN........ -.

... :.::-:::-:B NUMBER...

ESCR.PTION

BUILDING: :ELEVI" j ROM ISSUE::7RI 19809 14

-1JB-6453 JUNCTIONBOXSERVING 1-TE.162A Ul RB 519 TORUS l

I 19810 14 1-JB-6454 JUNCTION BOX SERVING 1-TE-162B UA RB 519 TORUS 19811 14 1-JB.6447 JUNCTION BOX SERVING 1-TE-162C U1 RB 519 TORUS 19812 14 1-JB-6448 JUNCTION BOX SERVING 1-TE-162D UI RB 519 TORUS 19813 14 1-JB-6449 JUNCTION BOX SERVING 1-TE-162E UI RB 519 TORUS 19814 14 1-JB-6450 JUNCTION BOX SERVING 1-TE-162F Ul RB 519 TORUS 19815 14 1-JB-6451 JUNCTION BOX SERVING 1-TE-162G Ul RB 519 TORUS 19816 14 1-JB-6452 JUNCTION BOX SERVING 1-TE-162H Ul RB 519 TORUS

• Note that these equipment items are either common to or shared by both Units 1 & 2, are not physically located in Unit 1, and were previously evaluated under the Unit 2 USI A-46 program. These items are included in the Unit 1 Safe Shutdown Equipment List for completeness.

• • DCN 51216, Stages 3 and 4, will remove all four Ul LPCI M/G Sets and associated automatic transfer capability for the 480V RMOV Boards 1 D and 1 E respectively. New cable feeds will be installed directly between the 480V Shutdown Boards 1 A & 1 B and the 480V RMOV Boards 1 D & 1 E replacing the LPCI M/G Set feeds.

APPENDIX B FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page C-1 APPENDIX C SEISMIC REVIEW SSEL FACILITY RISK CQNSULTANTS, INC.

TVABFN-01 -R-004 Revision 0 September 23, 2004 Page C-2 APPENDIX C SEISMIC REVIEW SSEL SSEL jI NUMBER ICLASSj EQUIPMENT I.D.

I DESCRIPTION BUILDING ELEV.

ROOM ISSUE TRAIN 10001 00 1-HCU-85.1-185 CRD/HYDRAULIC CONTROL UNIT U1 RB 565 R2 & R6/P-S Al 1,2 10002 07 1-FCV-85-82A CRD/WEST SDV VENT VALVE U1 RB 565 R2/S Al 1

10003 07 1-FCV.85-82 CRDIWEST SOV VENT VALVE U1 RB 565 R2/S Al 2

10004 07 1-FCV-85-37C CRD/WEST SDV DRAIN VALVE Ul RB 565 R2/P Al 1

10005 07 1-FCV-85-37D CRD/WEST SDV DRAIN VALVE Ut RB 565 R2/P Al 2

10006 07 1-FCV-85-83A CRD/EAST SDV VENT VALVE U1 RB 565 R6/S Al 1

10007 07 1-FCV-85-83 CRD/EAST SDV VENT VALVE Ut RB 565 R6/S Al 2

10008 07 1-FCV-85-37E CRD/EAST SDV DRAIN VALVE U1 RB 565 R6/P Al 1

10009 07 1-FCV-85-37F CRD/EAST SDV DRAIN VALVE U1 RB 565 R6/P Al 2

10010 21 1-TNK-85-901 CRD/WEST SCRAM INSTRUMENT VOLUME U1 RB 565 R2/P Al 1,2 10011 21 1-TNK-85-902 CRD/EAST SCRAM INSTRUMENT VOLUME Ut RB 565 R6/P Al 1,2 10012 08B 1-FSV-85-37A CRD/SCRAM DUMP VALVE U1 RB 565 R5/N Al 1

10013 08B 1-FSV-85-37B CRD/SCRAM DUMP VALVE U1 RB 565 RS/N Al 1

10014 08B 1 FSV-85-35A CRD/BACKUP SCRAM VALVE U1 RB 565 RS/N Al 2

10015 08B 1-FSV-85-35B CRD/BACKUP SCRAM VALVE U1 RB 565 R5/N Al 2

10016 20 1-HS-99-SASIA

.PS/REACTOR MANUAL SCRAM CHANNEL Al Ut CB 617 Ul MCR Al 1

10017 20 1-HS 99-5A/S1B RPS/REACTORMANUALSCRAMCHANNELB1 U1 CB 617 Ut MCR Al 1

10018 20 1-HS-99-5A-S1 RPS/REACTOR MODE SWITCH U1 CB 617 U1 MCR Al 2

10019 8B 1-FSV-85-70A CRD/BACKUP PILOT SCRAM VALVE A' Ut RB 565 R5/N Al 10020 8B 1-FSV-85-70B CR0/ BACKUP PILOT SCRAM VALVE B' Ut RB 565 R5/N Al 10023 8B 1-FSV-85-39A CR0/ISOLATION VALVE U1 RB 565 CRD RACKS Al 10024 88 1-FSV-85-39B CRDIASOLAT:ON VALVE U1 RB 565 CRD RACKS Al 10025 18 1-PI.85-88 PRESSURE INDICATOR Ut RB 565 R6/S Al 10026 18 1.PI*85-89 PRESSURE INDICATOR Ut RB 565 R2/P Al 10027 18 1-PI.85-90 PRESSURE INDICATOR Ut RB 565 R2/P Al 11001 08A 1-FCV-74-1 RHR/PUMP 1A SUCTION VALVE FROM SUPRESSION POOL Ul RB 519 SW CORNER Al 11002 08A 1-FCV-74-2 RHRIPUMP 1A SUCTION VALVE FROM SHUTDOWN COOLING U1 RB 541 SW CORNER Al 1

11004 06 1-PMP-74-5 RHR/PUMP IA U1 RB 519 SW CORNER Al 1

APPENDIX C FACILIy RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September 23, 2004 Page C-3 NUMBER CLASj EQUIPMENT l.0.

DESCRIPTION BUILDING ELEV.

ROOM ISSUE TRAIN 11006 08A 1-FCV-74-7 RHRIPUMP 1A& 10 MINIMUM FLOW VALVE U1 RB 541 SW CORNER Al 1

11009 21 1-HEX-74-900A RHRIHEAT EXCHANGER A U1 RB 565 SW HX Al I

11011 08A 1-FCV-74-12 RHRIPUMP iC SUCTION VALVE FROM SUPRESSION POOL U1 RB 519 SW CORNER Al IA 11012 08A 1-FCV-74-13 RHRIPUMP IC SUCTION VALVE FROM SHUTDOWN COOLING Ul RB 541 SW CORNER Al IA 11014 06 1-PMP-74-16 RHRIPUMP IC U1 RB 519 SW CORNER Al 1A 11017 21 1-HEX-74-900C RHRIHEAT EXCHANGER IC U1 RB 565 SW HX Al IA 11018 20 1*FI-74-50 RHR/LOOP I FLOW INDICATOR U1 CB 617 U1 MCR Al 1

11019 20 1-FI-74-56 RHRILOOP I FLOW INDICATOR U1 CB 617 Ul MCR Al 1

11020 08A 1-FCV-74-57 RHRILOOP I TORUS CONTAINMENT COOLING/SPRAY VALVE Ul RB 551 TORUS Al 1

11021 08A 1-FCV-74-59 RHRILOOP I SUPRESSION POOL COOLING VALVE Ul RB 551 TORUS Al 1

11022 08A 1-FCV-74-58 RHR=LOOPISUPRESSION POOL SPRAY VALVE U1 RB 551 TORUS I

1 11023 08A 1-FCV-74-52 RHRILOOP I OUTBOARD INJECTION VALVE Ut RB 565 R4/T Al 1

11024 08A 1-FCV-74-53 RHRILOOP I INBOARD INJECTION VALVE U1 RB 565 R4/T Al 1

11026 08A 1-FCV-78-61 FPC/SPENT FUEL POOL COOLING X-TIE TO RHR Ul RB 621 RS/S Al 1

11027 08A 1-FCV-74.60 RHRILOOP I OUTBOARD DRYWELL SPRAY VALVE Ul RB 593 R3/S Al 1

11028 08A 1-FCV-74-61 RHR/LOOP I INBOARD DRYWELL SPRAY VALVE Ut RB 593 R3/S I

I 11029 08A 1-FCV-74-24 RHRIPUMP 1B SUCTION VALVE FROM SUPRESSION POOL U1 RB 519 SE CORNER Al 2

11030 08A 1-FCV-74-25 RHRIPUMP 1B SUCTION VALVE FROM SHUTDOWN COOLING U1 RB 541 SECORNER Al 2

11031 06 1-PMP-74-28 RHRIPUMP IB U1 RB 519 SECORNER Al 2

11033 08A 1*FCV-74-30 RHR/PUMP 1B & 1 D MINIMUM FLOW VALVE U1 RB 541 SE CORNER Al 2

11036 21 1-HEX-74-900B RHR/HEAT EXCHANGER 1B U1 RB 565 SE HX Al 2

11037 08A 1-FCV-74-35 RHRIPUMP ID SUCTION VALVE FROM SUPRESSION POOL U1 RB 519 SE CORNER Al 2A 11038 08A 1-FCV-74-36 RHRIPUMP 1D SUCTION VALVE FROM SHUTDOWN COOLING U1 RB 541 SE CORNER Al 2A 11039 06 1-PMP-74-39 RHRIPUMP ID Ut RB 519 SE CORNER Al 2A 11042 21 1-HEX-74-900D RHRIHEAT EXCHANGER ID UIRB 565 SEHX Al 2A 11043 20 1-FI-74-64 RHRILOOP II FLOW INDICATOR U1CB 617 U1MCR Al 2

11044 20 1-FI-74-70 RHR/LOOP 11 FLOW INDICATOR UICIB 617 U1 MCR Al 2

11045 08A 1-FCV-74-71 RHR/LOOP 11 TORUS CONTAINMENT COOLING/SPRAY VALVE U1 RB 551 TORUS Al 2

11046 08A 1-FCV-74-73 RHRILOOP II SUPRESSION POOL COOLING VALVE U1 RB 551 TORUS Al 2

11047 08A 1-FCV-74-72 RHRILOOP ll SUPRESSION POOL SPRAY VALVE U1 RB 551 TORUS I

2 11048 08A 1LFCV-74-66 RHRILOOP 11 OUTBOARD INJECTION VALVE UI RB 565 R5/T Al 2

11049 08A 1-FCV-74.67 RHRILOOP 'I INBOARD INJECTION VALVE U1 RB 565 RS/T Al 2

APPENDIX C AP CFACILITY RISK CONSULTATS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page C-4 SSEL I I

I NUMBER lCLASSl EOUIPMENT l.D.

I DESCRIPTION BUILDING l ELEV.

ROOM__

ISSUE TRAIN 11051 08A 1-FCV-74-74 RHR/LOOP II OUTBOARD DRYWELL SPRAY VALVE Ut RB 565 R51S Al 2

11052 08A l-FCV-74-75 RHRILOOP II INBOARD DRYWELL SPRAY VALVE U1 RB 565 R61S I

2 11053 08A 1-FCV-74-101 RHR/U2 TO U1 RHR DISCHARGE X-TIE ISOLATION VALVE (BOD)

Ul RB 565 R6/T Al 1

12001 07 1-PCV_1-4 MS/MAIN STEAM SAFETY RELIEF VALVE Ul DW 584

_W Al 1

12003 07 1-PCV-1-5 MS/MAIN STEAM SAFETY RELIEF VALVE UI DW 584 DW Al 1

12006 07 1-PCV-1-18 MS/MAIN STEAM SAFETY RELIEF VALVE Ul DW 584 DW Al 1

12009 07 1-PCV-1-19 MS/MAIN STEAM SAFETY RELIEF VALVE U_ DW 584 OW Al 12012 07 1-PCV-1-22 MS/MAIN STEAM SAFETY RELIEF VALVE Ul DW 584 DW Al 1

12015 07 1-PCV-1-23 MS/MAIN STEAM SAFETY RELIEF VALVE U1 DW 584 DW Al 1

12018 07 1-PCV-1-179 MS/MAIN STEAM SAFETY RELIEF VALVE U1 DW 584 DW Al 1

12021 07 1-PCV-1-30 MS/MAIN STEAM SAFETY RELIEF VALVE UI DW 584 DW Al 2

12024 07 1-PCV-1-31 MS/MAIN STEAM SAFETY RELIEF VALVE U1 OW 584 DW Al 2

12027 07 1-PCV-1-34 MS/MAIN STEAM SAFETY RELIEF VALVE Ul DW 584 DW Al 2

12030 07 1-PCV-1-41 MSIMAIN STEAM SAFETY RELIEF VALVE Ul DW 584 DW Al 2

12033 07 1-PCV-1-42 MS/MAIN STEAM SAFETY RELIEF VALVE U1 DW 584 DW Al 2

12036 07 1-PCV-1-180 MS/MAIN STEAM SAFETY RELIEF VALVE U1 DW 584 DW Al 2

13001 07 1-FCV-1-14 MSIV/A INBOARD ISOLATION VALVE Ul DW 563 DW Al 1

13002 07 1-FCV-1-15 MSIV SAOUTBOARD ISOLATION VALVE U1 RB 565 MSIV VAULT Al 2

13003 07 1-FCV-1-26 MSIV ' INBOARD ISOLATION VALVE Ut DW 563 DW Al 1

13004 07 1-FCV-1-27 MSIV ' OUTBOARD ISOLATION VALVE U1 RB 565 MSIV VAULT Al 2

13005 07 1-FCV-1-37 MSIV '

INBOARD ISOLATION VALVE U1 DW 563 DW Al 1

13006 07 1-FCV-1-38 MSIV 'C OUTBOARD ISOLATION VALVE U1 RB 565 MSIV VAULT Al 2

13007 07 1-FCV-1-51 MSIV D INBOARD ISOLATION VALVE U1 DW 563 DW Al I

13008 07 1-FCV-1-52 MSIV D OUTBOARD ISOLATION VALVE U1 RB 565 MSIV VAULT Al 2

13009 08A 1-FCV-1-55 MAIN STEAM LINE DRAIN ISOLATION VALVE Ul DW 563 DW Al 1

13015 07 1-FCV-64-17 CONTAINMENT VENTILATION ISOLATION VALVE U1 RB 565 R3/U I

1,2 13016 07 1-FCV-64-30 CONTAINMENT VENTILATION ISOLATION VALVE Ut RB 621 R3/0 I

1,2 13017 07 1-FCV-64-33 CONTAINMENT VENTILATION ISOLATION VALVE U1 RB 565 R2/P I

1,2 13018 07 1-FCV-64-139 CONTAINMENT DW DP ISOLATION VALVE U1 RB 565 R2/P I

1,2 13019 07 1-FCV-64-140 CONTAINMENT DW DP ISOLATION VALVE Ul RB 565 R2/P I

1,2 13020 07 1-FCV-64-28A SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ul DW

<550 IN TORUS I

12 13021 07 l-FCV-64-28B SUPPRESSION CHAMBERIDRYWELL VACUUM BREAKERS U1 DW

<550 IN TORUS I

12 APPENDIX C FACILrn'RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page C-5 NUMBER CLASS EQUIPMENT I.D.

DESCRIPTION BUILDING ELEV.

ROOM ISSUE TRAIN 13022 07 1-FCV-64-28C SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ut DW

<550 IN TORUS I

1,2 13023 07 1-FCV-64-28D SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ut DW

<550 IN TORUIS 1,2 13024 07 1-FCV-64-28E SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ul oW

<550 IN TORUS I

1,2 13025 07 1-FCV-64-28F SUPPRESSION CHAMBERIDRYWELL VACUUM BREAKERS U1 DW

<550 IN TORUS I

1.2 13026 07 1-FCV-64-28G SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ul DW

<550 INTORUS I

1,2 13027 07 1-FCV-64-28H SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ul DW

<550 IN TORUS I

1,2 13028 07 1-FCV-64-28J SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW

<550 IN TORUS I

1,2 13029 07 t-FCV-64-28K SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ul oW

<550 IN TORUS I

1,2 13030 07 1-FCV-64-28L SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW

<550 IN TORUS I

1.2 13031 07 1-FCV-64-28M SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ul DW

<550 IN TORUS I

1,2 13032 08A 1-FCV-69-1 RWCU INBOARD ISOLATION VALVE U1 DW 584 DW Al 1

13033 08A 1-FCV-69-2 RWCU OUTBOARD ISOLATION VALVE U1 RB 593 RS/S Al 2

13035 08A 1-FCV.70-47 RBCCW DRYWELL RETURN VALVE U1 RB 551 TORUS I

1,2 13037 08A 1-FCV-71-2 RCIC INBOARD ISOLATION VALVE Ul DW 584 DW Al 1

13038 08A 1-FCV-71-3 RCIC OUTBOARD ISOLATION VALVE U1 RB 565 MSIV VAULT Al 2

13039 08A 1-FCV-71-18 RCIC OUTBOARD SUCTION VALVE U1 RB 519 NW CORNER I

1,2 13040 08A 1-FCV-73-2 HPCI STEAM SUPPLY ISOLATION VALVE Ul DW 563 DW Al 1

13041 08A 1-FCV-73-3 HPCI STEAM SUPPLY ISOLATION VALVE U_ RB 551 TORUS Al 2

13042 08A 1-FCV-73-81 HPCI STEAM SUPPLY ISOLATION BYPASS VALVE U1 RB 551 TORUS Al 2

13043 08A 1-FCV-73-27 HPCI OUTBOARD SUCTION VALVE U1 RB 519 HPCI ROOM I

1,2 13044 07 1-FCV-75-57 PSC PUMP SUCTION ISOLATION VALVE Ul RB 519 NW CORNER Al I

13045 07 1-FCV-75-58 PSC PUMP FUCTION ISOLATION VALVE U1 RB 519 NW CORNER Al 2

13046 07 1-FCV-76-24 PRIMARY CONTAINMENT ISOLATION VALVE U1 RB 565 R3/U I

1,2 13047 07 1-FCV-77-2B DRYWELL FLOOR DRAIN SUMP DISCHARGE U1 RB 551 TORUS I

1,2 13048 07 1-FCV-77-15B DRYWELL EQUIPMENT DRAIN SUMP DISCHARGE U1 RB 551 TORUS I

1,2 13049 07 1-FCV-84-19 CAD ISOLAT:ON VALVE Ul RB 621 R310 1

1,2 13050 07 1-FCV-84-20 CAD ISOLATION VALVE U1 RB 621 R3/Q I

1,2 13051 20 1-LI-3-58AA RPV LEVEL.NSTRUMENTATION U1 RB 617 U1 MCR Al 1

13052 20 1-LI-3-58BB RPV LEVEL INISTRUMENTATION U1 RB 617 U1 MCR Al 2

13053 20 1-PI-3-74A RPV PRESSURE INSTRUMENT U1 CB 617 U1 MCR Al 1

13054 20 1-PI-3-74B RPV PRESSURE INSTRUMENT U1 CB 617 U1 MCR Al 2

13055 20 1-XR-64-159 TORUS LEVEL AND DRYWELL PRESSURE INSTRUMENT U1 CB 617 U1 MCR Al 1

APPENDIX C AFACILTYRtSK CONSULTANTS, INC.

TVAJBFN-01 -R-004 Revision 0 September 23, 2004 Page C-6 SSEL

-I NUMBER lCLASSI EQUIPMENT I.D.

I DESCRIPTION B BUILDING ELEV.

ROOM ISSUE l TRAIN 13056 20 1-LI-64-159A TORUS LEVEL INSTRUMENT U1 CB 617 U1 MCR Al 2

13057 20 1-TI-64-161 TORUS TEMPERATURE INSTRUMENT Ul CB 617 U1 MCR Al 1

13058 20 1-TI-64-162 TORUS TEMPERATURE INSTRUMENT U1 CB 617 U1 MCR Al 2

13059 20 1-PI.64-67 DRYWELL PRESSURE INSTRUMENT U1 CB 617 U1 MCR I

1 13060 20 1-PI-64-160A DRYWELL PRESSURE INSTRUMENT U1 CB 617 Ul MCR I

2 13061 20 1-TI-64-52A DRYWELL TEMPERATURE INSTRUMENT U1 CB 617 U1 MCR I

1 13062 20 1-XR-64-50 DRYWELL TEMPERATURE AND PRESSURE INSTRUMENT U1 CB 617 Ul MCR I

2 13063 07 1.FCV-76-17 CONTAINMENT INERTING N2 MAKEUP U1 AB 565 R5/T I

1,2 13064 07 1-FCV-64-222 HARDENED WETWELL VENT U1 RB 565 R3/T I

1,2 13069 08A 1-FCV-71-40 PRIMARY CONTAINMENT ISOLATION VALVE U1 RB 565 R4/P Al 13074 08A 1-FCV-71-17 RCIC INBOARD SUCTION VALVE U1 RB 519 NW CORNER j

1,2 13075 08A 1-FCV-1-56 MAIN STEAM LINE DRAIN ISOLATION VALVE U1 RB 565 MSIV VAULT?

Al 13076 08A 1-FCV-73-26 HPCI INBOARD SUCTION VALVE Ul RB 519 SW CORNER 1

1,2 13079 07 1-FCV-32-62 DRYWELL CONTROL AIR SUCTION VALVE U1 RB 565 CLEAN RM I

1,2 13080 07 1-FCV-77-2A DRYWELL FLOOR DRAIN SUMP DISCHARGE U1 RB 551 TORUS I

1,2 13081 07 1-FCV-77-15A DRYWELL EQUIPMENT DRAIN SUMP DISCHARGE U1 RB 551 TORUS I

1,2 13082 07 1-FCV-64-18 COOLING/PURGE AIR TO DRYWELL U1 RB 565 R5/T I

1,2 13083 07 1-FCV-64-19 COOLING/PURGE AIR TO SUPPRESSION CHAMBER Ul RB 565 R3/T 1

1,2 13084 07 1-FCV-76-18 CONTAINMENT INERTING DRYWELL N2 MAKEUP VALVE Ul RB 565 R5/T I

1,2 13085 07 1-FCV-76-19 CONTAINMENT INERTING - PSC N2 MAKEUP VALVE U1 RB 565 R3IT I

1,2 13101 18 1-LT-64-159A TORUS LEVEL TRANSMITTER U1 RB 519 TORUS 13102 18 1-LT-64-159B TORUS LEVEL TRANSMITTER UI RB 519 TORUS 13111 19 1-TE-64-161A TORUS TEMPERATURE ELEMENT Ul RB 519 TORUS 13112 19 1-TE-64.161B TORUS TEMPERATURE ELEMENT Ul RB 519 TORUS 13113 19 1-TE-64-161C TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13114 19 1-TE-64-161D TORUS TEMvERATURE ELEMENT U1 RB 519 TORUS 13115 19 1-TE-64-161E TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13116 19 1-TE-64-161F TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13117 19 1.TE-64-161G TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13118 19 1-TE-64-161H TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13211 19 1-TE-64-162A TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13212 19 1-TE-64-162B TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS APPENDIX C FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page C-7 NUMBER lCLASS EQUIPMENT I.D.

DESCRIPTION BUILDING ELEV.

ROOM ISSUE 13213 19 1-TE-64.162C TORUS TEMPERATURE ELEMENT Ut RB 519 TORUS 13214 19 1-TE-64-162D TORUS TEMPERATURE ELEMENT Ul RB 519 TORUS 13215 19 1-TE-64-162E TORUS TEMPERATURE ELEMENT Ul RB 519 TORUS 13216 19 1-TE-64-162F TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13217 19 1-TE-64-162G TORUS TEMPERATURE ELEMENT U1 RB 519 TORUS 13218 19 1-TE-64-162H TORUS TEMPERATURE ELEMENT Ul RB 519 TORUS 14001 10 1-CLR-67-917 EECW/RHR PUMP IA ROOM COOLER U1 RB 519 SW CORNER Al 1

14002 10

.CLR-637-919 EECWCS PUMP IA ROOM COOLER Ut RB 519 NW CORNER Al 1

14003 10 1-CLR-67-921 EECW/RHR PUMP IC ROOM COOLER Ul RB 519 SW CORNER Al 1

14004 21 1-HEX-67-915 EECW/RHR SEALHX IA Ul RB 519 SW CORNER Al 1

14013 10 1-CLR-67-918 EECW/RHR PUMP IB ROOM COOLER U1 RB 519 SE CORNER Al 2

14014 10 1-CLR-67-920 EECW/CS PUMP IB ROOM COOLER U1 RB 519 NE CORNER Al 2

14015 10 1-CLR-67-922 EECW/RHR PUMP ID ROOM COOLER U1 RB 519 SE CORNER Al 2

14016 21 1.HEX-67-923 EECW/RHR SEAL HX 1B U1 RB 519 SE CORNER Al 2

14025 21 1-HEX-67-916 EECW/RHR SEAL HX IC U1 RB 519 SW CORNER Al 1

14026 21 1-HEX-67-924 EECW/RHR SEAL HX 1D U1 RB 519 SE CORNER Al 2

14046 07 1-FCV-67-50 EECW NORTI I HEADER BACKUP TO RBCCW Ut RB 593 R3/P Al 1

14049 07 0-FCV-67-53 EECW NORTH HEADER BACKUP TO THE AIR COMPRESSORS U1 RB 565 R3/N Al 1

14089 07 1-FCV-67-51 EECW SYSTEM SOUTH HEADER BACKUP TO RBCCW U1 RB 565 R3/T Al 2

15001 08A 1-FCV-75-2 CSIPUMP IA SUCTION ISOLATION VALVE U1 RB 519 NW CORNER Al 1

15002 06 1-PMP-75-5 CS/PUMP IA Ut RB 519 NW CORNER Al 1

15005 08A 1-FCV-75-9 CS/PUMPS IA & 1C MINI-FLOW VALVE Ul RB 541 NW CORNER Al 1

15006 08A 1-FCV-75-11 CS/PUMP 1C SUCTION ISOLATION VALVE U1 RB 519 NW CORNER Al 1

15007 06 t-PMP-75-14 CS/PUMP IC U1 RB 519 NW CORNER Al I

15010 08A 1-FCV-75-22 CS/PUMPS 1A& iC TEST ISOLATION VALVE U1 RB 541 NW CORNER Al 1

15011 20 1-FI-75-21 CS/PUMPS 1A & IC FLOW INDICATOR Ut CB 617 MCR Al 1

15012 08A 1-FCV-75-23 CS/DIV I OUTBOARD INJECTION VALVE Ut RB 593 R4/P Al 1

15013 08A 1-FCV-75-25 CS/DIV I INBOARD INJECTION VALVE U1 RB 593 R4/P Al 1

15015 08A 1-FCV-75-30 CS/PUMP lB SUCTION ISOLATION VALVE Ut RB 519 NE CORNER Al 2

15016 06 1-PMP-75-33 CS/PUMP 18 Ut RB 519 NE CORNER Al 2

15019 08A 1-FCV-75-37 CS/PUMPS lB & 10 MINI-FLOW VALVE Ut RB 541 NE CORNER Al 2

15020 08A 1.FCV-75-39 CS/PUMP 1 D SUCTION ISOLATION VALVE U1 RB 519 NE CORNER Al 2

APPENDIX C FACILi y RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September 23, 2004 Page C-8 SSEL I

I I

NUMBER lCLASSl EQUIPMENT I.D.

I DESCRIPTION BUILDING l ELEV.

ROOM l ISSUE TRAIN 15021 06 1-PMP-75-42 CS/PUMP iD U1 RB 519 NE CORNER Al 2

15024 08A 1-FCV.75-50 CS/PUMPS 1B & ID TEST ISOLATION VALVE U1 RB 541 NE CORNER Al 2

15025 20 1-FI-75-49 CS/PUMPS lB & 1D FLOW INDICATOR U1 CB 617 MCR Al 2

15026 08A 1-FCV-75-51 CS/DIV II OUTBOARD DISCHARGE VALVE UI RB 593 R4/P Al 2

15027 08A 1-FCV-75-53 CS/DIV II INBOARD DISCHARGE VALVE Ul RB 593 R4/P Al 2

16001 088 1-FSV-84-8A CAD/CAD TO DW (1 -FCV-64-18) SOLENOID VALVE U1 RB 565 R5/T Al 1

16002 08B 1-FSV-84-8B CAD/CAD TO DW (1-FCV-64-19) SOLENOID VALVE Ul RB 565 R3/T Al 1

16003 07 1-PREG-84-52 CAD/CAD SYSTEM A TO UNIT 1 DRYWELL CONTROL AIR U1 RB 565 R4/U Al 1

16004 08B 1-FSV-84-48 CAD/CAD SYSTEM ATO UNIT 1 DRYWELLCONTROLAIR U1 RB 565 R3/T Al 1

16009 21 1-ACC-32-6105 CAIACCUMULATOR FOR PSV.1-19 U1 DW 584 DW Al I

16010 08B 1-PSV-1-19 MS/SOLENOID VALVE FOR PCV-1-19 U1 DW 584 DW Al 1

16012 21 1-ACC-32-6107 CAVACCUMULATOR FOR PSV-1-22 U1 DW.

584 DW Al 1

16013 08B 1-PSV-1-22 MS/SOLENOID VALVE FOR PCV-1-22 U1 DW 584 DW Al 1

16015 21 1-ACC-32-6106 CAVACCUMULATOR FOR PSV-1.5 Ul DW 584 DW Al 1

16016 08B 1-PSV-1-5 MS/SOLENOID VALVE FOR PCV-1-5 U1 DW 584 DW Al 1

16017 08B 1-PSV-1-23 MS/SOLENOID VALVE FOR PCV-1-23 U1 DW 584 DW Al 1

16018 08B 1-PSV-1-179 MS/SOLENOID VALVE FOR PCV-1-179 Ul DW 584 DW Al 1

16019 08B 1-PSV.1-4 MS/SOLENOID VALVE FOR PCV-1-4 U1 DW 584 DW Al 1

16021 08B 1-PSV-1-18 MS/SOLENOID VALVE FOR PCV-1-18 Ul DW 584 DW Al 2

16023 08B 1-FSV-84-8C CAD/CAD TO DW (1-FCV-64-19) SOLENOID VALVE U1 RB 565 R3/T Al 2

16024 08B 1-FSV-84-8D CAD/CAD TO DW (1 -FCV-64-18) SOLENOID VALVE U1 RB 565 R5/T Al 2

16025 07 1-PREG-84-54 CAD/CAD SYSTEM B TO UNIT 1 DRYWELLCONTROLAIR Ul RB 565 R4/U Al 2

16026 088 1-FSV-84-49 CAD/CAD SYSTEM B TO UNIT 1 DRYWELL CONTROL AIR Ul RB 565 R3/T Al 2

16029 21 1-ACC-32-6111 CAIACCUMULATOR FOR PSV-1-30 U1 DW 584 DW Al 2

16030 088 1-PSV-1-30 MS/SOLENOID VALVE FOR PCV-1-30 UI DW 584 DW Al 2

16032 21 1-ACC-32-6108 CAVACCUMU.ATOR FOR PSV-1-31 Ul DW 584 DW Al 2

16033 08B 1-PSV-1-31 MS/SOLENO!D VALVE FOR PCV-1-31 U1 DW 584 DW Al 2

16035 21 1-ACC-32-6109 CAIACCUMULATOR FOR PSV-1-34 Ul DW 584 DW Al 2

16036 08B 1-PSV-1-34 MS/SOLENOID VALVE FOR PCV-1-34 Ul DW 584 DW Al 2

16038 08B 1-PSV-1-41 MS/SOLENO!D VALVE FOR PCV-1-41 Ul DW 584 DW Al 2

16040 08B 1-PSV-1-42 MS/SOLENOID VALVE FOR PCV-1-42 Ul DW 584 DW Al 2

16041 08B 1-PSV-1-180 MS/SOLENO.D VALVE FOR PCV-1-180 U1 DW 584 DW Al 2

APPENDIX C FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01-R-004 Revision 0 September 23, 2004 Page C-9 SSELIi 1

NUMBER lCLASSl EQUIPMENT LD.

I DESCRIPTION BUILDING ELEV.

ROOM ISSUE l TRAIN 16043

_07

-FCV-64-20 CONTAINMENT VENTILATION ISOLATION VALVE U. RB 565 R3.T Al 16044 07 1-FCV-64-21 CONTAINMENT VENTILATION ISOLATION VALVE UI RB 565 R3/T Al 18002 08A 1-FCV-23-034 RHRIRHRSW HXVA OUTLET VALVE U1 RB 565 R2/U Al 18004 08A 1-FCV-23-040 RHR/RHRSW HXC OUTLET VALVE U1 RB 565 R2/U Al 1

18006 08A 1-FCV-23-046 RHRIRHRSW( HX B OUTLET VALVE U1 RB 565 R5/T Al 2

18008 08A 1-FCV-23-052 RHR/RHRSW HX D OUTLET VALVE Ul RB 565 RS/T Al 2

18009 20 1-FI-23-36 RHRSW HXA FLOW INDICATOR Ul CB 617 MCR Al I

18010 20 1-FI-23-42 RHRSW HXC FLOW INDICATOR U1 CB 617 MCR Al 1

18011 20 1-FI-23-48 RHRSW HX B FLOW INDICATOR U1 CB 617 MCR Al 2

18012 20 1-FI-23-54 RHRSW HX D FLOW INDICATOR U1 CB 617 MCR Al 2

18029 08A 1-FCV-23-046 RHRIRHRSW HX B OUTLET VALVE Ul1 RB 565 R5IT Al 2

18032 08A 1-FCV-23-052 RHR/RHRSW HX D OUTLET VALVE UI RB 565 R5/T Al 2

18033 08A 1-FCV-23-57 RHR/RHRSW CROSS CONNECT VALVE UI RB 565 R6/S Al 2

19001 20 1-PNLA-009-0023/1 ELECTRICAL CONTROL PANEL 1-9-23-1 Ul CB 617 Ul MCR Al 19002 20 1-PNLA-009-0023/2 ELECTRICAL CONTROL PANEL 1-9-23-2 U1 CB 617 U1 MCR Al 19003 20 l-PNLA-009-0023/3 ELECTRICAL CONTROL PANEL 1-9-23-3 U1 CB 617 U1 MCR Al 19004 20 1-PNLA-009-0023/4 ELECTRICAL CONTROL PANEL 1-9-23-4 U1 CB 617 U1 MCR Al 19005 20

-PNLA-009-0023/5 ELECTRICAL CONTROL PANEL 1-9-23-5 U. CB 617 Ul MCR Al 19006 20 1-PNLA-009-0023/6 ELECTRICAL CONTROL PANEL 1-9-23-6 U1 CB 617 U1 MCR Al 19007 20 I-PNLA-009-002317 ELECTRICAL CONTROL PANEL 1-9-23-7 U1 CB 617 U1 MCR Al 19008 20 l-PNLA-009-0023/8 ELECTRICAL CONTROL PANEL 1-9-23-8 Ul CB 617 U1 MCR Al 19030 01 l-BDBB-281-OOOIA 250V DC RM')V BOARD IA Ul RB 621 O/R1 Al 1I 19031 01 1-BDBB-281-OOOIB 250V DC RMOV BOARD lB Ut RB 593 0/R1 Al I

19033 01 l-BDBB-281-OOlC 250V DC RMOV BOARD IC U1 RB 565 0/RI Al 19039 14 1-JBOX-253-6455 I&C BUS IA DISC SWITCH IA1 Ut RB 621 R/R1 Al I

19040 04 1-XFA-253-OOOlAI I&C BUS 1A480/208-120VTRANSFORMER U1 RB 621 R/RI Al I

19041 04 l-XFA-253-OOOIA I&C BUS IA REGULATING TRANSFORMER U1 RB 621 R/RI Al I

19042 14 1-JBOX-253-6457 I&C BUS IA DISC SW lA2 U1 CB 593 BATT BD 1 Al I

19043 14 1-JBOX-253-6456 I&C BUS IA DISC SWITCHES 1A3, 1A4, lA5, 1A6 U1 RB 621 R/RI Al I

19044 14 l-JBOX-253-8862 I&C BUS IA DISC SWITCH Ul RB 621 R/RI Al I

19045 20 1-PNLA-009-0009 I&C BUS IA (CAB 2 OF PNL 1-9-9)

Ul CB 617 Ul MCR Al I

19046 20 t-PX-64-160B POWER SUPPLY (PNL 1-9-19: t-LI-64-159B,160B)

Ut CB 593 Ut AIR Al I

APPENDIX C FACILIY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page 0-1 0 SSEL I

NUMBER ICLASSj EQUIPMENT I.D.I DESCRIPTION BUILDING ELEV.

ROOM ISSUE TRAIN 19047 20 1-PXMC-23-1 14 POWER SUPPLY (PNL 1-9-18: FI-23-36,42 : Ft-74.50)

UI CB 593 Ut AIR Al I

19048 20 1-PXMC-23-1 15 A&B POWER SUPPLY (PNL 1-9-19: F1-23-48,54; F1.74-64)

Ut CB 593 Ut AIR Al if 19049 04 1-XFA-253-000lBl I&C BUS lB 480/208-120V TRANSFORMER Ut RB 593 RIR1 Al II 19050 04 1-XFA-253-0001B2 I&C BUS lB3 REGULATING TRANSFORMER U1 RB 593 RJRI Al II 19051 14 1-JBOX-253-6460 I&C BUS l B DISC SW 1 B2 U1 CB 593 BATT BDI Al II 19052 14 t-JBOX-253-8865 I&C BUS IB DISC SWITCH Ul RB 593 RRIR Al II 19053 14 1-JBOX-253-6459 I&C BUS IB DISC SWITCHES 1B33, 1B4, lBS. lB3S Ut RB 593 R/R1 Al II 19054 20 t-PNLA-009-0009 I&C BUS IlB (CAB 3 OF PNL 1.9-9)

Ul CB 617 Ul1MCR Al-if 19055 20 1-PX-64-159B POWER SUPPLY (PNL 1-9-19)

UI CB 593 UIlAIR Al II 19068 14 1-JBOX-253-7160 I&C BUS IB DISC SWITCH IBI Ul RB 593 RIRI Al If 19070 16 1-INVT-256-0001 DIV I ECCS ATU INVERTER Ul RB 593 0/RI Al I

19071 20 I-PX-71-60-1 ECCS ATU CAB 1-9-81 POWER SUPPLY Ut CB 593 Ut AIR Al 19072 20 I-PX-71-60-IA ECCS ATU CAB 1-9-81 POWER SUPPLY Ut CB 593 Ut AIR Al 19073 20 1-PX-64-50 POWER SUPPLY (PNL 1-25-31: XR-64-50 [DEV BATERM 11/12])

Ut RB 621 01/R2 Al I

19074 20 1-PX-74-56 POWER SUPPLY (PNL 1-9-18: F1-74-56)

Ut CB 593 Ut AIR Al I

19075 16 l-INvr-256-0002 DIV II ECCS ATU INVERTER Ul RB 621 P/RI Al II 19076 20 1-PX-71-60-2 ECCS ATU CAB 1-9-82 POWER SUPPLY UI CB 593 Ut AIR Al It 19077 20 1-PX-71-60-2A ECCS ATU CAB 1-9-82 POWER SUPPLY Ut CB 593 Ut AIR Al II 19078 20 1-PX-74-70 POWER SUPPLY (PNL 1-9-19: F1-74-70)

UI CB 593 Ul AIR Al if 19079 20 1-PX-64-159A POWER SUPPLY (1-9-18)

UI CB 593 Ut AIR Al 19080 20 1-PX-64-160A POWER SUPPLY (1-9-18)

UIOCB 593 Ut AIR Al I

19081 20 1-PX-64-67B POWER SUPPLY (1-9-19)

U1 CB 593 Ut AIR Al II 19082 20 l-PX-64-161 POWER SUPPLY (PNL 9-87)

Ut CB 593 Ut AIR Al I

19083 20 1-PX-64-162 POWER SUPPLY (PNL 9-88)

Il CB 593 UIlAIR Al 1I 19084 18 1-PS-67.50 PRESSURE SWITCH FOR 1-FCV-67-50 (14046)

U1 RB 593 1P/R3 Al 19085 1 8 1-PS-67-51 PRESSURE SWITCH FOR 1-FCV-67-51 (14047)

Ul RB 565 T(R3 Al 19088 20 1-LPNL-925-044ANt 1 COMMON BD LOGIC RELAY PANEL 25-44-All1 Ut RB 621 S/Ri Al-19089 20 l-LPNL-925-044AN12 COMMON BD LOGIC RELAY PANEL 25-44-A12 Ut RB 621 S/R2 Al 19090 20 1-LPNL-925-044B/t I COMMON BD LOGIC RELAY PANEL 25-44-B 1 1 Ul RB 621 S/R1 Al 19091 20 1-LPNL-925-044B/12 COMMON BD LOGIC RELAY PANEL-25-44-1B12 Ut RB 621 S/R2 Al 19114 20 1-PNLA-009-0003A REACTOR SD & CONT. COOLING PNL Ut CB.

1 617 JUt MCR Al 115 20 l-PNLA-009-0003B REACTOR SD& CONT. COOQUNG PNL Ut CB 1617 JUt MCR Al APPENDIX C APPENIX CFAcILITY RISK CONSULTANTS~, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page C-1 1 SSEL 111 NUMBER lCLASSl EQUIPMENT I.D.

I DESCRIPTION BUILDING ELEV.

ROOM ISSUE TRAIN 19116 20 1-PNLA-009-0004 CLEANUP & RECIRC PNL Ul CB 617 U1 MCR Al 19117 20 1-PNLA-009-0005 REACTOR CONTROL PNL U1 CB 617 U1 MCR Al 19118 20 1.PNLA-009-0006 FW & COND. PNL U1 CB 617 U1 MCR Al 19120 20 1-PNLA-009-0015 RPS CH A (DIV I)

U1 CB 593 U1 AIR Al I

19121 20 1-PNLA-009-0016 RPS CH A, B, C, D U1 CB 593 U1 AIR Al 19122 20 1.PNLA-009-0017 RPS CH B (DIV Il)

U1 CB 593 U1 AIR Al If 19123 20 1-PNLA-009-0018 FW & RECIRC PNL U1 CB 593 U1 AIR Al 19124 20 1-PNLA-009-0019 PROCESS INSTR PNL U1 CB 593 U1 AIR Al 19125 20 1-PNLA-009-0021 TEMP RECORDING PNL U1 CB 617 U1 MCR Al 19126 20 l-PNLA-009-0028 CRD SELECT RELAY AUX PNL UI CB 593 U1 AIR Al 19127 20 1.PNLA-009-0030 AUTO BLOWNDOWN AUX PNL U1 CB 593 Ut AIR Al 19128 20 1-PNLA-009-0032 RHR, CS, & HPCI (CH A) PNL Ul RB 593 U1 AIR Al 19129 20 1-PNLA-009-0033 RHR, CS, & HPCI (CH B) PNL U1 CB 593 U1 AIR Al 19130 20 1-PNLA-009-0039 HPCI RELAY AUX PNL U1 CB 593 UI AIR Al 19131 20 1-PNLA.009-0042 MSIV (INBOARD) DIV II PNL U CB 593 JU. AIR Al 19132 20 1-PNLA-009-0043 MSIV (OUTBOARD) DIV II PNL U1 CB 593 Ut AIR Al 19133 20 1-PNLA-009-0054 CONTAINMENT ATM. DILUTION PNL U1 CB 617 Ut MCR Al 19134 20 1-PNLA-009-0055 CONTAINMENT ATM. DILUTION PNL Ut CB 617 Ut MCR Al 19135 20 1-PNLA-009-0081 DIV I ECCS A.TU CABINET U1 CB 593 U1 AIR Al-19136 20 1-PNLA-009-0082 DIV 11 ECCS ATU CABINET U1 CB 593 UI AIR Al if 19137 20 I-PNLA*009-0083 RPS ATU CAB UlCB 593 U1 AIR Al.

19138 20 1-PNLA-009-0084 RPS ATU CAB U1 CB 593 U1 AIR Al 19139 20 1-PNLA-009-0085 RPS ATU CAB U1 CB 593 Ul AIR Al if 19140 20 1-PNLA-009-0086 RPS ATU CAB U1 CB 593 U1 AIR Al if 19141 20 1-PNLA-009-0087 DIV I TORUS TEMP MONITORING U1 CB 593 U1 AIR Al 1

19142 20 1-PNLA-009-0088 DIV II TORUS TEMP MONITORING U1 CB 593 Ut AIR Al II 19145 20 1-PNLA-009-0093 NEW PNL (INSTALLED BY DCN W19433)

Ut CB 593 Ut AIR Al 19146 18 1-HS-74-7B LOCAL HS STATION U1 RB 541 SW CORNER Al I

19147 14 1-JB.668 JUNCTION BOX (TERM BLOCK) - SEALED BOX Ut RB 541 SW CORNER Al I

19148 18 1-HS.74.57B LOCAL HS STATION U1 RB 551 TORUS Al 19149 14 1-JB-654 JUNCTION BOX (TERM BLOCK) -SEALED BOX Ut RB 551 TORUS Al 19150 18 1-HS.74-59B LOCAL HS STATION U1 RB 551 TORUS Al I

APPENDIX C FACILY RISK CONSULTANTS, INC.

TVA/BFN-01-R-004 Revision 0 September 23, 2004 Page C-12 SSELII I

NUMBER lCLASSl EQUIPMENT l.D.

I DESCRIPTION BUILDING ELEV.

ROOM ISSUE TRAIN 19151 18 1.HS-74-58B LOCAL HS STATION U1 RB 551 TORUS I

I 19153 18 1-HS.74-52B LOCAL HS STATION Ut RB 565 T/R3 Al 11 19154 14 1-JB-1079 JUNCTION BOX (TERM BLOCK). SEALED BOX U1 RB 583 T/R3 Al if 19155 18 1-HS-74-53B LOCAL HS STATION UI RB 565 T/R3 Al I

19156 18 1-HS-74-60B LOCAL HS STATION U1 RB 593 S/R3 Al I

19158 18 1-HS-74-61B LOCAL HS STATION U1 RB 593 S/R3 I

I 19160 18 1.HS-74-30B LOCAL HS STATION URB 541 SE CORNER Al 11 19162 18 1-HS.74.71B LOCAL HS STATION Ul RB 551 TORUS Al If 19163 14 1-JB-665 JUNCTION BOX (TERM BLOCK) - SEALED BOX Ul RB 551 TORUS Al 11 19164 18 1-HS-74-72B LOCAL HS STATION U1 RB 551 TORUS I

11 19165 18 1-HS-74-66B LOCAL HS STATION Ut RB 583 T/R4 Al 11 19166 14 1-JB.1080 JUNCTION BOX (TERM BLOCK) - SEALED BOX Ul RB 583 T/R4 Al 11 19167 18 1-HS-74-67B LOCAL HS STATION U1 RB 583 T/R4 Al if 19170 18 1-HS-74-75B LOCAL HS STATION U1 RB 565 S/R6 I

II 19171 18 1-HS-70-47B LOCAL HS STATION U1 RB 551 TORUS I

II 19172 14 1-JB-1204 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 551 TORUS Al 11 19173 18 1-HS-75-09B LOCAL HS STATION U1 RB 519 NW CORNER Al 19175 18 1-HS-75-25B LOCAL HS STATION Ul RB 593 P/R4 Al I

19176 14 1-JBOX-1064 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 593 P/R4 Al 19177 18 1.HS-75-37B LOCAL HS STATION Ul RB 519 NE CORNER Al 11 19179 18 1-HS-75-53B LOCAL HS STATION (TERM BLOCK). SEALED BOX U1 RB 593 P/R4 Al II 19180 14 1-JBOX-1067 LOCAL HS STATION (TERM BLOCK) - SEALED BOX U1 RB 593 P/R4 Al II 19181 18 1-HS-23-34B LOCAL HS STATION (TERM BLOCK). SEALED BOX UI RB 565 U/R2 Al I

19182 14 1-JBOX-1077 JUNCTION BOX (TERM BLOCK). SEALED BOX U1 RB 565 U/R2 Al 1

19183 18 1-HS-23-40B LOCAL HS STATION (TERM BLOCK). SEALED BOX Ul RB 565 U/R2 Al I

19184 18 1-HS-23-46B LOCAL HS STATION UIRB 565 T/R4 Al II 19185 14 1-JB-1087 JUNCTION BOX (TERM BLOCK) -SEALED BOX UlRB 565 T/R4 Al II 19186 18 1-HS.23-52B LOCAL HS STATION UIRB.

565 T/R4 Al II 19187 18 1-HS-74-0005B LOCAL HS STATION. RHR PUMP IA U1 RB 519 SW CORNER Al I

19188 18 1-HS-74-0028B LOCAL HS STATION - RHR PUMP 1B U1 RB 519 SE CORNER Al 11 19189 18 1-HS-74-0016B LOCAL HS STATION - RHR PUMP iC U1 RB 519 SW CORNER Al I

19190 18 1-HS-74-0039B LOCAL HS STATION. RHR PUMP 1D Ut RB 519 SE CORNER Al if APPENDIX C FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page C-13 SSELI NUMBER lCLASSl EQUIPMENT LD.

I DESCRIPTION BUILDING l ELEV.

ROOM l ISSUE TRAIN 1991 18 l1-HS75-0005B LOCAL HS STA l

19192 18 1-HS-75-0033B LOCAL HS STATION - CS PUMP 1B U1 RB 519 NE CORNER Al 11 19193 18 1-HS-75-0014B LOCAL HS STATION - CS PUMP lC U1 RB 519 NW CORNER Al I

19194 18 1-HS-75-0042B LOCAL HS STATION - CS PUMP 1D UI RB 519 NE CORNER Al It 19194 18 I-LN-95-005A LOCAL PSATI 25-C U

UI RB 519 NCRN Al 19195 18 1-LPNL-925-005A LOCAL PANEL 25-5A UI RB 593 S/R3 Al 19196 18 1-LPNL-925-005B LOCAL PANEL 25-SB Ul RB 593 S/R3 Al 19197 18 1-LPNL-925-005D LOCAL PANEL 25-5-001 Ul RB 593 S/R3 Al 19198 18 1-LPNL-925-006A LOCAL PANEL 25-6A UI RB 593 P/RS Al 19199 18 1-LPNL-925-006D LOCAL PANEL 25-6-001 U1 RB 593 Q/R5 Al 19200 18 1-LPNL-925-0059 LOCAL PANEL 25-59 UI RB 519 SW CORNER Al 19201 18 1-LPNL-925-0062 LOCAL PANEL 25-62 UI RB 519 SE CORNER Al 19204 20 1-PNLA-925-0031 LOCAL PANEL 25-31 UI RB 621 O/R2 Al 19205 20 1-PNLA-925-0032 LOCAL PANEL 25-32 UIRB 621 Q/R2 Al 19206 18 1-LPNL-925-0001 LOCAL PANEL 25-1 UI RB 519 NW CORNER Al 19207 18 1-LPNL-925-0060 LOCAL PANEL 25-60 U1 RB 519 N/E CORNER Al 19220 20 1-PROT-099-OOOlAl RPS CIRCUIT PROTECTOR CABINET

.AI UiRB 593 BATT B1 I Al 19221 20 1-PROT-099-0001A2 RPS CIRCUIT PROTECTOR CABINET 1A2 U1 RB 593 BATT BD I Al 19222 20 1-PROT-099-000181 RPS CIRCUIT PROTECTOR CABINET IBI UI RB 593 BATT BD 1 Al 19223 20 1-PROT-099-0001B32 RPS CIRCUIT PROTECTOR CABINET 1B12 U1 RB 593 BATT BD 1 Al 19224 20 1-PROT-099-OOOICI RPS CIRCUIT PROTECTOR CABINET 1CI Ut RB 593 BATT BD I Al 19225 20 1-PROT-099-0001C2 RPS CIRCUIT PROTECTOR CABINET 1C2 Ut RB 593 BATT BD 1 Al 19226 18 1-LPNL-925-247A LOCAL PANEL 1-25-247A (CAD DRYWELL & SUPP. CHAMB. V.)

Ut RB 621 Q/R4 Al 19227 01 1-BDBB-265-0001B 480V RB VENT BD 1B Ut RB 565 U/R4 Al 19228 20 1-PNLA-009-0036A PANEL 1-9-30A U1lCB 593 Ul AIR Al 19229 18 1-LPNL-925-0247B LOCAL PANEL 1-25-247B (CAD N2 SUPPLY PANEL B)

UI RB 621 Q/R4 Al 19230 18 1-LPNL-925-0007A LOCAL PANEL 1-25-7A UI RB 541 SW CORNER Al 19231 18 1-LPNL-925-0007B LOCAL PANEL 1-25-7B UI RB 541 SW CORNER Al 19232 14 1-HS-74-101B HANDSWITCH FOR 1-FCV-74-101 (11055)

UI RB 565 T/R6 Al 19239 18 1-TS-64-68 HANDSWITCH FOR 1-CLR-67-917 (14001)

U1 RB 541 SW CORNER Al 19240 18 1-HS-64-69 HANDSWITCH FOR 1-CLR-67-918 (14013)

U1 RB 541 SECORNER Al 19241 18 1-TS-64-70 HANDSWITCH FOR 1-CLR-67-921 (14003)

U1 RB 541 SW CORNER Al 19242 18 1-HS-64-71 HANDSWITCH FOR 1-CLR-67.922 (14015)

Ut RB 541 SE CORNER Al APPENDIX C FACtuTy RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page C-14 SSEL j IIiI1 NUMBER lCLASSl EQUIPMENT l.D.

I DESCRIPTION BUILDING ELEV.

ROOM lISSUE TRAIN 19243 14 1.HS-69-2B HANDSWITCH FOR 1.FCV-69-2 (13033)

Ul RB 593 R5/S Al 19244 14 1-HS-71-18B HANDSWITCH FOR 1-FCV-71-18 (13039)

UJ RB 519 NW CORNER I

19245 01 1-HS-71-2B HANDSWITCH FOR 1-FCV-71-2 (13037)

UJ RB 593 R/R1 Al 19246 14 1-HS-73-27 HANDSWITCH FOR 1-FCV.73-27 (13043)

UI RB 519 HPCI I

19247 18 1-HS-73-3B HANDSWITCH FOR 1-FCV-73-3 (13041)

Ut RB 551 TORUS Al 19248 18 1-HS-73-81B HANDSWITCH FOR 1-FCV-73-81 (13042)

U1 RB 551 TORUS Al 19250

14.

1-HS-74-12B HANDSWITCH FOR 1-FCV-74-'12 (11011)

UJ RB 519 SW CORNER Al 19251 14 1-HS-74-13B HANDSWITCH FOR 1-FCV-74-13 (11012)

U1 RB 541 SW CORNER Al 19252 14 1-HS-74-1B HANDSWITCH FOR 1-FCV-74-1 (11001)

UJ RB 519 SW CORNER Al 19253 14 1-HS-74-24B HANDSWITCH FOR 1-FCV.74-24 (11029)

Ut RB 519 SE CORNER Al 19254 14 1-HS-74-25B HANDSWITCH FOR 1-FCV-74-25 (11030)

Ul RB 541 SE CORNER Al 19255 14 1-HS-74-2B HANDSWITCH FOR 1-FCV-74-2 (11002)

U1 RB 541 SW CORNER Al 19256 14 1-HS-74-35B HANDSWITCH FOR 1-FCV-74-35 (11037)

U1 RB 519 SE CORNER Al 19257 14 1-HS-74-36B HANDSWITCH FOR 1-FCV.74-36 (11038)

U1 RB 541 SE CORNER Al 19258 18 1-HS-74-73B HANDSWITCH FOR 1-FCV-74-73 (11046)

Ut RB 551 TORUS Al 19260 18 1-HS-75-11B HANDSWITCH FOR 1-FCV-75-11 (15006)

U1RB 519 NW CORNER Al 19261 14 1-HS-75-22B HANDSWITCH FOR 1-FCV-75-22 (15010)

Ut RB 541 NW CORNER Al 19262 18 1-HS-75-23B HANDSWITCH FOR 1-FCV-75-23 (15012)

U1 RB 593 P/R4 Al 19263 18 1-HS-75-2B HANDSWITCH FOR 1-FCV.75-2 (15001)

Ut RB 519 NW CORNER Al 19264 18 1-HS-75-30B HANDSWITCH FOR 1-FCV-75-30 (15015)

U1 RB 519 NE CORNER Al 19265 18 1-HS-75-39B HANDSWITCH FOR 1-FCV-75-39 (15020)

Ut RB 519 NECORNER Al 19266 14 1-HS-75-50B HANDSWITCH FOR 1-FCV-75-50 (15024)

Ut RB 541 NE CORNER Al 19267 18 1-HS-75-51B HANDSWITCH FOR 1-FCV-75-51 (15026)

Ut RB 593 P/R4 Al 19268 14 1-HS-78-61B HANDSWITCH FOR 1-FCV-78-61 (11026)

U1 RB 621 R5/S Al 19269 14 1-HS-64-72 HANDSWITCH FOR 1-CLR-67-919 (14002)

Ut RB 541 NW CORNER Al 19270 14 1-HS-64-73 HANDSWITCH FOR 1-CLR-67-920 (14014)

Ut RB 541 NE CORNER Al 19271 18 1-TS-64-68 TEMPERATURE SWITCH FOR 1-CLR-67-917 (14001)

U1 RB 519 SW CORNER Al 19272 18 1-TS-64-69 TEMPERATURE SWITCH FOR 1-CLR-67-918 (14013)

Ut RB 519 SE CORNER Al 19273 18 1-TS-64-70 TEMPERATURE SWITCH FOR 1-CLR-67-921 (14003)

U1 RB 519 SW CORNER Al 19274 18 1-TS-64-71 TEMPERATURE SWITCH FOR 1-CLR-67-922 (14015)

Ut RB 519 SE CORNER Al 19275 18 1-TS-1-17A MAIN STEAM VAULT TEMPERATURE SWITCH Ut RB 565 MSVLT N/T3 Al 19276 18 1-TS-1-17B MAIN STEAM VAULT TEMPERATURE SWITCH Ut RB 565 MSVLT N/T3 Al APPENDIX C FACLITYRISK CONSULTANTS, INC.

TVAtBFN-01 -R-004 Revision 0 September 23, 2004 Page C-15 SSEL C

1 1

1 NUMBER CLASS Q

EUIPMENT I.D.

I DESCRIPTION BUILDING ELEV.

ROOM ISSUE l TRAIN 19277 18 1-TS-1-17C MAIN STEAM VAULT TEMPERATURE SWITCH U1 RB 565 MSVLT N/T3 Al 19278 18 1-TS-1-17D MAIN STEAM VAULT TEMPERATURE SWITCH Ut RB 565 MSVLT N/T3 Al 19279 18 1-TS-1-29A MAIN STEAM TUNNEL TEMPERATURE SWITCH Ut TB 565 MSTNL KWT3 Al 19280 18 1-TS-1-29B MAIN STEAM TUNNEL TEMPERATURE SWITCH U1 TB 565 MSTNL K/T3 Al 19281 18 1-TS-1-29C MAIN STEAM TUNNEL TEMPERATURE SWITCH Ul TB 565 MSTNL KWT3 Al 19282 18 1-TS-1-29D MAIN STEAM TUNNEL TEMPERATURE SWITCH Ut TB 565 MSTNL KWT3 Al 19283 18 l-TS-1-40A MAIN STEAM TUNNEL TEMPERATURE SWITCH Ut TB 586 MSTNL KWT3 Al 19284 18 1-TS-1-40B MAIN STEAM TUNNELTEMPERATURE SWITCH jU1 TB 586 MSTNL WrT3 Al 19285 18 1-TS-1-40C MAIN STEAM TUNNEL TEMPERATURE SWITCH Ut TB 586 MSTNL KtT3 Al 19286 18 1-TS-1-40D MAIN STEAM TUNNEL TEMPERATURE SWITCH Ut TB 586 MSTNL KWT3 Al 19287 18 1-TS-1-54A MAIN STEAM, TUNNEL TEMPERATURE SWITCH U1 TB 586 MSTNL KWT3 Al 19288 18 1-TS-1-54B MAIN STEAM TUNNELTEMPERATURE SWITCH U1 TB 586 MSTNL KWT3 Al 19289 18 1-TS-1-54C MAIN STEAM TUNNEL TEMPERATURE SWITCH U1 TB 586 MSTNL KT3 Al 19290 18 1-TS-1-54D MAIN STEAM TUNNEL TEMPERATURE SWITCH U1 TB 586 MSTNL KtT3 Al 19291 18 1-TS-64-72 TEMPERATURE SWITCH FOR 1-CLR-67-919 (14002)

Ut RB 519 NW CORNER Al 19292 18 1-TS-64-73 TEMPERATURE SWITCH FOR 1-CLR-67-920 (14014)

U1 RB 519 NE CORNER Al 19294 00 1-AMP-092-0007/41A IRM CH. *A VOLTAGE PREAMPLIFIER 7-34A RB 565 S/R3 Al 19295 00 1-AMP-092-0007/41B IRM CH. 'B-VOLTAGE PREAMPLIFIER 7-34B RB 565 S/R3 Al 19296 14 1-LPNL-925-0027 PANEL 1-25-27 IRM PREAMP. RPS I RB 565 S/R3 Al 19297 00 1-AMP-092-0007/41C IRM CH. C VOLTAGE PREAMPLIFIER 7-34C RB 577 QIR5 Al 19298 00 1-AMP-092-0007/41D IRM CH. D VOLTAGE PREAMPLIFIER 7-340 RB 577 Q/R5 Al 19299 14 1-LPNL-925-0061 PANEL 1-25-61 IRM PREAMP. RPS 11 RB 577 Q/R5 Al 19300 20 1-NM-92-7/41A CHANNEL A IRM INDICATOR CB 617 Ut MCR Al 19301 20 1-NM-92-7/41B CHANNEL B IRM INDICATOR CB 617 U1 MCR Al 19302 20 1-NM-92-7/41C CHANNEL C IRM INDICATOR CB 617 U1 MCR Al 19303 20 1-NM-92-7/41D CHANNEL

• IRM INDICATOR CB 617 U1 MCR Al 19304 20 1-PNLA-009-012 PANEL 1-9-12 CB 617 U1 MCR Al 19305 15 1-BATD-283-OOOA1 24V NEUTRON MONITORING BATTERY, U1 CHANNEL A CB 593 BAT RM I Al 19306 15 1-BATD-283-OOOB1 24V NEUTRON MONITORING BATTERY, U1 CHANNEL B CB 593 BAT RM I Al 19307 16 1-CHGD-283-A1-1 24V NEUTRON BATTERY CHARGERS Al-I CB 593 BAT BD RM I Al 19308 16 1-CHGD-283-A2-1 24V NEUTRON BATTERY CHARGERS A2-1 CB 593 BAT BD RM 1 Al 19309 16 1-CHGD-283-B1-1 24V NEUTRON BATTERY CHARGERS B1-1 CB 593 BAT BO RM 1 Al APPENDIX C FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page C-1 6 NUMBER lCLASSl EQUIPMENT l.D.

l DESCRIPTION BUILDING ELEV.

ROOM l ISSUE TRAIN 19310 16 1-CHGD-283-B2-1 24V NEUTRON BATTERY CHARGERS B2-1 CB 593 BAT BD RM 1 Al 19312 14 1.HS-71-17B HANDSWITCH FOR I-FCV-71-17 (13074)

Ul RB 519 NW CORNER Al 19313 20 1-HS-1-56A HANDSWITCH FOR 1-FCV-1-56 (13075)

Ul CB 617 U1 MCR Al 19314 14 1-HS-73-26B HANDSWITCH FOR 1-FCV-73-26 (13076)

Ul RB 519 SW CORNER Al 19316 20 1-HS-77-2A HANDSWITCH FOR 1-FCV-:77-.2A (13080)

U1 CB 617 Ul MCR Al 19317 20 1-HS-77-1SA HANDSWITCH FOR 1-FCV-77-15A (1 3081)

Ul CB 617 U1 MCR Al 19318 20 1-HS-64-18 HANDSWITCH FOR 1-FCV-64-18 (13082)

U1 CB 617 U1 MCR Al 19319 20 1-HS-64-19 HANDSWITCH FOR 1-FCV-64-19 (13083)

Ul CB 617 Ul MCR Al 19320 20 1.HS-76-18 HANDSWITCH FOR 1-FCV-76-18 (13084)

U1 CB 617 U1 MCR Al 19321 20 1-HS-76-19 HANDSWITCH FOR 1-FCV-76.19 (13085)

U1 CB 617 U1 MCR Al 19323 14 1-JB-0375 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 519 SE CORNER Al 19324 14 1-JB-0662 JUNCTION BOX (TERM BLOCK) - SEALED BOX Ul RB 541 SE CORNER Al 19325 14 1-JB.0658 JUNCTION BOX (TERM BLOCK). SEALED BOX Ut RB 541 SECORNER Al 19326 14 1-JB-1032 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 593 S/R3 Al 19327 14 1-JB-1095 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 565 S/R6 Al 19328 14 1-JB-1559 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 565 T/R6 Al 19329 14 I-JB-0670 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 541 NE CORNER Al 19330 14 1-JB-0791 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 519 NW CORNER Al 19331 14 1-JB-0681 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 541 NW CORNER Al 19332 14 1-CS-75-9B CONTROL STATION FOR 1-HS-75-9B Ut RB 519 NW CORNER Al 19333 14 1-CS-75-37B CONTROLSTATION FOR 1-HS-75-37B U1 RB 519 NE CORNER Al 19334 14 1-JB-1231 JUNCTION BOX (TERM BLOCK). SEALED BOX Ut RB 565 S/R6 Al 19351 14 1-JB-3828 JUNCTION BOX FOR 1-TS-1-29A U1 RB 565 MSTNL KIT3 Al 19352 14 1-JB-3829 JUNCTION BOX FOR 1-TS-1-29B Ut RB 565 MSTNL KIT3 Al 19353 14 1-JB-3830 JUNCTION BOX FOR 1-TS-1-29C UI RB 565 MSTNL KT3 Al 19354 14 1-JB-3831 JUNCTION BOX FOR 1-TS-1-29D Ul RB 565 MSTNL KT3 Al 19355 14 1-JB-3801 JUNCTION BOX FOR 1-TS-1-40A UI RB 586 MSTNL KT3 Al 19356 14 1-JB-3802 JUNCTION BOX FOR 1-TS-1-40B UI RB 586 MSTNL KT3 Al 19357 14 1.JB-3803 JUNCTION BOX FOR 1-TS-1-40C UI RB 586 MSTNL K/T3 Al 19358 14 1-JB-3804 JUNCTION BOX FOR 1-TS-1-40D Ut RB 586 MSTNL KIT3 Al 19359 14 1-JB-3813 JUNCTION BOX FOR 1-TS-1-54A Ut RB 586 MSTNL KIT3 Al 19360 14 1-JB-3814 JUNCTION BOX FOR 1-TS-1-54B U1 RB 586 MSTNL KT3 Al APPENDIX C FACILITY RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September 23, 2004 Page C-17 SSEL1CLSI11 f1 f

NUMBER lCLASSl EQUIPMENT I.D.

I DESCRIPTION BUILDING ELEV.

ROOM l ISSUE TRAIN 19361 14 1-JB-3815 JUNCTION BOX FOR 1-TS-1-54C Ul RB 586 MSTNL KWT3 Al 19362 14 1-JB-3816 JUNCTION BOX FOR 1-TS-1-54D U1 RB 586 MSTNL K/T3 Al 19412 03 0-BDAA-211-0000A 4KV SHON BD A U1 RB 621 R/R2 Al IA 19413 03 0-BDAA-211-OOOOB 4KV SHDN BD B U1 RB 593 O/R2 Al IB 19418 02 1-BDBB-231-0001A 480V SHDN BD 1A U1 RB 621 S/RI Al I

19419 02 1-BDBB-231-0001B 480V SHDN RD IB U1 RB 621 S/R2 Al II 19423 01 1-BDBB-268-0001A 480V RMOV BD IA U1 RB 621 R/RI Al I 19424 01 1-BDBB-268-0001B 480V RMOV BD 1B U1 RB 593 R/R1 Al II 19437 14 0-BDDD-280-0001 2S0VBATTERYBD 1 U1 RB 593 P/R4 Al 19492 20 0-LPNL-925-0045A PANEL 25-45A U1 RB 621 RIR2 Al 19493 20 0-LPNL-925-0045B PANEL 25-45B Ul RB 593 R/R2 Al 19516 14 0-XSW-248-0001 250V MAIN BATT CHGR OUTPUT XFR SW I U1 RB 593 P(R4 Al 19519 15 0-BATA-248-OOOOA 250V BATTERY SB-A U1 RB 621 S/R2 Al IA 19520 14 0-PNLA-248-A 250V DISTRIBUTION PANELSB-A UL RB 621 S/R2 Al IA 19521 16 0-CHGA-248-OOOOA 250V BATTERY CHARGER SB-A U1 RB 621 S/R2 Al IA 19522 15 0-BATA-248-OOOOB 250V BATTERY SB-B U1 RB 621 RIR2 Al IB 19523 14 0-PNLA-248-B 250V DISTRIBUTION PANEL SB-B UL1 RB 621 R/R2 Al IB 19524 16 0-CHGA-248-0000B 250V BATTERY CHARGER SB-B U1 RB 621 R/R2 Al IB 19534 16 0-CHGA-248-0001 250V BATTERY CHARGER 1 U1 RB 593 P/R4 Al 19537 15 0-BATA-248-0001 250V MAIN BATTERY 1 U1 RB 593 P/R4 Al 19594 04 1-XFA-231-TS1A 4KV/480V TRiNSFORMER TSIA U1 RB 621 T/R1 Al 19595 04 1-XFA-231-TS1 B 4KV/480V TRANSFORMER TS1B U1 RB 621 S/R7 Al II 19709 20 1-PNLA-009-0020 PANEL 1-9-20 U1 CB 617 U1 MCR Al 19716 18 1-LPNL-925-0223 LOCAL PANEL 1-25-223 - RAW COOLING WATER PANEL U1 RB 593 Q/R2 Al 19729 14 1-HS-23-57B HANDSWITCH FOR 1-FCV-23-57 U1 RB 565 R61S Al 19791 20 1-PNLA-009-0008 PANEL 1-9-8 U1 CB 617 U1 MCR Al 19792 18 1-LPNL-925-006B LOCAL PANEL 25-6B Ul RB 593 R5/P Al 19794 04 1-XFA-099-0010 RPS REGUL/TING TRANSFORMER TRP-1 UI CB 593 BATT BD 1 Al 19795 14 1-FUDS-099-0OOICA RPS REG XFMR DISC SW FROM 480 V RMOV BD 1B U1 CB 593 BATT BD 1 Al 19796 04 TUPI UNIT PREFERRED XFMR U1 CB 593 BATT BD I Al 19797 14 1.FUDS-099-000ICB RPS BUS XFMR DISC SW U1 CB 593 BATT BD 1 Al 19801 14 1-JB-6439 JUNCTION-.OXSERVING 1-TE-161A Ul RB 519 TORUS APPENDIX C FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page C-1 8 SSEL rj__ _

NUMBER ICLASSI EQUIPMENT I.D.

DESCRIPTION IBUILDING I ELEV.

ROOM ISSUE TRAIN 19802 14 1-JB.6440 JUNCTION BOX SERVING 1-TE-161B Ul RB Sig TORUS 19803 14 1-JB-6441 JUNCTION BOX SERVING 1-TE-161C U1 RB 519 TORUS 19804 14 1-JB-6442 JUNCTIONBOXSERVING I-TE-161D U1 RB 519 TORUS 19805 14 t-JB-6443 JUNCTION BOX SERVING 1-TE-161E U1 RB 519 TORUS 19806 14 1-JB-6444 JUNCTION BOX SERVING 1-TE-161F U1 RB 519 TORUS 19807 14 1-JB-6445 JUNCTION BOX SERVING 1-TE-161G Ul RB 519 TORUS 19808 14 JB-6446 JUNCTION BOX SERVING 1-TE-161H Ut RB 519 TORUS 19809 14 1-JB-6453 JUNCTION BOXSERVING 1-TE-162A Ut RB 519 TORUS 19810 14 1-JB-6454 JUNCTION BOX SERVING 1-TE-162B Ut RB 519 TORUS 19811 14 1-JB-6447 JUNCTION BOX SERVING 1-TE-162C Ut RB 519 TORUS 19812 14 1-JB-6448 JUNCTION BOX SERVING 1-TE-162D Ut RB 519 TORUS 19813 14 1-JB-6449 JUNCTION BOX SERVING 1-TE-_162E U RB 519 TORUS 19814 14 1.JB-6450 JUNCTION BOX SERVING 1-TE-162F Ut RB 519 TORUS 19815 14 1-JB-6451 JUNCTION BOX SERVING 1-TE-162G U1 RB 519 TORUS 19816 14 1-JB-6452 JUNCTION BOX SERVING 1-TE-162H Ut RB 519 TORUS APPENDIX C FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page D-1 APPENDIX D SCREENING VERIFICATION DATA SHEETS FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page D-2 APPENDIX D SCREENING VERIFICATION DATA SHEETS (SVDS)

CERTIFICATION:

All the information contained on these Screening Verification Data Sheets (SVDS) is, to the best of our knowledge and belief, correct and accurate. This includes each entry and conclusion (whether verified to be seismically adequate or not).

Approved:

(Signatures of all Seismic Capability Engineers on the Seismic Review Team (SRT) are required; there should be at least two on the SRT. All signatories should agree with all the entries and conclusions. One signatory should be a licensed professional engineer.)

John 0. Dizon, P.E. (JOD)

Print or type name Stephen J. Eder, P.E. (SJE)

Print or type name Farid Elsabee (FE)

Print or type name Robert D. Hookwav, P.E. (RDH)

Print or type name Richard L. Tiong, P.E. (RLT)

Print or type name Sigfature Signature k Signature Signature Signtu L.

Signature U)

Signature G/13 e24 Date L43100 L Date Date g /30/0 i Date Da 3t -

e Date Date Print or type name FACuILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page D-3 APPENDIX D SCREENING VERIFICATION DATA SHEETS (SVDS)

(see Page D-19 for notes)

EI F

CAP bEM jANCHO M

1NlERS8; ElUI NO.jC.

1DSCIPIO I

~I IJ~~-

O' JPE

~SEC OK 1K?

,2 jO TEAM NOTES 10001 00 1HCU-85,1*185 CRD/HYDRAULIC CONTROL UNIT Ul RB 565' R2 & R6/P.S 565' Y

DOC RRS Y

N/A Y

N SJEIJOD 4

10002 07 1-FCV-85-82A CRDIWEST SDV VENT VALVE Ul RB 565' R2/S 565' Y

BS GRS Y

Y N/A Y

V FE/RLT 10003 07 1-fCV-85-82 CRD/WEST SDV VENT VALVE Ul RB 565' R2/S 565' Y

BS GRS Y

NMA FEIRLT 10004 07 1-FCV-85-37C CRD/WEST SDV DRAIN VALVE U1 RB 565' R2/P 565 Y

BS GRS Y

Y N/A Y

Y FE/RLT 10005 07 1-FCV-85-37D CRD/WEST SDV DRAIN VALVE U1 RB 565' R21P 565' Y

BS GRS Y

Y N/A r

V FE/RLT 10006 07 1-FCV-85-83A CRD/EAST SDV VENT VALVE U1 RB 565' R6/S 565' Y

BS GRS Y

Y.

N/A Y

Y.

FE/RLT 1

10007 07 1'FCV-85-83 CRD/EAST SDV VENT VALVE U1 RB 565' R61S 5656 Y BS GRS Y

Y N/A N

N FEIRLT 10008 07 1-FCV-85-37E CRD/EAST SDV DRAIN VALVE U1 RB 565' R6/P 565' Y

BS GRS Y

Y N/A Y

Y FEIRLT 10009 07 1-FCV-85-37F CRD/EAST SDV DRAIN VALVE Ul RB 565' R6/P 565' Y

BS GRS Y

Y N/A Y

Y FE/RLT 10010 21 1-TNK-85-901 CRD0WEST SCRAM INSTRUMENT VOLUME Ul RB 565' R2/P 565' Y

NMA N/A Y

N/A Y

Y N

JOD/SJE 4

10011 21 1-TNK-85-902 CRD/EAST SCRAM INSTRUMENT VOLUME U1 RS 565' R6/P 565' Y

N/A NIA Y

NIA Y

Y N

JOD/SJE 4

10012 083 1-FSV-85-37A CRD/SCRAM DUMP VALVE U1 RB 565' R5/N 565' Y

GERS RRS Y

Y N/A Y

Y FE/RLT 10013 086 1-FSV-85'378 CRD/SCRAM DUMP VALVE UI RB 565 R51N 565 Y

GERS RRS Y

Y NIA Y

Y FE/RLT 10014 08B 1-FSV-85-35A CR0/BACKUP SCRAM VALVE U1 RB 565' R5/N 565' Y

BS GRS Y

Y N/A Y

Y FE/RLT 10015 08B 1-FSV-85-35B CRD/BACKUP SCRAM VALVE U1 RB 565' R51N 565' Y

BS GRS Y

Y N/A Y

Y FE/RLT 10016 20 1-HS-99-5AiS1A RPS/REACTOR MANUAL SCRAM CHANNEL Al Ul CB 617' Ul MCR 617' N

ABS RRS Y

N/A Y

V Y

SJE/JOD 2,3 10017 20 1-HS-99-5A/SI B RPS/REACTOR MANUAL SCRAM CHANNEL 61 U1 CB 617 Ul MCR 617 N

ABS RRS Y

N/A M Y

Y SJE/JOD 2,3 10018 20 l-HS-99-5A-Sl RPS/REACTOR MODE SWITCH U1 CB 617 Ul MCR 617' N

ABS RRS Y

N/A Y

Y Y

FE/SJE 2,3 10019 8B 1-FSV-85-70A CRD/BACKUP PILOT SCRAM VALVE A Ul RB 565' R5SN 565' Y

BS GRS Y

Y NMA Y Y

FE/RLT 10020 86 1-FSV-85-70B CRD/ BACKUP PILOT SCRAM VALVE'B' Ul RB 565' RS/N 565' Y

BS GRS Y

Y N/A Y

Y FE/RLT 10023 8B 1'FSV-85-39A CRDASOLATION VALVE U1 RB 565' CRD RACKS 565' Y

GERS RRS Y

Y N/A Y

Y FE/RLT 10024 8B 1-FSV-85-39B CRDIISOLATION VALVE U1 RB 565' CRD RACKS 565' Y

GERS RRS Y

Y N/A Y

Y FE/RLT 10025 18 1-PI-85-88 PRESSURE INDICATOR U1 RB 565' R6/S 565' Y

ABS RRS Y

Y V

Y Y

JOD/SJE 10026 18 1-PI-85-89 PRESSURE INDICATOR Ul RB 565' R2/P 565' Y

ABS RRS Y

Y Y

Y Y

JOD/SJE 10027 18 1 PI-85-90 PRESSURE INDICATOR U1 RB 565' R2/P 565 Y

ABS RRS Y

Y Y

Y Y

JOD/SJE 11001 08A 1-FCV-74-1 RHR/PUMP 1A SUCTION VALVE FROM SUPRESSION POOL U1 RB 519 SW CORNER 519' Y

BS GRS Y

Y NMA Y F FE/RLT 11002 08A 1-FCV-74-2 RHR/PUMP IA SUCTION VALVE FROM SHUTDOWN COOUNG U1 RB 541'-6 SW CORNER 541' Y

BS GRS Y

Y N/A Y

V FE/RLT 11004 06 1-PMP-74-5 RHR/PUMP IA U1 RB 519 SW CORNER 519' Y

BS GRS Y

Y

_Y Y

SJEIJOD

=

11006 08A 1 -FCV-74-7 RHR/PUMP 1A & IC MINIMUM FLOW VALVE UI RB 541'-6 SW CORNER 541' Y

BS GRS Y

Y N/A I

Y FE/RLT APPENDIX D AFACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page D-4 S EL. IEQ IEU IPMEf 1

DESCRIPTION IB l

L AT N lASE BEO CA E I C

A T

E NO '_

_ _ E EV. 40 SPEC ISPEC.

OK' ;o

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R O K O ?

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11009 21 1-HEX-74-900A RHRIHEAT EXCHANGER 1A U_ FRB 565' SWHX 565' Y

lN/A N/A Y

N/A Y

Y N

lJOD/SJE 4

11011 08A 1-FCV-74-12 RHR/PUMP 1 CSUCTION VALVE FROM SUPRESSION POOL U1 RB 519' SW CORNER 519 V

BS GRS Y

V N/A Y

V FE/RLT 11012 08A 1 -FCV-74.13 RHR/PUMP 1 C SUCTION VALVE FROM SHUTDOWN COOLING U1 RB 541'-6 SW CORNER 541' Y

BS GRS Y

Y NMA Y

FE/RLT 11014 06 1-PMP-74-16 RHR/PUMP IC U1 RB 519' SWCORNER 519 BS GRS Y

V Y

Y Y

SJE/JOD 11017 21 1-HEX-74-900C RHR/HEAT EXCHANGER IC U1 RB 565' SW HX 565' Y

NIA N/A Y

N/A V

Y N

JOD/SJE 4

11018 20 1-FI-74-50 RHR/LOOP I FLOW INDICATOR U1 CB 61r Ul MCR 61r N

ABS RRS Y

NA Y

Y Y

FE/SJE 2

11019 20 1-FI-74-56 RHR/LOOP I FLOW INDICATOR U1 CB 61r U1 MCR 61r N

ABS RRS Y

NA Y

Y Y

FE/SJE 2

11020 08A 1-FCV-74-57 RHR/LOOP I TORUS CONTAINMENT COOUNS/SPRAY VALVE U1 RB 551' TORUS 565' Y

BS GRS Y

Y N/A Y

FE/RLT 11021 08A 1-FCV-74-59 RHR/IOOP I SUPRESSION POOL COOLING VALVE U1 RB 551' TORUS 565' Y

BS GRS Y

Y N/A Y

Y FE/RLT 11022 08A 1.FCV-74-58 RHR/LOOP I SUPRESSION POOL SPRAY VALVE U1 RB 551' TORUS 565' Y

BS GRS Y

Y N/A Y

FE/RLT 1023 08A 1-FCV-74-52 RHR/LOOP I OUTBOARD INJECTION VALVE U1 RB 565' R4/T 565' Y

BS GRS Y

Y N/A Y

Y.

FE/FLT 1

11024 08A 1-FCV.74-53 RHR/tOOP I INBOARD INJECTION VALVE Ut RB 565!

R4JT 565' Y

BS GRS Y

Y N/A Y

Y FE/RLT 1

11026 08A I-FCV.78-61 FPC/SPENT FUEL POOL COOLING X.TIE TO RHR U1 RB 621'.3' R5/S 621'-3 N

ABS RRS Y'

Y N/A Y

Y FE/RLT 2

11027 08A 1-FCV-74-60 RHR/LOOP I OUTBOARD DRYWELL SPRAY VALVE U1 RB 593 R3/S 593' Y

BS GRS Y

Y.

N/A Y

Y FE/RLT 1

11028 08A 1-FCV-74-61 RHR/LOOP I INBOARD DRYWELL SPRAY VALVE U1 RB 593' R3/S 593' Y

BS GRS Y

Y N/A Y

Y FE/RLT 11029 08A 1 FCV-74-24 RHR/PUMP IB SUCTION VALVE FROM SUPRESSION POOL U1 RB 519' SE CORNER 519' Y

BS GRS Y

Y N/A Y

Y FE/RLT 11030 08A 1.FCV.74-25 RHR/PUMP 1B SUCTION VALVE FROM SDCOOLING U1 RB 541'-6 SE CORNER 541' Y

BS GRS Y

Y N/A Y

Y FE/RLT 11031 06 1-PMP-74.28 RHR/PUMP 1B Ut RB 519' SE CORNER 519' Y

BS GRS Y

Y Y

Y Y

SJE/JOD 11033 08A 1 -FCV-74-30 RHR/PUMP 1 B & I D MINIMUM FLOW VALVE U1 RB 541V-6 SE CORNER 541' Y

BS GRS Y

Y N/A Y

Y FEIRLT 11036 21 1-HEX.74-900B RHRhNEAT EXCHANGER 1B U1 RB 565 SE HX 565 Y

N/A N/A Y

N/

Y Y

N JOD/SJE 4

11037 08A 1-FCV-74-35 RHR/PUMP ID SUCTION VALVE FROM SUPRESSION POOL Ul RB 519' SE CORNER 519' Y

BS GRS Y

Y N/A Y

Y FE/RLT 11038 08A 1-FCV-74-36 RHR/PUMP 1D SUCTION VALVE FROM SD COOUNG U1 RB 541-6' SE CORNER 541' Y

BS GRS Y

Y N/A Y

Y FE/RLT 11039 06 1-PMP.74.39 RHR/PUMP ID U1 RB 519 SE CORNER 519 Y

BS GRS Y

Y V

Y Y

SJE/JOD 11042 21 1-HEX-74-900D RHRJHEAT EXCHANGER ID U1 RB 565' SE HX 565' Y

N/A N/A Y

N/A Y

Y N

JOD/SJE 4

11043 20 1-FI.74-64 RHR/LOOP II FLOWINDICATOR U1 CB 617' Ut MCR 617' N

ABS FIRS Y

NA Y

Y Y

FE/SJE 2 3 11044 20 1-FI-74-70 RHR/LOOP II FLOW INDICATOR U1 CB 617' U1 MCR 617 N

ABS FIRS Y

NA Y

Y Y

FE/SJE 2, 3 11045 08A 1-FCV.74.71 RHRALOOP 11 TORUS CONT. COOLING/SPRAY VALVE U1 RB 551 TORUS 565' Y

BS GRS Y

Y N/A Y

Y FE/RLT 11046 08A 1 -FCV-74-73 RHRLOOP 11 SUPRESSION POOL COOLING VALVE Ui RB 551 TORUS 565' Y

BS GRS Y

Y N/A Y

Y FE/RLT 11047 08A 1-FCV-74-72 RHR/LOOP 11 SUPRESSION POOL SPRAY VALVE U1 RB 551 TORUS 565' Y

BS GRS Y

Y N/A Y

Y FE/RLT 11048 08A 1-FCV-74-66 RHR/LOOP II OUTBOARD INJECTION VALVE Ut RB 565' R5/T 565 Y

BS GRS Y Y N/A Y

Y FE/RLT 1

11049 08A 1 FCV-74-67 RHR/LOOP 11 INBOARD INJECTION VALVE U1 RB 565 R5/T 565' BS GRS Y

Y N/

FE-/R LT 11051 08A 1-FCV-74-74 RHR/LOOP 11 OUTBOARD DRYWELL SPRAY VALVE U1 RB 565' R6/S 581' Y

BS GRS Y

Y N/A Y

Y FE/RLT APPENDIX D FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page D-5 SSL EQ. ktN RPTONLOCAT1ON r~1L wCP OM~A C 1 OITRTEAM NOE No QUPET ESRPIO Vy 1EE

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jPSPEc]PEC

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11052 108A I I FCV-74.75 RHR/LOOP II INBOARD DRYWELL SPRAY VALVE Ul RB 1565' JRB/S 565' V

IBS GRS Y

JY N/A JY Y

FE/RLT 11053 08A 1-FCV-74.101 RHRIU2 TO Ul RHR DISCHARGE X.TIE ISO. VALVE (8,0)

Ul RB 1565' R6/T 565' V

IBS GRS Y

Y N/A Y

Y FE/RIT 12001 07 1-PCV-1-4 MS/MAIN STEAM SAFETY RELIEF VALVE Ul DW 1585' AZ=790 585' Y

BS GRS Y

LI N/A N

N JOD/ROH 12003 07 I-PCV-1-5 MS/MAIN STEAM SAFETY REUIEF VALVE Ul DW 585' AZ=1350 585' Y

BS GRS Y

Y N/A N

N JO D/RDH 12006 07 1-PCV-1-18 MS/MAIN STEAM SAFETY REUIEF VALVE Ul OW 585' AZ=350 585' Y

BS GRS Y

U N/A N

N JOD/ROH 12009 07 1-PCV-1-19 MS/MAIN STEAM SAFETY REUIEF VALVE Ui OW 585' AZ=450 585' Y

BS GRS Y

U IN/A N

N JOD/ROH 12012 0O7 il-PCV-1-22 MS/MAIN STEAM SAFETY RELIEF VALVE U1 DW 585' AZ=127.50 585' Y

BS GRS Y

Y N/A N

N JOD/RDH 12015 107 1 1-PCV-1 -23 MS/MAIN STEAM SAFETY RELIEF VALVE Ul OW 1585' AZ=137.50 585' Y

jBS GRS Y

Y N/A N

N JOD/RDH 12018 107 1I-PCV-1-179 MS/MAIN STEAM SAFETY RELIEF VALVE Ul OW 585' AZ=l105O 1585' Y

IBS ORS Y

V N/A N

N JOD/RDH 12021 107 11-PCV-1-30 MS/MAIN STEAM SAFETY RELIEF VALVE Ul OW 585' AZ=3250.

1585' Y

BS GRS Y

U N/A N

N JOO/RDH 12024 07 1 1-PCV-1 -31 MS/MAIN STEAM SAFETY RELIEF VALVE Ul OW 585' AZ=315 0 585' Y

BS GRS Y

V N/A N

N JOD/ROH 12027 07 11-PCV-1*34 MS/MAIN STEAM SAFETY REUIEF VALVE Ul DW 585' AZ=222.50 585' Y

BS GRS Y

V N/A N

N JOD/RDH 12030 07 11-PCV.1'41 MS/MAIN STEAM SAFETY RELIEF VALVE Ul OW 585' AZ=281D 585' Y

BS GRIS Y

V N/A N

N JOD/RDH 12033 07 11-PCV-1-42 MSIMAIN STEAM SAFETY RELIEF VALVE Ul DW 585' AZ=2250 585' Y

85S GRS Y

V N/A N

N JOD/RDH 12036 07 1-PCV-1-180 MS/MAIN STEAM SAFETY RELIEF VALVE Ul DW 585' AZ=2550 585' Y

BS GRS Y

Y N/A N

N JODIRDH 13001 07 1-FCV-1-14 MSIV "A"INBOARD ISOLATION VALVE UI OW 563' AZ=1604' 563' Y

BS GRS Y

N N/A Y

N JOD/RDH 4 13002 07 1-FC V-l -15 MSIV "A"OUTBOARD ISOLATION VALVE UlIRB 564' MSIV VAULT 564' Y

B5 GRS JY N

N/A Y

N SJEJJOD 4

13003 07 1-FCV-1-26 MSIV "B"INBOARD ISOLATION VALVE Ul ow 563' AZ=l1700 563' Y

BS GRIS Y

N N/A Y

N JOD/RDH 4 13004 07 1-FCV-1-27 MSIV'B'OUTBOARD ISOLATION VALVE UlIRB 564' MSIV VAULT 564' Y

BSs GRS Y

N N/A Y

N SJE/JOD 4

13005 107 11-FCV-1-37 MSIV"C" INBOARD ISOLATION VALVE UIODW 563' AZ-1900

.56 Y

IBS GRS Y

N N/A Y

N JOD/RDH 4 13006 107 11-FCV-1-38 MSIV "C"OUTBOARD ISOLATION VALVE UlIRB 564' MSIV VAULT 564' Y

BS GRS Y

N N/A Y

N SJEJJOD 4

13007 107 1-.FCV.1-51 MSIV'"0"INBOARD ISOLATION VALVE U1DOW 563' AZ=200 0 56Y Y

BS GRS Y

N N/A Y

N JOD/RDH 4 13008 07 1-FCV-1-52 MSIV'D'OUTBOARD ISOLATION VALVE U1 RB 564' MSIV VAULT 564' Y

BS GRIS Y

N N/A Y

N lSJEJJOD 4

13009 08A 1-FCV-1-55 MAIN STEAM UINE DRAIN ISOLATION VALVE Ul DW 563' AZ=1 80" 563' Y

BS GRS Y

Y.

N/A Y

Y.

JOD/RDH I 1-3015 07 i-FCV-64-17 CONTAINMENT VENTILATION ISOLATION VALVE Ul RB 565' R3/J

~

565' Y

BS GRS Y

Y IN/A JY Y

FE/RLT 13016 07 1-FCV-64-30 CONTAINMENT VENTILATION ISOLATION VALVE UlIRB 621-'-

R33/0 631' N

JABS RRS Y'

Y IN/A VY Y

FE/RLT 2

13017 107 1

1-FCV-64-33 CONTAINMENT VENTILATION ISOLATION VALVE UlIRB 1565' R21P 565' Y

IBS GRS l

Y V IN/A JY Y

FE/RLT 13018 07 1-FCV-64-139 CONTAINMENT OW OP ISOLATION VALVE UI RB 1565' R2/P 565' Y

BS GRS JY Y

N/A VY Y

FE/RLT 13019 07 1-FCV-64.140 CONTAINMENT OW OP ISOLATION VALVE UlIRB 1565' R2/P 565' Y

BS GRS Y

Y N/A JY Y

IFE/RLT 13020 07 1 -FCV-64-28A SUPPRESSION CHAMBER/DRYWELL VACUU.M BREAKERS Ul DW 1519' IN TORUS 519' Y

BS GRS Y

Y N/A Y

_Y SJEIJOD 13021 07 1-FCV-64-28B SUPPRESSION CHAMBER/DRYWELL VACUUIM BREAKERS UlIDW 1519' IN TORUS 1519' Y

BS GRS Y

Y N/A JY Y

SJEJJOD 132 0

-FCV-64-B SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ul DW 519' T519' 19 S

GRS Y

N/

V Y

SJIO APPENDIX D APPENDIX DFACLIY RISK CONSULTANTS, INC.

TVA/BFN-01-R-004 Revision 0 September 23, 2004 Page D-6 SSEL EllIID DSRPIO L.

FIOLOC ATO BASE.' IBEOWCAP ODEM ItA 1 CAV.

ANCHO INTER EOUIP EA DES=mz ACHlR EKIPTIONNOTESM NO C.EUPETjELEV.

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JOK10 I

OKR0(OIK?'KJ OK?

1 OE 13023 07 1-FCV64-28D SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW 519' IN TORUS 519' Y

BS GRS Y

Y N/A Y

Y SJE/JOD 13024 07 1-FCV-64-28E SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS Ul DW 519' IN TORUS 51g Y

BS GRS Y

Y N/A Y

Y SJENJOD 13025 07 1-FCV-64-28F SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW 519' IN TORUS 519' Y

BS GRS Y

Y N/A Y

Y SJE/JOD 13026 07 1-FCV-64-28G SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW 519 IN TORUS 519' Y

BS GRS Y

Y N/A Y

Y SJE/JOD 13027 07 1-FCV-64-28H SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 OW 519' IN TORUS 519' Y

BS GRS Y

Y N/A Y

V SJE/JOD 13028 07 1-FCV-64-28J SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW 519Y IN TORUS 519' Y

BS GRS Y

Y N/A Y

Y SJE/JOD 13029 07 I-FCV-64-28K SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW 519-IN TORUS S19 Y

BS GRS Y

Y N/A Y

Y SJE/JOD 13030 07 1-FCV-64-28L SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW 519' IN TORUS 519' Y

BS GRS Y

V N/A Y

Y SJE/JOD 13031 07 1-FCV-64-28M SUPPRESSION CHAMBER/DRYWELL VACUUM BREAKERS U1 DW 519' IN TORUS 519 Y

BS GRS Y

V N/A Y

Y SJE/JOD 13032 08A 1-FCV-69-1 RWCU INBOARD ISOLATION VALVE U1 DW 585' AZ-00 585' Y

BS GRS Y

Y' N/A Y

Y.

JOD/RDH 1 13033 08A 1-FCV-69-2 RWCU OUTBOARD ISOLATION VALVE U1 RB 593' R5/S 593' Y

BS GRS Y

Y N/A Y'

Y' FE/RLT 1

13035 08A 1-FCV-70-47 RBCCW DRYWELL RETURN VALVE U1 RB 551' TORUS 540' Y

BS GRS Y

Y N/A Y

Y FE/RLT 13037 08A 1-FCV-71-2 RCIC INBOARD ISOLATION VALVE U1 DW 585' AZ=1850 585' Y

BS GRS Y

Y N/A Y

Y JOD/ROH 13038 08A 1-FCV-71-3 RCIC OUTBOARD ISOLATION VALVE U1 RB 565' MSIV VAULT 565' Y

DOC RRS Y

Y N/A Y'

Y' SJE/JOD 1

13039 08A 1-FCV-71-18 RCICOUTBOARD SUCTION VALVE U1 RB 519' NW CORNER 52T-10' Y BS GRS Y

Y N/A Y

Y FE/RLT 13040 08A 1-FCV-73-2 HPCI STEAM SUPPLY ISOLATION VALVE U1 DW 563' AZ=50° 563' Y

BS GRS Y

Y N/A I

Y JOD/RDH 13041 08A 1-FCV-73-3 HPCI STEAM SUPPLY ISOLATION VALVE U1 RB 551' TORUS 565' Y

BS GRS Y

Y N/A Y

Y FEIRLT 13042 08A 1-FCV-73-81 HPCI STEAM SUPPLY ISOLATION BYPASS VALVE UI RB 551' TORUS 565' Y

BS GRS Y

Y N/A V

Y FE/RLT 13043 08A 1-FCV-73-27 HPCI OUTBOARD SUCTION VALVE U1 RB 519' HPCI ROOM 523' Y

BS GRS Y

Y NIA Y

Y' FE/RLT 1

13044 07 1-FCV-75-57 PSC PUMP SUCTION ISOLATION VALVE U1 RB 519' NW CORNER 519' Y

BS GRS Y

Y N/A Y

Y FEIRLT 13045 07 1-FCV-75-58 PSC PUMP SUCTION ISOLATION VALVE UI RB 519' NW CORNER 519 Y

BS GRS Y

Y N/A Y

Y FEIRLT 13046 07 1-FCV-76-24 PRIMARY CONTAINMENT ISOLATION VALVE U1 RB 565' R3/U 565' Y BS GRS Y

Y N/A Y

V FEIRLT 13047 07 1-FCV-77-28 DRYWELL FLOOR DRAIN SUMP DISCHARGE U1 RB 551 TORUS 565' Y

BS GRS Y

N N/A Y

N FE/RLT 13048 07 1-FCV-77-15B DRYWELL EQUIPMENTDRAINSUMP DISCHARGE U1 RB 551 TORUS 565' Y

BS GAS Y

N N/A Y

N FEIRLT 13049 07 t-FCV-84-19 CAD ISOLATION VALVE Ul RB 621'-3' R3/0 631' N

ABS RRS N

Y N/A Y

N FE/JOD 13050 07 1-FCV-84-20 CAD ISOLATION VALVE U1 RB 621'-3' R3/O 631' N

ABS RRS N

Y N/A Y

N FE/RLT 13051 20

-.1-3-58A RPV LEVEL INSTRUMENT U1 CB 617' UI MCR 617 N

ABS RRS Y

N/A Y

Y' Y.

SJEJOD 1,2,3 13052 20 1-LI13-58B RPV LEVEL INSTRUMENT U1 CB 617' U1 MCR 617 N

ABS RRS Y'

NA Y

Y' Y'

SJE/JOD 1, 2, 3 13053 20 1 *PI-3-74A RPV PRESSURE INSTRUMENT U1 CB 617' U1 MCR 617r N

ABS RRS Y,

NMA Y Y.

Y' SJE/JOD 1,2,3 13054 20 1-PI-3-74B RPV PRESSURE INSTRUMENT Ul CB 617' Ut MCR 61 N

ABS RRS Y'

NA Y

Y.

Y.

SJE/JOD 1,2,3 13055 20 1-XR44-159 TORUS LEVEL AND DRYWELL PRESSURE INSTRUMENT Ui CB 61r Ut MCR 61T N

ABS RRS Y'

NA V

Y Y

FE/SJE 2,3 13056 20 1-L1-64-159A TORUS LEVEL INSTRUMENT Ul CB 61r U1 MCR 617 N

ABS RRS Y'

NA Y

Y FE/SJE 2,3 APPENDIX D FACILriY RISK CONSULTANTS, INC.

TVAIBFN-01 -R-004 Revision 0 September 23, 2004 Page 0-7 SSLE EUPET10 ECITO

~L~~OC TOR I

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13057 120 11.TI-64.161 TORUS TEMPERATURE INSTRUMENT Ut CB 1617 Jul MCR 517' N

JABS RRS Y

INA Y

VY Y

FE/SJE 2.3 13058 120 1-T1-6"4-162 TORUS TEMPERATURE INSTRUMENT UI CB 16t17 Ul MCR 517' N

ASS RRS Y'

NA Y

VY V

TEJSJE

2. 3 13059 120 11-PI-64-67 DRYWELL PRESSURE INSTRUMENT UI CB 517" Ul MCR 617 N

ABS RRS Y'

NA V

VY V

FEISJE 2.3 13060 120 11.PI-64-160A DRYVVELL PRESSURE INSTRUMENT Ul B 617" Ul MCR 617 N

ABS RRS Y'

NA V

V Y

FEISJE 2.3 13061 20 1

1TI-64-52A ORYWELL TEMPERATURE INSTRUMENT Ul CB 517" Ul MCR 617 N

ABS RRS Y'

NA V

V V

FEISJE 2,3 13062 20 1i.XR.64*50 DRYWELL TEMPERATURE AND PRESSURE INSTRUMENT UtOCB 617" Ul MCR 1617" N

SABS RRS VY NA V

V V

FE/SJE

2. 3 13063 07 1

1-FCV-76-17 CONTAINMENT INERTING N2 MAKEUP UI RD 565.

RS/T 565' V

BS GRS V

V N/A Y

Y FE/RLT 13064 07 1 -FCV-64-222 HARDENED WETWELL VENT UtARB 1565' R3/T 565' Y

BS GRS Y

Y.

N/A Y'

Y' FEJRLT 1

13069 08A I1-FCV'71*40 CONTAINMENT ISOLATION RCIC VALVE U1 RB 565' MSIV VAULT 565' Y

D00 RRS Y

Y.

N/A Y.

Y.

SJEJJOD 1

13074 08A 1-FCV-71-17 RCIC INBOARD SUCTION VALVE Ul RB 519' NW CORNER 527-10' Y BS GRS Y

Y.

N/A Y

Y.

FERLT 1

13075 08A 1-FCV-1-56 MAIN STEAM UINE DRAIN ISOLATION VALVE Ul RB 564' MSIV VAULT 564' Y

IBS GRS lY N

N/A Y

N SJE/JOD 13076 O08A I1I.FCV-73-26 HPCI INBOARD SUCTION VALVE Ut RB 519' SW CORNER 519' Y

BDS GRS Y

Y N/A Y

Y FE/RLT 13079 107 11-FC V-32-62 DRYWELL CONTROL AIR SUCTION VALVE U1 RB 565' CLEAN RM 565' Y

IBS GRS Y

Y N/A Y

Y FE/RLT 13080 07 11-FC V-77-2A DRYrWELL FLOOR DRAIN SUMP DISCHARGE UIRB 551' TORUS 565.

Y BDS GRS Y

N N/A Y

N FE/RLT 13081 07 1.FCV'77-15A DRYWELL EQUIPMENT DRAIN SUMP DISCHARGE Ut RB 551P TORUS 1565.

Y BS

GRS, Y

N N/A Vy N

FE/RLT 13082 07 1 -FCV-64.18 COOLINGIPURGE AIR TO DRYWELL UtAR 565' R 5/T 565' Y

BS GRS Y

Y.

N/A Y

Y.

FE/RLT I

13083 07 11-FCV-64-19 COCILINGIPURGE AIR TO SUPPRESSION CHAMBER Ut RB 565' R3/T 565.

Y BS GRS VY Y'

N/A VY' Y.

FE/RLT I

13084 07 11-FCV-76'18 CONTAINMENT INERTING DRYWELL N2 MAKEUP VALVE Ut RB

'565' R5I 565.

Y BS GRS VY V

N/A Y

Y FE/RLT 13085 07 11-FCV-76-19 CONTAINMENT INERTING - PSC N2 MAKEUP VALVE Ut RIB 1565' R3I1' 565.

Y BS GRS Y

Y N/A Y

V FE/RLT 13101 18 1-LT-64-159A TORUS LEVEL TRANSMIT-TER Ut RB 519' ITORUS 524' Y

BS GRS V

Y Y

Y Y

'SJEIJOD 13102 18 1-LT-64-1598 TORUS LEVEL TRANSMITTER Ul RB 519' TORUS 524' Y

BS GRS V

Y Y

Y Y

JSJEJJOD 13111 19 1 -TE-64-161 A TORUS TEMPERATURE ELEMENT UIRB 519' TORUS 528' V

BS GRS Y

Y V

Y Y

SJE/OD 13112 1 9 1 -TE-64-161 B TORUS TEMPERATURE ELEMENT UIRB 519' TORUS 528' V

BS GRS Y

Y V

Y Y

SJEIJOD 13113 19 1-TE-64-161C TORUS TEMPERATURE ELEMENT U1RB 519' TORUS 528' V

BS GRS Y

Vy V

V V

SJEIJOD 13114 19 1 -TE-64'161 D TORUS TEMPERATURE ELEMENT UI RD 519' TORUS 528' V

BS GRS V

Y Y

Y V

SJE/JOD 13115 19 1 -TE-64-161 E TORUS TEMPERATURE ELEMENT UIRS 51 9' TORUS 528' V

BS GRIS V

Y V

Y Y

SJE/JOD 13116 19 I1-TE-64'161 F TORUS TEMPERATURE ELEMENT U1 RB 519' TORUS 528' Y

BS GRS V

Y V

Y Y

SJE/JOD 13117 19 I1.TE-64-161 G TORUS TEMPERATURE ELEMENT U1 Re 519' TORUS 1528' Y

BS GRS Y

Y V

Y Y

SJEJJOD 13118 19 I1 -TE-64'161 H TORUJSTEMPERATURE ELEMENT U1 RB 1519' TORUS 528' Y

IBS GRS Y

Y V

V Y

SJEJJOD 13211 19 1-TE-64-162A TORUS TEMPERATURE ELEMENT U1RB 519'.

TORUS 528' V

BS GRS V

Y V

V V

sjE/Jon 13 2 12 19 1-TE-64-162B ITORUS TEMPERATURE ELEMENT U1RB 519' TORUS 528' B

GRS Y

Y V

VY Y

SEJO 13213 19 1 -TE-64-162C ITORUS TEMPERATURE ELEMENT Ul RB 51 9' TORUS 528' V

S GRS V

v v

V V

JIO APPENDIX D APPENIX DFAcIL~n'RISK CONSULTANTS, INC.

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BS GRS Y

Y l

Y l

SJE/JOD 13215 19 1-TE-44 162E TORUS TEMPERATURE ELEMENT U1 RB 519' TORUS 528' V

BS GRS Y

V Y

V SJE/JOD_

13216 19 1.TE-44 162F TORUS TEMPERATURE ELEMENT U1 RB 519' TORUS 528' BS GRS

_, Y Y

VSJE/JOD

=

13217 19 1-TE644162G TORUS TEMPERATURE ELEMENT U1 RB 519' TORUS 528' Y

BS GRS IY Y

SJE/JOD 13218 19 1 -TE-64-162H TORUS TEMPERATURE ELEMENT U1 RB 519' TORUS 528' Y

BS GRS Y

V V

Y Y

SJEIJOD 14001 10 1CLR-7-917 EECW/RHR PUMP 1ATROOMCOOLER Ul RB 541'-6 W CORNER 565 Y

BS RRS Y

V Y

Y Y

SJE/JOD 14002 10 1-CLR-67-919 EECW/CS PUMP 1A ROOM COOLER U1 RB 541

NW CORNER 565 Y

BS RRS Y

Y S

SJEIJOD 14003 10 1 -CLR-67-921 EECW/RHR PUMP 1C ROOM COOLER U RB 541'-6 SW CORNER 565' Y

BS RRS Y

V Y

Y Y

SJE/JOD 14004 21 1HEX-67-915 EECW/RHRSEALMHXR1A U1 RB 519' SWCORNER 518' Y

BS GRS Y

NA Y

Y Y

SJE/JOD 3

14013 10 1-CLR-67.918 EECWIRHR PUMP IB ROOM COOLER Ul AB 541'-6' SE CORNER 565' Y

BS RRS Y

Y Y

Y Y

SJE/JOD 14014 10 1-CLR-67-920 EECW/CS PUMP 1 B ROOM COOLER U1 RB 541'-6 NE CORNER 565' Y

BS RRS Y

N Y

Y N

SJE/JOD 14015 10 1-CLR-67-922 EECW/RHR PUMP 10 ROOM COOLER U1 RB 541'-6' SE CORNER 565' Y

BS RRS Y

t Y

Y Y

SJE/JOD 14016 21 1-HEX67-923 EECW/RHR SEAL HX 1 8 U1 RB 518' SE CORNER 519' Y

BS GRS Y

N/A Y

V V

SJE/JOD 3

14025 21 1-HEX-67-916 EECW/RHR SEAL HXI C Ul RB 519' SW CORNER 516' Y

BS GRS Y

N Y

Y Y

SJE/JOD 3

14026 21 1 HEXL67-924 EECW/IRHR SEAL HX 1 C

U1 RB 516' SE CORNER 519' Y

BS GRS Y

N/A Y

N SJE/JOD 3

14046 07 1-FCV-67-50 EECW NORTH HEADER BACKUP TO RBCCW Ul RB 593' R3/P 604' Y

BS GRS Y

N/A Y

Y Y

SJE/JOD 14049 07 0-FCV47-53 EECW N. HEADER BACKUP TO THE AIR COMPRESSORS U1 RB 565' R3/N 568' Y

BS GRS Y

N/A Y

Y V

SJE/JOD 14089 07 1 -FCV-67*51 EECW SYSTEM SOUTH HEADER BACKUP TO RBCCW U1 RB 565' R3/T 56T Y

BS GRS Y

N/A Y

Y Y

SJE/JOD 15001 08A l.FCV.75-2 CS/PUMP 1A SUCTION ISOLATION VALVE U1 RB 519' NW CORNER 519' Y

BS GRS Y

Y' N/A Y

FE/RLT 1

15002 06 1-PMP-75-5 CS/PUMP IA U1 RB 519 NW CORNER 519' Y

BS GRS YV Y

Y Y

SJE/JOD 15005 08A 1 FCV-75-9 CS/PUMPS IA & 1C MINI-FLOW VALVE Ui RB 541'-6' NW CORNER 54P V

BS GRS Y

Y N/A Y

Y FE/RLT 15006 08A 1-FCV-75-11 CS/PUMP iC SUCTION ISOLATION VALVE U1 RB 519' NW CORNER 519' Y

BS GRS Y

Y N/A Y

Y FE/RLT 15007 06 1-PMP-75.14 CS/PUMP IC U1 RB 519 NWCORNER 519' Y

BS GRSY Y

Y N

N SJE/JOD 15010 08A 1-FCV-75-22 CS/PUMPS 1A & IC TEST ISOLATION VALVE Ul RB 541'-6 NW CORNER 543' Y

BS GRS Y

y N/A Y

Y FE/RLT 15011 20 1-F1 75-21 CS/PUMPS1A& ICFLOWINDICATOR U1 CB 617T U1 MCR 61T N

ABS RRS Y'

NA V

Y Y

FE/SJE 2,3 15012 08A 1-FCV-75-23 CS/DIV I OUTBOARD INJECTION VALVE U1 RB 593' R4/P 604' V

BS GRS Y

Y NMA

_Y FEIRLT 15013 08A 1-FCV-75-25 CS/DIV I INBOARD INJECTION VALVE U1 RB 593' R4/P 604' Y

BS GRS Y

Y N/A Y

Y FE/RLT 15015 08A 1-FCV-75-30 CS/PUMP 1B SUCTION ISOLATION VALVE U1 RB 519 NE CORNER 519' Y

BS GRS Y

Y.

N/A Y

Y FE/RLT 1

15016 06 1-PMP-75-33 CS/PUMP 1B U1 RB 519' NE CORNER 519' Y

BS GRS Y

Y _

SJEIJOD 1

15019 08A 1-FCV-75-37 CS/PUMPS 1B & 1D MINI-FLOW VALVE U1 RB 541'46 NE CORNER 540' Y

BS GAS Y

Y.

N/A Y

Y.

FE/RLT I

15020 08A 1-FCV-75-39 CS/PUMP ID SUCTION ISOLATION VALVE U1 RB 519 NE CORNER 519' Y

BS GAS Y'

N/A IY Y

FE/RLT I

15021 o06 1-PMP-75-42 CS/PUMP 10D U1 RB 519 NE CORNER 519 V

65 GRS V

V V

N N

SJE/JOD APPENDIX D FACILITY RISK CONSULTANTS, INC.

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15025 20 1-FI-75-49 CS/PUMPS 18 & 1D FLOW INDICATOR Ul CB 617 Ul MCR 617 N

ABS RRS Y'

NA Y

Y FE/SJE 2.3 15026 08A 1-FCV-75-51 CS/DIV II OUTBOARD DISCHARGE VALVE Ut RB 593' R4/P 604' Y

BS GRS Y

Y N/A Y

Y FE/RLT 15027 08A 1-FCV-75-53 CS/DIV II INBOARD DISCHARGE VALVE U1 RB 593' R4/P 604' Y

BS GRS Y

V N/A Y

Y FE/RLT 16001 08B 1-FSV-84-8A CAD/CADTO DW 1(-FCV-64-18) SOLENOIDVALVE U1 RB 565' R5/T 565' V

BS GRS Y

Y.

N/A Y

Y FE/RLT 1

16002 088 1-FSV-84-8B CAD/CAD TO DW (1-FCV-64-19) SOLENOID VALVE U1 RB 565' R3/T 565' Y

BS GRS Y

Y.

N/A Y

Y FE/RLT 1

16003 07 1-PREG-84-52 CAD/CAD SYSTEMWA"TO UNIT I DRYWELL CONTROL AIR U1 RB 565' R4AU 565' Y

DOC RRS Y

Y.

N/A Y'

Y FE/RLT 1

16004 08B 1 -FSV-84-48 CAD/CAD SYSTEM A TO UNIT 1 DRYWELL CONTROL AIR U1 RB 565' R3/T 565 Y

BS GRS Y

Y.

N/A Y'

Y FE/RLT 1

16009 21 I-ACC-32-6105 CA/ACCUMULATOR FOR PSV-1-19 Ut DW 585 AZ=450 585!

Y DOC RRS Y Y Y.

Y Y

JOD/RDH 1

16010 08B 1-PSV-1-19 MS/SOLENOID VALVE FOR PCV-1-19 U1 DW 585' AZ=450 585' Y

BS GRS Y

U N/A N

N JOD/RDH 16012 1

1*ACC-32-6107 CA/ACCUMULATOR FOR PSV-1-22 U1 DW 585' AZ=127.50 585' Y

DOC RRS Y

Y Y

Y Y

JOD/RDH 1 16013 08B 1-PSV-1-22 MS/SOLENOID VALVE FOR PCV-1-22 Ut DW 585' AZ=127.50 585' Y

BS GRS Y

Y N/A N

N JOD/RDH 16015 21 1 ACC-32-6106 CA/ACCUMULATOR FOR PSV-1-5 U1 DW 585' AZ=1350 585' Y

DOC RRS Y Y Y.

Y Y

JOD/RDH 1

16016 08B 1-PSV.1.5 MS/SOLENOID VALVE FOR PCV-1-5 U1 DW 585' AZ=1350 585' Y

BS GRS Y

Y N/A N

N JOD/RDH 16017 08B 1-PSV-1-23 MS/SOLENOID VALVE FOR PCV.1I23 U1 DW 585' AZ=137.5° 585' Y

BS GRS Y

Y N/A N

N JODIRDH 16018 088 1-PSV-1-179 MS/SOLENOID VALVE FOR PCV-1-179 U1 DW 585' AZ.1050 585' Y

BS GRS Y

Y N/A N

N JOD/RDH 16019 088 1-PSV.1-4 MS/SOLENOID VALVE FOR PCV.1-4 U1 DW 585' AZ=790 585' Y

BS GRS Y

U N/A N

N JOD/RDH 16021 08B 1-PSV-1-18 MS/SOLENOID VALVE FOR PCV.1-18 U1 DW 585' AZ=350 585' Y

BS GRS Y

U N/A N

N JOD/RDH 16023 08B 1-FSV-84-8C CAD/CAD TO DW (1-FCV.64.19) SOLENOID VALVE Ut RB 565' R3/T 565' Y

BS GRS

-Y Y

N/A Y

Y FE/RLT 16024 08B 1-FSV-84-8D CAD/CAD TO DW (1-FCV-64-18) SOLENOID VALVE U1 RB 565' R5/T 565' Y

BS GRS Y

Y N/A Y

Y FE/RLT 16025 07 1-PREG-84-54 CAD/CAD SYSTEM B TO UMT I DRYWELL CONTROL AIR U1 RB 565' R4/U 565' Y

DOC RRS Y

Y' N/A Y

Y' FE/RLT 1

16026 088 1 FSV-84-49 CAD/CAD SYSTEM B"TO UNIT 1 DRYWELL CONTROL AIR Ut RB 565' R3/T 565' Y

BS GRS Y

Y N/A Y

Y' FE/RLT I

16029 21 1-ACC-32-6111 CAIACCUMULATOR FOR PSV-1-30 Ut DW 585' AZ=3250 585' Y

DOC RRS Y

Y Y.

Y Y.

JOD/RDH 1

16030 08B 1-PSV.1I30 MS/SOLENOID VALVE FOR PCV-1-30 Ut DW 585 AZ=3250 585S Y

BS GRS Y

U N/A N

N JOD/RDH 16032 21 1-ACC-32-6108 CA/ACCUMULATOR FOR PSV-1-31 Ut DW 585' AZ=3150 585' Y

DOG RRS Y

Y Y.

Y Y.

JOD/RDH 1 16033 08B 1-PSV.1.31 MS/SOLENOID VALVE FOR PCV-1-31 Ut DW 585' AZ=3150 585' Y

BS GRS Y

Y N/A N

N JOD/RDH 16035 21 1 -ACC-32-6109 CA/ACCUMULATOR FOR PSV-1-34 Ut OW 585' AZ=222.5° 585' Y

DOC RRS Y

Y.

Y Y.

JOD/RDH 1 16036 08B 1-PSV.1-34 MS/SOLENOID VALVE FOR PCV-1-34 Ut OW 585' AZ=222-50 585' Y

BS GRS Y

Y N/A N

N JOD/RDH 16038 08B 1-PSV.1-41 MS/SOLENOID VALVE FOR PCV-1-41 Ut DW 585' AZ_2810 585' Y

BS GRS Y

Y N/A N

N JOD/RDH 16040 08B 1-PSV-1-42 MS/SOLENOID VALVE FOR PCV-1-42 U1 DW 585' AZ=2250 585' Y

BS GRS Y

Y N/A N

N JOD/RDH 16041 08B 1-PSV-1-180 MS/SOLENOID VALVE FOR PCV-1 180 U1 DW 585' AZ=2550 585' Y

BS GRS Y

N/A N

N JOD/RDH 16043 07 1-FCV-64-20 CONTAINMENT VENTILATION ISOLATION VALVE Ut RB 565' R3/T 565' BS GRS N/A Y

FE/RLT 1

APPENDIX D FAcILrn'RISK CONSULTANTS, INC.

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Y Y.

Y.

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18006 08A 1-FCV-23-046 RHRIRHRSW HX B OUTLET VALVE U1 RB 565' R51T 580 Y

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N/A Y

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18008 08A 1 -FCV-23-052 RHR/RHRSW HX D OUTLET VALVE Ut RB 565' RSIT 5685 Y BS GRS Y

Y.

N/A Y

Y.

FE/RLT 1

18009 20 1i-FI-23-36 RHRSW HX A FLOW INDICATOR U1 CB 617T Ut MCR 617' N

ABS RRS Y

NA Y

Y Y

FE/SJE 2.3 18010 20 1-FI-23-42 RHRSW HX C FLOW INDICATOR Ut CB 617 Ut MCR 617' N

ABS RRS Y

NA Y

Y Y

FE/SJE 2, 3 18011 20 1 -FI-23-48 RHRSW HX B FLOW INDICATOR U1 CB 61 7 U1 MCR 617T N

ABS RAS Y

NA Y

Y Y

FE/SJE 2, 3 18012 20 1-FI-23-54 RHRSW HX D FLOW INDICATOR Ut CB 61T Ut MCR 617T N

ABS RRS Y-NA Y

Y Y

FE/SJE 2,3 18029 08A 1-FCV-23-046 RHR/RHRSW HX B OUTLET VALVE Ut RB 565 RS/T 580 Y

BS GRS Y

Y N/A Y

Y JOD/SJE 18032 08A 1-FCV-23-052 RHR/RHRSW HX D OUTLET VALVE Ut RB 565' RS/T 580 Y

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Y N/A Y'

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JOD/SJE 1 18033 08A 1-FCV-23-57 RHR/RHRSW CROSS CONNECT VALVE Ut RB 565' R6/S 565' Y

BS GRS Y Y Y

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SJE/JOD 19001 20 1-PNLA-009-0023/1 ELECTRICAL CONTROL PANEL 1-9-23-1 Ut CB 617' Ut MCR 617' N

ABS RARS Y Y

Y Y

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19002 20 1 -PNLA-009-002312 ELECTRICAL CONTROL PANEL 1-9-23-2 Ut CB 61T Ut MCR 61r N

ABS RAS

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19003 20 1 -PNLA-009-0023/3 ELECTRICAL CONTROL PANEL 1-9-23-3 Ut CB 617' Ut MCR 617 N

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19004 20 1-PNLA-009-0023/4 ELECTRICAL CONTROL PANEL 1-9-23-4 U1 CB 61T U1 MCR 61T N

ABS RAS Y

[Y Y

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19005 20 1.PNLA-009-002315 ELECTRICAL CONTROL PANEL 1-9-23-5 Ut CB 617 Ut MCR 61T N

ABS RRS Y'

Y Y

Y Y

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19006 20 1-PNLA-009-002316 ELECTRICAL CONTROL PANEL 1-9-23-6 Ut CB 61T Ut MCR 617 N

ABS RRS Y'

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19007 20 1 -PNLA-009-002317 ELECTRICAL CONTROL PANEL 1-9-23-7 Ut CS 61r Ut MCR 61T N

ABS RAS Y'

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19008 20 1-PNLA-009-0023/8 ELECTRICAL CONTROL PANEL 1-9-23-8 U1 CB 617 Ut MCR 617 N

ABS RAS NY' Y

Y Y

Y SJE/JOD 2

19030 01 1-BDBB-281-0001A 250V DC RMOV BOARD IA Ut RB 621'-3 O/RI 621'-3 N

ABS RARS N N

N Y

N SJE/JOD 19031 01 I-BDBB-281-0001B 250V DC RMOV BOARD 1B Ut RB 593 O/Ri 593 Y

ABS RAS N N

Y Y

N SJE/JOD 19033 01 t-BDBB-281-0001C 250VDCRMOVBOARDIC Ut RB 565' 0/Ri 565' Y

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Y Y

SJE/JOD 19039 14 1-JBOX-253-6455 I&C BUS IA DISC SWITCH tAt Ut RB 621' R/R1 621'.3 N

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SJE/JOD 19042 14 1-JBOX-253-6457 I&C BUS IA DISC SW 1A2 Ut CB 593' BATT SD 1 593' BS GRS N

N N

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SJE/JOD 19043 14 1JBOX-253-6456 I&C BUS IA DISC SWITCHES tA3, tA4, 1AS, 1A6 Ut RB 621'-3' R/RI 621'-3 N

ABS RAS YN '

N' Y

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19044 14 t-JBOX-253-8862 I&C BUS IA DISC SWITCH Ut RB 621' RIRt 621'-3 N

ABS RAS Y' Y Y _

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19045 20 1-PNLA-009-0009 I&C BUS 1A (CAB 2 OF PNL 1-9-9)

U1 CB 617 U1 MCR 617 N

ABS RAS YN Y

Y Y

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N/A Y.

Y SJE/JOD 1,n 3

APPENDIX D FAcIITY RISK CQNSULTANSt INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page D-1 1 SSEL

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SJE/JOD 19051 14 14JBOX-253-6460 I&C BUS 1B DISC SW 1B2 U1 CB 593 BATT BD 1 593' Y

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SJE/JOO 19052 14 1-JBOX-253-8865 I&C BUS 1B DISC SWITCH Ul RB 593 R/Ri 593' Y

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SJE/JOD 19053 14 1-JBOX-253-6459 I&C BUS 1B DISC SWITCHES 183, 18B4,

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BS GRS Y

V V

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SJE/JOD 19054 20 1-PNLA-009-0009 I&C BUS 1B (CAB 3 OF PNL 1-9-9)

U1 CB 617 Ul MCR 61T N

ABS RRS Y

V Y

Y Y

SJE/JOD 2

19055 20 1-PX-64-159B POWER SUPPLY (PNL 1-9.19)

U1 CB 593 U1 AIR 593' Y

BS GRS Y

N/A Y

Y Y

SJE/JOD 1,3 19068 14 1-JBOX-253-7160 I&C BUS 18 DISC SWITCH 181 U1 RB 593' R/Ri 593' Y

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SJE/JOD 19070 16 1-INVT-256-0001 DIV I ECCS ATU INVERTER Ul RB 593' 0/Ri 593 Y

ABS RRS N

N N

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SJE/JOD 19071 20 1.PX-71-60-1 ECCS ATU CAB 1.9-81 POWER SUPPLY U1 CB 593 Ul AIR 593' Y

BS GRS Y

N/A Y

Y Y

SJE/JOD 1.3 19072 20 1-PX-71-60-1A ECCS ATU CAB 1-9-81 POWER SUPPLY U1 CB 593' Ul AIR 593' Y

BS GRS Y

NIA Y

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SJE/JOD 1,3 19073 20 1-PX-64-50 PWR SUPPLY (PNL 1-25-31: XR-64-50(DEVBATERM 11/121)

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ABS RRS Y

N/A Y

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SJE/JOD 1, 2.3 19074 20 1-PX-74-56 POWER SUPPLY (PNL 1-9-18: FI.74-56)

U1 CB 593' Ul AIR 593' Y

BS GRS Y

N/A Y

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SJE/JOD 1,3 19075 16 1-INVr-256-0002 DIV 11 ECCSATU INVERTER Ul RB 621'-3 P/RI 621-3 N

ABS RRS N

N N

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SJE/JOD 19076 20 1-PX-71-60-2 ECCS ATU CAB 149-82 POWER SUPPLY U1 CB 593 U1 AIR 593' Y

BS GRS Y

N/A Y

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SJE/JOD 1,3 19077 20 1-PX-71-60-2A ECCS ATU CAB 1-9-82 POWER SUPPLY U1 CB 593' Ul AIR 593' Y

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N/A Y

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SJE/JOD 1,3 19078 20 1 -PX-74-70 POWER SUPPLY (PNL 1-9-19: FI-74-70)

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BS GRS Y

N/A Y

Y.

Y SJE/JOD 1,3 19079 20 1-PX-64-159A POWER SUPPLY (1.9-18)

Ul CB 593' Ul AIR 593' Y

BS GRS Y

N/A Y

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U1 CB 593' U1 AIR 593' Y

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SJE/JOD 1,3 19082 20 1-PX-64-161 POWER SUPPLY (PNL 9-87)

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BS GRS Y

N/ A Y

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SJE/JOD 1,3 19083 20 1-PX-64-162 POWER SUPPLY (PNL 9-88)

Ul CB 593' Ul AIR 593' Y

BS GRS Y

N/A Y

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Y SJE/JOD 1,3 19084 18 1-PS-67-50 PRESSURE SWITCH FOR 1-FCV-67-50 (14046)

Ul RB 593' P/R3 604' Y

DOC RRS Y

Y Y

Y.

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19085 18 1-PS-67-51 PRESSURE SWITCH FOR 1-FCV-67-51 (14047)

Ul RB 565' T/R3 580 Y

DOC RRS Y

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Y SJE/JOD I

19088 20 11-LPNL-925-044A/11 COMMON BD LOGIC RELAY PANEL 25-44-Al 1 Ul RB 621'-3 S/RI 621'-3 N

ABS RRS Y

Y N

N N

SJE/JOD 2

19089 20 1-LPNL-925-044A/12 COMMON BD LOGIC RELAY PANEL 25-44-A;2 Ul RB 621'-3 S/R2 621'-3 N

JBS RRS Y

Y Y

Y Y

SJE/JOD 2

19090 20 1-LPNL-925-044B/11 COMMON BD LOGIC RELAY PANEL 25-44-B11 U1 RB 621'-3 S/Ri 621'-3 N

ABS RRS Y'

Y Y

Y SJE/JOD 2

19091 20 1-LPNL-925-044B/12 COMMON 80 LOGIC RELAY PANEL 25-44-812 Ul RB 621'-3 S/R2 621'-3 N

ABS IRRS Y

Y Y

iv Y

SJE/JOD 2

19114 20 1-PNLA-009-0003A REACTOR SD & CONT. COOLING PNL Ul1 CB 617 Ut MCR 617 N

ABS FIRS Y

Y Y

Y SJE/JOD 2

19115 20 1-PNLA-009-0003B REACTOR SD & CONT. COOUNG PNL Ul1 CB 61r U1 MCR 617 N

ABS RRS Y

Y Y

Y SJE/JOD 2

19116 20 1-PNLA-009-0004 CLEANUP & RECIRC PNL Ul CB 61T U1 MCR 617 N

ABS RRS Y

' Y Y

SJE/JOD 2

APPENDIX D FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page D-12 IfO,,

l I

EO IP I

1FOO 1**

N lBASE I BEO1 AP 1

EM ICP ICAINHI E

TEA NOI 19117 20 1-PNLA-009-0005 REACTOR CONTROL PNL U1 CB 61T U1 MCR 617 N

ABS RRS Y'

Y Y

Y Y

SJE/JOD 2

19118 20 1-PNLA-009'0006 FW & COND. PNL U1 CB 617 U1 MCR 617 N

ABS RRS Y'

Y Y

Y Y

SJENJOD 2

19120 20 1-PNLA-009-0015 RPSCCH APDIVI)

U1 CB 593' U1 AIR 593' Y

BS GRS Y

N Y

N N

SJE/JOD 19121 20 1-PNLA-009-0016 RPS CH A, B. C. D U1 CB 593 U1 AIR 593' Y

BS GRS Y

N Y

N N

SJE/JOD 19122 20 1-PNLA-009'0017 RPS CH B (IV 1f)

U1 CB 593 Ul AIR 593' Y

BS GRS NY N

N' N

N SJE/JOD 19123 20 1-PNLA-009-0018 FW & REGIRC PNL U1 CB 593' Ul AIR 593' Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19124 20 1-PNLA409-0019 PROCESS INSTR PNL U1 CB 593' U1 AIR 593 Y

BS GRS Y

Y Y

Y Y SJE1JOD 19125 20 1-PNLA409-0021 TEMP RECORDING PNL U1 CB 617 U1 MCR 617 N

ABS RRS Y

Y Y

Y Y

SJE/JOD 2

19126 20 1-PNLA-009-0028 CRD SELECT RELAY AUX PNL U1 CB 593' Ul AIR 593' BS GRS Y

Y Y

Y Y

SJE/JOD 19127 20 1-PNLA-009-0030 AUTO BLOWNDOWN AUX PNL U1 CB 593 UI AIR 593' Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19128 20 1-PNLA-009-0032 RHR, CS, & HPCI (CH A) PNL U1 RB 593' Ul AIR 593 Y

BS GRS

_Y N

Y N

N SJE/JOD 19129 20 1-PNLA-009-0033 RHR, CS, & HPCI (CH B) PNL U1 CB 593' U1 AIR 593 Y

BS GRS N'

N Y

N N

SJE/JOD 19130 20 1-PNLA-009-0039 HPCI RELAY AUX PNL U1 CB 593' U1 AIR 593' Y

BS GRS Y

N Y

N N

SJE/JOD 19131 20 1-PNLA-009-0042 MSIV (INBOARD)DIVII PNL U1 CB 593' U1 AIR 593 Y

BS GRS Y'

N Y

N N

SJElJOD 19132 20 1-PNLAU009-0043 MSIV (OUTBOARD) DIV II PNL U1 CB 593 U1 AIR 593' Y

BS GRS Y

N Y

N N

SJE/JOD 19133 20 1 PNLA-09-0054 CONTAINMENTATM DILU1nONPNL U1 CB 61T' Ul MCR 617 N

ABS RRS Y'

Y Y

Y Y SJE/JOD 2

19134 20 1 -PNLA-009-0055 CONTAINMENTATM. DILUTIONPNL UI CB 61T U1 MCR 617 N

ABS RRS Y'

Y Y

Y Y SJEIJOD 2

19135 20 1-PNLA-009-0081 DIV I ECCS ATU CABINET Ul CB 593' U1 AIR 593' Y

BS GRS Y

N Y

N N

SJE/JOD 19136 20 1-PNLA-009-0082 DIV 11 ECCSATU CABINET Ul CB 593' U1 AIR 593' BS GRS Y

N Y

N N

SJEIJOD 19137 20 1 PNLA-009-0083 RPS ATU CAB UG CB 593' U1 AIR 593 Y

BS GRS Y_

N Y

N N

SJE/JOD 19138 20 1-PNLA-009-0084 RPSATUCAB U1CB 593' U1AIR 593' BS GRS NY N

Y N

N SJE/JOD 19139 20 1-PNLA-009-0085 RPS ATU CAB U1 CB 593' U1 AIR 593 Y

BS GRS Y

N Y

N N

SJE/JOD 19140 20 1-PNLA-009-0086 RPS ATU CAB UG CB 593' Ul AIR 593' BS GRS Y

N Y

N N

SJE/JOD 19141 20 1-PNLAU09-0087 DIV I TORUS TEMP MONITORING U1 CB 593' Ul AIR 593' Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19142 20 1-PNLA-009-0088 DIV II TORUS TEMP MONITORING U1 CB 593' U1 AIR 593' Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19145 20 1'PNLAU009-0093 ELECTRICAL PANELS FS-90-134B & C Ul CB 593' U1 AIR 593 Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19146 18 1-HS 74 7B LOCAL HS STATION Ul RB 541"-6 SW CORNER 541' Y

BS GRS N'

Y Y Y Y

FE/RLT 19147 14 14JB-668 JUNC'TON BOX (TERM BLOCK) SEALED BOX Ul RB 541'-6' SW CORNER 541' N'

BS GRS Y

Y Y

Y Y

FE/RLT 19148 18 1-HS-74-578 LOCAL HS STATION Ul RB 519 TORUS 565' Y

BS GRS Y

Y Y

Y Y

FE/RLT 19149 14 1-JB-654 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 519' TORUS 565' Y

BS GRS Y'

Y Y

Y Y

FE/RLT 19150 18 1-HS-74-59B LOCAL HS STATION Ul RB 519' TORUS 565' Y

BS GRS Y

N Y

N' N'

FEIRLT 19151 18 1-HS-74-58B LOCAL HS STATION Ul RB 519' TORUS 565' Y

BS GRS N' Y NY r

N'Y FE/RLT APPENDIX D FACHuTY RISK CONSULTANTS, INC.

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NH INTER' EQI I

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1 I DESCRIPTION BID E

I BEC NO.

ELEW:;ELE 140~

SEC.:

IK't OK?

OK TAM OTE 19153 18 l-HS'74-523 LOCAL HS STATION U1 RB 565' T/R3 583' Y

BS GRS Y

N N

Y N

FE/RLT 19154 14 14JB 1079 JUNCTION BOX (TERM BLOCK) - SEALED BOX U1 RB 565' T/R3 583' Y

BS GRS Y

N N

Y N

FE/RLT 19155 18 11HS-74-533 LOCAL HS STATION U1 RB 565' T/R3 583' Y

BS GRS N

N N

FE/RLT 19156 18 1-HS-74-60B LOCAL HS STATION U1 RB 593' S/R3 593' BS GRS Y

V Y Y

FEIRLT 19158 18 1-HS-74-618 LOCAL HS STATION U1 RB 593' S/R3 593 Y

BS GRS Y

Y Y

Y Y

FE/RLT 19160 18 1 -HS-74-30B LOCAL HS STATION U1 RB 541'.6' SE CORNER 541' BS GRS Y

Y FE/RLT 19162 18 1-HS-74-71B LOCALHSSTATION U1 RB 519' TORUS 565 Y

BS GRS Y

Y Y

Y Y

FE/RLT 19163 14 1JB-665 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 519' TORUS 565'Y BS GRS Y

Y Y

Y V

FE/RLT 19164 18 1 -HS-74-72B LOCAL HS STATION U1 RB 519' TORUS 565' Y

BS GRS Y

V Y

Y V

FE/RLT 19165 18 1-HS574-66B LOCAL HS STATION Ul RB 565y T/R4 583' Y

BS GRS Y

V Y

V Y

FE/RLT 19166 14 14JB-1080 JUNCTION BOX (TERM BLOCK) -SEALED BOX Ul RB 565' TIR4 583' Y

BS GRS Y

Y y

FE/RLT 19167 18 1-HS-74-67B LOCAL HS STATION Ul RB 583' T/R4 583' Y

BS GRS Y

V V

Y Y

FE/RLT 19170 18 1-HS-74-75B LOCAL HS STATION UI RB 565' S/R6 565' Y

BS GRS

_ - F

/ R FERLT 19171 18 1-HS-70-47B LOCAL HS STATION U1 RB 519' TORUS 565 '

BS GRS Y

FE/RLT 19172 14 1-JB*1204 JUNCTnON BOX (TERM BLOCK) -SEALED BOX U1 RB 519 TORUS 565 V

BS GRS

'Y Y

Y Y

Y FE/RLT 19173 18 1-HS-75-09B LOCAL HS STATION U1 RB 519' NW CORNER 519' 8s GRS Y -

FE/RLT 19175 18 1-HS-75-25B LOCAL HS STATION U1 RB 593' P/R4 593' Y

3S GRS Y

Y Y

Y Y

FE/RLT 19176 14 14JBOX'1064 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 593' PIR4 593' Y

BS GRS Y

Y Y

Y Y

FE/RLT 19177 18 1-HS-75-37B LOCAL HS STATION U1 RB 519' NE CORNER 519' Y

BS GRS Y

V V

V V

FE/RLT 19179 18 1-HS-75-53B LOCAL HS STATION (TERM BLOCK) SEAL-D BOX Ul RB 593' P/R4 593' Y

BS GRS Y

V Y

Y V

FE/RLT 19180 14 1-JBOX-1067 LOCAL HS STATION (TERM BLOCK) SEALED BOX U1 RB 593' P/R4 593' Y

BS GRS Y

V V

Y V

FE/IRLT 19181 18 1-HS-23-34B LOCAL HS STATION (TERM BLOCK) SEALED BOX Ul RB 565' UIR2 565' Y

BS GRS YY V

V V

FE/RLT 19182 14 14BOX-1077 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 565' U/R2 565' Y

BS GRS Y

Y V

V Y

FE/RLT 19183 18 11-HS-23-40B LOCAL HS STATION (TERM BLOCK) -SEALED BOX U1 RB 565' U/R2 565' Y

BS GRS Y

V V

V V

FE/RLT 19184 18 1 HS-23-46B LOCAL HS STATION U1 RB 565' T/R4 584' Y

BS GRS V

V Y

V V

FE/RLT 19185 14 1JB-1087 JUNCTION BOX (TERM BLOCK). SEALED BOX U1 RB 565' T/R4 584' Y

BS GRS Y

V V

Y Y

FE/RLT 19186 18 1-HS-23-52B LOCAL HS STATION U1 RB 565 T/R4 584' Y

BS GRS Y

V V

Y Y

FE/RLT 19187 18 I-HS-74-005B LOCALHSSTATION-RHRPUMP 1A U1 RB 519' SWCORNER 519' Y

BS GRS V

Y V

Y Y

FE/RLT 19188 18 1-HS-74-0028B LOCAL HS STATION RHR PUMP 1B U1 RB 519' SE CORNER 519' Y

BS GRS V

V Y

Y V

FE/RLT 19189 18 1-HS-74-0016B LOCAL HS STATION -RHR PUMP IC U1 RB 519' SW CORNER 519' Y

BS GRS Y

V V

V V

FE/RLT 19190 18 I-HS-74-0039B LOCAL HS STATION RHR PUMP ID Ul RB 519 SE CORNER 519' Y

BS GRS Y

Y V

V FE/RLT 19191 18 1 HS-75-005B LOCAL HS STATION -CS PUMP IA UI RB 519' NW CORNER 519' BS GRS FE/RLT APPENDIX D

-FACILTnY RISK CONSULTANTS, INC.

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ISPEC: SPECCOK?

O RO (OK?

19192 18 1-HS-75-0033B LOCAL HS STATION-CS PUMP 1B U1 RB 519' NECORNER 519' Y

BS GRS Y

Y Y

Y Y

FE/RLT 19193 18 1-HS-75-0014B LOCALHSSTATION -CSPUMP IC U1 RB 519' NWCORNER 519 Y

BS GRS Y

Y V

Y Y

FE/RLT 19194 18 1-HS-75-0042B LOCALHSSTATION-CSPUMP1D U1 RB 5193 NE CORNER 519' Y

BS GRS Y

Y N

V FE/JROT 19195 18 1-LPNL-925-005A LOCAL PANEL 25-5A U1 RB 593' S/R3 593' Y

BS GRS Y

N Y

Y N

SJE/JOD 19196 18 1-LPNL-925-005B LOCAL PANEL 25-SB1 Ul RB 593' SIR3 593 Y

BS GRS Y

Y V

Y Y

SJE/JOD 19197 18 1-LPNL-925-OOAD LOCAL PANEL 25-5-001 U1 RB 593 S/R3 593' Y

ABS RRS N V

V Y

Y SJE/JOD 2

19198 18 1-LPNL-925-006A LOCALPANEL25-6A UI RB 593 PQR5 593' Y

BS GRS Y

N N

V N

SJE/JOD 19199 18 1jLPNL-925-0065 LOCAL PANEL 25-S9 URB 519 WORN5 519 Y

ABS RRS Y

Y Y

Y Y

SJE/JOD 2 19200 18 1-LPNL-925-0059 LOCAL PANEL 25-59 U1RB 519 SW CORNER 519 Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19201 18 1-LPNL-925-0062 LOCAL PANEL 25-62 U1RB 519 SE CORNER 519' Y

BS RRS Y Y

Y Y

Y SJE/JOD 19204 20 1-PNLA-925-0031 LOCAL PANEL 25-31 UIRB 621-3 O/R2 621'-3 N

ABS RRS Y

Y Y

Y Y

SJE/JOD 2

19205 20 1-PNLA-925-0032 LOCAL PANEL 25-32 U1 RB 5621'-39 R

621'-3C N ABS RRS Y'

Y V

Y Y

SJE/JOD 2

19206 18 1-LPNL-925-0001 LOCAL PANEL 25-1 UI RB 519' NW CORNER 519' Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19207 18 1-LPNL-925-0060 LOCAL PANEL 25-60 UIRB 519' N/E CORNER 51E Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19220 20 1-PROT-099-4001AI RPS CIRCUIT PROTECTOR CABINET 1A2 UI RB 593' BATT BD 1 593' Y

BS GRS Y

Y Y

Y Y

SJEJOD 19221 20 1'PROT-4994001A2 RPS CIRCUIT PROTECTOR CABINET 1A2 UiRB 593' BATT BD 1 593' Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19222 20 1-PROT-099-0001Bl RPS CIRCUIT PROTECTOR CABINET 1B2 U1RB 593 BATT BD 1 593 Y

BS GRS Y

Y V

Y Y

SJEIJOD 19223 20 I-PROT-099-000112 RPS CIRCUIT PROTECTOR CABINET 182 U1 RB 593 BATT BD 1 593' BS GRS Y

Y N

Y N

SJE/JOD 19224 20 1-PROT-099-OOOICI RPS CIRCUIT PROTECTOR CABINET IC2 U1RB 593' BATT BD 1 593 Y

BS GRS Y

Y Y

Y Y

SJE/JOD 1925 20 1-PROT-099-000C2 RPS CIRCUIT PROTECTOR CABINET1IC2 UIRB 593' BATT 80 1 593' Y

BS GRS Y

Y Y(

Y Y

SJE/JOD 9226 18 1-LPNL-925-247A LOCAL PANEL 1-25-247A (CAD DRYWELL & SUPP. CHAMB. V.) Ul RB 621'-3 Q/R4 621'-3' N

ABS RRS V Y

Y Y

Y SJEIJOD 2

19227 01 1-BDBB-265-0001B 480V RB VENT BD 1B U1RB 565S U/R4 565' Y

ABS RRS Y

Y Y

Y Y

SJE/JOD 19228 20 1-PNLA-009-0036A PANEL 1-9-36A UI CB 593' Ut AIR 593'Y ES GRS Y

Y Y

Y Y

SJE/JOD 19229 18 1-LPNL-925-0247B LOCAL PANEL 1-25S247B (CAD N2 SUPPLY PANEL B)

U1RB 621'-3 Q/R4 621'-3 N

ABS RRS Y'

Y Y

Y SJE/JOD 2

19230 18 11LPNL-925-0007A LOCAL PANEL 1-25-7A U1RB 541'-6 SW CORNER 541' Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19231 18 11LPNL-925-0007B LOCAL PANEL 1-25-7B U1RB 541'-6' SW CORNER 541' Y

BS GRS Y Y

Y

[

Y SJE/JOD 19232 14 1-HS74-101B HANDSWITCH FOR 1-FCV-74-101 (11055)

U1RB 565' T/R6 580 Y -

BS GRS Y

Y Y

Y Y

FEIRLT 19239 18 1-TS-64-68 HANDSWITCH FOR 1-CLR-67-917 (14001)

UIRB 541'-6 SW CORNER 541' Y

BS GRS Y

Y Y

Y Y

FE/RLT 19240 18 1-HS-64-69 HANDSWITCH FOR 1 CLR-67-918 (14013)

UIRB 541'-6 SE CORNER 541' Y

3S GRS Y

Y Y

Y Y

FE/RLT 19241 18

!-TS-64-70 HANDSWITCH FOR 1-CLR67-921 (14003)

U1 RB 541'-6 SW CORNER 541' Y

es GRS Y Y

Y Y

Y FE/RLT 19242 18 1-HS-64471 HANDSWITCH FOR 1 CLR-67-922 (14015)

U1RB 541'-6 SE CORNER 541' Y

ES GRS

_ Y Y

Y Y

FE/RLT 19243 14 1HS-69-2B HANDSWITCH FOR 1 FCV-69-2 (13033)

U1RB 593 RS/S 593 Y

8 S

GRS Y BS Y

Y FE/RLT APPENDIX D FACILITY RISK CONSULTANTS, INC.

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?--

19244 14 1-HS-71-18B HANDSWITCH FOR 1-FCV.71'18 (13039)

U1 RB 519' NW CORNER 519' Y

BS GRS Y

Y Y

V V

FE/RLT 19245 01 1lHS-71-2B HANDSWITCH FOR 1-FCV.71-2 (13037)

U1 RB 593' RIR1 593' 8S GRS Y

N/A V

M Y

FE/OD 3

19246 14 1-HS-73-27 HANDSWITCH FOR 1-FCV-73-27 (13043)

U1 RB 519' HPCI 519' Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19247 18 1-HS-73-3B HANDSWITCH FOR 1-FCV-73-3 (13041)

U1 RB 519' TORUS 565' Y

aS GRS V

V Y

Y V

FE/RLT 19248 18 1-HS-73-81B HANDSWITCH FOR 1-FCV-73-81 (13042)

U1 RB 519' TORUS 565' Y

BS GRS Y

Y Y

Y Y

FE/RLT 19250 14 1-HS-74-12B HANDSWITCH FOR 1 -FCV-74-12 (11011)

U1 RB 519' SW CORNER 519' Y

8_

GRS V

V V

V V

FE/RLT 19251 14 1-HS-74-13B HANDSWITCH FOR 1-FCV-74-13 (11012)

Ul RB 541'-6' SW CORNER 541' V

BS GRS V

V Y

Y V

FE/RLT 19252 14 1 -HS74*11B HANDSWITCH FOR 1 -FCV-74-1 (11001)

U1 RB 519' SW CORNER 519' Y

BS GRS Y

Y_

Y FE/RLT 19253 14 1-HS-74-24B HANDSWITCH FOR 1-FCV-74-24 (11029)

U1 RB 519' SE CORNER 519' Y

BS GRS Y

V V

V Y

FE/RLT 19254 14 1-HS-74-25B HANOSWITCH FOR 1-FCV-74-25 (11030)

UtRSB 541' SE CORNER 541' Y

BS GRS Y

Y FE/RLT 19255 14 1-HS-74-2B HANDSWITCH FOR 1-FCV-74-2 (11002)

U1 RB 541'-6 SW CORNER 541' Y

BS GRS Y

V Y

Y Y

FE/RLT 19256 14 1-HS-74-35B HANDSWITCH FOR 1 FCV-74-35 (11037)

U1 RB 519' SE CORNER 519' Y

BS GRS Y

Y Y

Y Y

FE/RLT 19257 14 1-HS-74-36B HANDSWITCH FOR 1 -FCV-74-36 (11038)

Ul AB 541' SE CORNER 541' Y

BS GRS Y

V V

V Y

FE/RLT 19258 18 1-HS-74-73B HANDSWITCH FOR 1-FCV*74-73 (11046)

U1 RB 519' TORUS 565' Y

BS GRS Y

Y Y

Y Y

FE/RLT 19260 18 1-HS-75-11B HANDSWITCH FOR 1-FCV-75-11 (15006)

U1 RB 519' NW CORNER 519' Y

BS GRS Y

Y Y

Y FE/ELT 19261 14 1-HS-75-22B HANDSWITCH FOR 1-FCV-75-22 (15010)

U1 RB 541' NW CORNER 541' Y

BS GRS Y

Y Y

Y Y

FE/RLT 19262 18 1-HS-75-23B HANOSWITCH FOR 1-FCV 75-23 (15012)

U1 RB 593' P/R4 593' BS GRS Y

Y Y

Y

_FE/RLT 19263 18 1-HS-75-2B HANDSWITCH FOR 1-FCV*75-2 (15001)

Ut RB 519' NW CORNER 519' Y

BS GRS Y

Y Y

Y Y

FE/RLT 19264 18 1-HS-75-30B HANDSWITCH FOR 1-FCV-75-30 (15015)

Ul RB 519' NE CORNER 519' Y

8S GRS Y

V Y

Y V

FE/RLT 19265 18 1-HS-75-39B HANDSWITCH FOR 1-FCV-75-39 (15020)

U1 RB 519' NE CORNER 519' Y

Rs GRS Y

Y Y

Y V

FE/RLT 19266 14 1-HS-75-50B HANDSWITCH FOR 1-FCV-75-50 (15024)

U1 RB 541'-6 NE CORNER 541' Y

BS GRS V

Y Y

Y Y

FE/RLT 19267 18 1*HS-75-51B HANDSWITCH FOR 1-FCV-75-51 (15026)

Ut RB 593' P/R4 593' Y

BS GRS Y

Y Y

Y FE/RLT 19268 14 1-HS-78-61B HANDSWITCH FOR 1-FCV-78-61 (11026)

U1 RB 621' R5/S 621'-3 Y

ABS RRS Y'

Y

- F FE/JOD 2

19269 14 1-HS-64*72 HANDSWITCH FOR 1-CLR-67-919 (14002)

Ut RB 541'-6' NW CORNER 541' Y

BS GRS Y

V Y

V V

FE/RLT 19270 14 1-HS-64-73 HANDSWITCH FOR 1-CLR-67-920 (14014)

Ut RB 541' NE CORNER 541' Y

BS GRS Y

V V

V V

FE/IRLT 19271 18 1-TS-64-68 TEMPERATURE SWITCH FOR 1 CLR-67-917 (14001)

Ut RB 541' SW CORNER 541' Y BS GRS Y

V V

Y V

SJE/JOD 19272 18 1-TS-64-69 TEMPERATURE SWITCH FOR 1-CLR-67-918 (14013)

Ul RB 541' SE CORNER 541'-6 Y

BS GRS Y

y Y

V SJE/JOD 19273 18 1 -TS-64470 TEMPERATURE SWITCH FOR 1-CLR-67-921 (14003)

U1 RB 541' SW CORNER 541'-6. Y BS GRS Y

Y V

Y V

SJEiJOD 19274 18 1-TS-64471 TEMPERATURE SWITCH FOR 1-CLR67-922 (14015)

Ut RB 541'-6 SE CORNER 541'-6" B

S GRS Y

Y SJE/JOD 19275 18 1*TS 1-17A MAIN STEAM VAULT TEMPERATURE SWITCH Ut RB 565 MSVLT N/T3 593' Y

DOC RRS Y

N/A Y

Y.

Y.

SJE/JOD 1, 3 19276 18 11TS-1-17B MAINSTEAM VAULTTEMPERATURESWITCH Ut RB 565' MSVLTN/T3 593' Y

DOC RRS Y

N/A

-Y Y.

SJE/JOD

1. 3 19277 18 1 TS-1-17C MAIN STEAM VAULTTEMPERATURE SWITCH U1 RB 565' MSVLT N/T3 593 Y-D 00 RRS Y

N/A Y.

Y.

SJE/JOD 1, 3 APPENDIX D FACILITY RISK CONSULTANTS, INC.

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R 40" PC S

OKI AK OK:'~ OK?:::.':::O 19278 118 1 1-TS-1-1 7D MAIN STEAM VAULT TEMPERATURE SWITCH Ul RB 565' MSVLT N/T3 593' Y

DOC RRS JY N/A JY Y'

Y' SJE/JOD 1.3 19279 118 11.TS-1-29A MAIN STEAM TUNNEL TEMPERATURE SWITCH Ul TB 565' MSTNL K1T3 580' V

BS GRS VY V

Y Y

V SJE/JOD 19280 118 I1.TS-1-29B MAIN STEAM TUNNEL TEMPERATURE SWITCH UlITS 565' MSTNL KJT3 580' Y

BS GRS VY V

V V

Y SJE/JOD 19281 1 8 1-TS-1-29C MAIN STEAM TUNNEL TEMPERATURE SWITCH Ul TB 565' MSTNL K/T3 580' Y

BS GRS VY Y

Y V

V SJEJJOD 19282 18 I-TS-1-29D MAIN STEAM TUNNEL TEMPERATURE SWITCH Ul TS

.565' MSTNL K/T3 1580' Y

E~S GRS IY Y

Y V

V SJE/JOD 19283 1 8 1 -TS-1 -40A MAIN STEAM TUNNELTEMPERATURE SWITCH Ul1TSB 606' MSTNL KTT3 606' Y

IBS GRS Y

Y Y

V Y

SJE/JOD 19284 1 8 1-TS-1-40B MAIN STEAM TUNNELTEMPERATURE SWITCH Ul TB 1606!

MSTNL K/T3 506' V

B.3 GRS Y

V Y

JY Y

JSJE/JOD 19285 118 11-TS-1-40C MAI NSTEAM TUNNEL TEMPERATURE SWIrCH U TS 1606' MSTNL K/T3 606 Y

BS GRS Y

Y V

V V

JSJElJOD 19286 1 8 I-TS-1-40D MAIN STEAM TUNNEL TEMPERATURE SWITCH UITS 1606 MSTNL K/T3 606' Y

BS GRS V

V Y

V V

SJE/JOD 19287 18 1-TS-1-54A MAIN STEAM TUNNEL TEMPERATURE SWITCH U TS 634 MSTNL KfT3.630' N

ABS RRS N

Y V

V N

SJE)OD 19288 1 8 1-TS-1-54B MAIN STEAM TUNNEL TEMPERATURE SWITCH Ut TS 634' MSTNL KIT3 630' N

ABS FIRS IN Y

V 2

N SJElJOD 19289 18 1-TS-1-54C MAIN STEAM TUNNEL TEMPERATURE SWITCH Ul1TS 634' MSTNL K`T3 630' N

JABS RRS N

V Y

V IN SJE/JOD 19290 1 8 1-TS-1-54D MAIN STEAM TUNNEL TEMPERATURE SWITCH Ul TS 634' MSTNL K/T3 630' N

ABS RRS N

V V

V N

SJE/JOD 19291 18 11-TS-64-72 TEMPERATURE SWITCH FOR 1-CLR-67-919 (14002)

UI RB 1541'-6' NW CORNER 541'-6' Y

as GRS Y

V Y

V V

S&JE/OD 1922 1 8 1-TS-64-73 TEMPERATURE SWITCH FOR 1-CLR-67-920 (14014)

UlIRB 1541' NE CORNER.541'-6' Y

BS GRS Y

V V

V V

SJE/JOD 19294 14 1 -AMP-092-0007/41 A IRM CH.'A'VOLTAGE PREAMPLIFIER 7-34A U1RB 565' S/R3 565' Y

BS GRS V

V Y.

Y Y.

SJEIJOD 1,3 19295 1 4 I-AMP-092-0007/41B IRM CH. B" VOLTAG EPR EAMPLIFf ER 7-34 B UtRB 565' SIR3 555' Y

BS GRS Y

Y Y.

Y Y.

SJE/JOD 1,

1926 1 4 1-LPNL-925-0027 PANELI1-25-27 IRM PREAMP. RPS I U1RS 565' S/R3 565' Y

BS GRS Y

Y Y

lY Y

SJE/JOD 19297 14 1-AMP-092-0007/41C IRM CH. C VOLTAGE PREAMPUIFIER 7-34C UlRB 577' O/RS 577' Y

BS GRS Y

Y Y.

Y Y.

SjE/JOD 1,3 19298 14 I-AMP-092-0007/410 IRM CH. 'D` VOLTAGE PREAMPLIFIER 7-34()

UIRB 577' O/R5 577' Y

BS GRS Y

Y Y.

Y y'

JE/OD 1,3 19299 1 4 1-LPNL-925-0061 PANEL 1-25-61 IRM PREAMP. RPSII1 UIRB 577' Q/RS 577' Y

B5 GRS Y

Y Y

Y SJE/JOD 19300 20 1-NM'92-7141A CHANNEL A"IRM INDICATOR Ul CB 617' MCR 617' N

ABS RRS Y'

N/A Y

Y.

Y FEISJE 1,2,3 19301 20 1-NM-92-7/41B C-HANNEL 'B IRM INDICATOR UI CB 617' MCR 617 N

ABS RRS Y,

N/A Y

Y.

Y.

FE/S.JE 1,2,3 19302 20 1-NM-92-7/41C CHANNEL C IRM INDICATOR Ul CB 517' MCR 617' N

ABS RRS Y'

N/A Y

Y.

Y.

FE/SJE 1,2,3 19303 120 1I-NM-92-7/41D CHANNEL'D'IRM INDICATOR UI CB 1617' MCR 617' N

IABS RRS Y'

N/A Y

Y.

Y*

JFEISJE 1,2,3 19304 20 1-PNLA-009-012 PANEL 1-9-12 CB 617' U1 MCR 617' N

JABS RRS lY' Y

Y Y

Y SE/JOD 2

19305 15 I1-BATD-283-00OAI 24V NEUTRON MONITORING BA1TERY, Ul CHANNEL A CB 593' BAT RM 1 593' Y

BS GRS Y

Y Y

Y V

JE/JOD 19306 15 1-BATD-283-000B1 24V NEUTRON MONITORING BATTERY, Ul CHANNEL B CB 593' BAT RM 1 593' Y

BS GRS Y

Y VY Y

Y SJE/J0D 19307 16 1-CHGD-283-A-I1 24V NEUTRON BATTERY CHARGERS Al-I' CB 593' BAT SD RM 1 593' Y

8S GRIS Y

N IN Y

N SJE/JOD 19308 1 6 1-CHGD-283.A2-1 24V NEUTRON BATrERY CHARGERS A241 CB 593' BAT BD RM 1 593' Y

BS GRS Y

N N

Y N

SJE/JOD 19309 116 11-CHGD-283-BI-1 124V NEUTRON BATTERY CHARGERS B1-1 CB 593' BAT BD RM 1 593' VY 55 GRS Y

N N

jSJEIJOD 19310 116 11-CHGO'283-B2'1 124V NEUTRON BAITERY CHARGERS B2-1 CB 593' BAT BDRM i 593'

_Y IBS GR Y

N SJE/JOD APPENDIX D APPENIX DFAcILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page D-17 ssE E

EFLOOR L

IBASE BELO I P D

C

[

1 INTER oIE :TE NO.,.

{CL._:

DECPTO LV._

___jELE tl4o?:4o?

SPEC -- SPEC::-

OKI7 A 0

OKJ2

OK?:. jOK?.

19312 14 1-HS-71-17B HANDSWITCH FOR 1-FCV-71-17 (13074)

U1 RB 519' NW CORNER 519' Y

BS GRS Y

Y V

N N

FE/RLT 19313 20 1-HS-1-56A HANDSWITCH FOR 1-FCV-1-56 (13075)

Ul CB 61T Ul MCR 61T N

ABS RRS Y'

N/A N

y FE/JOD 2, 3 19314 14 1-HS-73-26B HANDSWITCH FOR 1-FCV-73-26 (13076)

U1 RB 519' SW CORNER 519' Y

BS GRS N

Y Y

FERILT 19316 20 1-HS-77-2A HANDSWITCH FOR 1-FCV-77-2A (13080)

Ui CB 61T U1 MCR 61T N

ABS RRS Y'

N/A

_ FE/JOD 2,3 19317 20 1-HS-77-15A HANDSWITCH FOR 1-FCV-77-15A (13081)

UI CB 617 U1 MCR 61T N

ABS RRS Y'

N/A Y

Y Y

FEJOD 2,3 19318 20 1-HS-64-18 HANDSWITCH FOR 1-FCV-64-18 (13082)

U1 CB 617 U1 MCR 61T N

ABS RRS Y'

N/A Y

_ Y FE/JOD 2.3 19319 20 1-HS-64-19 HANDSWITCH FOR 1-FCV-64-19 (13083)

Ui CB 61T U1 MCR 61T N

ABS RRS Y'

N/A Y

Y N

FE/JOD 2, 3 19320 20 1-HS-76-18 HANDSWITCH FOR 1-FCV-76-18 (13084)

U1 CB 617T U1 MCR 617T N

ABS RRS Y'

N/A Y

Y

_ FE/JOD 2, 3 19321 20 1-HS-76-19 HANDSWITCH FOR 2-FCV-76-19 (13085)

U1 CB 61T Ul MCR 617 N

ABS RRS Y'

N/A Y

N N

FE/JOD 2,3 19323 14 1-JB40375 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 519' SE CORNER 519' Y

BS GRS

_' Y N'

y FE/RLT 19324 14 I1JB-0662 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1RB 541' SE CORNER 541' N

8BS GRS N'

N N'

Y Y

FE/RLT 19325 14 14B-0658 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 541'-6' SE CORNER 541' Y

N BS GRS N

FE/RLT 19326 14 14JB-1032 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 593' S/R3 593' N

BS GAS Y

Y N

N Y

FEIRLT 19327 14 14JB-1095 JUNCTON BOX (TERM BLOCK)

• SEALED BOX U1 RB 565' S/R6 565' N

BS GRS Y

N N

FEMRLT 19328 14 14JB-1559 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 565' T/R6 565' BS GAS FE/JOD 19329 14 1-JB-0670 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RB 541'-6' NE CORNER 541' Y

BS GAS Y

Y N

Y' N

FE/RLT 19330 14 14B-0791 JUNCTION BOX (TERM BLOCK) -SEALED eox Ul RB 519' NW CORNER 519' 8S GAS

_Y Y

NY V

FE/RLT 19331 14 14JB-0681 JUNCTION BOX (TERM BLOCK)

• SEALED EOX U1 RB 541'-6' NW CORNER 541' Y

BS GAS Y

Y NY Y

Y FE/RLT 19332 14 1-CS-75-9B CONTROL STATION FOR 1-HS-75-9B U1 RB 519' NW CORNER 519' N

BS GAS Y

Y Y

N N

FE/RLT 19333 14 1-CS-75-37B CONTROL STATION FOR 1-HS-75-37B U1 RB 519' NE CORNER 519' Y

BS GRS Y

Y N

N N

FE/RLT 19334 14 IJB-1231 JUNCTION BOX (TERM BLOCK) -SEALED BOX U1 RS 565' S/R6 565' Y

BS GAS Y

Y Y

Y Y

FE/RLT 19351 14 14JB-3828 JUNCTION BOX FOR 1-TS-1-29A U1 TB 565' MSTNL K/T3 580' Y

BS GAS Y

N' N

N N

SJEIJOD 19352 14 14JB-3829 JUNCTION BOX FOR 1-TS-1-295 U1 TB 565' MSTNL K/T3 580' 5

BS GAS NY N

Y N

V SJE/JOD 19353 14 1.JB-3830 JUNCTION BOX FOR 1-TS-1-29C U1 TB 565 MSTNL K/T3 580' N

BS GAS N'

N N

Y N

SJENJOD 19354 14 1-JB-3831 JUNCTION BOX FOR 1-TS-1-29D U1 TB 565' MSTNL KtT3 580' N

8BS GAS I'Y Y

Y

_' SJE/JOD 19355 14 1-JB-3801 JUNCTION BOX FOR'1-TS-1 -40A U1 TS 606' MSTNL K/T3 606' N

BS GRS N'

N Y

Y N

SJE/JOD 19356 14 1JB-3802 JUNCTION BOX FOR 1-TS-1-40B U1 TB 606' MSTNL KtT3 606' e s GRS NY Y

N N

N SJE/JOD 19357 14 1-JB-3803 JUNCTION BOX FOR I-TS-1-40C U1 TB 606' MSTNLKIT3 606' N

BS GAS N'

N N

N N

SJENJOD 19358 14 1.JB-3804 JUNCTION BOX FOR 1 -TS-1 -40D U1 TB 606' MSTNL K/T3 606' N

BS GAS N'

V Y Y

SJE/JOD 19359 14 14B-3813 JUNCTION BOX FOR 1-TS-1-54A U1 TB 634' MSTNL KIT3 630' N

GERS RAS N

V N

N N

SJE/JOD 19360 14 lJB-3814 JUNCTION BOX FOR 1-TS-1-54B U1 TB 634' MSTNL K/T3 630' N

GERS RAS Y

N N

SJE/JOD 19361 14 14JB-3815 JUNCTION BOX FOR 1-TS-1-54C U1 TB 634' MSTNL KIT3 630' N

GERS RRS N

Ny Y

SJE/JOD APPENDIX D FACruTY RISK CONSULTANTS, INC.

TVA/BFN-01-R -004 Revision 0 September 23, 2004 Page D-1 8 1SE 1

I

-J-AI SSEL EQ. lEQUIPENT; l

Es RIPTI

l INTER EluP TEAM FLORSOCTINIASTBEOWCANO-CP CA AEH NO...

DECRPIO 8D:

LEELEV.

'-40'?'

ISPEC ISPEC

[OKI OK?:

R OK?

OK?.:

OKNOE 19362 14 1-B-3816 JUNCTION BOX FOR 1.TS-1-54D U1 TB 634' MSTNL K/T3 630 N

GERS RRS Y

Y Y

V Y

SJE/JOD 19412 03 0-BOAA-211-OOOOA 4KVSHDN BO A Ut R3 621' R/R2 621'-3 N

ABS RRS YV V

Y Y

Y SJE/JOD 2

19413 03 0-BDAA-211-O0OOB 4KVSHDN BD B Ui RB 593 Q/R2 593 V

BS GRS Y

V V

V Y

SJE/JOD 19418 02 1-BDBB-231-0001A 480VSHDN BD 1A U1 RB 621'-3 SiRi 621' N ABS RRS Y'

V Y

N N

SJE/JOD 2

19419 02 1-BOBB-231-0001B 480VSHON BD 1B U1 RB 621'-3 S/R2 621' N ABS RRS Y Y Y

y SJE/JOD 2

19423 01 1-BOBB-268-0001A 480V RMOV 0D IA U1 R3 621'-3 R/R1 621-3 N

DOC RRS V

Y Y

Y V

SJE/JOD 19424 01 1-BDBB-268-OOO1B 480V RMOV BD 1B U1 RB 593 RIR1 593' Y

0D0 RRS Y

V Y

Y Y

SJE/JOD 19437 14 0-BDD0-280-0001 250V BATTERY BD 1 U1 RB 593' PIR4 593 Y

DOC RRS Y

V V

Y SJE/JOD 19492 20 0-LPNL-925-0045A PANEL 25-45A UI RB 621' S/R1 621' N ABS RRS V.

Y Y

V Y

SJE/JOD 2

19493 20 0-LPNL-925-0045B PANEL 25-45B U1 RB 593 R/R2 600 Y

BS GRS Y

V V

V Y

SJE/JOD 19516 14 0-XSW-248-0001 250V MAIN BATT CHGR OUTPUT XFR SW 1 Ul RB 593' P/R4 598' V

BS GRS Y

i V

V Y

SJE/JOD 19519 15 0-BATA-248-OOOOA 250V BATTERY SB-A Ul RB 621'-3 S/R2 621' N GERS RRS Y

i Y

V Y

SJE/JOD 19520 14 0-PNLA-248-A 250V DISTRIBUTION PANEL SB-A U1 RB 621'-3' S/R2 621 N DOC RRS Y

Y V

Y Y

SJE/JOD 19521 16 O-CHGA-248-OOOOA 250V BATTERY CHARGER SB-A U1 RB 621' S/R2 621' N DOC RRS Y

V V

V V

SJE/JOD 19522 15 0-BATA-248-OOOOB 250V BATTERY SB-B U1 RB 621'-3 S/R2 621'-3 N

GERS RRS Y

Y Y

V V

SJE/JOD 19523 14 0-PNLA-248-B 250V DISTRIBUTION PANEL SB-B U1 RB 621' R/R2 621' N DOC RRS Y

V V

V V

SJE/JOD 19524 16 0-CHGA-248-0000B 250V BATTERY CHARGER SB-B U1 RB 621-3 R/R2 621' N DOC RRS V

V Y

V V

SJE/JOD 19534 16 0-CHGA-248-0001 250V BATTERY CHARGER 1 Ul RB 593' P/R4 593' Y

BS GRS Y _

V Y

V SJE/JOD 19537 15 0-BATA-248-0001 250V MAIN BATTERY 1 Ul RB 593' P/R4 593' BS GRS V

Y V

V SJE/JOD 19594 04 1-XFA-231-TSlA 4KV/480VTRANSFORMERTSlA U1 RB 621' T/R1 621 N ABS RRS r

Y Y

Y Y

SJENJOD 2

19595 04 l-XFA-231-TS18 4KV/460VTRANSFORMERTSIB Ul R3 621'-3 TIR1 621-3 N

ABS RRS Y

V V

V Y

SJEIJOD 2

19709 20 l-PNLA-009-0020 PANEL 1-9-20 Ul CB 617 Ul MCR 617T N ABS RRS Y

V V

Y V

SJEIJOD 2

19716 18 l-LPNL-925-0223 LOCAL PANEL 1-25-223 - RAW COOUNG WATER PANEL U1 RB 593' Q/R3 593' 8 BS GRS Y

Y V

V SJEIJOD 19729 14 1-HS-23-57B HANDSWITCH FOR 1-FCV-23-57 Ul RB 565' R6/S 565 3

BS GRS Y

Y Y

y Y

RLT/FE 19791 20 1-PNLA-009-0008 PANEL 1-9-8 U1 CB 617 U

IMCR 617" N

ABS RRS V

Y Y

Y SJEIJOD 2

19792 18 1-LPNL-925-006B LOCAL PANEL 25-6B Ul RB 593' RS/P 593' V

83 GRS Y

N N

V N

SJE/JOD 19794 04 1 -XFA-099-0010 RPS REGULATING TRANSFORMER TRP-1 Ul CB 593 BATT BD 1 593' V

ABS GERS Y

N N

V N

SJEIJOD 19795 14 1-FUDS-099-0001CA RPS REG XFMR DISCSW FROM480VRMO/BD 1B U1 CB 593' BATT BD 1 593' 85 GRS V

V Y

Y SJE/JOD 19796 04 TUPI UNITPREFERREDXFMR U1 CB 593' BATT BD 1 593' V

BS GRS Y

Y V

Y Y

SJE/JOD 19797 14 1-FUDS-099-0001CB RPS BUS XFMR DISC SW Ul CB 593' BATT BD 1 593' BS GRS Y

N N

N SJE/JOD 19801 14 1 JB-6439 JUNCTION BOX SERVING 1-TE-161A U1 RB 519' TORUS 528 BS GRS Y

YY SJE/JOD 19802 14 1-8JB440 JUNCTION BOX SERVING 1TE-161B Ul RB 519' TORUS 528' 85 GRS Y

-Y SSJEEJOD APPENDIXD FACILJY RISK CONSULTANTS, INC.

TVA/BFN-01-R-004 Revision 0 September 23, 2004 Page D-19

'DESCRIPTION-1AMBOSEEB NO7 -

~ICLTIoQN M LT I

D ID CAANC IFNTRIE NlCI OU K llIP ITEAM lOTES NO.

L EILEV_________________________.E.:

'_t~%~C tK~1K ROK? jOK?OK ?j 19803 14 11JB-6441 JUNCTION BOX SERVING 1'TE-161C U1 RB 519' TORUS 528' Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19804 14 IJB-6442 JUNCTION BOX SERVING 1-TE-161D U1 RB 519' TORUS 528' BS GRS VY Y

V Y

SJE/JOD 19805 14 1JB-6443 JUNCTION BOXSERVING 1TE-161E Ui RB 519' TORUS 528' Y

BS GRS V

Y Y

.Y SJE/JOD 19806 14 1JB-6444 JUNCTION BOX SERVING 1 TE-161F U1 RB 519' TORUS 528' Y

BS GRS Y

Y V

Y SJE/JOD 19807 114 1JB6445 JUNCTION BOX SERVING 1-TE-161G UlRB 519' TORUS 528' Y

_5 GRS V

V Y _

SJEIJOD 19808 14 11JB-6446 JUNCTION BOX SERVING 1TE-161H U1 RB 519' TORUS 528' Y

BS GRS Y

Y Y

Y Y SJE/JOD 19809 14 11-JB-6453 JUNCTION BOX SERVING 1-TE*162A U1 RB 519' TORUS 528' Y

BS GRS Y

S

/

SJE/JO

=

19810 14 11JB-6454 JUNCTION BOX SERVING 1 TE-162B Ui RB 519Y TORUS 528' Y

BS GRS Y

Y Y

Y Y

SJEIJOD 19811 14 1JB-447 JUNCTION BOX SERVING 1-TE.162C U1 RB 519' TORUS 528' Y

aS GRS VY Y

Y Y

SJE/JOD 19812 14 1JB-6448 JUNCTION BOX SERVING 1 -TE*162D Ui RB 519' TORUS 528' Y

BS GRS V

SJE/JOD 19813 14 1JB-6449 JUNCTION BOXSERVING 1-TE-162E U1 RB 519' TORUS 528' Y

BS GRS V

Y Y

Y Y

SJEIJOD 19814 14 1-JB-6450 JUNCTION BOX SERVING 1-TE-162F U1 RB 519' TORUS 528 Y

BS GRS Y

Y Y

Y Y

SJE/JOD 19815 14 ltJB-6451 JUNCTION BOX SERVING 1-TE-162G U1 B 519 TORUS 528' Y

6 GRS Y

Y Y

Y Y

SJE/JOD 19816 14 1JB-6452 JUNCTION BOX SERVING 1-TE.162H Ul RB 519' TORUS 528' Y

BS GRS Y

Y y

y SJE/JOD NOTES:

1.

Based on the walkdown evaluation and available existing documentation, the item passes the GIP screening criteria and a conditional Y (Y') Is assigned on the SVDS. The final configuration wDI be verified in the Area Turnover walkdowns (see Appendix H).

2.

A special exception to enveloping of seismic demand spectrum Is Invoked per Section 4.2 of the GIP. The capacity spectrum envelops the demand spectrum for frequencies at and above a conservatively estimated lowest natural frequency of the component See discussion in Chapter 4 of this report. The Intent of the capacity versus demand screening criteria Is met.

3.

The 'CAV OK? criterion is marked with 'NIA' because thb Rtem of equipment Is included within the evaluation of a separate SSEL Rem as *rule-of-the box' and that separate SSEL item was found to be acceptable.

4.

The type or configuration of this equipment tem is not specfica1ly covered by the SOUG GIP screening criteria, so this equipment Rem is documented as an outrier.

APPENDIX D FACILITY RISK CONSULTA TS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page E-1 APPENDIX E RESULTS OF THE CABLE TRAY AND CONDUIT RACEWAY REVIEW FACIIJTY RISK CONSULTANTS1 INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page E-2 APPENDIX E: RESULTS OF THE CABLE TRAY AND CONDUIT RACEWAY REVIEW The scope of the review covers all the electrical raceway systems at BFN-1 not previously covered in the BFN-2 & 3 A-46 program. All common areas between Units 1, 2 and 3 as well as some areas in Unit 1 were evaluated in the BFN-2 & 3 A-46 program. All of the required modifications as a result of those reviews have been implemented. The areas previously covered are:

U3 Reactor Building (all elevations, including Drywell)

U3 Diesel Generator Building Control Bay (all elevations), Units 1, 2, and 3

• Stand By Gas Treatment (SBGT) Building

• Off Gas Building

• Intake Pump House

• Cable Tunnel Reactor Building, Units 1 and 2, EL 664 Ft.

U2 Reactor Building (all elevations except El. 664 Ft., and including Drywell)

U1/U2 Diesel Generator Building Based on the BFN-1 A-46 evaluations performed per the requirements of the GIP, there are no indications of any generic seismic concerns with the cable tray and conduit systems at BFN-1.

Furthermore, all analytical evaluations performed to resolve the outliers and the limited analytical reviews (LAR) were performed using a 100% fill for the cable trays and conduits.

Therefore, addition of cables to existing systems is acceptable as long as the raceways are not overfilled beyond their physical capacity.

Table E-1 provides a summary of the results.

FACITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page E-3 Table E-1: Results of the Cable and Conduit Raceway Review

....;.t i:.

Locaion-AR/Outlier WV Cal.Ta.Tp ofCnen.vlaeda.oi.cto.Rqie Maineac eured Throughout RB639-01 Conduit Wall supports with %4" anchors Acceptable EL 621 '-3" I Between Q&R East of R2 RB621 -02 Conduit Bent 3h4" rod Acceptable_____________

EL 621t '-3" / Between R3&R4 Adjacent RB621 -03 Conduit Broken Weld Re-weld the Support using /4" to NorthWalliwel 3n lon EL 621'-3" RB621 -04 Cable Tray Umited analy~cal review Acceptable______________

Two Uers of trays not using Rework tray connections to EL 593' / Between R4&R5 at T RB593-01 Cable Tray Tee section at a tray meet NEMA Standards intersection EL 593'I/ Near R5 & S RB593-02 Cable eray rod msngfr Acceptable EL593' R3&T RB593-03 Conduit Halnge offsetfrom w al anchors Acceptable EL 593' / East face of T&R2 RB593-04 Conduit Short rod trapeze Acceptable EL 593' RB593-05 Cable Tray Umited analytical review Acceptable EL 593' RB593-06 Cable Tray Umited analytical review Acceptable EL 593' RB593-07 Cable Tray Umited analytical review Acceptable meetl EL 593' RB593-08 Colduit Umited analygmcal review Acceptable EL 593' RB593-03 Conduit Umited analytical review Acceptable EL 565'/ Southwest stairwell RB565-04 Conduit Improper anchor installation Acceptable EL 565'/ Above West CR Platform RB565-02 Conduit Loose cupling rTighten threaded coupling FACILITY RISK CONSULTANTS, lNQ

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page E-4

..................u.

.A./O.lie.

onui!

ype: ofConcern Evluadas MdfctoReirdaneaceeqrd Loca ion.

C Provide clamp to the 3" EL 565'I Above MCC along West Wall RB565-03 Conduit Overspan conduit to attach to existing strut for the three 1" conduits N/A RB565-04 Number not used EL 565' / West of R2&Q RB565-05 Conduit Anchorage Detail Acceptable EL 565' RB565-06 Cable Tray Umited analytcal review Acceptable EL 565' RB565-07 Conduit Umited analytcal review Acceptable EL 565' RB565-08 Conduit Umited analytical review Acceptable Long vertical drop for 1 @1" Provide new lateral restraint Re-install missing clamps to and 1 @1-112" conduits may for both conduits (5' below existing conduit strut support sway and cause damage to overhead platform support EL 519' / Northeast Comer Room R8519-01 Conduit flex connection to core spray steel).

pump motor. In additon, the last (existing) support for both conduit is disengaged.

Long vertical drop for 3" Provide new lateral restraint EL 519'/ Northeast Comer Room RB519-02 Conduit conduit may sway and cause for conduit (5' below overhead damage to flex connection to platform support steel).

core spray pump motor.

Long vertical drop for 2@1" Provide new lateral restraint and 1 @3" conduits may sway for all 3 conduits (5' below EL 519'/ Northwest Comer Room RB519-03 Conduit and cause damage to flex overhead platform support connection to core spray steel).

pump motor.

FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page F-1 APPENDIX F RESULTS OF THE PLANT OPERATIONS DEPARTMENT REVIEW OF THE SSEL AGAINST THE PLANT OPERATING PROCEDURES FActun' RISK CONSULTANT, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page F-2 F.1 Summary The BFN-1 Operations Department review of the SSEL against plant operating procedures will be completed after:

Major plant modifications are complete.

Operating procedures for BFN-1 are completed.

The plant operations department review will be performed as a desk top study of the applicable plant normal and emergency operating procedures. The review will check whether all equipment called out in the operating procedures for the selected path are included on the SSEL. The review will also verify that there are no paths from which an operator could not recover with the selected set of SSEL equipment. Common and shared BFN-2 and BFN-3 plant systems will be reviewed in light of a scenario involving simultaneous shutdown of all three operating units with loss of offsite power.

Plant operating procedures and/or the SSEL will be revised as required based on the results of the plant operations department review.

The planned schedule for the plant operations department review of the SSEL is as follows:

temom....p..i.

-in Da Completion of major modifications 4/30/05 Completion of BFN-1 plant operating 6/30/05 procedures Review of BFN-1 SSEL against plant 8/30/05 operating procedures Review of common and shared plant systems for simultaneous 3 unit 8/30/05 shutdown with loss of offsite power.

Completion of operations department 8/30/05 review of the SSEL FACILiTY RiSK CONSULTANTSt INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page F-3 The BFN-1 Operations Department performed a preliminary review of the SSEL based on their working knowledge of the plant design changes that are going to be implemented prior to plant start-p. They recommended the following changes to the SSEL. Note that these recommendations have been implemented in the SSEL as shown in this report (Appendix B).

• The Drywell header for CAD will be split and supply will be provided through separate penetrations. This configuration will provide redundant pressure relief.

• The CAD system, which is currently cut and capped to BFN-1, will be re-connected and tied into the two Drywell control air headers to supply the safety-related back-up.

• The Drywell control air system suction isolation valves will be deleted and capped.

FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September23, 2004 Page G-1 APPENDIX G INDEPENDENT PEER REVIEWER RESUME FACILITY RISK CONSULTANTSt INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page G-2 RESUME - Seismic Capability Engineer Independent Peer Reviewer Tennessee Valley Authority Browns Ferry Nuclear Plant Unit 1 Name:

James J. Johnson Bachelors Degree:

B. of Civil Engineering, 1967 Institution:

University of Minnesota, Minneapolis Advanced Degree:

M.S. (1969); Ph.D. (1972) Civil Engineering Institution:

University of Illinois, Urbana-Champaign Date and location of Seismic Adequacy Verification Training Courses:

USI A-46 Course:

SQUG Walkdown Screening & Seismic Evaluation Training Course Date:

June 22 - 26,1992 Location:

Charlotte, NC Seismic Course:

Seismic IPE Add-On Training Course IPEEEE Date:

July 27 - 29, 1992 Location:

Charlotte, NC Earthquake engineering experience applicable to nuclear power plants and in structural or mechanical engineering:

32 years (see attached resume)

Licensed Professional Engineer: Yes El No El States of Alabama & California FACILITY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page G-3 JAMES J. JOIINSON, PH.D., P.E.

PROFESSIONAL HISTORY James J. Johnson and Associates, President, 2001-Present EQECAT, Inc., San Francisco, California, Chairman, 1995-2001 EQE International, San Francisco, California, Chief Operating Officer, Executive Vice President, 1986-2001 NTSIStructural Mechanics Associates, San Ramon, California, Vice President, 1984-1986 Structural Mechanics Associates, San Ramon, California, Vice President, Project Manager, 1980-1984 Lawrence Liver7nore National Laboratory, Livermore, California, Project Manager, 1978-1980 General Atoinic Company, San Diego, California, Branch Manager, Staff Engineer, Senior Engineer, 1972-1978 PROFESSIONAL EXPERIENCE Dr. Johnson, President of James J. Johnson and Associates, is an independent consultant specializing in risk management consulting for operational and personnel risks due to natural hazards (earthquakes, wind storms, floods, etc.), terrorist perils, such as aircraft impact, vehicle and other bombs, chemical and biological agent releases, etc., and internally generated hazards (fires, explosions, chemical spills, etc.).

Dr. Johnson specializes in assembling and managing teams of experts to address complex inter-disciplinary issues and problems. Dr. Johnson draws from an extensive group of colleagues for team composition.

Dr. Johnson was Executive Vice President and Chief Operating Officer of EQE International, the fourth largest independent risk management consulting firm in the US, as rated by Business Insurance. EQE specializes in operational risk management and mitigation services by providing software, information/data, and consulting to it's clients. EQE's annual revenue exceeded $70 million during his tenure. The company has offices throughout the wvorld. Dr. Johnson, also, was responsible for the firm's insurance industry services. He served as Chairman, President and Chief Operating Officer of EQECAT.

Established in 1994, EQECAT provides catastrophic risk management services to the global insurance and reinsurance industries, including catastrophe modeling software, portfolio and single site analysis, risk management consulting, training, and information.

During the period 2001 September to the present (2004 May), Dr. Johnson has participated in numerous programs related to terrorist attack risk assessments.

Dr. Johnson was a key contributor to the development of EQECAT's terrorist risk assessment methodology, a fully probabilistic methodology whose result metrics are financial losses (average annualized losses and loss exceedance relationships).

The focus of his contributions were frequency of occurrence estimates by peril, by location (facility, city, state), and overall likelihood in the US; and the engineering methodologies (blast and explosion, chemical and biological releases, sabotage of critical facilities and infrastructure) and their application to terrorist attack scenarios. Dr. Johnson is a key contributor to the development of self-assessment guidelines for the terrorist attack of nuclear facilities (power plants, research facilities, spent fuel storage facilities). These guidelines are being developed, implemented, and training provided by the International Atomic Energy Agency (IAEA).

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page G-4 During this same period (September 2001 to the present), Dr. Johnson supported the independent review of: the TVA Sequoyah ISFSI pad/cask assemblage including soil-structure interaction effects; and the TVA Browns Ferry Unit I Recovery Programs of seismic 1111 systems interaction, A-46/IPEEE safe shutdown equipment list development, cable tray/conduit seismic evaluation.

In addition, Dr. Johnson has more than 30 years of experience in risk analysis for natural and man-made hazards. Dr. Johnson has participated in the development, implementation, and teaching of seismic risk and seismic margin assessment methodologies. He has participated in seismic PRAs of over 20 nuclear power plants. His participation encompasses many aspects including hazard definition, seismic response and uncertainty determination, detailed walkdowns, and fragility assessment. A major element of seismic PRAs and seismic margin assessments is best estimate response analyses. Dr. Johnson participated in the development of best estimate or median-centered response procedures and has participated in its application to over 60 nuclear facilities.

Dr. Johnson was responsible for several portions of the U.S.

Nuclear Regulatory Commission (NRC) Seismic Safety Margins Research Program (SSMRP) -- soil-structure interaction, major structure response, subsystem response, and the seismic analysis calculational procedures (SMACS).

Dr. Johnson has presented numerous seminars and training courses on beyond design basis events, including seismic PRA and seismic margin methodologies.

Recently, Dr. Johnson participated in a number of IAEA sponsored missions and activities, e.g., development of "Guidelines for the Self-Assessment of Safety and Security of Nuclear Installations," 2002-present; evaluation of the design for external events of the Korean Peninsula Energy Development Organization's (KEDO's) North Korean LWR project, Kumho, DPRK, and Taejon, South Korea, 18-29 June 2001; Technical Committee Meeting on Structural Safety of NPPs in Relation to Extreme Loads, Vienna, 4-8 December, 2000 and Expert Team Mission, Romania, 12-16 March 2001; and he participated in the U.S. NRC-sponsored Eastern European Regulatory Training in Hungary and Slovakia (February 1995). He also participated in a presentation sponsored by the China State Education Commission in cooperation with Tsinghua University and China National Regulatory Bureau of Nuclear Safety on seismic issues of nuclear power plant design and analysis wvhich was presented in Beijing, China (May 1994); and the International Atomic Energy Agency's Regional Training Course on re-evaluation of seismic safety of existing nuclear power plants in Paks, Hungary (May 1993).

Dr. Johnson has played a significant role in the development of general and plant-specific seismic evaluation procedures. This project participation has ranged from the SQUG Generic Implementation Procedure (GIP) to plant-specific procedures for the Savannah River Site. Procedures include criteria for assessing equipment and component functionality and structural integrity, seismic systems interaction, anchorage, and other issues.

Dr. Johnson has extensive theoretical and practical experience in the soil-structure interaction (SSI) analysis of major facilities and has written a comprehensive assessment of the state-of-the-art of SSI.

Most recently, Dr. Johnson authored "Soil-Structure Interaction," Chap. 10, and co-authored "Loss Estimation," Chap. 30, Earthquake Engineering Handbook, 2003. Dr. Johnson was a lecturer for the NATO Advanced Study Institute on Developments in Dynamic Soil-structure Interaction.

Dr. Johnson was principal investigator for EQE on the SSI modeling, predictive analysis, and resolution of measured and predicted response for the combined EPRI/NRC Lotung, Taiwan scale model project.

He has performed SSI analyses of a wide variety of surface and embedded structures using simplified to sophisticated substructure methods and linear and nonlinear finite element techniques. Nonlinear analyses included geometric effects (sliding and separation) and soil material behavior. He has made extensive use of comparative analyses and parametric studies to benchmark techniques and soil and structure configurations.

He has extensive experience applying SASSI and CLASSI to SSI analysis of major

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page G-5 facilities. Dr. Johnson was a consultant to the U.S. Nuclear Regulatory Commission (NRC) concerning revisions to the Standard Review Plan for seismic analysis and design.

In addition, Dr. Johnson was project manager for the U.S. NRC Structural Damping Research Program Dr. Johnson has developed, verified, maintained, and extensively applied several large computer programs to perform stress and seismic analysis. Among these are: MODSAP, a general purpose finite element program with special capability in the dynamic analysis of structures with localized nonlinearities; and SMACS, a probabilistic response analysis program for soil, structures, equipment, and piping systems.

Dr. Johnson was responsible for the analysis and design of components subjected to extreme internally and externally generated loading conditions.

This work includes seismic qualification of control room equipment and motor control centers, fuel handling components, core and core support structures, heat exchanger shell and tubes subjected to tube burst loadings, and shipping casks of irradiated fuel and equipment subjected to impact loading.

Dr. Johnson has taught Earthquake Engineering of Major Facilities at the University of California, Berkeley. This course covered all phases of the earthquake engineering process, including seismic hazard definition; seismic analysis and design of structures, equipment and tanks; and seismic risk analysis. Dr.

Johnson coordinated and taught portions of the SQUG training course that covered the seismic evaluation of equipment, cable trays and conduit, piping, anchorage, and seismic systems interaction.

EDUCATION University of Illinois: Ph.D. Civil Engineering, 1972 University of Illinois: M.S. Civil Engineering, 1969 University of Minnesota: B.C.E. Civil Engineering, 1967 REGISTRATION California: Civil Engineer Alabama: Civil Engineer AFFILIATI ONS American Society of Civil Engineers, Member Dynamic Analysis Committee Committee on Nuclear Standards, Seismic Analysis of Safety Class Structures, Author of ASCE 4-98, "SeismicAnalysis of Safety-Relaied Nuclear Structures and Comimentary."

Earthquake Engineering Research Institute Phi Kappa Phi Honor Society Sigma Xi PUBLICATIONS Dr. Johnson has over 120 publications. A detailed list is available upon request.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page H-1 APPENDIX H AREA TURNOVER WALKDOWN PUNCH LIST FACILITY RISK CONSULTANTS. INC.

TVAIBFN-01 -R-004 Revision 0 September 23, 2004 Page H-2 Appendix H: Area Turnover Walkdown Punch List Certain items of equipment on the SVDS (Appendix D) are designated as conditionally acceptable (the final column on the SVDS is filled in with a "Y*" instead of a 'Y'). For these items, based on the walkdown evaluation and available existing documentation, the item of equipment passes the GIP screening criteria. However, full verification of final configuration was not possible at the time of the walkdown due to ongoing plant activities such as maintenance or DCN implementation. For these items, final seismic verification will be conducted during the Area Turnover walkdowns. This Appendix H contains the Punch List for those items of equipment requiring verification of the final configuration during the Area Turnover walkdowns prior to plant restart.

In addition, several outliers are resolved by plant modifications in the form of Design Change Notices (DCNs), Work Orders, or Problem Evaluation Report (PER) corrective actions. For these items, final verification for outlier resolution will be performed during the Area Turnover walkdowns. As such, this Appendix H also contains the Punch List for those items of equipment requiring verification of the final configuration for outlier resolution during the Area Turnover walkdowns prior to plant restart.

A total of 139 SSEL equipment items will require verification of the final configuration during the Area Turnover walkdowns prior to plant restart.

FACILITY RISK CONSULTANTS, INC.

TVANBFN-01 -R-004 Revision 0 September 23, 2004 Page H-3 Punch List for Area Turnover Walkdowns SSL Cas..pnn.

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Ss mt 10006 07 1-FCV-85-83A CRD/EAST SDV VENT VALVE Seismic Interaction Valve will be repaired by WO. Verify acceptability of final configuration.

10007 07 1 -FCV-85-83 CRD/EAST SDV VENT VALVE Seismic Interaction Beam will be coped by WO. Verify acceptability of final configuration.

(OSVS 10007-01) 11023 08A 1 -FCV-74-52 RHR'LOOP I OUTBOARD INJECTION VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

11024 08A 1 -FCV-74-53 RHR/LOOP I INBOARD INJECTION VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

11027 08A 1 -FCV-74-60 RHR/LOOP I OUTBOARD DRYWELL SPRAY BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

VALVE 11048 08A 1-FCV-74-66 RHR/LOOP II OUTBOARD INJECTION VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

12001 07 1 -PCV-1-4 MS/MAIN STEAM SAFETY REUEF VALVE Seismic Interaction Verify that chain hoists are propedy restrained.

12003 07 1-PCV-1-5 MS/MAIN STEAM SAFETY REUEF VALVE (OSVS 12001-01) 12006 07 1-PCV-1 -18 MS/MAIN STEAM SAFETY REUEF VALVE 12009 07 1-PCV-1 -19 MS/MAIN STEAM SAFETY REUEF VALVE 12012 07 1-PCV-1-22 MS/MAIN STEAM SAFETY REUEF VALVE 12015 07 1-PCV-1-23 MS/MAIN STEAM SAFETY REUEF VALVE 12018 07 1-PCV-1-179 MS/MAIN STEAM SAFETY REUEF VALVE 12021 07 1-PCV-1-30 MS/MAIN STEAM SAFETY REUEF VALVE 12024 07 1-PCV-1-31 MS/MAIN STEAM SAFETY REUEF VALVE 12027 07 1-PCV-1-34 MS/MAIN STEAM SAFETY REUEF VALVE 12030 07 1-PCV-1-41 MS/MAIN STEAM SAFETY REUEF VALVE 12033 07 1 -PCV-1 -42 MS/MAIN STEAM SAFETY REUEF VALVE 12036 07 1-PCV-1 -180 MS/MAIN STEAM SAFETY REUEF VALVE 13009 08A 1-FCV-1-55 MAIN STEAM LINE DRAIN ISOLATION VALVE BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

Seismic Interaction 13032 08A 1-PCV-69-1 RWCU INBOARD ISOLATION VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

13033 08A 1-CV-69-2 RWCU OUTBOARD ISOLATION VALVE BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

I _Seismic Interaction 13038 08A 1-FCV-71-3 RCIC OUTBOARD ISOLATION VALVE Seismic Interaction Valve will be modified by DCN. Verify acceptability of final configuration.

FACILITY RISK CONSULTANTS, INC.

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s.

Componen Dscri.io A.46 Criteront 1ecrplo o ssetob Ased.

beAdrese,..

ss 13043 08A 1 -FCV*73-27 HPCI OUTBOARD SUCTION VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

13047 07 1-FCV-77-2B DRYWELL FLOOR DRAIN SUMP DISCHARGE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

(OSVS 13047-01) 13048 07 1-FCV-77-15B DRYWELL EQUIP. DRAIN SUMP DISCHARGE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

(OSVS 13048-01) 13051 20 1 -L-3-58A RPV LEVEL INSTRUMENT Seismic Interaction Verify component mounting to panel and final configuration.

13052 20 1-LI-3-58B RPV LEVEL INSTRUMENT Seismic Interaction Verify component mounting to panel and final configuration.

13053 20 1-PI-3-74A RPV PRESSURE INSTRUMENT Seismic Interaction Verify component mounting to panel and final configuration.

13054 20 1-PI-3-74B RPV PRESSURE INSTRUMENT Seismic Interaction Verify component mounting to panel and final configuration.

13064 07 1 -FCV-64-222 HARDENED WETWELL VENT BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

Seismic Interaction 13069 08A 1-FCV-71-40 CONTAINMENT ISOLATION RCIC VALVE BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

Seismic Interaction 13074 08A 1-FCV-71-17 RCIC INBOARD SUCTION VALVE BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

Seismic Interaction 13080 07 1 -FCV-77-2A DRYWELL FLOOR DRAIN SUMP DISCHARGE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

(OSVS 13080-01) 13081 07 1 -FCV-77-15A DRYWELL EQUIP. DRA IN SUMP DISCHARGE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

(OSVS 13081-01) 13082 07 1-FCV-64-18 COOUNG/PURGE AIR TO DRYWELL BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

13083 07 1-FCV-64-19 COOUNG/PURGE AIR TO SUPPRESSION BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

CHAMBER Seismic Interaction 14014 10 1 -CLR-67-920 EECW/CS PUMP 1 B ROOM COOLER BS Caveats Conduit coupling will be repaired by work order. Verify acceptability of (OSVS 14014-01) final configuration.

15001 08A 1-FCV-75-2 CS/PUMP 1A SUCTION ISOLATION VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

15007 06 1-PMP-75-14 CS/PUMP 1C BS Caveats Conduit support will be added by DON. Verify acceptability of final (OSVS RB519-03) configuration.

15015 08A 1 -FCV-75-30 CS/PUMP I B SUCTION SOLATION VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

15016 06 1-PMP-75-33 CS/PUMP 1B BS Caveats Pump motorwas disassembled. Verify acceptability of final configuration.

15019 08A 1-FCV-75-37 CS/PUMPS 1B & 1D MINI-FLOW VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

FACILITY RISK CONSULTANTS, IN

TVANBFN-01-R-004 Revision 0 September 23, 2004 Page H-5

.No....

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.:..........F.as fb Ih6.It 6t W be Addrese 15020 08A 1 -FCV-75-39 CS/PUMP 1 D SUCTION ISOLATION VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

15021 06 1-PMP-75-42 CS/PUMP ID BS Caveats Pump motorwas disassembled. Verify acceptability of final configuration.

BS Caveats Conduit support will be added by DCN. Verify acceptability of final (OSVS RB519-01 configuration.

& RB519-02) 15024 08A 1-FCV-75-50 CS/PUMPS 1B & ID TEST ISOLATION VALVE Seismic Interaction Valve will be modified by DCN. Verify acceptability of final configuration.

16001 08B 1-FSV-84-8A CAD/CAD TO DW (1-FCV-64-18) SOLENOID VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

16002 08B 1-FSV-84-8B CAD/CAD TO DW (1-FCV-64-19) SOLENOID VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

16003 07 1-PREG-84-52 CAD/CAD SYSTEM 'Al TO UNIT 1 DRYWELL BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

CONTROL AIR Seismic Interaction 16004 08B 1-FSV-84-48 CAD/CAD SYSTEM OA' TO UNIT 1 DRYWELL BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

CONTROL AIR Seismic Interaction 16009 21 1-ACC-32-6105 CA/ACCUMULATOR FOR PSV-1-19 Anchorage Accumulatorwill be modified by DCN. Verify acceptability of final configuration 16012 21 1 -ACC-32-6107 CAIACCUMULATOR FOR PSV-1-22 Anchorage Accumulator will be modified by DON. Verify acceptability of final configuration 16015 21 1-ACC-32-6106 CA/ACCUMULATOR FOR PSV-1-5 Anchorage Accumulator will be modified by DON. Verify acceptability of final configuration 16010 08B 1-PSV-1-19 MS/SOLENOID VALVE FOR PCV-1-19 Seismic Interaction Verify that chain hoists are properiy restrained.

16013 08B 1-PSV-1-22 MS/SOLENOID VALVE FOR PCV-1-22 (OSVS 12001-01) 16016 082 1-PSV-1-5 MS/SOLENOID VALVE FOR PCV-1-5 16017 08B 1-PSV-1-23 MS/SOLENOID VALVE FOR PCV-1-23 16018 08B 1-PSV-1-179 MS/SOLENOID VALVE FOR PCV-1-179 16019 08B 1-PSV-1-4 MS/SOLENOID VALVE FOR PCV-1-4 16021 0823 PSV-1-18 MS/SOLENOID VALVE FOR PCV-1-18 16030 082 1-PSV-1-30 MS/SOLENOID VALVE FOR PCV-1-30 16033 08B 1-PSV-1-31 MS/SOLENOID VALVE FOR PCV-1-31 16036 08B 1-PSV-1-34 MS/SOLENOID VALVE FOR PCV-1-34 16038 08B 1-PSV-1-41 MS/SOLENOID VALVE FOR PCV-1-41 16040 08B 1-PSV-1-42 MS/SOLENOID VALVE FOR PCV-1-42 FACILIWTY RISK CONSULTANTS, INC

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A6 Criterin to mDescriptionof Isee to be Assess b e A d d r e s e d :.:...............

16041 086 1-PSV-1-180 MS/SOLENOID VALVE FOR PCV-1-180 16023 08B 1-FSV-84-8C CAD/CAD TO DW (1-FCV-64-19) SOLENOID VALVE BS Caveats Valve will be modified by DCN. Verify acceptability of final configuration.

16025 07 1-PREG-84-54 CAD/CAD SYSTEM 'B TO UNIT 1 DRYWELL BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

CONTROLAIR Seismic Interaction 16026 086 1-FSV-84-49 CAD/CAD SYSTEM BU TO UNIT 1 DRYWELL BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

CONTROL AIR Seismic Interaction 16029 21 1 -ACC-32-6111 CNACCUMULATOR FOR PSV-1-30 Anchorage Accumulator will be modified by DCN. Verify acceptability of final configuration 16032 21 1-ACC-32-6108 CANACCUMULATOR FOR PSV-1-31 Anchorage Accumulator will be modified by DCN. Verify acceptability of final configuration 16035 21 1-ACC-32-6109 CANACCUMULATOR FOR PSV-1-34 Anchorage Accumulatorwill be modified by DCN. Verify acceptability of final configuration 16043 07 1-FCV-64-20 CONTAINMENT VENTILATION ISOLATION VALVE BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

Seismic Interaction 16044 07 1 -FCV-64-21 CONTAINMENT VENTILATION ISOLATION VALVE BS Caveats and Valve will be modified by DOCN. Verify acceptability of final configuration.

Seismic Interaction 18004 08A 1.FCV-23.040 RHRIRHRSW HX C OUTLET VALVE BS Caveats and Valve will be modified by DCN. Verify acceptability of final configuration.

Seismic Interaction 18006 08A 1 -FCV-23-046 RHRIRHRSW HX B OUTLET VALVE BS Caveats and Cables to operator will be replaced by DON. Verify acceptability of final Seismic Interaction configuration.

18008 08A 1 -FCV-23-052 RHR/RHRSW HX D OUTLET VALVE BS Caveats and Cables to operator will be replaced by DCN. Verify acceptability of final Seismic Interaction configuration.

18032 08A 1-FCV-23-052 RHR1RHRSW HX D OUTLET VALVE Seismic Interaction Valve will be modified by DCN. Check flexibility of attached conduit on final assembly.

19030 01 1 -BDBB-281-250V DC RMOV BOARD 1A BS Caveats MCC will be modified by DCN. Verify acceptability of final configuration.

O001A (OSVS 19030402)

Anchorage MCC will be modified by DCN. Verify acceptability of final configuration.

(OSVS 19030-03) 19031 01 1-BDBB-281-250V DC RMOV BOARD l B BS Caveats MCC will be modified by DCN. Verify acceptability of final configuration.

0001 B (OSVS 19031-02) 19046 20 1-PX-64-160B POWER SUPPLY (PNL 1.9-19: 1-LI-64-159B,160B)

Anchorage Afterinstallation of device, verify its mounting to the panel.

19047 20 1 -PXMC-23-114 POWER SUPPLY (PNL 1-9-18: FI-23-36,42: FI Anchorage After installation of device, verify its mounting to the panel.

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50) 19048 20 1-PXMC-23-115 POWER SUPPLY (PNL 1-9-19: Fl-23-48,54; Fl Anchorage Afterinstallation of device, verifyits mounting to the panel.

A&B 64) 19055 20 1 -PX-64-159B POWER SUPPLY (PNL 1-9-19)

Seismic Interaction After installation of device, verify its mounting to the panel.

19070 16 1-INVT-2560001 DIV I ECCS ATU INVERTER BS Caveats Inverter will be replaced by DCN. Verify acceptability of final (OSVS 19031-02) configuration.

19071 20 1 -PX-71-60-1 ECCS ATU CAB 1-9-81 POWER SUPPLY Seismic Interaction After installation of device, verify its mounting to the panel.

19072 20 1-PX-71-60-IA ECCS ATU CAB 1-9-81 POWER SUPPLY Seismic Interaction After installation of device, verify its mounting to the panel.

19073 20 1 -PX-64-50 POWER SUPPLY (PNL 1-25-31: XR-64-50 [DEV BA Seismic Interaction After installation of device, verify its mounting to the panel.

TERM 11/12])

19074 20 I-PX-74-56 POWER SUPPLY (PNL 1-9-18: FI-74-56)

Seismic Interaction Afterinstallation of device, verify its mounting to the panel.

19075 16 1-INVT-256-0002 DIV II ECCS ATU INVERTER BS Caveats Inverter will be replaced by DCN. Verify acceptability of final (OSVS 19031-02) configuration.

19076 20 1 -PX-71-60-2 ECCS ATU CAB 1-9-82 POWER SUPPLY Seismic Interaction After installation of device, verify its mounting to the panel.

19077 20 1 -PX-71-60-2A ECCS ATU CAB 1-9-82 POWER SUPPLY Seismic Interaction Afterinstallation of device, verify its mounting to the panel.

19078 20 1-PX-74-70 POWER SUPPLY (PNL 1-9-19: Fl-74-70)

Seismic Interaction Afterinstallation of device, verify its mounting to the panel.

19079 20 1 -PX-64-159A POWER SUPPLY (1-9-18)

Seismic Interaction After installation of device, verify its mounting to the panel.

19080 20 1 -PX-64-160A POWER SUPPLY (1-9-18)

Seismic Interaction After installation of device, verify its mounting to the panel.

19081 20 1-PX-64-67B POWER SUPPLY (1-9-19)

Seismic Interaction After installation of device, verify its mounting to the panel.

19082 20 1-PX-64-161 POWER SUPPLY (PNL 9-87)

Seismic Interaction After installation of device, verify its mounting to the panel.

19083 20 1 -PX-64-162 POWER SUPPLY (PNL 9-88)

Seismic Interaction After installation of device, verify its mounting to the panel.

19084 18 1-PS-67-50 PRESSURE SWITCH FOR 1-FCV-67-50 (14046)

Seismic Interaction New pressure switch will be installed by DCN. Verify acceptability of final configuration.

19085 18 1-PS-67-51 PRESSURE SWITCH FOR 1-FCV-67-51 (14047)

Seismic Interaction New pressure switch will be installed by DCN. Verify acceptability of final configuration.

19088 20 1-LPNL-925-COMMON BD LOGIC RELAY PANEL 25-44-A1l Seismic Interaction Panel will be modified by DCN. Verify acceptability of final configuration.

044A11 and Anchorage (OSVS 19088-01).

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be AdresSd.

19120 20 1-PNLA-009-0015 RPS CH A (DIV I)

Seismic Interaction Panel will be modified by DCN (gap between wall and panel filled with 19121 20 1 -PNLA-009-0016 RPS CH A, B, C, D and BS Caveat sealant). Verify acceptability of final configuration.

19122 20 1-PNLA-009-0017 RPS CH B (DIV 11)

(OSVS 19120-01) 19128 20 1-PNLA-009-0032 RHR, CS, & HPCI (CH A) PNL 19129 20 1-PNLA-009-0033 RHR, CS, & HPCI (CH B) PNL 19130 20 1-PNLA-009-0039 HPCI RELAY AUX PNL 19132 20 1-PNLA-009-0043 MSIV (OUTBOARD) DIV II PNL 19136 20 1-PNLA-009-0082 DIV II ECCS ATU CABINET (9-82) 19129 20 1-PNLA-009-0033 RHR, CS, & HPCI (CH B) PNL Seismic Interaction Panels -39 and -82 will be bolted together by DCN. Verify acceptability of (1) and BS Caveat final configuration.

19130 20 1-PNLA-009-0039 HPCI RELAY AUX PNL (OSVS 19130-01 (1)L and 19136-01) 19132 20 1-PNLA-009-0043 MSIV (OUTBOARD) DIV II PNL (1) 19136 20 1-PNLA-009-0082 DIV II ECCS ATU CABINET (9-82)

(1) 19131 20 1-PNLA-009-0042 MSIV (INBOARD) DIV II PNL Seismic Interaction Panels -42 and *81 will be bolted together by DCN. Verify acceptability of 19135 20 1-PNLA-009-0081 DIV I ECCS ATU CABINET (9-81) and BS Caveat final configuration (OSVS 19131-01 and 19135-01) 19137 20 1-PNLA-009-0083 RPS ATU CAB Seismic Interaction Panels -83 thnr -86 will be bolted together by DCN. Verify acceptability 19138 20 1-PNLA-009-0084 RPS ATU CAB and BS Caveat of final configuration 19139 20 1-PNLA-009-0085 RPS ATU CAB (OSVS 19137-01 19140 20 1-PNLA-009-0086 RPS ATU CAB thru 19140-01) 19153 18 1-HS-74-52B LOCAL HS STATION Anchorage Junction box will be repaired by work order. Verify acceptability of final 19154 14 1-JB-1 079 JUNCTION BOX (TERM BLOCK) - SEALED BOX (OSVS 19154-01) configuration.

19155 18 1 -HS-74-53B LOCAL HS STATION 19195 18 1 -LPNL-925-005A LOCAL PANEL 25-5A BS Caveats Instrument rack to be repaired by work order. Verify acceptability of final (OSVS 19195-01) configuration.

19198 18 1 -LPNL-925-006A LOCAL PANEL 25-6A Anchorage Grout to be installed by work order. Verify acceptability of final (OSVS 19198-01).

configuration.

19275 18 1-TS-1-17A MAIN STEAM VAULT TEMPERATURE SWITCH Seismic Interaction Mounting of new temperature switch in RPS ATU Cabinet 9-83.

19276 18 1-TS-1-17B MAIN STEAM VAULT TEMPERATURE SWITCH Seismic Interaction Mounting of new temperature switch in RPS ATU Cabinet 9-84.

FACIUTY RISK CONSULTANM, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page H-9 on:

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I eddresd 19277 18 1-TS-1 -170 MAIN STEAM VAULT TEMPERATURE SWITCH Seismic Interaction Mounting of new temperature switch in RPS ATU Cabinet 9-85.

19278 18 1-TS-1-17D MAIN STEAM VAULT TEMPERATURE SWITCH Seismic Interaction Mounting of new temperature switch in RPS ATU Cabinet 9-86.

19294 00 1-AMP-092-IRM CH. 'A VOLTAGE PREAMPLIFIER 7-34A Anchorage After installation of device, verify its mounting to the panel.

_____0007/41 A

19295 00 1 -AMP-092-IRM OH. ou VOLTAGE PREAMPLIFIER 7-34B Anchorage After installation of device, verify its mounting to the panel.

0007/4 1 B 19297 00 1 -AMP-092-IRM CH. C0 VOLTAGE PREAMPUFIER 7-34C Anchorage After installation of device, verify its mounting to the panel.

0007/41 C 19298 00 1-AMP-092-IRM CH. 'D VOLTAGE PREAMPUFIER 7-34D Anchorage Afterinstallation of device, verify its mounting to the panel.

0007/410D 19300 20 1-NM-92-7/41A CHANNEL 'A IRM INDICATOR Anchorage Verify equipment mounfing to panel 19301 20 1-NM-92-7141B CHANNEL '2 IRM INDICATOR Anchorage Verify equipment mounting to panel 19302 20 1-NM-92-7/41C CHANNEL '0' IRM INDICATOR Anchorage Verify equipment mounting to panel 19303 20 1 -NM-92-7/41 D CHANNEL D0 IRM INDICATOR Anchorage Verify equipment mounting to panel 19307 16 1-CHGD-283-A1-1 24V NEUTRON BATTERY CHARGERS Al-i Anchorage New support system to be installed by DCN. Verify acceptability of final (OSVS 19307-01) configuration.

19308 16 1 -CHGD-283-A2-1 24V NEUTRON BATTERY CHARGERS A2-1 Anchorage New support system to be installed by DCN. Verify acceptability of final

__________________________________(OSVS 19308-01) configuration.

19309 16 1-CHGD-283-B1-1 24V NEUTRON BATTERY CHARGERS 01-1 Anchorage New support system to be installed by DCN. Verify acceptability of final (OSYS 19309-01) configuration..

19310 16 1 -CHGD-283-B2-1 24V NEUTRON BATTERY CHARGERS 82-1 Anchorage New support system to be installed by DCN. Verify acceptability of final (OSVS 19310-01) configuration.

19418 02 1-0002-231-480V SHON 00 1A Interaction Procedure will be improved as required to ensure breaker lifting device is 0001 A (OSVS 19418-01) restrained when lifting device is not being used. Verify acceptability of final configuration.

19792 18 1 -LPNL-925-006B LAL P AN LT 6

MB S

A ncho rage Grout to be installed by work order. Verify acceptability of final 19278 1-TS-1-17DMAINSTEAMVAULTTEMPERATURESWITCHSeismic Itrcin Muigofewem ruesch819792-01).

configuration.

FACILTY RISK CONSULTANTS, INC.

TVA/BFN-01 -R-004 Revision 0 September 23, 2004 Page H-10

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Eo:tv'.,I No opnn DDsrpinA4 rtroescr ipscito of issuetob qe Asssd 19794 04 1-XFA-099-0010 RS REGULATING TRANSFORMER TRP-Caveats Anchorage detail will be modified by DAN. Verfy acceptability of final

.(OSVS 19794-01) configuration.

Anchorage (OSVS 19794-02)

Note: (1) This item of equipment appears more than once in the above table.

FACIUTY RISK CONSULTANTS, INC