View source for CNL-14-212, Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident

{{Adams
| number = ML14365A072
| issue date = 12/30/2014
| title = Expedited Seismic Evaluation Process Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident
| author name = Shea J
| author affiliation = Tennessee Valley Authority
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000390, 05000391
| license number = CPPR-0092, NPF-090
| contact person = 
| case reference number = CNL-14-212
| document type = Letter type:CNL, Report, Miscellaneous
| page count = 111
| project = 
| stage = Response to RAI
}}

=Text=
{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-212 December 30, 2014 10 CFR 50.4 10 CFR 50.54(f)
Attn: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390 Watts Bar Nuclear Plant, Unit 2 Construction Permit No. CPPR-92 NRC Docket No. 50-391

==Subject:==
Tennessee Valley Authoritys Watts Bar 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

==Reference:==
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 Watts Bar Nuclear Plant.

U.S. Nuclear Regulatory Commission CNL-14-212 Page 2 December 30, 2014 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.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 30th day of December 2014.
Respectfully, Digitally signed by J. W. Shea DN: cn=J. W. Shea, o=Tennessee J. W. Shea    Valley Authority, ou=Nuclear Licensing, email=jwshea@tva.gov, c=US Date: 2014.12.30 11:50:55 -05'00' J. W. Shea Vice President, Nuclear Licensing

==Enclosure:==
Expedited Seismic Evaluation Process (ESEP) Report for Watts Bar 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 - Watts Bar Nuclear Plant, Unit 1 NRR Project Manager - Watts Bar Nuclear Plant, Unit 2 NRR JLD Project Manager - Watts Bar Nuclear Plant NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 1 NRC Senior Resident Inspector - Watts Bar Nuclear Plant, Unit 2

ENCLOSURE EXPEDITED SEISMIC EVALUATION PROCESS (ESEP) REPORT FOR WATTS BAR NUCLEAR PLANT

Watts Bar Nuclear Plant ESEP Report EXPEDITED SEISMIC EVALUATION PROCESS (ESEP) REPORT FOR WATTS BAR NUCLEAR PLANT

Watts Bar 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.................................................................................. 8 3.1     Equipment Selection Process and ESEL .............................................................................. 8 3.1.1         ESEL Development ............................................................................................... 9 3.1.2         PowerOperated 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 ................................................................................................................ 11 4.0    GROUND MOTION RESPONSE SPECTRUM (GMRS) ...................................................................... 11 4.1     Plot of GMRS Submitted by the Licensee ......................................................................... 11 4.2     Comparison to SSE ............................................................................................................ 13 5.0    REVIEW LEVEL GROUND MOTION (RLGM) ................................................................................... 14 5.1     Description of RLGM Selected .......................................................................................... 14 5.2     Method to Estimate InStructure Response Spectra (ISRS) .............................................. 15 6.0    SEISMIC MARGIN EVALUATION APPROACH ................................................................................. 16 6.1     Summary of Methodologies Used .................................................................................... 16 6.2     HCLPF Screening Process .................................................................................................. 17 6.3     Seismic Walkdown Approach ........................................................................................... 18 6.3.1         Walkdown Approach.......................................................................................... 18 6.3.2         Application of Previous Walkdown Information ............................................... 19 6.3.3         Significant Walkdown Findings .......................................................................... 19 6.4     HCLPF Calculation Process ................................................................................................ 20 6.5     Functional Evaluations of Relays ...................................................................................... 21 6.6     Tabulated ESEL HCLPF Values (Including Key Failure Modes) .......................................... 21 7.0    INACCESSIBLE ITEMS ..................................................................................................................... 21 7.1     Identification of ESEL items inaccessible for walkdowns ................................................. 21 7.2     Planned Walkdown / Evaluation Schedule / Close Out .................................................... 22 8.0    ESEP CONCLUSIONS AND RESULTS ............................................................................................... 22 8.1     Supporting Information .................................................................................................... 22

Watts Bar Nuclear Plant ESEP Report Table of Contents (continued)
Page 8.2   Identification of Planned Modifications ........................................................................... 23 8.3   Modification Implementation Schedule ........................................................................... 23 8.4   Summary of Regulatory Commitments ............................................................................ 24

==9.0 REFERENCES==
 .................................................................................................................................. 25

Watts Bar Nuclear Plant ESEP Report List of Tables Page TABLE 41: GMRS FOR WATTS BAR NUCLEAR PLANT .............................................................................. 11 TABLE 42: SSE FOR WATTS BAR NUCLEAR PLANT .................................................................................. 13 TABLE 51: RLGM FOR WATTS BAR NUCLEAR PLANT .............................................................................. 14 TABLE A1: EXPEDITED SEISMIC EQUIPMENT LIST (ESEL) FOR SEQUOYAH NUCLEAR PLANT ................ A2 TABLE B1: ESEP HCLPF VALUES AND FAILURE MODES FOR WATTS BAR NUCLEAR PLANT .................. B2 Page 4

Watts Bar Nuclear Plant ESEP Report List of Figures Page FIGURE 41: GMRS FOR WATTS BAR NUCLEAR PLANT ............................................................................ 12 FIGURE 42: GMRS TO SSE COMPARISON FOR WATTS BAR NUCLEAR PLANT ........................................ 13 FIGURE 51: RLGM FOR WATTS BAR NUCLEAR PLANT ............................................................................ 15 FIGURE 52: NUREG/CR0098 (0.5) VERSUS WATTS BAR NUCLEAR PLANT SSE ...................................... 16 Page 5

Watts Bar Nuclear Plant ESEP Report 1.0     PURPOSE AND OBJECTIVE Following the accident at the Fukushima DaiIchi Nuclear Power Plant (NPP) 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 United States of America (U.S.) NPPs. 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 United States NRC requirements and guidance. Depending on the comparison between the reevaluated seismic hazard and the current design basis, further risk assessment may be required. Risk assessment approaches acceptable to the staff include a Seismic Probabilistic Risk Assessment (SPRA), or a Seismic Margin assessment (SMA). Based upon the risk assessment results, the NRC staff will determine whether additional regulatory actions are necessary.
This Report describes the Expedited Seismic Evaluation Process (ESEP) undertaken for the Watts Bar NPP, Unit 1 and Unit 2 (WBNP). The intent of the ESEP is to perform an interim action in response to the NRCs 50.54(f) letter [1] 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 NTTF 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 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 Watts Bar Nuclear Plant FLEX response strategies for Reactor Core Cooling and Heat Removal, Reactor Inventory Control/Longterm Subcriticality, and Containment Function are summarized below.
This summary is derived from the WBNP Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA12049 [3].
For At Power Conditions Core Cooling and Heat Removal Reactor core cooling and heat removal is achieved via steam release from the Steam Generators (SGs) with SG makeup from the Turbine Driven Auxiliary Feedwater Pump (TDAFWP) during FLEX Phase 1 with suction from the Auxiliary Feedwater Storage Tank. Local control and operation of the SG Atmospheric Relief Valves (ARVs) and the TDAFWP system is available and proceduralized so that operation from the main control room is not required.
To provide an unlimited supply of water for core cooling during Phase 2, portable LP FLEX Pumps will be staged at the Intake Pump Station (IPS) and take suction from the intake channel and discharge to Page 6

Watts Bar Nuclear Plant ESEP Report four emergency raw cooling water (ERCW) FLEX connections inside the IPS. They will be used to pressurize the ERCW headers which can then be used for direct supply to the TDAFWP suction.
When the TDAFWP becomes unavailable due to reduction in available steam pressure, a permanently installed IP FLEX pump will be used to continue to supply feedwater to the SGs. Suction would be from an ERCW FLEX connection on AB elevation (EL) 737 feet (ft). The discharge is routed by hose to the TDAFWP discharge FLEX connections on EL 729 ft in the South MSVV.
For Phase 3, WBNP will continue the Phase 2 coping strategies.
Reactor Inventory control For Phase 1, Reactor Coolant System (RCS) makeup will be provided by the cold leg accumulators. RCS depressurization and cool down will be initiated as soon as possible to reduce the Reactor Coolant Pump (RCP) seal leakage rate.
In Phase 2, RCS makeup will be provided by repowering existing Safety Injection (SI) pumps and using the pumps to inject borated water as needed into the RCS. The SI pumps will be repowered with a 3 MWe FLEX Diesel Generator. The SI pumps can be manually controlled with hand switches on Main Control Room Panel M6. The source of RCS makeup will be the Refueling Water Storage Tank (RWST).
Component Cooling System (CCS) pumps will be repowered using the 3 MWe FLEX diesel generators to provide cooling water to the SI pump oil cooler.
Later in Phase 2, when the RCS is depressurized sufficiently, a permanently installed HP FLEX pump will be used to inject borated water into the RCS through SI piping. These pumps would be aligned with a suction hose from RWST FLEX connections located on AB EL 692 ft and a discharge hose routed to a SIP discharge FLEX header connection on AB EL 692 ft. The HP FLEX Pumps are fed from and operated from the 480v C&A Vent Boards 1A22 and 2B22.
For Phase 3, WBNP will continue the Phase 2 coping strategies.
Containment Function There are no Phase 1 FLEX actions to maintain containment integrity. The primary Phase 2 FLEX strategy for containment integrity entails repowering one train of hydrogen igniters. For Phase 2, a Containment Air Return Fan inside of containment can be repowered.
For Phase 3, WBNP will continue the Phase 2 coping strategies.
Support Systems Key reactor parameters to be monitored during FLEX implementation are measured and indicated by instrumentation that is powered by the 125V DC vital battery. During Phase 1, the vital batteries provide power to needed instrumentation through the vital battery boards, vital inverters and vital instrument power boards.
During Phase 2, power to vital instrumentation will be maintained by supplying 480V AC power to the vital battery chargers through new, fused, FLEX distribution panels, which will be connected directly to the battery chargers. 480V AC power will be supplied to the distribution panels by prestaged, 480V AC FLEX diesel generators located on the roof of the Auxiliary Building.
During the early portions of Phase 2, the 6.9kV switchgear and 6.9kV Shutdown Boards will be energized with a prestaged 3 MWe FLEX diesel generator located in the FLEX building. This will allow reenergizing the SI pumps for inventory control.
Page 7

Watts Bar Nuclear Plant ESEP Report For Phase 3, WBNP will continue the Phase 2 coping strategies.
For Shutdown Conditions Reactor core cooling and heat removal with SGs not available is provided during Phase 1 by heating up and boiling of the RCS coolant inventory.
RCS inventory during Phase 1 may be maintained by gravity feed from the RWST at each unit. The ability of the RWST at each unit to provide a gravity feed to the RCS is limited by the RWST fluid height, line losses through the gravity feed path, and pressure within the RCS.
If it is determined that gravity feed is not effective to cool the RCS and prevent fuel damage, Watts Bar has taken actions to proceduralize administrative controls to prestage FLEX equipment prior to entering a condition where the SGs cannot provide adequate core cooling.
With SGs unavailable the transition to Phase 2 strategies will be required as inventory is lost from the RCS. Prior to loss of gravity feed from the RWST, the permanently installed 480v motor driven Mode 5
& 6 IP FLEX pump must be aligned to take suction from the RWST and deliver the coolant to the RCS via the Safety Injection System FLEX connections. Power supply and control are from the 480v C&A Vent Boards. Sufficient flushing flow will be needed to prevent boron precipitation.
Reactor core cooling with SGs not available is adequately maintained via the Phase 2 strategy.
For Phase 3, WBNP will continue the Phase 2 coping strategies.
WBNP will follow the guidance contained within the Nuclear Energy Institute (NEI) position paper dated September 18, 2013, entitled Position Paper: Shutdown/Refueling Modes (ADAMS No.
ML13273A514) [23].
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 Unit 1 and Unit 2 in presented in Attachments A. Information presented in Attachment A is drawn from [25].
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 Beyond Design Basis External Event (BDBEE), as outlined in the WBNP OIP in Response to the March 12, 2012, Commission Order EA 12049 [3]. The OIP provides the WBNP 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 Watts Bar OIP [3]. FLEX mitigation 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 follows the EPRI guidance outlined in Section 3.2 of EPRI 3002000704.
Page 8

Watts Bar Nuclear Plant ESEP Report
: 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 [2]. 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 Watts Bar OIP [3].
: 2. The scope of components is limited to installed plant equipment and FLEX connections necessary to implement the Watts Bar, 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 train was specified as a primary or backup strategy, then only one train component (generally A train) is included in the ESEL.
3.1.1 ESEL Development The ESEL was developed by reviewing the WBNP OIP [3] to determine the major equipment involved in the FLEX strategies. Further reviews of plant drawings (e.g., Process and Instrumentation Diagrams (P&IDs) and Electrical OneLine 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 flowpath. 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.
3.1.2 PowerOperated 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 Page 9

Watts Bar Nuclear Plant ESEP Report failure modes of electrical and mechanical portions of the installed Phase 1 equipment should be considered (e.g. Auxiliary Feedwater (AFW) trips). To address this concern, the following guidance is applied in the Watts Bar 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 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 add to the ESELs as these components provide completely passive locations for pulling or installing cables. No breaks or connections in the cabling are included in pull boxes. Pull boxes were considered part of conduit and cabling, which are excluded in accordance with EPRI 3002000704 [2].
3.1.4 Termination Cabinets Termination cabinets, including cabinets necessary for FLEX Phase 2 and 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 WBNP 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, 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.
Page 10

Watts Bar Nuclear Plant ESEP Report 3.2     Justification for Use of Equipment that is not the Primary Means for FLEX Implementation The WBNP 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 Safe Shutdown Earthquake (SSE) control point is defined at the reactor building (RB) foundation level at elevation 684 ft and is the deepest structure foundation control point. Table 41 shows the GMRS accelerations for a range of frequencies. The GMRS at the control point elevation is shown in Figure 41 [4].
Table 41 GMRS for Watts Bar Nuclear Plant Frequency (Hz)                GMRS (g) 100                      3.68E01 90                       3.71E01 80                       3.77E01 70                       3.89E01 60                       4.21E01 50                       4.95E01 40                       5.93E01 35                       6.40E01 30                       6.80E01 25                       7.23E01 20                       7.59E01 15                       7.66E01 12.5                      7.58E01 10                       7.26E01 9                       6.90E01 8                       6.55E01 7                       6.12E01 6                       5.60E01 Page 11

Watts Bar Nuclear Plant ESEP Report Table 41 GMRS for Watts Bar Nuclear Plant (Continued)
Frequency (Hz)                    GMRS (g) 5                           4.93E01 4                           3.95E01 3.5                          3.46E01 3                           2.99E01 2.5                          2.50E01 2                           2.28E01 1.5                          1.95E01 1.25                          1.65E01 1                           1.26E01 0.9                          1.13E01 0.8                          1.03E01 0.7                          9.51E02 0.6                          8.71E02 0.5                          7.67E02 0.4                          6.13E02 0.35                          5.37E02 0.3                          4.60E02 0.25                          3.83E02 0.2                          3.07E02 0.15                          2.30E02 0.125                         1.92E02 0.1                          1.53E02 GMRS at Control point for Watts Bar Nuclear Plant, 5%
Damping 8.00E01 7.00E01 6.00E01 Acceleration (g) 5.00E01 4.00E01 3.00E01 2.00E01 1.00E01 0.00E+00 0.1                1                    10                 100 Frequency (Hz)
Figure 41: GMRS for Watts Bar Nuclear Plant Page 12

Watts Bar Nuclear Plant ESEP Report 4.2    Comparison to SSE The SSE was developed in accordance with 10 CFR Part 100 Appendix A through an evaluation of the maximum earthquake potential for the region surrounding the site. The SSE horizontal spectrum at the WBNP site derives from the maximum historic earthquake reported in the site province (the 1897 Giles County event) placed adjacent to the Site. The SSE response spectrum is characterized by a peak ground acceleration (PGA) of 0.18 acceleration of gravity (g) and a shape that conforms to a modified Newmark spectrum [6], which is similar to the Regulatory Guide (RG) 1.60 spectral shape. Figure 42 compares the GMRS to the SSE and illustrates that the GMRS exceeds the SSE in the frequency range above 4.5 Hertz (Hz). The maximum ratio of GMRS to SSE between 1 Hz and 10 Hz occurs at a frequency of 10 Hz and that ratio is approximately 2.0.
Table 42: SSE for Watts Bar Nuclear Plant 0.5                       0.11 1                        0.22 2                        0.46 2.5                       0.46 5                        0.46 6.67                       0.46 10                        0.36 25                        0.22 33                        0.18 100                        0.18 GMRS to SEE Comparison for Watts Bar Nuclear Plant, 5%
Damping 9.00E01 8.00E01 7.00E01 Acceleration (g) 6.00E01 5.00E01 4.00E01                                                              Watts Bar GMRS 3.00E01                                                              WBN SSE (0.18g) 2.00E01 1.00E01 0.00E+00 0.1            1                    10       100 Frequency (Hz)
Figure 42: GMRS to SSE Comparison for Watts Bar Nuclear Plant Page 13

Watts Bar Nuclear Plant ESEP Report 5.0     REVIEW LEVEL GROUND MOTION (RLGM) 5.1     Description of RLGM Selected Section 4 of EPRI 3002000704 [2] presents two approaches for developing the 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 Table 41 and the SSE values in 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) = 0.726g/0.36g = 2.02 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.
Table 51 RLGM for Watts Bar Nuclear Plant 0.5                        0.22 1                         0.44 2                         0.92 2.5                        0.92 5                         0.92 6.67                        0.92 10                         0.72 25                         0.44 33                         0.36 100                         0.36 Page 14

Watts Bar Nuclear Plant ESEP Report RLGM for Watts Bar Nuclear Plant 1.00E+00 9.00E01 8.00E01 7.00E01 Acceleration (g) 6.00E01 5.00E01 Watts Bar GMRS 4.00E01 RLGM= 2x SSE 3.00E01 2.00E01 1.00E01 0.00E+00 0.1            1                    10     100 Frequency (Hz)
Figure 51: RLGM for Watts Bar Nuclear Plant 5.2    Method to Estimate InStructure Response Spectra (ISRS)
EPRI SMA Methodology recommends that median centered response should be used in HCLPF calculations. The ISRS used in the updated IPEEE [12] are based on the NUREG0098 median shape for rock with a PGA of 0.5g. As shown on Figure 52 this shape is similar to the SSE spectrum. This figure also illustrates that the updated IPEEE [12] RLE spectrum with a PGA of 0.5g envelops the RLGM over the entire range of frequencies. Therefore, the median centered ISRS developed in the updated IPEEE
[12] represent the seismic demand on which the HCLPF values reported here are based.
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Watts Bar Nuclear Plant ESEP Report 1.20E+00 1.00E+00 8.00E01 Acceleration (g)
RLE  NUREG/CR0098 (0.5g) 6.00E01 RLGM= 2x SSE 4.00E01 WBN SSE (0.18g) 2.00E01 0.00E+00 0.1        1             10          100 Frequency (Hz)
Figure 52: NUREG/CR0098 (0.5g) versus Watts Bar Nuclear Plant SSE 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:
: 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 [10] .
6.1    Summary of Methodologies Used WBNP performed a SMA for Unit 1 in 1998 [11] and completed an IPEEE Final Report for Unit 2 in 2014
[21]. The SMA consisted of screening walkdowns, functional evaluation, and HCLPF anchorage calculations. The screening walkdowns used the screening tables from Chapter 2 of EPRI NP6041 [8].
The walkdowns were conducted by engineers trained in EPRI NP 6041 (the engineers attended the EPRI SMA AddOn course in addition to the Seismic Qualification Utility Group (SQUG) Walkdown Screening and Seismic Evaluation Training Course), and were documented on Screening Evaluation Work Sheets from EPRI NP6041. Anchorage capacity calculations used the CDFM criteria from EPRI NP6041.
Seismic demand was the IPEEE Review Level Earthquake (RLE) for SMA (median NUREG/CR0098 [6]
ground response spectrum for rock anchored to 0.3g PGA).
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Watts Bar Nuclear Plant ESEP Report After submittal of the IPEEE Reports to the NRC and considering insights into the seismic ruggedness of WBN equipment obtained from the IPEEE reports, WBN performed updated HCLPF capacity evaluations. The updated HCLPF capacity evaluations focused on removing excess conservatism and determining HCLPF capacity in a more accurate manner. The updated HCLPF evaluations document a minimum HCLPF of 0.5g for components on the IPEEE SSEL [12].
Considering insights from the updated HCLPF evaluations, a minimum HCLPF of 0.5 g was selected as the RLE for the SMA in the ESEP. Figure 52 shows the median NUREG/CR0098 (0.5g) ground response spectrum selected as the RLE for the SMA in the ESEP, compared to the required ESEP RLGM response spectrum. The figure shows that the selected ESEP RLE envelops the required ESEP RLGM at all frequencies.
6.2     HCLPF Screening Process The screening capacity in EPRI NP6041 [8] Table 24 based on ground peak spectral accelerations of 1.2g exceeds the RLGM peak spectral acceleration. The anchorage capacity calculations were based on floor response spectra generated for the RLE. Therefore, equipment for which the screening caveats were met and for which the anchorage capacity exceeds the RLE seismic demand associated with the PGA of 0.5g can be screened out from ESEP seismic capacity determination because the HCLPF capacity exceeds the RLGM.
The combined Unit 1 and Unit 2 ESEL includes 452 items. Of these, 87 are valves, both poweroperated and relief. In accordance with Table 24 of EPRI NP6041 [8], active valves may be assigned a functional capacity of 1.2g peak spectral acceleration, and anchorage is not a failure mode if evaluation recommended for motoroperated valves in piping lines of 2 inches diameter or less is performed.
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. Poweroperated valves were addressed in the WBNP Unit 1 and 2 IPEEE SMA. In the SMA, the valves were found to meet EPRI NP6041 Figures F25 and F26 (thus meeting the 1.2g peak spectral acceleration screening criteria) or to exceed the RLE floor response spectra on the basis of vendor seismic qualification reports.
The IPEEE SMA reviews covered 449 valves in Unit 1, and 27 valves described as Unit 0. This review focused on motoroperated valves on small diameter piping and valves at high elevations in the plant.
Relief valves were not included in the IPEEE review except for the poweroperated relief valves, which met the criteria. Springoperated relief valves are considered to meet the EPRI NP6041 1.2g peak spectral acceleration screening criteria without explicit review. On the basis of the above, the ESEL valves may be screened out from ESEP seismic capacity determination.
The nonvalve components in the ESEL are generally screened based on the SMA results. If the SMA showed that the component met the EPRI NP6041 screening caveats and the CDFM capacity exceeded the RLE demand, the component can be screened out from the ESEP capacity determination.
Individual instrumentation items are generically associated with instrument racks and instrument panels. These will be assigned HCLPF values based on similar assemblies evaluated in the IPEEE.
The ESEL includes an instrument loop for parameters monitored during the FLEX implementation. A typical loop consists of a probe or sensor, an indicator and/or transmitter on a local rack, a cabinet in the Auxiliary Instrument Room, an indicator in the Main Control Room, and an indicator in the Aux Control Room. Panels in the Main Control Room, Aux Control Room, and the Aux Instrument Room Page 17

Watts Bar Nuclear Plant ESEP Report have been screened by the updated IPEEE evaluation [12] as discussed above, and all probes or sensors will be boxed/mounted with their respective component.
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 NP6041 [8] for the SMA process. Pages 226 through 230 of EPRI NP6041
[8] 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 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.
Page 18

Watts Bar Nuclear Plant ESEP Report Attachment A was consolidated from the 452 components into a walkdown list containing 210 components. Consolidated from this list are components in the previously credited walkdowns and components that are mounted on or boxed into other components. The details of these walkdown are summarized in ESEP Walkdown Package [19].
6.3.2 Application of Previous Walkdown Information Previous seismic walkdowns were used to support the ESEP seismic evaluations. Some of the components on the ESEL were included in the NTTF 2.3 seismic walkdowns [18]. Those walkdowns were recent enough that they did not need to be repeated for the ESEP.
Several ESEL items were previously walked down during the WBNP Unit 1 and 2 Seismic IPEEE program.
Additionally, previous walkdowns performed as part of the Unit 1 and Unit 2 Integrated Interaction Program (IIP) and Equipment Seismic Qualification (ESQ) Programs as referenced in the WBN Unit 1 and Unit 2 IPEEE reports are also credited. 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.
The construction work on WBN2 is currently ongoing. However, the construction and equipment installation is sufficiently complete so that a seismic margins walkdown of items of equipment that are unique to the WBN2 ESEL could be performed. This walkdown was recently completed as part of the ESEP in accordance with the requirements of the EPRI SMA methodology.
6.3.3 Significant Walkdown Findings Consistent with the guidance from NP6041 [8], no significant outliers or anchorage concerns were identified during the WBNP seismic walkdowns. The following findings were noted during the walkdowns, but are not considered significant.
Several block walls were identified in the proximity of ESEL equipment. These block walls were also identified during the IPEEE walkdown and assessed for their structural adequacy to withstand the seismic loads resulting from the RLE. Per IPEEE, all block walls at Watts Bar exceed the HCLPF limit of the ESEP and are adequate [21].
WBN2DPL2681 - Panel is adjacent to block wall (corresponding Unit 1 panel is not near wall). As stated above, this block wall is adequate.
WBN0XSW2361/AS, WBN0XSW2362/AS, and WBN0XSW2363/AS - Panels are mounted on partition walls. The partition walls are load rated and considered part of building structure, thus the walls are not considered part of the scope for the ESEL.
WBN0PNL360FP/A, and FP/B - Both panels are in contact with, but not tied to, a cable tray support above. These interactions are judged to be credible, but not significant by the SRT.
Page 19

Watts Bar Nuclear Plant ESEP Report WBN2MCC213A1 - Motor Control Center (MCC) has interaction issue with an overhead cable tray support. This MCC was reviewed under the IPEEE evaluation for the plant and all potential interactions were resolved for RLGM [21].
WBN1PNL276L1000 - Two anchor bolts project from the floor about an inch higher than the typical installation. Embedment adequacy for these bolts is addressed and it has been verified that the minimum embedment for the anchors has been met.
The findings and other information developed from the ESEP walkdown are summarized in ESEP Walkdown Package [19]. Based on walkdown results, HCLPF capacity evaluations were recommended for the following twelve (12) components.
Motor Control Centers and Switchgear Transformers Control and Instrumentation Panels Instrument Racks Distribution Panels Engine Generators Horizontal Pumps Air Operated Valves Motor Operated Valves Vertical Tanks and Heat Exchangers Horizontal Tanks and Heat Exchangers Relays 6.4     HCLPF Calculation Process ESEL items not included in the previous updated IPEEE evaluations at WBNP were evaluated using the criteria in EPRI NP6041 [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 NP6041 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 the Summary of HCLPF Calculations for WBNP ESEP [20]. The HCLPF capacities for functionality are based on the comparison of the demand (ISRS) with EPRI 6041 [8] screening level HCLPFs, GERS, or test response spectra. ESEL items not included in the previous updated IPEEE evaluations have HCLPF 0.5g.
Page 20

Watts Bar Nuclear Plant ESEP Report 6.5     Functional Evaluations of Relays ESEP considers cabinets and equipment controls containing relays, contactors, switches, circuit breakers and other electrical and instrumentation components that could be affected by high frequency earthquake motions and that impact operation of equipment in the ESEL.
A focused scope SMA was performed to support the IPEEE for WBNP as summarized in the February 1998 WBNP Unit 1 IPEEE submittal [11] and the November 2014 WBNP Unit 2 IPEEE Final Report [21].
The relay evaluation for a focusedscope plant is limited to a review of low seismic ruggedness relays (bad actor relays). The relay evaluation documented that there are no low seismic ruggedness relays used in applications which qualify them as essential relays.
In 2013, as part of the additional evaluations to document a HCLPF of 0.5g, a relay seismic functionality evaluation was performed for Unit 1 and 2. The purpose of the relay functionality evaluation was to verify that safe shutdown systems modeled in the WBN IPEEE would not be prevented from performing their safe shutdown functions because of relay (contact) chatter during the period of strong motion. The relay evaluation found that relay (contact) chatter during the period of strong motion would not prevent safe shutdown systems in the WBN IPEEE from performing their safe shutdown functions [22].
For the WBNP ESEP Analysis, an evaluation was performed to identify components that are (1) needed for FLEX implementation, (2) not on the IPEEE SSEL, and (3) that have the potential for relay chatter issues. The evaluation identified two sets of components. The first set is System 46 relays associated with the auxiliary feedwater system. A HCLPF was calculated for the relays and in all cases, the HCLFP 0.5g [20]. The second set is the FCV117 and FCV118 steam isolation valves that can isolate the steam supply to the TDAFW pump. In the event of a steam line break, both of these valves can receive a close signal if high temperature is detected in the TDAFW pump room. However, because these valves are motor operated valves (MOV), with a Loss of Offsite Power (LOOP) the valves will not isolate even with a spurious close signal. Therefore, these valves do not present a problem for successful FLEX implementation.
6.6     Tabulated ESEL HCLPF Values (Including Key Failure Modes)
Tabulated ESEL HCLPF values are provided in Attachment B for Unit 1 and Unit 2 items, as well as for items common to both units. The following notes apply to the information in the tables.
For items screened out using NP 6041 [8] screening tables, the screening level is provided as
        >RLGM (0.5g) and the failure mode is listed as Screened, (unless the controlling HCLPF value is governed by anchorage).
For items where anchorage controls the HCLPF value, the HCLPF value is listed in the table and the failure mode is noted as anchorage.
7.0     INACCESSIBLE ITEMS 7.1     Identification of ESEL items inaccessible for walkdowns As concluded by ESEP Walkdown Package [19], no items on the ESEL were judged to require any further walkdowns to satisfy the ESEP evaluation Page 21

Watts Bar Nuclear Plant ESEP Report 7.2     Planned Walkdown / Evaluation Schedule / Close Out Unit 1 Containment was not accessible during the walk by verifications. The ESEL components inside the Unit 1 Containment are the same as those inside the Unit 2 Containment. Detailed closeup inspection of all ESEL components was performed for the components inside Unit 2 Containment. All of these Unit 2 ESEL components inside Unit 2 Containment were found to be well constructed, seismically rugged, and had adequate commodity clearance. The TVA Watts Bar radiation protection and operations groups maintain current photographs of all areas inside Unit 1 Containment. These photographs were made available to the walkdown team. The ESEP walkdown team reviewed the photographs and concluded that the ESEL components inside Unit 1 Containment are the same as those inside Unit 2 Containment. It was also concluded that the components were well constructed, seismically rugged, and had adequate commodity clearance [24]. Based on these observations, as concluded by the ESEP Walkdown Package [19], it is judged that no items on the ESEL require any further walkdowns to satisfy the ESEP evaluation.
8.0     ESEP CONCLUSIONS AND RESULTS 8.1     Supporting Information WBNP has 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 WBNP response to the NRCs 50.54(f) letter [1]. On March 12, 2014, NEI submitted to the NRC results of a study [13] 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.
The NRCs May 9, 2014 NTTF 2.1 Screening and Prioritization letter [15] concluded that the fleetwide 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 WBNP was included in the fleet risk evaluation submitted in the March 12, 2014 NEI letter [13] therefore, the conclusions in the NRCs May 9 letter
[15] also apply to WBNP.
In addition, the March 12, 2014 NEI letter [13] provided an attached Perspectives on the Seismic Capacity of Operating Plants, which (1) assessed a number of qualitative reasons why the design of 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.
Page 22

Watts Bar Nuclear Plant ESEP Report The fleet of currently operating NPPs 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 ISRS calculations Broadening criteria for ISRS Response spectra enveloping criteria typically used in SSCs 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 [1] 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 plantspecific basis, a more detailed seismic risk assessment (SPRA or riskbased SMA) is to be performed in accordance with EPRI 1025287 [16]. As identified in the WBNP Seismic Hazard and GMRS submittal [4], WBNP screens in for a risk evaluation.
The complete risk evaluation will more completely characterize the probabilistic seismic ground motion input into the plant, the plant response to that probabilistic seismic ground motion input, and the resulting plant risk characterization. WBNP will complete that evaluation in accordance with the schedule identified in NEIs letter dated April 9, 2013 [14] and endorsed by the NRC in their May 7, 2013 letter [17].
8.2     Identification of Planned Modifications Based on the HCLPF values assigned according to the methodology described in Section 6.0, no necessary planned modifications are identified.
8.3     Modification Implementation Schedule Per Section 8.2 above, no scheduling of modifications is required.
Page 23

Watts Bar Nuclear Plant ESEP Report 8.4    Summary of Regulatory Commitments There are no additional actions to be performed as a result of the ESEP.
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Watts Bar Nuclear Plant ESEP Report

==9.0 REFERENCES==
: 1. NRC 2012, 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, Nuclear Regulatory Commission, March 2012.
: 2. Electric Power Research Institute (EPRI) 3002000704, Seismic Evaluation Guidance:
Augmented Approach for the Resolution of Fukushima NearTerm Task Force Recommendation 2.1Seismic, May 31, 2013.
: 3. Tennessee Valley Authority (TVA), Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for BeyondDesignBasis External Events (Order Number EA12049) for Watts Bar Nuclear Plant (TAC Nos. MF0950 and MF1177), February 7, 2014.
: 4. TVA, CNL14038, Seismic Hazard and Screening Report(CEUS Sites), Enclosure 4  Seismic Hazard and Screening Report for Watts Bar Nuclear Plant, March 31, 2014.
: 5. EPRI, Watts Bar Seismic Hazard and Screening Report, Electric Power Research Institute, Palo Alto, CA, dated February 7, 2014.
: 6. N.M. Newmark Consulting Engineering Services, NUREG/CR0098, Development of Criteria for Seismic Review of Selected Nuclear Power Plants, 1978.
: 7. Not Used
: 8. EPRI 1991, A Methodology for Assessment of Nuclear Power Plant Seismic Margin, EPRI NP 6041SL, Revision 1, Electric Power Research Institute, Palo Alto, CA, USA, August 1991.
: 9. EPRI, 1991a, Seismic Ruggedness of Relays, EPRI, Palo Alto, California: August 1991, NP7147SL, 1991.
: 10. EPRI 1994, Methodology for Developing Seismic Fragilities, EPRI TR103959, Electric Power Research Institute, June 1994.
: 11. TVA, Watts Bar Nuclear Plant Unit 1 Individual Plant Evaluation of External Events - Final Report,1998.
: 12. TVA Calculation CDQ 000 999 2012 000125, Updated WBN Seismic IPEEE HCLPF Capacity, April 2014.
: 13. NEI 2014, Seismic Core Damage Risk Estimates Using the Updated Seismic Hazards for the Operating Nuclear Plants in the Central and Eastern United States, Nuclear Energy Institute, March 2014.
: 14. NEI 2013, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, Nuclear Energy Institute, April 2013.
: 15. NRC 2014, 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, Nuclear Regulatory Commission, May 2014.
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Watts Bar Nuclear Plant ESEP Report
: 16. EPRI 2013a, Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the resolution of Fukushima NearTerm Task Force Recommendation 2.1: Seismic, EPRI1025287, Electric Power Research Institute, February 2013
: 17. NRC 2013, Electric Power Research Institute Final Draft Report Xxxxxx, 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, Nuclear Regulatory Commission, May 2013.
: 18. NRC ADAMs Number ML12353A251, Enclosure 1  Watts Bar Nuclear Plant, Unit 1 Fukushima NearTerm Task Force Recommendation 2.3: Seismic Response Report, 2012.
: 19. RIZZO, R15  ESEP Walkdown of Watts Bar Nuclear Plant Units 1 & 2, October 21, 2014.
: 20. RIZZO, F31, Summary of HCLPF Calculations for WBNP ESEP Report, October 21, 2014.
21  TVA, 2014, Watts Bar Nuclear Plant Unit 2 (WBN2) Individual Plant Examination of External Events (IPEEE), Revision 0, November 10, 2014.
: 22. Scientech, 2014, WBN2 Enhanced IPEEE Relay Chatter Analysis Report, Revision 0, March 4, 2014.
: 23. NEI 2013, Position Paper: Shutdown/Refueling Modes. Nuclear Energy Institute, September 2013. NRC ADAMS No. ML13273A514.
: 24. RIZZO, R12, Seismic Walkdown of Watts Bar Nuclear Plant Units 1 and 2 Seismic Probabilistic Risk Assessment Project, December 22, 2014.
: 25. TVA, 2014, Whitepaper Watts Bar Nuclear Plant Expedited Seismic Equipment List, December 20, 2014.
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Watts Bar Nuclear Plant ESEP Report ATTACHMENT A  EXPEDITED SEISMIC EQUIPMENT LIST (ESEL) FOR WATTS BAR NUCLEAR PLANT Page A1

Watts Bar Nuclear Plant ESEP Report Table A1: EXPEDITED SEISMIC EQUIPMENT LIST (ESEL) FOR WATTS BAR NUCLEAR PLANT ESEL                                      Equipment State Item     UNID          Description      Normal      Desired                    Notes/Comments
   #                                     State       State Solid State WBN1PNL 1                    Protection    Operational Operational 099R48A System Train A Solid State WBN2PNL 2                    Protection    Operational Operational 099R50B System Train B Reactor WBN2PNL 3                   Protection I   Operational Operational 099R2D Process System Solid State WBN2PNL 4                    Protection    Operational Operational 099R48A System Train A Solid State WBN1PNL 5                    Protection    Operational Operational 099R50B System Train B Reactor WBN2PNL 6                   Protection II  Operational Operational 099R6E Process System WBN1PNL       ICCM System 7                                  Operational Operational ICCM Train A Unit 1 Unit 1 Auxiliary Instrument Room 275R179A       Train A CH 1 Common Q WBN2PNL                                                 Common Q Train A Unit 2 Unit 2 Auxiliary Instrument 8                   PAMS Panel     Operational Operational 275R179A                                                                      Room Train A WBN1PNL       ICCM System 9                                  Operational Operational ICCM Train B Unit 1 Unit 1 Auxiliary Instrument Room 275R180B       Train B CH 2 Common Q WBN2PNL                                                 Common Q Train B unit 2 Unit 2 Auxiliary Instrument 10                   PAMS Panel     Operational Operational 275R180B                                                                      Room Train B Page A2

Watts Bar Nuclear Plant ESEP Report ESEL                                Equipment State Item     UNID      Description    Normal      Desired             Notes/Comments
   #                               State       State WBN2HIC  RX HEAD VENT 11                            Operational Operational 0FSI8; Main Control Room panel M4 068396  FLOW CONTROL Solid State WBN2PNL 12               Protection   Operational Operational 099R46A System Train A Solid State WBN2PNL 13               Protection   Operational Operational 099R49B System Train B Reactor WBN2PNL 14              Protection II Operational Operational 099R6E Process System WBN1 SIS Accumulator 15 ACUM063                  Operational Operational Tank 1 0001 WBN1 SIS Accumulator 16 ACUM063                  Operational Operational Tank 2 0002 WBN1 SIS Accumulator 17 ACUM063                  Operational Operational Tank 3 0003 WBN1 SIS Accumulator 18 ACUM063                  Operational Operational Tank 4 0004 WBN0BAT    125 V Vital 19                            Operational Operational 2360001D     Battery I WBN0BAT    125 V Vital 20                            Operational Operational 2360002E     Battery II WBN0BAT    125 V Vital 21                            Operational Operational 2360003F     Battery III Page A3

Watts Bar Nuclear Plant ESEP Report ESEL                                   Equipment State Item     UNID       Description      Normal      Desired               Notes/Comments
   #                                  State       State WBN0BAT     125 V Vital 22                               Operational Operational 2360004G     Battery IV WBN1BD  6.9 KV Shutdown 23                               Operational Operational  Primary Path OIP Figure A324, 25, and 26 211AA     Board 1AA WBN2BD  6.9 KV Shutdown                           Primary Path OIP Figure A324 and A326.
24                               Operational Operational 211BB     Board 2BB                                      Also, see ESEL Item 200.
WBN1BD  480V Shutdown 25                               Operational Operational 212A001A   Board 1A1A WBN2BD  480V Shutdown 26                               Operational Operational   Component Cooling System Pump 2AA 212A001A   Board 2A1A WBN1BD  480V Shutdown 27                               Operational Operational Primary Path OIP Figure A324, 25, and 26 212A002A   Board 1A2A WBN2BD  480V Shutdown 28                               Operational Operational Containment Air Return Fan 39. ESEL # 146.
212B002B   Board 2B2B WBN0BD      125V Vital 29                               Operational Operational 2360001D  Battery Board I WBN0BD      125V Vital 30                               Operational Operational 2360002E  Battery Board II WBN0BD      125V Vital 31                               Operational Operational 2360003F Battery Board III WBN0BD      125V Vital 32                               Operational Operational 2360004G Battery Board IV WBN0CHGR    125 V Vital 33                               Operational Operational 2360001D Battery Charger I 125 V Vital WBN0CHGR 34              Battery Charger  Operational Operational 2360002/E II Page A4

Watts Bar Nuclear Plant ESEP Report ESEL                                  Equipment State Item     UNID       Description     Normal      Desired             Notes/Comments
   #                                 State       State 125 V Vital WBN0CHGR 35             Battery Charger  Operational Operational 2360003/F III 125 V Vital WBN0CHGR 36             Battery Charger  Operational Operational 2360004/G IV WBN1HTX       CCS HEAT 37                              Operational Operational Flow path to support SIP lube oil cooler 0700185   EXCHANGER A WBN2HTX       CCS HEAT 38                              Operational Operational Flow path to support SIP lube oil cooler 0700185   EXCHANGER B WBN1HTX       RHR HEAT                                   RWST gravity feed path 39                              Operational Operational 0740030A EXCHANGER 1A                             Flow path to support SIP lube oil cooler WBN2HTX       RHR HEAT                                   RWST gravity feed path 40                              Operational Operational 0740031A EXCHANGER 2A                             Flow path to support SIP lube oil cooler WBN1INV   120 V AC Vital 41                              Operational Operational 2350001D     Inverter 1I WBN2INV   120 V AC Vital 42                              Operational Operational 2350001D     Inverter 2I WBN1INV   120 V AC Vital 43                              Operational Operational 2350002E    Inverter 1II WBN2INV   120 V AC Vital 44                              Operational Operational 2350002E    Inverter 2II WBN1INV   120 V AC Vital 45                              Operational Operational 2350003F   Inverter 1III WBN2INV   120 V AC Vital 46                              Operational Operational 2350003F   Inverter 2III WBN1INV   120 V AC Vital 47                              Operational Operational 2350004G   Inverter 1IV Page A5

Watts Bar Nuclear Plant ESEP Report ESEL                                Equipment State Item    UNID       Description    Normal      Desired                   Notes/Comments
   #                               State       State WBN2INV  120 V AC Vital 48                            Operational Operational 2350004G   Inverter 2IV 480V Reactor WBN1MCC                                         FCV6380 and 118 Cold Leg 1 and 3 Accumulator 49            MOV Board 1A1  Operational Operational 213A001A                                                             Isolation A
480V Reactor WBN2MCC                                         FCV6380 and 118 Cold Leg 1 and 3 Accumulator 50            MOV Board 2A1  Operational Operational 213A001A                                                             Isolation A
480V Reactor WBN1MCC                                          FCV6398 and 67 Cold Leg 2 and 4 Accumulator 51            MOV Board 1B1  Operational Operational 213B001B                                                             Isolation B
480V Reactor WBN2MCC                                          FCV6398 and 67 Cold Leg 2 and 4 Accumulator 52            MOV Board 2B1  Operational Operational 213B001B                                                             Isolation B
Cont & Aux Bldg WBN1MCC 53            Vent Board 1A1 Operational Operational                  H2 igniters U1A 214A001A A
Cont & Aux Bldg WBN2MCC 54            Vent Board 2B1 Operational Operational                  H2 igniters U2B 214B001B B
Cont & Aux Bldg WBN1MCC 55            Vent Board 1A2 Operational Operational     2 IP & 1 HP FLEX Pump. OIP Figure A323 214A002A A
Cont & Aux Bldg WBN2MCC 56            Vent Board 2B2 Operational Operational     2 IP & 2 HP FLEX Pump. OIP Figure A323 214B002B B
480 V WBN1OXF 57              Transformer   Operational Operational 212A001A 1A1A Page A6

Watts Bar Nuclear Plant ESEP Report ESEL                                Equipment State Item    UNID       Description    Normal      Desired                    Notes/Comments
   #                               State       State 480 V WBN2OXF 58              Transformer   Operational Operational 212A001A 2A1A 480 V WBN1OXF 59              Transformer   Operational Operational     OIP Figure A324 and 26 , Primary Path 212A002A 1A2A 480 V WBN2OXF 60              Transformer   Operational Operational     OIP Figure A324 and 26 , Primary Path 212B002B 2B2B Centrifugal WBN1PMP                                         Pump oil cooler in flow path to support SIP lube oil 61             Charging Pump  Operational Operational 0620108A                                                                cooler 1AA Centrifugal WBN2PMP                                         Pump 0il cooler in flow path to support SIP lube oil 62             Charging Pump  Operational Operational 0620108A                                                                cooler 2AA SAFETY WBN1PMP 63            INJECTION PUMP  Operational Operational           OIP Figure A325 Primary Path 0630010A 1AA SAFETY WBN2PMP 64            INJECTION PUMP  Operational Operational           OIP Figure A325 Primary Path 0630010A 2AA Component WBN1PMP 65             Cooling System Operational Operational             support SIP lube oil cooler 0700046A Pump 1AA Component WBN2PMP 66             Cooling System Operational Operational             support SIP lube oil cooler 0700059A Pump 2AA WBN1PMP                                             seal water heat exchanger in flow path 67             RHR PUMP 1AA  Operational Operational 0740010A                                                        for SIP lube oil cooler Page A7

Watts Bar Nuclear Plant ESEP Report ESEL                                Equipment State Item    UNID       Description    Normal      Desired               Notes/Comments
   #                               State       State WBN2PMP                                          seal water heat exchanger in flow path 68            RHR PUMP 2BB   Operational Operational 0740020B                                                   for SIP lube oil cooler Steam Generator WBN1PNL 69              Level Control Operational Operational          Auxiliary Control Room 276L011A Panel Steam Generator WBN2PNL 70              Level Control Operational Operational          Auxiliary Control Room 276L011A Panel Steam Generator WBN1PNL 71              Level Control Operational Operational          Auxiliary Control Room 276L011B Panel Steam Generator WBN2PNL 72              Level Control Operational Operational          Auxiliary Control Room 276L011B Panel UNIT CONT.
WBN1PNL                                         Main Control Room Panels M1 through M6 73            BOARD PNL 1M  Operational Operational 278M003 3
UNIT CONT.
WBN2PNL                                         Main Control Room Panels M1 through M6 74            BOARD PNL 2M  Operational Operational 278M003 3
UNIT CONT.
WBN1PNL 75            BOARD PNL 1M  Operational Operational Main Control Room Panels M1 through M6 278M004 4
UNIT CONT.
WBN2PNL 76            BOARD PNL 2M  Operational Operational Main Control Room Panels M1 through M6 278M004 4
WBN1PNL  TEMPERATURE 77                            Operational Operational         Main Control Room Panel 278M010    MONITORING Page A8

Watts Bar Nuclear Plant ESEP Report ESEL                                   Equipment State Item     UNID        Description     Normal      Desired              Notes/Comments
   #                                  State       State WBN2PNL   TEMPERATURE 78                               Operational Operational         Main Control Room Panel 278M010     MONITORING WBN1, 2 7 Day Fuel Oil                         1TANK1838 DG A, 1TANK1841 DG 3B 79   TANK18                     Available   Available Sup Dsl Gen                           2TANK1838 DG 3A, 2TANK1841 DG B 38,41 WBN1TANK  Refueling Water 80                               Operational Operational     Cool without SG & RCS inventory 0630046     Storage Tank WBN2TANK  Refueling Water 81                               Operational Operational     Cool without SG & RCS inventory 0630046     Storage Tank Component WBN1TANK 82               Cooling Water   Operational Operational  Flow path to support SIP lube oil cooler 0700001 Surge Tank Component WBN2TANK 83               Cooling Water   Operational Operational  Flow path to support SIP lube oil cooler 0700001 Surge Tank CVCS SEAL WBN1FCV 84              WATER RETURN     Operational Operational   ECA 0.0 App. A isolate RCP seal return 0620063A HEADER ISOL CVCS SEAL WBN2FCV 85              WATER RETURN     Operational Operational   ECA 0.0 App A isolate RCP seal return 0620063A HEADER ISOL Accumulator WBN1FCV 86               Isolation Valve Operational Operational      480V RMOV Bd ESEL Item # 51 0630067 4
Accumulator WBN2FCV 87               Isolation Valve Operational Operational      480V RMOV Bd ESEL Item # 52 0630067 4
WBN1FCV     Accumulator 88                               Operational Operational      480V RMOV Bd ESEL Item # 49 0630080  Isolation Valve 3 Page A9

Watts Bar Nuclear Plant ESEP Report ESEL                                  Equipment State Item    UNID        Description     Normal      Desired            Notes/Comments
   #                                 State        State WBN2FCV    Accumulator 89                              Operational Operational   480V RMOV Bd ESEL Item # 50 0630080  Isolation Valve 3 WBN1FCV   LWR CNTMT A 90                                Open         Closed           FSI5.05 Appendix A 0670083     CLRS SUP CIV WBN1FCV    Accumulator 91                              Operational Operational   480V RMOV Bd ESEL Item # 51 0630098  Isolation Valve 2 WBN2FCV    Accumulator 92                              Operational Operational   480V RMOV Bd ESEL Item # 52 0630098  Isolation Valve 2 WBN1FCV    Accumulator 93                              Operational Operational   480V RMOV Bd ESEL Item # 49 0630118  Isolation Valve 1 WBN2FCV    Accumulator 94                              Operational Operational   480V RMOV Bd ESEL Item # 50 0630118  Isolation Valve 1 WBN2FCV   LWR CNTMT A 95                                Open         Closed   FSI5.05 App. A: align ERCW header 0670083     CLRS SUP CIV WBN1FCV   LWR CNTMT C 96                                Open         Closed   FSI5.05 App. A: align ERCW header 0670091     CLRS SUP CIV WBN2FCV   LWR CNTMT C 97                                Open         Closed   FSI5.05 App. A: align ERCW header 0670091     CLRS SUP CIV WBN1FCV   LWR CNTMT B 98                                Open         Closed   FSI5.05 App. A: align ERCW header 0670099     CLRS SUP CIV WBN2FCV   LWR CNTMT B 99                                Open         Closed   FSI5.05 App. A: align ERCW header 0670099     CLRS SUP CIV WBN1FCV   LWR CNTMT D 100                                Open         Closed   FSI5.05 App. A: align ERCW header 0670107     CLRS SUP CIV WBN2FCV   LWR CNTMT D 101                                Open         Closed   FSI5.05 App. A: align ERCW header 0670107     CLRS SUP CIV WBN1FCV UPR CNTMT CLR 102                                Open         Closed   FSI5.05 App. A: align ERCW header 0670130       A SUP CIV Page A10

Watts Bar Nuclear Plant ESEP Report ESEL                                Equipment State Item    UNID      Description     Normal      Desired             Notes/Comments
  #                                State        State WBN2FCV UPR CNTMT CLR 103                              Open         Closed    FSI5.05 App. A: align ERCW header 0670130     A SUP CIV WBN1FCV UPR CNTMT CLR 104                              Open         Closed    FSI5.05 App. A: align ERCW header 0670133     C SUP CIV WBN2FCV UPR CNTMT CLR 105                              Open         Closed    FSI5.05 App. A: align ERCW header 0670133     C SUP CIV WBN1FCV UPR CNTMT CLR 106                              Open         Closed    FSI5.05 App. A: align ERCW header 0670138     B SUP CIV WBN2FCV UPR CNTMT CLR 107                              Open         Closed    FSI5.05 App. A: align ERCW header 0670138     B SUP CIV WBN1FCV UPR CNTMT CLR 108                              Open         Closed    FSI5.05 App. A: align ERCW header 0670141     D SUP CIV WBN2FCV UPR CNTMT CLR 109                              Open         Closed    FSI5.05 App. A: align ERCW header 0670141     D SUP CIV WBN2FCV CCS HX DISCH to 110                              Open         Closed    FSI5.05 App. A: align ERCW header 0670143       HDR B WBN1FCV CCS HX DISCH to 111                              Open         Closed    FSI5.05 App. A: align ERCW header 0670143       HDR B WBN0FCV CCS HX C DISCH 112                            Operational Operational            FS15.05 step 16 0670144     to HDR A PRESSURIZER WBN2FCV 113             PORV BLOCK       Open         Open                 0FSI8, Train B 0680332B VALVE PRESSURIZER WBN1FCV 114             PORV BLOCK       Open         Open                 0FSI8, Train A 0680333 VALVE RC Pump Therm WBN1FCV 115              Barrier Ret   Operational Operational ECA 0.0 App. A Isolate thermal barrier 0700090A CNTNMT Isol Page A11

Watts Bar Nuclear Plant ESEP Report ESEL                                  Equipment State Item    UNID       Description      Normal      Desired                 Notes/Comments
  #                                  State       State RC Pump Therm WBN2FCV 116               Barrier Ret    Operational Operational      ECA 0.0 App. A Isolate thermal barrier 0700090A CNTNMT Isol RC Thermal WBN1FCV 117            Barrier Cont Isol Operational Operational      ECA 0.0 App. A Isolate thermal barrier 0700133A Valve RC Thermal WBN2FCV 118            Barrier Cont Isol Operational Operational      ECA 0.0 App. A Isolate thermal barrier 0700133A Valve TD AFW PUMP                               Fails open on loss of AC power or control air.
WBN2LCV 119              SG # 2 Level    Operational Operational       Backup N2 supply bottles available.
0020173B Control                              Manual operation with hand wheel is available.
TD AFW PUMP                               Fails open on loss of AC power or control air.
WBN1LCV 120              SG # 3 Level    Operational Operational       Backup N2 supply bottles available.
0030172A Control                              Manual operation with hand wheel is available.
TD AFW PUMP                               Fails open on loss of AC power or control air.
WBN2LCV 121              SG # 3 Level    Operational Operational       Backup N2 supply bottles available.
0030172A Control                              Manual operation with hand wheel is available.
TD AFW PUMP                               Fails open on loss of AC power or control air.
WBN1LCV 122              SG # 2 Level    Operational Operational       Backup N2 supply bottles available.
0030173B Control                              Manual operation with hand wheel is available.
Page A12

Watts Bar Nuclear Plant ESEP Report ESEL                               Equipment State Item    UNID      Description    Normal      Desired                    Notes/Comments
  #                               State       State TD AFW PUMP                               Fails open on loss of AC power or control air.
WBN1LCV 123              SG # 1 Level Operational Operational         Backup N2 supply bottles available.
0030174B Control                              Manual operation with hand wheel is available.
TD AFW PUMP                               Fails open on loss of AC power or control air.
WBN2LCV 124              SG # 1 Level Operational Operational         Backup N2 supply bottles available.
0030174B Control                              Manual operation with hand wheel is available.
TD AFW PUMP                               Fails open on loss of AC power or control air.
WBN1LCV 125              SG # 4 Level Operational Operational         Backup N2 supply bottles available.
0030175A Control                              Manual operation with hand wheel is available.
TD AFW PUMP                               Fails open on loss of AC power or control air.
WBN2LCV 126              SG # 4 Level Operational Operational         Backup N2 supply bottles available.
0030175A Control                              Manual operation with hand wheel is available.
SG 1Main STM WBN1PCV                                                Backup N2 supply bottles available; 127            HDR PWR Relief Operational Operational 0010005T                                        Manual operation with hand wheel is available 0FSI7.
Control Valve SG 1Main STM WBN2PCV                                                Backup N2 supply bottles available; 128            HDR PWR Relief Operational Operational 0010005T                                        Manual operation with hand wheel is available 0FSI7.
Control Valve SG 2 Main STM WBN1PCV                                                Backup N2 supply bottles available; 129            HDR PWR Relief Operational Operational 0010012T                                        Manual operation with hand wheel is available 0FSI7.
Control Valve Page A13

Watts Bar Nuclear Plant ESEP Report ESEL                                Equipment State Item    UNID       Description    Normal      Desired                     Notes/Comments
  #                                State       State SG 2 Main STM WBN2PCV                                                 Backup N2 supply bottles available; 130             HDR PWR Relief Operational Operational 0010012T                                         Manual operation with hand wheel is available 0FSI7.
Control Valve SG 3 Main STM WBN1PCV                                                 Backup N2 supply bottles available; 131             HDR PWR Relief Operational Operational 0010023T                                         Manual operation with hand wheel is available 0FSI7.
Control Valve SG 3 Main STM WBN2PCV                                                 Backup N2 supply bottles available; 132             HDR PWR Relief Operational Operational 0010023T                                         Manual operation with hand wheel is available 0FSI7.
Control Valve SG 4Main STM WBN1PCV                                                 Backup N2 supply bottles available; 133             HDR PWR Relief Operational Operational 0010030T                                         Manual operation with hand wheel is available 0FSI7.
Control Valve SG 4Main STM WBN2PCV                                                 Backup N2 supply bottles available; 134             HDR PWR Relief Operational Operational 0010030T                                         Manual operation with hand wheel is available 0FSI7.
Control Valve WBN2PCV   PRESSURIZER 135                              Closed    Operational        0FSI8, 125V DC Vital Battery Board II 0680334        PORV WBN1PCV   PRESSURIZER 136                              Closed    Operational        0FSI8, 125V DC Vital Battery Board I 0680340A        PORV Steam Generator WBN1SFV 137             #3 Main Steam    Closed    Operational 0010512 Safety Valve Steam Generator WBN2SFV 138             #3 Main Steam    Closed    Operational 0010512 Safety Valve Steam Generator WBN1SFV 139             #2 Main Steam    Closed    Operational 0010517 Safety Valve Page A14

Watts Bar Nuclear Plant ESEP Report ESEL                                    Equipment State Item     UNID          Description    Normal      Desired              Notes/Comments
  #                                    State       State Steam Generator WBN2SFV 140                #2 Main Steam     Closed    Operational 0010517 Safety Valve Steam Generator WBN1SFV 141                #1 Main Steam     Closed    Operational 0010522 Safety Valve Steam Generator WBN2SFV 142                #1 Main Steam     Closed    Operational 0010522 Safety Valve Steam Generator WBN1SFV 143                #4 Main Steam     Closed    Operational 0010527 Safety Valve Steam Generator WBN2SFV 144                #4 Main Steam     Closed    Operational 0010527 Safety Valve WBN1FAN    Containment Air 145                                Operational Operational        480V SD Bd A1A, ESEL # 25.
0300038     Return Fan AA WBN2FAN    Containment Air 146                                Operational Operational        480V SD Bd B2B, ESEL # 28 0300039     Return Fan BB AC OUTPUT WBN1EI235 147                    AMMETER     Operational Operational 0FSI7. 125V vital battery board voltage 001/A1 INVERTER 1I 120 V AC Vital WBN1BD 148                   Instrument   Operational Operational 2350001D Power Board 1I AC OUTPUT WBN1EI235 149                    AMMETER     Operational Operational 0FSI7. 125V vital battery board voltage 002/A1 INVERTER 1II Page A15

Watts Bar Nuclear Plant ESEP Report ESEL                                   Equipment State Item     UNID         Description    Normal      Desired              Notes/Comments
  #                                   State       State 120 V AC Vital WBN1BD 150                  Instrument   Operational Operational 2350002E Power Board 1II 120 V AC Vital WBN1BD 151                  Instrument   Operational Operational 2350003F Power Board 1III 120 V AC Vital WBN1BD       Instrument 152                               Operational Operational 2350004G  Power Board 1 IV WBN1CLR    CCP 1AA LUBE 153                               Operational Operational Flow path to support SIP lube oil cooler 0620108AA   OIL COOLER WBN1CLR    CCP 1AA GEAR 154                               Operational Operational Flow path to support SIP lube oil cooler 0620108BA   OIL COOLER SAFETY WBN1CLR  INJECTION PUMP 155                               Operational Operational Flow path to support SIP lube oil cooler 0630010    1AA LUBE OIL COOLER CNTMT SPRAY WBN1CLR 156               PUMP 1AA OIL   Operational Operational Flow path to support SIP lube oil cooler 0720027 COOLER RHR PUMP 1AA WBN1HTX      SEAL WATER 157                               Operational Operational Flow path to support SIP lube oil cooler 0740010A         HEAT EXCHANGER WBN1XS   STM GEN #3 TRF 158                               Operational Operational   Auxiliary Control Room panel L11A 0030172AA          SW WBN1XS   STM GEN #4 TRF 159                               Operational Operational   Auxiliary Control Room panel L11A 0030175AA          SW Page A16

Watts Bar Nuclear Plant ESEP Report ESEL                                   Equipment State Item     UNID         Description    Normal      Desired                Notes/Comments
  #                                   State       State WBN1XS   STM GEN #2 TRF 160                               Operational Operational     Auxiliary Control Room panel L11B 0030173AB          SW WBN1XS   STM GEN #1 TRF 161                               Operational Operational     Auxiliary Control Room panel L11B 0030174AB          SW WBN1XI046    TURB AFWP 162                               Operational Operational       Main Control Room panel M3 57          DEMAND AUX FPT FLOW WBN1FIC 163                      IND      Operational Operational       Main Control Room panel M4 0460057AS CONTROLLER TD AFW PMP Trip/Throttle Valve WBN1HS 164                  Handswitch   Operational Operational       Main Control Room panel M4 0460056AS AUTO MAN REMOTE SP FOR FIC4657B WBN1SI046     AFWT AS 165                               Operational Operational       Main Control Room panel M4 0056AS          SPEED WBN1XI046     AFWT AS 166                               Operational Operational       Main Control Room panel M4 0054A      MOP POSITION WBN1XI068 167                Plasma Display Operational Operational   ICCM Train A Unit 1 Main Control Room 0100 WBN1XS    Plasma Display 168                               Operational Operational   ICCM Train A Unit 1 Main Control Room 0680101         Key Pad WBN1HS    RCS PRZR PWR 169                               Operational Operational       Main Control Room panel M5 068340AA     RELIEF VALVE Common Q WBN2CPU       Operator 170                               Operational Operational Common Q Train B unit 2 Main Control Room 0946000     Module Node Box Page A17

Watts Bar Nuclear Plant ESEP Report ESEL                                     Equipment State Item     UNID          Description     Normal      Desired              Notes/Comments
  #                                     State       State WBN2FOC    Common Q first 171                                 Operational Operational Common Q Train B unit 2 Main Control Room 0944001A          modem WBN1HIC    RX HEAD VENT 172                                 Operational Operational      Main Control Room panel M6 068397     FLOW CONTROL WBN2HS      SIS PUMP AA 173                                 Operational Operational      Main Control Room panel M6 0630010A          MOTOR WBN1HS      SIS PUMP AA 174                                 Operational Operational      Main Control Room panel M6 0630010A          MOTOR WBN1HS    AIR RET FAN AA 175                                 Operational Operational       Main Control Room panel M9 0300038A          ON/OFF WBN2HS    AIR RET FAN BB 176                                 Operational Operational       Main Control Room panel M9 0300039B          ON/OFF AC OUTPUT WBN2EI235 177                   AMMETER       Operational Operational     125V Vital Battery Board Voltage 001/A1 INVERTER 2I 120 V AC Vital WBN2BD 178                   Instrument    Operational Operational 2350001D Power Board 2I 120 V AC Vital WBN2BD 179                   Instrument    Operational Operational 2350002E Power Board 2II AC OUTPUT WBN2EI235 180                   AMMETER       Operational Operational     125V Vital Battery Board Voltage 002/A1 INVERTER 2II 120 V AC Vital WBN2BD 181                   Instrument    Operational Operational 2350003F Power Board 2III Page A18

Watts Bar Nuclear Plant ESEP Report ESEL                                    Equipment State Item     UNID          Description    Normal      Desired              Notes/Comments
  #                                    State       State 120 V AC Vital WBN2BD        Instrument 182                                Operational Operational 2350004G   Power Board 2 IV WBN2CLR    CCP 2AA LUBE 183                                Operational Operational Flow path to support SIP lube oil cooler 0620108 AA   OIL COOLER WBN2CLR    CCP 2AA GEAR 184                                Operational Operational Flow path to support SIP lube oil cooler 0620108BA    OIL COOLER SAFETY WBN2CLR INJECTION PUMP 185                                Operational Operational Flow path to support SIP lube oil cooler 0630010     2AA LUBE OIL COOLER CNTMT SPRAY WBN2CLR 186                PUMP 2AA OIL   Operational Operational Flow path to support SIP lube oil cooler 0720027 COOLER RHR PUMP 2AA WBN2HTX      SEAL WATER 187                                Operational Operational Flow path to support SIP lube oil cooler 0740010A          HEAT EXCHANGER WBN2XS    STM GEN #3 TRF 188                                Operational Operational   Auxiliary Control Room panel L11A 0030172AA           SW WBN2XS    STM GEN #4 TRF 189                                Operational Operational   Auxiliary Control Room panel L11A 0030175AA           SW WBN2XS    STM GEN #2 TRF 190                                Operational Operational   Auxiliary Control Room panel L11B 0030173AB           SW WBN2XS    STM GEN #1 TRF 191                                Operational Operational   Auxiliary Control Room panel L11B 0030174AB           SW WBN2XI046    TURB AFWP 192                                Operational Operational     Main Control Room Panel M3 57            DEMAND Page A19

Watts Bar Nuclear Plant ESEP Report ESEL                                   Equipment State Item     UNID         Description    Normal      Desired              Notes/Comments
  #                                   State       State AUX FPT FLOW WBN2FIC 193                      IND      Operational Operational      Main Control Room panel M4 0460057AS CONTROLLER TD AFW PMP Trip/Throttle Valve WBN2HS 194                  Handswitch   Operational Operational      Main Control Room panel M4 0460056AS AUTO MAN REMOTE SP FOR FIC4657B WBN2SI046     AFWT AS 195                               Operational Operational      Main Control Room panel M4 0056AS          SPEED WBN2XI046     AFWT AS 196                               Operational Operational      Main Control Room panel M4 0054A     MOP POSITION WBN2HS    RCS PRZR REL 197                               Operational Operational      Main Control Room panel M5 068333A    FLOW CONTROL WBN2HIC    RX HEAD VENT 198                               Operational Operational      Main Control Room panel M6 068397    FLOW CONTROL WBN2MON     Plasma Touch 199                               Operational Operational Common Q Train B Unit 2 Main Control Room 0680110     Screen Display WBN2BD   6.9kV Shutdown 200                               Operational Operational      Primary Path OIP Figure A325 211AA       Board 2AA WBN2 SIS Accumulator 201  ACUM063                    Operational Operational Tank 1 0001 WBN2 SIS Accumulator 202  ACUM063                    Operational Operational Tank 2 0002 Page A20

Watts Bar Nuclear Plant ESEP Report ESEL                                      Equipment State Item      UNID         Description      Normal      Desired                   Notes/Comments
  #                                      State       State WBN2 SIS Accumulator 203  ACUM063                       Operational Operational Tank 3 0003 WBN2 SIS Accumulator 204  ACUM063                       Operational Operational Tank 4 0004 WBN1HIC     RX HEAD VENT 205                                  Operational Operational                       0FSI8 068396    FLOW CONTROL Reactor WBN1PNL 206                   Protection I   Operational Operational 099R2D Process System Solid State WBN1PNL 207                   Protection     Operational Operational 099R46A System Train A Solid State WBN1PNL 208                   Protection     Operational Operational 099R49B System Train B Reactor WBN1PNL 209                  Protection II   Operational Operational 099R6E Process System WBN1PMP       Containment 210                                  Operational Operational seal water HX in flow path to support SIP oil cooler 0720027A   Spray Pump 1AA MAIN STEAM LOOP 4 WBN2PI001 211                    PRESSURE      Operational Operational                Local Panel 2L381 0027D (typical for each SG)
TD AFW PMP WBN2HS 212               TRIP/THV 2FCV    Operational Operational         junction box 2238 TDAFWP Room 0460056BS 151 POS CNTL Page A21

Watts Bar Nuclear Plant ESEP Report ESEL                                     Equipment State Item      UNID         Description     Normal      Desired              Notes/Comments
  #                                     State       State Pressure Switch to open U2 AOV 2FCV36386 from AFW WBN2PS 213                   Supply Tank   Operational Operational 0020321 upon low pressure in U1 Condensate supply piping.
Solenoid valve to open AFW WBN1, 2FSV 214                   Supply Tank   Operational Operational 0036386 insolation Valve 1,2 FCV36386 WBN1FT63 Safety Injection                                   FT63151 on rack L655 215                                 Operational Operational 151         Pump Flow                                   (refer to M6 for FI63151)
WBN2FT63 Safety Injection                                    FT6320 on rack L472 216                                 Operational Operational 20         Pump Flow                                    (refer to M6 for FI6320)
MAIN STEAM LOOP 4 WBN1PI001                                             Typical for each steam generator.
217                    PRESSURE     Operational Operational 0027D                                               Local Panel L381, ESEL # 247 and 248.
(typical for each SG)
TD AFW PMP WBN1HS 218               TRIP/THV 1FCV   Operational Operational   junction box 2238 TDAFWP Room 0460056BS 151 POS CNTL Fuel Oil XFR WBN0SW Pump 219   3600103C,                     Standby    Operational Disconnect 203C Switch Page A22

Watts Bar Nuclear Plant ESEP Report ESEL                                    Equipment State Item    UNID         Description      Normal      Desired            Notes/Comments
  #                                    State       State 220                                                                     Not used WBN0PMP    Fuel Oil System 221                                 Standby    Operational 360103, 203  Transfer Pump Level Indicating Transmitter for WBN0LIT  the AFW Supply 222                                Operational Operational Yard  AFW Supply Tank Valve Vault 003227        Tank and High/Low Level Alarms Primary Cntrl WBN0FU1 223              Fuse for Fuel Oil  Standby    Operational          0SW3600003A/1 3600103A Pump A Starter Secondary Cntrl WBN0FU1 224              Fuse for Fuel Oil  Standby    Operational          0SW3600003A/1 3600103B Pump A Starter Primary Cntrl WBN0FU1 225              Fuse for Fuel Oil  Standby    Operational          0SW3600003A/1 3600103C Pump A Starter 480 V FLEX Main WBN0FUDS 226              Panel A  Main    Standby    Operational             PNL360FP/A 360FP/AM Disconnect 480 v FLEX Main WBN0FUDS 227              Panel B  Main    Standby    Operational             PNL360FP/B 360FP/BM Disconnect 480v AC Vital WBN0XSW 228              Transfer Switch   Operational Operational 2360004S IV Page A23

Watts Bar Nuclear Plant ESEP Report ESEL                                     Equipment State Item     UNID         Description      Normal      Desired             Notes/Comments
  #                                     State       State 480v AC Vital WBN0XSW 229               Transfer Switch   Operational Operational 2360003S III WBN0XSW      480v AC Vital 230                                 Operational Operational 2360002S  Transfer Switch II WBN0XSW      480v AC Vital 231                                 Operational Operational 2360001S  Transfer Switch I 480 V FLEX DG WBN0GNGC         Neutral 232                                  Standby    Operational 360DG/A, B       Grounding Resistor Box WBN0BKR   480 V FLEX DG 233                                  Standby    Operational 360DG/A, B    Circuit Breaker Hydrogen WBN1HTR 234              Igniters Group A   Operational Operational 1SI2681A lists locations of igniters 268various 34 igniters Hydrogen WBN2HTR 235              Igniters Group B   Operational Operational 2SI2681B lists locations of igniters 268various 34 igniters Conservation WBN0RFV     vent valve for 236                                 Operational Operational 0030005    the AFW Supply Tank.
TD Aux WBN1FCV 237               Feedwater Pmp     Operational Operational 0010052 Governor Valve TD Aux WBN2FCV 238               Feedwater Pmp     Operational Operational 0010052 Governor Valve Page A24

Watts Bar Nuclear Plant ESEP Report ESEL                                     Equipment State Item     UNID         Description      Normal      Desired                    Notes/Comments
  #                                     State       State Pressure WBN0PI003 239               indicator for the Operational Operational         Yard  AFW Supply Tank Valve Vault 1
AFW Supply Tank Pressure Switch to open U1 AOV 1FCV36386 from AFW WBN1PS 240                  Supply Tank    Operational Operational 0020320 upon low pressure in U1 Condensate supply piping.
3MW Diesel                             3A Primary U1, 3B Primary U2 OIP Figure A324 and WBN0BD 241               Generator 6.9KV    Standby    Operational                        26.
3600003A, 3B Switchgear                                  3A Primary U1 and U2 OIP figure A325.
Hydrogen WBN2DXF 242                   Mitigation    Operational Operational             C&A VT BD 2B1B, ESEL # 54 2680002B Transformer Hydrogen WBN1DXF 243                   Mitigation    Operational Operational             C&A VT BD 1A1A, ESEL # 53 2680001A Transformer WBN0DXF   480 V FLEX DG 2 244  360DG/AP,      KVA Sealed      Standby    Operational BP              XFMR 6900V 3MW WBN0XFMR FLEX Diesel GEN 245   3603A/1,                      Standby    Operational 20 KVA Dry Type 3B/1 Transformer Page A25

Watts Bar Nuclear Plant ESEP Report ESEL                                    Equipment State Item     UNID        Description      Normal      Desired   Notes/Comments
  #                                    State       State 6900V 3MW WBN0XFMR FLEX Diesel GEN 246  3603A/2,                      Standby    Operational 5 KVA Dry Type 3B/2 Transformer WBN1PNL   TDAFWP Control 247                                Operational Operational 276L381         Panel WBN2PNL   TDAFWP Control 248                                Operational Operational 276L381         Panel Fuel Oil Transfer WBN0PNL 249                Pump Control     Standby    Operational 360DG/A, B1 Panel 125V Vital Batt WBN0XSW    CHGR I 480 V 250                                 Standby    Operational OIP Figure A322 2360001AS    FLEX Transfer Switch 125V Vital Batt WBN0XSW   CHGR 2 480 V 251                                 Standby    Operational OIP Figure A322 2360002AS    FLEX Transfer Switch 125V Vital Batt WBN0XSW    CHGR 3 480 V 252                                 Standby    Operational OIP Figure A322 2360003AS    FLEX Transfer Switch 125V Vital Batt WBN0XSW    CHGR 4 480 V 253                                 Standby    Operational OIP Figure A322 2360004AS    FLEX Transfer Switch WBN0PNL   480 V FLEX Fuse 254                                 Standby    Operational OIP Figure A322 360FP/A        Panel A Page A26

Watts Bar Nuclear Plant ESEP Report ESEL                                   Equipment State Item     UNID        Description     Normal      Desired                   Notes/Comments
  #                                   State       State WBN0PNL   480 V FLEX Fuse 255                                Standby    Operational                 OIP Figure A322 360FP/B        Panel B AUX FW WBN1PNL 256               TURBINE SPEED   Operational Operational 276L326S CONTROL PANEL AUX FW WBN2PNL 257               TURBINE SPEED   Operational Operational 276L326S CONTROL PANEL 3MW Diesel Generator WBN0RES 258                   Neutral      Standby    Operational 360003A, 3B Grounding Resistor WBN1PNL   AUX FEEDWATER 259                               Operational Operational 276L381A       CONTROL WBN2PNL   AUX FEEDWATER 260                               Operational Operational 276L381A       CONTROL FLEX COMMON WBN0XSW   SPARE HP PUMP 261                                Standby    Operational 360HPCS       TRANSFER SWITCH DG 1AA Transfer                                     Kirkkey, EDG XFSW 1AA WBN1XSW 262              Switch TO 6.9KV Operational Operational        Primary Path OIP Figure A324, 25, 26 82A SD BD 1AA                            Walkdown ID for this UNID is WBN1XSW82A/2A DG 2AA Transfer                                     Kirkkey, EDG XSW 2AA WBN2XSW 263              Switch TO 6.9KV Operational Operational           Primary Path OIP Figure A325 82A SD BD 2AA                            Walkdown ID for this UNID is WBN2XSW82A/2A Page A27

Watts Bar Nuclear Plant ESEP Report ESEL                                    Equipment State Item      UNID        Description     Normal      Desired            Notes/Comments
  #                                    State       State DG 1BB Transfer WBN1XSW 264                SwitchDG CS to Operational Operational               Kirkkey 82B SD BD 1BB DG 2BB Transfer WBN2XSW                                                  Kirkkey, EDG XFSW 2BB 265                SwitchDG CS to Operational Operational 82B                                              Primary Path OIP Figure A325 and 26 SD BD 2BB 480 V FLEX DG WBN0FUDS Pump 266  360DG/AP2,                    Standby    Operational Disconnect BP2 Switch 3MW FLEX Diesel WBN0STR 267                   GEN PMP       Standby    Operational 3600103, 203 Starter 6900V 3MW WBN0SW    FLEX Diesel GEN 268 3600003A/1,         Fused      Standby    Operational 3B/1         Disconnect Switch Reactor Level WBN1TE 269                Cap tube Temp   Operational Operational      Common Q Train B Unit 2 0680380E Comp Reactor Vessel WBN2PNL 270               instrumentation  Operational Operational 276L340 System II Panel Reactor Vessel WBN1PNL 271               instrumentation  Operational Operational 276L388 System I Panel Reactor Level WBN2TE 272                Cap tube Temp   Operational Operational      Common Q Train B Unit 2 0680380E Comp Page A28

Watts Bar Nuclear Plant ESEP Report ESEL                                   Equipment State Item    UNID         Description     Normal      Desired       Notes/Comments
  #                                   State       State WBN0LI3  AFW Supply Tank 273                               Operational Operational 227       Level Indicator WBN1LI63                                            LT6351 on rack L435 274                 RWST Level    Operational Operational 51                                               (refer to M6 for LI6351)
WBN2LI63                                            LT6351 on rack L435 275                 RWST Level    Operational Operational 51                                               (refer to M6 for LI6351)
WBN1LPF3  TDAFW Pump                                FT3142 on rack L656 276                               Operational Operational 142            Flow                               (refer to M4 for FI3142)
WBN2LPF3  TDAFW Pump                                FT3142 on rack L215 277                               Operational Operational 142            Flow                               (refer to M4 for FI3142)
WBN1LPF3                                            FT3147 on rack L341 278              AFW Flow S/G 3   Operational Operational 147B                                               (refer to M3 for FI3147)
WBN2LPF3                                            FT3147 on rack L912 279              AFW Flow S/G 3   Operational Operational 147B                                               (refer to M3 for FI3147)
WBN1LPF3                                            FT3155 on rack L217 280              AFW Flow S/G 2   Operational Operational 155A                                               (refer to M3 for FI3155)
WBN2LPF3                                            FT3155 on rack L193 281              AFW Flow S/G 2   Operational Operational 155A                                               (refer to M3 for FI3155)
WBN1LPF3                                            FT3163 on rack L654 282              AFW Flow S/G 1   Operational Operational 163B                                               (refer to M3 for FI3163)
WBN2LPF3                                            FT3163 on rack L654 283              AFW Flow S/G 1   Operational Operational 163B                                               (refer to M3 for FI3163)
WBN1LPF3                                            FT3170 on rack L216 284              AFW Flow S/G 4   Operational Operational 170A                                               (refer to M3 for FI3170)
WBN2LPF3                                            FT3170 on rack L216 285              AFW Flow S/G 4   Operational Operational 170A                                               (refer to M3 for FI3170)
WBN1LPL3   S/G WR Level                             LT3111 on rack L183 286                               Operational Operational 111           Loop 4                              (refer to M4 for LI3111)
Page A29

Watts Bar Nuclear Plant ESEP Report ESEL                               Equipment State Item    UNID       Description   Normal      Desired        Notes/Comments
  #                               State       State WBN2LPL3 S/G WR Level                           LT3111 on rack L183 287                           Operational Operational 111          Loop 4                            (refer to M4 for LI3111)
WBN1LPL3 S/G NR Level                           LT3148 on rack L182 288                           Operational Operational 148          Loop 3                            (refer to M3 for LI3148)
WBN2LPL3 S/G NR Level                           LT3148 on rack L182 289                           Operational Operational 148          Loop 3                            (refer to M3 for LI3148)
WBN1LPL3 S/G NR Level                           LT3156 on rack L597 290                           Operational Operational 156          Loop 2                            (refer to M3 for LI3148)
WBN2LPL3 S/G NR Level                           LT3156 on rack L597 291                           Operational Operational 156          Loop 2                            (refer to M3 for LI3148)
WBN1LPL3 S/G NR Level                           LT3164 on rack L183 292                           Operational Operational 164          Loop 1                            (refer to M3 for LI3164)
WBN2LPL3 S/G NR Level                           LT3164 on rack L183 293                           Operational Operational 164          Loop 1                            (refer to M3 for LI3164)
WBN1LPL3 S/G NR Level                           LT3171 on rack L183 294                           Operational Operational 171          Loop 4                            (refer to M3 for LI3171)
WBN2LPL3 S/G NR Level                           LT3171 on rack L183 295                           Operational Operational 171          Loop 4                            (refer to M3 for LI3171)
WBN1LPL3 S/G WR Level                            LT343 on rack L183 296                           Operational Operational 43          Loop 1                             (refer to M4 for LI343)
WBN2LPL3 S/G WR Level                            LT343 on rack L183 297                           Operational Operational 43          Loop 1                             (refer to M4 for LI343)
WBN1LPL3 S/G WR Level                            LT356 on rack L182 298                           Operational Operational 56          Loop 1                             (refer to M4 for LI356)
WBN2LPL3 S/G WR Level                            LT356 on rack L182 299                           Operational Operational 56          Loop 2                             (refer to M4 for LI356)
WBN1LPL3 S/G WR Level                            LT398 on rack L182 300                           Operational Operational 98          Loop 3                             (refer to M4 for LI398)
Page A30

Watts Bar Nuclear Plant ESEP Report ESEL                               Equipment State Item    UNID       Description   Normal      Desired                    Notes/Comments
  #                               State       State WBN2LPL3 S/G WR Level                                        LT398 on rack L182 301                           Operational Operational 98         Loop 3                                         (refer to M4 for LI398)
WBN1LPL 302                PZR Level  Operational Operational LT68335 on rack L660(refer to M4 for LI68335) 68335 WBN2LPL                                                    LT68335 on rack L660 303                PZR Level  Operational Operational 68335                                                     (refer to M4 for LI68335)
WBN0LPL                                                      LT7842 on rack L945 304                SFP Level  Operational Operational 7842                                                    (refer to 2M10 for LI7842)
WBN1LPN                                         detector through amplifier and optical isolator 305              Nuclear Flux Operational Operational 92131                                                          to indicator on M13 WBN2LPN                                         detector through amplifier and optical isolator 306              Nuclear Flux Operational Operational 92132                                                          to indicator on M13 WBN1LPP1 S/G Pressure                                        PT120 on rack L194 307                           Operational Operational 20A         Loop 3                                        (refer to M4 for PI120)
WBN2LPP1 S/G Pressure                                        PT120 on rack L194 308                           Operational Operational 20A         Loop 3                                        (refer to M4 for PI120)
WBN1LPP1 S/G Pressure                                        PT127 on rack L700 309                           Operational Operational 27B         Loop 4                                        (refer to M4 for PI127)
WBN2LPP1 S/G Pressure                                        PT127 on rack L196 310                           Operational Operational 27B         Loop 4                                        (refer to M4 for PI127)
WBN1LPP1 S/G Pressure                                         PT12 on rack L196 311                           Operational Operational 2A         Loop 1                                          (refer to M4 for PI12)
WBN2LPP1 S/G Pressure                                         PT12 on rack L196 312                           Operational Operational 2A         Loop 1                                          (refer to M4 for PI12)
WBN1LPP1 S/G Pressure                                         PT19 on rack L697 313                           Operational Operational 9A         Loop 2                                          (refer to M4 for PI19)
WBN2LPP1 S/G Pressure                                         PT19 on rack L194 314                           Operational Operational 9A         Loop 2                                          (refer to M4 for PI19)
Page A31

Watts Bar Nuclear Plant ESEP Report ESEL                                 Equipment State Item    UNID        Description    Normal      Desired         Notes/Comments
  #                                 State       State WBN1LPP                                              PT6868 on rack L384 315             RCS WR Pressure Operational Operational 6868                                             (refer to M6 for PT6868)
WBN2LPP                                              PT6866 on rack L360 316             RCS WR Pressure Operational Operational 6866                                            (refer to M6 for PT6866A)
WBN1LPPD   Containment                              PT30310 on rack L188 317                             Operational Operational 30310        Pressure                             (refer to M9 for PI30310)
WBN2LPPD   Containment                              PT30310 on rack L188 318                             Operational Operational 30310        Pressure                             (refer to M9 for PI30310)
WBN1LPT    Containment                                      PNLR143 319                             Operational Operational 301032     Temperature                            (refer to M6 for TI301032)
WBN2LPT    Containment                                      PNLR143 320                             Operational Operational 301032     Temperature                            (refer to M6 for TI301032)
WBN1LPT    RCS WR Thot                                     PNL099R2 321                             Operational Operational 681         Loop 1                                (refer to M5 for TI681)
WBN2LPT    RCS WR Thot                                     PNL099R2 322                             Operational Operational 681         Loop 1                                (refer to M5 for TI681)
WBN1LPT    RCS WR Tcold                                    PNL099R2 323                             Operational Operational 6818         Loop 1                               (refer to M5 for TI6818)
WBN2LPT    RCS WR Tcold                                    PNL099R2 324                             Operational Operational 6818         Loop 1                               (refer to M5 for TI6818)
WBN1LPT    RCS WR Tcold                                    PNL099R2 325                             Operational Operational 6841         Loop 2                               (refer to M5 for TI6841)
WBN2LPT    RCS WR Tcold                                    PNL099R2 326                             Operational Operational 6841         Loop 2                               (refer to M5 for TI6841)
WBN1LPT    RCS WR Tcold                                    PNL099R6 327                             Operational Operational 6860         Loop 3                               (refer to M5 for TI6860)
WBN2LPT    RCS WR Tcold                                    PNL099R6 328                             Operational Operational 6860         Loop 3                               (refer to M5 for TI6860)
Page A32

Watts Bar Nuclear Plant ESEP Report ESEL                                  Equipment State Item     UNID        Description    Normal      Desired         Notes/Comments
  #                                  State       State WBN1LPT    RCS WR Tcold                                    PNL099R6 329                              Operational Operational 6883          Loop 4                              (refer to M5 for TI6883)
WBN2LPT    RCS WR Tcold                                    PNL099R6 330                              Operational Operational 6883          Loop 4                              (refer to M5 for TI6883)
PORV AND AFW WBN1PNL 331               LCV STM GEN 3  Operational Operational FLEX Nitrogen Control Station 276L1000
                       & 4 PNL PORV AND AFW WBN2PNL 332               LCV STM GEN 3  Operational Operational FLEX Nitrogen Control Station 276L1000
                       & 4 PNL PORV AND AFW WBN1PNL 333               LCV STM GEN 1  Operational Operational FLEX Nitrogen Control Station 276L1001
                       & 2 PNL PORV AND AFW WBN2PNL 334               LCV STM GEN 1  Operational Operational FLEX Nitrogen Control Station 276L1001
                       & 2 PNL Incore WBN1PNL 335               Thermocouple                                ICCM Train A Unit 1 0940008AJ Mon Sys Jbox Incore WBN1PNL 336               Thermocouple                                ICCM Train B Unit 1 0940008BJ Mon Sys Jbox WBN0DPL      480Volt 337 3600003A/1,    Distribution  Standby    Operational 3B/1            Panel WBN0DPL 120/240 VAC 338 3600003A/2,                  Standby    Operational Panel board 3B/2 Page A33

Watts Bar Nuclear Plant ESEP Report ESEL                                    Equipment State Item      UNID        Description     Normal      Desired                    Notes/Comments
  #                                    State       State Hydrogen WBN2DPL      Mitigation 339                                Operational Operational 2680002B    Distribution Panel Hydrogen WBN1DPL      Mitigation 340                                Operational Operational 2680001A    Distribution Panel WBN0FUSD    480 V FLEX DG 341  360DG/AP1,   Pump Fusible     Standby    Operational BP1        Disc Switch WBN0DG   480V FLEX/ESBO DG A Primary to Battery Boards 1 and 3 342    360000A,   225 KVA Diesel   Standby    Operational DG B Primary to Battery Boards 2 and 4; OIP fig A322.
000B        Generator 6900V 3MW WBN0DG                                             3A Primary U1, 3B Primary U2 OIP Figure A324, 26.
343               Diesel Generator  Standby    Operational 3600003A, 3B                                                 3A primary U1 and U2 OIP Figure A325.
TD Aux WBN1PMP 344               Feedwater Pump Operational Operational                 Automatic start on LOOP 0030001AS 1AS TD Aux WBN2PMP 345               Feedwater Pump Operational Operational                 Automatic start on LOOP 0030002AS 2AS WBN0PMP Fuel Oil Transfer 346                                 Standby    Operational 360DG/A1, B1       Pump WBN1PMP 347                HP FLEX Pump     Standby    Operational                   OIP Figure A323.
360HP01 WBN2PMP 348                HP FLEX Pump     Standby    Operational                   OIP Figure A323.
360HP01 Page A34

Watts Bar Nuclear Plant ESEP Report ESEL                                   Equipment State Item    UNID       Description       Normal      Desired                   Notes/Comments
  #                                   State        State WBN1PMP 349            FLEX IP PUMP 01     Standby    Operational              OIP Figure A34, A323.
360IP01 WBN2PMP 350            FLEX IP PUMP 01     Standby    Operational               OIP Figure A34, A323 360IP01 WBN1PMP                                               OIP Figure A311, Mode 5 & 6 RCS Makeup.
351            FLEX IP PUMP 02     Standby    Operational 360IP02                                                              OIP Figure A323 WBN2PMP                                               OIP Figure A311. Mode 5 & 6 RCS Makeup 352            FLEX IP PUMP 02     Standby    Operational 360IP02                                                             OIP Figure A323.
FCV SHARED WBN1FCV     AFW TANK 353                                 Closed       Open 0036386  OUTLET PIPE TO U1 CONDENSATE FCV FOR AFW WBN2FCV    Supply Tank 354                                 Closed       Open 0036386   Outlet Piping to U2 Condensate SFP HEAT WBN0FCV                                               Boundary Valve for Flow path to support SIP 355             EXCHANGER B       Operational Operational 0700194B                                                              lube oil cooler CCS SUPPLY SFP HEAT WBN0FCV                                            Boundary Valve for Flow path to support SIP lube oil 356             EXCHANGER A       Operational Operational 0700197A                                                                  cooler CCS SUPPLY Sta Ser & Cntl Air WBN0FCV                                                           FSI5.05 Appendix A 357            Cmpr Supply Hdr      Open         Closed 0670205                                                            align ERCW header A Isol valve Page A35

Watts Bar Nuclear Plant ESEP Report ESEL                                    Equipment State Item    UNID        Description       Normal      Desired                    Notes/Comments
  #                                    State        State Sta Ser & Cntl Air WBN0FCV                                                            FSI5.05 Appendix A 358             Cmpr Supply Hdr      Open         Closed 0670208                                                              align ERCW header B Isol valve TD Aux WBN1FCV   Feedwater Pmp 359                                Operational Operational  normal power supply: 125V Vital Battery Board III 001051    Trip & Throttle Valve TD Aux WBN2FCV   Feedwater Pmp 360                                Operational Operational  normal power supply: 125V Vital Battery Board I 001051    Trip & Throttle Valve ERCW Header B WBN2FCV                                             switchover to ERCW header. 480V RMOV BD 2B2B 361               TD AFW PMP       Operational Operational 0030179AB                                                               or handwheel SUCT (PS144)
ERCW Header A WBN2FCV                                             switchover to ERCW header. 480V RMOV BD 2A2A 362               TD AFW PMP       Operational Operational 0030136AA                                                               or handwheel SUCT (PS139)
ERCW Header A WBN2FCV                                             switchover to ERCW header. 480V RMOV BD 2A2A 363               TD AFW PMP       Operational Operational 0030136BA                                                               or handwheel SUCT ERCW Header B WBN2FCV                                             switchover to ERCW header. 480V RMOV BD 2B2B 364               TD AFW PMP       Operational Operational 0030179BB                                                               or handwheel SUCT ERCW Header A WBN1FCV                                             switchover to ERCW header. 480V RMOV BD 1A2A 365               TD AFW PMP       Operational Operational 0030136AA                                                               or handwheel SUCT (PS139)
ERCW Header A WBN1FCV                                             switchover to ERCW header. 480V RMOV BD 1A2A 366               TD AFW PMP       Operational Operational 0030136BA                                                               or handwheel SUCT Page A36

Watts Bar Nuclear Plant ESEP Report ESEL                                Equipment State Item    UNID        Description   Normal      Desired                    Notes/Comments
  #                                State       State ERCW Header B WBN1FCV                                         switchover to ERCW header. 480V RMOV BD 1B2B 367               TD AFW PMP   Operational Operational 0030179AB                                                           or handwheel SUCT (PS144)
ERCW Header B WBN1FCV                                         switchover to ERCW header. 480V RMOV BD 1B2B 368               TD AFW PMP   Operational Operational 0030179BB                                                           or handwheel SUCT Admin WBN1FCV    CCS HX C SUP                                        FSI5.05 Appendix A 369                              locked       Open 0670147A   FROM HDR 1A                                           align ERCW header closed Admin WBN1FCV    CCS HX C SUP                                        FSI5.05 Appendix A 370                              locked       Open 0670458A   FROM HDR 1B                                           align ERCW header closed N2 TANK NO. 1 WBN1TANK 371               SUPPLY TO 1 Operational Operational 30402A LCV0030173B N2 TANK NO. 1 WBN1TANK 372              SUP TO 1PCV Operational Operational 0010405A 0010012B N2 TANK NO. 1 WBN2TANK 373              SUP TO 2PCV Operational Operational 0010405A 0010012B N2 TANK NO. 2 WBN1TANK 374              SUP TO 1PCV Operational Operational 0010405B 0010012B N2 TANK NO. 2 WBN2TANK 375              SUP TO 2PCV Operational Operational 0010405B 0010012B N2 TANK NO. 1 WBN1TANK 376              SUP TO 1PCV Operational Operational 0010406A 0010030B Page A37

Watts Bar Nuclear Plant ESEP Report ESEL                                 Equipment State Item    UNID       Description     Normal      Desired   Notes/Comments
  #                                 State       State N2 TANK NO. 1 WBN2TANK 377              SUP TO 2PCV  Operational Operational 0010406A 0010030B N2 TANK NO. 2 WBN1TANK 378              SUP TO 1PCV  Operational Operational 0010406B 0010030B N2 TANK NO. 2 WBN2TANK 379              SUP TO 2PCV  Operational Operational 0010406B 0010030B N2 TANK NO. 1 WBN1TANK 380              SUP TO 1PCV  Operational Operational 0010407A 0010023A N2 TANK NO. 1 WBN2TANK 381             SUP TO 2PCV1 Operational Operational 0010407A 0023A N2 TANK NO. 2 WBN1TANK 382              SUP TO 1PCV  Operational Operational 0010407B 0010023A N2 TANK NO. 2 WBN2TANK 383             SUP TO 2PCV1 Operational Operational 0010407B 0023A N2 TANK NO. 1 WBN1TANK 384              SUP TO 1PCV  Operational Operational 0010408A 0010005A N2 TANK NO. 1 WBN2TANK 385              SUP TO 2PCV  Operational Operational 0010408A 0010005A N2 TANK NO. 2 WBN1TANK 386              SUP TO 1PCV  Operational Operational 0010408B 0010005A Page A38

Watts Bar Nuclear Plant ESEP Report ESEL                                 Equipment State Item    UNID        Description    Normal      Desired   Notes/Comments
  #                                 State       State N2 TANK NO. 1 WBN2TANK 387              SUP TO 2PCV  Operational Operational 0010408B 0010005A N2 TANK NO. 1 WBN2TANK 388               SUPPLY TO 2  Operational Operational 30402A LCV0030173B N2 TANK NO. 2 WBN1TANK 389               SUPPLY TO 1  Operational Operational 30402B LCV0030173B N2 TANK NO. 2 WBN2TANK 390               SUPPLY TO 2  Operational Operational 30402B LCV0030173B N2 TANK NO. 1 WBN1TANK 391               SUPPLY TO 1  Operational Operational 30402C LCV0030174B N2 TANK NO. 1 WBN2TANK 392               SUPPLY TO 2  Operational Operational 30402C LCV0030174B N2 TANK NO. 2 WBN1TANK 393               SUPPLY TO 1  Operational Operational 30402D LCV0030174B N2 TANK NO. 2 WBN2TANK 394               SUPPLY TO 2  Operational Operational 30402D LCV0030174B N2 TANK NO. 1 WBN1TANK 395              SUP TO 1LCV  Operational Operational 30403A 0030172A N2 TANK NO. 1 WBN2TANK 396             SUP TO 2LCV3 Operational Operational 30403A 172A Page A39

Watts Bar Nuclear Plant ESEP Report ESEL                                    Equipment State Item     UNID         Description     Normal      Desired                    Notes/Comments
  #                                    State       State N2 TANK NO. 2 WBN1TANK 397                SUP TO 1LCV   Operational Operational 30403B 003172A N2 TANK NO. 2 WBN2TANK 398              SUP TO 2LCV3   Operational Operational 30403B 172A N2 TANK NO. 1 WBN1TANK 399                SUP TO 1LCV   Operational Operational 30403C 0030175A N2 TANK NO. 1 WBN2TANK 400              SUP TO 2LCV3   Operational Operational 30403C 175A N2 TANK NO. 2 WBN1TANK 401                SUP TO 1LCV   Operational Operational 30403D 0030175A N2 TANK NO. 2 WBN2TANK 402              SUP TO 2LCV3   Operational Operational 30403D 175A WBN0TANK  AFW Supply Tank 403                                Operational Operational 0030226    500,000 gallons 6900V 3MW WBN0TANK 404              FLEX DG Fuel Oil   Standby    Operational 360113, 213 Storage Tank WBN1CLR   TD Aux FW PMP 405                                Operational Operational 0030001B       Oil Cooler WBN2CLR   TD Aux FW PMP 406                                Operational Operational 0030001B       Oil Cooler WBN2RLY     Transfer Sw in 407                                Operational Operational 0460057S   Aux Pos Isol Rly                         T351/TycoPotter & Brumfield Page A40

Watts Bar Nuclear Plant ESEP Report ESEL                                  Equipment State Item     UNID       Description     Normal      Desired                    Notes/Comments
  #                                  State       State B21 Relay AFPT WBN2RLY 408              Trip & Throttle Operational Operational 046B002/1S Vlv Photo Iso                          Struthers Dunn B22 Relay AFPT WBN2RLY 409              Trip & Throttle Operational Operational 046B002/2S Vlv Photo Iso                          Struthers Dunn B23 Relay AFPT WBN2RLY 410               Speed Control  Operational Operational 046B002/3S Instr Pwr                            P297/Potter & Brumfield BA & BB Relay WBN2RLY    AFPT Speed 411                              Operational Operational 046BAS    Control Buffer Relay                              A160/AllenBradley Co.
BA1 Relay AFPT WBN2RLY 412               Speed Control  Operational Operational 046BA1S Buffer                             A160/AllenBradley Co.
BA & BB Relay WBN2RLY    AFPT Speed 413                              Operational Operational 046BBS    Control Buffer Relay                              A160/AllenBradley Co.
WBN2RLY   Aux FW Pump 414                              Operational Operational 046R/AA    Vlv Sep Relay                          W120/Westinghouse Elec Corp.
WBN2RLY   Aux FW Pump 415                              Operational Operational 046R/BB    Vlv Sep Relay                          W120/Westinghouse Elec Corp.
WBN2RLY  AFPT ACC Reset 416                              Operational Operational 046R1S        Relay                              A160/AllenBradley Co.
WBN2RLY  AFPT ACC Reset 417                              Operational Operational 046R2S        Relay                              A160/AllenBradley Co.
Page A41

Watts Bar Nuclear Plant ESEP Report ESEL                                  Equipment State Item    UNID       Description      Normal      Desired                     Notes/Comments
  #                                  State       State AFPT SUP Xfer WBN2RLY FCV115,16 &
418                              Operational Operational 046R4A   51 Sep Relay TR A                                 AllenBradley Co.
Aux Feed Pump WBN2RLY  Trb Stm Supply 419                              Operational Operational 046R5A  Xfer Sep Relay TR A                                 Agastat Turb/Mtr Driven WBN2RLY 420              Aux FW Pump     Operational Operational 046RA1A Vlvs Aux Relay                          W120/Westinghouse Elec Corp.
Turb/Mtr Driven WBN2RLY 421              Aux FW Pump     Operational Operational 046RA2A Vlv SSEP Relay                          W120/Westinghouse Elec Corp.
AFPT Pump 2 WBN2RLY FCV151 Mtr Dr 422                              Operational Operational 046RASS   Vlv 2LCV3156
                      & 164                               W120/Westinghouse Elec Corp.
Turb/Mtr Driven WBN2RLY 423              Aux FW Pump     Operational Operational 046RB1B Vlvs Aux Relay                          W120/Westinghouse Elec Corp.
Turb Driven Aux WBN2RLY 424              FW Pump Vlv     Operational Operational 046RB2B SEP Relay                             W120/Westinghouse Elec Corp.
AFPT Pump 2 WBN2RLY FCV151 Mtr Dr 425                              Operational Operational 046RBSS   Vlv 2LCV3171
                      & 148                               W120/Westinghouse Elec Corp.
Page A42

Watts Bar Nuclear Plant ESEP Report ESEL                                   Equipment State Item     UNID        Description     Normal      Desired                    Notes/Comments
  #                                   State       State AFPT SUP Xfer WBN2RLY 426              FCV115,16 &  Operational Operational 046SSTS 51 Sep Relay                           A160/AllenBradley Co.
WBN1RLY   Transfer Sw in 427                               Operational Operational 0460057S  Aux Pos Isol Rly                         T351/TycoPotter & Brumfield B21 Relay AFPT WBN1RLY 428               Trip & Throttle Operational Operational 046B002/1S Vlv Photo Iso                          Struthers Dunn B22 Relay AFPT WBN1RLY 429               Trip & Throttle Operational Operational 046B002/2S Vlv Photo Iso                          Struthers Dunn B23 Relay AFPT WBN1RLY 430               Speed Control   Operational Operational 046B002/3S Instr Pwr                            P297/Potter & Brumfield BA & BB Relay WBN1RLY     AFPT Speed 431                               Operational Operational 046BAS    Control Buffer Relay                              A160/AllenBradley Co.
BA1 Relay AFPT WBN1RLY 432               Speed Control   Operational Operational 046BA1S Buffer                             A160/AllenBradley Co.
BA & BB Relay WBN1RLY     AFPT Speed 433                               Operational Operational 046BBS    Control Buffer Relay                              A160/AllenBradley Co.
WBN1RLY   Aux FW Pump 434                               Operational Operational 046R/AA     Vlv Sep Relay                          W120/Westinghouse Elec Corp.
WBN1RLY   Aux FW Pump 435                               Operational Operational 046R/BB     Vlv Sep Relay                          W120/Westinghouse Elec Corp.
Page A43

Watts Bar Nuclear Plant ESEP Report ESEL                                  Equipment State Item    UNID       Description      Normal      Desired                     Notes/Comments
  #                                  State       State WBN1RLY  AFPT ACC Reset 436                              Operational Operational 046R1S         Relay                              A160/AllenBradley Co.
WBN1RLY  AFPT ACC Reset 437                              Operational Operational 046R2S         Relay                              A160/AllenBradley Co.
AFPT SUP Xfer WBN1RLY FCV115,16 &
438                              Operational Operational 046R4A   51 Sep Relay TR A                                AllenBradley Co.
Aux Feed Pump WBN1RLY  Trb Stm Supply 439                              Operational Operational 046R5A  Xfer Sep Relay TR A                                Agastat Turb/Mtr Driven WBN1RLY 440              Aux FW Pump     Operational Operational 046RA1A Vlvs Aux Relay                          W120/Westinghouse Elec Corp.
Turb/Mtr Driven WBN1RLY 441              Aux FW Pump     Operational Operational 046RA2A Vlv SSEP Relay                          W120/Westinghouse Elec Corp.
AFPT Pump 2 WBN1RLY FCV151 Mtr Dr 442                              Operational Operational 046RASS   Vlv 2LCV3156
                      & 164                               W120/Westinghouse Elec Corp.
Turb/Mtr Driven WBN1RLY 443              Aux FW Pump     Operational Operational 046RB1B Vlvs Aux Relay                          W120/Westinghouse Elec Corp.
Turb Driven Aux WBN1RLY 444              FW Pump Vlv     Operational Operational 046RB2B SEP Relay                             W120/Westinghouse Elec Corp.
Page A44

Watts Bar Nuclear Plant ESEP Report ESEL                                   Equipment State Item     UNID         Description    Normal      Desired                      Notes/Comments
  #                                   State       State AFPT Pump 2 WBN1RLY  FCV151 Mtr Dr 445                               Operational Operational 046RBSS   Vlv 2LCV3171
                        & 148                              W120/Westinghouse Elec Corp.
AFPT SUP Xfer WBN1RLY 446              FCV115,16 &  Operational Operational 046SSTS 51 Sep Relay                          A160/AllenBradley Co.
TDAFW WBN1STR 447                Trip/Throttle  Operational Operational 0460056AS Motor Starter TDAFW WBN2STR 448                Trip/Throttle  Operational Operational 0460056AS Motor Starter WBN1FSV   Reactor Vessel   Operational Operational 125v DC Vital Battery Bd I 449 0680394     Head Vent Isol 450 WBN1FSV   RV HV Throttle   Operational Operational 125v DC Vital Battery Bd I 0680397     Valve 451 WBN2FSV   RV HV Isolation  Operational Operational 125v DC Vital Battery Bd II 0680395     Valve 452 WBN2FSV   RV HV Throttle   Operational Operational 125v DC Vital Battery Bd II 0680396     Valve Page A45

Watts Bar Nuclear Plant ESEP Report ATTACHMENT B ESEP HCLPF VALUES AND FAILURE MODES TABULATION FOR WATTS BAR NUCLEAR PLANT Page B1

Watts Bar Nuclear Plant ESEP Report Table B1: ESEP HCLPF VALUES AND FAILURE MODES FOR WATTS BAR NUCLEAR PLANT Item                                                  Failure UNID         Description   Notes/Comments                  HCLPF (g)
    #                                                  Mode WBN1         Solid State 1   PNL099   Protection System                  Screened         > 0.5 R48A          Train A WBN2         Solid State 2   PNL099   Protection System                  Screened         > 0.5 R50B           Train B WBN2          Reactor 3   PNL099       Protection I                   Screened         > 0.5 R2D      Process System WBN2         Solid State 4   PNL099   Protection System                  Screened         > 0.5 R48A          Train A WBN1         Solid State 5   PNL099   Protection System                  Screened         > 0.5 R50B           Train B WBN2          Reactor 6   PNL099       Protection II                  Screened         > 0.5 R6E     Process System WBN1 ICCM System 7   PNL275                                      Screened         > 0.5 Train A CH 1 R179A WBN2 Common Q PAMS 8   PNL275                                      Screened         > 0.5 Panel Train A R179A WBN1 ICCM System 9   PNL275                                      Screened         > 0.5 Train B CH 2 R180B WBN2 Common Q PAMS 10   PNL275                                      Screened         > 0.5 Panel Train B R180B WBN2 RX HEAD VENT 11   HIC068                                      Screened         > 0.5 FLOW CONTROL 396 WBN2         Solid State 12   PNL099   Protection System                  Screened         > 0.5 R46A          Train A WBN2         Solid State 13   PNL099   Protection System                  Screened         > 0.5 R49B           Train B Page B2

Watts Bar Nuclear Plant ESEP Report Item                                          Failure UNID      Description  Notes/Comments                HCLPF (g)
   #                                          Mode WBN2       Reactor 14 PNL099   Protection II                Screened         > 0.5 R6E    Process System WBN1 SIS Accumulator 15  ACUM                                  Screened         > 0.5 Tank 1 0630001 WBN1 SIS Accumulator 16  ACUM                                  Screened         > 0.5 Tank 2 0630002 WBN1 SIS Accumulator 17  ACUM                                  Screened         > 0.5 Tank 3 0630003 WBN1 SIS Accumulator 18  ACUM                                  Screened         > 0.5 Tank 4 0630004 WBN0 125 V Vital 19 BAT236                                Screened         > 0.5 Battery I 0001D WBN0 125 V Vital 20 BAT236                                Screened         > 0.5 Battery II 0002E WBN0 125 V Vital 21 BAT236                                Screened         > 0.5 Battery III 0003F WBN0 125 V Vital 22 BAT236                                Screened         > 0.5 Battery IV 0004G WBN1 6.9 KV shutdown 23  BD211                                Screened         > 0.5 Board 1AA AA WBN2 6.9 KV shutdown 24  BD211                                Screened         > 0.5 Board 2BB BB WBN1 480V Shutdown 25  BD212                                Screened         > 0.5 Board 1A1A A001A WBN2 480V Shutdown 26  BD212                                Screened         > 0.5 Board 2A1A A001A WBN1 480V Shutdown 27  BD212                                Screened         > 0.5 Board 1A2A A002A Page B3

Watts Bar Nuclear Plant ESEP Report Item                                              Failure UNID      Description      Notes/Comments                HCLPF (g)
   #                                              Mode WBN2 480V Shutdown 28 BD212                                     Screened         > 0.5 Board 2B2B B002B WBN0 125V Vital Battery 29 BD236                                     Screened         > 0.5 Board I 0001D WBN0 125V Vital Battery 30 BD236                                     Screened         > 0.5 Board II 0002E WBN0 125V Vital Battery 31 BD236                                     Screened         > 0.5 Board III 0003F WBN0 125V Vital Battery 32 BD236                                     Screened         > 0.5 Board IV 0004G WBN0 CHGR       125 V Vital 33                                             Screened         > 0.5 236   Battery Charger I 0001D WBN0 CHGR       125 V Vital 34                                             Screened         > 0.5 236   Battery Charger II 0002/E WBN0 CHGR       125 V Vital 35                                             Screened         > 0.5 236   Battery Charger III 0003/F WBN0 125 V Vital CHGR 36           Battery Charger                   Screened         > 0.5 236 IV 0004/G WBN1 CCS HEAT 37 HTX070                                    Screened         > 0.5 EXCHANGER A 0185 WBN2 CCS HEAT 38 HTX070                                    Screened         > 0.5 EXCHANGER B 0185 WBN1 RHR HEAT 39 HTX074                                    Screened         > 0.5 EXCHANGER 1A 0030A Page B4

Watts Bar Nuclear Plant ESEP Report Item                                            Failure UNID       Description   Notes/Comments                HCLPF (g)
   #                                            Mode WBN2 RHR HEAT 40 HTX074                                  Screened         > 0.5 EXCHANGER 2A 0031A WBN1 120 V AC Vital 41 INV235                                  Screened         > 0.5 Inverter 1I 0001D WBN2 120 V AC Vital 42 INV235                                  Screened         > 0.5 Inverter 2I 0001D WBN1 120 V AC Vital 43 INV235                                  Screened         > 0.5 Inverter 1II 0002E WBN2 120 V AC Vital 44 INV235                                  Screened         > 0.5 Inverter 2II 0002E WBN1 120 V AC Vital 45 INV235                                  Screened         > 0.5 Inverter 1III 0003F WBN2 120 V AC Vital 46 INV235                                  Screened         > 0.5 Inverter 2III 0003F WBN1 120 V AC Vital 47 INV235                                  Screened         > 0.5 Inverter 1IV 0004G WBN2 120 V AC Vital 48 INV235                                  Screened         > 0.5 Inverter 2IV 0004G WBN1 MCC     480V Reactor 49                                           Screened         > 0.5 213   MOV Board 1A1A A001A WBN2 MCC     480V Reactor 50                                           Screened         > 0.5 213   MOV Board 2A1A A001A WBN1 MCC     480V Reactor 51                                           Screened         > 0.5 213   MOV Board 1B1B B001B Page B5

Watts Bar Nuclear Plant ESEP Report Item                                           Failure UNID      Description   Notes/Comments                HCLPF (g)
   #                                           Mode WBN2 MCC     480V Reactor 52                                          Screened         > 0.5 213   MOV Board 2B1B B001B WBN1 Cont & Aux Bldg MCC 53          Vent Board 1A1                 Screened         > 0.5 214 A
A001A WBN2 MCC    Cont & Aux Bldg 54                                          Screened         > 0.5 214   Vent Board 2B1B B001B WBN1 Cont & Aux Bldg MCC 55          Vent Board 1A2                 Screened         > 0.5 214 A
A002A WBN2 MCC    Cont & Aux Bldg 56                                          Screened         > 0.5 214   Vent Board 2B2B B002B WBN1         480 V 57 OXF212 Transformer 1A1                Screened         > 0.5 A001A          A WBN2         480 V 58 OXF212 Transformer 2A1                Screened         > 0.5 A001A          A WBN1         480 V 59 OXF212 Transformer 1A2                Screened         > 0.5 A002A          A WBN2         480 V 60 OXF212 Transformer 2B2                Screened         > 0.5 B002B          B WBN1 Centrifugal PMP 61           Charging Pump                  Screened         > 0.5 062 1AA 0108A WBN2 Centrifugal PMP 62           Charging Pump                  Screened         > 0.5 062 2AA 0108A Page B6

Watts Bar Nuclear Plant ESEP Report Item                                          Failure UNID      Description  Notes/Comments                HCLPF (g)
   #                                          Mode WBN1 SAFETY PMP 63          INJECTION PUMP                 Screened         > 0.5 063 1AA 0010A WBN2 SAFETY PMP 64          INJECTION PUMP                 Screened         > 0.5 063 2AA 0015A WBN1 Component PMP 65           Cooling System                Screened         > 0.5 070 Pump 1AA 0046A WBN2 Component PMP 66           Cooling System                Screened         > 0.5 070 Pump 2AA 0059A WBN1 PMP 67           RHR PUMP 1AA                 Screened         > 0.5 074 0010A WBN2 PMP 68           RHR PUMP 2BB                 Screened         > 0.5 074 0020B WBN1  Steam Generator 69 PNL276   Level Control                Screened         > 0.5 L011A         Panel WBN2  Steam Generator 70 PNL276   Level Control                Screened         > 0.5 L011A         Panel WBN1  Steam Generator 71 PNL276   Level Control                Screened         > 0.5 L011B         Panel WBN2  Steam Generator 72 PNL276   Level Control                Screened         > 0.5 L011B         Panel WBN1 UNIT CONT.
73 PNL278                                Screened         > 0.5 BOARD PNL 1M3 M003 WBN2 UNIT CONT.
74 PNL278                                Screened         > 0.5 BOARD PNL 2M3 M003 Page B7

Watts Bar Nuclear Plant ESEP Report Item                                             Failure UNID       Description    Notes/Comments                HCLPF (g)
   #                                             Mode WBN1 UNIT CONT.
75 PNL278                                   Screened         > 0.5 BOARD PNL 1M4 M004 WBN2 UNIT CONT.
76 PNL278                                   Screened         > 0.5 BOARD PNL 2M4 M004 WBN1 TEMPERATURE 77 PNL278                                   Screened         > 0.5 MONITORING M010 WBN2 TEMPERATURE 78 PNL278                                   Screened         > 0.5 MONITORING M010 WBN1,2 TANK   7 Day Fuel Oil Sup 79                                            Screened         > 0.5 018         Dsl Gen 0038, 41 WBN1 Refueling Water 80  TANK                                     Screened         > 0.5 Storage Tank 0630046 WBN2 Refueling Water 81  TANK                                     Screened         > 0.5 Storage Tank 0630046 WBN1      Component 82  TANK     Cooling Water                   Screened         > 0.5 0700001     Surge Tank WBN2      Component 83  TANK     Cooling Water                   Screened         > 0.5 0700001     Surge Tank WBN1      CVCS SEAL 84 FCV062  WATER RETURN                     Screened         > 0.5 0063A     HEADER ISOL WBN2      CVCS SEAL 85 FCV062  WATER RETURN                     Screened         > 0.5 0063A     HEADER ISOL WBN1 Accumulator 86 FCV063                                   Screened         > 0.5 Isolation Valve 4 0067 WBN2 Accumulator 87 FCV063                                   Screened         > 0.5 Isolation Valve 4 0067 Page B8

Watts Bar Nuclear Plant ESEP Report Item                                            Failure UNID       Description   Notes/Comments                HCLPF (g)
   #                                            Mode WBN1 Accumulator 88 FCV063                                  Screened         > 0.5 Isolation Valve 3 0080 WBN2 Accumulator 89 FCV063                                  Screened         > 0.5 Isolation Valve 3 0080 WBN1 LWR CNTMT A 90 FCV067                                  Screened         > 0.5 CLRS SUP CIV 0083 WBN1 Accumulator 91 FCV063                                  Screened         > 0.5 Isolation Valve 2 0098 WBN2 Accumulator 92 FCV063                                  Screened         > 0.5 Isolation Valve 2 0098 WBN1 Accumulator 93 FCV063                                  Screened         > 0.5 Isolation Valve 1 0118 WBN2 Accumulator 94 FCV063                                  Screened         > 0.5 Isolation Valve 1 0118 WBN2 LWR CNTMT A 95 FCV067                                  Screened         > 0.5 CLRS SUP CIV 0083 WBN1 LWR CNTMT C 96 FCV067                                  Screened         > 0.5 CLRS SUP CIV 0091 WBN2 LWR CNTMT C 97 FCV067                                  Screened         > 0.5 CLRS SUP CIV 0091 WBN1 LWR CNTMT B 98 FCV067                                  Screened         > 0.5 CLRS SUP CIV 0099 WBN2 LWR CNTMT B 99 FCV067                                  Screened         > 0.5 CLRS SUP CIV 0099 WBN1 LWR CNTMT D 100 FCV067                                  Screened         > 0.5 CLRS SUP CIV 0107 WBN2 LWR CNTMT D 101 FCV067                                  Screened         > 0.5 CLRS SUP CIV 0107 Page B9

Watts Bar Nuclear Plant ESEP Report Item                                            Failure UNID      Description    Notes/Comments                HCLPF (g)
  #                                             Mode WBN1 UPR CNTMT CLR 102 FCV067                                  Screened         > 0.5 A SUP CIV 0130 WBN2 UPR CNTMT CLR 103 FCV067                                  Screened         > 0.5 A SUP CIV 0130 WBN1 UPR CNTMT CLR C 104 FCV067                                  Screened         > 0.5 SUP CIV 0133 WBN2 UPR CNTMT CLR C 105 FCV067                                  Screened         > 0.5 SUP CIV 0133 WBN1 UPR CNTMT CLR B 106 FCV067                                  Screened         > 0.5 SUP CIV 0138 WBN2 UPR CNTMT CLR B 107 FCV067                                  Screened         > 0.5 SUP CIV 0138 WBN1 UPR CNTMT CLR 108 FCV067                                  Screened         > 0.5 D SUP CIV 0141 WBN2 UPR CNTMT CLR 109 FCV067                                  Screened         > 0.5 D SUP CIV 0141 WBN2 CCS HX DISCH to 110 FCV067                                  Screened         > 0.5 HDR B 0143 WBN1 CCS HX DISCH to 111 FCV067                                  Screened         > 0.5 HDR B 0143 WBN0 CCS HX C DISCH to 112 FCV067                                  Screened         > 0.5 HDR A 0144 WBN2    PRESSURIZER 113 FCV068   PORV BLOCK                     Screened         > 0.5 0332B        VALVE WBN1    PRESSURIZER 114 FCV068   PORV BLOCK                     Screened         > 0.5 0333         VALVE WBN1   RC Pump Therm 115 FCV070    Barrier Ret                   Screened         > 0.5 0090A    CNTNMT Isol Page B10

Watts Bar Nuclear Plant ESEP Report Item                                             Failure UNID       Description    Notes/Comments                HCLPF (g)
  #                                              Mode WBN2   RC Pump Therm 116 FCV070     Barrier Ret                   Screened         > 0.5 0090A     CNTNMT Isol WBN1      RC Thermal 117 FCV070  Barrier Cont Isol                Screened         > 0.5 0133A         Valve WBN2      RC Thermal 118 FCV070  Barrier Cont Isol                Screened         > 0.5 0133A         Valve WBN2 TD AFW PUMP SG 119 LCV002                                   Screened         > 0.5
               # 2 Level Control 0173B WBN1 TD AFW PUMP SG 120 LCV003                                   Screened         > 0.5
               # 3 Level Control 0172A WBN2 TD AFW PUMP SG 121 LCV003                                   Screened         > 0.5
               # 3 Level Control 0172A WBN1 TD AFW PUMP SG 122 LCV003                                   Screened         > 0.5
               # 2 Level Control 0173B WBN1 TD AFW PUMP SG 123 LCV003                                   Screened         > 0.5
               # 1 Level Control 0174B WBN2 TD AFW PUMP SG 124 LCV003                                   Screened         > 0.5
               # 1 Level Control 0174B WBN1 TD AFW PUMP SG 125 LCV003                                   Screened         > 0.5
               # 4 Level Control 0175A Page B11

Watts Bar Nuclear Plant ESEP Report Item                                             Failure UNID       Description    Notes/Comments                HCLPF (g)
  #                                              Mode WBN2 TD AFW PUMP SG 126 LCV003                                   Screened         > 0.5
               # 4 Level Control 0175A WBN1    SG 1Main STM 127 PCV001  HDR PWR Relief                   Screened         > 0.5 0005T     Control Valve WBN2    SG 1Main STM 128 PCV001  HDR PWR Relief                   Screened         > 0.5 0005T     Control Valve WBN1    SG 2 Main STM 129 PCV001  HDR PWR Relief                   Screened         > 0.5 0012T     Control Valve WBN2    SG 2 Main STM 130 PCV001  HDR PWR Relief                   Screened         > 0.5 0012T     Control Valve WBN1    SG 3 Main STM 131 PCV001  HDR PWR Relief                   Screened         > 0.5 0023T     Control Valve WBN2    SG 3 Main STM 132 PCV001  HDR PWR Relief                   Screened         > 0.5 0023T     Control Valve WBN1    SG 4Main STM 133 PCV001  HDR PWR Relief                   Screened         > 0.5 0030T     Control Valve WBN2    SG 4Main STM 134 PCV001  HDR PWR Relief                   Screened         > 0.5 0030T     Control Valve WBN2 PRESSURIZER 135 PCV068                                   Screened         > 0.5 PORV 0334 WBN1 PRESSURIZER 136 PCV068                                   Screened         > 0.5 PORV 0340A WBN1  Steam Generator 137 SFV001   #3 Main Steam                   Screened         > 0.5 0512      Safety Valve WBN2  Steam Generator 138 SFV001   #3 Main Steam                   Screened         > 0.5 0512      Safety Valve Page B12

Watts Bar Nuclear Plant ESEP Report Item                                            Failure UNID        Description  Notes/Comments                HCLPF (g)
  #                                             Mode WBN1   Steam Generator 139 SFV001   #2 Main Steam                  Screened         > 0.5 0517        Safety Valve WBN2   Steam Generator 140 SFV001   #2 Main Steam                  Screened         > 0.5 0517        Safety Valve WBN1   Steam Generator 141 SFV001   #1 Main Steam                  Screened         > 0.5 0522        Safety Valve WBN2   Steam Generator 142 SFV001   #1 Main Steam                  Screened         > 0.5 0522        Safety Valve WBN1   Steam Generator 143 SFV001   #4 Main Steam                  Screened         > 0.5 0527        Safety Valve WBN2   Steam Generator 144 SFV001   #4 Main Steam                  Screened         > 0.5 0527        Safety Valve WBN1 Containment Air 145 FAN030                                  Screened         > 0.5 Return Fan AA 0038 WBN2 Containment Air 146 FAN030                                  Screened         > 0.5 Return Fan BB 0039 WBN1       AC OUTPUT 147  EI235       AMMETER                    Screened         > 0.5 001/A1      INVERTER 1I WBN1     120 V AC Vital 148  BD235 Instrument Power                 Screened         > 0.5 0001D         Board 1I WBN1       AC OUTPUT 149  EI235       AMMETER                    Screened         > 0.5 002/A1     INVERTER 1II WBN1     120 V AC Vital 150  BD235 Instrument Power                 Screened         > 0.5 0002E        Board 1II WBN1     120 V AC Vital 151  BD235 Instrument Power                 Screened         > 0.5 0003F        Board 1III WBN1     120 V AC Vital 152  BD235 Instrument Power                 Screened         > 0.5 0004G        Board 1IV Page B13

Watts Bar Nuclear Plant ESEP Report Item                                            Failure UNID       Description  Notes/Comments                HCLPF (g)
  #                                             Mode WBN1 CCP 1AA LUBE 153 CLR062                                  Screened         > 0.5 OIL COOLER 0108AA WBN1 CCP 1AA GEAR 154 CLR062                                  Screened         > 0.5 OIL COOLER 0108BA SAFETY WBN1 INJECTION PUMP 155 CLR063                                  Screened         > 0.5 1AA LUBE OIL 0010 COOLER WBN1     CNTMT SPRAY 156 CLR072    PUMP 1AA OIL                 Screened         > 0.5 0027         COOLER WBN1    RHR PUMP 1AA 157 HTX074     SEAL WATER                   Screened         > 0.5 0010A  HEAT EXCHANGER WBN1 STM GEN #3 TRF 158  XS003                                  Screened         > 0.5 SW 0172AA WBN1 STM GEN #4 TRF 159  XS003                                  Screened         > 0.5 SW 0175AA WBN1 STM GEN #2 TRF 160  XS003                                  Screened         > 0.5 SW 0173AB WBN1 STM GEN #1 TRF 161  XS003                                  Screened         > 0.5 SW 0174AB WBN1       TURB AFWP 162                                           Screened         > 0.5 XI04657      DEMAND WBN1 AUX FPT FLOW 163  FIC046                                 Screened         > 0.5 IND CONTROLLER 0057AS TD AFW PMP Trip/Throttle WBN1 Valve Handswitch 164  HS046                                  Screened         > 0.5 AUTO MAN 0056AS REMOTE SP FOR FIC4657B WBN1 AFWT AS 165   SI046                                 Screened         > 0.5 SPEED 0056AS Page B14

Watts Bar Nuclear Plant ESEP Report Item                                           Failure UNID       Description  Notes/Comments                HCLPF (g)
  #                                            Mode WBN1 AFWT AS 166  XI046                                 Screened         > 0.5 MOP POSITION 0054A WBN1 167  XI068   Plasma Display                Screened         > 0.5 0100 WBN1 Plasma Display 168  XS068                                 Screened         > 0.5 Key Pad 0101 WBN1 RCS PRZR PWR 169  HS068                                 Screened         > 0.5 RELIEF VALVE 340AA WBN2      Common Q 170 CPU094 Operator Module                 Screened         > 0.5 6000       Node Box WBN2 Common Q first 171 FOC094                                 Screened         > 0.5 modem 4001A WBN1 RX HEAD VENT 172 HIC068                                 Screened         > 0.5 FLOW CONTROL 397 WBN2 SIS PUMP AA 173  HS063                                 Screened         > 0.5 MOTOR 0010A WBN1 SIS PUMP AA 174  HS063                                 Screened         > 0.5 MOTOR 0010A WBN1 AIR RET FAN AA 175  HS030                                 Screened         > 0.5 ON/OFF 0038A WBN2 AIR RET FAN BB 176  HS030                                 Screened         > 0.5 ON/OFF 0039B WBN2      AC OUTPUT 177  EI235     AMMETER                     Screened         > 0.5 001/A1     INVERTER 2I WBN2    120 V AC Vital 178  BD235 Instrument Power                Screened         > 0.5 0001D       Board 2I WBN2    120 V AC Vital 179  BD235 Instrument Power                Screened         > 0.5 0002E       Board 2II Page B15

Watts Bar Nuclear Plant ESEP Report Item                                              Failure UNID         Description  Notes/Comments                HCLPF (g)
  #                                               Mode WBN2        AC OUTPUT 180   EI235       AMMETER                     Screened         > 0.5 002/A1       INVERTER 2II WBN2       120 V AC Vital 181  BD235  Instrument Power                  Screened         > 0.5 0003F        Board 2III WBN2       120 V AC Vital 182  BD235  Instrument Power                  Screened         > 0.5 0004G         Board 2IV WBN2 CCP 2AA LUBE 183 CLR062                                    Screened         > 0.5 OIL COOLER 0108AA WBN2 CCP 2AA GEAR 184 CLR062                                    Screened         > 0.5 OIL COOLER 0108BA SAFETY WBN2 INJECTION PUMP 185 CLR063                                    Screened         > 0.5 2AA LUBE OIL 0010 COOLER WBN2      CNTMT SPRAY 186 CLR072     PUMP 2AA OIL                  Screened         > 0.5 0027          COOLER WBN2     RHR PUMP 2AA 187 HTX074       SEAL WATER                   Screened         > 0.5 0010A  HEAT EXCHANGER WBN2 STM GEN #3 TRF 188  XS003                                    Screened         > 0.5 SW 0172AA WBN2 STM GEN #4 TRF 189  XS003                                    Screened         > 0.5 SW 0175AA WBN2 STM GEN #2 TRF 190  XS003                                    Screened         > 0.5 SW 0173AB WBN2 STM GEN #1 TRF 191  XS003                                    Screened         > 0.5 SW 0174AB WBN2        TURB AFWP 192                                             Screened         > 0.5 XI04657        DEMAND WBN2 AUX FPT FLOW 193  FIC046                                   Screened         > 0.5 IND CONTROLLER 0057AS Page B16

Watts Bar Nuclear Plant ESEP Report Item                                           Failure UNID       Description  Notes/Comments                HCLPF (g)
  #                                            Mode TD AFW PMP Trip/Throttle WBN2 Valve Handswitch 194  HS046                                 Screened         > 0.5 AUTO MAN 0056AS REMOTE SP FOR FIC4657B WBN2 AFWT AS 195  SI046                                 Screened         > 0.5 SPEED 0056AS WBN2 AFWT AS 196  XI046                                 Screened         > 0.5 MOP POSITION 0054A WBN2 RCS PRZR REL 197  HS068                                 Screened         > 0.5 FLOW CONTROL 333A WBN2 RX HEAD VENT 198 HIC068                                 Screened         > 0.5 FLOW CONTROL 397 WBN2 Plasma Touch 199   MON                                   Screened         > 0.5 Screen Display 0680110 WBN2  6.9 KV shutdown 200                                          Screened         > 0.5 BD211A     Board 2AA WBN2 SIS Accumulator 201  ACUM                                   Screened         > 0.5 Tank 1 0630001 WBN2 SIS Accumulator 202  ACUM                                   Screened         > 0.5 Tank 2 0630002 WBN2 SIS Accumulator 203  ACUM                                   Screened         > 0.5 Tank 3 0630003 WBN2 SIS Accumulator 204  ACUM                                   Screened         > 0.5 Tank 4 0630004 WBN1 RX HEAD VENT 205 HIC068                                 Screened         > 0.5 FLOW CONTROL 396 WBN1        Reactor 206 PNL099     Protection I                Screened         > 0.5 R2D    Process System Page B17

Watts Bar Nuclear Plant ESEP Report Item                                               Failure UNID       Description    Notes/Comments                  HCLPF (g)
  #                                                Mode WBN1       Solid State 207 PNL099 Protection System                   Screened         > 0.5 R46A        Train A WBN1       Solid State 208 PNL099 Protection System                   Screened         > 0.5 R49B         Train B WBN1        Reactor 209 PNL099     Protection II                   Screened         > 0.5 R6E    Process System WBN1 PMP      Containment 210                                              Screened         > 0.5 072  Spray Pump 1AA 0027A MAIN STEAM WBN2        LOOP 4 211  PI001      PRESSURE                      Anchorage          0.56 0027D    (typical for each SG)
WBN2     TD AFW PMP 212 HS046   TRIP/THV 2FCV                  Functionality       0.57 0056BS    151 POS CNTL Pressure Switch to open U2 AOV 2FCV36386 WBN2 from AFW Supply 213  PS002                                   Functionality       0.83 Tank upon 0321 low pressure in U1 Condensate supply piping.
Solenoid valve to WBN1,2 open AFW Supply 214 FSV003   Tank insolation                 Functionality       0.83 6386   Valve 1,2FCV3 6386 WBN1 Safety Injection 215   FT63                                    Anchorage         > 0.5 Pump Flow 151 WBN2   Safety Injection 216                                             Anchorage         > 0.5 FT6320     Pump Flow Page B18

Watts Bar Nuclear Plant ESEP Report Item                                                 Failure UNID      Description    Notes/Comments                     HCLPF (g)
  #                                                   Mode MAIN STEAM WBN1       LOOP 4 217  PI001    PRESSURE                           Anchorage         0.56 0027D   (typical for each SG)
WBN1    TD AFW PMP 218  HS046 TRIP/THV 1FCV                      Functionality      0.57 0056BS   151 POS CNTL WBN0                     HCLPF associated Fuel Oil Transfer SW360                      with Item #404 219          Pmp Disconnect                        Anchorage         0.66 103C,                      Fuel Oil Storage SW 203C                    Tank. Rule of box.
220                                 Not Used WBN0                     HCLPF associated PMP    Fuel Oil System    with Item #404 221                                                Anchorage         0.66 360103,  Transfer Pump      Fuel Oil Storage 203                    Tank. Rule of box.
Level Indicating Transmitter for WBN0 the AFW Supply 222 LIT003                                       Anchorage         0.51 Tank and 227 High/Low Level Alarms HCLPF associated WBN0    Primary Cntrl     with Item #267, 223 FU1360 Fuse for Fuel Oil and conservatively  Anchorage          0.5 0103A    Pump A Starter    assigned as 0.5g.
Rule of box.
HCLPF associated WBN0  Secondary Cntrl     with Item #267, 224 FU1360 Fuse for Fuel Oil and conservatively  Anchorage          0.5 0103B   Pump A Starter    assigned as 0.5g.
Rule of box.
HCLPF associated WBN0    Primary Cntrl     with Item #267, 225 FU1360 Fuse for Fuel Oil and conservatively  Anchorage          0.5 0103C   Pump A Starter    assigned as 0.5g.
Rule of box.
WBN0 480 V FLEX Main FUDS 226          Panel A  Main                      Functionality      0.57 360 Disconnect FP/AM Page B19

Watts Bar Nuclear Plant ESEP Report Item                                                    Failure UNID       Description     Notes/Comments                     HCLPF (g)
  #                                                      Mode WBN0 480 v FLEX Main FUDS 227            Panel B  Main                      Functionality       0.57 360 Disconnect FP/BM WBN0 480v AC Vital 228 XSW236                                        Functionality       0.50 Transfer Switch IV 0004S WBN0 480v AC Vital 229 XSW236                                        Functionality       0.50 Transfer Switch III 0003S WBN0 480v AC Vital 230 XSW236                                        Functionality       0.50 Transfer Switch II 0002S WBN0 480v AC Vital 231 XSW236                                        Functionality       0.50 Transfer Switch I 0001S WBN0     480 V FLEX DG      HCLPF assigned GNGC         Neutral       based on Junction 232                                                 Functionality       0.57 360       Grounding          Box subgroup DG/A, B     Resistor Box      from HCLPF calc WBN0 480 V FLEX DG 233 BKR360                                        Functionality       0.57 Circuit Breaker DG/A, B WBN1   Hydrogen Igniters screened 234 HTR268     Group A  34                                            0.5 (rugged) various        igniters WBN2   Hydrogen Igniters screened 235 HTR268     Group B  34                                            0.5 (rugged) various        igniters WBN0   Conservation vent screened 236 RFV003  valve for the AFW                                          0.5 (Table 2.4) 0005      Supply Tank.
WBN1   TD Aux Feedwater 237 FCV001    Pmp Governor                          screened           0.5 0052          Valve WBN2   TD Aux Feedwater 238 FCV001    Pmp Governor                          screened           0.5 0052          Valve Pressure indicator WBN0                                           screened 239              for the AFW                                             0.5 PI0031                                         (rugged)
Supply Tank Page B20

Watts Bar Nuclear Plant ESEP Report Item                                               Failure UNID       Description    Notes/Comments                  HCLPF (g)
  #                                                 Mode Pressure Switch to open U1 AOV 1FCV36386 WBN1 from AFW Supply                     screened 240  PS002                                                        0.5 Tank upon low                     (rugged) 0320 pressure in U1 Condensate supply piping.
WBN0 3MW Diesel BD360 241          Generator 6.9KV                   Functionality       0.68 0003A, Switchgear 3B WBN2        Hydrogen 242 DXF268      Mitigation                    Anchorage          0.51 0002B      Transformer WBN1        Hydrogen 243 DXF268      Mitigation                    Anchorage          0.51 0001A      Transformer WBN0 DXF360 480 V FLEX DG 2 244                                            Functionality       0.57 DG/AP,  KVA Sealed XFMR BP WBN0 6900V 3MW FLEX XFMR Diesel GEN 20 245   360                                     Functionality       0.58 KVA Dry Type 3A/1, Transformer 3B/1 WBN0 6900V 3MW FLEX XFMR Diesel GEN 5 KVA 246   360                                     Functionality       0.57 Dry Type 3A/2, Transformer 3B/2 WBN1 TDAFWP Control 247 PNL276                                    Anchorage          0.56 Panel L381 WBN2 TDAFWP Control 248 PNL276                                    Anchorage          0.56 Panel L381 WBN0   Fuel Oil Transfer 249 PNL360    Pump Control                   Functionality       0.65 DG/A1           Panel Page B21

Watts Bar Nuclear Plant ESEP Report Item                                            Failure UNID     Description   Notes/Comments                 HCLPF (g)
  #                                              Mode 125V Vital Batt WBN0 CHGR I 480 V 250 XSW236                                 Functionality      0.58 FLEX Transfer 0001AS Switch 125V Vital Batt WBN0 CHGR 2 480 V 251 XSW236                                 Functionality      0.58 FLEX Transfer 0002AS Switch 125V Vital Batt WBN0 CHGR 3 480 V 252 XSW236                                 Functionality      0.58 FLEX Transfer 0003AS Switch 125V Vital Batt WBN0 CHGR 4 480 V 253 XSW236                                 Functionality      0.58 FLEX Transfer 0004AS Switch WBN0 480 V FLEX Fuse 254 PNL360                                 Functionality      0.57 Panel A FP/A WBN0 480 V FLEX Fuse 255 PNL360                                 Functionality      0.57 Panel B FP/B WBN1  AUX FW TURBINE 256 PNL276 SPEED CONTROL                   Functionality      0.85 L326S       PANEL WBN2  AUX FW TURBINE 257 PNL276 SPEED CONTROL                   Functionality      0.85 L326S       PANEL 3MW Diesel WBN0      Generator 258 RES360      Neutral                    Functionality      0.79 003A, 3B     Grounding Resistor WBN1 AUX FEEDWATER 259 PNL276                                 Functionality      0.57 CONTROL L381A WBN2 AUX FEEDWATER 260 PNL276                                 Functionality      0.57 CONTROL L381A Page B22

Watts Bar Nuclear Plant ESEP Report Item                                                 Failure UNID      Description   Notes/Comments                     HCLPF (g)
  #                                                   Mode FLEX COMMON WBN0 SPARE HP PUMP 261 XSW360                                      Functionality      0.57 TRANSFER HPCS SWITCH WBN1  DG 1AA Transfer 262 XSW82   Switch TO 6.9KV                     Functionality      0.57 A       SD BD 1AA WBN2  DG 2AA Transfer 263 XSW82   Switch TO 6.9KV                     Functionality      0.57 A       SD BD 2AA WBN1  DG 1BB Transfer 264 XSW82   Switch DG to SD                     Functionality      0.57 B         BD 1BB WBN2  DG 2BB Transfer 265 XSW82   Switch DG to SD                     Functionality      0.57 B         BD 2BB WBN0 FUDS    480 V FLEX DG 266    360  Pump Disconnect                      Functionality      0.57 DG/AP2,        Switch BP2 WBN0 STR360 3MW FLEX Diesel 267                                                Anchorage         0.54 0103, GEN PMP Starter 203 WBN0 6900V 3MW FLEX SW360 268          Diesel GEN Fused                      Anchorage          0.5 0003A/1, Disconnect Switch 3B/1 WBN1 Reactor Level Cap 269  TE068                                       Anchorage        > 0.5 tube Temp Comp 0380E HCLPF assigned based on WBN2    Reactor Vessel Instruments 270 PNL276  instrumentation                      Anchorage         0.52 mounted on L340    System II Panel unitstrut subgroup from HCLPF calc Page B23

Watts Bar Nuclear Plant ESEP Report Item                                                Failure UNID       Description   Notes/Comments                    HCLPF (g)
  #                                                  Mode HCLPF assigned based on WBN1    Reactor Vessel Instruments 271 PNL276  instrumentation                     Anchorage         0.52 mounted on L388    System I Panel unitstrut subgroup from HCLPF calc WBN2 Reactor Level Cap 272  TE068                                      Anchorage        > 0.5 tube Temp Comp 0380E WBN0  AFW Supply Tank                                       > 0.5 273                                               Anchorage LI3227   Level Indicator WBN1                                                        > 0.5 274              RWST Level                       Anchorage LI6351 WBN2                                                        > 0.5 275              RWST Level                       Anchorage LI6351 WBN1                                                        > 0.5 TDAFW Pump 276   LPF3                                      Anchorage Flow 142 WBN2                                                        > 0.5 TDAFW Pump 277   LPF3                                      Anchorage Flow 142 WBN1                                                        > 0.5 278   LPF3 AFW Flow S/G 3                       Anchorage 147B WBN2                                                        > 0.5 279   LPF3 AFW Flow S/G 3                       Anchorage 147B WBN1                                                        > 0.5 280   LPF3 AFW Flow S/G 2                       Anchorage 155A WBN2                                                        > 0.5 281   LPF3 AFW Flow S/G 2                       Anchorage 155A WBN1                                                        > 0.5 282   LPF3 AFW Flow S/G 1                       Anchorage 163B WBN2                                                        > 0.5 283   LPF3 AFW Flow S/G 1                       Anchorage 163B WBN1                                                        > 0.5 284   LPF3 AFW Flow S/G 4                       Anchorage 170A Page B24

Watts Bar Nuclear Plant ESEP Report Item                                             Failure UNID      Description    Notes/Comments                HCLPF (g)
  #                                               Mode WBN2                                                     > 0.5 285    LPF3  AFW Flow S/G 4                  Anchorage 170A WBN1     S/G WR Level                                    > 0.5 286                                            Anchorage LPL3111      Loop 4 WBN2     S/G WR Level                                    > 0.5 287                                            Anchorage LPL3111      Loop 4 WBN1   S/G NR Level Loop                                 > 0.5 288                                            Anchorage LPL3148         3 WBN2   S/G NR Level Loop                                 > 0.5 289                                            Anchorage LPL3148         3 WBN1   S/G NR Level Loop                                 > 0.5 290                                            Anchorage LPL3156         2 WBN2   S/G NR Level Loop                                 > 0.5 291                                            Anchorage LPL3156         2 WBN1   S/G NR Level Loop                                 > 0.5 292                                            Anchorage LPL3164         1 WBN2   S/G NR Level Loop                                 > 0.5 293                                            Anchorage LPL3164         1 WBN1   S/G NR Level Loop                                 > 0.5 294                                            Anchorage LPL3171         4 WBN2   S/G NR Level Loop                                 > 0.5 295                                            Anchorage LPL3171         4 WBN1     S/G WR Level                                    > 0.5 296                                            Anchorage LPL343      Loop 1 WBN2     S/G WR Level                                    > 0.5 297                                            Anchorage LPL343      Loop 1 WBN1     S/G WR Level                                    > 0.5 298                                            Anchorage LPL356      Loop 1 WBN2     S/G WR Level                                    > 0.5 299                                            Anchorage LPL356      Loop 2 WBN1     S/G WR Level                                    > 0.5 300                                            Anchorage LPL398      Loop 3 WBN2     S/G WR Level                                    > 0.5 301                                            Anchorage LPL398      Loop 3 WBN1                                                     > 0.5 302   LPL68     PZR Level                    Anchorage 335 WBN2                                                     > 0.5 303   LPL68     PZR Level                    Anchorage 335 Page B25

Watts Bar Nuclear Plant ESEP Report Item                                             Failure UNID       Description   Notes/Comments                HCLPF (g)
  #                                               Mode WBN0                                                     > 0.5 304                SFP Level                   Anchorage LPL7842 WBN1                                                     > 0.5 305  LPN92     Nuclear Flux                  Anchorage 131 WBN2                                                     > 0.5 306  LPN92     Nuclear Flux                  Anchorage 132 WBN1                                                     > 0.5 S/G Pressure Loop 307   LPP1                                   Anchorage 3
20A WBN2                                                     > 0.5 S/G Pressure Loop 308   LPP1                                   Anchorage 3
20A WBN1                                                     > 0.5 S/G Pressure Loop 309   LPP1                                   Anchorage 4
27B WBN2                                                     > 0.5 S/G Pressure Loop 310   LPP1                                   Anchorage 4
27B WBN1   S/G Pressure Loop                                 > 0.5 311                                            Anchorage LPP12A           1 WBN2   S/G Pressure Loop                                 > 0.5 312                                            Anchorage LPP12A           1 WBN1   S/G Pressure Loop                                 > 0.5 313                                            Anchorage LPP19A           2 WBN2   S/G Pressure Loop                                 > 0.5 314                                            Anchorage LPP19A           2 WBN1                                                     > 0.5 315  LPP68   RCS WR Pressure                 Anchorage 68 WBN2                                                     > 0.5 316  LPP68   RCS WR Pressure                 Anchorage 66 WBN1                                                     > 0.5 Containment 317 LPPD30                                   Anchorage Pressure 310 WBN2                                                     > 0.5 Containment 318 LPPD30                                   Anchorage Pressure 310 Page B26

Watts Bar Nuclear Plant ESEP Report Item                                            Failure UNID      Description    Notes/Comments                HCLPF (g)
  #                                              Mode WBN1                                                    > 0.5 Containment 319  LPT30                                  Anchorage Temperature 1032 WBN2                                                    > 0.5 Containment 320  LPT30                                  Anchorage Temperature 1032 WBN1  RCS WR Thot Loop                                  > 0.5 321                                           Anchorage LPT681        1 WBN2  RCS WR Thot Loop                                  > 0.5 322                                           Anchorage LPT681        1 WBN1                                                    > 0.5 RCS WR Tcold Loop 323  LPT68                                  Anchorage 1
18 WBN2                                                    > 0.5 RCS WR Tcold Loop 324  LPT68                                  Anchorage 1
18 WBN1                                                    > 0.5 RCS WR Tcold Loop 325  LPT68                                  Anchorage 2
41 WBN2                                                    > 0.5 RCS WR Tcold Loop 326  LPT68                                  Anchorage 2
41 WBN1                                                    > 0.5 RCS WR Tcold Loop 327  LPT68                                  Anchorage 3
60 WBN2                                                    > 0.5 RCS WR Tcold Loop 328  LPT68                                  Anchorage 3
60 WBN1                                                    > 0.5 RCS WR Tcold Loop 329  LPT68                                  Anchorage 4
83 WBN2                                                    > 0.5 RCS WR Tcold Loop 330  LPT68                                  Anchorage 4
83 WBN1   PORV AND AFW 331 PNL276 LCV STM GEN 3 &                  Anchorage         0.52 L1000       4 PNL WBN2   PORV AND AFW 332 PNL276 LCV STM GEN 3 &                  Anchorage         0.52 L1000       4 PNL Page B27

Watts Bar Nuclear Plant ESEP Report Item                                              Failure UNID       Description    Notes/Comments                 HCLPF (g)
  #                                                Mode WBN1  PORV AND AFW 333 PNL276 LCV STM GEN 1 &                    Anchorage         0.52 L1001         2 PNL WBN2  PORV AND AFW 334 PNL276 LCV STM GEN 1 &                    Anchorage         0.52 L1001         2 PNL WBN1        Incore 335 PNL094   Thermocouple                     Anchorage         0.52 0008AJ    Mon Sys Jbox WBN1        Incore 336 PNL094   Thermocouple                     Anchorage         0.52 0008BJ    Mon Sys Jbox WBN0 DPL360      480Volt 337                                            Functionality      0.68 0003A/1, Distribution Panel 3B/1 WBN0 DPL360    120/240 VAC 338                                            Functionality      0.68 0003A/2,     Panelboard 3B/2 WBN2       Hydrogen 339 DPL268     Mitigation                    Functionality      0.57 0002B  Distribution Panel WBN1       Hydrogen 340 DPL268     Mitigation                    Functionality      0.57 0001A  Distribution Panel WBN0 FUSD    480 V FLEX DG 341    360    Pump Fusible                    Functionality      0.57 DG/AP1,      Disc Switch BP1 WBN0 480V FLEX/ESBO DG360 342            225 KVA Diesel                  Functionality      0.57 000A, Generator 000B WBN0 DG360     6900V 3MW 343                                             Anchorage         0.87 0003A,  Diesel Generator 3B Page B28

Watts Bar Nuclear Plant ESEP Report Item                                              Failure UNID       Description    Notes/Comments                 HCLPF (g)
  #                                                Mode WBN1 PMP   TD Aux Feedwater 344                                             Anchorage         0.59 003      Pump 1AS 0001AS WBN2 PMP   TD Aux Feedwater 345                                             Anchorage         0.59 003      Pump 2AS 0002AS WBN0 PMP Fuel Oil Transfer 346    360                                    Functionality      0.57 Pump DG/A1, B1 WBN1 347   PMP     HP FLEX Pump                    Functionality       0.5 360HP01 WBN2 348   PMP     HP FLEX Pump                    Functionality       0.5 360HP01 WBN1 349   PMP    FLEX IP PUMP 01                  Functionality       0.5 360IP01 WBN2 350   PMP    FLEX IP PUMP 01                  Functionality       0.5 360IP01 WBN1 351   PMP    FLEX IP PUMP 02                  Functionality       0.5 360IP02 WBN2 352   PMP    FLEX IP PUMP 02                  Functionality       0.5 360IP02 FCV SHARED AFW WBN1 TANK OUTLET 353 FCV003                                   Functionality      0.83 PIPE TO U1 6386 CONDENSATE FCV FOR AFW WBN2 Supply Tank 354 FCV003                                   Functionality      0.83 Outlet Piping to 6386 U2 Condensate WBN0       SFP HEAT 355 FCV070   EXCHANGER B                     Functionality      0.69 0194B      CCS SUPPLY Page B29

Watts Bar Nuclear Plant ESEP Report Item                                               Failure UNID        Description    Notes/Comments                 HCLPF (g)
  #                                                 Mode WBN0        SFP HEAT 356 FCV070    EXCHANGER A                     Functionality      0.69 0197A       CCS SUPPLY WBN0   Sta Ser & Cntl Air 357 FCV067  Cmpr Supply Hdr                   Functionality      0.83 0205        A Isol valve WBN0   Sta Ser & Cntl Air 358 FCV067  Cmpr Supply Hdr                   Functionality      0.83 0208        B Isol valve WBN1  TD Aux Feedwater 359 FCV001      Pmp Trip &                    Functionality       0.7 051      Throttle Valve WBN2  TD Aux Feedwater 360 FCV001      Pmp Trip &                    Functionality       0.7 051      Throttle Valve WBN2    ERCW Header B 361 FCV003     TD AFW PMP                     Functionality      1.14 0179AB    SUCT (PS144)
WBN2    ERCW Header A 362 FCV003     TD AFW PMP                     Functionality      1.14 0136AA    SUCT (PS139)
WBN2    ERCW Header A 363 FCV003     TD AFW PMP                     Functionality      1.14 0136BA          SUCT WBN2    ERCW Header B 364 FCV003     TD AFW PMP                     Functionality      1.14 0179BB          SUCT WBN1    ERCW Header A 365 FCV003     TD AFW PMP                     Functionality      1.14 0136AA    SUCT (PS139)
WBN1    ERCW Header A 366 FCV003     TD AFW PMP                     Functionality      1.14 0136BA          SUCT WBN1    ERCW Header B 367 FCV003     TD AFW PMP                     Functionality      1.14 0179AB    SUCT (PS144)
WBN1    ERCW Header B 368 FCV003     TD AFW PMP                     Functionality      1.14 0179BB          SUCT WBN1 CCS HX C SUP 369 FCV067                                    Functionality      0.92 FROM HDR 1A 0147A Page B30

Watts Bar Nuclear Plant ESEP Report Item                                            Failure UNID      Description   Notes/Comments                 HCLPF (g)
  #                                              Mode WBN1 CCS HX C SUP 370 FCV067                                 Functionality      0.92 FROM HDR 1B 0458A WBN1   N2 TANK NO. 1 371 TANK3  SUPPLY TO 1LCV                 Anchorage         0.63 0402A      0030173B WBN1 N2 TANK NO. 1 TANK 372           SUP TO 1PCV                   Anchorage         0.63 001 0010012B 0405A WBN2 N2 TANK NO. 1 TANK 373           SUP TO 2PCV                   Anchorage         0.63 001 0010012B 0405A WBN1 N2 TANK NO. 2 TANK 374           SUP TO 1PCV                   Anchorage         0.63 001 0010012B 0405B WBN2 N2 TANK NO. 2 TANK 375           SUP TO 2PCV                   Anchorage         0.63 001 0010012B 0405B WBN1 N2 TANK NO. 1 TANK 376           SUP TO 1PCV                   Anchorage         0.63 001 0010030B 0406A WBN2 N2 TANK NO. 1 TANK 377           SUP TO 2PCV                   Anchorage         0.63 001 0010030B 0406A WBN1 N2 TANK NO. 2 TANK 378           SUP TO 1PCV                   Anchorage         0.63 001 0010030B 0406B WBN2 N2 TANK NO. 2 TANK 379           SUP TO 2PCV                   Anchorage         0.63 001 0010030B 0406B WBN1 N2 TANK NO. 1 TANK 380           SUP TO 1PCV                   Anchorage         0.63 001 0010023A 0407A Page B31

Watts Bar Nuclear Plant ESEP Report Item                                          Failure UNID      Description   Notes/Comments                HCLPF (g)
  #                                            Mode WBN2 N2 TANK NO. 1 TANK 381          SUP TO 2PCV1                Anchorage         0.63 001 0023A 0407A WBN1 N2 TANK NO. 2 TANK 382           SUP TO 1PCV                 Anchorage         0.63 001 0010023A 0407B WBN2 N2 TANK NO. 2 TANK 383          SUP TO 2PCV1                Anchorage         0.63 001 0023A 0407B WBN1 N2 TANK NO. 1 TANK 384           SUP TO 1PCV                 Anchorage         0.63 001 0010005A 0408A WBN2 N2 TANK NO. 1 TANK 385           SUP TO 2PCV                 Anchorage         0.63 001 0010005A 0408A WBN1 N2 TANK NO. 2 TANK 386           SUP TO 1PCV                 Anchorage         0.63 001 0010005A 0408B WBN2 N2 TANK NO. 1 TANK 387           SUP TO 2PCV                 Anchorage         0.63 001 0010005A 0408B WBN2    N2 TANK NO. 1 388 TANK3 SUPPLY TO 2LCV                Anchorage         0.63 0402A     0030173B WBN1    N2 TANK NO. 2 389 TANK3 SUPPLY TO 1LCV                Anchorage         0.63 0402B     0030173B WBN2    N2 TANK NO. 2 390 TANK3 SUPPLY TO 2LCV                Anchorage         0.63 0402B     0030173B WBN1    N2 TANK NO. 1 391 TANK3 SUPPLY TO 1LCV                Anchorage         0.63 0402C     0030174B Page B32

Watts Bar Nuclear Plant ESEP Report Item                                           Failure UNID       Description  Notes/Comments                HCLPF (g)
  #                                             Mode WBN2    N2 TANK NO. 1 392  TANK3 SUPPLY TO 2LCV                Anchorage         0.63 0402C      0030174B WBN1    N2 TANK NO. 2 393  TANK3 SUPPLY TO 1LCV                Anchorage         0.63 0402D      0030174B WBN2    N2 TANK NO. 2 394  TANK3 SUPPLY TO 2LCV                Anchorage         0.63 0402D      0030174B WBN1    N2 TANK NO. 1 395  TANK3   SUP TO 1LCV                 Anchorage         0.63 0403A      0030172A WBN2    N2 TANK NO. 1 396  TANK3  SUP TO 2LCV3                Anchorage         0.63 0403A         172A WBN1    N2 TANK NO. 2 397  TANK3   SUP TO 1LCV                 Anchorage         0.63 0403B       003172A WBN2    N2 TANK NO. 2 398  TANK3  SUP TO 2LCV3                Anchorage         0.63 0403B         172A WBN1    N2 TANK NO. 1 399  TANK3   SUP TO 1LCV                 Anchorage         0.63 0403C      0030175A WBN2    N2 TANK NO. 1 400  TANK3  SUP TO 2LCV3                Anchorage         0.63 0403C         175A WBN1    N2 TANK NO. 2 401  TANK3   SUP TO 1LCV                 Anchorage         0.63 0403D      0030175A WBN2    N2 TANK NO. 2 402  TANK3  SUP TO 2LCV3                Anchorage         0.63 0403D         175A WBN0 AFW Supply Tank 403   TANK                                  Anchorage         0.51 500,000 gallons 0030226 WBN0 6900V 3MW FLEX TANK 404              DG Fuel Oil                 Anchorage         0.66 360113, Storage Tank 213 Page B33

Watts Bar Nuclear Plant ESEP Report Item                                             Failure UNID       Description   Notes/Comments                 HCLPF (g)
  #                                               Mode WBN1 TD Aux FW PMP 405 CLR003                                  Functionality        3 Oil Cooler 0001B WBN2 TD Aux FW PMP 406 CLR003                                  Functionality        3 Oil Cooler 0001B WBN2 Transfer Sw in 407 RLY046                                    Chatter          1.55 Aux Pos Isol Rly 0057S WBN2    B21 Relay AFPT 408 RLY046   Trip & Throttle                  Chatter           1.3 B002/1S    Vlv Photo Iso WBN2    B22 Relay AFPT 409 RLY046   Trip & Throttle                  Chatter           1.3 B002/2S    Vlv Photo Iso WBN2    B23 Relay AFPT 410 RLY046   Speed Control                    Chatter          1.55 B002/3S      Instr Pwr BA & BB Relay WBN2 AFPT Speed 411 RLY046                                    Chatter          1.79 Control Buffer BAS Relay WBN2    BA1 Relay AFPT 412 RLY046   Speed Control                    Chatter          1.79 BA1S          Buffer BA & BB Relay WBN2 AFPT Speed 413 RLY046                                    Chatter          1.79 Control Buffer BBS Relay WBN2 Aux FW Pump Vlv 414 RLY046                                    Chatter           1.4 Sep Relay R/AA WBN2 Aux FW Pump Vlv 415 RLY046                                    Chatter           1.4 Sep Relay R/BB WBN2 AFPT ACC Reset 416 RLY046                                    Chatter          1.79 Relay R1S WBN2 AFPT ACC Reset 417 RLY046                                    Chatter          1.79 Relay R2S Page B34

Watts Bar Nuclear Plant ESEP Report Item                                           Failure UNID       Description   Notes/Comments               HCLPF (g)
  #                                             Mode WBN2     AFPT SUP Xfer 418 RLY046  FCV115,16 &                 Chatter          1.79 R4A   51 Sep Relay TR A Aux Feed Pump WBN2 Trb Stm Supply 419 RLY046                                  Chatter          1.62 Xfer Sep Relay TR R5A A
WBN2    Turb/Mtr Driven 420 RLY046   Aux FW Pump                    Chatter           1.4 RA1A     Vlvs Aux Relay WBN2    Turb/Mtr Driven 421 RLY046 Aux FW Pump Vlv                  Chatter           1.4 RA2A       SSEP Relay AFPT Pump 2 WBN2 FCV151 Mtr Dr 422 RLY046                                  Chatter           1.4 Vlv 2LCV3156 &
RASS 164 WBN2    Turb/Mtr Driven 423 RLY046   Aux FW Pump                    Chatter           1.4 RB1B     Vlvs Aux Relay WBN2    Turb Driven Aux 424 RLY046 FW Pump Vlv SEP                  Chatter           1.4 RB2B          Relay AFPT Pump 2 WBN2 FCV151 Mtr Dr 425 RLY046                                  Chatter           1.4 Vlv 2LCV3171 &
RBSS 148 WBN2     AFPT SUP Xfer 426 RLY046  FCV115,16 &                 Chatter          1.79 SSTS     51 Sep Relay WBN1 Transfer Sw in 427 RLY046                                  Chatter          1.55 Aux Pos Isol Rly 0057S WBN1    B21 Relay AFPT 428 RLY046   Trip & Throttle                Chatter           1.3 B002/1S    Vlv Photo Iso WBN1    B22 Relay AFPT 429 RLY046   Trip & Throttle                Chatter           1.3 B002/2S    Vlv Photo Iso WBN1    B23 Relay AFPT 430 RLY046   Speed Control                  Chatter          1.55 B002/3S      Instr Pwr Page B35

Watts Bar Nuclear Plant ESEP Report Item                                           Failure UNID        Description   Notes/Comments               HCLPF (g)
  #                                             Mode BA & BB Relay WBN1 AFPT Speed 431 RLY046                                  Chatter          1.79 Control Buffer BAS Relay WBN1    BA1 Relay AFPT 432 RLY046   Speed Control                  Chatter          1.79 BA1S         Buffer BA & BB Relay WBN1 AFPT Speed 433 RLY046                                  Chatter          1.79 Control Buffer BBS Relay WBN1 Aux FW Pump Vlv 434 RLY046                                  Chatter           1.4 Sep Relay R/AA WBN1 Aux FW Pump Vlv 435 RLY046                                  Chatter           1.4 Sep Relay R/BB WBN1 AFPT ACC Reset 436 RLY046                                  Chatter          1.79 Relay R1S WBN1 AFPT ACC Reset 437 RLY046                                  Chatter          1.79 Relay R2S WBN1     AFPT SUP Xfer 438 RLY046  FCV115,16 &                 Chatter          1.79 R4A   51 Sep Relay TR A Aux Feed Pump WBN1 Trb Stm Supply 439 RLY046                                  Chatter          1.62 Xfer Sep Relay TR R5A A
WBN1    Turb/Mtr Driven 440 RLY046   Aux FW Pump                    Chatter           1.4 RA1A     Vlvs Aux Relay WBN1    Turb/Mtr Driven 441 RLY046 Aux FW Pump Vlv                  Chatter           1.4 RA2A       SSEP Relay AFPT Pump 2 WBN1 FCV151 Mtr Dr 442 RLY046                                  Chatter           1.4 Vlv 2LCV3156 &
RASS 164 Page B36

Watts Bar Nuclear Plant ESEP Report Item                                              Failure UNID        Description  Notes/Comments                  HCLPF (g)
  #                                                Mode WBN1   Turb/Mtr Driven 443 RLY046    Aux FW Pump                      Chatter           1.4 RB1B     Vlvs Aux Relay WBN1    Turb Driven Aux 444 RLY046  FW Pump Vlv SEP                    Chatter           1.4 RB2B          Relay AFPT Pump 2 WBN1 FCV151 Mtr Dr 445 RLY046                                     Chatter           1.4 Vlv 2LCV3171 &
RBSS 148 WBN1     AFPT SUP Xfer 446 RLY046  FCV115,16 &                    Chatter          1.79 SSTS      51 Sep Relay WBN1         TDAFW 447 STR046     Trip/Throttle                Functionality       0.57 0056AS    Motor Starter WBN2         TDAFW 448 STR046     Trip/Throttle                Functionality       0.57 0056AS    Motor Starter WBN1   Reactor Vessel                   Screened        > 0.5 449 FSV68  Head Vent 394      Isolation Valve 450  WBN1   Reactor Vessel                   Screened        > 0.5 FSV68  Head Vent 397      Throttle Valve 451  WBN2   Reactor Vessel                   Screened        > 0.5 FSV68  Head Vent 395      Isolation Valve 452  WBN2   Reactor Vessel                   Screened        > 0.5 FSV68  Head Vent 396      Throttle Valve Page B37}}