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#REDIRECT [[ULNRC-06161, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Expedited.]]
| number = ML14363A313
| issue date = 12/31/2014
| title = Ameren Missouri Callaway Energy Center Expedited Seismic Evaluation Process Report
| author name =
| author affiliation = Ameren Missouri, Stevenson & Associates, Westinghouse Electric Co, LLC
| addressee name =
| addressee affiliation = NRC/NRR
| docket = 05000483
| license number = NPF-030
| contact person =
| case reference number = ULNRC-06161
| package number = ML14363A311
| document type = Facility Safety Evaluation Report
| page count = 61
}}
 
=Text=
{{#Wiki_filter:Enclosure 2 to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report AMEREN MISSOURI CALLAWAY ENERGY CENTER EXPEDITED SEISMIC EVALUATION PROCESS (ESEP) REPORT December 31, 2014 Prepared by:      Ameren Missouri Westinghouse Electric Company LLC Stevenson & Associates 12/1/14                                                                              Page 1 of 61
              © 2014 by Westinghouse Electric Company LLC. All Rights Reserved.
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report EXPEDITED SEISMIC EVALUATION PROCESS REPORT Table of Contents 1.0  Purpose and Objective ..................................................................................................................... 4 2.0  Brief Summary of the FLEX Seismic Implementation Strategies .................................................... 5 3.0  Equipment Selection Process and ESEL ........................................................................................... 6 3.1                    Equipment Selection Process and ESEL.......................................................... 6 3.1.1                ESEL Development .......................................................................................... 7 3.1.2                Power Operated Valves .................................................................................. 7 3.1.3                Pull Boxes ........................................................................................................ 8 3.1.4                Termination Cabinets ..................................................................................... 8 3.1.5                Critical Instrumentation Indicators ................................................................ 8 3.1.6                Phase 2 and Phase 3 Piping Connections ....................................................... 8 3.1.7                Relays .............................................................................................................. 9 3.2                    Justification for Use of Equipment That Is Not the Primary Means for FLEX Implementation .............................................................................................. 9 4.0  Ground Motion Response Spectrum (GMRS) .................................................................................. 9 4.1                    Plot of GMRS Submitted by the Licensee ...................................................... 9 4.2                    Comparison to SSE ........................................................................................ 12 5.0  Review Level Ground Motion (RLGM) ........................................................................................... 13 5.1                    Description of RLGM Selected ...................................................................... 13 5.2                    Method to Estimate ISRS.............................................................................. 14 6.0  Seismic Margin Evaluation Approach ............................................................................................ 15 6.1                    Summary of Methodologies Used................................................................ 15 6.2                    HCLPF Screening Process .............................................................................. 15 6.2.1                Overview ....................................................................................................... 15 6.2.2                Generic Screening Results ............................................................................ 16 6.3                    Seismic Walkdown Approach ....................................................................... 19 6.3.1                Walkdown Approach .................................................................................... 19 6.3.2                Application of Previous Walkdown Information ......................................... 19 6.3.3                Significant Walkdown Findings .................................................................... 19 12/2/14                                                                                                                        Page 2 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 6.4                          HCLPF Calculation Process ............................................................................ 23 6.5                          Functional Evaluations of Relays.................................................................. 23 6.6                          Tabulated ESEL HCLPF Values (Including Key Failure Modes) ..................... 23 7.0  Inaccessible Items .......................................................................................................................... 26 7.1                          Identification of ESEL items inaccessible for walkdowns ............................ 26 8.0  ESEP Conclusions and Results ........................................................................................................ 26 8.1                          Supporting Information ................................................................................ 26 8.2                          Indication of Planned Modifications ............................................................ 28 8.3                          Modification Implementation Schedule ...................................................... 29 8.4                          Summary of Regulatory Commitments ....................................................... 29 9.0  References ...................................................................................................................................... 31 Attachment A              Callaway ESEL................................................................................................ 34 Attachment B              ESEP HCLPF Values and Failure Modes Tabulation ..................................... 50 12/2/14                                                                                                                                Page 3 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 1.0    Purpose and Objective Following the accident at the Fukushima Dai-ichi nuclear power plant resulting from the March 11, 2011, Great Tohoku Earthquake and subsequent tsunami, the Nuclear Regulatory Commission (NRC) established a Near-Term Task Force (NTTF) to conduct a systematic review of NRC processes and regulations and to determine if the agency should make additional improvements to its regulatory system. The NTTF developed a set of recommendations intended to clarify and strengthen the regulatory framework for protection against natural phenomena. Subsequently, the NRC issued a 50.54(f) letter on March 12, 2012 [1], requesting information to assure that these recommendations are addressed by all U.S. nuclear power plants. The 50.54(f) letter requests that licensees and holders of construction permits under 10 CFR Part 50 reevaluate the seismic hazards at their sites against present-day NRC requirements and guidance. Depending on the comparison between the reevaluated seismic hazard and the current design basis, further risk assessment may be required. Assessment approaches acceptable to the staff include a seismic probabilistic risk assessment (SPRA), or a seismic margin assessment (SMA). Based upon the assessment results, the NRC staff will determine whether additional regulatory actions are necessary.
This report describes the Expedited Seismic Evaluation Process (ESEP) undertaken for the Callaway Energy Center (CEC). The intent of the ESEP is to perform an interim action in response to the NRCs 50.54(f) letter [1] and 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 EPRI 3002000704, Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic [2]. The guidance discusses the use of the ongoing FLEX process [3] as a starting point for consideration.
This report examines the FLEX equipment and strategy [3] (Section 2.0) to develop the initial Expedited Seismic Equipment List (ESEL) and uses an iterative process to develop the final ESEL [4] (Section 3.0).
The ESEL is used to evaluate the listed equipment against the review level ground motion (RLGM) data (Section 5) with respect to the equipments seismic capacity based on characterization of the high confidence of a low probability of failure (HCLPF).
Equipment which has seismic capacity larger than the RLGM data can be screened from further evaluation. For equipment that has a seismic capacity below the RLGM, modifications need to be performed following the NRC endorsed guidance in EPRI 3002000704.
The objective of this report is to provide summary information describing the ESEP evaluations and results. The level of detail provided in this report is intended to enable the NRC to understand the inputs used, the evaluations performed, and the decisions made as a result of the interim evaluations.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 2.0    Brief Summary of the FLEX Seismic Implementation Strategies The Callaway FLEX strategies for Reactor Core Cooling and Heat Removal, Reactor Inventory Control/Long-term Subcriticality, and Containment Function are summarized below. This summary is derived from the Callaway Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA-12-049 [3].
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 (TDAFP) during FLEX Phase 1 with suction from the Condensate Storage Tank (CST).
Ameren Missouri has elected to construct a new Hardened Condensate Storage Tank (HCST) [3]. The larger HCST volume would be capable of feeding the steam generators for at least 72 hours. This extended coping duration will not require HCST make-up from the UHS before the Phase 3 off-site equipment is deployed. The TDAFP flow control valves and Main Steam Atmospheric Relief Valves (ARVs) are also required to provide reactor core heat-removal capability. Phase 2 reactor core heat removal is achieved via the new FLEX mechanical connections. The only permanent plant equipment manipulated for the Phase 2 is manual valves.
Reactor Inventory Control/Long-term Subcriticality strategy consists of reactor coolant system borated make-up via the FLEX primary make-up connections.
Reactor coolant system (RCS) inventory reduction is a result of water volume reduction due to cooldown, reactor coolant pump seal leakage, and letdown via head-vents and/or pressurizer PORVs. The reactor coolant pump seal leak-off containment isolation valve is manually isolated to conserve inventory and keep leak-off flow within the Reactor Building. To avoid adverse effects on the RCS natural circulation flow, the accumulator isolation valves are electrically closed during the cooldown to prevent nitrogen injection into the reactor coolant system.
There are no Phase 1 or Phase 2 FLEX actions required to maintain containment integrity. In fact, containment function is not expected to be challenged during all three phases.
Necessary electrical components are outlined in the Callaway FLEX OIP submittal [3],
and primarily entail the installation of a 480V generator (FLEX) to provide power to vital batteries, equipment installed to support FLEX electrical connections, and monitoring instrumentation required for core cooling, reactor coolant inventory, and containment integrity.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 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 Callaway is presented in Attachment A.
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 Phases 1, 2 and 3 mitigation of a Beyond Design Basis External Event (BDBEE), as outlined in the Callaway Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA-12-049 [3]. The OIP provides the Callaway 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 Callaway OIP [3]. FLEX recovery actions are excluded from the ESEP scope per EPRI 3002000704 [2]. The overall list of planned FLEX modifications and the scope for consideration herein is limited to those required to support core cooling, reactor coolant inventory and subcriticality, and containment integrity functions. Portable and pre-staged FLEX equipment (not permanently installed) are excluded from the ESEL per EPRI 3002000704 [2].
The ESEL component selection followed the EPRI guidance outlined in Section 3.2 of EPRI 3002000704.
: 1. The scope of components is limited to that required to accomplish the core cooling and containment safety functions identified in Table 3-2 of EPRI 3002000704. The instrumentation monitoring requirements for core cooling/containment safety functions are limited to those outlined in the EPRI 3002000704 guidance, and are a subset of those outlined in the Callaway OIP [3].
: 2. The scope of components is limited to installed plant equipment and the FLEX connections necessary to implement the Callaway OIP [3] 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 Back-up/Alternate).
: 4. The Primary FLEX success path is to be specified. Selection of the Back-up/Alternate FLEX success path must be justified.
: 5. Phase 3 coping strategies are included in the ESEP scope, whereas recovery strategies are excluded.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report
: 6. Structures, systems, and components excluded per the EPRI 3002000704
[2] 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.
* Power-operated valves not required to change state as part of the FLEX mitigation strategies.
* Nuclear steam supply system components (e.g., reactor pressure vessel and internals, reactor coolant pumps and seals, etc.)
: 7. For cases in which neither train was specified as a primary or back-up 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 Callaway 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 One Line Diagrams) were performed to identify the boundaries of the flowpaths to be used in the FLEX strategies and to identify specific components in the flowpaths 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 one-line drawings, system descriptions, design basis documents, etc., as necessary. The P&IDs are also used to determine the normal position of system valves and the valve positioning required in order to align the system in support of the FLEX functions.
The electrical equipment required to support the mechanical components used in the FLEX strategies evaluated for the ESEL was also evaluated for its inclusion on the ESEL using electrical drawings and guidance [2].
3.1.2 Power Operated Valves Page 3-3 of EPRI 3002000704 [2] notes that power operated valves not required to change state are excluded from the ESEL. Page 3-2 also notes that functional failure modes of electrical and mechanical portions of the installed Phase 1 equipment should be considered (e.g., RCIC/AFW trips). To address this 12/2/14                                                                                Page 7 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report concern, the following guidance is applied in the Callaway ESEL for functional failure modes associated with power operated valves:
* Power operated valves that remain energized during the Extended Loss of all AC Power (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 de-energized.
* Power operated valves not required to change state as part of the FLEX mitigation strategies during Phase 1, and are re-energized 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 re-powered.
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 Phase 3 connections, provide consolidated locations for permanently connecting multiple cables. The termination cabinets and the internal connections provide a completely passive function; however, the cabinets are included in the ESEL to ensure industry knowledge on panel/anchorage failure vulnerabilities is addressed.
3.1.5 Critical Instrumentation Indicators Critical indicators and recorders are typically physically located on panels/cabinets and are included as separate components; however, seismic evaluation of the instrument indication may be included in the panel/cabinet seismic evaluation (rule-of-the-box).
3.1.6 Phase 2 and Phase 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 Callaway 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 Back-up/Alternate).
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Item 6 in Section 3.1 above goes on to explain that Piping, cabling, conduit, HVAC, and their supports are excluded from the ESEL scope in accordance with EPRI 3002000704 [2].
Therefore, piping and pipe supports associated with FLEX Phase 2 and Phase 3 connections are excluded from the scope of the ESEP evaluation. However, any active valves in FLEX Phase 2 and Phase 3 connection flow path are included in the ESEL.
3.1.7 Relays Relays essential to the FLEX strategy were explicitly addressed [5]. Relays were screened and where relay chatter was found to result in an undesirable alignment the relay, and its parent cabinet, were added to the analysis. Parent cabinets were walked down and, if needed, HCLPF estimates were performed.
3.2  Justification for Use of Equipment That Is Not the Primary Means for FLEX Implementation No equipment outside of the primary FLEX strategy is credited in the Callaway ESEP [4].
The complete ESEL for Callaway [4] is presented in Attachment A.
4.0    Ground Motion Response Spectrum (GMRS) 4.1  Plot of GMRS Submitted by the Licensee The CEC design response spectra are stated to be applied in the free field at finished grade [6].
The 1E-4 and 1E-5 Uniform Hazard Response Spectra (UHRS), along with a design factor (DF), are used to compute the GMRS at the control point as shown in the seismic hazard and GMRS submittal to the NRC [7].
Table 4-1 shows the UHRS and GMRS spectral accelerations.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Table 4-1: UHRS for 10-4 and 10-5 and GMRS at the control point for Callaway
                                    -4                -5 Freq. (Hz)  10 UHRS (g)      10 UHRS (g)        GMRS (g) 100        4.20E-01        9.88E-01        5.00E-01 90        4.24E-01        1.00E+00        5.06E-01 80        4.30E-01        1.02E+00        5.15E-01 70        4.40E-01        1.05E+00        5.30E-01 60        4.61E-01        1.11E+00        5.57E-01 50        5.12E-01        1.23E+00        6.17E-01 40        6.17E-01        1.45E+00        7.34E-01 35        6.83E-01        1.60E+00        8.12E-01 30        7.68E-01        1.82E+00        9.20E-01 25        8.70E-01        2.10E+00        1.06E+00 20        9.16E-01        2.21E+00        1.11E+00 15        9.02E-01        2.18E+00        1.10E+00 12.5        9.10E-01        2.16E+00        1.09E+00 10        9.54E-01        2.17E+00        1.11E+00 9        9.90E-01        2.21E+00        1.13E+00 8        1.02E+00        2.24E+00        1.15E+00 7        1.03E+00        2.24E+00        1.15E+00 6        1.01E+00        2.19E+00        1.12E+00 5        9.14E-01        2.00E+00        1.02E+00 4        6.74E-01        1.55E+00        7.85E-01 3.5        5.29E-01        1.25E+00        6.32E-01 3        4.00E-01        9.59E-01        4.83E-01 2.5        2.87E-01        6.81E-01        3.44E-01 2        2.31E-01        5.32E-01        2.70E-01 1.5        1.70E-01        3.75E-01        1.92E-01 12/2/14                                                                                Page 10 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report
                              -4                -5 Freq. (Hz)  10 UHRS (g)      10 UHRS (g)        GMRS (g) 1.25        1.58E-01        3.39E-01        1.75E-01 1        1.36E-01        2.86E-01        1.48E-01 0.9        1.24E-01        2.61E-01        1.35E-01 0.8        1.12E-01        2.38E-01        1.23E-01 0.7        1.02E-01        2.19E-01        1.13E-01 0.6        9.47E-02        2.04E-01        1.05E-01 0.5        8.64E-02        1.89E-01        9.68E-02 0.4        6.91E-02        1.51E-01        7.75E-02 0.35        6.05E-02        1.32E-01        6.78E-02 0.3        5.18E-02        1.13E-01        5.81E-02 0.25        4.32E-02        9.44E-02        4.84E-02 0.2        3.45E-02        7.55E-02        3.87E-02 0.15        2.59E-02        5.66E-02        2.91E-02 0.125        2.16E-02        4.72E-02        2.42E-02 0.1        1.73E-02        3.77E-02        1.94E-02 12/2/14                                                                          Page 11 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Figure 4-1 shows the control point UHRS and GMRS.
Mean Soil UHRS and GMRS at Callaway 2.5 2.
1E-5 UHRS Spectral acceleration, g 1.5                                                                        GMRS 1E-4 UHRS 1.
0.5 0.
0.1                1                    10                  100 Spectral frequency, Hz Figure 4-1:    Plots of 1E-4 and 1E-5 UHRS and GMRS at control point for Callaway (5%-damped response spectra) 4.2                              Comparison to SSE The definition of the SSE for Callaway is discussed in Section 2.5, 3.7 and 3.7(B) of the FSAR [6]. The SSE is anchored to a 0.20g Peak Ground Acceleration (PGA) and is presented in Table 4-2.
Table 4-2: SSE for Callaway Freq (Hz)        SA (g) 0.25          0.09 2.50          0.63 9.00          0.52 33.00          0.20 100.00        0.20 12/2/14                                                                                                        Page 12 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report As shown in Figure 4-2, the GMRS begins to exceed the SSE at around 3.5 Hz.
SSE        GMRS 10.00 1.00 Acceleration (g) 0.10 0.01 0.1                          1                              10                      100 Frequency (Hz)
Figure 4-2: Callaway SSE - GMRS Comparison 5.0                  Review Level Ground Motion (RLGM) 5.1          Description of RLGM Selected The Review Level Ground Motion is derived by linearly scaling the current design basis SSE by the maximum ratio of the GMRS to the SSE between the 1 and 10 Hz range (not to exceed two times the SSE) [2]. The maximum GMRS/SSE ratio occurs at 10 Hz as seen in Figure 4-2. The In-Structure Response Spectra document provides logarithmic interpolation at 10 Hz to determine that the SSE spectral acceleration is 0.48 g [8]. Examination of Table 4-1 shows that the GMRS spectral acceleration is 1.11 g. The result is a maximum GMRS/SSE ratio between 1 - 10 Hz of 2.31 (witness 1.11 g / 0.48 g = 2.31). Since the GMRS/SSE ratio cannot exceed 2 the RGLM is scaled at 2 X SSE. The resulting RLGM is shown in Table 5-1 and Figure 5-1.
It is noted that for surface-mounted structures, systems, and components (SSC)
(TAP01, TBN01, and the CST pipe house) directly applying the GMRS for HCLPF 12/2/14                                                                                                    Page 13 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report determination is acceptable. Results based upon the GMRS as the seismic margins earthquake are noted where applicable herein.
Table 5-1: RLGM for Callaway Freq. (Hz)          100        33          9          2.5  0.25 RLGM (g)            0.4      0.4      1.04          1.26  0.18 SSE        GMRS        RLGM 10.00 1.00 Acceleration (g) 0.10 0.01 0.1                              1                              10                      100 Frequency (Hz)
Figure 5-1: Callaway RLGM vs GMRS 5.2          Method to Estimate In-Structure Response Spectra (ISRS)
The ISRS for Callaway [10a] uses the scaled approach to estimate the ISRS. As mentioned in Section 5.1, the RLGM is scaled by a factor of 2 which is also applied to the existing ISRS curves.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 6.0    Seismic Margin Evaluation Approach It is necessary to demonstrate that the ESEL items have sufficient seismic capacity to meet or exceed the demand characterized by the RLGM. The seismic capacity is characterized as the peak ground acceleration (PGA) for which there is a high confidence of a low probability of failure (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 NP-6041, A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1) [8].
: 2. Probabilistic approach using the fragility analysis methodology of EPRI TR-103959, Methodology for Developing Seismic Fragilities [9].
Callaway has elected to use the deterministic approach by applying the EPRI NP-6041 screening process [8].
6.1      Summary of Methodologies Used The seismic margins methodology of EPRI report NP-6041-SL [8] was applied for this effort. Use of this methodology conforms to Section 5 of EPRI 3002000704. The primary tasks performed were:
* Generic seismic screening per NP-6041, Table 2-4.
* Performance of seismic walkdowns.
* Item-specific screening via walkdown, review of design data, and performance of screening calculations.
* Performance of HCLPF calculations for screened-in equipment 6.2      HCLPF Screening Process 6.2.1 Overview The seismic margins screening methodology of NP-6041-SL was applied. The primary steps for this screening process are:
: 1. Apply NP-6041-SL, Table 2-4 to determine which equipment items and failure modes may be screened-out on a generic basis.
: 2. For each equipment item, perform a seismic walkdown to verify generic screening may be applied and to verify the item does not have any specific seismic vulnerabilities.
: 3. Verify anchorage capacity.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report The generic screening criteria of Table 2-4 are dependent on the applied screening level and are applicable to equipment located within 40 feet of plant grade. For the Callaway ESEP project:
* The peak 5% spectral acceleration of the RLGM is 1.26g and occurs at 2.5 Hz. At 3.5 Hz, the RLGM decreases to 1.2g 1. From FSAR SP Table 3.7(B)-4 and SA Tables 3.7-3 and 3.7-4, all Category I structures have fundamental frequencies exceeding 3.5 Hz and can reasonably be considered to respond in the frequency range corresponding to accelerations less than 1.2g. Accordingly, the 2nd screening column (0.8 - 1.2g) screening criteria of NP-6041-SL, Table 2-4, were applied with special consideration for components with low frequencies.
* A number of components in the Auxiliary/Control Building and the Reactor Building were located above 40 from grade; all other equipment was located within 40 of plant grade. Per Appendix A of NP-6041-SL, components that are above 40 from grade and have corresponding ISRS at the base of component in exceedance of 1.5 times the bounding spectrum (equivalent to a 1.8g peak spectral acceleration) may not be screened to the 2nd screening column and require HCLPF analysis.
Table 6-1 below summarizes the application of Table 2-4 screening for the ESEP.
Applied plant grade was Elevation 2000. Per the FSAR this grade elevation is constant through-out the power block area.
After completion of the screening process, an item is either screened-out or screened-in. The presumptive seismic capacity of a screened-out item exceeds the applied screening level and no further evaluation is needed. An item that is screened-in requires a HCLPF analysis to address the failure mode cited by the seismic review team (SRT). The HCLPF capacity may or may not be above the screening level.
6.2.2 Generic Screening Results Table 6-1 summarizes the generic screening results for the ESEL. Only the relevant equipment types are listed. Based on the generic screening:
* HCLPF analyses are required for atmospheric storage tanks
* Relay chatter requires evaluation 1
The frequency where the RLGM spectra equals 1.2g is determined by logarithmic interpolation based on the control point accelerations and frequencies in Reference 8 as follows:
log(1.04 g ) log(1.26 g )
(log( X Hz ) log( 2.5 Hz )                            + log(1.26 g )
log( 9 Hz ) log( 2.5 Hz )
1.2 g = 10 X = 3.46 Hz 12/2/14                                                                                                                    Page 16 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Other generic screening requirements were addressed by walkdown, design review and anchorage verification. These assessments are documented in the screening evaluation work sheets (SEWS) [10f].
Table 6-1: Summary of generic screening per NP-6041-SL Table 2-4, 1.2g Screening Level Equipment Type            Generic Screening Criteria                  Screening Result Active valves                  Note (f) applies.              There are no extremely large extended motor operators on 2-inch or smaller piping.
Passive valves                  No evaluation required.        N/A Atmospheric storage tanks      Evaluation required.          HCLPF analyses required for the atmospheric storage tanks.
Pressure vessels                Notes (h), (i) apply          For the pressurized tanks on the ESEL, anchorage and load path were verified by bounding calculations using qualification reports during screening. Potential failure modes of the vessel bodies were addressed by walkdown and design review.
Batteries and racks            Note (k) applies.              Batteries are braced racks and are designed for seismic loads. HCLPF analyses are required for the battery rack anchorage.
Horizontal pumps                No evaluation required.        Although no evaluation is required for the component per se, a HCLPF evaluation for the auxiliary feedwater turbine-driven pump is required.
Active electrical power        Notes (s) and (t) apply.      Note (s) was addressed by walkdown and distribution panels                                            design review. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required.
Relays are evaluated separately per Reference 5.
Passive electrical power        Note (s) applies.              Note (s) was addressed by walkdown and distribution panels                                            design review. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required.
Transformers                    Notes (u) and (v) apply.      The ESEL includes dry-type transformers. A design review verified coil restraint. HCLPF analysis of anchorage is required.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Equipment Type              Generic Screening Criteria                  Screening Result Battery chargers & inverters    Note (w) applies.              Per walkdown and design review, the items on the ESEL are solid state units. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required.
Instrumentation and control      Notes (s) and (t) apply.      Note (s) was addressed by walkdown and panels and racks                                                design review. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required.
Relays are evaluated separately per Reference 5.
Temperature sensors; pressure    Note (x) applies.              Note (x) was addressed by walkdown and and level sensors.                                              design review. Sensors in the scope were typically mounted in-line on piping.
Relevant notes from NP-6041-SL Table 2-4
: f. Evaluation recommended for MOVs in piping lines of 2 inches diameter or less.
: h. Margin evaluation only needs to consider anchorage and supports.
: i. For vessels designed by dynamic analysis or equivalent static analysis enveloping vessel inertial and piping loading, only the anchorage and supports require evaluation. For vessel not meeting these criteria, all potential failure modes require evaluation.
: k. Batteries mounted in braced racks designed for seismic loads or qualified by dynamic testing do not require evaluation. Rigid spacers between batteries and end restraints are required. Batteries should be tightly supported by side rails.
: s. Walkdown should be conducted to verify that the instruments are properly attached to the cabinets.
: t. Relays, contactors, switches, and breakers must be evaluated for chatter and trip if functionality during strong shaking is required.
: u. Anchorage evaluation required.
: v. Liquid-filled transformers require evaluation of overpressure safety switches. The transformer coils should be restrained within the cabinet for dry transformers.
: w. Solid state units require anchorage checks. Others require evaluation.
: x. Insufficient data are available for screening guidelines. Emphasis should be on attachments.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 6.3    Seismic Walkdown Approach 6.3.1 Walkdown Approach Walkdowns were performed by two-person seismic review teams (SRTs) consisting of engineers with seismic experience. Walkdowns followed the guidance of Section 5 of EPRI 3002000704 [2] and Section 2 of NP-6041-SL [8]. The SRT used NP-6041-SL, Appendix F, to evaluate item-specific equipment caveats. The SRT also recorded notes and took photographs of the items under review.
Two walkdown sessions have been performed as indicated below.
Walkdown Date                          SRT                          Plant Support Week of July 14, 2014            Hunter Young (S&A)                  Jim Cunningham (Callaway)
Samer El-Bahey (S&A)                Steve Sampson (Callaway)
George Belchik (Callaway)
Week of November 3, 2014        Hunter Young (S&A)                  David Hollabaugh (Callaway)
Apostolos Karavoussianis (S&A)
The walkdown findings for each item are documented in screening evaluation work sheets (SEWS). The SEWS notes also identify evaluations and reviews performed to support screening. The SEWS are included in Appendix C of Reference 10f. Also, Appendix A [10f] provides a concise summary of screening results in tabular format.
6.3.2 Application of Previous Walkdown Information New seismic walkdowns were performed for ESEL equipment. The results of the previous seismic margin evaluation, performed for the Seismic IPEEE program [11], were reviewed and used for background purposes only.
6.3.3 Significant Walkdown Findings The walkdown and screening results are summarized in Table 6-2.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Table 6-2: Items Selected for HCLPF Analysis No.        ID          Description          Bldg    Elev                              Basis for Selection
: 1. NB001    4.16KV SWGR NB001 (Class    CB      2000-00  Anchorage could not be readily screened. Perform HCLPF analysis 1E, Train A)                                  of anchorage.
: 2. NG001    480 V LOAD CENTER NG01      CB/CC  2000-00  Anchorage could not be readily screened. Perform HCLPF analysis of anchorage.
Apply results to similar items NG002 and NG003.
: 3. NK011    125 V BATTERY NK011          CB/CC  2016-00  Anchorage could not be readily screened. Perform HCLPF analysis of anchorage.
Apply results to similar items NK013 and NK014.
: 4. NK021    125 V BATTERY CHARGER        CB/CC  2016-00  Anchorage could not be readily screened. Perform HCLPF analysis NK021                                          of anchorage.
Apply results to similar items NK023 and NK024.
: 5. NK025    125 V BATTERY CHARGER        CB      2000-00  Anchorage could not be readily screened. Perform HCLPF analysis NK025 (Swing Battery                          of anchorage.
Charger)
: 6. NN001    Class 1E AC DIST SWBD        CB/CC  2016-00  Anchorage could not be readily screened. Perform HCLPF analysis NN01 (SEP GRP 1)                              of anchorage.
Apply results to similar items NK043, NN003, NK051, NK041, NK001, NK003, NK004, and NN004.
: 7. NN011    7.5KVA INVERTER (FED        CB/CC  2016-00  Anchorage could not be readily screened. Perform HCLPF analysis FROM BATT CHARGER                              of anchorage.
NK021)
Apply results to similar item NN013.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report No.        ID        Description      Bldg      Elev                              Basis for Selection
: 8. PA003    CUBICLE PT FOR RCP      AUX      2026-00  Anchorage could not be readily screened. Perform HCLPF analysis MOTOR DPBB01A                              of anchorage.
Apply results to similar item PA004.
: 9. PAL02    TDAFW Pump              AUX      2000-00  Anchorage could not be readily screened. Perform HCLPF analysis of anchorage.
: 10. RL001    REACTOR COOLANT AND      CB      2047-06  Anchorage could not be readily screened. Perform HCLPF analysis SUPT SYS CONSOLE                            of anchorage.
Apply results to similar items RL002, RL005, RL006, and RL017 thru RL026.
: 11. SB102A    W CABINET FOR REACTOR    AUX      2026-00  Anchorage could not be readily screened. Perform HCLPF analysis TRIP SWG TRAIN-A                            of anchorage.
: 12. TAP01    Condensate Storage Tank  YARD    2000-00  Perform HCLPF analysis per Appendix H of NP-6041. In addition, evaluate block wall doghouse that is adjacent for interaction hazard.
: 13. TBN01    RWST                    YRD      2000-00  Perform HCLPF analysis per Appendix H of NP-6041.
: 14. XNG01    4.16-KV/480 V LOAD      CB/CC    2000-00  Anchorage could not be readily screened. Perform HCLPF analysis CENTER TRANSFORMER                          of anchorage.
XNG01 FOR LC NG001 12/2/14                                                                      Page 21 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report No.          ID        Description          Bldg      Elev                            Basis for Selection
: 15. Generic    Equipment 40 above grade  AB/CB    2047-06  Equipment on the Aux/Ctrl 2047.5' elevation are 40' above grade and have ISRS spectral accelerations in both horizontal directions exceeding 1.8g (with clipping) and therefore do not screen to the 2nd screening lane. HCLPF analysis for component functionality and structure (including anchorage) are required for the associated components.
Affected components include NF039A, NF039B, NF039C, NG003C, NG004C, RP053AC, RP053BC, RP053DB, RP068, RP081A, RP081B, RP289, SA036A, SA036C, SA066A, SA066B, SA075A, SB029A, SB029D, SB030A, SB032A, SB032D, SB033A, SB037, SB038, SB041, SB078, SB079, SE054A, SE054C, and SE054D.
: 16. Generic    BLOCK WALLS                AB/ CB  Var.      Per NP-6041-SL Table 2-4 seismic capacity cannot be screened and HCLPF analysis is required for block wall seismic capacity.
Affected components include NB001, NK025, NG003, TAP01, NK043, NN003, NN013, NK041, NN001, NK021, NN011, NK051, NK001, NK023, NK071, NK073, NK011, NK013, AB007, NK003, RP209, NG002, NK024, NK074, NK004, NK014, NN014, NN004, RP140, and RP334.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 6.4    HCLPF Calculation Process All HCLPF values were calculated using the conservative, deterministic failure margin (CDFM) criteria of NP-6041-SL [8]. CDFM analysis criteria are summarized in NP-6041-SL, Table 2-5.
For structural failure modes, the HCLPF capacity is equal to the earthquake magnitude at which the strength limit is reached. For equipment functionality, experience data or available test response spectra (TRS) are typically used to define the HCLPF capacity.
The methods of NP-6041-SL, Appendix Q were applied for functionality evaluations.
6.5    Functional Evaluations of Relays Verification of the functional capacity for equipment mounted within 40 of grade was addressed by application NP-6041-SL, Table 2-4 generic screening criteria as described above. For equipment mounted higher than 40 above grade and for in-scope relays, the methods of NP-6041-SL, Appendix Q were applied for functionality evaluations. In those cases the seismic capacity was based upon one of the following:
* Test response spectra (TRS) from plant-specific seismic qualification reports.
* Generic equipment ruggedness spectra (GERS) from EPRI report NP-5223-SL [12].
* Experience based seismic capacity per the guidelines of EPRI TR-1019200 [13].
Screening of relays within the scope of the ESEP (in accordance with EPRI 3002000704) is conducted within 14C4258-RPT-003 [5]. Cabinets requiring HCLPF evaluation for relay functionality are noted in Table 7-2 [5] under Item 17.
6.6    Tabulated ESEL HCLPF Values (Including Key Failure Modes)
Table 6-3 lists HCLPF analysis results. The failure modes analyzed are identified.
Supporting calculation documents [10.d &e] containing the detailed HCLPF calculations are also identified.
For the following discussion, an ESEP outlier is defined as an item whose HCLPF capacity is less than the RLGM. There are currently four ESEP outliers:
* NG003C (Relay Capacity)
* NG004C (Relay Capacity)
* TAP01 (Anchorage Capacity)
* TBN01 (Anchorage Capacity)
Note that for the CST (TAP01) and RWST (TBN01), the applied ground motion and HCLPF are based on the GMRS of Reference 7. The GMRS is acceptable as an alternative RLGM per EPRI 3002000704, Section 4, Option 2. The CST and RWST are founded on a slab-on-grade in the yard. The GMRS has a horizontal PGA of 0.50g.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Relay Chatter Failure Modes NG003C and NG004C are ESEP-outliers with respect to relay chatter. Refer to 14C4258-RPT-003 [5] for specific relays. Credit for operator action may resolve the relay chatter failure modes.
Tabulated HCLPF Values In general, the HCLPF values for screened-out items equals or exceeds the RLGM.
HCLPF  0.40g                        The HCLPF for screened-out items and failure modes Unless justified by calculations, the above HCLPF is applicable for all screened-out items and covers the relevant failure modes.
The HCLPF values for all ESEL items are tabulated in Appendix B.
Table 6-3: HCLPF Analysis Results No. ID          Description            Bldg    Elev    HCLPF2    Failure Mode Basis    Related Components (g, PGA)  Analyzed
: 1. NB001      4.16KV SWGR NB001      CB      2000-00 0.41      Equipment    14C4258- n/a (Class 1E, Train A)                              capacity and CAL-005 anchorage
: 2. NG001      480 V LOAD CENTER      CB/CC  2000-00 0.41      Equipment    14C4258- NG002, NG003 NG01                                              capacity and CAL-005 anchorage
: 3. NK011      125 V BATTERY NK011    CB/CC  2016-00 2.36      Anchorage    14C4258- NK013, NK014 CAL-004
: 4. NK021      125 V BATTERY          CB/CC  2016-00 1.33      Anchorage    14C4258- NK023, NK024 CHARGER NK021                                                  CAL-004
: 5. NK025      125 V BATTERY          CB      2000-00 0.85      Anchorage    14C4258- n/a CHARGER NK025 (Swing                                          CAL-004 Battery Charger)
: 6. NN001      Class 1E AC DIST SWBD  CB/CC  2016-00 0.71      Anchorage    14C4258- NK043, NN003, NK051, NK041, NN01 (SEP GRP 1)                                              CAL-004 NK001, NK003, NK004, NN004
: 7. NN011      7.5KVA INVERTER (FED    CB/CC  2016-00 0.75      Anchorage    14C4258- NN013 FROM BATT CHARGER                                              CAL-004 NK021)
: 8. PA003      CUBICLE PT FOR RCP      AUX    2026-00 0.62      Anchorage    14C4258- PA004 MOTOR DPBB01A                                                  CAL-004 2
HCLPFs based upon RLGM (PGA=0.40g) as the seismic margins earthquake with the exception of TAP01, TBN01, and the CST pipe house block walls, which are based upon the GMRS (PGA=0.50g).
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report No. ID        Description              Bldg    Elev    HCLPF2    Failure Mode        Basis    Related Components (g, PGA)  Analyzed
: 9. PAL02      TDAFW Pump              AUX    2000-00 1.75      Anchorage          14C4258- n/a CAL-004
: 10. RL001      REACTOR AUX CNTRL        CB      2047-06 0.71      Anchorage          14C4258- RL002, RL005, RL006, RL017 thru PANEL                                                                  CAL-004 RL026
: 11. SB102A    W CABINET FOR            AUX    2026-00 0.58      Anchorage          14C4258- n/a REACTOR TRIP SWG                                                      CAL-004 TRAIN-A
: 12. TAP01      Condensate Storage      YARD    2000-00 0.30      Equipment          14C4258- n/a Tank                                              capacity and        CAL-002 anchorage
: 13. TBN01      RWST                    YRD    2000-00 0.33      Equipment          14C4258- n/a capacity and        CAL-002 anchorage
: 14. XNG01      4.16-KV/480 V LOAD      CB/CC  2000-00 0.45      Anchorage          14C4258-CENTER TRANSFORMER                                                    CAL-004 XNG01 FOR LC NG001
: 15. Generic    Equipment >40 SE054A    NIS Cabinet              CB      2047-06 0.41      Equipment          14C4258- SE054C, SE054D capacity and        CAL-005 anchorage SB037      7300 Series Three Bay    CB      2047-06 0.41      Equipment          14C4258- SB038, SB041, SB078, SB079 Cabinets                                          capacity and        CAL-005 anchorage SA066A      STATUS INDICATING      CB      2047-06 0.41      Equipment          14C4258- SA066B SYS                                                capacity and        CAL-005 anchorage RP068      BOP Instrumentation      CB      2047-06 0.41      Equipment          14C4258- n/a Panel                                              capacity and        CAL-005 anchorage RP053AC    BOP Instrumentation      CB      2047-06 0.41      Equipment          14C4258- RP053BC, RP053DB Rack                                              capacity and        CAL-005 anchorage RP081A      T/C SUBCOOLING          CB      2047-06 0.41      Equipment          14C4258- RP081B MONITOR CABINET                                    capacity and        CAL-005 anchorage
: 16. Generic    Block Wall Seismic Interaction CTRL 2000 All block walls on CTRL  CB      2000-00 1.17      Seismic interaction 14C4258- NB001, NK025, NG003, RP140, 2000 elev                                                            CAL-003 and RP334.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report No. ID          Description              Bldg    Elev    HCLPF2    Failure Mode        Basis    Related Components (g, PGA)  Analyzed CTRL 2016  All block walls on CTRL  CB      2016-00 0.87      Seismic interaction 14C4258- NK043, NN003, NN004, NN013, 2016 elev                                                            CAL-003 NN014, NK041, NN001, NK021, NN011, NK051, NK001, NK023, NK071, NK073, NK074 NK011, NK013, NK014, AB007, NK003, NK004, NK024 AUX 2000  2000 elev wall on      AUX    2000-00 0.67      Seismic interaction 14C4258- RP209 column line AF north of                                                CAL-003 Stair A-2 CST House  CST Pipe house          YARD    2000-00 0.40      Seismic interaction 14C4258- TAP01 masonry walls                                                          CAL-003
: 17. Generic    Cabinets containing essential relays NG003C      MCC NG03C BUS            CB      2047-06 0.32      Functional          14C4258- NG004C capacity and host CAL-005 component capacity NG002B      MCC NG02B BUS            CB      2026-00 0.40      Functional          14C4258- NG001A capacity and host CAL-005 component capacity FC0219      LOCAL CONTROL PANEL      AB      2000-00 0.41      Functional          14C4258- n/a FOR TD AFW PUMP                                    capacity and host CAL-005 component capacity 7.0    Inaccessible Items 7.1    Identification of ESEL items inaccessible for walkdowns Sufficient access was provided for all ESEL items and no additional walkdowns are planned.
8.0    ESEP Conclusions and Results 8.1    Supporting Information Callaway 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 near-term 12/2/14                                                                                                    Page 26 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 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 Callaway response to the NRCs 50.54(f) letter [1].
On March 12, 2014, NEI submitted to the NRC results of a study [14] 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 "site-specific seismic hazards show that there
[...] has not been an overall increase in seismic risk for the fleet of U.S. plants" based on the re-evaluated 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 Gl-199 safety/risk assessment. The letter also stated that, As a result, the staff has confirmed that the conclusions reached in Gl-199 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 Callaway was included in the fleet risk evaluation submitted in the March 12, 2014 NEI letter [14] therefore, the conclusions in the NRCs May 9 letter [15] also apply to Callaway.
In addition, the March 12, 2014 NEI letter [14] 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.
The fleet of currently operating nuclear power plants was designed using conservative practices, such that the plants have significant margin to withstand large ground motions safely. This has been borne out for those plants that have actually experienced significant earthquakes. The seismic design process has inherent (and intentional) conservatisms which result in significant seismic margins within SSCs. These conservatisms are reflected in several key aspects of the seismic design process, including:
* Safety factors applied in design calculations
* Damping values used in dynamic analysis of SSCs
* Bounding synthetic time histories for in-structure response spectra calculations
* Broadening criteria for in-structure response spectra
* Response spectra enveloping criteria typically used in SSC analysis and testing applications 12/2/14                                                                              Page 27 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report
* 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, and
* 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 plant specific basis, a more detailed seismic risk assessment (SPRA or risk-based SMA) is to be performed in accordance with EPRI 1025287 [16]. As identified in the Callaway Seismic Hazard and GMRS submittal [7], Callaway 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. Callaway will complete that evaluation in accordance with the schedule identified in NEIs letter dated April 9, 2013 [17]
and endorsed by the NRC in their May 7, 2013 letter [2].
8.2  Indication of Planned Modifications This report presents the seismic evaluation results for the ESEP as applied to Callaway Energy Center. A primary goal of the ESEP is to demonstrate that HCLPF seismic capacities of ESEL items exceed the RLGM seismic demand. For Callaway, the RLGM is equal to the SSE scaled-up by a 2.0 factor. The RLGM has a PGA of 0.40g at grade. Exceptions to this include the CST (TAP01) and RWST (TBN01),
which apply the GMRS (PGA of 0.50g) for HCLPF evaluation [10b].
Insights from the ESEP identified the following items (Table 8-1) where the HCLPF is below the RLGM and plant modifications will be made in accordance with EPRI 3002000704 [2] to enhance the seismic capacity of the plant.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Table 8-1: Equipment with HCLPF Capacities below the RLGM Requiring Modification 3
HCLPF Capacity ID                Description                (g, PGA)            Failure Mode NG003C              MCC NG03C BUS                  0.32            Relay functionality NG004C              MCC NG04C BUS                  0.32            Relay functionality TAP01          Condensate Storage Tank            0.30                Anchorage TBN01                  RWST                      0.33                Anchorage 8.3      Modification Implementation Schedule Plant modifications will be performed in accordance with the schedule identified in NEI letter dated April 9, 2013 [15], which states that plant modifications not requiring a planned refueling outage will be completed by December 2016 and modifications requiring a refueling outage will be completed within two planned refueling outages after December 31, 2014.
Section 8.4 contains the regulatory commitment dates to complete planned plant modifications as a result of ESEP. Referencing Section 8.4, Actions 1 and 2 do not require a refueling outage and will be completed by December 31, 2016.
Action 3 requires a refueling outage and will be completed by the end of RF21, Spring 2016, as required to support FLEX implementation. Action 4 requires a refueling outage and will be completed no later than the end of the second refueling outage after 12/31/14, currently RF22 scheduled for Fall 2017.
8.4      Summary of Regulatory Commitments The following actions will be performed as a result of the ESEP.
Completion Action #  Equipment ID    Equipment Description            Action Description              Date 1                                                Modify FLEX Support Guidelines      December 31, to include operator actions to      2016 reset relays with HCLPF values NG003C      MCC NG03C BUS              less than the RLGM.
2                                                Modify FLEX Support Guidelines      December 31, to include operator actions to      2016 reset relays with HCLPF values NG004C      MCC NG04C BUS              less than the RLGM.
3                                                Install a new hardened            End of RF21, TAP01      Condensate Storage Tank    Condensate Storage Tank.            Spring 2016 3
All HCLPFs based upon RLGM (PGA=0.40g) as the seismic margins earthquake with the exception of TAP01, TBN01, and the CST pipe house block walls, which are based upon the GMRS (PGA=0.50g).
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Completion Action # Equipment ID  Equipment Description            Action Description            Date 4                                            Three step response in order of  No later than priority: 1) Re-evaluate FLEX    the end of the response strategies to eliminate  second the need for the tank. 2) Re-    refueling analyze the tank with the more    outage after realistic median-centered        12/31/14, structural response based on the  currently RF22 new GMRS which will be            scheduled for generated once the Seismic PRA    Fall 2017 starts, 3) Upgrade/replace the TBN01      RWST                    tank.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 9.0    References
: 1.      Letter from E. J. Leeds and M. R. Johnson, USNRC, to M. W. Sunseri, WCNOC, 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, March 12, 2012.
ADAMS Accession No. ML12053A340.
: 2.      Letter from E. J. Leeds, USNRC, to J. E. Pollock, NEI, Electric Power Research Institute Final Draft Report XXXXXX, Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, May 7, 2013.
3002000704; ADAMS Accession No. ML13106A331.
: 3.      Callaway Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA-12-049.
: a.      Callaway Letter ULNRC-05962, Docket No. 50-483: Callaway Plant Unit 1 Union Electric Co. Facility Operating License NPF-30 Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), February 18, 2013, (ADAMS Accession Number ML13063A459).
: b.      Callaway Letter ULNRC-06024, Docket No. 50-483: Callaway Plant Unit 1 Union Electric Co. Facility Operating License NPF-30 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), August 29, 2013, (ADAMS Accession Number ML13242A239).
: c.      Callaway Letter ULNRC-06087, Docket No. 50-483: Callaway Plant Unit 1 Union Electric Co. Facility Operating License NPF-30 Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), February 26, 2014, (ADAMS Accession Number ML14057A770).
: d.      Callaway Letter ULNRC-06135, Docket No. 50-483: Callaway Plant Unit 1 Union Electric Co. Facility Operating License NPF-30 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-12/2/14                                                                                  Page 31 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Design-Basis External Events (Order Number EA-12-049), August 28, 2014, (ADAMS Accession Number ML13063A459).
: 4. SCP-14-82, Transmittal of Updated Callaway ESEL for ESEP Report, December 2014.
: 5. S&A report 14C4258-RPT-003 Rev. 0, Callaway ESEL Relay Assessment, December 2014.
: 6. CEC FSAR, Rev. OL-20, Callaway Energy Center Final Safety Analysis Report (FSAR). December 2013.
: 7. Callaway Seismic Hazard and GMRS submittal, dated March 31, 2014.
: 8. Electric Power Research Institute Report, NP-6041-SLR1, Revision 1, A Methodology for Assessment of Nuclear Power Plant Seismic Margin, 1991.
: 9. Electric Power Research Institute Report, TR-103959, Methodology for Developing Seismic Fragilities, 1994.
: 10. S&A Calculations:
a) 14C4258-CAL-001 Rev. 0, Generation of Scaled In-Structure Response Spectra for Callaway, December 2014.
b) 14C4258-CAL-002 Rev. 0, Seismic Capacity of CST (TAP01) and RWST (TBN01), December 2014.
c)    14C4258-CAL-003 Rev. 0, HCLPF Analyses for Block Walls, December 2014.
d) 14C4258-CAL-004 Rev. 0, HCLPF Seismic Capacity Evaluations for Selected Equipment, December 2014.
e) 14C4258-CAL-005 Rev. 0, HCLPF Analysis of Components Based on Seismic Test Data, December 2014.
f)    14C4258-RPT-002, Revision 1, Seismic Evaluation of Equipment at CEC for the Expedited Seismic Evaluation Process, December 2014.
: 11. ULNRC-3232, Callaway Plant Individual Plant Examination of External Events (IPEEE), June 1995.
: 12. Electric Power Research Institute Report, NP-5223-SL, Revision 1, Generic Seismic Ruggedness of Power Plant Equipment, 1991.
: 13. Electric Power Research Institute Technical Report, TR-1019200, Seismic Fragility Applications Guide Update, 2009.
: 14. Letter from A. R. Pietrangelo, NEI, to D. L Skeen, USNRC, Seismic Risk Estimates for Plants in the Central and Eastern United States, March 12, 2014. ADAMS Accession No. ML14083A584.
: 15. NRC (E Leeds) Letter to All Power Reactor Licensees et al., Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(F) Regarding Seismic Hazard Re-Evaluations for 12/2/14                                                                              Page 32 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Recommendation 2.1 of the Near-Term Task Force Review of Insights From the Fukushima Dai-Ichi Accident, May 9, 2014.
: 16. Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic. EPRI, Palo Alto, CA: February 2013. 1025287.
: 17. Letter from A. R. Pietrangelo, NEI, to D. L. Skeen, USNRC, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, April 9, 2013.
ADAMS Accession No. ML13107B386.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Attachment A Callaway ESEL 12/2/14                                                              Page 34 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                      Normal        Desired          Notes/Comments[1]
ID          Description Num                                        State        State Mechanical ESEL Items 1  TAP01      Condensate Storage                                CST provides AFW suction for Tank                    Operable Operable        the first 17 hours 2  PAL02      TDAFW Pump              Not                      TDAFW provides pump power Operating Operating      to move AFW to SG 3  ALHV0034  MOV                                                MOV required to isolate flow Open          Closed      path 4  ALHV0035  MOV                                                MOV required to isolate flow Open          Closed      path 5  ALPI0029  Suction Pressure Indicator 6  ALFE0049  TDAFWP Miniflow Flow Element 7  ALFI0049  TDAFWP Miniflow Flow Indicator 8  APLV0002  Level Control Valve      Open          Closed      Fail closed valve 9  ALPI0020  TDAFW Pump Discharge Pressure Indicator 10  ALHV0012  Air Operated Valve                                Valve may be operated to Open          Open        throttle AFW flow to SG 11  ALFE0004  Flow Element                                      AFW flow related hardware 12  ALFT0004  Flow Transmitter                                  AFW flow related hardware 13  ALFT0011  Flow Transmitter                                  AFW flow related hardware 14  AEFV0041  Feedwater Isolation Valve                    Open          Closed      Fail closed valve 15  ALHV0010  Air Operated Valve                                Valve may be operated to Open          Open        throttle AFW flow to SG 16  ALFE0003  Flow Element 17  ALFT0003  Flow Transmitter                                  AFW flow related hardware 18  ALFT0009  Flow Transmitter                                  AFW flow related hardware 19  AEFV0040  Feedwater Isolation Valve                    Open          Closed      Fail closed valve 20  ALHV0008  Air Operated Valve                                Valve may be operated to Open          Open        throttle AFW flow to SG 21  ALFE0002  Flow Element                                      AFW flow related hardware 22  ALFT0002  Flow Transmitter                                  AFW flow related hardware 23  ALFT0007  Flow Transmitter                                  AFW flow related hardware 12/2/14                                                                              Page 35 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL            Equipment                    Operating State Item                                        Normal        Desired          Notes/Comments[1]
ID          Description Num                                          State        State 24  AEFV0039    Feedwater Isolation Valve                    Open          Closed      Fail closed valve 25  ALHV0006    Air Operated Valve                                Valve may be operated to Open          Open        throttle AFW flow to SG 26  ALFE0001    Flow Element                                      AFW flow related hardware 27  ALFT0001    Flow Transmitter                                  AFW flow related hardware 28  AEFV0042    Feedwater Isolation Valve                    Open          Closed      Fail closed valve 29  ABHV0005    Air Operated Valve                                TDAFW controls and steam Closed        Fail Open  flow controls. Fails open.
30  ABHV0048    Air Operated Valve                    Fail        TDAFW controls and steam Open          Closed      flow controls. Fails closed.
31  ABHV0006    Air Operated Valve                                TDAFW controls and steam Closed        Fail Open  flow controls. Fails open.
32  ABHV0049    Air Operated Valve                    Fail        TDAFW controls and steam Open          Closed      flow controls. Fails closed.
33  FCPI0311    Pressure Indicator 34  FCLT0010    Level Indicator                                    Needed to prevent water intrusion in TDAFWP 35  FCFV0310    Level Control Valve                                Needed to prevent water Fail        intrusion in TDAFWP. Valve Open          Closed      fails closed.
36  FCHV0312    Trip and Throttle Valve                                              TDAFW controls and steam flow controls. Operation of this manual valve should be accounted for in operating Closed        Operating  procedures.
37  Speed      Speed Governor                                    TDAFW controls and steam Governor                            Standby      Operating  flow controls.
38  FCFV0313    Speed Governor Valve                              TDAFW controls and steam Open          Operating  flow controls.
39  KFC02      AFW Pump Turbine        Not                      TDAFW controls and steam Operating    Operating  flow controls.
40  BBPV8702A  RHR TO RCS              Closed        Open 41  EMHV8803B  MOTOR-OPERATED                                    Primary flow path, can be VALVE EMHV8803B          Closed        Open        operated manually 42  EMHV8801B  MOTOR-OPERATED                                    Primary flow path, can be VALVE EMHV8801B          Closed        Open        operated manually 12/2/14                                                                                Page 36 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL            Equipment                        Operating State Item                                          Normal      Desired        Notes/Comments[1]
ID          Description Num                                            State        State 43  EMFE0924    ECCS FLOW TO RCS COLD-LEG 1 44  EMFE0925    ECCS FLOW TO RCS COLD-LEG 2 45  EMFE0926    ECCS FLOW TO RCS COLD-LEG 3 46  EMFE0927    ECCS FLOW TO RCS COLD-LEG 4 47  TBN01      RWST                                                Secondary source for core makeup after BAT exhausted 48  BNLT0930    RWST Level Transmitter                                        Monitor RWST level 49  EJHCV0606  RHR Heat Exchanger A Outlet Isolation Valve    Fail Open    Closed      Can be operated manually 50  TBG03A      Boric Acid Tank 51  BGLT0102    BORIC ACID TANK A LEV                                                Monitor BAT level 52  BGLI0102    BORIC ACID TANK A LEV                                                Local level indicator 53  EJFCV0610  RHR Pump A miniflow Valve                      Open        Closed 54  EJFCV0610  RHR Pump A miniflow Valve                      Open        Closed 55  EJFCV0610  RHR Pump A miniflow Valve                      Open        Closed Electrical ESEL Items 56  NB001      4.16KV SWGR NB001 This component is powered by (Class 1E, Train A) the FLEX DG in Phase 3 as stated in Sec. 8 of the Callaway N/A          N/A        Plant FLEX Integrated Plan 57  NB00101    4.16 kV FDR BKR FOR This component is powered by RHRP-A DPEJ01A the FLEX DG in Phase 3 as (Residual Heat stated in Sec. 8 of the Callaway Removal Pump A)
N/A          N/A        Plant FLEX Integrated Plan 58  NB00107    4.16 kV FDR BKR FOR This component is powered by CCWP-A DPEG01A the FLEX DG in Phase 3 as (Component Cooling stated in Sec. 8 of the Callaway Water Pump A)
N/A          N/A        Plant FLEX Integrated Plan 12/2/14                                                                                Page 37 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                      Normal        Desired          Notes/Comments[1]
ID          Description Num                                        State        State 59  NB00109  4.16 kV FLEX GEN (Phase 3) TIE-IN POINT This breaker position is the tie-(BKR) FOR TRAIN A in point for the Phase 3 FLEX N/A          N/A        diesel generator 60  NB00113  4.16 kV FDR BKR FOR This component is powered by XFMR XNG01 (4160 V the FLEX DG in Phase 3 as to 480 V for LC stated in Sec. 8 of the Callaway NG001)
N/A          N/A        Plant FLEX Integrated Plan 61  XNG01    4.16-KV/480 V LOAD This component is powered by CENTER the FLEX DG in Phase 3 as TRANSFORMER stated in Sec. 8 of the Callaway XNG01 FOR LC NG001 N/A          N/A        Plant FLEX Integrated Plan 62  NG001    480 V LOAD CENTER                                  This component is powered by NG01                                              the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 63  NG00101  MAIN BKR FOR LC This component is powered by NG01 the FLEX DG in Phase 3 as stated in Sec. 8 of the Callaway N/A          N/A        Plant FLEX Integrated Plan 64  NG00103  FDR BKR FOR 125 V                                  This component is powered by VITAL BATTERY                                      the FLEX DG, first Phase 2, CHARGER NK021                                      then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 65  NG00112  FLEX 500 kW TIE IN This component is powered by BRK (Phase 2 the FLEX DG in Phase 2 as connection point) stated in Sec. 8 of the Callaway N/A          N/A        Plant FLEX Integrated Plan 66  NG00116  TIE BKR (CONNECTS                                  This component is powered by NG01 AND NG03)                                    the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 67  NG003    480 V LOAD CENTER                                  This component is powered by NG03                                              the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 12/2/14                                                                              Page 38 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                  Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 68  NG00303  FDR BKR FOR 125 V                                This component is powered by VITAL BATTERY                                    the FLEX DG, first Phase 2, CHARGER NK023                                    then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 69  NK021    125 V BATTERY                                    This component is powered by CHARGER NK021                                    the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 70  NK071    TRANSFER SWITCH                                  This component is powered by BUS NK01 BATTERY                                the FLEX DG, first Phase 2, CHARGER NK21/NK25                                then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 71  NK001    125 VDC BUS                                      This component is powered SWITCHBOARD NK001                                during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 72  NK00102  FDR BKR FROM BATT                                This component is powered by CHGR NK021 TO                                    the FLEX DG, first Phase 2, NK001                                            then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 73  NK00104  MAIN BREAKER FOR                                This component is powered CNTRL AND DIST PNL                              during ALL phases of the FLEX NK041 (PART OF                                  strategy as stated in Sec. 8 of SWBD NK001)                                      the Callaway Plant FLEX N/A          N/A        Integrated Plan 74  NK00105  MAIN BREAKER FOR                                This component is powered CNTRL AND DIST PNL                              during ALL phases of the FLEX NK051 (PART OF                                  strategy as stated in Sec. 8 of SWBD NK001)                                      the Callaway Plant FLEX N/A          N/A        Integrated Plan 75  NK011    125 V BATTERY NK011                              This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                            Page 39 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL            Equipment                    Operating State Item                                        Normal        Desired          Notes/Comments[1]
ID            Description Num                                          State        State 76  NK00101    ISOLATION BKR FOR                                  This component is powered BATTERY NK011                                      during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 77  NK00111    FDR BKR FOR                                        This component is powered INVERTER NN011                                    during ALL phases of the FLEX (PART OF SWBD                                      strategy as stated in Sec. 8 of NK001)                                            the Callaway Plant FLEX N/A          N/A        Integrated Plan 78  NN011      7.5KVA INVERTER                                    This component is powered (FED FROM BATT                                    during ALL phases of the FLEX CHARGER NK021)                                    strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 79  NN001      Class 1E AC DIST                                  This component is powered SWBD NN01 (SEP GRP                                during ALL phases of the FLEX
: 1)                                                strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 80  SA066A      STATUS INDICATING                                  This component is powered SYS                                                during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 81  SENY0060A  NEUTRON FLUX                                      This component is powered MONITORING SYSTEM                                  during ALL phases of the FLEX DETECTOR AMPLIFIER                                strategy as stated in Sec. 8 of SENY 60A                                          the Callaway Plant FLEX N/A          N/A        Integrated Plan 82  SENY0060B  NEUTRON FLUX                                      This component is powered MONITORING SYSTEM                                  during ALL phases of the FLEX DETECTOR AMPLIFIER                                strategy as stated in Sec. 8 of SENY 60B                                          the Callaway Plant FLEX N/A          N/A        Integrated Plan 83  SB038      W PROCESS ANALOG                                  This component is powered PROTECTION SET CAB-                                during ALL phases of the FLEX 01                                                strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                                Page 40 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 84  SE054A    W NUC INSTM NIS 1                                This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 85  RP053AC  BOP                                              This component is powered INSTRUMENTATION                                  during ALL phases of the FLEX RACK (TERMINATION                                strategy as stated in Sec. 8 of AREA)                                            the Callaway Plant FLEX N/A          N/A        Integrated Plan 86  SB078    RPV LEVEL INSTR SYS                              This component is powered (RVLIS) PROC PROT                                during ALL phases of the FLEX SYS CABINET                                      strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 87  RP081A    T/C SUBCOOLING                                    This component is powered MONITOR CABINET                                  during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 88  NK041    CNTRL & INSTR DIST                                This component is powered SWBD NK041 (CLASS                                during ALL phases of the FLEX 1E 125 VDC)                                      strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 89  NE107    DIESEL GEN PNL                                    This component is powered NE107 & FIELD                                    during ALL phases of the FLEX FLASHING                                          strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 90  RL005    TURBINE GENERATOR                                This component is powered AND FW CONSOLE                                    during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 91  RL006    TURBINE GENERATOR                                This component is powered AND FW CONSOLE                                    during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                            Page 41 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL        Equipment                    Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 92  RP315    DC DIST PNL RP315                                This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 93  RL023    TURBINE GENERATOR                                This component is powered AND FW MCB                                        during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 94  RL024    TURBINE GENERATOR                                This component is powered AND FW MCB                                        during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 95  RL017    ESF MCB                                          This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 96  RL018    ESF MCB                                          This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 97  RL019    ESF MCB                                          This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 98  RL020    ESF MCB                                          This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 99  RL001    REACTOR COOLANT                                  This component is powered AND SUPT SYS                                      during ALL phases of the FLEX CONSOLE                                          strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                            Page 42 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL            Equipment                  Operating State Item                                      Normal        Desired          Notes/Comments[1]
ID          Description Num                                        State        State 100  RL002      REACTOR COOLANT                                  This component is powered AND SUPT SYS                                    during ALL phases of the FLEX CONSOLE                                          strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 101  RL025      TURBINE GENERATOR                                This component is powered AND FW MCB                                      during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 102  RL026      TURBINE GENERATOR                                This component is powered AND FW MCB                                      during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 103  RP317      FUSED 125 VDC DIST                              This component is powered PNL RP317                                        during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 104  NK051      CNTRL & INSTR DIST                              This component is powered SWBD NK051 (CLASS                                during ALL phases of the FLEX 1E 125 VDC)                                      strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 105  BBPCV0455A BBPCV0455A PORV                                  This component is powered SOLENOID FAILS TO                                during ALL phases of the FLEX OPEN ON DEMAND                                  strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 106  RL021      REACTOR AUX CNTRL                                This component is powered PANEL                                            during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 107  RL022      REACTOR AUX CNTRL                                This component is powered PANEL                                            during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                              Page 43 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 108  KJ0121    DIESEL GAUGE AND                                  This component is powered CONTROL PANEL                                    during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 109  RP209    B AUXILIARY RELAY                                This component is powered RACK                                              during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 110  RP289    DC DIST PNL RP289                                This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 111  RP068    MISC BOP                                          This component is powered INSTRUMENT RACK                                  during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 112  RP330    AUX RELAY RACK                                    This component is powered RP330                                            during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 113  RP332    B AUXILIARY RELAY                                This component is powered RACK                                              during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 114  NK051A    EM'CY LIGHTING DIST                              This component is powered SWBD NK051A                                      during ALL phases of the FLEX (SUBPNL OF NK051)                                strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 115  NK023    125 V BATTERY                                    This component is powered by CHARGER NK023                                    the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 12/2/14                                                                            Page 44 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 116  NK073    TRANSFER SWITCH                                  This component is powered by BUS NK03 BATTERY                                  the FLEX DG, first Phase 2, CHARGER NK23/NK25                                then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 117  NK003    125 VDC BUS                                      This component is powered SWITCHBOARD NK003                                during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 118  NK00302  FDR BKR FROM BATT                                This component is powered by CHGR NK023 TO                                    the FLEX DG, first Phase 2, NK003                                            then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 119  NK00304  MAIN BREAKER FOR                                  This component is powered CNTRL AND DIST PNL                                during ALL phases of the FLEX NK043 (PART OF                                    strategy as stated in Sec. 8 of SWBD NK003)                                      the Callaway Plant FLEX N/A          N/A        Integrated Plan 120  NK013    125 V BATTERY NK013                              This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 121  NK00301  ISOLATION BKR FOR                                This component is powered BATTERY NK013                                    during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 122  NK00311  FDR BKR FOR                                      This component is powered INVERTER NN013                                    during ALL phases of the FLEX (PART OF SWBD                                    strategy as stated in Sec. 8 of NK003)                                            the Callaway Plant FLEX N/A          N/A        Integrated Plan 123  NN013    7.5KVA INVERTER                                  This component is powered (FED FROM BATT                                    during ALL phases of the FLEX CHARGER NK023)                                    strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                            Page 45 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                      Normal        Desired          Notes/Comments[1]
ID          Description Num                                        State        State 124  NN003    Class 1E AC DIST                                  This component is powered SWBD NN03 (SEP GRP                                during ALL phases of the FLEX
: 3)                                                strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 125  RP053DB  BOP INSTR RACK                                    This component is powered RP053DB                                            during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 126  SB037    W PROCESS ANALOG                                  This component is powered PROTECTION SET CAB-                                during ALL phases of the FLEX 03                                                strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 127  SE054C    W NUC INSTM NIS 3                                  This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 128  NK043    CNTRL & INSTR DIST                                This component is powered SWBD NK043 (CLASS                                  during ALL phases of the FLEX 1E 125 VDC)                                        strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 129  AB007    Aux Relay Rack                                    This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 130  NG00109  FDR BKR FOR 125 V SWING BATTERY This component provides CHARGER NK025 power to NK025 and, in turn, N/A          N/A        Separation Group 1.
131  NK025    125 V BATTERY CHARGER NK025 The A-Train swing charger will (Swing Battery be used to power Separation Charger)
N/A          N/A        Group 1.
132  NG002    480 V LOAD CENTER                                  This component is powered by NG02                                              the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 12/2/14                                                                              Page 46 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 133  NG00212  FLEX 500 kW TIE IN                                This component is powered by BKR from FD201                                    the FLEX DG, first Phase 2, (Phase 2 connection                              then in Phase 3, as stated in point)                                            Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 134  NG00203  FDR BKR FOR 125 V                                This component is powered by VITAL BATTERY                                    the FLEX DG, first Phase 2, CHARGER NK024                                    then in Phase 3, as stated in Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 135  NK024    125 V BATTERY                                    This component is powered by CHARGER NK024                                    the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 136  NK074    TRANSFER SWITCH                                  This component is powered by BUS NK04 BATTERY                                  the FLEX DG, first Phase 2, CHARGER NK24/NK26                                then in Phase 3, as stated in Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 137  NK004    125 VDC BUS                                      This component is powered SWITCHBOARD NK004                                during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 138  NK00402  FDR BKR FROM BATT                                This component is powered by CHGR NK024 TO                                    the FLEX DG, first Phase 2, NK004                                            then in Phase 3, as stated in Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 139  NK014    125 V BATTERY NK014                              This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 140  NK00401  ISOLATION BKR FOR                                This component is powered BATTERY NK014                                    during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 12/2/14                                                                            Page 47 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL            Equipment                    Operating State Item                                        Normal        Desired          Notes/Comments[1]
ID            Description Num                                          State        State 141  NK00411    FDR BKR FOR                                        This component is powered INVERTER NN011                                    during ALL phases of the FLEX (PART OF SWBD                                      strategy as stated in Sec. 8 of NK004)                                            the Callaway Integrated FLEX N/A          N/A        Plan 142  NN014      7.5KVA INVERTER                                    This component is powered (FED FROM BATT                                    during ALL phases of the FLEX CHARGER NK024)                                    strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 143  NN004      Class 1E AC DIST                                  This component is powered SWBD NN04 (SEP GRP                                during ALL phases of the FLEX
: 4)                                                strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 144  RP147B      BOP Instrumentation                                This component is powered Rack RP147B                                        during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 145  SENY0061A  NEUTRON FLUX                                      This component is powered MONITORING SYSTEM                                  during ALL phases of the FLEX DETECTOR AMPLIFIER                                strategy as stated in Sec. 8 of SENY 61A                                          the Callaway Integrated FLEX N/A          N/A        Plan 146  SENY0061B  NEUTRON FLUX                                      This component is powered MONITORING SYSTEM                                  during ALL phases of the FLEX DETECTOR AMPLIFIER                                strategy as stated in Sec. 8 of SENY 61B                                          the Callaway Integrated FLEX N/A          N/A        Plan 147  SE054D      W NUC INSTM NIS 4                                  This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 148  SB041      W PROCESS ANALOG                                  This component is powered PROTECTION SET CAB-                                during ALL phases of the FLEX 04                                                strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 12/2/14                                                                                Page 48 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                      Operating State Item                                      Normal        Desired          Notes/Comments[1]
ID          Description Num                                        State        State 149  RP053BC  BOP Instrumentation                                This component is powered Rack RP053BC                                        during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 150  SB079    RVLIS Process Cabinet                              This component is powered SB079                                              during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 151  RP081B    Subcooling Monitor                                  This component is powered Cabinet                                            during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 152  SB148B    W PROCESS                                          This component is powered PROTECTION (Fire                                    during ALL phases of the FLEX Isolation)                                          strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 153  SA066B    STATUS INDICATING                                  This component is powered SYS                                                during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 154  RP140    PANEL RP140                                        This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 12/2/14                                                                              Page 49 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Attachment B ESEP HCLPF Values and Failure Modes Tabulation HCLPF values are listed in Table B-1. These notes are applicable:
: 1. The listed HCLPF value is for comparison to the horizontal PGA at the bedrock surface.
: 2. Items covered by the NP-6041-SL rule of the box (ROB) are identified in Table A-2 [9].
In each case, the HCLPF value for the parent item applies.
: 3. For the CST and RWST only (TAP01 and TBN01, respectively), the applied ground motion was based on the GMRS (PGA = 0.50g).
: 4. Where an anchorage HCLPF is performed but the component per se is screened, the equipment capacity is assigned based upon the 1.2g peak spectral acceleration coinciding with the 2nd screening lane of NP-6041-SL. Since the Callaway RLGM has a peak spectral acceleration of 1.2g in the building frequency range of interest (see Section 6.2.1) and PGA of 0.40g [Ref. 7], the equipment capacity is assigned as 0.40g PGA.
: 5. As a result of the relay chatter evaluation, additional items were added to the ESEL list for evaluation.
12/2/14                                                                                Page 50 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Table B-1: ESEL HCLPF Values ESEL Item      ID        Description    Bldg    Elev      HCLPF          Failure Mode                                Basis Number Condensate Storage                                                        Tank capacity evaluated in 14C4258-CAL-002. Block wall 1    TAP01                        YARD  2000-00      0.3            Anchorage Tank                                                                        evaluated per 14C4258-CAL-003.
Component per se screened. Anchorage evaluated per 2    PAL02      TDAFW Pump      AUX    2000-00      0.4        Equipment Capacity 14C4258-CAL-004.
3  ALHV0034          MOV        AUX    1988-00    >RLGM            Screened                              SRT disposition 4  ALHV0035          MOV        AUX    1988-00    >RLGM            Screened                              SRT disposition Suction Pressure 5  ALPI0029                      AUX    2000-00    >RLGM            Screened                              SRT disposition Indicator TDAFWP Miniflow Flow 6  ALFE0049                      AUX    2000-00    >RLGM            Screened                              SRT disposition Element TDAFWP Miniflow Flow 7  ALFI0049                      AUX    2000-00    >RLGM            Screened                              SRT disposition Indicator 8  APLV0002  Level Control Valve YARD  2000-00    >RLGM            Screened                              SRT disposition TDAFW Pump Discharge 9  ALPI0020                      AUX    2000-00    >RLGM            Screened                              SRT disposition Pressure Indicator 10  ALHV0012  Air Operated Valve  AUX    2004-07    >RLGM            Screened                              SRT disposition 11  ALFE0004      Flow Element    AUX    2000-00    >RLGM            Screened                              SRT disposition 12  ALFT0004    Flow Transmitter  AUX    2016-01    >RLGM            Screened                              SRT disposition 13  ALFT0011    Flow Transmitter  AUX    2000-00    >RLGM            Screened                              SRT disposition Feedwater Isolation 14  AEFV0041                      AUX    2028-00    >RLGM            Screened                              SRT disposition Valve 15  ALHV0010  Air Operated Valve  AUX    2002-09    >RLGM            Screened                              SRT disposition 16  ALFE0003      Flow Element    AUX    2000-00    >RLGM            Screened                              SRT disposition 17  ALFT0003    Flow Transmitter  AUX    2016-00    >RLGM            Screened                              SRT disposition 18  ALFT0009    Flow Transmitter  AUX    2000-00    >RLGM            Screened                              SRT disposition Feedwater Isolation 19  AEFV0040                      AUX    2027-10    >RLGM            Screened                              SRT disposition Valve 20  ALHV0008  Air Operated Valve  AUX    2004-00    >RLGM            Screened                              SRT disposition 12/2/14                                                                            Page 51 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item          ID            Description      Bldg    Elev      HCLPF          Failure Mode                                  Basis Number 21      ALFE0002          Flow Element      AUX    2000-00    >RLGM            Screened                              SRT disposition 22      ALFT0002      Flow Transmitter    AUX    2016-00    >RLGM            Screened                              SRT disposition 23      ALFT0007      Flow Transmitter    AUX    2000-00    >RLGM            Screened                              SRT disposition Feedwater Isolation 24      AEFV0039                            AUX    2028-00    >RLGM            Screened                              SRT disposition Valve 25      ALHV0006      Air Operated Valve    AUX    2001-06    >RLGM            Screened                              SRT disposition 26      ALFE0001          Flow Element      AUX    2000-00    >RLGM            Screened                              SRT disposition 27      ALFT0001      Flow Transmitter    AUX    2015-00    >RLGM            Screened                              SRT disposition Feedwater Isolation 28      AEFV0042                            AUX    2027-10    >RLGM            Screened                              SRT disposition Valve 29      ABHV0005      Air Operated Valve    AUX    2027-10    >RLGM            Screened                              SRT disposition 30      ABHV0048      Air Operated Valve    AUX    2027-10    >RLGM            Screened                              SRT disposition 31      ABHV0006      Air Operated Valve    AUX    2027-10    >RLGM            Screened                              SRT disposition 32      ABHV0049      Air Operated Valve    AUX    2027-10    >RLGM            Screened                              SRT disposition 33      FCPI0311      Pressure Indicator  AUX    2000-00    >RLGM            Screened                              SRT disposition 34      FCLT0010        Level Indicator    AUX    2000-00    >RLGM            Screened                              SRT disposition 35      FCFV0310      Level Control Valve  AUX    1988-00    >RLGM            Screened                              SRT disposition 36      FCHV0312    Trip and Throttle Valve AUX    2000-00    >RLGM            Screened                              SRT disposition Item is ROB to PAL02. Component per se screened. Anchorage 37  Speed Governor    Speed Governor      AUX    2000-00      0.4        Equipment Capacity evaluated per 14C4258-CAL-004.
Item is ROB to PAL02. Component per se screened. Anchorage 38      FCFV0313    Speed Governor Valve    AUX    2000-00      0.4        Equipment Capacity evaluated per 14C4258-CAL-004.
Item is ROB to PAL02. Component per se screened. Anchorage 39        KFC02      AFW Pump Turbine      AUX    2000-00      0.4        Equipment Capacity evaluated per 14C4258-CAL-004.
40    BBPV8702A          RHR TO RCS        RB    2007-09    >RLGM            Screened                              SRT disposition MOTOR-OPERATED 41    EMHV8803B                            AUX    1975-08    >RLGM            Screened                              SRT disposition VALVE EMHV8803B MOTOR-OPERATED 42    EMHV8801B                            AUX    2002-00    >RLGM            Screened                              SRT disposition VALVE EMHV8801B 12/2/14                                                                                    Page 52 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item        ID          Description      Bldg    Elev      HCLPF          Failure Mode                                  Basis Number ECCS FLOW TO RCS 43  EMFE0924                            RB    1998-06    >RLGM            Screened                                SRT disposition COLD-LEG 1 ECCS FLOW TO RCS 44  EMFE0925                            RB    1998-06    >RLGM            Screened                                SRT disposition COLD-LEG 2 ECCS FLOW TO RCS 45  EMFE0926                            RB    1998-06    >RLGM            Screened                                SRT disposition COLD-LEG 3 ECCS FLOW TO RCS 46  EMFE0927                            RB    1998-06    >RLGM            Screened                                SRT disposition COLD-LEG 4 47      TBN01              RWST        YRD    2000-00      0.33          Anchorage                Tank capacity evaluated in 14C4258-CAL-002.
48  BNLT0930  RWST Level Transmitter  YRD    1993-00    >RLGM            Screened                                SRT disposition RHR Heat Exchanger A 49  EJHCV0606                          AUX    2001-06    >RLGM            Screened                                SRT disposition Outlet Isolation Valve 50    TBG03A        Boric Acid Tank  AUX    1974-00    >RLGM            Screened                                SRT disposition 51  BGLT0102  BORIC ACID TANK A LEV    AUX    1968-01    >RLGM            Screened                                SRT disposition Item is ROB to RL001. Component per se screened. Anchorage 52    BGLI0102 BORIC ACID TANK A LEV    CB    2047-06      0.4      Equipment Capacity evaluated per 14C4258-CAL-004.
RHR Pump A miniflow 53  EJFCV0610                          AUX    1968-01    >RLGM            Screened                                SRT disposition Valve Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 4.16KV SWGR NB001 56      NB001                            CB    2000-00      0.41          Anchorage          evaluated per 14C4258-CAL-005 Block wall evaluated per (Class 1E, Train A) 14C4258-CAL-003.
4.16 kV FDR BKR FOR Item is ROB to NB001. Equipment capacity evaluated in RHRP-A DPEJ01A 57    NB00101                            CB    2000-00      0.41          Anchorage          14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-(Residual Heat Removal 005. Block wall evaluated per 14C4258-CAL-003.
Pump A) 4.16 kV FDR BKR FOR Item is ROB to NB001. Equipment capacity evaluated in CCWP-A DPEG01A 58    NB00107                            CB    2000-00      0.41          Anchorage          14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-(Component Cooling 004. Block wall evaluated per 14C4258-CAL-003.
Water Pump A) 4.16 kV FLEX GEN                                                            Item is ROB to NB001. Equipment capacity evaluated in 59    NB00109  (Phase 3) TIE-IN POINT  CB    2000-00      0.41          Anchorage          14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-(BKR) FOR TRAIN A                                                              004. Block wall evaluated per 14C4258-CAL-003.
4.16 kV FDR BKR FOR                                                            Item is ROB to NB001. Equipment capacity evaluated in 60    NB00113  XFMR XNG01 (4160 V to    CB    2000-00      0.41          Anchorage          14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-480 V for LC NG001)                                                              004. Block wall evaluated per 14C4258-CAL-003.
12/2/14                                                                                Page 53 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item      ID          Description    Bldg    Elev      HCLPF          Failure Mode                                  Basis Number 4.16-KV/480 V LOAD Component per se screened. Anchorage evaluated per 61    XNG01  CENTER TRANSFORMER    CB/CC  2000-00      0.4      Equipment Capacity 14C4258-CAL-004.
XNG01 FOR LC NG001 480 V LOAD CENTER                                                        Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 62    NG001                        CB/CC  2000-00      0.41          Anchorage NG01                                                                            evaluated per 14C4258-CAL-005.
Item is ROB to NG001. Equipment capacity evaluated in 63  NG00101 MAIN BKR FOR LC NG01    CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-004.
FDR BKR FOR 125 V                                                          Item is ROB to NG001. Equipment capacity evaluated in 64  NG00103      VITAL BATTERY      CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHARGER NK021                                                                                      004.
FLEX 350 kW TIE IN BRK                                                        Item is ROB to NG001. Equipment capacity evaluated in 65  NG00112    (Alternate Phase 2  CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-connection point)                                                                                    004.
Item is ROB to NG001. Equipment capacity evaluated in TIE BKR (CONNECTS 66  NG00116                          CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NG01 AND NG03) 005.
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 480 V LOAD CENTER 67    NG003                        CB/CC  2000-00      0.41          Anchorage          evaluated per 14C4258-CAL-005. Block wall evaluated per NG03 14C4258-CAL-003.
FDR BKR FOR 125 V                                                          Item is ROB to NG003. Equipment capacity evaluated in 68  NG00303      VITAL BATTERY      CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHARGER NK023                                                                005. Block wall evaluated per 14C4258-CAL-003.
125 V BATTERY                                                            Component per se screened. Anchorage evaluated per 69    NK021                        CB/CC  2016-00      0.4      Equipment Capacity CHARGER NK021                                                          14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
TRANSFER SWITCH BUS Component per se screened. Block wall evaluated per 70    NK071        NK01 BATTERY      CB    2016-00      0.4      Equipment Capacity 14C4258-CAL-003.
CHARGER NK21/NK25 Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 125 VDC BUS 71    NK001                        CB/CC  2016-00      0.71          Anchorage          evaluated per 14C4258-CAL-004. Block wall evaluated per SWITCHBOARD NK001 14C4258-CAL-003.
Item is ROB to NK001. Equipment capacity evaluated in FDR BKR FROM BATT 72  NK00102                          CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHGR NK021 TO NK001 004. Block wall evaluated per 14C4258-CAL-003.
MAIN BREAKER FOR Item is ROB to NK001. Equipment capacity evaluated in CNTRL AND DIST PNL 73  NK00104                          CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NK041 (PART OF SWBD 004. Block wall evaluated per 14C4258-CAL-003.
NK001) 12/2/14                                                                            Page 54 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item        ID          Description      Bldg    Elev      HCLPF          Failure Mode                                  Basis Number MAIN BREAKER FOR Item is ROB to NK001. Equipment capacity evaluated in CNTRL AND DIST PNL 74    NK00105                          CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NK051 (PART OF SWBD 004. Block wall evaluated per 14C4258-CAL-003.
NK001)
Component per se screened. Anchorage evaluated per 75    NK011    125 V BATTERY NK011  CB/CC  2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
Item is ROB to NK001. Equipment capacity evaluated in ISOLATION BKR FOR 76    NK00101                          CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-BATTERY NK011 004. Block wall evaluated per 14C4258-CAL-003.
FDR BKR FOR INVERTER                                                          Item is ROB to NK001. Equipment capacity evaluated in 77    NK00111  NN011 (PART OF SWBD      CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NK001)                                                                  004. Block wall evaluated per 14C4258-CAL-003.
7.5KVA INVERTER (FED Component per se screened. Anchorage evaluated per 78    NN011    FROM BATT CHARGER    CB/CC  2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
NK021)
Class 1E AC DIST SWBD                                                          Component per se screened. Anchorage evaluated per 79    NN001                          CB/CC  2016-00      0.4      Equipment Capacity NN01 (SEP GRP 1)                                                        14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 80    SA066A  STATUS INDICATING SYS    CB    2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
NEUTRON FLUX MONITORING SYSTEM 81  SENY0060A                        AUX    2026-00    >RLGM            Screened                              SRT disposition DETECTOR AMPLIFIER SENY 60A NEUTRON FLUX MONITORING SYSTEM 82  SENY0060B                        AUX    2026-00    >RLGM            Screened                              SRT disposition DETECTOR AMPLIFIER SENY 60B W PROCESS ANALOG Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 83      SB038  PROTECTION SET CAB-  CB/CC  2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
01 Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 84    SE054A    W NUC INSTM NIS 1    CB/CC  2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
BOP INSTRUMENTATION                                                          Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 85    RP053AC                          CB    2047-06      0.41          Anchorage RACK (TERMINATION                                                                      evaluated per 14C4258-CAL-005.
AREA)
RPV LEVEL INSTR SYS Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 86      SB078  (RVLIS) PROC PROT SYS    CB    2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
CABINET 12/2/14                                                                              Page 55 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item      ID        Description        Bldg        Elev      HCLPF          Failure Mode                                Basis Number T/C SUBCOOLING                                                              Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 87    RP081A                            CB      2047-06      0.41          Anchorage MONITOR CABINET                                                                            evaluated per 14C4258-CAL-005.
CNTRL & INSTR DIST Component per se screened. Anchorage evaluated per 88    NK041  SWBD NK041 (CLASS 1E    CB/CC      2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
125 VDC)
DIESEL GEN PNL NE107 89    NE107                            DGB      2000-00    >RLGM            Screened                            SRT disposition
                  & FIELD FLASHING TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 90    RL005                            CB      2047-06      0.4      Equipment Capacity AND FW CONSOLE                                                                                    14C4258-CAL-004.
TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 91    RL006                            CB      2047-06      0.4      Equipment Capacity AND FW CONSOLE                                                                                    14C4258-CAL-004.
92    RP315    DC DIST PNL RP315 ESW Pumphouse  2000-00    >RLGM            Screened                            SRT disposition TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 93    RL023                            CB      2047-06      0.4      Equipment Capacity AND FW MCB                                                                                    14C4258-CAL-004.
TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 94    RL024                            CB      2047-06      0.4      Equipment Capacity AND FW MCB                                                                                    14C4258-CAL-004.
Component per se screened. Anchorage evaluated per 95    RL017        ESF MCB            CB      2047-06      0.4      Equipment Capacity 14C4258-CAL-004.
Component per se screened. Anchorage evaluated per 96    RL018        ESF MCB            CB      2047-06      0.4      Equipment Capacity 14C4258-CAL-004.
Component per se screened. Anchorage evaluated per 97    RL019        ESF MCB            CB      2047-06      0.4      Equipment Capacity 14C4258-CAL-004.
Component per se screened. Anchorage evaluated per 98    RL020        ESF MCB            CB      2047-06      0.4      Equipment Capacity 14C4258-CAL-004.
REACTOR COOLANT                                                                  Component per se screened. Anchorage evaluated per 99    RL001                            CB      2047-06      0.4      Equipment Capacity AND SUPT SYS CONSOLE                                                                                14C4258-CAL-004.
REACTOR COOLANT                                                                  Component per se screened. Anchorage evaluated per 100    RL002                            CB      2047-06      0.4      Equipment Capacity AND SUPT SYS CONSOLE                                                                                14C4258-CAL-004.
TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 101    RL025                            CB      2047-06      0.4      Equipment Capacity AND FW MCB                                                                                    14C4258-CAL-004.
TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 102    RL026                            CB      2047-06      0.4      Equipment Capacity AND FW MCB                                                                                    14C4258-CAL-004.
FUSED 125 VDC DIST 103    RP317                          UHS      2000-00    >RLGM            Screened                            SRT disposition PNL RP317 12/2/14                                                                                  Page 56 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item        ID          Description    Bldg    Elev      HCLPF          Failure Mode                                  Basis Number CNTRL & INSTR DIST Component per se screened. Anchorage evaluated per 104    NK051    SWBD NK051 (CLASS 1E CB/CC  2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
125 VDC)
BBPCV0455A PORV 105  BBPCV0455A    SOLENOID FAILS TO  RB    2070-00    >RLGM            Screened                                SRT disposition OPEN ON DEMAND REACTOR AUX CNTRL                                                            Component per se screened. Anchorage evaluated per 106      RL021                          CB    2047-06      0.4      Equipment Capacity PANEL                                                                                  14C4258-CAL-004.
REACTOR AUX CNTRL                                                            Component per se screened. Anchorage evaluated per 107      RL022                          CB    2047-06      0.4      Equipment Capacity PANEL                                                                                  14C4258-CAL-004.
DIESEL GAUGE AND 108    KJ0121                        DGB    2000-00    >RLGM            Screened                                SRT disposition CONTROL PANEL B AUXILIARY RELAY                                                          Component per se screened. Block wall evaluated per 109      RP209                        AUX    2000-00      0.4      Equipment Capacity RACK                                                                                  14C4258-CAL-003.
110      RP289      DC DIST PNL RP289  AUX    2047-06    >RLGM            Screened                                SRT disposition MISC BOP INSTRUMENT                                                      Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 111      RP068                          CB    2047-06      0.41          Anchorage RACK                                                                          evaluated per 14C4258-CAL-005.
112      RP330  AUX RELAY RACK RP330  AUX    2000-00    >RLGM            Screened                                SRT disposition B AUXILIARY RELAY 113      RP332                        AUX    2000-00    >RLGM            Screened                                SRT disposition RACK EM'CY LIGHTING DIST                                                    Item is ROB to NK051. Component per se screened. Anchorage 114    NK051A  SWBD NK051A (SUBPNL    CB    2016-00      0.4        Equipment Capacity    evaluated per 14C4258-CAL-004. Block wall evaluated per OF NK051)                                                                                14C4258-CAL-003.
125 V BATTERY                                                            Component per se screened. Anchorage evaluated per 115    NK023                        CB/CC  2016-00      0.4      Equipment Capacity CHARGER NK023                                                        14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
TRANSFER SWITCH BUS Component per se screened. Block wall evaluated per 116    NK073        NK03 BATTERY      CB    2016-00      0.4      Equipment Capacity 14C4258-CAL-003.
CHARGER NK23/NK25 Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 125 VDC BUS 117    NK003                        CB/CC  2016-00      0.71          Anchorage          evaluated per 14C4258-CAL-004. Block wall evaluated per SWITCHBOARD NK003 14C4258-CAL-003.
Item is ROB to NK003. Equipment capacity evaluated in FDR BKR FROM BATT 118    NK00302                          CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHGR NK023 TO NK003 004. Block wall evaluated per 14C4258-CAL-003.
12/2/14                                                                              Page 57 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item      ID        Description    Bldg    Elev      HCLPF          Failure Mode                                  Basis Number MAIN BREAKER FOR Item is ROB to NK003. Equipment capacity evaluated in CNTRL AND DIST PNL 119  NK00304                        CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NK043 (PART OF SWBD 004. Block wall evaluated per 14C4258-CAL-003.
NK003)
Component per se screened. Anchorage evaluated per 120    NK013  125 V BATTERY NK013  CB/CC  2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
Item is ROB to NK003. Equipment capacity evaluated in ISOLATION BKR FOR 121  NK00301                        CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-BATTERY NK013 004. Block wall evaluated per 14C4258-CAL-003.
FDR BKR FOR INVERTER                                                          Item is ROB to NK003. Equipment capacity evaluated in 122  NK00311 NN013 (PART OF SWBD    CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NK003)                                                                  004. Block wall evaluated per 14C4258-CAL-003.
7.5KVA INVERTER (FED Component per se screened. Anchorage evaluated per 123    NN013  FROM BATT CHARGER    CB/CC  2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
NK023)
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage Class 1E AC DIST SWBD 124    NN003                        CB/CC  2016-00      0.71          Anchorage          evaluated per 14C4258-CAL-004. Block wall evaluated per NN03 (SEP GRP 3) 14C4258-CAL-003.
BOP INSTR RACK                                                        Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 125  RP053DB                        CB    2047-06      0.41          Anchorage RP053DB                                                                          evaluated per 14C4258-CAL-005.
W PROCESS ANALOG Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 126    SB037  PROTECTION SET CAB-  CB/CC  2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
03 Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 127    SE054C  W NUC INSTM NIS 3  CB/CC  2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
CNTRL & INSTR DIST                                                      Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 128    NK043  SWBD NK043 (CLASS 1E  CB/CC  2016-00      0.71          Anchorage          evaluated per 14C4258-CAL-004. Block wall evaluated per 125 VDC)                                                                                14C4258-CAL-003.
Component per se screened. Block wall evaluated per 129    AB007      Aux Relay Rack    CB    2016-00      0.4      Equipment Capacity 14C4258-CAL-003.
FDR BKR FOR 125 V                                                          Item is ROB to NG001. Equipment capacity evaluated in 130  NG00109    SWING BATTERY      CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHARGER NK025                                                                                      004.
125 V BATTERY Component per se screened. Anchorage evaluated per 131    NK025  CHARGER NK025 (Swing    CB    2000-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
Battery Charger) 12/2/14                                                                            Page 58 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item      ID            Description    Bldg    Elev      HCLPF          Failure Mode                                Basis Number Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 480 V LOAD CENTER 132    NG002                          CB    2000-00      0.41          Anchorage          evaluated per 14C4258-CAL-005 Block wall evaluated per NG02 14C4258-CAL-003.
FLEX 500 kW TIE IN BKR                                                        Item is ROB to NG002. Equipment capacity evaluated in 133    NG00212    from FD201 (Phase 2  CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-connection point)                                                                                  005.
FDR BKR FOR 125 V                                                          Item is ROB to NG002. Equipment capacity evaluated in 134    NG00203        VITAL BATTERY    CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHARGER NK024                                                                                    005.
125 V BATTERY                                                            Component per se screened. Anchorage evaluated per 135    NK024                          CB    2016-00      0.4      Equipment Capacity CHARGER NK024                                                        14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
TRANSFER SWITCH BUS Component per se screened. Block wall evaluated per 136    NK074        NK04 BATTERY      CB    2016-00      0.4        Equipment Capacity 14C4258-CAL-003.
CHARGER NK24/NK26 125 VDC BUS                                                            Component per se screened. Anchorage evaluated per 137    NK004                          CB    2016-00      0.4      Equipment Capacity SWITCHBOARD NK004                                                        14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
FDR BKR FROM BATT                                                      Item is ROB to NK004. Component per se screened. Anchorage 138    NK00402                          CB    2016-00      0.4      Equipment Capacity CHGR NK024 TO NK004                                                                      evaluated per 14C4258-CAL-004.
Component per se screened. Anchorage evaluated per 139    NK014    125 V BATTERY NK014    CB    2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
ISOLATION BKR FOR                                                      Item is ROB to NK004. Component per se screened. Anchorage 140    NK00401                          CB    2016-00      0.4      Equipment Capacity BATTERY NK014                                                                      evaluated per 14C4258-CAL-004.
FDR BKR FOR INVERTER Item is ROB to NK004. Component per se screened. Anchorage 141    NK00411  NN011 (PART OF SWBD    CB    2016-00      0.4        Equipment Capacity evaluated per 14C4258-CAL-004.
NK004) 7.5KVA INVERTER (FED Component per se screened. Block wall evaluated per 142    NN014    FROM BATT CHARGER      CB    2016-00      0.4      Equipment Capacity 14C4258-CAL-003.
NK024)
Class 1E AC DIST SWBD                                                          Component per se screened. Anchorage evaluated per 143    NN004                          CB    2016-00      0.4      Equipment Capacity NN04 (SEP GRP 4)                                                      14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
BOP Instrumentation 144    RP147B                          CB    2000-00    >RLGM            Screened                              SRT disposition Rack RP147B NEUTRON FLUX MONITORING SYSTEM 145  SENY0061A                        AUX    2047-00    >RLGM            Screened                              SRT disposition DETECTOR AMPLIFIER SENY 61A 12/2/14                                                                              Page 59 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item        ID          Description    Bldg    Elev      HCLPF          Failure Mode                                  Basis Number NEUTRON FLUX MONITORING SYSTEM 146  SENY0061B                        AUX    2047-00    >RLGM            Screened                              SRT disposition DETECTOR AMPLIFIER SENY 61B Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 147    SE054D    W NUC INSTM NIS 4    CB    2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
W PROCESS ANALOG Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 148      SB041  PROTECTION SET CAB-    CB    2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
04 BOP Instrumentation                                                    Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 149    RP053BC                          CB    2047-06      0.41          Anchorage Rack RP053BC                                                                        evaluated per 14C4258-CAL-005.
RVLIS Process Cabinet                                                    Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 150      SB079                          CB    2047-06      0.41          Anchorage SB079                                                                          evaluated per 14C4258-CAL-005.
Subcooling Monitor                                                    Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 151    RP081B                          CB    2047-06      0.41          Anchorage Cabinet                                                                          evaluated per 14C4258-CAL-005.
W PROCESS 152    SB148B      PROTECTION (Fire    CB    2000-00    >RLGM            Screened                              SRT disposition Isolation)
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 153    SA066B  STATUS INDICATING SYS  CB    2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
Component per se screened. Block wall evaluated per 154      RP140        PANEL RP140      CB    2000-00      0.4      Equipment Capacity 14C4258-CAL-003.
Item is ROB to RL002. Component per se screened. Anchorage Note 5  BGLI0104 BORIC ACID TANK A LEV  CB    2047-06      0.4      Equipment Capacity evaluated per 14C4258-CAL-004.
Note 5  BGLT0104  BORIC ACID TANK A LEV  AUX    1974-00    >RLGM            Screened                              SRT disposition RWST SUPPLY TO CTMT Note 5  BNHV0003                        AUX    1974-00    >RLGM            Screened                              SRT disposition SPRAY PUMP B RWST SUPPLY TO CTMT Note 5  BNHV0004                        AUX    1974-00    >RLGM            Screened                              SRT disposition SPRAY PUMP A RWST TO SAFETY INJ Note 5 BNHV8806A                        AUX    1976-10    >RLGM            Screened                              SRT disposition PUMP A SUCTION RWST TO SAFETY INJ Note 5 BNHV8806B                        AUX    1976-10    >RLGM            Screened                              SRT disposition PUMP B SUCTION RWST TO RHR PUMP B Note 5 BNHV8812B                        AUX    1968-01    >RLGM            Screened                              SRT disposition SUCTION Note 5  BNLT0933  RWST Level Transmitter YRD    1993-00    >RLGM            Screened                              SRT disposition 12/2/14                                                                              Page 60 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item      ID      Description    Bldg    Elev      HCLPF          Failure Mode                                  Basis Number Equipment capacity evaluated in 14C4258-CAL-005. Anchorage LOCAL CONTROL PANEL Note 5  FC0219                    AUX    2002-00      0.41      Equipment Capacity    evaluated per 14C4258-CAL-005. Relay functionality evaluated FOR TD AFW PUMP per 14C4258-CAL-005.
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage Note 5  NG002B    MCC NG02B BUS    AUX    2026-00      0.4        Relay functionality  evaluated per 14C4258-CAL-004. Relay functionality evaluated per 14C4258-CAL-005.
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage Note 5  NG003C    MCC NG03C BUS    AUX    2047-00      0.32        Relay functionality  evaluated per 14C4258-CAL-005. Relay functionality evaluated per 14C4258-CAL-005.
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage Note 5  NG004C    MCC NG04C BUS    AUX    2047-00      0.32        Relay functionality  evaluated per 14C4258-CAL-005. Relay functionality evaluated per 14C4258-CAL-005.
Component per se screened. Block wall evaluated per Note 5  RP334  LOCKOUT RELAY RACK  CB    2000-00      0.4      Equipment Capacity 14C4258-CAL-003.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report AMEREN MISSOURI CALLAWAY ENERGY CENTER EXPEDITED SEISMIC EVALUATION PROCESS (ESEP) REPORT December 31, 2014 Prepared by:      Ameren Missouri Westinghouse Electric Company LLC Stevenson & Associates 12/1/14                                                                              Page 1 of 61
              © 2014 by Westinghouse Electric Company LLC. All Rights Reserved.
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report EXPEDITED SEISMIC EVALUATION PROCESS REPORT Table of Contents 1.0  Purpose and Objective ..................................................................................................................... 4 2.0  Brief Summary of the FLEX Seismic Implementation Strategies .................................................... 5 3.0  Equipment Selection Process and ESEL ........................................................................................... 6 3.1                    Equipment Selection Process and ESEL.......................................................... 6 3.1.1                ESEL Development .......................................................................................... 7 3.1.2                Power Operated Valves .................................................................................. 7 3.1.3                Pull Boxes ........................................................................................................ 8 3.1.4                Termination Cabinets ..................................................................................... 8 3.1.5                Critical Instrumentation Indicators ................................................................ 8 3.1.6                Phase 2 and Phase 3 Piping Connections ....................................................... 8 3.1.7                Relays .............................................................................................................. 9 3.2                    Justification for Use of Equipment That Is Not the Primary Means for FLEX Implementation .............................................................................................. 9 4.0  Ground Motion Response Spectrum (GMRS) .................................................................................. 9 4.1                    Plot of GMRS Submitted by the Licensee ...................................................... 9 4.2                    Comparison to SSE ........................................................................................ 12 5.0  Review Level Ground Motion (RLGM) ........................................................................................... 13 5.1                    Description of RLGM Selected ...................................................................... 13 5.2                    Method to Estimate ISRS.............................................................................. 14 6.0  Seismic Margin Evaluation Approach ............................................................................................ 15 6.1                    Summary of Methodologies Used................................................................ 15 6.2                    HCLPF Screening Process .............................................................................. 15 6.2.1                Overview ....................................................................................................... 15 6.2.2                Generic Screening Results ............................................................................ 16 6.3                    Seismic Walkdown Approach ....................................................................... 19 6.3.1                Walkdown Approach .................................................................................... 19 6.3.2                Application of Previous Walkdown Information ......................................... 19 6.3.3                Significant Walkdown Findings .................................................................... 19 12/2/14                                                                                                                        Page 2 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 6.4                          HCLPF Calculation Process ............................................................................ 23 6.5                          Functional Evaluations of Relays.................................................................. 23 6.6                          Tabulated ESEL HCLPF Values (Including Key Failure Modes) ..................... 23 7.0  Inaccessible Items .......................................................................................................................... 26 7.1                          Identification of ESEL items inaccessible for walkdowns ............................ 26 8.0  ESEP Conclusions and Results ........................................................................................................ 26 8.1                          Supporting Information ................................................................................ 26 8.2                          Indication of Planned Modifications ............................................................ 28 8.3                          Modification Implementation Schedule ...................................................... 29 8.4                          Summary of Regulatory Commitments ....................................................... 29 9.0  References ...................................................................................................................................... 31 Attachment A              Callaway ESEL................................................................................................ 34 Attachment B              ESEP HCLPF Values and Failure Modes Tabulation ..................................... 50 12/2/14                                                                                                                                Page 3 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 1.0    Purpose and Objective Following the accident at the Fukushima Dai-ichi nuclear power plant resulting from the March 11, 2011, Great Tohoku Earthquake and subsequent tsunami, the Nuclear Regulatory Commission (NRC) established a Near-Term Task Force (NTTF) to conduct a systematic review of NRC processes and regulations and to determine if the agency should make additional improvements to its regulatory system. The NTTF developed a set of recommendations intended to clarify and strengthen the regulatory framework for protection against natural phenomena. Subsequently, the NRC issued a 50.54(f) letter on March 12, 2012 [1], requesting information to assure that these recommendations are addressed by all U.S. nuclear power plants. The 50.54(f) letter requests that licensees and holders of construction permits under 10 CFR Part 50 reevaluate the seismic hazards at their sites against present-day NRC requirements and guidance. Depending on the comparison between the reevaluated seismic hazard and the current design basis, further risk assessment may be required. Assessment approaches acceptable to the staff include a seismic probabilistic risk assessment (SPRA), or a seismic margin assessment (SMA). Based upon the assessment results, the NRC staff will determine whether additional regulatory actions are necessary.
This report describes the Expedited Seismic Evaluation Process (ESEP) undertaken for the Callaway Energy Center (CEC). The intent of the ESEP is to perform an interim action in response to the NRCs 50.54(f) letter [1] and 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 EPRI 3002000704, Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic [2]. The guidance discusses the use of the ongoing FLEX process [3] as a starting point for consideration.
This report examines the FLEX equipment and strategy [3] (Section 2.0) to develop the initial Expedited Seismic Equipment List (ESEL) and uses an iterative process to develop the final ESEL [4] (Section 3.0).
The ESEL is used to evaluate the listed equipment against the review level ground motion (RLGM) data (Section 5) with respect to the equipments seismic capacity based on characterization of the high confidence of a low probability of failure (HCLPF).
Equipment which has seismic capacity larger than the RLGM data can be screened from further evaluation. For equipment that has a seismic capacity below the RLGM, modifications need to be performed following the NRC endorsed guidance in EPRI 3002000704.
The objective of this report is to provide summary information describing the ESEP evaluations and results. The level of detail provided in this report is intended to enable the NRC to understand the inputs used, the evaluations performed, and the decisions made as a result of the interim evaluations.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 2.0    Brief Summary of the FLEX Seismic Implementation Strategies The Callaway FLEX strategies for Reactor Core Cooling and Heat Removal, Reactor Inventory Control/Long-term Subcriticality, and Containment Function are summarized below. This summary is derived from the Callaway Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA-12-049 [3].
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 (TDAFP) during FLEX Phase 1 with suction from the Condensate Storage Tank (CST).
Ameren Missouri has elected to construct a new Hardened Condensate Storage Tank (HCST) [3]. The larger HCST volume would be capable of feeding the steam generators for at least 72 hours. This extended coping duration will not require HCST make-up from the UHS before the Phase 3 off-site equipment is deployed. The TDAFP flow control valves and Main Steam Atmospheric Relief Valves (ARVs) are also required to provide reactor core heat-removal capability. Phase 2 reactor core heat removal is achieved via the new FLEX mechanical connections. The only permanent plant equipment manipulated for the Phase 2 is manual valves.
Reactor Inventory Control/Long-term Subcriticality strategy consists of reactor coolant system borated make-up via the FLEX primary make-up connections.
Reactor coolant system (RCS) inventory reduction is a result of water volume reduction due to cooldown, reactor coolant pump seal leakage, and letdown via head-vents and/or pressurizer PORVs. The reactor coolant pump seal leak-off containment isolation valve is manually isolated to conserve inventory and keep leak-off flow within the Reactor Building. To avoid adverse effects on the RCS natural circulation flow, the accumulator isolation valves are electrically closed during the cooldown to prevent nitrogen injection into the reactor coolant system.
There are no Phase 1 or Phase 2 FLEX actions required to maintain containment integrity. In fact, containment function is not expected to be challenged during all three phases.
Necessary electrical components are outlined in the Callaway FLEX OIP submittal [3],
and primarily entail the installation of a 480V generator (FLEX) to provide power to vital batteries, equipment installed to support FLEX electrical connections, and monitoring instrumentation required for core cooling, reactor coolant inventory, and containment integrity.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 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 Callaway is presented in Attachment A.
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 Phases 1, 2 and 3 mitigation of a Beyond Design Basis External Event (BDBEE), as outlined in the Callaway Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA-12-049 [3]. The OIP provides the Callaway 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 Callaway OIP [3]. FLEX recovery actions are excluded from the ESEP scope per EPRI 3002000704 [2]. The overall list of planned FLEX modifications and the scope for consideration herein is limited to those required to support core cooling, reactor coolant inventory and subcriticality, and containment integrity functions. Portable and pre-staged FLEX equipment (not permanently installed) are excluded from the ESEL per EPRI 3002000704 [2].
The ESEL component selection followed the EPRI guidance outlined in Section 3.2 of EPRI 3002000704.
: 1. The scope of components is limited to that required to accomplish the core cooling and containment safety functions identified in Table 3-2 of EPRI 3002000704. The instrumentation monitoring requirements for core cooling/containment safety functions are limited to those outlined in the EPRI 3002000704 guidance, and are a subset of those outlined in the Callaway OIP [3].
: 2. The scope of components is limited to installed plant equipment and the FLEX connections necessary to implement the Callaway OIP [3] 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 Back-up/Alternate).
: 4. The Primary FLEX success path is to be specified. Selection of the Back-up/Alternate FLEX success path must be justified.
: 5. Phase 3 coping strategies are included in the ESEP scope, whereas recovery strategies are excluded.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report
: 6. Structures, systems, and components excluded per the EPRI 3002000704
[2] 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.
* Power-operated valves not required to change state as part of the FLEX mitigation strategies.
* Nuclear steam supply system components (e.g., reactor pressure vessel and internals, reactor coolant pumps and seals, etc.)
: 7. For cases in which neither train was specified as a primary or back-up 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 Callaway 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 One Line Diagrams) were performed to identify the boundaries of the flowpaths to be used in the FLEX strategies and to identify specific components in the flowpaths 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 one-line drawings, system descriptions, design basis documents, etc., as necessary. The P&IDs are also used to determine the normal position of system valves and the valve positioning required in order to align the system in support of the FLEX functions.
The electrical equipment required to support the mechanical components used in the FLEX strategies evaluated for the ESEL was also evaluated for its inclusion on the ESEL using electrical drawings and guidance [2].
3.1.2 Power Operated Valves Page 3-3 of EPRI 3002000704 [2] notes that power operated valves not required to change state are excluded from the ESEL. Page 3-2 also notes that functional failure modes of electrical and mechanical portions of the installed Phase 1 equipment should be considered (e.g., RCIC/AFW trips). To address this 12/2/14                                                                                Page 7 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report concern, the following guidance is applied in the Callaway ESEL for functional failure modes associated with power operated valves:
* Power operated valves that remain energized during the Extended Loss of all AC Power (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 de-energized.
* Power operated valves not required to change state as part of the FLEX mitigation strategies during Phase 1, and are re-energized 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 re-powered.
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 Phase 3 connections, provide consolidated locations for permanently connecting multiple cables. The termination cabinets and the internal connections provide a completely passive function; however, the cabinets are included in the ESEL to ensure industry knowledge on panel/anchorage failure vulnerabilities is addressed.
3.1.5 Critical Instrumentation Indicators Critical indicators and recorders are typically physically located on panels/cabinets and are included as separate components; however, seismic evaluation of the instrument indication may be included in the panel/cabinet seismic evaluation (rule-of-the-box).
3.1.6 Phase 2 and Phase 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 Callaway 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 Back-up/Alternate).
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Item 6 in Section 3.1 above goes on to explain that Piping, cabling, conduit, HVAC, and their supports are excluded from the ESEL scope in accordance with EPRI 3002000704 [2].
Therefore, piping and pipe supports associated with FLEX Phase 2 and Phase 3 connections are excluded from the scope of the ESEP evaluation. However, any active valves in FLEX Phase 2 and Phase 3 connection flow path are included in the ESEL.
3.1.7 Relays Relays essential to the FLEX strategy were explicitly addressed [5]. Relays were screened and where relay chatter was found to result in an undesirable alignment the relay, and its parent cabinet, were added to the analysis. Parent cabinets were walked down and, if needed, HCLPF estimates were performed.
3.2  Justification for Use of Equipment That Is Not the Primary Means for FLEX Implementation No equipment outside of the primary FLEX strategy is credited in the Callaway ESEP [4].
The complete ESEL for Callaway [4] is presented in Attachment A.
4.0    Ground Motion Response Spectrum (GMRS) 4.1  Plot of GMRS Submitted by the Licensee The CEC design response spectra are stated to be applied in the free field at finished grade [6].
The 1E-4 and 1E-5 Uniform Hazard Response Spectra (UHRS), along with a design factor (DF), are used to compute the GMRS at the control point as shown in the seismic hazard and GMRS submittal to the NRC [7].
Table 4-1 shows the UHRS and GMRS spectral accelerations.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Table 4-1: UHRS for 10-4 and 10-5 and GMRS at the control point for Callaway
                                    -4                -5 Freq. (Hz)  10 UHRS (g)      10 UHRS (g)        GMRS (g) 100        4.20E-01        9.88E-01        5.00E-01 90        4.24E-01        1.00E+00        5.06E-01 80        4.30E-01        1.02E+00        5.15E-01 70        4.40E-01        1.05E+00        5.30E-01 60        4.61E-01        1.11E+00        5.57E-01 50        5.12E-01        1.23E+00        6.17E-01 40        6.17E-01        1.45E+00        7.34E-01 35        6.83E-01        1.60E+00        8.12E-01 30        7.68E-01        1.82E+00        9.20E-01 25        8.70E-01        2.10E+00        1.06E+00 20        9.16E-01        2.21E+00        1.11E+00 15        9.02E-01        2.18E+00        1.10E+00 12.5        9.10E-01        2.16E+00        1.09E+00 10        9.54E-01        2.17E+00        1.11E+00 9        9.90E-01        2.21E+00        1.13E+00 8        1.02E+00        2.24E+00        1.15E+00 7        1.03E+00        2.24E+00        1.15E+00 6        1.01E+00        2.19E+00        1.12E+00 5        9.14E-01        2.00E+00        1.02E+00 4        6.74E-01        1.55E+00        7.85E-01 3.5        5.29E-01        1.25E+00        6.32E-01 3        4.00E-01        9.59E-01        4.83E-01 2.5        2.87E-01        6.81E-01        3.44E-01 2        2.31E-01        5.32E-01        2.70E-01 1.5        1.70E-01        3.75E-01        1.92E-01 12/2/14                                                                                Page 10 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report
                              -4                -5 Freq. (Hz)  10 UHRS (g)      10 UHRS (g)        GMRS (g) 1.25        1.58E-01        3.39E-01        1.75E-01 1        1.36E-01        2.86E-01        1.48E-01 0.9        1.24E-01        2.61E-01        1.35E-01 0.8        1.12E-01        2.38E-01        1.23E-01 0.7        1.02E-01        2.19E-01        1.13E-01 0.6        9.47E-02        2.04E-01        1.05E-01 0.5        8.64E-02        1.89E-01        9.68E-02 0.4        6.91E-02        1.51E-01        7.75E-02 0.35        6.05E-02        1.32E-01        6.78E-02 0.3        5.18E-02        1.13E-01        5.81E-02 0.25        4.32E-02        9.44E-02        4.84E-02 0.2        3.45E-02        7.55E-02        3.87E-02 0.15        2.59E-02        5.66E-02        2.91E-02 0.125        2.16E-02        4.72E-02        2.42E-02 0.1        1.73E-02        3.77E-02        1.94E-02 12/2/14                                                                          Page 11 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Figure 4-1 shows the control point UHRS and GMRS.
Mean Soil UHRS and GMRS at Callaway 2.5 2.
1E-5 UHRS Spectral acceleration, g 1.5                                                                        GMRS 1E-4 UHRS 1.
0.5 0.
0.1                1                    10                  100 Spectral frequency, Hz Figure 4-1:    Plots of 1E-4 and 1E-5 UHRS and GMRS at control point for Callaway (5%-damped response spectra) 4.2                              Comparison to SSE The definition of the SSE for Callaway is discussed in Section 2.5, 3.7 and 3.7(B) of the FSAR [6]. The SSE is anchored to a 0.20g Peak Ground Acceleration (PGA) and is presented in Table 4-2.
Table 4-2: SSE for Callaway Freq (Hz)        SA (g) 0.25          0.09 2.50          0.63 9.00          0.52 33.00          0.20 100.00        0.20 12/2/14                                                                                                        Page 12 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report As shown in Figure 4-2, the GMRS begins to exceed the SSE at around 3.5 Hz.
SSE        GMRS 10.00 1.00 Acceleration (g) 0.10 0.01 0.1                          1                              10                      100 Frequency (Hz)
Figure 4-2: Callaway SSE - GMRS Comparison 5.0                  Review Level Ground Motion (RLGM) 5.1          Description of RLGM Selected The Review Level Ground Motion is derived by linearly scaling the current design basis SSE by the maximum ratio of the GMRS to the SSE between the 1 and 10 Hz range (not to exceed two times the SSE) [2]. The maximum GMRS/SSE ratio occurs at 10 Hz as seen in Figure 4-2. The In-Structure Response Spectra document provides logarithmic interpolation at 10 Hz to determine that the SSE spectral acceleration is 0.48 g [8]. Examination of Table 4-1 shows that the GMRS spectral acceleration is 1.11 g. The result is a maximum GMRS/SSE ratio between 1 - 10 Hz of 2.31 (witness 1.11 g / 0.48 g = 2.31). Since the GMRS/SSE ratio cannot exceed 2 the RGLM is scaled at 2 X SSE. The resulting RLGM is shown in Table 5-1 and Figure 5-1.
It is noted that for surface-mounted structures, systems, and components (SSC)
(TAP01, TBN01, and the CST pipe house) directly applying the GMRS for HCLPF 12/2/14                                                                                                    Page 13 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report determination is acceptable. Results based upon the GMRS as the seismic margins earthquake are noted where applicable herein.
Table 5-1: RLGM for Callaway Freq. (Hz)          100        33          9          2.5  0.25 RLGM (g)            0.4      0.4      1.04          1.26  0.18 SSE        GMRS        RLGM 10.00 1.00 Acceleration (g) 0.10 0.01 0.1                              1                              10                      100 Frequency (Hz)
Figure 5-1: Callaway RLGM vs GMRS 5.2          Method to Estimate In-Structure Response Spectra (ISRS)
The ISRS for Callaway [10a] uses the scaled approach to estimate the ISRS. As mentioned in Section 5.1, the RLGM is scaled by a factor of 2 which is also applied to the existing ISRS curves.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 6.0    Seismic Margin Evaluation Approach It is necessary to demonstrate that the ESEL items have sufficient seismic capacity to meet or exceed the demand characterized by the RLGM. The seismic capacity is characterized as the peak ground acceleration (PGA) for which there is a high confidence of a low probability of failure (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 NP-6041, A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1) [8].
: 2. Probabilistic approach using the fragility analysis methodology of EPRI TR-103959, Methodology for Developing Seismic Fragilities [9].
Callaway has elected to use the deterministic approach by applying the EPRI NP-6041 screening process [8].
6.1      Summary of Methodologies Used The seismic margins methodology of EPRI report NP-6041-SL [8] was applied for this effort. Use of this methodology conforms to Section 5 of EPRI 3002000704. The primary tasks performed were:
* Generic seismic screening per NP-6041, Table 2-4.
* Performance of seismic walkdowns.
* Item-specific screening via walkdown, review of design data, and performance of screening calculations.
* Performance of HCLPF calculations for screened-in equipment 6.2      HCLPF Screening Process 6.2.1 Overview The seismic margins screening methodology of NP-6041-SL was applied. The primary steps for this screening process are:
: 1. Apply NP-6041-SL, Table 2-4 to determine which equipment items and failure modes may be screened-out on a generic basis.
: 2. For each equipment item, perform a seismic walkdown to verify generic screening may be applied and to verify the item does not have any specific seismic vulnerabilities.
: 3. Verify anchorage capacity.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report The generic screening criteria of Table 2-4 are dependent on the applied screening level and are applicable to equipment located within 40 feet of plant grade. For the Callaway ESEP project:
* The peak 5% spectral acceleration of the RLGM is 1.26g and occurs at 2.5 Hz. At 3.5 Hz, the RLGM decreases to 1.2g 1. From FSAR SP Table 3.7(B)-4 and SA Tables 3.7-3 and 3.7-4, all Category I structures have fundamental frequencies exceeding 3.5 Hz and can reasonably be considered to respond in the frequency range corresponding to accelerations less than 1.2g. Accordingly, the 2nd screening column (0.8 - 1.2g) screening criteria of NP-6041-SL, Table 2-4, were applied with special consideration for components with low frequencies.
* A number of components in the Auxiliary/Control Building and the Reactor Building were located above 40 from grade; all other equipment was located within 40 of plant grade. Per Appendix A of NP-6041-SL, components that are above 40 from grade and have corresponding ISRS at the base of component in exceedance of 1.5 times the bounding spectrum (equivalent to a 1.8g peak spectral acceleration) may not be screened to the 2nd screening column and require HCLPF analysis.
Table 6-1 below summarizes the application of Table 2-4 screening for the ESEP.
Applied plant grade was Elevation 2000. Per the FSAR this grade elevation is constant through-out the power block area.
After completion of the screening process, an item is either screened-out or screened-in. The presumptive seismic capacity of a screened-out item exceeds the applied screening level and no further evaluation is needed. An item that is screened-in requires a HCLPF analysis to address the failure mode cited by the seismic review team (SRT). The HCLPF capacity may or may not be above the screening level.
6.2.2 Generic Screening Results Table 6-1 summarizes the generic screening results for the ESEL. Only the relevant equipment types are listed. Based on the generic screening:
* HCLPF analyses are required for atmospheric storage tanks
* Relay chatter requires evaluation 1
The frequency where the RLGM spectra equals 1.2g is determined by logarithmic interpolation based on the control point accelerations and frequencies in Reference 8 as follows:
log(1.04 g ) log(1.26 g )
(log( X Hz ) log( 2.5 Hz )                            + log(1.26 g )
log( 9 Hz ) log( 2.5 Hz )
1.2 g = 10 X = 3.46 Hz 12/2/14                                                                                                                    Page 16 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Other generic screening requirements were addressed by walkdown, design review and anchorage verification. These assessments are documented in the screening evaluation work sheets (SEWS) [10f].
Table 6-1: Summary of generic screening per NP-6041-SL Table 2-4, 1.2g Screening Level Equipment Type            Generic Screening Criteria                  Screening Result Active valves                  Note (f) applies.              There are no extremely large extended motor operators on 2-inch or smaller piping.
Passive valves                  No evaluation required.        N/A Atmospheric storage tanks      Evaluation required.          HCLPF analyses required for the atmospheric storage tanks.
Pressure vessels                Notes (h), (i) apply          For the pressurized tanks on the ESEL, anchorage and load path were verified by bounding calculations using qualification reports during screening. Potential failure modes of the vessel bodies were addressed by walkdown and design review.
Batteries and racks            Note (k) applies.              Batteries are braced racks and are designed for seismic loads. HCLPF analyses are required for the battery rack anchorage.
Horizontal pumps                No evaluation required.        Although no evaluation is required for the component per se, a HCLPF evaluation for the auxiliary feedwater turbine-driven pump is required.
Active electrical power        Notes (s) and (t) apply.      Note (s) was addressed by walkdown and distribution panels                                            design review. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required.
Relays are evaluated separately per Reference 5.
Passive electrical power        Note (s) applies.              Note (s) was addressed by walkdown and distribution panels                                            design review. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required.
Transformers                    Notes (u) and (v) apply.      The ESEL includes dry-type transformers. A design review verified coil restraint. HCLPF analysis of anchorage is required.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Equipment Type              Generic Screening Criteria                  Screening Result Battery chargers & inverters    Note (w) applies.              Per walkdown and design review, the items on the ESEL are solid state units. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required.
Instrumentation and control      Notes (s) and (t) apply.      Note (s) was addressed by walkdown and panels and racks                                                design review. Where bounding analysis of anchorage configurations for the RLGM could not be provided, HCLPF analyses are required.
Relays are evaluated separately per Reference 5.
Temperature sensors; pressure    Note (x) applies.              Note (x) was addressed by walkdown and and level sensors.                                              design review. Sensors in the scope were typically mounted in-line on piping.
Relevant notes from NP-6041-SL Table 2-4
: f. Evaluation recommended for MOVs in piping lines of 2 inches diameter or less.
: h. Margin evaluation only needs to consider anchorage and supports.
: i. For vessels designed by dynamic analysis or equivalent static analysis enveloping vessel inertial and piping loading, only the anchorage and supports require evaluation. For vessel not meeting these criteria, all potential failure modes require evaluation.
: k. Batteries mounted in braced racks designed for seismic loads or qualified by dynamic testing do not require evaluation. Rigid spacers between batteries and end restraints are required. Batteries should be tightly supported by side rails.
: s. Walkdown should be conducted to verify that the instruments are properly attached to the cabinets.
: t. Relays, contactors, switches, and breakers must be evaluated for chatter and trip if functionality during strong shaking is required.
: u. Anchorage evaluation required.
: v. Liquid-filled transformers require evaluation of overpressure safety switches. The transformer coils should be restrained within the cabinet for dry transformers.
: w. Solid state units require anchorage checks. Others require evaluation.
: x. Insufficient data are available for screening guidelines. Emphasis should be on attachments.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 6.3    Seismic Walkdown Approach 6.3.1 Walkdown Approach Walkdowns were performed by two-person seismic review teams (SRTs) consisting of engineers with seismic experience. Walkdowns followed the guidance of Section 5 of EPRI 3002000704 [2] and Section 2 of NP-6041-SL [8]. The SRT used NP-6041-SL, Appendix F, to evaluate item-specific equipment caveats. The SRT also recorded notes and took photographs of the items under review.
Two walkdown sessions have been performed as indicated below.
Walkdown Date                          SRT                          Plant Support Week of July 14, 2014            Hunter Young (S&A)                  Jim Cunningham (Callaway)
Samer El-Bahey (S&A)                Steve Sampson (Callaway)
George Belchik (Callaway)
Week of November 3, 2014        Hunter Young (S&A)                  David Hollabaugh (Callaway)
Apostolos Karavoussianis (S&A)
The walkdown findings for each item are documented in screening evaluation work sheets (SEWS). The SEWS notes also identify evaluations and reviews performed to support screening. The SEWS are included in Appendix C of Reference 10f. Also, Appendix A [10f] provides a concise summary of screening results in tabular format.
6.3.2 Application of Previous Walkdown Information New seismic walkdowns were performed for ESEL equipment. The results of the previous seismic margin evaluation, performed for the Seismic IPEEE program [11], were reviewed and used for background purposes only.
6.3.3 Significant Walkdown Findings The walkdown and screening results are summarized in Table 6-2.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Table 6-2: Items Selected for HCLPF Analysis No.        ID          Description          Bldg    Elev                              Basis for Selection
: 1. NB001    4.16KV SWGR NB001 (Class    CB      2000-00  Anchorage could not be readily screened. Perform HCLPF analysis 1E, Train A)                                  of anchorage.
: 2. NG001    480 V LOAD CENTER NG01      CB/CC  2000-00  Anchorage could not be readily screened. Perform HCLPF analysis of anchorage.
Apply results to similar items NG002 and NG003.
: 3. NK011    125 V BATTERY NK011          CB/CC  2016-00  Anchorage could not be readily screened. Perform HCLPF analysis of anchorage.
Apply results to similar items NK013 and NK014.
: 4. NK021    125 V BATTERY CHARGER        CB/CC  2016-00  Anchorage could not be readily screened. Perform HCLPF analysis NK021                                          of anchorage.
Apply results to similar items NK023 and NK024.
: 5. NK025    125 V BATTERY CHARGER        CB      2000-00  Anchorage could not be readily screened. Perform HCLPF analysis NK025 (Swing Battery                          of anchorage.
Charger)
: 6. NN001    Class 1E AC DIST SWBD        CB/CC  2016-00  Anchorage could not be readily screened. Perform HCLPF analysis NN01 (SEP GRP 1)                              of anchorage.
Apply results to similar items NK043, NN003, NK051, NK041, NK001, NK003, NK004, and NN004.
: 7. NN011    7.5KVA INVERTER (FED        CB/CC  2016-00  Anchorage could not be readily screened. Perform HCLPF analysis FROM BATT CHARGER                              of anchorage.
NK021)
Apply results to similar item NN013.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report No.        ID        Description      Bldg      Elev                              Basis for Selection
: 8. PA003    CUBICLE PT FOR RCP      AUX      2026-00  Anchorage could not be readily screened. Perform HCLPF analysis MOTOR DPBB01A                              of anchorage.
Apply results to similar item PA004.
: 9. PAL02    TDAFW Pump              AUX      2000-00  Anchorage could not be readily screened. Perform HCLPF analysis of anchorage.
: 10. RL001    REACTOR COOLANT AND      CB      2047-06  Anchorage could not be readily screened. Perform HCLPF analysis SUPT SYS CONSOLE                            of anchorage.
Apply results to similar items RL002, RL005, RL006, and RL017 thru RL026.
: 11. SB102A    W CABINET FOR REACTOR    AUX      2026-00  Anchorage could not be readily screened. Perform HCLPF analysis TRIP SWG TRAIN-A                            of anchorage.
: 12. TAP01    Condensate Storage Tank  YARD    2000-00  Perform HCLPF analysis per Appendix H of NP-6041. In addition, evaluate block wall doghouse that is adjacent for interaction hazard.
: 13. TBN01    RWST                    YRD      2000-00  Perform HCLPF analysis per Appendix H of NP-6041.
: 14. XNG01    4.16-KV/480 V LOAD      CB/CC    2000-00  Anchorage could not be readily screened. Perform HCLPF analysis CENTER TRANSFORMER                          of anchorage.
XNG01 FOR LC NG001 12/2/14                                                                      Page 21 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report No.          ID        Description          Bldg      Elev                            Basis for Selection
: 15. Generic    Equipment 40 above grade  AB/CB    2047-06  Equipment on the Aux/Ctrl 2047.5' elevation are 40' above grade and have ISRS spectral accelerations in both horizontal directions exceeding 1.8g (with clipping) and therefore do not screen to the 2nd screening lane. HCLPF analysis for component functionality and structure (including anchorage) are required for the associated components.
Affected components include NF039A, NF039B, NF039C, NG003C, NG004C, RP053AC, RP053BC, RP053DB, RP068, RP081A, RP081B, RP289, SA036A, SA036C, SA066A, SA066B, SA075A, SB029A, SB029D, SB030A, SB032A, SB032D, SB033A, SB037, SB038, SB041, SB078, SB079, SE054A, SE054C, and SE054D.
: 16. Generic    BLOCK WALLS                AB/ CB  Var.      Per NP-6041-SL Table 2-4 seismic capacity cannot be screened and HCLPF analysis is required for block wall seismic capacity.
Affected components include NB001, NK025, NG003, TAP01, NK043, NN003, NN013, NK041, NN001, NK021, NN011, NK051, NK001, NK023, NK071, NK073, NK011, NK013, AB007, NK003, RP209, NG002, NK024, NK074, NK004, NK014, NN014, NN004, RP140, and RP334.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 6.4    HCLPF Calculation Process All HCLPF values were calculated using the conservative, deterministic failure margin (CDFM) criteria of NP-6041-SL [8]. CDFM analysis criteria are summarized in NP-6041-SL, Table 2-5.
For structural failure modes, the HCLPF capacity is equal to the earthquake magnitude at which the strength limit is reached. For equipment functionality, experience data or available test response spectra (TRS) are typically used to define the HCLPF capacity.
The methods of NP-6041-SL, Appendix Q were applied for functionality evaluations.
6.5    Functional Evaluations of Relays Verification of the functional capacity for equipment mounted within 40 of grade was addressed by application NP-6041-SL, Table 2-4 generic screening criteria as described above. For equipment mounted higher than 40 above grade and for in-scope relays, the methods of NP-6041-SL, Appendix Q were applied for functionality evaluations. In those cases the seismic capacity was based upon one of the following:
* Test response spectra (TRS) from plant-specific seismic qualification reports.
* Generic equipment ruggedness spectra (GERS) from EPRI report NP-5223-SL [12].
* Experience based seismic capacity per the guidelines of EPRI TR-1019200 [13].
Screening of relays within the scope of the ESEP (in accordance with EPRI 3002000704) is conducted within 14C4258-RPT-003 [5]. Cabinets requiring HCLPF evaluation for relay functionality are noted in Table 7-2 [5] under Item 17.
6.6    Tabulated ESEL HCLPF Values (Including Key Failure Modes)
Table 6-3 lists HCLPF analysis results. The failure modes analyzed are identified.
Supporting calculation documents [10.d &e] containing the detailed HCLPF calculations are also identified.
For the following discussion, an ESEP outlier is defined as an item whose HCLPF capacity is less than the RLGM. There are currently four ESEP outliers:
* NG003C (Relay Capacity)
* NG004C (Relay Capacity)
* TAP01 (Anchorage Capacity)
* TBN01 (Anchorage Capacity)
Note that for the CST (TAP01) and RWST (TBN01), the applied ground motion and HCLPF are based on the GMRS of Reference 7. The GMRS is acceptable as an alternative RLGM per EPRI 3002000704, Section 4, Option 2. The CST and RWST are founded on a slab-on-grade in the yard. The GMRS has a horizontal PGA of 0.50g.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Relay Chatter Failure Modes NG003C and NG004C are ESEP-outliers with respect to relay chatter. Refer to 14C4258-RPT-003 [5] for specific relays. Credit for operator action may resolve the relay chatter failure modes.
Tabulated HCLPF Values In general, the HCLPF values for screened-out items equals or exceeds the RLGM.
HCLPF  0.40g                        The HCLPF for screened-out items and failure modes Unless justified by calculations, the above HCLPF is applicable for all screened-out items and covers the relevant failure modes.
The HCLPF values for all ESEL items are tabulated in Appendix B.
Table 6-3: HCLPF Analysis Results No. ID          Description            Bldg    Elev    HCLPF2    Failure Mode Basis    Related Components (g, PGA)  Analyzed
: 1. NB001      4.16KV SWGR NB001      CB      2000-00 0.41      Equipment    14C4258- n/a (Class 1E, Train A)                              capacity and CAL-005 anchorage
: 2. NG001      480 V LOAD CENTER      CB/CC  2000-00 0.41      Equipment    14C4258- NG002, NG003 NG01                                              capacity and CAL-005 anchorage
: 3. NK011      125 V BATTERY NK011    CB/CC  2016-00 2.36      Anchorage    14C4258- NK013, NK014 CAL-004
: 4. NK021      125 V BATTERY          CB/CC  2016-00 1.33      Anchorage    14C4258- NK023, NK024 CHARGER NK021                                                  CAL-004
: 5. NK025      125 V BATTERY          CB      2000-00 0.85      Anchorage    14C4258- n/a CHARGER NK025 (Swing                                          CAL-004 Battery Charger)
: 6. NN001      Class 1E AC DIST SWBD  CB/CC  2016-00 0.71      Anchorage    14C4258- NK043, NN003, NK051, NK041, NN01 (SEP GRP 1)                                              CAL-004 NK001, NK003, NK004, NN004
: 7. NN011      7.5KVA INVERTER (FED    CB/CC  2016-00 0.75      Anchorage    14C4258- NN013 FROM BATT CHARGER                                              CAL-004 NK021)
: 8. PA003      CUBICLE PT FOR RCP      AUX    2026-00 0.62      Anchorage    14C4258- PA004 MOTOR DPBB01A                                                  CAL-004 2
HCLPFs based upon RLGM (PGA=0.40g) as the seismic margins earthquake with the exception of TAP01, TBN01, and the CST pipe house block walls, which are based upon the GMRS (PGA=0.50g).
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report No. ID        Description              Bldg    Elev    HCLPF2    Failure Mode        Basis    Related Components (g, PGA)  Analyzed
: 9. PAL02      TDAFW Pump              AUX    2000-00 1.75      Anchorage          14C4258- n/a CAL-004
: 10. RL001      REACTOR AUX CNTRL        CB      2047-06 0.71      Anchorage          14C4258- RL002, RL005, RL006, RL017 thru PANEL                                                                  CAL-004 RL026
: 11. SB102A    W CABINET FOR            AUX    2026-00 0.58      Anchorage          14C4258- n/a REACTOR TRIP SWG                                                      CAL-004 TRAIN-A
: 12. TAP01      Condensate Storage      YARD    2000-00 0.30      Equipment          14C4258- n/a Tank                                              capacity and        CAL-002 anchorage
: 13. TBN01      RWST                    YRD    2000-00 0.33      Equipment          14C4258- n/a capacity and        CAL-002 anchorage
: 14. XNG01      4.16-KV/480 V LOAD      CB/CC  2000-00 0.45      Anchorage          14C4258-CENTER TRANSFORMER                                                    CAL-004 XNG01 FOR LC NG001
: 15. Generic    Equipment >40 SE054A    NIS Cabinet              CB      2047-06 0.41      Equipment          14C4258- SE054C, SE054D capacity and        CAL-005 anchorage SB037      7300 Series Three Bay    CB      2047-06 0.41      Equipment          14C4258- SB038, SB041, SB078, SB079 Cabinets                                          capacity and        CAL-005 anchorage SA066A      STATUS INDICATING      CB      2047-06 0.41      Equipment          14C4258- SA066B SYS                                                capacity and        CAL-005 anchorage RP068      BOP Instrumentation      CB      2047-06 0.41      Equipment          14C4258- n/a Panel                                              capacity and        CAL-005 anchorage RP053AC    BOP Instrumentation      CB      2047-06 0.41      Equipment          14C4258- RP053BC, RP053DB Rack                                              capacity and        CAL-005 anchorage RP081A      T/C SUBCOOLING          CB      2047-06 0.41      Equipment          14C4258- RP081B MONITOR CABINET                                    capacity and        CAL-005 anchorage
: 16. Generic    Block Wall Seismic Interaction CTRL 2000 All block walls on CTRL  CB      2000-00 1.17      Seismic interaction 14C4258- NB001, NK025, NG003, RP140, 2000 elev                                                            CAL-003 and RP334.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report No. ID          Description              Bldg    Elev    HCLPF2    Failure Mode        Basis    Related Components (g, PGA)  Analyzed CTRL 2016  All block walls on CTRL  CB      2016-00 0.87      Seismic interaction 14C4258- NK043, NN003, NN004, NN013, 2016 elev                                                            CAL-003 NN014, NK041, NN001, NK021, NN011, NK051, NK001, NK023, NK071, NK073, NK074 NK011, NK013, NK014, AB007, NK003, NK004, NK024 AUX 2000  2000 elev wall on      AUX    2000-00 0.67      Seismic interaction 14C4258- RP209 column line AF north of                                                CAL-003 Stair A-2 CST House  CST Pipe house          YARD    2000-00 0.40      Seismic interaction 14C4258- TAP01 masonry walls                                                          CAL-003
: 17. Generic    Cabinets containing essential relays NG003C      MCC NG03C BUS            CB      2047-06 0.32      Functional          14C4258- NG004C capacity and host CAL-005 component capacity NG002B      MCC NG02B BUS            CB      2026-00 0.40      Functional          14C4258- NG001A capacity and host CAL-005 component capacity FC0219      LOCAL CONTROL PANEL      AB      2000-00 0.41      Functional          14C4258- n/a FOR TD AFW PUMP                                    capacity and host CAL-005 component capacity 7.0    Inaccessible Items 7.1    Identification of ESEL items inaccessible for walkdowns Sufficient access was provided for all ESEL items and no additional walkdowns are planned.
8.0    ESEP Conclusions and Results 8.1    Supporting Information Callaway 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 near-term 12/2/14                                                                                                    Page 26 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 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 Callaway response to the NRCs 50.54(f) letter [1].
On March 12, 2014, NEI submitted to the NRC results of a study [14] 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 "site-specific seismic hazards show that there
[...] has not been an overall increase in seismic risk for the fleet of U.S. plants" based on the re-evaluated 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 Gl-199 safety/risk assessment. The letter also stated that, As a result, the staff has confirmed that the conclusions reached in Gl-199 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 Callaway was included in the fleet risk evaluation submitted in the March 12, 2014 NEI letter [14] therefore, the conclusions in the NRCs May 9 letter [15] also apply to Callaway.
In addition, the March 12, 2014 NEI letter [14] 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.
The fleet of currently operating nuclear power plants was designed using conservative practices, such that the plants have significant margin to withstand large ground motions safely. This has been borne out for those plants that have actually experienced significant earthquakes. The seismic design process has inherent (and intentional) conservatisms which result in significant seismic margins within SSCs. These conservatisms are reflected in several key aspects of the seismic design process, including:
* Safety factors applied in design calculations
* Damping values used in dynamic analysis of SSCs
* Bounding synthetic time histories for in-structure response spectra calculations
* Broadening criteria for in-structure response spectra
* Response spectra enveloping criteria typically used in SSC analysis and testing applications 12/2/14                                                                              Page 27 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report
* 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, and
* 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 plant specific basis, a more detailed seismic risk assessment (SPRA or risk-based SMA) is to be performed in accordance with EPRI 1025287 [16]. As identified in the Callaway Seismic Hazard and GMRS submittal [7], Callaway 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. Callaway will complete that evaluation in accordance with the schedule identified in NEIs letter dated April 9, 2013 [17]
and endorsed by the NRC in their May 7, 2013 letter [2].
8.2  Indication of Planned Modifications This report presents the seismic evaluation results for the ESEP as applied to Callaway Energy Center. A primary goal of the ESEP is to demonstrate that HCLPF seismic capacities of ESEL items exceed the RLGM seismic demand. For Callaway, the RLGM is equal to the SSE scaled-up by a 2.0 factor. The RLGM has a PGA of 0.40g at grade. Exceptions to this include the CST (TAP01) and RWST (TBN01),
which apply the GMRS (PGA of 0.50g) for HCLPF evaluation [10b].
Insights from the ESEP identified the following items (Table 8-1) where the HCLPF is below the RLGM and plant modifications will be made in accordance with EPRI 3002000704 [2] to enhance the seismic capacity of the plant.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Table 8-1: Equipment with HCLPF Capacities below the RLGM Requiring Modification 3
HCLPF Capacity ID                Description                (g, PGA)            Failure Mode NG003C              MCC NG03C BUS                  0.32            Relay functionality NG004C              MCC NG04C BUS                  0.32            Relay functionality TAP01          Condensate Storage Tank            0.30                Anchorage TBN01                  RWST                      0.33                Anchorage 8.3      Modification Implementation Schedule Plant modifications will be performed in accordance with the schedule identified in NEI letter dated April 9, 2013 [15], which states that plant modifications not requiring a planned refueling outage will be completed by December 2016 and modifications requiring a refueling outage will be completed within two planned refueling outages after December 31, 2014.
Section 8.4 contains the regulatory commitment dates to complete planned plant modifications as a result of ESEP. Referencing Section 8.4, Actions 1 and 2 do not require a refueling outage and will be completed by December 31, 2016.
Action 3 requires a refueling outage and will be completed by the end of RF21, Spring 2016, as required to support FLEX implementation. Action 4 requires a refueling outage and will be completed no later than the end of the second refueling outage after 12/31/14, currently RF22 scheduled for Fall 2017.
8.4      Summary of Regulatory Commitments The following actions will be performed as a result of the ESEP.
Completion Action #  Equipment ID    Equipment Description            Action Description              Date 1                                                Modify FLEX Support Guidelines      December 31, to include operator actions to      2016 reset relays with HCLPF values NG003C      MCC NG03C BUS              less than the RLGM.
2                                                Modify FLEX Support Guidelines      December 31, to include operator actions to      2016 reset relays with HCLPF values NG004C      MCC NG04C BUS              less than the RLGM.
3                                                Install a new hardened            End of RF21, TAP01      Condensate Storage Tank    Condensate Storage Tank.            Spring 2016 3
All HCLPFs based upon RLGM (PGA=0.40g) as the seismic margins earthquake with the exception of TAP01, TBN01, and the CST pipe house block walls, which are based upon the GMRS (PGA=0.50g).
12/2/14                                                                                                Page 29 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Completion Action # Equipment ID  Equipment Description            Action Description            Date 4                                            Three step response in order of  No later than priority: 1) Re-evaluate FLEX    the end of the response strategies to eliminate  second the need for the tank. 2) Re-    refueling analyze the tank with the more    outage after realistic median-centered        12/31/14, structural response based on the  currently RF22 new GMRS which will be            scheduled for generated once the Seismic PRA    Fall 2017 starts, 3) Upgrade/replace the TBN01      RWST                    tank.
12/2/14                                                                                    Page 30 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report 9.0    References
: 1.      Letter from E. J. Leeds and M. R. Johnson, USNRC, to M. W. Sunseri, WCNOC, 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, March 12, 2012.
ADAMS Accession No. ML12053A340.
: 2.      Letter from E. J. Leeds, USNRC, to J. E. Pollock, NEI, Electric Power Research Institute Final Draft Report XXXXXX, Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, May 7, 2013.
3002000704; ADAMS Accession No. ML13106A331.
: 3.      Callaway Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA-12-049.
: a.      Callaway Letter ULNRC-05962, Docket No. 50-483: Callaway Plant Unit 1 Union Electric Co. Facility Operating License NPF-30 Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), February 18, 2013, (ADAMS Accession Number ML13063A459).
: b.      Callaway Letter ULNRC-06024, Docket No. 50-483: Callaway Plant Unit 1 Union Electric Co. Facility Operating License NPF-30 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), August 29, 2013, (ADAMS Accession Number ML13242A239).
: c.      Callaway Letter ULNRC-06087, Docket No. 50-483: Callaway Plant Unit 1 Union Electric Co. Facility Operating License NPF-30 Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049), February 26, 2014, (ADAMS Accession Number ML14057A770).
: d.      Callaway Letter ULNRC-06135, Docket No. 50-483: Callaway Plant Unit 1 Union Electric Co. Facility Operating License NPF-30 Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-12/2/14                                                                                  Page 31 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Design-Basis External Events (Order Number EA-12-049), August 28, 2014, (ADAMS Accession Number ML13063A459).
: 4. SCP-14-82, Transmittal of Updated Callaway ESEL for ESEP Report, December 2014.
: 5. S&A report 14C4258-RPT-003 Rev. 0, Callaway ESEL Relay Assessment, December 2014.
: 6. CEC FSAR, Rev. OL-20, Callaway Energy Center Final Safety Analysis Report (FSAR). December 2013.
: 7. Callaway Seismic Hazard and GMRS submittal, dated March 31, 2014.
: 8. Electric Power Research Institute Report, NP-6041-SLR1, Revision 1, A Methodology for Assessment of Nuclear Power Plant Seismic Margin, 1991.
: 9. Electric Power Research Institute Report, TR-103959, Methodology for Developing Seismic Fragilities, 1994.
: 10. S&A Calculations:
a) 14C4258-CAL-001 Rev. 0, Generation of Scaled In-Structure Response Spectra for Callaway, December 2014.
b) 14C4258-CAL-002 Rev. 0, Seismic Capacity of CST (TAP01) and RWST (TBN01), December 2014.
c)    14C4258-CAL-003 Rev. 0, HCLPF Analyses for Block Walls, December 2014.
d) 14C4258-CAL-004 Rev. 0, HCLPF Seismic Capacity Evaluations for Selected Equipment, December 2014.
e) 14C4258-CAL-005 Rev. 0, HCLPF Analysis of Components Based on Seismic Test Data, December 2014.
f)    14C4258-RPT-002, Revision 1, Seismic Evaluation of Equipment at CEC for the Expedited Seismic Evaluation Process, December 2014.
: 11. ULNRC-3232, Callaway Plant Individual Plant Examination of External Events (IPEEE), June 1995.
: 12. Electric Power Research Institute Report, NP-5223-SL, Revision 1, Generic Seismic Ruggedness of Power Plant Equipment, 1991.
: 13. Electric Power Research Institute Technical Report, TR-1019200, Seismic Fragility Applications Guide Update, 2009.
: 14. Letter from A. R. Pietrangelo, NEI, to D. L Skeen, USNRC, Seismic Risk Estimates for Plants in the Central and Eastern United States, March 12, 2014. ADAMS Accession No. ML14083A584.
: 15. NRC (E Leeds) Letter to All Power Reactor Licensees et al., Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(F) Regarding Seismic Hazard Re-Evaluations for 12/2/14                                                                              Page 32 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Recommendation 2.1 of the Near-Term Task Force Review of Insights From the Fukushima Dai-Ichi Accident, May 9, 2014.
: 16. Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic. EPRI, Palo Alto, CA: February 2013. 1025287.
: 17. Letter from A. R. Pietrangelo, NEI, to D. L. Skeen, USNRC, Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations, April 9, 2013.
ADAMS Accession No. ML13107B386.
12/2/14                                                                              Page 33 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Attachment A Callaway ESEL 12/2/14                                                              Page 34 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                      Normal        Desired          Notes/Comments[1]
ID          Description Num                                        State        State Mechanical ESEL Items 1  TAP01      Condensate Storage                                CST provides AFW suction for Tank                    Operable Operable        the first 17 hours 2  PAL02      TDAFW Pump              Not                      TDAFW provides pump power Operating Operating      to move AFW to SG 3  ALHV0034  MOV                                                MOV required to isolate flow Open          Closed      path 4  ALHV0035  MOV                                                MOV required to isolate flow Open          Closed      path 5  ALPI0029  Suction Pressure Indicator 6  ALFE0049  TDAFWP Miniflow Flow Element 7  ALFI0049  TDAFWP Miniflow Flow Indicator 8  APLV0002  Level Control Valve      Open          Closed      Fail closed valve 9  ALPI0020  TDAFW Pump Discharge Pressure Indicator 10  ALHV0012  Air Operated Valve                                Valve may be operated to Open          Open        throttle AFW flow to SG 11  ALFE0004  Flow Element                                      AFW flow related hardware 12  ALFT0004  Flow Transmitter                                  AFW flow related hardware 13  ALFT0011  Flow Transmitter                                  AFW flow related hardware 14  AEFV0041  Feedwater Isolation Valve                    Open          Closed      Fail closed valve 15  ALHV0010  Air Operated Valve                                Valve may be operated to Open          Open        throttle AFW flow to SG 16  ALFE0003  Flow Element 17  ALFT0003  Flow Transmitter                                  AFW flow related hardware 18  ALFT0009  Flow Transmitter                                  AFW flow related hardware 19  AEFV0040  Feedwater Isolation Valve                    Open          Closed      Fail closed valve 20  ALHV0008  Air Operated Valve                                Valve may be operated to Open          Open        throttle AFW flow to SG 21  ALFE0002  Flow Element                                      AFW flow related hardware 22  ALFT0002  Flow Transmitter                                  AFW flow related hardware 23  ALFT0007  Flow Transmitter                                  AFW flow related hardware 12/2/14                                                                              Page 35 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL            Equipment                    Operating State Item                                        Normal        Desired          Notes/Comments[1]
ID          Description Num                                          State        State 24  AEFV0039    Feedwater Isolation Valve                    Open          Closed      Fail closed valve 25  ALHV0006    Air Operated Valve                                Valve may be operated to Open          Open        throttle AFW flow to SG 26  ALFE0001    Flow Element                                      AFW flow related hardware 27  ALFT0001    Flow Transmitter                                  AFW flow related hardware 28  AEFV0042    Feedwater Isolation Valve                    Open          Closed      Fail closed valve 29  ABHV0005    Air Operated Valve                                TDAFW controls and steam Closed        Fail Open  flow controls. Fails open.
30  ABHV0048    Air Operated Valve                    Fail        TDAFW controls and steam Open          Closed      flow controls. Fails closed.
31  ABHV0006    Air Operated Valve                                TDAFW controls and steam Closed        Fail Open  flow controls. Fails open.
32  ABHV0049    Air Operated Valve                    Fail        TDAFW controls and steam Open          Closed      flow controls. Fails closed.
33  FCPI0311    Pressure Indicator 34  FCLT0010    Level Indicator                                    Needed to prevent water intrusion in TDAFWP 35  FCFV0310    Level Control Valve                                Needed to prevent water Fail        intrusion in TDAFWP. Valve Open          Closed      fails closed.
36  FCHV0312    Trip and Throttle Valve                                              TDAFW controls and steam flow controls. Operation of this manual valve should be accounted for in operating Closed        Operating  procedures.
37  Speed      Speed Governor                                    TDAFW controls and steam Governor                            Standby      Operating  flow controls.
38  FCFV0313    Speed Governor Valve                              TDAFW controls and steam Open          Operating  flow controls.
39  KFC02      AFW Pump Turbine        Not                      TDAFW controls and steam Operating    Operating  flow controls.
40  BBPV8702A  RHR TO RCS              Closed        Open 41  EMHV8803B  MOTOR-OPERATED                                    Primary flow path, can be VALVE EMHV8803B          Closed        Open        operated manually 42  EMHV8801B  MOTOR-OPERATED                                    Primary flow path, can be VALVE EMHV8801B          Closed        Open        operated manually 12/2/14                                                                                Page 36 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL            Equipment                        Operating State Item                                          Normal      Desired        Notes/Comments[1]
ID          Description Num                                            State        State 43  EMFE0924    ECCS FLOW TO RCS COLD-LEG 1 44  EMFE0925    ECCS FLOW TO RCS COLD-LEG 2 45  EMFE0926    ECCS FLOW TO RCS COLD-LEG 3 46  EMFE0927    ECCS FLOW TO RCS COLD-LEG 4 47  TBN01      RWST                                                Secondary source for core makeup after BAT exhausted 48  BNLT0930    RWST Level Transmitter                                        Monitor RWST level 49  EJHCV0606  RHR Heat Exchanger A Outlet Isolation Valve    Fail Open    Closed      Can be operated manually 50  TBG03A      Boric Acid Tank 51  BGLT0102    BORIC ACID TANK A LEV                                                Monitor BAT level 52  BGLI0102    BORIC ACID TANK A LEV                                                Local level indicator 53  EJFCV0610  RHR Pump A miniflow Valve                      Open        Closed 54  EJFCV0610  RHR Pump A miniflow Valve                      Open        Closed 55  EJFCV0610  RHR Pump A miniflow Valve                      Open        Closed Electrical ESEL Items 56  NB001      4.16KV SWGR NB001 This component is powered by (Class 1E, Train A) the FLEX DG in Phase 3 as stated in Sec. 8 of the Callaway N/A          N/A        Plant FLEX Integrated Plan 57  NB00101    4.16 kV FDR BKR FOR This component is powered by RHRP-A DPEJ01A the FLEX DG in Phase 3 as (Residual Heat stated in Sec. 8 of the Callaway Removal Pump A)
N/A          N/A        Plant FLEX Integrated Plan 58  NB00107    4.16 kV FDR BKR FOR This component is powered by CCWP-A DPEG01A the FLEX DG in Phase 3 as (Component Cooling stated in Sec. 8 of the Callaway Water Pump A)
N/A          N/A        Plant FLEX Integrated Plan 12/2/14                                                                                Page 37 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                      Normal        Desired          Notes/Comments[1]
ID          Description Num                                        State        State 59  NB00109  4.16 kV FLEX GEN (Phase 3) TIE-IN POINT This breaker position is the tie-(BKR) FOR TRAIN A in point for the Phase 3 FLEX N/A          N/A        diesel generator 60  NB00113  4.16 kV FDR BKR FOR This component is powered by XFMR XNG01 (4160 V the FLEX DG in Phase 3 as to 480 V for LC stated in Sec. 8 of the Callaway NG001)
N/A          N/A        Plant FLEX Integrated Plan 61  XNG01    4.16-KV/480 V LOAD This component is powered by CENTER the FLEX DG in Phase 3 as TRANSFORMER stated in Sec. 8 of the Callaway XNG01 FOR LC NG001 N/A          N/A        Plant FLEX Integrated Plan 62  NG001    480 V LOAD CENTER                                  This component is powered by NG01                                              the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 63  NG00101  MAIN BKR FOR LC This component is powered by NG01 the FLEX DG in Phase 3 as stated in Sec. 8 of the Callaway N/A          N/A        Plant FLEX Integrated Plan 64  NG00103  FDR BKR FOR 125 V                                  This component is powered by VITAL BATTERY                                      the FLEX DG, first Phase 2, CHARGER NK021                                      then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 65  NG00112  FLEX 500 kW TIE IN This component is powered by BRK (Phase 2 the FLEX DG in Phase 2 as connection point) stated in Sec. 8 of the Callaway N/A          N/A        Plant FLEX Integrated Plan 66  NG00116  TIE BKR (CONNECTS                                  This component is powered by NG01 AND NG03)                                    the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 67  NG003    480 V LOAD CENTER                                  This component is powered by NG03                                              the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 12/2/14                                                                              Page 38 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                  Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 68  NG00303  FDR BKR FOR 125 V                                This component is powered by VITAL BATTERY                                    the FLEX DG, first Phase 2, CHARGER NK023                                    then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 69  NK021    125 V BATTERY                                    This component is powered by CHARGER NK021                                    the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 70  NK071    TRANSFER SWITCH                                  This component is powered by BUS NK01 BATTERY                                the FLEX DG, first Phase 2, CHARGER NK21/NK25                                then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 71  NK001    125 VDC BUS                                      This component is powered SWITCHBOARD NK001                                during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 72  NK00102  FDR BKR FROM BATT                                This component is powered by CHGR NK021 TO                                    the FLEX DG, first Phase 2, NK001                                            then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 73  NK00104  MAIN BREAKER FOR                                This component is powered CNTRL AND DIST PNL                              during ALL phases of the FLEX NK041 (PART OF                                  strategy as stated in Sec. 8 of SWBD NK001)                                      the Callaway Plant FLEX N/A          N/A        Integrated Plan 74  NK00105  MAIN BREAKER FOR                                This component is powered CNTRL AND DIST PNL                              during ALL phases of the FLEX NK051 (PART OF                                  strategy as stated in Sec. 8 of SWBD NK001)                                      the Callaway Plant FLEX N/A          N/A        Integrated Plan 75  NK011    125 V BATTERY NK011                              This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                            Page 39 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL            Equipment                    Operating State Item                                        Normal        Desired          Notes/Comments[1]
ID            Description Num                                          State        State 76  NK00101    ISOLATION BKR FOR                                  This component is powered BATTERY NK011                                      during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 77  NK00111    FDR BKR FOR                                        This component is powered INVERTER NN011                                    during ALL phases of the FLEX (PART OF SWBD                                      strategy as stated in Sec. 8 of NK001)                                            the Callaway Plant FLEX N/A          N/A        Integrated Plan 78  NN011      7.5KVA INVERTER                                    This component is powered (FED FROM BATT                                    during ALL phases of the FLEX CHARGER NK021)                                    strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 79  NN001      Class 1E AC DIST                                  This component is powered SWBD NN01 (SEP GRP                                during ALL phases of the FLEX
: 1)                                                strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 80  SA066A      STATUS INDICATING                                  This component is powered SYS                                                during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 81  SENY0060A  NEUTRON FLUX                                      This component is powered MONITORING SYSTEM                                  during ALL phases of the FLEX DETECTOR AMPLIFIER                                strategy as stated in Sec. 8 of SENY 60A                                          the Callaway Plant FLEX N/A          N/A        Integrated Plan 82  SENY0060B  NEUTRON FLUX                                      This component is powered MONITORING SYSTEM                                  during ALL phases of the FLEX DETECTOR AMPLIFIER                                strategy as stated in Sec. 8 of SENY 60B                                          the Callaway Plant FLEX N/A          N/A        Integrated Plan 83  SB038      W PROCESS ANALOG                                  This component is powered PROTECTION SET CAB-                                during ALL phases of the FLEX 01                                                strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                                Page 40 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 84  SE054A    W NUC INSTM NIS 1                                This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 85  RP053AC  BOP                                              This component is powered INSTRUMENTATION                                  during ALL phases of the FLEX RACK (TERMINATION                                strategy as stated in Sec. 8 of AREA)                                            the Callaway Plant FLEX N/A          N/A        Integrated Plan 86  SB078    RPV LEVEL INSTR SYS                              This component is powered (RVLIS) PROC PROT                                during ALL phases of the FLEX SYS CABINET                                      strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 87  RP081A    T/C SUBCOOLING                                    This component is powered MONITOR CABINET                                  during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 88  NK041    CNTRL & INSTR DIST                                This component is powered SWBD NK041 (CLASS                                during ALL phases of the FLEX 1E 125 VDC)                                      strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 89  NE107    DIESEL GEN PNL                                    This component is powered NE107 & FIELD                                    during ALL phases of the FLEX FLASHING                                          strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 90  RL005    TURBINE GENERATOR                                This component is powered AND FW CONSOLE                                    during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 91  RL006    TURBINE GENERATOR                                This component is powered AND FW CONSOLE                                    during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                            Page 41 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL        Equipment                    Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 92  RP315    DC DIST PNL RP315                                This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 93  RL023    TURBINE GENERATOR                                This component is powered AND FW MCB                                        during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 94  RL024    TURBINE GENERATOR                                This component is powered AND FW MCB                                        during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 95  RL017    ESF MCB                                          This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 96  RL018    ESF MCB                                          This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 97  RL019    ESF MCB                                          This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 98  RL020    ESF MCB                                          This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 99  RL001    REACTOR COOLANT                                  This component is powered AND SUPT SYS                                      during ALL phases of the FLEX CONSOLE                                          strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                            Page 42 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL            Equipment                  Operating State Item                                      Normal        Desired          Notes/Comments[1]
ID          Description Num                                        State        State 100  RL002      REACTOR COOLANT                                  This component is powered AND SUPT SYS                                    during ALL phases of the FLEX CONSOLE                                          strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 101  RL025      TURBINE GENERATOR                                This component is powered AND FW MCB                                      during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 102  RL026      TURBINE GENERATOR                                This component is powered AND FW MCB                                      during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 103  RP317      FUSED 125 VDC DIST                              This component is powered PNL RP317                                        during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 104  NK051      CNTRL & INSTR DIST                              This component is powered SWBD NK051 (CLASS                                during ALL phases of the FLEX 1E 125 VDC)                                      strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 105  BBPCV0455A BBPCV0455A PORV                                  This component is powered SOLENOID FAILS TO                                during ALL phases of the FLEX OPEN ON DEMAND                                  strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 106  RL021      REACTOR AUX CNTRL                                This component is powered PANEL                                            during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 107  RL022      REACTOR AUX CNTRL                                This component is powered PANEL                                            during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                              Page 43 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 108  KJ0121    DIESEL GAUGE AND                                  This component is powered CONTROL PANEL                                    during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 109  RP209    B AUXILIARY RELAY                                This component is powered RACK                                              during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 110  RP289    DC DIST PNL RP289                                This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 111  RP068    MISC BOP                                          This component is powered INSTRUMENT RACK                                  during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 112  RP330    AUX RELAY RACK                                    This component is powered RP330                                            during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 113  RP332    B AUXILIARY RELAY                                This component is powered RACK                                              during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 114  NK051A    EM'CY LIGHTING DIST                              This component is powered SWBD NK051A                                      during ALL phases of the FLEX (SUBPNL OF NK051)                                strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 115  NK023    125 V BATTERY                                    This component is powered by CHARGER NK023                                    the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 12/2/14                                                                            Page 44 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 116  NK073    TRANSFER SWITCH                                  This component is powered by BUS NK03 BATTERY                                  the FLEX DG, first Phase 2, CHARGER NK23/NK25                                then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 117  NK003    125 VDC BUS                                      This component is powered SWITCHBOARD NK003                                during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 118  NK00302  FDR BKR FROM BATT                                This component is powered by CHGR NK023 TO                                    the FLEX DG, first Phase 2, NK003                                            then in Phase 3, as stated in Sec. 8 of the Callaway Plant N/A          N/A        FLEX Integrated Plan 119  NK00304  MAIN BREAKER FOR                                  This component is powered CNTRL AND DIST PNL                                during ALL phases of the FLEX NK043 (PART OF                                    strategy as stated in Sec. 8 of SWBD NK003)                                      the Callaway Plant FLEX N/A          N/A        Integrated Plan 120  NK013    125 V BATTERY NK013                              This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 121  NK00301  ISOLATION BKR FOR                                This component is powered BATTERY NK013                                    during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 122  NK00311  FDR BKR FOR                                      This component is powered INVERTER NN013                                    during ALL phases of the FLEX (PART OF SWBD                                    strategy as stated in Sec. 8 of NK003)                                            the Callaway Plant FLEX N/A          N/A        Integrated Plan 123  NN013    7.5KVA INVERTER                                  This component is powered (FED FROM BATT                                    during ALL phases of the FLEX CHARGER NK023)                                    strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 12/2/14                                                                            Page 45 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                      Normal        Desired          Notes/Comments[1]
ID          Description Num                                        State        State 124  NN003    Class 1E AC DIST                                  This component is powered SWBD NN03 (SEP GRP                                during ALL phases of the FLEX
: 3)                                                strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 125  RP053DB  BOP INSTR RACK                                    This component is powered RP053DB                                            during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 126  SB037    W PROCESS ANALOG                                  This component is powered PROTECTION SET CAB-                                during ALL phases of the FLEX 03                                                strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 127  SE054C    W NUC INSTM NIS 3                                  This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 128  NK043    CNTRL & INSTR DIST                                This component is powered SWBD NK043 (CLASS                                  during ALL phases of the FLEX 1E 125 VDC)                                        strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 129  AB007    Aux Relay Rack                                    This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Plant FLEX N/A          N/A        Integrated Plan 130  NG00109  FDR BKR FOR 125 V SWING BATTERY This component provides CHARGER NK025 power to NK025 and, in turn, N/A          N/A        Separation Group 1.
131  NK025    125 V BATTERY CHARGER NK025 The A-Train swing charger will (Swing Battery be used to power Separation Charger)
N/A          N/A        Group 1.
132  NG002    480 V LOAD CENTER                                  This component is powered by NG02                                              the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 12/2/14                                                                              Page 46 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                    Operating State Item                                    Normal        Desired          Notes/Comments[1]
ID        Description Num                                      State        State 133  NG00212  FLEX 500 kW TIE IN                                This component is powered by BKR from FD201                                    the FLEX DG, first Phase 2, (Phase 2 connection                              then in Phase 3, as stated in point)                                            Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 134  NG00203  FDR BKR FOR 125 V                                This component is powered by VITAL BATTERY                                    the FLEX DG, first Phase 2, CHARGER NK024                                    then in Phase 3, as stated in Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 135  NK024    125 V BATTERY                                    This component is powered by CHARGER NK024                                    the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 136  NK074    TRANSFER SWITCH                                  This component is powered by BUS NK04 BATTERY                                  the FLEX DG, first Phase 2, CHARGER NK24/NK26                                then in Phase 3, as stated in Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 137  NK004    125 VDC BUS                                      This component is powered SWITCHBOARD NK004                                during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 138  NK00402  FDR BKR FROM BATT                                This component is powered by CHGR NK024 TO                                    the FLEX DG, first Phase 2, NK004                                            then in Phase 3, as stated in Sec. 8 of the Callaway N/A          N/A        Integrated FLEX Plan 139  NK014    125 V BATTERY NK014                              This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 140  NK00401  ISOLATION BKR FOR                                This component is powered BATTERY NK014                                    during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 12/2/14                                                                            Page 47 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL            Equipment                    Operating State Item                                        Normal        Desired          Notes/Comments[1]
ID            Description Num                                          State        State 141  NK00411    FDR BKR FOR                                        This component is powered INVERTER NN011                                    during ALL phases of the FLEX (PART OF SWBD                                      strategy as stated in Sec. 8 of NK004)                                            the Callaway Integrated FLEX N/A          N/A        Plan 142  NN014      7.5KVA INVERTER                                    This component is powered (FED FROM BATT                                    during ALL phases of the FLEX CHARGER NK024)                                    strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 143  NN004      Class 1E AC DIST                                  This component is powered SWBD NN04 (SEP GRP                                during ALL phases of the FLEX
: 4)                                                strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 144  RP147B      BOP Instrumentation                                This component is powered Rack RP147B                                        during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 145  SENY0061A  NEUTRON FLUX                                      This component is powered MONITORING SYSTEM                                  during ALL phases of the FLEX DETECTOR AMPLIFIER                                strategy as stated in Sec. 8 of SENY 61A                                          the Callaway Integrated FLEX N/A          N/A        Plan 146  SENY0061B  NEUTRON FLUX                                      This component is powered MONITORING SYSTEM                                  during ALL phases of the FLEX DETECTOR AMPLIFIER                                strategy as stated in Sec. 8 of SENY 61B                                          the Callaway Integrated FLEX N/A          N/A        Plan 147  SE054D      W NUC INSTM NIS 4                                  This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 148  SB041      W PROCESS ANALOG                                  This component is powered PROTECTION SET CAB-                                during ALL phases of the FLEX 04                                                strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 12/2/14                                                                                Page 48 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL          Equipment                      Operating State Item                                      Normal        Desired          Notes/Comments[1]
ID          Description Num                                        State        State 149  RP053BC  BOP Instrumentation                                This component is powered Rack RP053BC                                        during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 150  SB079    RVLIS Process Cabinet                              This component is powered SB079                                              during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 151  RP081B    Subcooling Monitor                                  This component is powered Cabinet                                            during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 152  SB148B    W PROCESS                                          This component is powered PROTECTION (Fire                                    during ALL phases of the FLEX Isolation)                                          strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 153  SA066B    STATUS INDICATING                                  This component is powered SYS                                                during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 154  RP140    PANEL RP140                                        This component is powered during ALL phases of the FLEX strategy as stated in Sec. 8 of the Callaway Integrated FLEX N/A          N/A        Plan 12/2/14                                                                              Page 49 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Attachment B ESEP HCLPF Values and Failure Modes Tabulation HCLPF values are listed in Table B-1. These notes are applicable:
: 1. The listed HCLPF value is for comparison to the horizontal PGA at the bedrock surface.
: 2. Items covered by the NP-6041-SL rule of the box (ROB) are identified in Table A-2 [9].
In each case, the HCLPF value for the parent item applies.
: 3. For the CST and RWST only (TAP01 and TBN01, respectively), the applied ground motion was based on the GMRS (PGA = 0.50g).
: 4. Where an anchorage HCLPF is performed but the component per se is screened, the equipment capacity is assigned based upon the 1.2g peak spectral acceleration coinciding with the 2nd screening lane of NP-6041-SL. Since the Callaway RLGM has a peak spectral acceleration of 1.2g in the building frequency range of interest (see Section 6.2.1) and PGA of 0.40g [Ref. 7], the equipment capacity is assigned as 0.40g PGA.
: 5. As a result of the relay chatter evaluation, additional items were added to the ESEL list for evaluation.
12/2/14                                                                                Page 50 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report Table B-1: ESEL HCLPF Values ESEL Item      ID        Description    Bldg    Elev      HCLPF          Failure Mode                                Basis Number Condensate Storage                                                        Tank capacity evaluated in 14C4258-CAL-002. Block wall 1    TAP01                        YARD  2000-00      0.3            Anchorage Tank                                                                        evaluated per 14C4258-CAL-003.
Component per se screened. Anchorage evaluated per 2    PAL02      TDAFW Pump      AUX    2000-00      0.4        Equipment Capacity 14C4258-CAL-004.
3  ALHV0034          MOV        AUX    1988-00    >RLGM            Screened                              SRT disposition 4  ALHV0035          MOV        AUX    1988-00    >RLGM            Screened                              SRT disposition Suction Pressure 5  ALPI0029                      AUX    2000-00    >RLGM            Screened                              SRT disposition Indicator TDAFWP Miniflow Flow 6  ALFE0049                      AUX    2000-00    >RLGM            Screened                              SRT disposition Element TDAFWP Miniflow Flow 7  ALFI0049                      AUX    2000-00    >RLGM            Screened                              SRT disposition Indicator 8  APLV0002  Level Control Valve YARD  2000-00    >RLGM            Screened                              SRT disposition TDAFW Pump Discharge 9  ALPI0020                      AUX    2000-00    >RLGM            Screened                              SRT disposition Pressure Indicator 10  ALHV0012  Air Operated Valve  AUX    2004-07    >RLGM            Screened                              SRT disposition 11  ALFE0004      Flow Element    AUX    2000-00    >RLGM            Screened                              SRT disposition 12  ALFT0004    Flow Transmitter  AUX    2016-01    >RLGM            Screened                              SRT disposition 13  ALFT0011    Flow Transmitter  AUX    2000-00    >RLGM            Screened                              SRT disposition Feedwater Isolation 14  AEFV0041                      AUX    2028-00    >RLGM            Screened                              SRT disposition Valve 15  ALHV0010  Air Operated Valve  AUX    2002-09    >RLGM            Screened                              SRT disposition 16  ALFE0003      Flow Element    AUX    2000-00    >RLGM            Screened                              SRT disposition 17  ALFT0003    Flow Transmitter  AUX    2016-00    >RLGM            Screened                              SRT disposition 18  ALFT0009    Flow Transmitter  AUX    2000-00    >RLGM            Screened                              SRT disposition Feedwater Isolation 19  AEFV0040                      AUX    2027-10    >RLGM            Screened                              SRT disposition Valve 20  ALHV0008  Air Operated Valve  AUX    2004-00    >RLGM            Screened                              SRT disposition 12/2/14                                                                            Page 51 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item          ID            Description      Bldg    Elev      HCLPF          Failure Mode                                  Basis Number 21      ALFE0002          Flow Element      AUX    2000-00    >RLGM            Screened                              SRT disposition 22      ALFT0002      Flow Transmitter    AUX    2016-00    >RLGM            Screened                              SRT disposition 23      ALFT0007      Flow Transmitter    AUX    2000-00    >RLGM            Screened                              SRT disposition Feedwater Isolation 24      AEFV0039                            AUX    2028-00    >RLGM            Screened                              SRT disposition Valve 25      ALHV0006      Air Operated Valve    AUX    2001-06    >RLGM            Screened                              SRT disposition 26      ALFE0001          Flow Element      AUX    2000-00    >RLGM            Screened                              SRT disposition 27      ALFT0001      Flow Transmitter    AUX    2015-00    >RLGM            Screened                              SRT disposition Feedwater Isolation 28      AEFV0042                            AUX    2027-10    >RLGM            Screened                              SRT disposition Valve 29      ABHV0005      Air Operated Valve    AUX    2027-10    >RLGM            Screened                              SRT disposition 30      ABHV0048      Air Operated Valve    AUX    2027-10    >RLGM            Screened                              SRT disposition 31      ABHV0006      Air Operated Valve    AUX    2027-10    >RLGM            Screened                              SRT disposition 32      ABHV0049      Air Operated Valve    AUX    2027-10    >RLGM            Screened                              SRT disposition 33      FCPI0311      Pressure Indicator  AUX    2000-00    >RLGM            Screened                              SRT disposition 34      FCLT0010        Level Indicator    AUX    2000-00    >RLGM            Screened                              SRT disposition 35      FCFV0310      Level Control Valve  AUX    1988-00    >RLGM            Screened                              SRT disposition 36      FCHV0312    Trip and Throttle Valve AUX    2000-00    >RLGM            Screened                              SRT disposition Item is ROB to PAL02. Component per se screened. Anchorage 37  Speed Governor    Speed Governor      AUX    2000-00      0.4        Equipment Capacity evaluated per 14C4258-CAL-004.
Item is ROB to PAL02. Component per se screened. Anchorage 38      FCFV0313    Speed Governor Valve    AUX    2000-00      0.4        Equipment Capacity evaluated per 14C4258-CAL-004.
Item is ROB to PAL02. Component per se screened. Anchorage 39        KFC02      AFW Pump Turbine      AUX    2000-00      0.4        Equipment Capacity evaluated per 14C4258-CAL-004.
40    BBPV8702A          RHR TO RCS        RB    2007-09    >RLGM            Screened                              SRT disposition MOTOR-OPERATED 41    EMHV8803B                            AUX    1975-08    >RLGM            Screened                              SRT disposition VALVE EMHV8803B MOTOR-OPERATED 42    EMHV8801B                            AUX    2002-00    >RLGM            Screened                              SRT disposition VALVE EMHV8801B 12/2/14                                                                                    Page 52 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item        ID          Description      Bldg    Elev      HCLPF          Failure Mode                                  Basis Number ECCS FLOW TO RCS 43  EMFE0924                            RB    1998-06    >RLGM            Screened                                SRT disposition COLD-LEG 1 ECCS FLOW TO RCS 44  EMFE0925                            RB    1998-06    >RLGM            Screened                                SRT disposition COLD-LEG 2 ECCS FLOW TO RCS 45  EMFE0926                            RB    1998-06    >RLGM            Screened                                SRT disposition COLD-LEG 3 ECCS FLOW TO RCS 46  EMFE0927                            RB    1998-06    >RLGM            Screened                                SRT disposition COLD-LEG 4 47      TBN01              RWST        YRD    2000-00      0.33          Anchorage                Tank capacity evaluated in 14C4258-CAL-002.
48  BNLT0930  RWST Level Transmitter  YRD    1993-00    >RLGM            Screened                                SRT disposition RHR Heat Exchanger A 49  EJHCV0606                          AUX    2001-06    >RLGM            Screened                                SRT disposition Outlet Isolation Valve 50    TBG03A        Boric Acid Tank  AUX    1974-00    >RLGM            Screened                                SRT disposition 51  BGLT0102  BORIC ACID TANK A LEV    AUX    1968-01    >RLGM            Screened                                SRT disposition Item is ROB to RL001. Component per se screened. Anchorage 52    BGLI0102 BORIC ACID TANK A LEV    CB    2047-06      0.4      Equipment Capacity evaluated per 14C4258-CAL-004.
RHR Pump A miniflow 53  EJFCV0610                          AUX    1968-01    >RLGM            Screened                                SRT disposition Valve Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 4.16KV SWGR NB001 56      NB001                            CB    2000-00      0.41          Anchorage          evaluated per 14C4258-CAL-005 Block wall evaluated per (Class 1E, Train A) 14C4258-CAL-003.
4.16 kV FDR BKR FOR Item is ROB to NB001. Equipment capacity evaluated in RHRP-A DPEJ01A 57    NB00101                            CB    2000-00      0.41          Anchorage          14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-(Residual Heat Removal 005. Block wall evaluated per 14C4258-CAL-003.
Pump A) 4.16 kV FDR BKR FOR Item is ROB to NB001. Equipment capacity evaluated in CCWP-A DPEG01A 58    NB00107                            CB    2000-00      0.41          Anchorage          14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-(Component Cooling 004. Block wall evaluated per 14C4258-CAL-003.
Water Pump A) 4.16 kV FLEX GEN                                                            Item is ROB to NB001. Equipment capacity evaluated in 59    NB00109  (Phase 3) TIE-IN POINT  CB    2000-00      0.41          Anchorage          14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-(BKR) FOR TRAIN A                                                              004. Block wall evaluated per 14C4258-CAL-003.
4.16 kV FDR BKR FOR                                                            Item is ROB to NB001. Equipment capacity evaluated in 60    NB00113  XFMR XNG01 (4160 V to    CB    2000-00      0.41          Anchorage          14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-480 V for LC NG001)                                                              004. Block wall evaluated per 14C4258-CAL-003.
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to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item      ID          Description    Bldg    Elev      HCLPF          Failure Mode                                  Basis Number 4.16-KV/480 V LOAD Component per se screened. Anchorage evaluated per 61    XNG01  CENTER TRANSFORMER    CB/CC  2000-00      0.4      Equipment Capacity 14C4258-CAL-004.
XNG01 FOR LC NG001 480 V LOAD CENTER                                                        Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 62    NG001                        CB/CC  2000-00      0.41          Anchorage NG01                                                                            evaluated per 14C4258-CAL-005.
Item is ROB to NG001. Equipment capacity evaluated in 63  NG00101 MAIN BKR FOR LC NG01    CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-004.
FDR BKR FOR 125 V                                                          Item is ROB to NG001. Equipment capacity evaluated in 64  NG00103      VITAL BATTERY      CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHARGER NK021                                                                                      004.
FLEX 350 kW TIE IN BRK                                                        Item is ROB to NG001. Equipment capacity evaluated in 65  NG00112    (Alternate Phase 2  CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-connection point)                                                                                    004.
Item is ROB to NG001. Equipment capacity evaluated in TIE BKR (CONNECTS 66  NG00116                          CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NG01 AND NG03) 005.
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 480 V LOAD CENTER 67    NG003                        CB/CC  2000-00      0.41          Anchorage          evaluated per 14C4258-CAL-005. Block wall evaluated per NG03 14C4258-CAL-003.
FDR BKR FOR 125 V                                                          Item is ROB to NG003. Equipment capacity evaluated in 68  NG00303      VITAL BATTERY      CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHARGER NK023                                                                005. Block wall evaluated per 14C4258-CAL-003.
125 V BATTERY                                                            Component per se screened. Anchorage evaluated per 69    NK021                        CB/CC  2016-00      0.4      Equipment Capacity CHARGER NK021                                                          14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
TRANSFER SWITCH BUS Component per se screened. Block wall evaluated per 70    NK071        NK01 BATTERY      CB    2016-00      0.4      Equipment Capacity 14C4258-CAL-003.
CHARGER NK21/NK25 Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 125 VDC BUS 71    NK001                        CB/CC  2016-00      0.71          Anchorage          evaluated per 14C4258-CAL-004. Block wall evaluated per SWITCHBOARD NK001 14C4258-CAL-003.
Item is ROB to NK001. Equipment capacity evaluated in FDR BKR FROM BATT 72  NK00102                          CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHGR NK021 TO NK001 004. Block wall evaluated per 14C4258-CAL-003.
MAIN BREAKER FOR Item is ROB to NK001. Equipment capacity evaluated in CNTRL AND DIST PNL 73  NK00104                          CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NK041 (PART OF SWBD 004. Block wall evaluated per 14C4258-CAL-003.
NK001) 12/2/14                                                                            Page 54 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item        ID          Description      Bldg    Elev      HCLPF          Failure Mode                                  Basis Number MAIN BREAKER FOR Item is ROB to NK001. Equipment capacity evaluated in CNTRL AND DIST PNL 74    NK00105                          CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NK051 (PART OF SWBD 004. Block wall evaluated per 14C4258-CAL-003.
NK001)
Component per se screened. Anchorage evaluated per 75    NK011    125 V BATTERY NK011  CB/CC  2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
Item is ROB to NK001. Equipment capacity evaluated in ISOLATION BKR FOR 76    NK00101                          CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-BATTERY NK011 004. Block wall evaluated per 14C4258-CAL-003.
FDR BKR FOR INVERTER                                                          Item is ROB to NK001. Equipment capacity evaluated in 77    NK00111  NN011 (PART OF SWBD      CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NK001)                                                                  004. Block wall evaluated per 14C4258-CAL-003.
7.5KVA INVERTER (FED Component per se screened. Anchorage evaluated per 78    NN011    FROM BATT CHARGER    CB/CC  2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
NK021)
Class 1E AC DIST SWBD                                                          Component per se screened. Anchorage evaluated per 79    NN001                          CB/CC  2016-00      0.4      Equipment Capacity NN01 (SEP GRP 1)                                                        14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 80    SA066A  STATUS INDICATING SYS    CB    2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
NEUTRON FLUX MONITORING SYSTEM 81  SENY0060A                        AUX    2026-00    >RLGM            Screened                              SRT disposition DETECTOR AMPLIFIER SENY 60A NEUTRON FLUX MONITORING SYSTEM 82  SENY0060B                        AUX    2026-00    >RLGM            Screened                              SRT disposition DETECTOR AMPLIFIER SENY 60B W PROCESS ANALOG Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 83      SB038  PROTECTION SET CAB-  CB/CC  2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
01 Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 84    SE054A    W NUC INSTM NIS 1    CB/CC  2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
BOP INSTRUMENTATION                                                          Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 85    RP053AC                          CB    2047-06      0.41          Anchorage RACK (TERMINATION                                                                      evaluated per 14C4258-CAL-005.
AREA)
RPV LEVEL INSTR SYS Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 86      SB078  (RVLIS) PROC PROT SYS    CB    2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
CABINET 12/2/14                                                                              Page 55 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item      ID        Description        Bldg        Elev      HCLPF          Failure Mode                                Basis Number T/C SUBCOOLING                                                              Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 87    RP081A                            CB      2047-06      0.41          Anchorage MONITOR CABINET                                                                            evaluated per 14C4258-CAL-005.
CNTRL & INSTR DIST Component per se screened. Anchorage evaluated per 88    NK041  SWBD NK041 (CLASS 1E    CB/CC      2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
125 VDC)
DIESEL GEN PNL NE107 89    NE107                            DGB      2000-00    >RLGM            Screened                            SRT disposition
                  & FIELD FLASHING TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 90    RL005                            CB      2047-06      0.4      Equipment Capacity AND FW CONSOLE                                                                                    14C4258-CAL-004.
TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 91    RL006                            CB      2047-06      0.4      Equipment Capacity AND FW CONSOLE                                                                                    14C4258-CAL-004.
92    RP315    DC DIST PNL RP315 ESW Pumphouse  2000-00    >RLGM            Screened                            SRT disposition TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 93    RL023                            CB      2047-06      0.4      Equipment Capacity AND FW MCB                                                                                    14C4258-CAL-004.
TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 94    RL024                            CB      2047-06      0.4      Equipment Capacity AND FW MCB                                                                                    14C4258-CAL-004.
Component per se screened. Anchorage evaluated per 95    RL017        ESF MCB            CB      2047-06      0.4      Equipment Capacity 14C4258-CAL-004.
Component per se screened. Anchorage evaluated per 96    RL018        ESF MCB            CB      2047-06      0.4      Equipment Capacity 14C4258-CAL-004.
Component per se screened. Anchorage evaluated per 97    RL019        ESF MCB            CB      2047-06      0.4      Equipment Capacity 14C4258-CAL-004.
Component per se screened. Anchorage evaluated per 98    RL020        ESF MCB            CB      2047-06      0.4      Equipment Capacity 14C4258-CAL-004.
REACTOR COOLANT                                                                  Component per se screened. Anchorage evaluated per 99    RL001                            CB      2047-06      0.4      Equipment Capacity AND SUPT SYS CONSOLE                                                                                14C4258-CAL-004.
REACTOR COOLANT                                                                  Component per se screened. Anchorage evaluated per 100    RL002                            CB      2047-06      0.4      Equipment Capacity AND SUPT SYS CONSOLE                                                                                14C4258-CAL-004.
TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 101    RL025                            CB      2047-06      0.4      Equipment Capacity AND FW MCB                                                                                    14C4258-CAL-004.
TURBINE GENERATOR                                                                  Component per se screened. Anchorage evaluated per 102    RL026                            CB      2047-06      0.4      Equipment Capacity AND FW MCB                                                                                    14C4258-CAL-004.
FUSED 125 VDC DIST 103    RP317                          UHS      2000-00    >RLGM            Screened                            SRT disposition PNL RP317 12/2/14                                                                                  Page 56 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item        ID          Description    Bldg    Elev      HCLPF          Failure Mode                                  Basis Number CNTRL & INSTR DIST Component per se screened. Anchorage evaluated per 104    NK051    SWBD NK051 (CLASS 1E CB/CC  2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
125 VDC)
BBPCV0455A PORV 105  BBPCV0455A    SOLENOID FAILS TO  RB    2070-00    >RLGM            Screened                                SRT disposition OPEN ON DEMAND REACTOR AUX CNTRL                                                            Component per se screened. Anchorage evaluated per 106      RL021                          CB    2047-06      0.4      Equipment Capacity PANEL                                                                                  14C4258-CAL-004.
REACTOR AUX CNTRL                                                            Component per se screened. Anchorage evaluated per 107      RL022                          CB    2047-06      0.4      Equipment Capacity PANEL                                                                                  14C4258-CAL-004.
DIESEL GAUGE AND 108    KJ0121                        DGB    2000-00    >RLGM            Screened                                SRT disposition CONTROL PANEL B AUXILIARY RELAY                                                          Component per se screened. Block wall evaluated per 109      RP209                        AUX    2000-00      0.4      Equipment Capacity RACK                                                                                  14C4258-CAL-003.
110      RP289      DC DIST PNL RP289  AUX    2047-06    >RLGM            Screened                                SRT disposition MISC BOP INSTRUMENT                                                      Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 111      RP068                          CB    2047-06      0.41          Anchorage RACK                                                                          evaluated per 14C4258-CAL-005.
112      RP330  AUX RELAY RACK RP330  AUX    2000-00    >RLGM            Screened                                SRT disposition B AUXILIARY RELAY 113      RP332                        AUX    2000-00    >RLGM            Screened                                SRT disposition RACK EM'CY LIGHTING DIST                                                    Item is ROB to NK051. Component per se screened. Anchorage 114    NK051A  SWBD NK051A (SUBPNL    CB    2016-00      0.4        Equipment Capacity    evaluated per 14C4258-CAL-004. Block wall evaluated per OF NK051)                                                                                14C4258-CAL-003.
125 V BATTERY                                                            Component per se screened. Anchorage evaluated per 115    NK023                        CB/CC  2016-00      0.4      Equipment Capacity CHARGER NK023                                                        14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
TRANSFER SWITCH BUS Component per se screened. Block wall evaluated per 116    NK073        NK03 BATTERY      CB    2016-00      0.4      Equipment Capacity 14C4258-CAL-003.
CHARGER NK23/NK25 Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 125 VDC BUS 117    NK003                        CB/CC  2016-00      0.71          Anchorage          evaluated per 14C4258-CAL-004. Block wall evaluated per SWITCHBOARD NK003 14C4258-CAL-003.
Item is ROB to NK003. Equipment capacity evaluated in FDR BKR FROM BATT 118    NK00302                          CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHGR NK023 TO NK003 004. Block wall evaluated per 14C4258-CAL-003.
12/2/14                                                                              Page 57 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item      ID        Description    Bldg    Elev      HCLPF          Failure Mode                                  Basis Number MAIN BREAKER FOR Item is ROB to NK003. Equipment capacity evaluated in CNTRL AND DIST PNL 119  NK00304                        CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NK043 (PART OF SWBD 004. Block wall evaluated per 14C4258-CAL-003.
NK003)
Component per se screened. Anchorage evaluated per 120    NK013  125 V BATTERY NK013  CB/CC  2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
Item is ROB to NK003. Equipment capacity evaluated in ISOLATION BKR FOR 121  NK00301                        CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-BATTERY NK013 004. Block wall evaluated per 14C4258-CAL-003.
FDR BKR FOR INVERTER                                                          Item is ROB to NK003. Equipment capacity evaluated in 122  NK00311 NN013 (PART OF SWBD    CB    2016-00      0.71          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-NK003)                                                                  004. Block wall evaluated per 14C4258-CAL-003.
7.5KVA INVERTER (FED Component per se screened. Anchorage evaluated per 123    NN013  FROM BATT CHARGER    CB/CC  2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
NK023)
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage Class 1E AC DIST SWBD 124    NN003                        CB/CC  2016-00      0.71          Anchorage          evaluated per 14C4258-CAL-004. Block wall evaluated per NN03 (SEP GRP 3) 14C4258-CAL-003.
BOP INSTR RACK                                                        Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 125  RP053DB                        CB    2047-06      0.41          Anchorage RP053DB                                                                          evaluated per 14C4258-CAL-005.
W PROCESS ANALOG Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 126    SB037  PROTECTION SET CAB-  CB/CC  2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
03 Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 127    SE054C  W NUC INSTM NIS 3  CB/CC  2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
CNTRL & INSTR DIST                                                      Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 128    NK043  SWBD NK043 (CLASS 1E  CB/CC  2016-00      0.71          Anchorage          evaluated per 14C4258-CAL-004. Block wall evaluated per 125 VDC)                                                                                14C4258-CAL-003.
Component per se screened. Block wall evaluated per 129    AB007      Aux Relay Rack    CB    2016-00      0.4      Equipment Capacity 14C4258-CAL-003.
FDR BKR FOR 125 V                                                          Item is ROB to NG001. Equipment capacity evaluated in 130  NG00109    SWING BATTERY      CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHARGER NK025                                                                                      004.
125 V BATTERY Component per se screened. Anchorage evaluated per 131    NK025  CHARGER NK025 (Swing    CB    2000-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
Battery Charger) 12/2/14                                                                            Page 58 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item      ID            Description    Bldg    Elev      HCLPF          Failure Mode                                Basis Number Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 480 V LOAD CENTER 132    NG002                          CB    2000-00      0.41          Anchorage          evaluated per 14C4258-CAL-005 Block wall evaluated per NG02 14C4258-CAL-003.
FLEX 500 kW TIE IN BKR                                                        Item is ROB to NG002. Equipment capacity evaluated in 133    NG00212    from FD201 (Phase 2  CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-connection point)                                                                                  005.
FDR BKR FOR 125 V                                                          Item is ROB to NG002. Equipment capacity evaluated in 134    NG00203        VITAL BATTERY    CB    2000-00      0.41          Anchorage        14C4258-CAL-005. Anchorage evaluated per 14C4258-CAL-CHARGER NK024                                                                                    005.
125 V BATTERY                                                            Component per se screened. Anchorage evaluated per 135    NK024                          CB    2016-00      0.4      Equipment Capacity CHARGER NK024                                                        14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
TRANSFER SWITCH BUS Component per se screened. Block wall evaluated per 136    NK074        NK04 BATTERY      CB    2016-00      0.4        Equipment Capacity 14C4258-CAL-003.
CHARGER NK24/NK26 125 VDC BUS                                                            Component per se screened. Anchorage evaluated per 137    NK004                          CB    2016-00      0.4      Equipment Capacity SWITCHBOARD NK004                                                        14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
FDR BKR FROM BATT                                                      Item is ROB to NK004. Component per se screened. Anchorage 138    NK00402                          CB    2016-00      0.4      Equipment Capacity CHGR NK024 TO NK004                                                                      evaluated per 14C4258-CAL-004.
Component per se screened. Anchorage evaluated per 139    NK014    125 V BATTERY NK014    CB    2016-00      0.4      Equipment Capacity 14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
ISOLATION BKR FOR                                                      Item is ROB to NK004. Component per se screened. Anchorage 140    NK00401                          CB    2016-00      0.4      Equipment Capacity BATTERY NK014                                                                      evaluated per 14C4258-CAL-004.
FDR BKR FOR INVERTER Item is ROB to NK004. Component per se screened. Anchorage 141    NK00411  NN011 (PART OF SWBD    CB    2016-00      0.4        Equipment Capacity evaluated per 14C4258-CAL-004.
NK004) 7.5KVA INVERTER (FED Component per se screened. Block wall evaluated per 142    NN014    FROM BATT CHARGER      CB    2016-00      0.4      Equipment Capacity 14C4258-CAL-003.
NK024)
Class 1E AC DIST SWBD                                                          Component per se screened. Anchorage evaluated per 143    NN004                          CB    2016-00      0.4      Equipment Capacity NN04 (SEP GRP 4)                                                      14C4258-CAL-004. Block wall evaluated per 14C4258-CAL-003.
BOP Instrumentation 144    RP147B                          CB    2000-00    >RLGM            Screened                              SRT disposition Rack RP147B NEUTRON FLUX MONITORING SYSTEM 145  SENY0061A                        AUX    2047-00    >RLGM            Screened                              SRT disposition DETECTOR AMPLIFIER SENY 61A 12/2/14                                                                              Page 59 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item        ID          Description    Bldg    Elev      HCLPF          Failure Mode                                  Basis Number NEUTRON FLUX MONITORING SYSTEM 146  SENY0061B                        AUX    2047-00    >RLGM            Screened                              SRT disposition DETECTOR AMPLIFIER SENY 61B Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 147    SE054D    W NUC INSTM NIS 4    CB    2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
W PROCESS ANALOG Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 148      SB041  PROTECTION SET CAB-    CB    2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
04 BOP Instrumentation                                                    Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 149    RP053BC                          CB    2047-06      0.41          Anchorage Rack RP053BC                                                                        evaluated per 14C4258-CAL-005.
RVLIS Process Cabinet                                                    Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 150      SB079                          CB    2047-06      0.41          Anchorage SB079                                                                          evaluated per 14C4258-CAL-005.
Subcooling Monitor                                                    Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 151    RP081B                          CB    2047-06      0.41          Anchorage Cabinet                                                                          evaluated per 14C4258-CAL-005.
W PROCESS 152    SB148B      PROTECTION (Fire    CB    2000-00    >RLGM            Screened                              SRT disposition Isolation)
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage 153    SA066B  STATUS INDICATING SYS  CB    2047-06      0.41          Anchorage evaluated per 14C4258-CAL-005.
Component per se screened. Block wall evaluated per 154      RP140        PANEL RP140      CB    2000-00      0.4      Equipment Capacity 14C4258-CAL-003.
Item is ROB to RL002. Component per se screened. Anchorage Note 5  BGLI0104 BORIC ACID TANK A LEV  CB    2047-06      0.4      Equipment Capacity evaluated per 14C4258-CAL-004.
Note 5  BGLT0104  BORIC ACID TANK A LEV  AUX    1974-00    >RLGM            Screened                              SRT disposition RWST SUPPLY TO CTMT Note 5  BNHV0003                        AUX    1974-00    >RLGM            Screened                              SRT disposition SPRAY PUMP B RWST SUPPLY TO CTMT Note 5  BNHV0004                        AUX    1974-00    >RLGM            Screened                              SRT disposition SPRAY PUMP A RWST TO SAFETY INJ Note 5 BNHV8806A                        AUX    1976-10    >RLGM            Screened                              SRT disposition PUMP A SUCTION RWST TO SAFETY INJ Note 5 BNHV8806B                        AUX    1976-10    >RLGM            Screened                              SRT disposition PUMP B SUCTION RWST TO RHR PUMP B Note 5 BNHV8812B                        AUX    1968-01    >RLGM            Screened                              SRT disposition SUCTION Note 5  BNLT0933  RWST Level Transmitter YRD    1993-00    >RLGM            Screened                              SRT disposition 12/2/14                                                                              Page 60 of 61
 
to ULNRC-06161 Westinghouse Non-Proprietary Class 3 Callaway Energy Center ESEP Final Report ESEL Item      ID      Description    Bldg    Elev      HCLPF          Failure Mode                                  Basis Number Equipment capacity evaluated in 14C4258-CAL-005. Anchorage LOCAL CONTROL PANEL Note 5  FC0219                    AUX    2002-00      0.41      Equipment Capacity    evaluated per 14C4258-CAL-005. Relay functionality evaluated FOR TD AFW PUMP per 14C4258-CAL-005.
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage Note 5  NG002B    MCC NG02B BUS    AUX    2026-00      0.4        Relay functionality  evaluated per 14C4258-CAL-004. Relay functionality evaluated per 14C4258-CAL-005.
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage Note 5  NG003C    MCC NG03C BUS    AUX    2047-00      0.32        Relay functionality  evaluated per 14C4258-CAL-005. Relay functionality evaluated per 14C4258-CAL-005.
Equipment capacity evaluated in 14C4258-CAL-005. Anchorage Note 5  NG004C    MCC NG04C BUS    AUX    2047-00      0.32        Relay functionality  evaluated per 14C4258-CAL-005. Relay functionality evaluated per 14C4258-CAL-005.
Component per se screened. Block wall evaluated per Note 5  RP334  LOCKOUT RELAY RACK  CB    2000-00      0.4      Equipment Capacity 14C4258-CAL-003.
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