CNL-14-210, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.

Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima.

ML14365A046
Person / Time
Site:	Browns Ferry
Issue date:	12/22/2014
From:	James Shea Tennessee Valley Authority
To:	Document Control Desk, Division of Operating Reactor Licensing
References
CNL-14-210
Download: ML14365A046 (79)

Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-210 December 22, 2014 10 CFR 50.4 10 CFR 50.54(f)

Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, and 50-296

Subject:

Tennessee Valley Authoritys Browns Ferry Nuclear Plant Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

References:

NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12, 2012 (ML12056A046)

On March 12, 2012, the U.S. Nuclear Regulatory Commission (NRC) issued the referenced letter to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of the referenced letter requested each addressee located in the Central and Eastern United States (CEUS) to submit a Seismic Hazard Evaluation that includes an interim evaluation and actions taken or planned to address the higher seismic hazard relative to the design basis, as appropriate, prior to completion of the risk evaluation.

In accordance with the referenced letter above, TVA is enclosing the Expedited Seismic Evaluation Process (ESEP) Report for Browns Ferry Nuclear Plant.

There are no new regulatory commitments resulting from this submittal. Should you have questions concerning the content of this letter, please contact Mr. Kevin Casey at (423) 751-8523.

U.S. Nuclear Regulatory Commission CNL-14-210 Page 2 December 22, 2014 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 22nd day of December 2014.

.Shea President, Nuclear Licensing

Enclosure:

Expedited Seismic Evaluation Process (ESEP) Report for Browns Ferry Nuclear Plant cc (Enclosure):

NRR Director- NRC Headquarters NRO Director - NRC Headquarters NRR JLD Director- NRC Headquarters NRC Regional Administrator- Region II NRR Project Manager - Browns Ferry Nuclear Plant NRR JLD Project Manager- Browns Ferry Nuclear Plant NRC Senior Resident Inspector - Browns Ferry Nuclear Plant

ENCLOSURE EXPEDITED SEISMIC EVALUATION PROCESS (ESEP) REPORT FOR BROWNS FERRY NUCLEAR PLANT

EXPEDITED SEISMIC EVALUATION PROCESS (ESEP) REPORT FOR BROWNS FERRY NUCLEAR PLANT Page 1

Browns Ferry Nuclear Plant ESEP Report Table of Contents Page LIST OF TABLES ............................................................................................................................................ 4 LIST OF FIGURES .......................................................................................................................................... 5 1.0 PURPOSE AND OBJECTIVE ............................................................................................................... 6 2.0 BRIEF

SUMMARY

OF THE FLEX SEISMIC IMPLEMENTATION STRATEGIES ...................................... 6 3.0 EQUIPMENT SELECTION PROCESS AND ESEL.................................................................................. 7 3.1 Equipment Selection Process and ESEL .............................................................................. 8 3.1.1 ESEL Development ............................................................................................... 9 3.1.2 Power Operated Valves ....................................................................................... 9 3.1.3 Pull Boxes ........................................................................................................... 10 3.1.4 Termination Cabinets......................................................................................... 10 3.1.5 Critical Instrumentation Indicators .................................................................... 10 3.1.6 Phase 2 and 3 Piping Connections ..................................................................... 10 3.2 Justification for Use of Equipment That is Not the Primary Means for FLEX Implementation ................................................................................................................ 10 4.0 GROUND MOTION RESPONSE SPECTRUM (GMRS) ...................................................................... 10 4.1 Plot of GMRS Submitted by the Licensee ......................................................................... 10 4.2 Comparison to SSE ............................................................................................................ 12 5.0 REVIEW LEVEL GROUND MOTION (RLGM) ................................................................................... 13 5.1 Description of RLGM Selected .......................................................................................... 13 5.2 Method to Estimate InStructure Response Spectra (ISRS) .............................................. 14 6.0 SEISMIC MARGIN EVALUATION APPROACH ................................................................................. 14 6.1 Summary of Methodologies Used .................................................................................... 15 6.2 HCLPF Screening Process .................................................................................................. 15 6.3 Seismic Walkdown Approach ........................................................................................... 16 6.3.1 Walkdown Approach.......................................................................................... 16 6.3.2 Application of Previous Walkdown Information ............................................... 17 6.3.3 Significant Walkdown Findings .......................................................................... 17 6.4 HCLPF Calculation Process ................................................................................................ 18 6.5 Functional Evaluations of Relays ...................................................................................... 18 6.6 Tabulated ESEL HCLPF Values (Including Key Failure Modes) .......................................... 18 7.0 INACCESSIBLE ITEMS ..................................................................................................................... 19 7.1 Identification of ESEL Item Inaccessible for Walkdowns .................................................. 19 7.2 Planned Walkdown / Evaluation Schedule / Close Out .................................................... 19 8.0 ESEP CONCLUSIONS AND RESULTS ............................................................................................... 19 8.1 Supporting Information .................................................................................................... 19 Page 2

Browns Ferry Nuclear Plant ESEP Report Table of Contents (continued)

Page 8.2 Identification of Planned Modifications ........................................................................... 21 8.3 Modification Implementation Schedule ........................................................................... 21 8.4 Summary of Regulatory Commitments ............................................................................ 21

9.0 REFERENCES

.................................................................................................................................. 22 ATTACHMENT A - EXPEDITED SEISMIC EQIPMENT LIST (ESEL) FOR BROWNS FERRY NUCLEAR PLANT ......................................................................................................................... A1 ATTACHMENT B - ESEP HCLPF VALUES AND FAILURE MODES TABULATION FOR BROWNS FERRY NUCLEAR PLANT......................................................................................................... B1 Page 3

Browns Ferry Nuclear Plant ESEP Report List of Tables Page TABLE 41: GMRS FOR BROWNS FERRY NUCLEAR PLANT ....................................................................... 11 TABLE 42: SSE FOR BROWNS FERRY NUCLEAR PLANT............................................................................ 12 TABLE 51: 2X SSE FOR BROWNS FERRY NUCLEAR PLANT....................................................................... 14 TABLE A1: EXPEDITED SEISMIC EQUIPMENT LIST (ESEL) FOR BROWNS FERRY NUCLEAR PLANT......... A2 TABLE B1: ESEP HCLPF VALUES AND FAILURE MODES FOR BROWNS FERRY NUCLEAR PLANT ............ B2 Page 4

Browns Ferry Nuclear Plant ESEP Report List of Figures Page FIGURE 41: GMRS AT CONTROL POINT FOR BROWNS FERRY NUCLEAR PLANT .................................... 12 FIGURE 42: GMRS TO SSE COMPARISON FOR BROWNS FERRY NUCLEAR PLANT ................................. 13 FIGURE 51: 2X SSE FOR BROWNS FERRY NUCLEAR PLANT..................................................................... 14 FIGURE 61: COMPARISON OF BROWNS FERRY NUCLEAR PLANT RLGM AND IPEEE RLE ....................... 15 Page 5

Browns Ferry Nuclear Plant ESEP Report 1.0 PURPOSE AND OBJECTIVE Following the accident at the Fukushima Daiichi nuclear power plant resulting from the March 11, 2011, Great Tohoku Earthquake and subsequent tsunami, the Nuclear Regulatory Commission (NRC) established a NearTerm Task Force (NTTF) to conduct a systematic review of NRC processes and regulations and to determine if the agency should make additional improvements to its regulatory system. The NTTF developed a set of recommendations intended to clarify and strengthen the regulatory framework for protection against natural phenomena. Subsequently, the NRC issued a 50.54(f) letter on March 12, 2012 [1], requesting information to assure that these recommendations are addressed by all U.S. nuclear power plants. The 50.54(f) letter requests that licensees and holders of construction permits under 10 CFR Part 50 reevaluate the seismic hazards at their sites against presentday NRC requirements and guidance. Depending on the comparison between the reevaluated seismic hazard and the current design basis, further risk assessment may be required. Assessment approaches acceptable to the staff include a seismic probabilistic risk assessment (SPRA), or a seismic margin assessment (SMA). Based upon the assessment results, the NRC staff will determine whether additional regulatory actions are necessary.

This report describes the Expedited Seismic Evaluation Process (ESEP) undertaken for Tennessee Valley Authority (TVA) Browns Ferry Nuclear Plant Units 1, 2, and 3. The intent of the ESEP is to perform an interim action in response to the NRCs 50.54(f) letter to demonstrate seismic margin through a review of a subset of the plant equipment that can be relied upon to protect the reactor core following beyond design basis seismic events.

The ESEP is implemented using the methodologies in the NRC endorsed guidance in Electric Power Research Institute (EPRI) 3002000704, Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima NearTerm Task Force Recommendation 2.1: Seismic [2].

The objective of this report is to provide summary information describing the ESEP evaluations and results. The level of detail provided in the report is intended to enable the NRC to understand the inputs used, the evaluations performed, and the decisions made as a result of the interim evaluations.

2.0 BRIEF

SUMMARY

OF THE FLEX SEISMIC IMPLEMENTATION STRATEGIES The Browns Ferry Nuclear Plant FLEX strategies for Reactor Core Cooling and Heat Removal, Reactor Inventory Control, and Containment Function are summarized below. This summary is derived from the Browns Ferry Nuclear Plant Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA12049 submitted in February 2013 [3] and is consistent with the third six month status report issued to the NRC in August 2014 [4].

The OIP provides an indepth sequence of events that describes the response of the plant to the Extended Loss of all AC Power (ELAP) and loss of Ultimate Heat Sink (UHS) and the operator actions to be taken. The major milestones of the response are described for each phase of the response to the Beyond Design Basis External Event (BDBEE).

Core Cooling and Heat Removal During Phase 1 (approximately the first eight (8) hours) reactor core cooling will be maintained by using the Reactor Core Isolation Cooling (RCIC) system aligned to take suction from the torus. Pressure control will be maintained by utilizing the Safety Relief Valves (SRVs). A controlled Reactor Pressure Vessel (RPV) depressurization will begin approximately thirty (30) minutes after reactor shutdown Page 6

Browns Ferry Nuclear Plant ESEP Report using the RCIC system and manually cycling the SRVs to reduce the RPV to a pressure of 150 psig. The RPV will be maintained between 150 psig and 200 psig until the beginning of Phase 2.

During Phase 1, fire protection personnel are dispatched to deploy the portable FLEX pumping systems and commence laying hose as required for transition to Phase 2.

At approximately eight (8) hours into the event (beginning of Phase 2), the operators will lower RPV pressure by using SRVs to reduce pressure, allowing for transition from RCIC to injecting river water utilizing the portable FLEX pumping systems taking advantage of the Residual Heat Removal (RHR) service water/RHR crosstie.

Containment Integrity During Phase 1, containment integrity is maintained by controlling reactor parameters to not challenge containment limits within the first eight (8) hours of the event.

During Phase 2 containment cooling is accomplished by containment venting, utilizing the existing hardened wetwell vent system, as the primary strategy for containment cooling. This will utilize a new severe accident capable venting system, as described in NRC Order EA13109 [5]. Containment spray can still be accomplished with portable FLEX pumping systems utilizing the service water to RHR cross tie feature to augment containment venting.

Support Systems The 250 VDC system, supplied by batteries in Phase 1 and batteries and battery chargers in Phases 2 and 3, supports the operation of the RCIC system Automatic Depressurization System (ADS) valves Phase 1 Instrumentation and Control (I&C) components, as well as the control power for the 480 VAC shutdown boards associated with the ESEL loads in Phases 2 and 3.

Battery boards 1, 2, and 3 supply loads in all three units, so all three battery boards, their associated 250 VDC batteries and battery chargers, and all 250 VDC Reactor Motor Operated Valve (RMOV) boards have been added to the ESEL. Also on the ESEL are 250 VDC panels SBA, SBB, SBC, SBD, and SBEB and their associated batteries and battery chargers.

Two portable 480V FLEX Generators will be available. A single generator has the capacity to supply all safety related 250V DC battery chargers via a load control center. These will be available before Phase

2. A 480V FLEX generator can be connected to a distribution panel and provide power for the 250V DC Unit Battery Charger #1, 250V DC Unit Battery Charger #2A, and 250V DC Unit Battery Charger #3.

Two portable 1.1 MWe, 4kv FLEX Support Generators will be deployed and connected to the 4.6 KV shutdown boards to power MOVs with the ability to supply additional loads such:

120 VAC instrumentation Ventilation Pump motors Figures 1a, 1b, and 2a of [4] provide the FLEX flow paths for BFN.

3.0 EQUIPMENT SELECTION PROCESS AND ESEL The selection of equipment for the Expedited Seismic Equipment List (ESEL) followed the guidelines of EPRI 3002000704 [2]. The ESEL for Browns Ferry Nuclear Plant Units 1, 2, and 3 is presented in Attachment A. Information presented in Attachment A is drawn from Reference [6].

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Browns Ferry Nuclear Plant ESEP Report 3.1 Equipment Selection Process and ESEL The selection of equipment to be included on the ESEL was based on installed plant equipment credited in the FLEX strategies during Phase 1, 2 and 3 mitigation of a BDBEE, as outlined in the Browns Ferry Nuclear Plant OIP in Response to the March 12, 2012, Commission Order EA12049 [3] and is consistent with the third six month status report issued to the NRC in August 2014 [4]. The OIP provides the Browns Ferry Nuclear Plant FLEX mitigation strategy and serves as the basis for equipment selected for the ESEP.

The scope of installed plant equipment includes equipment relied upon for the FLEX strategies to sustain the critical functions of core cooling and containment integrity consistent with the Browns Ferry Nuclear Plant OIP. FLEX recovery actions are excluded from the ESEP scope per EPRI 3002000704

[2]. The overall list of planned FLEX modifications and the scope for consideration herein is limited to those required to support core cooling, reactor coolant inventory and subcriticality, and containment integrity functions. Portable and prestaged FLEX equipment (not permanently installed) are excluded from the ESEL per EPRI 3002000704.

The ESEL component selection followed the EPRI guidance outlined in Section 3.2 of EPRI 3002000704.

1. The scope of components is limited to that required to accomplish the core cooling and containment safety functions identified in Table 32 of EPRI 3002000704. The instrumentation monitoring requirements for core cooling/containment safety functions are limited to those outlined in the EPRI 3002000704 guidance, and are a subset of those outlined in the Browns Ferry Nuclear Plant OIP.

2. The scope of components is limited to installed plant equipment, and FLEX connections necessary to implement the Browns Ferry Nuclear Plant OIP as described in Section 2.

3. The scope of components assumes the credited FLEX connection modifications are implemented, and are limited to those required to support a single FLEX success path (i.e.,

either Primary or Backup/Alternate).

4. The Primary FLEX success path is to be specified. Selection of the Backup/Alternate FLEX success path must be justified.

5. Phase 3 coping strategies are included in the ESEP scope, whereas recovery strategies are excluded.

6. Structures, systems, and components excluded per the EPRI 3002000704 guidance are:

Structures (e.g. containment, reactor building, control building, auxiliary building, etc.)

Piping, cabling, conduit, HVAC, and their supports Manual valves and rupture disks Poweroperated valves not required to change state as part of the FLEX mitigation strategies Nuclear steam supply system components (e.g. RPV and internals, reactor coolant pumps and seals, etc.)

7. For cases in which neither division was specified as a primary or backup strategy, then only one division component (generally Division I) is included in the ESEL Page 8

Browns Ferry Nuclear Plant ESEP Report 3.1.1 ESEL Development The ESEL was developed by reviewing the Browns Ferry Nuclear Plant OIP [3] [4] to determine the major equipment involved in the FLEX strategies. Further reviews of plant drawings (e.g., Piping and Instrumentation Diagrams (P&IDs) and Electrical One Line Diagrams) were performed to identify the boundaries of the flow paths to be used in the FLEX strategies and to identify specific components in the flow paths needed to support implementation of the FLEX strategies. Boundaries were established at an electrical or mechanical isolation device (e.g., isolation amplifier, valve, etc.) in branch circuits/branch lines off the defined strategy electrical or fluid flow path. P&IDs were the primary reference documents used to identify mechanical components and instrumentation. The flow paths used for FLEX strategies were selected and specific components were identified using detailed equipment and instrument drawings, piping isometrics, electrical schematics and oneline drawings, system descriptions, design basis documents, etc., as necessary. Host components were identified for subassemblies.

Cabinets and equipment controls containing relays, contactors, switches, potentiometers, circuit breakers and other electrical and instrumentation that could be affected by highfrequency earthquake motions and that impact the operation of equipment in the ESEL are required to be on the ESEL. These cabinets and components were identified in the ESEL. For the ESEL, the relays identified were in the RCIC and Automatic Depressurization System (ADS), and malfunction of these relays during a seismic event could lead to the failure of the reactor core cooling safety function.

For Phase 1, RCIC is the preferred path for inventory control and core cooling. Therefore, the RCIC system was used as the basis for the Phase 1 ESEL. For Phase 2 and Phase 3, inventory control and core cooling is maintained by portable FLEX pumps injecting to the RHR service water and to the RHR system via the RHR service water to RHR crosstie. Relays that could malfunction during a seismic event and prevent successful RCIC operation were included in the ESEL.

For each parameter monitored during the FLEX implementation, a single indication was selected for inclusion in the ESEL. For each parameter indication, the components along the flow path from measurement to indication were included, since any failure along the path would lead to failure of that indication. Components such as flow elements were considered as part of the piping and were not included in the ESEL.

3.1.2 Power Operated Valves Page 33 of EPRI 3002000704 [2] notes that power operated valves not required to change state as part of the FLEX mitigation strategies are excluded from the ESEL. Page 32 also notes that functional failure modes of electrical and mechanical portions of the installed Phase 1 equipment should be considered (e.g. RCIC). To address this concern, the following guidance is applied in the Browns Ferry Nuclear Plant ESEL for functional failure modes associated with power operated valves:

Power operated valves that remain energized during the ELAP events (such as DC powered valves), were included on the ESEL.

Power operated valves not required to change state as part of the FLEX mitigation strategies were not included on the ESEL. The seismic event also causes the ELAP event; therefore, the valves are incapable of spurious operation as they would be deenergized.

Power operated valves not required to change state as part of the FLEX mitigation strategies during Phase 1, and are reenergized and operated during subsequent Phase 2 and 3 Page 9

Browns Ferry Nuclear Plant ESEP Report strategies, were not evaluated for spurious valve operation as the seismic event that caused the ELAP has passed before the valves are repowered.

3.1.3 Pull Boxes Pull boxes were deemed unnecessary to be added to the ESELs as these components provide completely passive locations for pulling or installing cables. No breaks or connections in the cabling were included in pull boxes. Pull boxes were considered part of conduit and cabling, which were excluded in accordance with EPRI 3002000704 [2].

3.1.4 Termination Cabinets Termination cabinets, including cabinets necessary for FLEX Phase 2 and Phase 3 connections, provide consolidated locations for permanently connecting multiple cables. The termination cabinets and the internal connections provide a completely passive function; however, the cabinets are included in the ESEL to ensure industry knowledge on panel/anchorage failure vulnerabilities is addressed.

3.1.5 Critical Instrumentation Indicators Critical indicators and recorders are typically physically located on panels/cabinets and are included as separate components; however, seismic evaluation of the instrument indication may be included in the panel/cabinet seismic evaluation (ruleofthebox).

3.1.6 Phase 2 and 3 Piping Connections Item 2 in Section 3.1 above notes that the scope of equipment in the ESEL includes FLEX connections necessary to implement the Browns Ferry Nuclear Plant OIP [3] as described in Section 2.

Item 3 in Section 3.1 also notes that The scope of components assumes the credited FLEX connection modifications are implemented, and are limited to those required to support a single FLEX success path (i.e., either Primary or Backup/Alternate).

Item 6 in Section 3.1 above goes on to explain that Piping, cabling, conduit, HVAC, and their supports are excluded from the ESEL scope in accordance with EPRI 3002000704 [2].

Therefore, piping and pipe supports associated with FLEX Phase 2 and Phase 3 connections are excluded from the scope of the ESEP evaluation. However, any active valves in FLEX Phase 2 and Phase 3 connection flow path are included in the ESEL.

3.2 Justification for Use of Equipment That is Not the Primary Means for FLEX Implementation The Browns Ferry Nuclear Plant ESEL is based on the primary means of implementing the FLEX strategy. Therefore, no additional justification is required.

4.0 GROUND MOTION RESPONSE SPECTRUM (GMRS) 4.1 Plot of GMRS Submitted by the Licensee The Design Basis Earthquake (DBE) control point elevation is defined at the base of the Reactor Building, which corresponds to a depth of 52 ft. (El. 519) and is the deepest structure foundation elevation control point. Hereafter DBE is referred to as Safe Shutdown Earthquake (SSE). Table 41 shows the GMRS accelerations for a range of frequencies. The GMRS at the control point elevation is shown in Figure 41 [7].

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Browns Ferry Nuclear Plant ESEP Report Table 41: GMRS for Browns Ferry Nuclear Plant Frequency GMRS (Hz) (g) 100 2.71E01 90 2.74E01 80 2.79E01 70 2.93E01 60 3.28E01 50 4.04E01 40 4.90E01 35 5.20E01 30 5.57E01 25 5.80E01 20 5.68E01 15 5.27E01 12.5 4.99E01 10 4.73E01 9 4.56E01 8 4.25E01 7 4.05E01 6 3.96E01 5 3.52E01 4 3.19E01 3.5 3.02E01 3 2.80E01 2.5 2.47E01 2 2.31E01 1.5 1.98E01 1.25 1.77E01 1 1.46E01 0.9 1.37E01 0.8 1.30E01 0.7 1.21E01 0.6 1.08E01 0.5 9.54E02 0.4 7.63E02 0.35 6.68E02 0.3 5.72E02 0.25 4.77E02 0.2 3.82E02 0.15 2.86E02 0.125 2.39E02 0.1 1.91E02 Page 11

Browns Ferry Nuclear Plant ESEP Report Figure 41: GMRS at Control Point for Browns Ferry Nuclear Plant 4.2 Comparison to SSE The SSE was developed consistent with 10 CFR Part 100, Appendix A through an evaluation of the maximum earthquake potential for the region surrounding the site. Considering the historic seismicity of the site region, Browns Ferry Nuclear Plant was designed using a conservative assumption that a seismic event at an unstated location could cause a response with an intensity VII on the Modified Mercalli Intensity Scale of 1931 at the plant site.

The SSE is defined in terms of a Peak Ground Acceleration (PGA) and a design response spectrum.

Considering a site intensity of VII, a PGA of 0.20g was estimated. Table 42 shows the spectral acceleration values as a function of frequency for the 5%damped horizontal SSE [7].

Table 42: SSE for Browns Ferry Nuclear Plant Frequency Spectral Acceleration (Hz) (g) 100 0.2 25 0.2 10 0.22 5 0.3 2.5 0.28 1 0.16 0.5 0.12 Page 12

Browns Ferry Nuclear Plant ESEP Report Figure 42: GMRS to SSE Comparison for Browns Ferry Nuclear Plant The SSE envelops the GMRS for lower frequency range up to 3Hz. The GMRS exceeds the SSE beyond that point. As the GMRS exceeds the SSE in the 1 to 10Hz range, the plant does not screen out of the ESEP according to Section 2.2 of EPRI 3002000704 [2]. The two special screening considerations as described in Section 2.2.1 of EPRI 3002000704, namely a) Low Seismic Hazard Site and b) Narrow Band Exceedances in the 1 to 10Hz range do not apply for Browns Ferry Nuclear Plant and hence High Confidence of a Low Probability of Failure (HCLPF) evaluations are required.

5.0 REVIEW LEVEL GROUND MOTION (RLGM) 5.1 Description of RLGM Selected Section 4 of Reference [2] presents two approaches for developing the Review Level Ground Motion (RLGM) to be used in the ESEP:

1. The RLGM may be derived by linearly scaling the SSE by the maximum ratio of the GMRS/SSE between the 1 and 10 Hz range (not to exceed 2x SSE). Instructure RLGM seismic motions would be derived using existing SSE based instructure response spectra (ISRS) with the same scale factor.

2. Alternately, licensees who have developed appropriate structural/soilstructure interaction (SSI) models capable of calculating ISRS based on site GMRS /uniform hazard response spectrum (UHRS) input may opt to use these ISRS in lieu of scaled SSE ISRS.

Based on a review of tabulated data in Tables 41 and the SSE values of Table 42, in the range between 1 and 10 Hz the maximum ratio of GMRS to the SSE is calculated to be:

SFmax = SAGMRS(10 HZ)/SA SSE 10Hz) = 0.473g/0.22g = 2.15 Since the computed scale factor is greater than 2.0, the RLGM would be set a level of 2x SSE. This is shown in Table 51 and Figure 51.

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Browns Ferry Nuclear Plant ESEP Report Table 51: 2x SSE for Browns Ferry Nuclear Plant Frequency Spectral Acceleration (Hz) (g) 100 0.4 25 0.4 10 0.44 5 0.6 2.5 0.56 1.0 0.32 0.5 0.24 Figure 51: 2x SSE for Browns Ferry Nuclear Plant 5.2 Method to Estimate InStructure Response Spectra (ISRS)

The RLGM ISRS for Browns Ferry Nuclear Plant are generated by scaling the design basis SSE up to 0.3g RLE as determined in the Seismic IPEEE. Additional information is provided in Section 6.1.

6.0 SEISMIC MARGIN EVALUATION APPROACH It is necessary to demonstrate that ESEL items have sufficient seismic capacity to meet or exceed the demand characterized by the RLGM. The seismic capacity is characterized as the PGA for which there is a HCLPF. The PGA is associated with a specific spectral shape, in this case the 5%damped RLGM spectral shape. The HCLPF capacity must be equal to or greater than the RLGM PGA. The criteria for seismic capacity determination are given in Section 5 of EPRI 3002000704 [2].

There are two basic approaches for developing HCLPF capacities:

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Browns Ferry Nuclear Plant ESEP Report

1. Deterministic approach using the conservative deterministic failure margin (CDFM) methodology of EPRI NP6041SL, A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1) [8].

2. Probabilistic approach using the fragility analysis methodology of EPRI TR103959, Methodology for Developing Seismic Fragilities [9].

6.1 Summary of Methodologies Used Browns Ferry Nuclear Plant performed a SMA for Units 2 and 3 in 1996 and Unit 1 in 2004. The SMA is documented in References [10] and [11] and consisted of screening walkdowns and HCLPF anchorage calculations. The screening walkdowns used the screening tables from Chapter 2 of EPRI NP6041SL

[8]. The walkdowns were conducted by engineers trained in EPRI NP6041SL (the engineers attended the EPRI SMA AddOn course in addition to the SQUG Walkdown Screening and Seismic Evaluation Training Course), and were documented on Screening Evaluation Work Sheets (SEWS) from EPRI NP 6041SL. Anchorage capacity calculations used the CDFM criteria from EPRI NP6041SL. Seismic demand was the Individual Plant Examination of External Events (IPEEE) Review Level Earthquake (RLE) for SMA (mean NUREG/CR0098 [12] ground response spectrum anchored to 0.3g PGA).

Figure 61 shows the mean NUREG/CR0098 ground response spectrum used as the IPEEE RLE for the SMA, compared to the ESEP RLGM response spectrum. The figure shows that IPEEE RLE envelopes the ESEP RLGM at all frequencies between 1 and 10 Hz.

Figure 61: Comparison of Browns Ferry Nuclear Plant RLGM and IPEEE RLE 6.2 HCLPF Screening Process The SMA was based on the IPEEE RLE, which was anchored to 0.3g peak ground acceleration. Browns Ferry Nuclear Plant Units 2 and 3 identified a minimum HCLPF of 0.26g and Unit 1 identified a minimum HCLPF of at least 0.3g. The limiting configurations were reevaluated [13] and determined to also have a HCLPF capacity of at least 0.3g. Note these components have been replaced. The RLE is greater than the RLGM at frequencies between 1Hz to 10 Hz. Therefore, any components whose SMA based HCLPF capacity exceeds the RLE can be screened out from HCLPF calculations. The screening tables in EPRI NP6041SL [8] are based on ground peak spectral accelerations of 0.8g and 1.2g. These Page 15

Browns Ferry Nuclear Plant ESEP Report both exceed the RLGM peak spectral acceleration. The anchorage capacity calculations were based on SSE floor response spectra scaled to the RLE. Equipment for which the screening caveats were met and for which the anchorage capacity exceeded the RLE seismic demand can be screened out from ESEP seismic capacity determination because the HCLPF capacity exceeds the RLGM.

The Browns Ferry Nuclear Plant Units 1, 2 and 3 ESEL contains a total of 549 items. Of these, 135 are valves, both poweroperated and relief. In accordance with Table 24 of EPRI NP6041SL [8] active valves may be assigned a functional capacity of 0.8g peak spectral acceleration without any review other than looking for valves with large extended operators on small diameter piping, and anchorage is not a failure mode. Therefore, valves on the ESEL may be screened out from ESEP seismic capacity determination, subject to the caveat regarding large extended operators on small diameter piping.

The nonvalve components in the ESEL are generally screened based on the SMA results. If the SMA showed that the component met the EPRI NP6041SL screening caveats and the CDFM capacity exceeded the RLE demand, the component can be screened out from the ESEP capacity determination.

6.3 Seismic Walkdown Approach 6.3.1 Walkdown Approach Walkdowns were performed in accordance with the criteria provided in Section 5 of EPRI 3002000704

[2], which refers to EPRI NP6041SL [8] for the Seismic Margin Assessment process. Pages 226 through 230 of EPRI NP6041SL describe the seismic walkdown criteria, including the following key criteria.

The SRT [Seismic Review Team] should walk by 100% of all components which are reasonably accessible and in nonradioactive or low radioactive environments. Seismic capability assessment of components which are inaccessible, in highradioactive environments, or possibly within contaminated containment, will have to rely more on alternate means such as photographic inspection, more reliance on seismic reanalysis, and possibly, smaller inspection teams and more hurried inspections. A 100% walk by does not mean complete inspection of each component, nor does it mean requiring an electrician or other technician to deenergize and open cabinets or panels for detailed inspection of all components. This walkdown is not intended to be a QA or QC review or a review of the adequacy of the component at the SSE level.

If the SRT has a reasonable basis for assuming that the group of components are similar and are similarly anchored, then it is only necessary to inspect one component out of this group. The similaritybasis should be developed before the walkdown during the seismic capability preparatory work (Step 3) by reference to drawings, calculations or specifications. The one component or each type which is selected should be thoroughly inspected which probably does mean deenergizing and opening cabinets or panels for this very limited sample. Generally, a spare representative component can be found so as to enable the inspection to be performed while the plant is in operation. At least for the one component of each type which is selected, anchorage should be thoroughly inspected.

The walkdown procedure should be performed in an ad hoc manner. For each class of components the SRT should look closely at the first items and compare the field configurations with the construction drawings and/or specifications. If a onetoone correspondence is found, then subsequent items do not have to be inspected in as great a detail. Ultimately the walkdown becomes a walk by of the component class as the SRT becomes confident that the Page 16

Browns Ferry Nuclear Plant ESEP Report construction pattern is typical. This procedure for inspection should be repeated for each component class; although, during the actual walkdown the SRT may be inspecting several classes of components in parallel. If serious exceptions to the drawings or questionable construction practices are found then the system or component class must be inspected in closer detail until the systematic deficiency is defined.

The 100% walk by is to look for outliers, lack of similarity, anchorage which is different from that shown on drawings or prescribed in criteria for that component, potential SI [Seismic Interaction] problems, situations that are at odds with the team members past experience, and any other areas of serious seismic concern. If any such concerns surface, then the limited sample size of one component of each type for thorough inspection will have to be increased.

The increase in sample size which should be inspected will depend upon the number of outliers and different anchorages, etc., which are observed. It is up to the SRT to ultimately select the sample size since they are the ones who are responsible for the seismic adequacy of all elements which they screen from the margin review. Appendix D gives guidance for sampling selection.

6.3.2 Application of Previous Walkdown Information Several ESEL items were previously walked down during the Browns Ferry Nuclear Plant Units 1, 2 and 3, Seismic IPEEE program. Those walkdown results were reviewed and the following steps were taken to confirm that the previous walkdown conclusions remained valid.

A walk by was performed to confirm that the equipment material condition and configuration is consistent with the walkdown conclusions and that no new significant interactions related to block walls or piping attached to tanks exist.

If the ESEL item was screened out based on the previous walkdown, that screening evaluation was reviewed and reconfirmed for the ESEP.

In all cases it was determined that the HCLPF capacities established for these items under the seismic IPEEE program remained valid. Thus, all ESEL components that were part of the IPEEE program have a HCLPF capacity of 0.3g or greater and are thus adequate for ESEP [7].

6.3.3 Significant Walkdown Findings Consistent with the guidance from EPRI NP6041SL [8], no significant outliers or anchorage concerns were identified during the Browns Ferry Nuclear Plant Units 1, 2 and 3 seismic walkdowns. Based on walkdown results, HCLPF capacity evaluations were recommended for the following twelve (12) components:

RCIC Turbine Driven Pump Terry Turbine Control Box Vacuum Tank RCIC BackUp Control Panel Main Control Room Benchboard LPNL Instrument Rack Motor Operated Valve Page 17

Browns Ferry Nuclear Plant ESEP Report Air Operated Valve Piping and Tubing Electrical Raceways Block Walls Relay Evaluations 6.4 HCLPF Calculation Process ESEL items not included in the previous IPEEE evaluations at Browns Ferry Nuclear Plant were evaluated using the criteria in EPRI NP6041SL [8]. Those evaluations included the following steps:

Performing seismic capability walkdowns for equipment not included in previous seismic walkdowns (SQUG, IPEEE, or NTTF 2.3) to evaluate the equipment installed plant conditions Performing screening evaluations using the screening tables in EPRI NP6041SL as described in Section 6.2 Performing HCLPF calculations considering various failure modes that include both structural failure modes (e.g. anchorage, load path etc.) and functional failure modes All HCLPF calculations were performed using the CDFM methodology and are documented in TVA Calculation: CDQ999 2014 000268 BFN Expedited Seismic Evaluation Process (ESEP) HCLPF Capacity Calculation [13].

6.5 Functional Evaluations of Relays The ESEL identifies essential relays for ESEP. All of these relays are associated with the RCIC system.

The relays are the same configuration and type for Browns Ferry Nuclear Plant Units 1, 2, and 3. All of the relays are in the normally open state, except for four (4) that can be excluded from this evaluation because chatter is acceptable. The relay types addressed in this evaluation include the following:

GE 12HFA51A41 GE 12HFA151A1F GE 12HGA11A51F AMERACE 7012SB (formerly Agastat)

The relays were evaluated using the guidance provided in EPRI NP6041SL [8] for equipment qualified by testing (relay GERS). Subject relays were determined to have higher HCLPF values than the plant RLGM as well as the RLE, with a minimum HCLPF of 0.37g.

The ESEP relay functional evaluations are documented in a TVA calculation [13].

6.6 Tabulated ESEL HCLPF Values (Including Key Failure Modes)

Tabulated ESEL HCLPF values are provided in Attachment B. The following notes apply to the information in the tables.

Items previously included in the USI A46 and seismic IPEEE programs are not listed. Walkby verifications reconfirmed the HCLPF capacities from the IPEEE, and the IPEEE 0.3g RLE HCLPF capacity exceeds the RLGM.

Page 18

Browns Ferry Nuclear Plant ESEP Report HCLPF capacity evaluations were performed for the nonIPEEE items on the ESEL, addressing both structural/anchorage and functional failure modes. The HCLPF capacity of each item is listed in the tables, with associated governing failure mode.

New permanently installed FLEX items are not listed. TVA design criteria BFN57360 [14]

requires that new FLEX items have HCLPF capacity exceeding the RLGM.

All ESEP components have a HCLPF capacity greater than the RLGM for the frequency range of 1 to 10Hz.

7.0 INACCESSIBLE ITEMS 7.1 Identification of ESEL Item Inaccessible for Walkdowns Inside Drywell was not accessible during the walk by verifications. The components inside the Drywell consist of the seismically rugged Main Steam Safety Relief Valves (MSRVs) and associated accumulators and solenoid valves. The MSRVs are located in an upper elevation region of the Drywell, and by design are remote from other plant features. The Browns Ferry Nuclear Plant operations group maintains current photographs of the MSRVs and these photographs were made available to the SRT for review for ESEP. Based on close review of all of the photographs, it was confirmed that the MSRVs and associated subcomponents are intact, well maintained, and remote from any nearby item and thus free of seismic interaction concerns. It was noted that the chain falls from the overhead monorail crane (used for MSRV replacement service) was appropriately secured well away from the MSRVs.

Based on these observations, it is concluded that no further investigation is required for these rugged items.

7.2 Planned Walkdown / Evaluation Schedule / Close Out There are no components that require follow up seismic walkdowns.

8.0 ESEP CONCLUSIONS AND RESULTS 8.1 Supporting Information Browns Ferry Nuclear Plant Units 1, 2, and 3 have performed the ESEP as an interim action in response to the NRCs 50.54(f) letter [1]. It was performed using the methodologies in the NRC endorsed guidance in EPRI 3002000704 [2].

The ESEP provides an important demonstration of seismic margin and expedites plant safety enhancements through evaluations and potential nearterm modifications of plant equipment that can be relied upon to protect the reactor core following beyond design basis seismic events.

The ESEP is part of the overall Browns Ferry Nuclear Plant Units 1, 2, and 3 response to the NRCs 50.54(f) letter. On March 12, 2014, NEI submitted to the NRC results of a study [16] of seismic core damage risk estimates based on updated seismic hazard information as it applies to operating nuclear reactors in the Central and Eastern United States (CEUS). The study concluded that "sitespecific seismic hazards show that there has not been an overall increase in seismic risk for the fleet of U.S.

plants" based on the reevaluated seismic hazards. As such, the "current seismic design of operating reactors continues to provide a safety margin to withstand potential earthquakes exceeding the seismic design basis."

Page 19

Browns Ferry Nuclear Plant ESEP Report The NRCs May 9, 2014 NTTF 2.1 Screening and Prioritization letter [15] concluded that the fleet wide seismic risk estimates are consistent with the approach and results used in the Gl199 safety/risk assessment. The letter also stated that As a result, the staff has confirmed that the conclusions reached in Gl199 safety/risk assessment remain valid and that the plants can continue to operate while additional evaluations are conducted.

An assessment of the change in seismic risk for Browns Ferry Nuclear Plant Units 1, 2, and 3 was included in the fleet risk evaluation submitted in the March 12, 2014 NEI letter [16] therefore, the conclusions in the NRCs May 9 letter also apply to Browns Ferry Nuclear Plant Units 1, 2, and 3.

In addition, the March 12, 2014 NEI letter provided an attached Perspectives on the Seismic Capacity of Operating Plants, which (1) assessed a number of qualitative reasons why the design of Structures, Systems and Components (SSCs) inherently contain margin beyond their design level, (2) discussed industrial seismic experience databases of performance of industry facility components similar to nuclear SSCs, and (3) discussed earthquake experience at operating plants.

The fleet of currently operating nuclear power plants was designed using conservative practices, such that the plants have significant margin to withstand large ground motions safely. This has been borne out for those plants that have actually experienced significant earthquakes. The seismic design process has inherent (and intentional) conservatisms which result in significant seismic margins within SSCs.

These conservatisms are reflected in several key aspects of the seismic design process, including:

Safety factors applied in design calculations Damping values used in dynamic analysis of SSCs Bounding synthetic time histories for instructure response spectra calculations Broadening criteria for instructure response spectra Response spectra enveloping criteria typically used in SSC analysis and testing applications Response spectra based frequency domain analysis rather than explicit time history based time domain analysis Bounding requirements in codes and standards Use of minimum strength requirements of structural components (concrete and steel)

Bounding testing requirements Ductile behavior of the primary materials (that is, not crediting the additional capacity of materials such as steel and reinforced concrete beyond the essentially elastic range, etc.)

These design practices combine to result in margins such that the SSCs will continue to fulfill their functions at ground motions well above the SSE.

The intent of the ESEP is to perform an interim action in response to the NRCs 50.54(f) letter to demonstrate seismic margin through a review of a subset of the plant equipment that can be relied upon to protect the reactor core following beyond design basis seismic events. In order to complete the ESEP in an expedited amount of time, the RLGM used for the ESEP evaluation is a scaled version of the plants SSE rather than the actual GMRS. To more fully characterize the risk impacts of the seismic ground motion represented by the GMRS on a plant specific basis, a more detailed seismic risk assessment (SPRA, riskbased SMA, or other justification) can be performed. Browns Ferry Nuclear Page 20

Browns Ferry Nuclear Plant ESEP Report Plant Units 1, 2, and 3 will complete that evaluation in accordance with the schedule identified in NEIs letter dated April 9, 2013 [17] and endorsed by the NRC in their May 7, 2013 letter [18].

8.2 Identification of Planned Modifications There are no additional plant modifications required for Browns Ferry Nuclear Plant Units 1, 2 and 3.

8.3 Modification Implementation Schedule There are no additional plant modifications required for Browns Ferry Nuclear Plant Units 1, 2 and 3.

8.4 Summary of Regulatory Commitments There are no additional actions to be performed as a result of the ESEP.

Page 21

Browns Ferry Nuclear Plant ESEP Report

9.0 REFERENCES

1. NRC (E Leeds and M Johnson) Letter to All Power Reactor Licensees et al., Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the NearTerm Task Force Review of Insights from the Fukushima DaiIchi Accident, March 12, 2012.

2. EPRI 3002000704, Seismic Evaluation Guidance, Augmented Approach for the Resolution of Fukushima NearTerm Task Force Recommendation 2.1: Seismic, May 2013.

3. TVA Letter to U.S. NRC, Tennessee Valley Authority - Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (Order Number EA12049),

February 28, 2013.

4. TVA Letter to U.S. NRC, Third SixMonth Status Report and Revised Overall Integrated Plan in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond Design Basis External Events (Order Number EA12049) for Browns Ferry Nuclear Plant (TAC Nos. MF0902, MF0903, and MF0904), August 28, 2014.

5. NRC Order EA13109, Issuance of Order to Modify Licenses with Regard to Reliable Hardened Containment Vents Capable of Operating Under Severe Accident Conditions, June 6, 2013.

6. AREVA NP Document 519217417003,ESEP Expedited Seismic Equipment List (ESEL) - Browns Ferry Nuclear Plant Units 1, 2, and 3.

7. TVA Letter to U.S. NRC, Tennessee Valley Authoritys Seismic Hazard and Screening Report (CEUS Sites), response to NRC Request for Information Pursuant to 10 CFR 50.54(f) regarding Recommendation 2.1 of the NearTerm Task Force Review of Insights from the Fukushima Dai ichi Accident, March 31, 2014.

8. EPRINP6041SL, Methodology for Assessment of Nuclear Power Plant Seismic Margin, Revision 1, August 1991.

9. EPRI TR103959, Methodology for Developing Seismic Fragilities, July 1994.

10. Seismic IPEEE Report, Browns Ferry Nuclear Plant" Prepared by EQE Inc, June 1996.

11. Browns Ferry Nuclear Plant Unit 1 Seismic IPEEE Report," prepared by Facility Risk Consultants, October 2004.

12. U.S. NRC NUREG/CR0098, Development of Criteria for Seismic Review of Selected Nuclear Power Plants, May 1978.

13. TVA Calculation CDQ 000999 2014 000268 "BFN Expedited Seismic Evaluation Process (ESEP)

HCLPF Capacity Calculation", October 2014.

14. TVA Design Criteria BFN57360, Revision 2, FLEX Mitigation System.

15. NRC (E. Leeds) Letter to All Power Reactor Licensees et al., Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(F)

Regarding Seismic Hazard ReEvaluations for Recommendation 2.1 of the NearTerm Task Force Review of Insights From the Fukushima DaiIchi Accident, May 9, 2014.

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Browns Ferry Nuclear Plant ESEP Report

16. Nuclear Energy Institute (NEI), A. Pietrangelo, Letter to D. Skeen of the USNRC, Seismic Core Damage Risk Estimates Using the Updated Seismic Hazards for the Operating Nuclear Plants in the Central and Eastern United States, March 12, 2014.

17. Nuclear Energy Institute (NEI), A. Pietrangelo, Letter to D. Skeen of the USNRC, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, April 9, 2013. NRC Adams Accession No. ML13101A379.

18. NRC (E Leeds) Letter to NEI (J Pollock), Electric Power Research Institute Final Draft Report xxxxx, Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima NearTerm Task Force Recommendation 2.1: Seismic, as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, May 7, 2013.

Page 23

Browns Ferry Nuclear Plant ESEP Report ATTACHMENT A - EXPEDITED SEISMIC EQIPMENT LIST (ESEL) FOR BROWNS FERRY NUCLEAR PLANT Page A1

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments Must close to swap RCIC suction to the suppression pool RCIC Pump Condensate 1 1FCV 7119 Open Closed Power: 250V Reactor Motor Operated Valve (RMOV) Board Storage Tank Suction Valve 1C breaker 1BKR0710019 Normally closed, must open to supply RCIC suction from torus 2 1FCV7117 RCIC Suction from Torus Closed Open Power: From 250V RMOV Board 1C breaker 1BKR071 0017 Normally closed, must open to supply RCIC suction from torus 3 1FCV7118 RCIC Suction from Torus Closed Open Power: From 250V RMOV Board 1C breaker 1BKR071 0018 4 1PMP7119 RCIC Pump Standby Operating Provides RPV makeup in Phase 1 Normally closed, must open to supply RCIC injection flow 5 1FCV 7139 RCIC Discharge Isolation Valve Closed Open Power: From 250V RMOV Board 1C breaker 1BKR071 0039 RCIC Lube Oil Cooling Water 6 1PCV 7122 Open Controls cooling water flow to RCIC lube oil cooler Pressure Control Valve Normally closed, opens to allow cooling water flow to RCIC RCIC Turbine Lube Oil Inlet 7 1FCV 7125 Closed Open turbine lube oil cooler Valve Power: 250V RMOV Board 1C breaker 1BKR0710025 8 1TNK7127 RCIC Vacuum Tank Standby Operating Collects and condenses RCIC gland seal leakage 9 1CND7127 RCIC Barometric Condenser Standby Operating Collects and condenses RCIC gland seal leakage 10 1CLR7125 RCIC Lube Oil Cooler Standby Operating Cools RCIC lube oil Page A2

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments Pumps condensate from vacuum tank to pump suction RCIC Vacuum Tank Condensate 11 1PMP7129 Standby Operating Power: From 250V RMOV Board 1C breaker 1BKR071 Pump 0029 Maintains vacuum on barometric condenser 12 1PMP7131 RCIC Vacuum Pump Standby Operating Power: From 250V RMOV Board 1C breaker 1BKR071 0031 Opens on RCIC start to admit steam to RCIC turbine 13 1FCV718 RCIC Turbine Steam Inlet Valve Closed Open Power: From 250V RMOV Board 1C breaker 1BKR071 0008 Trips closed on RCIC protective function RCIC Turbine Steam Throttle Open/ Close 14 1FCV719 Open Power: From 250V RMOV Board 1C breaker 1BKR071 Valve as needed 009A Open/ Close 15 1FCV7110 RCIC Turbine Governor Valve Open Modulates steam flow to RCIC turbine as needed 16 1TRB719 RCIC Turbine Standby Operating Supplies motive force to RCIC pump RCIC Pump Flow Transmitter 17 1FT7136 On On Transmits RCIC flow to flow control circuit for Turbine Control Auto Set at Auto Set at 18 1FIC7136A RCIC Flow Indicating Controller Controls RCIC flow 620 gpm 620 gpm Power Supply for RCIC flow 19 1PX7136A Energized Energized Supplies AC power to RCIC flow control circuitry Controller 1LPNL925 20 RCIC Local Controls Energized Energized Local control of RCIC turbine 672 Page A3

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 21 1SC7110 Electronic Governor Module Operating Operating RCIC Auto Isolation SealIn 22 113AK15 Energized Energized Relay RCIC High Space Temperature 23 113AK10 Operable Operable Relay RCIC High Space Temperature 24 113AK11 Operable Operable Relay RCIC Low Steam Supply 25 113AK13 Operable Operable Pressure Relay RCIC Steam Line High 26 1271K12 Operable Operable Differential Pressure Relay RCIC High Rupture Disc 27 113AK44 Operable Operable Pressure Relay RCIC High Rupture Disc 28 113AK45 Operable Operable Pressure Relay RCIC Auto Isolation SealIn 29 113AK12 Operable Operable Relay RCIC Auto Isolation SealIn 30 113AK14 Operable Operable Relay RCIC Auto Isolation SealIn 31 113AK16 Operable Operable Relay RCIC Manual Steam Isolation 32 113AK38 Operable Operable relay RCIC Auto Discharge Circuit 33 113AK17 Operable Operable Reset relay Page A4

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments RCIC Auto Discharge Circuit 34 113AK18 Operable Operable Reset relay RCIC Vessel Low Water Level 35 113AK37 Operable Operable relay RCIC Steam Line Space Excess 36 113AK30 Operable Operable Temperature Isolation relay RCIC Steam Line Space Excess 37 113AK31 Operable Operable Temperature Isolation relay RCIC Steam Line Space Excess 38 171K32 Operable Operable Temperature Isolation relay RCIC Steam Line Space Excess 39 113AK32 Operable Operable Temperature Isolation relay 40 113AK33 RCIC Auto Isolation Signal relay Operable Operable RCIC - Unit 2 Must close to swap RCIC suction to the suppression pool RCIC Pump Condensate 41 2FCV 7119 Open Closed Power: From 250V RMOV Board 2C breaker 2BKR071 Storage Tank Suction Valve 0019 Normally closed, must open to supply RCIC suction from torus 42 2FCV7117 RCIC Suction from Torus Closed Open Power: From 250V RMOV Board 2C breaker 2BKR071 0017 Page A5

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments Normally closed, must open to supply RCIC suction from torus 43 2FCV7118 RCIC Suction from Torus Closed Open Power: From 250V RMOV Board 2C breaker 2BKR071 0018 44 2PMP7119 RCIC Pump Standby Operating Provides RPV makeup in Phase 1 Normally closed, must open to supply RCIC injection flow 45 2FCV 7139 RCIC Discharge Isolation Valve Closed Open Power: From 250V RMOV Board 2C breaker 2BKR071 0039 RCIC Lube Oil Cooling Water Open/ Close 46 2PCV 7122 Open Controls cooling water flow to RCIC lube oil cooler Pressure Control Valve as needed Normally closed, opens to allow cooling water flow to RCIC RCIC Turbine Lube Oil Inlet turbine lube oil cooler 47 2FCV 7125 Closed Open Valve Power: From 250V RMOV Board 2C breaker 2BKR071 0025 48 2TNK7127 RCIC Vacuum Tank Standby Operating Collects and condenses RCIC gland seal leakage 49 2CND7127 RCIC Barometric Condenser Standby Operating Collects and condenses RCIC gland seal leakage 50 2CLR7125 RCIC Lube Oil Cooler Standby Operating Cools RCIC lube oil RCIC Vacuum Tank Condensate Pumps condensate from vacuum tank to pump suction 51 2PMP7129 Standby Operating Pump Power: From250V RMOV Board 2C breaker 2BKR0710029 Maintains vacuum on barometric condenser 52 2PMP7131 RCIC Vacuum Pump Standby Operating Power: From 250V RMOV Board 2C breaker 2BKR071 0031 Page A6

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments Opens on RCIC start to admit steam to RCIC turbine 53 2FCV718 RCIC Turbine Steam Inlet Valve Closed Open Power: From 250V RMOV Board 2C breaker 2BKR071 0008 Trips closed on RCIC protective function RCIC Turbine Steam Throttle Open/ Close 54 2FCV719 Open Power: From 250V RMOV Board 2C breaker 2BKR071 Valve as needed 009A Open/ Close 55 2FCV7110 RCIC Turbine Governor Valve Open Modulates steam flow to RCIC turbine as needed 56 2TRB719 RCIC Turbine Standby Operating Supplies motive force to RCIC pump RCIC Pump Flow Transmitter 57 2FT7136 On On Transmits RCIC flow to flow control circuit for Turbine Control Auto Set at Auto Set at 58 2FIC7136A RCIC Flow Indicating Controller Controls RCIC flow 620 gpm 620 gpm Power Supply for RCIC Flow 59 2PX7136A Energized Energized Supplies AC power to RCIC flow control circuitry Controller 2LPNL925 60 RCIC Local Controls Energized Energized Local control of RCIC turbine 672 61 2SC7110 Electronic Governor Module Operating Operating RCIC Auto Isolation SealIn 62 213AK15 Operable Operable Relay RCIC High Space Temperature 63 213AK10 Operable Operable Relay RCIC High Space Temperature 64 213AK11 Operable Operable Relay Page A7

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments RCIC Low Steam Supply 65 213AK13 Operable Operable Pressure Relay RCIC Steam Line High 66 2271K12 Operable Operable Differential Pressure Relay RCIC High Rupture Disc Pres.

67 213AK44 Operable Operable Relay RCIC High Rupture Disc 68 213AK45 Operable Operable Pressure Relay RCIC Auto Isolation SealIn 69 213AK12 Operable Operable Relay RCIC Auto Isolation SealIn 70 213AK14 Operable Operable Relay RCIC Auto Isolation SealIn 71 213AK16 Operable Operable Relay RCIC Manual Steam Isolation 72 213AK38 Operable Operable relay RCIC Auto Discharge Circuit 73 213AK17 Operable Operable Reset relay RCIC Auto Discharge Circuit 74 213AK18 Operable Operable Reset relay RCIC Vessel Low Water Level 75 213AK37 Operable Operable relay RCIC Steam Line Space Excess 76 213AK30 Operable Operable Temperature Isolation relay RCIC Steam Line Space Excess 77 213AK31 Operable Operable Temperature Isolation relay Page A8

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments RCIC Steam Line Space Excess 78 271K32 Operable Operable Temperature Isolation relay RCIC Steam Line Space Excess 79 213AK32 Operable Operable Temperature Isolation relay 80 213AK33 RCIC Auto Isolation Signal relay Operable Operable RCIC - Unit 3 Must close to swap RCIC suction to the suppression pool RCIC Pump Condensate 81 3FCV 7119 Open Closed Power: From 250V RMOV Board 3C breaker 3BKR071 Storage Tank Suction Valve 0019 Normally closed, must open to supply RCIC suction from torus 82 3FCV7117 RCIC Suction from Torus Closed Open Power: From 250V RMOV Board 3C breaker 3BKR071 0017 Normally closed, must open to supply RCIC suction from torus 83 3FCV7118 RCIC Suction from Torus Closed Open Power: From 250V RMOV Board 3C breaker 3BKR071 0018 84 3PMP7119 RCIC Pump Standby Operating Provides RPV makeup in Phase 1 Normally closed, must open to supply RCIC injection flow 85 3FCV 7139 RCIC Discharge Isolation Valve Closed Open Power: From 250V RMOV Board 3C breaker 3BKR071 0039 RCIC Lube Oil Cooling Water Open/ Close 86 3PCV 7122 Open Controls cooling water flow to RCIC lube oil cooler Pressure Control Valve as needed Page A9

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments Normally closed, opens to allow cooling water flow to RCIC RCIC Turbine Lube Oil Inlet turbine lube oil cooler 87 3FCV 7125 Closed Open Valve Power: From 250V RMOV Board 3C breaker 3BKR071 0025 88 3TNK7127 RCIC Vacuum Tank Standby Operating Collects and condenses RCIC gland seal leakage 89 3CND7127 RCIC Barometric Condenser Standby Operating Collects and condenses RCIC gland seal leakage 90 3CLR7125 RCIC Lube Oil Cooler Standby Operating Cools RCIC lube oil Pumps condensate from vacuum tank to pump suction RCIC Vacuum Tank Condensate 91 3PMP7129 Standby Operating Power: From 250V RMOV Board 3C breaker 3BKR071 Pump 0029 Maintains vacuum on barometric condenser 92 3PMP7131 RCIC Vacuum Pump Standby Operating Power: From 250V RMOV Board 3C breaker 3BKR071 0031 Opens on RCIC start to admit steam to RCIC turbine 93 3FCV718 RCIC Turbine Steam Inlet Valve Closed Open Power: From 250V RMOV Board 3C breaker 3BKR071 0008 Trips closed on RCIC protective function RCIC Turbine Steam Throttle Open/ Close 94 3FCV719 Open Power: From 250V RMOV Board 3C breaker 3BKR071 Valve as needed 009A Open/ Close 95 3FCV7110 RCIC Turbine Governor Valve Open Modulates steam flow to RCIC turbine as needed 96 3TRB719 RCIC Turbine Standby Operating Supplies motive force to RCIC pump Page A10

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments RCIC Pump Flow Transmitter 97 3FT7136 On On Transmits RCIC flow to flow control circuit for Turbine Control Auto Set at Auto Set at 98 3FIC7136A RCIC Flow Indicating Controller Controls RCIC flow 620 gpm 620 gpm Power Supply for RCIC flow 99 3PX7136A Energized Energized Supplies AC power to RCIC flow control circuitry Controller 3LPNL925 100 RCIC Local Controls Energized Energized Local control of RCIC turbine 672 101 3SC7136A Electronic Governor Module Operating Operating RCIC Auto Isolation SealIn 102 313AK15 Operable Operable Relay RCIC High Space Temperature 103 313AK10 Operable Operable Relay RCIC High Space Temperature 104 313AK11 Operable Operable Relay Page A11

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments RCIC Low Steam Supply 105 313AK13 Operable Operable Pressure Relay RCIC Steam Line High 106 371K12 Operable Operable Differential Pressure Relay RCIC High Rupture Disc 107 313AK44 Operable Operable Pressure Relay RCIC High Rupture Disc 108 313AK45 Operable Operable Pressure Relay RCIC Manual Steam Isolation 109 371K12 Operable Operable Relay RCIC Auto Isolation SealIn 110 313AK14 Operable Operable Relay RCIC Auto Isolation SealIn 111 313AK16 Operable Operable Relay RCIC Manual Steam Isolation 112 313AK38 Operable Operable relay RCIC Auto Discharge Circuit 113 313AK17 Operable Operable Reset relay RCIC Auto Discharge Circuit 114 313AK18 Operable Operable Reset relay RCIC Vessel Low Water Level 115 313AK37 Operable Operable relay Page A12

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments RCIC Steam Line Space Excess 116 313AK30 Operable Operable Temperature Isolation relay RCIC Steam Line Space Excess 117 313AK31 Operable Operable Temperature Isolation relay RCIC Steam Line Space Excess 118 371K32 Operable Operable Temperature Isolation relay RCIC Steam Line Space Excess 119 313AK32 Operable Operable Temperature Isolation relay 120 313AK33 RCIC Auto Isolation Signal relay Operable Operable ADS - Unit 1 FLEX Nitrogen Bottle Rack for 121 TBD Operable Operable UNID to be established in DCN 71387 MSRV Operation MS/Main Steam Safety Relief 122 1PCV14 Shut Open Used for pressure control and cooldown Valve Pilot valve for associated SRV 123 1PSV14 MS/Solenoid Valve for PCV14 Deenergized Energized Power: From 250V DC RMOV Board 1A MS/Main Steam Safety Relief 124 1PCV15 Shut Open Used for pressure control and cooldown Valve Pilot valve for associated SRV 125 1PSV15 MS/Solenoid Valve for PCV15 Deenergized Energized Power: From 250VDC RMOV Board 1C 1ACC32 126 CA/Accumulator for PSV15 Operable Operable Holds operating nitrogen for SRV 6106 MS/Main Steam Safety Relief 127 1PCV118 Shut Open Used for pressure control and cooldown Valve Page A13

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 128 1PSV118 Deenergized Energized 18 Power: From 250VDC RMOV Board 1B MS/Main Steam Safety Relief 129 1PCV119 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot Valve for associated SRV 130 1PSV119 Deenergized Energized 19 Power: From 250VDC RMOV Board 1B 1ACC32 131 CA/Accumulator for PSV119 Operable Operable Holds operating nitrogen for SRV 6105 MS/Main Steam Safety Relief 132 1PCV122 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 133 1PSV122 Deenergized Energized 22 Power: From 250VDC RMOV Board 1B 1ACC32 134 CA/Accumulator for PSV122 Operable Operable Holds operating nitrogen for SRV 6107 MS/Main Steam Safety Relief 135 1PCV123 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 136 1PSV123 Deenergized Energized 23 Power: From 250 VDC RMOV Board 1C MS/Main Steam Safety Relief 137 1PCV130 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot Valve for associated SRV 138 1PSV130 Deenergized Energized 30 Power: From 250VDC RMOV Board 1B 1ACC32 139 CA/Accumulator for PSV130 Operable Operable Holds operating nitrogen for SRV 6108 Page A14

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments MS/Main Steam Safety Relief 140 1PCV131 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 141 1PSV131 Deenergized Energized 31 Power: From 250VDC RMOV Board 1B 1ACC32 142 CA/Accumulator for PSV131 Operable Operable Holds operating nitrogen for SRV 6111 MS/Main Steam Safety Relief 143 1PCV134 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 144 1PSV134 Deenergized Energized 34 Power: From 250VDC RMOV Board 1C 1ACC32 145 CA/Accumulator for PSV134 Operable Operable Holds operating nitrogen for SRV 6109 MS/Main Steam Safety Relief 146 1PCV141 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 147 1PSV141 Deenergized Energized 41 Power: From 250VDC RMOV Board 1A MS/Main Steam Safety Relief 148 1PCV142 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 149 1PSV142 Deenergized Energized 42 Power: From 250VDC RMOV Board 1B MS/Main Steam Safety Relief 150 1PCV1179 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 151 1PSV1179 Deenergized Energized 179 Power: From 250VDC RMOV Board 1B Page A15

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments MS/Main Steam Safety Relief 152 1PCV1180 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 153 1PSV1180 Deenergized Energized 180 Power: From 250VDC RMOV Board 1C 1PCV 14 Control Room Hand Open SRV for cooldown 154 1HS14 Auto Open Switch Power: From 250VDC RMOV Board 1A 155 2XS14 Transfer Switch for 2PCV14 Closed Closed 1PCV 15 Control Room Hand Open SRV for cooldown 156 1HS15A Auto Open Switch Power: From 250VDC RMOV Board 1C 157 1XS15 Transfer Switch for 1PCV15 Closed Closed 1PCV 118 Control Room Hand Open SRV for cooldown 158 1HS118 Auto Open Switch Power: From 250VDC RMOV Board 1B 159 1XS118 Transfer Switch for 1PCV118 Closed Closed 1PCV 119 Control Room Hand Open SRV for cooldown 160 1HS119A Auto Open Switch Power: From 250VDC RMOV Board 1B Transfer Switch for 1PCV1 161 1XS119 Closed Closed 19A 1PCV 122 Control Room Hand Open SRV for cooldown 162 1HS122A Auto Open Switch Power: From 250VDC RMOV Board 1B Transfer Switch for 2PCV1 163 1XS122 Closed Closed 22A 1PCV 123 Control Room Hand Open SRV for cooldown 164 1HS123A Auto Open Switch Power: From 250VDC RMOV Board 1C Page A16

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments Transfer Switch for 2PCV1 165 1XS123 Closed Closed 23A 1PCV 130 Control Room Hand Open SRV for cooldown 166 1HS130A Auto Open Switch Power: From 250VDC RMOV Board 1B Transfer Switch for 1PCV1 167 1XS130 Closed Closed 30A 1PCV 131 Control Room Hand Open SRV for cooldown 168 1HS131A Auto Open Switch Power: From 250VDC RMOV Board 1B Transfer Switch for 1PCV1 169 1XS131 Closed Closed 30A 1PCV 134 Control Room Hand Open SRV for cooldown 170 1HS134A Auto Open Switch Power: From 250VDC RMOV Board 1C 171 1XS134 Transfer Switch for 1PCV134 Closed Closed 1PCV 141 Control Room Hand Open SRV for cooldown 172 1HS141 Auto Open Switch Power: From 250VDC RMOV Board 1A 173 1XS141 Transfer Switch for 1PCV141 Closed Closed 1PCV 142 Control Room Hand Open SRV for cooldown 174 1HS142 Auto Open Switch Power: From 250VDC RMOV Board 1B 175 1XS142 Transfer Switch for 1PCV142 Closed Closed 1PCV 1179 Control Room Open SRV for cooldown 176 1HS1179A Auto Open Hand Switch Power: From 250VDC RMOV Board 1B Transfer Switch for 1PCV1 177 1XS1179 Closed Closed 179 Page A17

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 1PCV 1180 Control Room Open SRV for cooldown 178 1HS1180A Auto Open Hand Switch Power: From 250VDC RMOV Board 1C Transfer Switch for 1PCV1 179 1XS1180 Closed Closed 180 Used to inhibit automatic initiation of ADS 180 1XS1159A ADS Inhibit Switch Normal Inhibit Power: From 250VDC RMOV Board 1B Used to inhibit automatic initiation of ADS 181 1XS1161A ADS Inhibit Switch Normal Inhibit Power: From 250VDC RMOV Board 1B 1LPNL925 Local Panel 2532: Backup 182 Operable Operable Failure of panel or components can prevent opening SRVs 0032 Control ADS - Unit 2 FLEX Nitrogen Bottle Rack For 183 TBD Operable Operable UNID to be established in DCN 70810 MSRV Operation MS/Main Steam Safety Relief Used for pressure control and cooldown 184 2PCV14 Shut Open Valve Power: From 250 VDC RMOV Board 2A 185 2PSV14 MS/Solenoid Valve for PCV14 Deenergized Energized Pilot valve for associated SRV MS/Main Steam Safety Relief 186 2PCV15 Shut Open Used for pressure control and cooldown Valve Pilot valve for associated SRV 187 2PSV15 MS/Solenoid Valve for PCV15 Deenergized Energized Power: From 250 VDC RMOV Board 2C 2ACC32 188 CA/Accumulator for PSV15 Operable Operable Holds operating nitrogen for SRV 6106 MS/Main Steam Safety Relief 189 2PCV118 Shut Open Used for pressure control and cooldown Valve Page A18

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 190 2PSV118 Deenergized Energized 18 Power: From 250 VDC RMOV Board 2B MS/Main Steam Safety Relief 191 2PCV119 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 192 2PSV119 Deenergized Energized 19 Power: From 250 VDC RMOV Board 2B 2ACC32 193 CA/Accumulator for PSV119 Operable Operable Holds operating nitrogen for SRV 6105 MS/Main Steam Safety Relief 194 2PCV122 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 195 2PSV122 Deenergized Energized 22 Power: From 250 VDC RMOV Board 2B 2ACC32 196 CA/Accumulator For PSV122 Operable Operable Holds operating nitrogen for SRV 6107 MS/Main Steam Safety Relief 197 2PCV123 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 198 2PSV123 Deenergized Energized 23 Power: From 250 VDC RMOV Board 2C MS/Main Steam Safety Relief 199 2PCV130 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 200 2PSV130 Deenergized Energized 30 Power: From 250 VDC RMOV Board 2A 2ACC32 201 CA/Accumulator for PSV130 Operable Operable Holds operating nitrogen for SRV 6111 Page A19

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments MS/Main Steam Safety Relief 202 2PCV131 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 203 2PSV131 Deenergized Energized 31 Power: From 250 VDC RMOV Board 2B 2ACC32 204 CA/Accumulator for PSV131 Operable Operable Holds operating nitrogen for SRV 6108 MS/Main Steam Safety Relief 205 2PCV134 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot Valve for associated SRV 206 2PSV134 Deenergized Energized 34 Power: From 250 VDC RMOV Board 2C 2ACC32 207 CA/Accumulator for PSV134 Operable Operable Holds operating nitrogen for SRV 6109 MS/Main Steam Safety Relief 208 2PCV141 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 209 2PSV141 Deenergized Energized 41 Power: From 250 VDC RMOV Board 2A MS/Main Steam Safety Relief 210 2PCV142 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 211 2PSV142 Deenergized Energized 42 Power: From 250 VDC RMOV Board 2B MS/Main Steam Safety Relief 212 2PCV1179 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 213 2PSV1179 Deenergized Energized 179 Power: From 250 VDC RMOV Board 2B Page A20

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments MS/Main Steam Safety Relief 214 2PCV1180 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 215 2PSV1180 Deenergized Energized 30 Power: From 250 VDC RMOV Board 2C 2PCV 14 Control Room Hand Open SRV for cooldown 216 2HS14 Auto Open Switch Power: From 250 VDC RMOV Board 2A 217 2XS14 Transfer Switch for 2PCV14 Closed Closed 2PCV 15 Control Room Hand Open SRV for cooldown 218 2HS15A Auto Open Switch Power: From 250 VDC RMOV Board 2C 219 2XS15 Transfer Switch for 2PCV15 Closed Closed 2PCV 118 Control Room Hand Open SRV for cooldown 220 2HS118 Auto Open Switch Power: From 250 VDC RMOV Board 2B 221 2XS118 Transfer Switch for 2PCV118 Closed Closed 2PCV 119 Control Room Hand Open SRV for cooldown 222 2HS119A Auto Open Switch Power: From 250 VDC RMOV Board 2B 223 2XS119A Transfer Switch for 2PCV119 Closed Closed 2PCV 122 Control Room Hand Open SRV for cooldown 224 2HS122A Auto Open Switch Power: From 250 VDC RMOV Board 2B Transfer Switch for 2PCV1 225 2XS122A Closed Closed 22A 2PCV 123 Control Room Hand Open SRV for cooldown 226 2HS123 Auto Open Switch Power: From 250 VDC RMOV Board 2C Page A21

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 227 2XS123 Transfer Switch for 2PCV123 Closed Closed 2PCV 130 Control Room Hand Open SRV for cooldown 228 2HS130A Auto Open Switch Power: From 250 VDC RMOV Board 2A 229 2XS130 Transfer Switch for 2PCV130 Closed Closed 2PCV 131 Control Room Hand Open SRV for cooldown 230 2HS131A Auto Open Switch Power: From 250 VDC RMOV Board 2B 231 2XS131 Transfer Switch for 2PCV130 Closed Closed 2PCV 134 Control Room Hand Open SRV for cooldown 232 2HS134A Auto Open Switch Power: From 250 VDC RMOV Board 2C 233 2XS134 Transfer Switch for 2PCV134 Closed Closed 2PCV 141 Control Room Hand Open SRV for cooldown 234 2HS141 Auto Open Switch Power: From 250 VDC RMOV Board 2A 235 2XS141 Transfer Switch for 2PCV141 Closed Closed 2PCV 142 Control Room Hand Open SRV for cooldown 236 2HS42 Auto Open Switch Power: From 250 VDC RMOV Board 2B 237 2XS142 Transfer Switch for 2PCV142 Closed Closed 2PCV 1179 Control Room Open SRV for cooldown 238 2HS1179A Auto Open Hand Switch Power: From 250 VDC RMOV Board 2B Transfer Switch for 2PCV1 239 2XS1179 Closed Closed 179 Page A22

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 2PCV 1180 Control Room Open SRV for cooldown 240 2HS1180A Auto Open Hand Switch Power: From 250 VDC RMOV Board 2C Transfer Switch for 2PCV1 241 2XS1180 Closed Closed 180 Used to inhibit automatic initiation of ADS 242 2XS1159A ADS Inhibit Switch Normal Inhibit Power: From 250 VDC RMOV Board 2B Used to inhibit automatic initiation of ADS 243 2XS1161A ADS Inhibit Switch Normal Inhibit Power: From 250 VDC RMOV Board 2B Local Panel 2532: Backup 244 2LPNL2532 Operable Operable Failure of panel or components can prevent opening SRVs Control ADS - Unit 3 FLEX Nitrogen Bottle Rack for 245 TBD Operable Operable UNID to be established in DCN 71386 MSRV Operation MS/Main Steam Safety Relief 246 3PCV14 Shut Open Used for pressure control and cooldown Valve Pilot valve for associated SRV 247 3PSV14 MS/Solenoid Valve for PCV14 Deenergized Energized Power: From 250 VDC RMOV Board 3A MS/Main Steam Safety Relief 248 3PCV15 Shut Open Used for pressure control and cooldown Valve Pilot valve for associated SRV 249 3PSV15 MS/Solenoid Valve for PCV15 Deenergized Energized Power: From 250 VDC RMOV Board 3C 3ACC32 250 CA/Accumulator for PSV15 Operable Operable Holds operating nitrogen for SRV 6106 Page A23

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments MS/Main Steam Safety Relief 251 3PCV118 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 252 3PSV118 Deenergized Energized 18 Power: From 250 VDC RMOV Board 3B 3ACC32 253 CA/Accumulator for Psv118 Operable Operable Holds operating nitrogen for SRV 6104 MS/Main Steam Safety Relief 254 3PCV119 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 255 3PSV119 Deenergized Energized 19 Power: From 250 VDC RMOV Board 3B 3ACC32 256 CA/Accumulator for PSV119 Operable Operable Holds operating nitrogen for SRV 6105 MS/Main Steam Safety Relief 257 3PCV122 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 258 3PSV122 Deenergized Energized 22 Power: From 250 VDC RMOV Board 3B 3ACC32 259 CA/Accumulator for PSV122 Operable Operable Holds operating nitrogen for SRV 6107 MS/Main Steam Safety Relief 260 3PCV123 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 261 3PSV123 Deenergized Energized 23 Power: From 250 VDC RMOV Board 3C MS/Main Steam Safety Relief 262 3PCV130 Shut Open Used for pressure control and cooldown Valve Page A24

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 263 3PSV130 Deenergized Energized 30 Power: From 250 VDC RMOV Board 3A 3ACC32 264 CA/Accumulator for PSV130 Operable Operable Holds operating nitrogen for SRV 6111 MS/Main Steam Safety Relief 265 3PCV131 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 266 3PSV131 Deenergized Energized 31 Power: From 250 VDC RMOV Board 3B 3ACC32 267 CA/Accumulator for PSV131 Operable Operable Holds operating nitrogen for SRV 6108 MS/Main Steam Safety Relief 268 3PCV134 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 269 3PSV134 Deenergized Energized 34 Power: From 250 VDC RMOV Board 3C 3ACC32 270 CA/Accumulator for PSV134 Operable Operable Holds operating nitrogen for SRV 6109 MS/Main Steam Safety Relief 271 3PCV141 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 272 3PSV141 Deenergized Energized 41 Power: From 250 VDC RMOV Board 3C 3ACC32 273 CA/Accumulator for PSV141 Operable Operable Holds operating nitrogen for SRV 6110 MS/Main Steam Safety Relief 274 3PCV142 Shut Open Used for pressure control and cooldown Valve Page A25

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 275 3PSV142 Deenergized Energized 42 Power: From 250 VDC RMOV Board 3B MS/Main Steam Safety Relief 276 3PCV1179 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 277 3PSV1179 Deenergized Energized 179 Power: From 250 VDC RMOV Board 3B MS/Main Steam Safety Relief 278 3PCV1180 Shut Open Used for pressure control and cooldown Valve MS/Solenoid Valve for PCV1 Pilot valve for associated SRV 279 3PSV1180 Deenergized Energized 180 Power: From 250 VDC RMOV Board 3A 3PCV 14 Control Room Hand Open SRV for cooldown 280 3HS14 Auto Open Switch Power: From 250 VDC RMOV Board 3A 281 3XS14 Transfer Switch for 3PCV14 Closed Closed 3PCV 15 Control Room Hand Open SRV for cooldown 281 3HS15A Auto Open Switch Power: From 250 VDC RMOV Board 3C 282 3XS15 Transfer Switch for 3PCV15 Closed Closed 3PCV 119 Control Room Hand Open SRV for cooldown 283 3HS118 Auto Open Switch Power: From 250 VDC RMOV Board 3B 284 3XS118 Transfer Switch for 2PCV118 Closed Closed 3PCV 119 Control Room Hand Open SRV for cooldown 285 3HS119A Auto Open Switch Power: From 250 VDC RMOV Board 3B Page A26

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 286 3XS119 Transfer Switch for 3PCV119 Closed Closed 3PCV 122 Control Room Hand Open SRV for cooldown 287 3HS122A Auto Open Switch Power: From 250 VDC RMOV Board 3B 288 3XS122 Transfer Switch for 3PCV122 Closed Closed 3PCV 123 Control Room Hand Open SRV for cooldown 289 3HS123 Closed Closed Switch Power: From 250 VDC RMOV Board 3C 290 3XS123 Transfer Switch for 3PCV123 Closed Closed 3PCV 130 Control Room Hand Open SRV for cooldown 291 3HS130A Auto Open Switch Power: From 250 VDC RMOV Board 3A 292 3XS130 Transfer Switch for 3PCV130 Closed Closed 3PCV 131 Control Room Hand Open SRV for cooldown 293 3HS131A Auto Open Switch Power: From 250 VDC RMOV Board 3B 294 3XS131 Transfer Switch for 3PCV131 Closed Closed 3PCV 134 Control Room Hand Open SRV for cooldown 295 3HS134A Auto Open Switch Power: From 250 VDC RMOV Board 3C 296 3XS134 Transfer Switch for 3PCV134 Closed Closed 3PCV 141 Control Room Hand Open SRV for cooldown 297 3HS141 Auto Open Switch Power: From 250 VDC RMOV Board 3C 298 3XS141 Transfer Switch for 3PCV141 Closed Closed Page A27

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 3PCV 142 Control Room Hand Open SRV for cooldown 299 3HS142 Auto Open Switch Power: From 250 VDC RMOV Board 3B 300 3XS142 Transfer Switch for 3PCV142 Closed Closed 3PCV 1179 Control Room Open SRV for cooldown 301 3HS1179A Auto Open Hand Switch Power: From 250 VDC RMOV Board 3B Transfer Switch for 3PCV1 302 3XS1179 Closed Closed 179 3PCV 1180 Control Room Open SRV for cooldown 303 3HS1180A Auto Open Hand Switch Power: From 250 VDC RMOV Board 3A Transfer Switch for 3PCV1 304 3XS1180 Closed Closed 180 Used to inhibit automatic initiation of ADS 305 3XS1159A ADS Inhibit Switch Normal Inhibit Power: From 250 VDC RMOV Board 3B 306 Number not used. Duplicate UNID removed.

Used to inhibit automatic initiation of ADS 307 3XS1161A ADS Inhibit Switch Normal Inhibit Power: From 250 VDC RMOV Board 3B Local Panel 2532: Backup 308 3LPNL2532 Operable Operable Failure of panel or components can prevent opening SRVs Control Instrumentation - Unit 1 Gives indication of RPV level 309 1LI358B RPV Level Instrument Operating Operating Power: From Division II 250 VDC RPV Level Indication Gives indication of RPV level 310 1LIS358B Operating Operating Switch Power: From Division II 250 VDC Page A28

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments Gives indication of RPV level 311 1LT358B RPV Level Transmitter Operating Operating Power: From Division II 250 VDC Gives indication of RPV level 312 1LS358B RPV Level Switch Operating Operating Power: From Division II 250 VDC 313 1LI355 RPV Shutdown Floodup Range Operating Operating 314 1LT355 RPV Shutdown Floodup Range Operating Operating Gives indication of RPV pressure 315 1PI374B RPV Pressure Indicator Operating Operating Power: From Division II 250 VDC RPV Pressure Indication / Gives indication of RPV pressure 316 1PIS374B Operating Operating Switch Power: From Division II 250 VDC Gives indication of RPV pressure 317 1PT374B RPV Pressure Transmitter Operating Operating Power: From Division II 250 VDC 1TIS64 Drywell Temperature Indicator 318 Operating Operating 52AA Switch 319 1TI6452AB Drywell Temperature Indicator Operating Operating 320 1PI06467B Drywell Pressure Indicator Operating Operating Gives indication of drywell pressure 321 1PT06467 Drywell Pressure Transmitter Operating Operating Gives indication of drywell pressure 1LI064 Suppression Pool Level Gives indication of suppression pool level 322 Operating Operating 159A Indicator (Division II) Power: From Division II 250 VDC Power Page A29

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 1LT064 Suppression Pool Level Gives indication of suppression pool level 323 Operating Operating 159A Transmitter (Division II) Power: From Division II 250 VDC Power Torus Bulk Water Temperature 324 1TI064161 Operating Operating Gives indication of bulk torus water temperature (Division I) 1TM64 325 Torus Temperature Module A Operating Operating Feeds the indication of bulk torus water temperature 161A 326 1TE64161A Torus Temperature Element A Operating Operating Feeds the indication of bulk torus water temperature 1TM64 327 Torus Temperature Module B Operating Operating Feeds the indication of bulk torus water temperature 161B 328 1TE64161B Torus Temperature Element B Operating Operating Feeds the indication of bulk torus water temperature 1TM64 329 Torus Temperature Module C Operating Operating Feeds the indication of bulk torus water temperature 161C 330 1TE64161C Torus Temperature Element C Operating Operating Feeds the indication of bulk torus water temperature 1TM64 331 Torus Temperature Module D Operating Operating Feeds the indication of bulk torus water temperature 161D 332 1TE64161D Torus Temperature Element D Operating Operating Feeds the indication of bulk torus water temperature 1TM64 333 Torus Temperature Module E Operating Operating Feeds the indication of bulk torus water temperature 161E 334 1TE64161E Torus Temperature Element E Operating Operating Feeds the indication of bulk torus water temperature 1TM64 335 Torus Temperature Module F Operating Operating Feeds the indication of bulk torus water temperature 161F Page A30

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 336 1TE64161F Torus Temperature Element F Operating Operating Feeds the indication of bulk torus water temperature 1TM64 337 Torus Temperature Module G Operating Operating Feeds the indication of bulk torus water temperature 161G 338 1TE64161G Torus Temperature Element G Operating Operating Feeds the indication of bulk torus water temperature 1TM64 339 Torus Temperature Module H Operating Operating Feeds the indication of bulk torus water temperature 161H 340 1TE64161H Torus Temperature Element H Operating Operating Feeds the indication of bulk torus water temperature 341 1TM64161J Torus Temperature Module J Operating Operating Feeds the indication of bulk torus water temperature 1TM64 342 Torus Temperature Module K Operating Operating Feeds the indication of bulk torus water temperature 161K 1TM64 343 Torus Temperature Module L Operating Operating Feeds the indication of bulk torus water temperature 161L 1PNLA009 Reactor Shutdown &

344 Operable Operable Indications and controls 0003A Containment Cooling Panel 1PNLA009 Reactor Shutdown &

345 Operable Operable Indications and controls 0003B Containment Cooling Panel 1PNLA009 I&C Bus 1A and 1B (Cabinet 2 346 Operable Operable Power for I&C Buses 1A and 1B 009 and 3 of Panel 199) 1PNLA009 RHR, CS, HPCI (Channel A), Logic for RHR, core spray, High Pressure Core Injection 347 Operable Operable 0032 RCIC, ADS Panel (HPCI), RCIC, ADS 1PNLA009 RHR, CS, HPCI (Channel B),

348 Operable Operable Logic for Emergency Core Cooling System (ECCS) 0033 RCIC, ADS Logic Panel Page A31

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 1PNLA009 Analog Trip Unit (ATU) for RPV and containment instrument 349 Division I ECCS ATU Cabinet Operable Operable 0081 signals 1PNLA009 350 Division II ECCS ATU Cabinet Operable Operable ATU for RPV and containment instrument signals 0082 1PNLA009 Division I Torus Temperature 351 Operable Operable Provides indication of torus water temperature 0087 Monitoring 1LPNL925 352 Local Panel 255A Operable Operable Local instrumentation rack/panel 005A 1LPNL925 353 Local Panel 255B Operable Operable Local instrumentation rack/panel 005B 1LPNL925 354 RCIC Instrumentation Panel Operable Operable RCIC local instrumentation panel 0058 1LPNL925 355 Instrumentation Rack 256B Operable Operable Local instrumentation rack/panel (drywell pressure) 006B 1PNLA925 356 Local Panel 2531 Operable Operable RCIC local isolation instrumentation 0031 1LPNL925 357 RCIC Local Controls Operable Operable Can fail and block control room operation 672 Instrumentation - Unit 2 Gives indication of RPV level 358 2LI358B RPV Level Instrument Operating Operating Power: From Division II 250 VDC Gives indication of RPV level 359 2LIS358B RPV Level Indication / Switch Operating Operating Power: From Division II 250 VDC Gives indication of RPV level 360 2LT358B RPV Level Transmitter Operating Operating Power: From Division II 250 VDC Page A32

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments Gives indication of RPV level 361 2LS358B RPV Level Switch Operating Operating Power: From Division II 250 VDC 362 2LI355 RPV Shutdown Floodup Range Operating Operating 363 2LT355 RPV Shutdown Floodup Range Operating Operating 364 2PI374B RPV Pressure Indicator Operating Operating Power: From Division II 250 VDC RPV Pressure Indication /

365 2PIS374B Operating Operating Gives indication of RPV pressure Switch 366 2PT374B RPV Pressure Transmitter Operating Operating Gives indication of RPV pressure 2TIS64 Drywell Temperature Indicator 367 Operating Operating 52AA Switch 368 2TI6452AB Drywell Temperature Indicator Operating Operating 369 2PI06467B Drywell Pressure Indicator Operating Operating Gives indication of drywell pressure 370 2PT06467B Drywell Pressure Transmitter Operating Operating Gives indication of drywell pressure 2LI064 Suppression Pool Level Gives indication of suppression pool level 371 Operating Operating 159A Indicator (Division II) Power: From Division II 250 VDC Power 2LT064 Suppression Pool Level Gives indication of suppression pool level 372 Operating Operating 159A Transmitter (Division II) Power: From Division II 250 VDC Power Torus Bulk Water Temperature 373 2TI064161 Operating Operating Gives indication of bulk torus water temperature (Division I)

Page A33

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 2TM64 374 Torus Temperature Module A Operating Operating Feeds the indication of bulk torus water temperature 161A 375 2TE64161A Torus Temperature Element A Operating Operating Feeds the indication of bulk torus water temperature 2TM64 376 Torus Temperature Module B Operating Operating Feeds the indication of bulk torus water temperature 161B 377 2TE64161B Torus Temperature Element B Operating Operating Feeds the indication of bulk torus water temperature 2TM64 378 Torus Temperature Module C Operating Operating Feeds the indication of bulk torus water temperature 161C 379 2TE64161C Torus Temperature Element C Operating Operating Feeds the indication of bulk torus water temperature 2TM64 380 Torus Temperature Module D Operating Operating Feeds the indication of bulk torus water temperature 161D 381 2TE64161D Torus Temperature Element D Operating Operating Feeds the indication of bulk torus water temperature 2TM64 382 Torus Temperature Module E Operating Operating Feeds the indication of bulk torus water temperature 161E 383 2TE64161E Torus Temperature Element E Operating Operating Feeds the indication of bulk torus water temperature 2TM64 384 Torus Temperature Module F Operating Operating Feeds the indication of bulk torus water temperature 161F 385 2TE64161F Torus Temperature Element F Operating Operating Feeds the indication of bulk torus water temperature 2TM64 386 Torus Temperature Module G Operating Operating Feeds the indication of bulk torus water temperature 161G Page A34

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 387 2TE64161G Torus Temperature Element G Operating Operating Feeds the indication of bulk torus water temperature 2TM64 388 Torus Temperature Module H Operating Operating Feeds the indication of bulk torus water temperature 161H 389 2TE64161H Torus Temperature Element H Operating Operating Feeds the indication of bulk torus water temperature 390 2TM64161J Torus Temperature Module J Operating Operating Feeds the indication of bulk torus water temperature 2TM64 391 Torus Temperature Module K Operating Operating Feeds the indication of bulk torus water temperature 161K 2TM64 392 Torus Temperature Module L Operating Operating Feeds the indication of bulk torus water temperature 161L 2PNLA009 Reactor Shutdown &

393 Operable Operable Indications and controls 0003A Containment Cooling Panel 2PNLA009 Reactor Shutdown &

394 Operable Operable Indications and controls 0003B Containment Cooling Panel 2PNLA009 I&C Bus 1A and 1B (Cabinet 2 395 Operable Operable Power for I&C Buses 1A and 1B 009 and 3 of panel 199) 2PNLA009 RHR, CS, HPCI (Channel A),

396 Operable Operable Logic for ECCS systems 0032 RCIC, ADS Panel 2PNLA009 RHR, CS, HPCI (Channel B),

397 Operable Operable Logic for ECCS systems 0033 RCIC, ADS Logic Panel 2PNLA009 398 Division I ECCS ATU Cabinet Operable Operable ATU for RPV and containment instrument signals 0081 2PNLA009 399 Division II ECCS ATU Cabinet Operable Operable ATU for RPV and containment instrument signals 0082 Page A35

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 2PNLA009 Division I Torus Temperature 400 Operable Operable Provides indication of torus water temperature 0087 Monitoring 2LPNL925 401 Local Panel 255A Operable Operable Local instrumentation rack/panel 005A 2LPNL925 402 Local Panel 255B Operable Operable Local instrumentation rack/panel 005B 2LPNL925 403 RCIC Instrumentation Panel Operable Operable RCIC local instrumentation panel 0058 2LPNL925 404 Instrumentation Rack 256A Operable Operable Local instrumentation rack/panel (RPV level) 006A 2PNLA925 406 Local Panel 2531 Operable Operable RCIC local isolation instrumentation 0031 2LPNL925 406 RCIC Local Controls Operable Operable Can fail and block control room operation 672 Instrumentation - Unit 3 Gives indication of RPV level 407 3LI358B RPV Level Instrument Operating Operating Power: From Division II 250 VDC Gives indication of RPV level 408 3LIS358B RPV Level Indication Operating Operating Power: From Division II 250 VDC Gives indication of RPV level 409 3LT358B RPV Level Transmitter Operating Operating Power: From Division II 250 VDC Gives indication of RPV level 410 3LS358B RPV Level Switch Operating Operating Power: From Division II 250 VDC 411 3LI355 RPV Shutdown Floodup Range Operating Operating Page A36

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 412 3LT355 RPV Shutdown Floodup Range Operating Operating 413 3PI374B RPV Pressure Indicator Operating Operating Power: From Division II 250 VDC RPV Pressure Indication /

414 3PIS374B Operating Operating Gives indication of RPV pressure Switch 415 3PT374B RPV Pressure Transmitter Operating Operating Gives indication of RPV pressure 3TIS64 Drywell Temperature Indicator 416 Operating Operating 52AA Switch 417 3TI6452AB Drywell Temperature Indicator Operating Operating 418 3PI06467B Drywell Pressure Indicator Operating Operating Gives indication of drywell pressure 419 3PT06467 Drywell Pressure Transmitter Operating Operating Gives indication of drywell pressure 3LI064 Suppression Pool Level Gives indication of suppression pool level 420 Operating Operating 159A Indicator (Division II) Power: From Division II 250 VDC Power 3LT064 Suppression Pool Level Gives indication of suppression pool level 421 Operating Operating 159A Transmitter (Division II) Power: From Division II 250 VDC Power Torus Bulk Water Temperature 422 3TI064161 Operating Operating Gives indication of bulk torus water temperature (Division I) 3TM64 423 Torus temperature module A Operating Operating Feeds the indication of bulk torus water temperature 161A 424 3TE64161A Torus Temperature Element A Operating Operating Feeds the indication of bulk torus water temperature Page A37

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 3TM64 425 Torus Temperature Module B Operating Operating Feeds the indication of bulk torus water temperature 161B 426 3TE64161B Torus Temperature Element B Operating Operating Feeds the indication of bulk torus water temperature 3TM64 427 Torus Temperature Module C Operating Operating Feeds the indication of bulk torus water temperature 161C 428 3TE64161C Torus Temperature Element C Operating Operating Feeds the indication of bulk torus water temperature 3TM64 429 Torus Temperature Module D Operating Operating Feeds the indication of bulk torus water temperature 161D 430 3TE64161D Torus Temperature Element D Operating Operating Feeds the indication of bulk torus water temperature 3TM64 431 Torus Temperature Module E Operating Operating Feeds the indication of bulk torus water temperature 161E 432 3TE64161E Torus Temperature Element E Operating Operating Feeds the indication of bulk torus water temperature 3TM64 433 Torus Temperature Module F Operating Operating Feeds the indication of bulk torus water temperature 161F 434 3TE64161F Torus Temperature Element F Operating Operating Feeds the indication of bulk torus water temperature 3TM64 435 Torus Temperature Module G Operating Operating Feeds the indication of bulk torus water temperature 161G 436 3TE64161G Torus Temperature Element G Operating Operating Feeds the indication of bulk torus water temperature 3TM64 437 Torus Temperature Module H Operating Operating Feeds the indication of bulk torus water temperature 161H Page A38

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 438 3TE64161H Torus Temperature Element H Operating Operating Feeds the indication of bulk torus water temperature 439 3TM64161J Torus Temperature Module J Operating Operating Feeds the indication of bulk torus water temperature 3TM64 440 Torus Temperature Module K Operating Operating Feeds the indication of bulk torus water temperature 161K 3TM64 441 Torus Temperature Module L Operating Operating Feeds the indication of bulk torus water temperature 161L 3PNLA009 Reactor Shutdown &

442 Operable Operable Indications and controls 0003A Containment Cooling Panel 3PNLA009 Reactor Shutdown &

443 Operable Operable Indications and controls 0003B Containment Cooling Panel 3PNLA009 I&C Bus 1A and 1B (Cabinet 2 444 Operable Operable Power for I&C Buses 1A and 1B 009 and 3 of Panel 199) 3PNLA009 RHR, CS, HPCI (Channel A),

445 Operable Operable Logic for ECCS systems 0032 RCIC, ADS Panel 3PNLA009 RHR, CS, HPCI (Channel B),

446 Operable Operable Logic for ECCS systems 0033 RCIC, ADS Logic Panel 3PNLA009 447 Division I ECCS ATU Cabinet Operable Operable ATU for RPV and containment instrument signals 0081 3PNLA009 448 Division II ECCS ATU Cabinet Operable Operable ATU for RPV and containment instrument signals 0082 3PNLA009 Division I Torus Temp 449 Operable Operable Provides indication of torus water temperature 0087 Monitoring 3LPNL925 450 Local Panel 255A Operable Operable Local instrumentation rack/panel 005A Page A39

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 3LPNL925 451 Local Panel 255B Operable Operable Local instrumentation rack/panel 005B 3LPNL925 452 RCIC Instrumentation Panel Operable Operable RCIC local instrumentation panel 0058 3LPNL925 453 Instrumentation Rack 256B Operable Operable Local instrumentation rack/panel (drywell pressure) 006B 3PNLA925 454 Local Panel 2531 Operable Operable RCIC local isolation instrumentation 0031 3LPNL925 455 RCIC Local Controls Operable Operable Can fail and block control room operation 672 Electric Power - All Three Units 1BDBB281 456 250V RMOV Board 1A Energized Energized Power: For RCIC and ADS 0001A 1BDBB281 457 250V RMOV Board 1B Energized Energized Power: For RCIC and ADS 0001B 1BDBB281 458 250V RMOV Board 1C Energized Energized Power: For RCIC and ADS 0001C 2BDBB281 459 250V RMOV Board 2A Energized Energized Power: For RCIC and ADS 0002A 2BDBB281 460 250V RMOV Board 2B Energized Energized Power: For RCIC and ADS 0002B 2BDBB281 461 250V RMOV Board 2C Energized Energized Power: For RCIC and ADS 0002C 3BDBB281 462 250V RMOV Board 3A Energized Energized Power: For RCIC and ADS 0003A Page A40

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 3BDBB281 463 250V RMOV Board 3B Energized Energized Power: For RCIC and ADS 0003B 3BDBB281 464 250V RMOV Board 3C Energized Energized Power: For RCIC and ADS 0003C 0BDDD280 465 250V Battery Board 1 Energized Energized 250 VDC power for 250 VDC buses and AC control power 0001 0BATA248 466 250V Main Battery 1 Energized Energized 250 VDC power for 250 VDC buses and AC control power 0001 0CHGA248 467 Unit Battery Charger 1 Energized Energized 250 VDC power for 250 VDC buses and AC control power 0001 0BDDD280 468 250V Battery Board 2 Energized Energized 250 VDC power for 250 VDC buses and AC control power 0002 0BATA248 469 250V Main Battery 2 Energized Energized 250 VDC power for 250 VDC buses and AC control power 0002 0CHGA248 470 Unit Battery Charger 2A Energized Energized 250 VDC power for 250 VDC buses and AC control power 0002A 0BDDD280 471 250V Battery Board 3 Energized Energized 250 VDC power for 250 VDC buses and AC control power 0003 0BATA248 472 250V Main Battery 3 Energized Energized 250 VDC power for 250 VDC buses and AC control power 0003 0CHGA248 473 Unit Battery Charger 3 Energized Energized 250 VDC power for 250 VDC buses and AC control power 0003 0PNLA248 474 250V Distribution Panel SBA Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000A 0BATA248 475 250V Battery SBA Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000A Page A41

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 0CHGA248 476 250V Battery Charger SBA Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000A 477 0PNLA248B 250V Distribution Panel SBB Energized Energized 250 VDC power for 250 VDC buses and AC control power 0BATA248 478 250V Battery SBB Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000B 0CHGA248 479 250V Battery Charger SBB Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000B 0BATA248 480 250V Battery SBC Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000C 0PNLA248 481 250V Distribution Panel SBC Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000C 0CHGA248 482 250V Battery Charger SBC Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000C 0BATA248 483 250V Battery SBD Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000D 0PNLA248 484 250V Distribution Panel SBD Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000D 0CHGA248 485 250V Battery Charger SBD Energized Energized 250 VDC power for 250 VDC buses and AC control power 0000D 1BDBB231 Acts as the connection point for the Unit 1 480V FLEX diesel 486 480 V Shutdown Board 1A Energized Energized 0001A generator and provides 480 VAC for FLEX loads 1BDBB231 487 480 V Shutdown Board 1B Energized Energized Provides 480 VAC for FLEX loads 0001B 2BDBB231 Acts as the connection point for the Unit 2 480V FLEX diesel 488 480 V Shutdown Board 2A Energized Energized 0002A generator and provides 480 VAC for FLEX loads Page A42

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 2BDBB231 489 480 V Shutdown Board 2B Energized Energized Provides 480 VAC for FLEX loads 0002B 3BDBB231 490 480 V Shutdown Board 3A Energized Energized Provides 480 VAC for FLEX loads 0003A 3BDBB231 491 480 V Shutdown Board 3B Energized Energized Provides 480 VAC for FLEX loads 0003B 1BDBB268 492 480 V RMOV Board 1A Energized Energized Provides 480 VAC for FLEX loads 0001A 1BDBB268 493 480 V RMOV Board 1B Energized Energized Provides 480 VAC for FLEX loads 0001B 2BDBB268 494 480 V RMOV Board 2A Energized Energized Provides 480 VAC for FLEX loads 0002A 2BDBB268 495 480 V RMOV Board 2B Energized Energized Provides 480 VAC for FLEX loads 0002B 3BDBB268 496 480 V RMOV Board 3A Energized Energized Provides 480 VAC for FLEX loads 0003A 3BDBB268 497 480 V RMOV Board 3B Energized Energized Provides 480 VAC for FLEX loads 0003B 0BDAA211 498 4 kV Shutdown Board A Operable Operable 0000A 0BDAA211 499 4 kV Shutdown Board B Operable Operable 0000B 0BDAA211 500 4 kV Shutdown Board C Operable Operable 0000C 0BDAA211 501 4 kV Shutdown Board D Operable Operable 0000D Page A43

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments 0BDAA211 502 4 kV Shutdown Board 3EA Operable Operable 0000EA 0BDAA211 503 4 kV Shutdown Board 3EC Operable Operable 0000EC 1XFA231 504 4KV/480 Transformer TS1A Operable Operable TS1A 1XFA231 505 4KV/480 Transformer TS1A Operable Operable TS1B 2XFA231 506 4KV/480 Transformer TS1A Operable Operable TS2A 2XFA231 507 4KV/480 Transformer TS1A Operable Operable TS2B 3XFA231 508 4KV/480 Transformer TS1A Operable Operable TS2A 3XFA231 509 4KV/480 Transformer TS1A Operable Operable TS2B 3XFA231 510 4KV/480 Transformer TS1E Operable Operable TS1E FLEX 480V Diesel Generator 511 TBD Battery Charging Distribution Operable Operable UNID to be established in DCN 71470 Panel RHR - Unit 1 RHR/Loop II Torus Open to provide containment heat removal 512 1FCV7471 Containment Cooling/Spray Shut Open Power: From 480V RMOV Board 1B Valve Page A44

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments RHR/Loop II Suppression Pool Open to provide containment heat removal 513 1FCV7472 Shut Open Spray Valve Power: From 480V RMOV Board 1B RHR/Loop II Recirculation 514 1FCV7473 Shut Open Power: From 480V RMOV Board 1B Pump Test Valve RHR/Loop II Outboard Drywell Open to provide containment heat removal 515 1FCV7474 Shut Open Spray Valve Power: From 480V RMOV Board 1B RHR/Loop II Inboard Drywell Open to provide containment heat removal 516 1FCV7475 Shut Open Spray Valve Power: From 480V RMOV Board 1B Unit 1 RHR Outboard Injection Open to provide shutdown cooling in Phases 2 and 3 517 1FCV7467 Valve to Recirculation Loop A Shut Open Power: From 480V RMOV Board 1B for Shutdown Cooling Crosstie to Unit 2 RHR Heat Open to provide shutdown cooling in Phases 2 and 3 519 1FCV74101 Shut Open Exchanger Power: From 480V RMOV Board 1B 519 1HEX900B B RHR Heat Exchanger Operable Operable Failure could result in flow diversion 520 1HEX900D B RHR Heat Exchanger Operable Operable Failure could result in flow diversion RHR - Unit 2 RHR/Loop II Torus Open to provide containment heat removal 521 2FCV7471 Containment Cooling/Spray Shut Open Power: From 480V RMOV Board 2B Valve RHR/Loop II Suppression Pool Open to provide containment heat removal 522 2FCV7472 Shut Open Spray Valve Power: From 480V RMOV Board 2B RHR/Loop II Recirculation 523 2FCV7473 Shut Open Power: From 480V RMOV Board 2B Pump Test Valve Page A45

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments RHR/Loop II Outboard Drywell Open to provide containment heat removal 524 2FCV7474 Shut Open Spray Valve Power: From 480V RMOV Board 2B RHR/Loop II Inboard Drywell Open to provide containment heat removal 525 2FCV7475 Shut Open Spray Valve Power: From 480V RMOV Board 2B Unit 2 RHR Outboard Injection Open to provide shutdown cooling in phases 2 and 3 526 2FCV 7467 Valve To Recirculation Loop A Shut Open Power: From 480V RMOV Board 2E For Shutdown Cooling Opened to provide flow path for RHR service water to RHR Crosstie to Unit 1 RHR Heat 527 2FCV74100 Shut Open injection.

Exchanger Power: From 480V RMOV Board 1B Opened to provide flow path for RHR service water to RHR Crosstie to Unit 3 RHR Heat 528 2FCV74101 Shut Open injection.

Exchanger Power: From 480V RMOV Board 3B 529 2HEX900A A RHR Heat Exchanger Operable Operable Failure could result in flow diversion 530 2HEX900C C RHR Heat Exchanger Operable Operable Failure could result in flow diversion 531 2HEX900B B RHR Heat Exchanger Operable Operable Failure could result in flow diversion 532 2HEX900D D RHR Heat Exchanger Operable Operable Failure could result in flow diversion RHR - Unit 3 RHR/Loop II Torus Open to provide containment heat removal 533 2FCV7457 Containment Cooling/Spray Shut Open Power: From 480V RMOV Board 3A Valve Page A46

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments RHR/Loop II Suppression Pool Open to provide containment heat removal 534 3FCV7458 Shut Open Spray Valve Power: From 480V RMOV Board 3A RHR/Loop I Recirculation Pump 535 3FCV7459 Shut Open Power: From 480V RMOV Board 3A Test Valve RHR/Loop II Outboard Drywell Open to provide containment heat removal 536 3FCV7460 Shut Open Spray Valve Power: From 480V RMOV Board 3A RHR/Loop II Inboard Drywell Open to provide containment heat removal 537 3FCV7461 Shut Open Spray Valve Power: From 480V RMOV Board 3A Unit 3 RHR Outboard Injection Open to provide shutdown cooling in Phases 2 and 3 538 3FCV 7453 Valve to Recirculation Loop A Closed Open Power: From 480V RMOV Board 3D for Shutdown Cooling Crosstie to Unit 3 RHR Heat Open to provide shutdown cooling in Phases 2 and 3 539 3FCV74100 Closed Open Exchanger Power: From 480V RMOV Board 3B 540 3HEX900A A RHR Heat Exchanger Operable Operable Failure could result in flow diversion 541 3HEX900C C RHR Heat Exchanger Operable Operable Failure could result in flow diversion RHR Service Water - Unit 1 RHR/RHR Service Water Cross 542 1FCV2357 Closed Open 480 RMOV Board 1B Connect Valve RHR Service Water - Unit 2 RHR/RHR Service Water Cross 543 2FCV2357 Closed Open 480 RMOV Board 3B Connect Valve Page A47

Browns Ferry Nuclear Plant ESEP Report Table A1: Expedited Seismic Equipment List (ESEL) for Browns Ferry Nuclear Plant (Continued)

ESEL Equipment Operating State Item Number Normal Desired ID Description State State Notes/Comments Containment Vent - Unit 1 Containment Hardened Vent 544 1FCV64221 Closed Open To be operated manually walkby only Valve Containment Hardened Vent 545 1FCV64222 Closed Open To be operated manually walkby only Valve Containment Vent - Unit 2 Containment Hardened Vent 546 2FCV64221 Closed Open To be operated manually walkby only Valve Containment Hardened Vent 547 2FCV64222 Closed Open To be operated manually walkby only Valve Containment Vent - Unit 3 Containment Hardened Vent 548 3FCV64221 Closed Open To be operated manually walkby only Valve Containment Hardened Vent 549 3FCV64222 Closed Open To be operated manually walkby only Valve Page A48

Browns Ferry Nuclear Plant ESEP Report ATTACHMENT B - ESEP HCLPF VALUES AND FAILURE MODES TABULATION FOR BROWNS FERRY NUCLEAR PLANT Page B1

Browns Ferry Nuclear Plant ESEP Report Table B1: ESEP HCLPF Values and Failure Modes for Browns Ferry Nuclear Plant HCLPF Equipment Equipment Floor Equipment Description Building Failure Mode Capacity ID Class Elevation (g) 1FCV7119 U1 RB RCIC Pump Condensate 2FCV7119 Storage Tank Suction 8A U2 RB 528 Functional 0.69g Valve 3FCV7119 U3 RB 1FCV7117 U1 RB 2FCV7117 RCIC Suction from Torus 8A U2 RB 528 Functional 0.69g 3FCV7117 U3 RB 1FCV7118 U1 RB 2FCV7118 RCIC Suction from Torus 8A U2 RB 528 Functional 0.69g 3FCV7118 U3 RB 1PMP7119 U1 RB 2PMP7119 RCIC Pump 5 U2 RB 519 Functional 0.85g 3PMP7119 U3 RB 1FCV7139 U1 RB RCIC Discharge Isolation 2FCV7139 8A U2 RB 541 Functional 0.69g Valve 3FCV7139 U3 RB 1PCV7122 U1 RB RCIC Lube Oil Cooling 2PCV7122 Water Pressure Control 7 U2 RB 519 Functional 0.67g Valve 3PCV7122 U3 RB Page B2

Browns Ferry Nuclear Plant ESEP Report Table B1: ESEP HCLPF Values and Failure Modes for Browns Ferry Nuclear Plant (Continued)

HCLPF Equipment Equipment Floor Equipment Description Building Failure Mode Capacity ID Class Elevation (g) 1FCV7125 U1 RB RCIC Turbine Lube Oil 2FCV7125 8A U2 RB 528 Functional 0.69g Inlet Valve 3FCV7125 U3 RB 1TNK7127 U1 RB RCIC Barometric 2TNK7127 Condenser and Vacuum 21 U2 RB 519 Functional 1.38g Tank 3TNK7127 U3 RB 1CLR7125 U1 RB 2CLR7125 RCIC Lube Oil Cooler 21 U2 RB 519 Anchorage 1.35g 3CLR7125 U3 RB 1PMP7129 U1 RB RCIC Vacuum Tank 2PMP7129 6 U2 RB 519 Functional 1.38g Condenser Pump 3PMP7129 U3 RB 1PMP7131 U1 RB 2PMP7131 RCIC Vacuum Pump 5 U2 RB 519 Functional 1.38g 3PMP7131 U3 RB 1FCV718 U1 RB RCIC Turbine Steam Inlet 2FCV718 8A U2 RB 528 Functional 0.69g Valve 3FCV718 U3 RB 1FCV719 U1 RB RCIC Turbine Steam 8A 528 Functional 0.69g Throttle Valve 2FCV719 U2 RB Page B3

Browns Ferry Nuclear Plant ESEP Report Table B1: ESEP HCLPF Values and Failure Modes for Browns Ferry Nuclear Plant (Continued)

HCLPF Equipment Equipment Floor Equipment Description Building Failure Mode Capacity ID Class Elevation (g) 3FCV719 U3 RB 1FCV7110 U1 RB RCIC Turbine Governor 2FCV7110 7 U2 RB 519 Functional 0.85g Valve 3FCV7110 U3 RB 1TRB719 U1 RB 2TRB719 RCIC Turbine 5 U2 RB 519 Functional 0.85g 2TRB719 U3 RB 1FT7136 U1 RB RCIC Pump Flow 2FT7136 Transmitter for Turbine 18 U2 RB 519 Anchorage 0.74g Control 3FT7136 U3 RB 1FIC7136A U1 RB RCIC Flow Indicating 2FIC7136A 20 U2 RB 617 Functional 0.62g Controller 3FIC7136A U3 RB 1PX7136A U1 RB Power Supply for RCIC 2PX7136A 20 U2 RB 621 Functional 0.62g Flow Controller 3PX7136A U3 RB 1LPNL925 U1 RB 672 2LPNL925 RCIC Local Controls 20 U2 RB 519 Anchorage 0.74g 672 3LPNL925 U3 RB 672 1LPNL25 Transfer Switches for 20 U1 RB 593 Functional 0.62g 658 System 1 PCVs Page B4

Browns Ferry Nuclear Plant ESEP Report Table B1: ESEP HCLPF Values and Failure Modes for Browns Ferry Nuclear Plant (Continued)

HCLPF Equipment Equipment Floor Equipment Description Building Failure Mode Capacity ID Class Elevation (g) 2LPNL25 U2 RB 658 3LPNL25 U3 RB 658 Crosstie to U1 RHR Heat 2FCV74100 8A U1 RB 565 Functional 0.71g Exchanger Crosstie to U3 RHR Heat 2FCV74101 8A U2 RB 565 Functional 0.71g Exchanger Crosstie to U3 RHR Heat 3FCV74101 8A U2 RB 565 Functional 0.71g Exchanger 1LPNL925 U1 RB 0058 2LPNL925 RCIC Instrumentation 20 U2 RB 519 Anchorage 0.74g 0058 Panel 3LPNL925 U3 RB 0058 Page B5