WO 14-0095, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident

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

ML14365A262
Person / Time
Site:	Wolf Creek
Issue date:	12/23/2014
From:	Reasoner C Wolf Creek
To:	Document Control Desk, Division of Operating Reactor Licensing
References
WO 14-0095
Download: ML14365A262 (54)

Text

S!W0LF CREEK NUCLEAR OPERATING CORPORATION Cleveland Reasoner Site Vice President December 23, 2014 WO 14-0095 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

Reference:

1) Letter dated March 12, 2012, 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 (NTTF) Review of Insights from the Fukushima Dai-ichi Accident"

2) Letter dated April 9, 2013, from A. R. Pietrangelo, NEI, to D. L. Skeen, USNRC, "Proposed Path Forward for NTTF Recommendation 2.1:

Seismic Reevaluations"

3) Letter dated May 7, 2013, from E. J. Leeds, USNRC, to J. E. Pollock, NEI, "EPRI Final Draft Report XXXXXX, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Near-Term Task Force Recommendation 2.1: Seismic," as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations"

Subject:

Docket No. 50-482: Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Gentlemen:

On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a 50.54(f) letter to all power reactor licensees and holders of construction permits in active or deferred status. of Reference 1 requested each addressee located in the Central and Eastern United States (CEUS) to submit a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of Reference 1.

P.O. Box 411 / Burlington, KS 66839 / Phone: (620) 364-8831

• jLIl An Equal Opportunity Employer M/F/HC/VET

WO 14-0095 Page 2 of 3 In Reference 2, the Nuclear Energy Institute (NEI) requested NRC agreement to delay submittal of the final CEUS Seismic Hazard Evaluation and Screening Reports so that an update to the Electric Power Research Institute (EPRI) ground motion attenuation model could be completed and used to develop that information. NEI proposed that descriptions of subsurface materials and properties and base case velocity profiles be submitted to the NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted by March 31, 2014.

NRC agreed with that proposed path forward in Reference 3.

Reference 1 requested that licensees provide interim evaluations and actions taken or planned to address the higher seismic hazard relative to the design basis, as appropriate, prior to completion of the risk evaluation. In accordance with the NRC endorsed guidance in Reference 3, the attached Expedited Seismic Evaluation Process Report for Wolf Creek Nuclear Operating Corporation (WCNOC) provides the information described in Section 7 of Reference 3 in accordance with the schedule identified in Reference 2.

This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4156, or Mr. Steven R. Koenig at (620) 364-4041.

Sincerely, Cleveland Reasoner COR/rlt

Enclosure:

Wolf Creek Generating Station Expedited Seismic Evaluation Process (ESEP)

Report cc: M. L. Dapas (NRC), w/e C. F. Lyon (NRC), w/e N. F. O'Keefe (NRC), w/e Senior Resident Inspector (NRC), w/e

WO 14-0095 Page 3 of 3 STATE OF KANSAS

)S COUNTY OF COFFEY Cleveland Reasoner, of lawful age, being first duly sworn upon oath says that he is Site Vice President of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.

Byy_

Cleveland Reasoner Site Vice President SUBSCRIBED and sworn to before me this J3*day of & mboj ,2014.

I-OY~ RHONDA L.TIEMEYER A2 Notary Public

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-*-*u~..*'* My January Appointment Expires 11, 2018 t Expiration Date2*JJU* iI* 1,

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report WOLF CREEK NUCLEAR OPERATING CORPORATION WOLF CREEK GENERATING STATION EXPEDITED SEISMIC EVALUATION PROCESS (ESEP) REPORT December 31, 2014 Prepared by: Wolf Creek Nuclear Operating Corporation Westinghouse Electric Company LLC Stevenson & Associates 12/31/14 Page 1 of 51

© 2014 by Westinghouse Electric Company LLC. All Rights Reserved.

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station 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 ........................................................ 5 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 GM RS Submitted by the Licensee .................................................... 9 4.2 Comparison to SSE ..................................................................................... 12 5.0 Review Level Ground Motion (RLGM) ......................................................... 14 5.1 Description of RLGM Selected .................................................................. 14 5.2 Method to Estimate In-Structure Response Spectra (ISRS) .......................... 15 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 W alkdown Approach .................................................................... 18 12/31/14 Page 2 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report 6.3.1 Walkdown Approach ........................................................................... 18 6.3.2 Application of Previous Walkdown Information ................................... 19 6.3.3 Significant Walkdown Findings ........................................................... 19 6.4 HCLPF Calculation Process ......................................................................... 23 6.5 Functional Evaluations of Relays ................................................................. 23 6.6 Tabulated ESEL HCLPF Values (Including Key Failure Modes) ...................... 23 7.0 Inaccessible Item s .................................................................................... 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 Identification of Planned Modifications ..................................................... 28 8.3 Modification Implementation Schedule ..................................................... 28 8.4 Summary of Regulatory Commitments ..................................................... 28 9.0 References ................................................................................................ 29 Attachment A. Wolf Creek Generating Station ESEL ................................. 32 Attachment B. ESEP HCLPF Values and Failure Modes Tabulation ............ 43 12/31/14 Page 3 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station 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 Wolf Creek Generating Station (WCGS). The intent of the ESEP is to perform an interim action in response to the NRC's 50.54(f) letter [1] to demonstrate seismic margin through a review of a subset of the plant equipment that can be relied upon to protect the reactor core following beyond design basis seismic events.

The ESEP is implemented using the methodologies in the NRC endorsed guidance in EPRI 3002000704, Seismic Evaluation Guidance:Augmented Approachfor 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 (Section 2) to develop the initial Expedited Seismic Equipment List (ESEL) and uses an iterative process to develop the final ESEL (Section 3).

The ESEL is later used to evaluate the listed equipment against the review level ground motion (RLGM) data (Section 5) with respect to the equipment's 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 12/31/14 Page 4 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report NRC to understand the inputs used, the evaluations performed, and the decisions made as a result of the interim evaluations.

2.0 Brief Summary of the FLEX Seismic Implementation Strategies The Wolf Creek 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 Wolf Creek 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 make-up from the Turbine Driven Auxiliary Feedwater Pump (TDAFP) during FLEX Phase 1 with suction from the Condensate Storage Tank (CST).

The Phase 2 strategy includes SG cooling water make-up via a FLEX portable pump with suction from the CST, additional CST inventory will be pumped from the Ultimate Heat Sink (UHS). 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 Wolf Creek 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.

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 WCGS [4] is presented in Attachment A.

12/31/14 Page 5 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report 3.1 Equipment Selection Process and ESEL The selection of equipment to be included on the ESEL was based on installed plant equipment credited in the FLEX strategies during Phase 1, 2 and 3 mitigation of a Beyond Design Basis External Event (BDBEE), as outlined in the Wolf Creek Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA-12-049 [3]. The OIP provides the Wolf Creek 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 Wolf Creek 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 Wolf Creek OIP [3].

2. The scope of components is limited to installed plant equipment and the FLEX connections necessary to implement the Wolf Creek 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.

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.

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Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report

• 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 [4] was developed by reviewing the Wolf Creek 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 concern, the following guidance is applied in the Wolf Creek 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.

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Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report

• 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 Wolf Creek 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")."

Item 6 in Section 3 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].

12/31/14 Page 8 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report 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 ESEL.

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 Wolf Creek ESEP [4].

The complete ESEL for Wolf Creek [4] is presented in Attachment A.

4.0 Ground Motion Response Spectrum (GMRS) 4.1 Plot of GMRS Submitted by the Licensee The SSE control point elevation is defined at 1099.5 ft NGVD [6]. At WCGS, this elevation denotes free field at finished grade.

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.

12/31/14 Page 9 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report Table 4-1: UHRS for 10-4 and 10-5 and GMRS at control point for Wolf Creek Freq. (Hz) 10 UHRS (g) 10s UHRS (g) GMRS (g) 100 1.95E-01 6.00E-01 2.88E-01 90 1.96E-01 6.07E-01 2.90E-01 80 1.97E-01 6.16E-01 2.94E-01 70 2.OOE-01 6.30E-01 3.01E-01 60 2.06E-01 6.59E-01 3.13E-01 50 2.20E-01 7.20E-01 3.41E-01 40 2.43E-01 8.14E-01 3.83E-01 35 2.62E-01 8.88E-01 4.17E-01 30 2.93E-01 9.75E-01 4.60E-01 25 3.39E-01 1.11E+00 5.26E-01 20 3.89E-01 1.24E+00 5.89E-01 15 4.80E-01 1.41E+00 6.83E-01 12.5 5.09E-01 1.50E+00 7.27E-01 10 4.87E-01 1.47E+00 7.06E-01 9 4.70E-01 1.40E+00 6.74E-01 8 4.48E-01 1.29E+00 6.28E-01 7 4.25E-01 1.18E+00 5.79E-01 6 3.75E-01 1.03E+00 5.05E-01 5 3.26E-01 8.93E-01 4.38E-01 4 2.50E-01 6.67E-01 3.29E-01 12/31/14 Page 10 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report Freq. (Hz) 10.4 UHRS (g) 10"5 UHRS (g) GMRS (g) 3.5 2.03E-01 5.37E-01 2.65E-01 3 1.68E-01 4.31E-01 2.14E-01 2.5 1.37E-01. 3.41E-01 1.71E-01 2 1.31E-01 3.18E-01 1.60E-01 1.5 1.12E-01 2.66E-01 1.34E-01 1.25 1.O1E-01 2.35E-01 1.19E-01 1 8.46E-02 1.86E-01 9.54E-02 0.9 7.72E-02 1.71E-01 8.74E-02 0.8 7.13E-02 1.58E-01 8.10E-02 0.7 6.58E-02 1.47E-01 7.52E-02 0.6 6.04E-02 1.36E-01 6.94E-02 0.5 5.56E-02 1.26E-01 6.43E-02 0.4 4.45E-02 1.01E-01 5.15E-02 0.35 3.89E-02 8.84E-02 4.50E-02 0.3 3.34E-02 7.58E-02 3.86E-02 0.25 2.78E-02 6.32E-02 3.22E-02 0.2 2.22E-02 5.05E-02 2.57E-02 0.15 1.67E-02 3.79E-02 1.93E-02 0.125 1.39E-02 3.16E-02 1.61E-02 0.1 1.11E-02 2.53E-02 1.29E-02 Figure 4-1 shows the control point UHRS and GMRS.

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Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report Mean Soil UHRS and GMRS at Wolf Creek

2. -

1t5 I - -1E-5UHRS

.2

-GMRS CL

1. A 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 Wolf Creek (5%-

damped response spectra) 4.2 Comparison to SSE The definition of the SSE for Wolf Creek is discussed in Section 2.5.2, 3.7(B),

3.7(S) and Appendix 3C of the USAR [6]. Wolf Creek happens to use a dual SSE approach, one for the power block and one for the non-power block. All ESEL equipment is located within the WCGS power block and therefore only the power block SSE is presented in Table 4-2.

12/31/14 Page 12 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report Table 4-2: SSE for Wolf Creek Power Block Freq (Hz) SA (g) 0.25 0.09 2.50 0.63 9.00 0.52 33.00 0.20 100.00 0.20 As shown in Figure 4-2 the GMRS begins to exceed the power block SSE at around 6.5 Hz.

-SSE Powerblock -GMRS 1.00 A I 000000 4.

00

&M0.10 0.1 1 10 100 Frequency (Hz)

Figure 4-2: Wolf Creek SSE - GMRS Comparison 12/31/14 Page 13 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report 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 [10a]. Examination of Table 4-1 shows that the GMRS spectral acceleration is 0.706 g. The result is a maximum GMRS/SSE ratio between 1 - 10 Hz of 1.47 (witness 0.706 g / 0.48 g = 1.47). The resulting RLGM is shown in Table 5-1 and Figure 5-1.

Table 5-1: RLGM for Wolf Creek (Power Block)

Freq. (Hz) 331 231 91 51 2.51 11 0.25 RLGM (g) 0.29 0.37 0.75 0.83 0.93 0.41 0.14

- SSE Powerblock - GMRS - RLGM (Scaled SSE) 1.00 - 11

.2, 0.10

.I U

0 .0 1

0.1 1 10 100 Frequency (Hz)

Figure 5-1: Wolf Creek RLGM vs GMRS 12/31/14 Page 14 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report 5.2 Method to Estimate In-Structure Response Spectra (ISRS)

The ISRS for Wolf Creek [lOa] uses the scaled approach to estimate the ISRS. As mentioned in Section 5.1, the RLGM is scaled by a factor of 1.47 which is also applied to the existing ISRS curves.

6.0 Seismic Margin Evaluation Approach It is necessary to demonstrate that ESEL items have sufficient seismic capacity to meet or exceed the demand characterized by the RLGM. The seismic capacity is characterized as the 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].

Wolf Creek 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 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.

This conforms to Section 5 of EPRI 3002000704. 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.

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Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report

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.

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 WCGS ESEP project:

" The peak 5% spectral acceleration of the RLGM is 0.93g. This level is in the 2nd screening column (0.8 - 1.2g) of NP-6041-SL, Table 2-

4. Therefore, the 1.2g screening criteria of Table 2-4 were applied (2 nd screening lane).

• A number of components in the Auxiliary/Control Building and one in the RB 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 2 nd screening column and require HCLPF analysis.

Table 6-1 below summarizes application of Table 2-4 screening for the ESEP.

Applied plant grade was Elevation 2000'. Per the USAR, 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 Other generic screening requirements were addressed by walkdown, design review and anchorage verification. These assessments are documented in the screening evaluation work sheets (SEWS) [1Of].

12/31/14 Page 16 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report 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.

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 address by walkdown and design review.

Batteries and racks Note (k) applies. Batteries are in plastic shell frames braced for overturning by steel rods and are designed for seismic loads. HCLPF analyses are required for the battery rack structure and 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.

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.

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.

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.

12/31/14 Page 17 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report 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.

Note (x) applies. Note (x) was addressed by walkdown and Temperature sensors; pressure 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.

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 12/31/14 Page 18 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report guidance of Section 5 of EPRI 3002000704 and Section 2 of NP-6041-SL. 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.

Three walkdown sessions have been performed as indicated below.

Walkdown Date SRT Plant Support Week of March 24,2014 Hunter Young (S&A) Tim Solberg (WCNOC)

Timothy Nealon (S&A) Bud Freeman (WCNOC)

Week of July 20, 2014 Hunter Young (S&A) Tim Solberg (WCNOC)

Samer El-Bahey (S&A)

Week of November 3, 2014 Hunter Young (S&A) Tim Solberg (WCNOC)

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.

12/31/14 Page 19 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station 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 Cabinet Anchorage could not be readily screened out for RLGM. Perform 1E, Train A) -00 HCLPF analysis for anchorage.

2. NG001 480 V LOAD CENTER NG01 CB 2000 Cabinet Anchorage could not be readily screened out for RLGM. Perform

-00 HCLPF analysis for anchorage.

Apply results to similar items NG002 and NG003.

NK001 125 VDC BUS CB 2016 Cabinet Anchorage could not be readily screened out for RLGM. Perform SWITCHBOARD NK0O1 -00 HCLPF analysis for anchorage.

Apply results to similar items NKO03, NKO04, NK041 and NK043.

NK011 125 V BATTERY NK011 CB 2016 Battery rack is not comprised of steel bracing. Perform HCLPF analysis for

-00 plastic frame.

Apply results to similar items NK013 and NK014.

NK011 125 V BATTERY NK011 CB 2016 Rack Anchorage could not be readily screened. Perform HCLPF analysis for

-00 anchorage.

Apply results to similar items NK013 and NK014.

6. NK021 125 V BATTERY CHARGER CB 2016 Cabinet Anchorage could not be readily screened out for RLGM. Perform NK021 -00 HCLPF analysis for anchorage.

Apply results to similar items NK023, NK024, and NK025.

12/31/14 Page 20 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report No. ID Description Bldg Elev Basis for Selection

7. NN011 7.5KVA INVERTER (FED CB 2016 Cabinet Anchorage could not be readily screened out for RLGM. Perform FROM BATT CHARGER -00 HCLPF analysis for anchorage.

NK021)

Apply results to similar items NNO13 and NN014.

PAL02 TDAFW Pump AB 2000 Pump Anchorage could not be readily screened out for RLGM. Perform HCLPF

-00 analysis for anchorage.

RL021 REACTOR AUX CNTRL CB 2047 Console embedded plate could not be readily screened out for RLGM. Perform PANEL -06 HCLPF analysis for embedded plate.

Apply results to similar items RL002, RL005, RL006, RL018, RL022.

RPO53DB BOP INSTR RACK RP053DB CB 2047 Cabinet Anchorage could not be readily screened out for RLGM. Perform

-06 HCLPF analysis for anchorage.

Apply results to similar items RP053AC, RPO53BC, and RP053DA.

11. RP081A T/C SUBCOOLING MONITOR CB 2047 Door cutout sizes exceed threshold of experience database in NP-6041-SL.

CABINET -06 Evaluate component structure (including anchorage) and functionality via HCLPF analysis.

Apply results to similar item RP081B.

12. SE054A W NUC INSTM NIS 1 CB 2047 Cabinet Anchorage could not be readily screened out for RLGM. Perform

-06 HCLPF analysis for anchorage.

12/31/14 Page 21 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report No. ID Description Bldg Elev Basis for Selection

13. TAP01 Condensate Storage Tank YARD 2000 Per NP-6041-SL Table 2-4 seismic capacity cannot be screened and HCLPF

-00 analysis is required for overall seismic capacity. In addition, HCLPF evaluation required for block wall doghouse adjacent to tank.

14. TBN01 REFUELING WATER YARD 2000 Per NP-6041-SL Table 2-4 seismic capacity cannot be screened and HCLPF STORAGE TANK -00 analysis is required for overall seismic capacity.

15. XNG01 4.16-KV/480 V LOAD CB 2000 Transformer Anchorage could not be readily screened out for RLGM. Perform CENTER TRANSFORMER -00 HCLPF analysis for anchorage.

XNG01 FOR LC NG001 Apply results to similar item XNG03.

16. Generic BLOCK WALLS AB/ CB Var. Per N P-6041-SL Table 2-4 seismic capacity cannot be screened and HCLPF analysis is required for block wall seismic capacity.

Affected components include NB001, NG003, TAP01, NK043, NNO03, NNO13, NK041, NN001, NK021, NNO11, NK051, NK001, NK023, NK071, NK073, NK011, NK013, AB007, NK003, RP209, NG001A, NG002, RP334, RP147A/B, NK004, NK074, NNO04, NNO14, NK024, and NK014.

Generic Cabinets containing AB/CB Var. Per 14C4257-RPT-003 [Ref. 5], the following components contain essential essential relays relays that do not screen and require HCLPF evaluation: NG001A, NG002B, NGO03C, NG004, and FC0219.

12/31/14 Page 22 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station 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 the 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].

0 Experience based seismic capacity per the guidelines of EPRI TR-1019200

[131.

Screening of relays within the scope of the ESEP (in accordance with EPRI 3002000704) is conducted within 14C4257-RPT-003 [5]. Cabinets requiring a 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 [1Oe] containing the detailed HCLPF calculations are also identified.

Note that for the CST (TAPOl) and RWST (TBNO1) the applied ground motion and HCLPF are based on the GMRS [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 0.29.

Tabulated HCLPF Values All HCLPF values for screened-out items equals or exceeds the RLGM HCLPF > 0.29g HCLPF for screened-out items and failure modes 12/31/14 Page 23 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report Unless justified by calculations, the above HCLPF is applicable for screened-out items and covers all 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 HCLPF' Failure Mode Basis Related Components (g, PGA) knalyzed

1. NBO01 4.16KVSWGR NB001 CB 2000- 0.37 Equipment L4C4257-CAL- n/a (Class 1E, Train A) 00 -apacity and D05 nchorage 2 NGO01 480 V LOAD CENTER CB 2000- 0.29 Equipment .4C4257-CAL- NG002, NG003 NG01 00 capacity and )05 anchorage NK001 125 VDC BUS CB 2016- 0.32 Equipment 4C4257-CAL- NK003, NKO04, NK041, SWITCHBOARD NKO01 00 capacity and 05 NK043, NNO03 anchorage NK011 125 V BATTERY NK011 CB 2016- 0.45 Anchorage L4C4257-CAL- NK013, NKO14 00 304 NK011 125 V BATTERY NK011 CB 2016- 0.69 Equipment 14C4257-CAL- NK013, NK014 00 capacity 305

6. NK021 125 V BATTERY CB 2016- 2.24 Anchorage [4C4257-CAL- NK023, NK024, NK025 CHARGER NK021 00 )04 NN011 7.5KVA INVERTER (FED CB 2016- 0.68 Anchorage 14C4257-CAL- NN013, NNO14 FROM BATT CHARGER 00 )04 NK021)

8. PAL02 TDAFW Pump AB 2000- 1.70 nchorage 4C4257-CAL- n/a 00 04 RL021 REACTOR AUX CNTRL CB 2047- 0.32 Anchorage 4C4257-CAL- L002, RLO05, RLO06, PANEL 06 04 RL018, RL022 1 HCLPFs based upon RLGM (PGA=0.29g) as the seismic margins earthquake with the exception of TAP01, TBNO1, and the CST pipe house block walls, which are based upon the GMRS (PGA=0.29g).

12/31/14 Page 24 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report No. ID Description Bldg Elev HCLPF1 Fallure Mode Basis Related Components (g, PGA) Analyzed

10. RP053DB BOP INSTR RACK CB 2047- 0.56 Anchorage 14C4257-CAL- RP053AC, RP053BC, RP053DB 06 )04 RP053DA RP081A T/C SUBCOOLING CB 2047- 0.61 Equipment 14C4257-CAL- RP081B MONITOR CABINET 06 capacity and )05 nchorage

12. SE054A W NUC INSTM NIS 1 CB 2047- 0.86 Anchorage 14C4257-CAL- n/a 06 004

13. TAP01 Condensate Storage YARD 2000- 0.30 Equipment 14C4257-CAL- n/a Tank 00 apacity and D02 nchorage

14. TBN01 REFUELING WATER YARD 2000- 0.32 Equipment 14C4257-CAL- r/a STORAGE TANK 00 capacity and 302 anchorage

15. XNG01 4.16-KV/480 VLOAD CB 2000- 0.47 Anchorage 14C4257-CAL- KNG03 CENTER 00 304 TRANSFORMER XNG01 FOR LC NG001

16. Generic BLOCK WALLS AB/ Var.

CB CTRL All block walls on CTRL CB 2000- 2.66 Seismic 14C4257-CAL- NB001, NG003, NGOO1A, 2000' 2000' elev 00 nteraction D03 4G002, RP334, RP147A/B, CTRL All block walls no CTRL CB 2016- 1.85 Seismic 14C4257-CAL- 4K043, NNO03, NNO13, 2016' 2016' elev 00 nteraction 003 4K041, NNO01, NK021, 1NO11, NK051, NK001, 1K023, NK071, NK073, 1K011, NK013, AB007, NK003, NK004, NK074, IN004, NNO14, NK024, 1K014 AUX 2000' 2000' elev wall on AUX 2000- 1.15 Seismic 14C4257-CAL- RP209 column line AF north 00 nteraction )03 of Stair A-2 CST House CST Pipe house YARD 2000- 0.37 eismic 4C4257-CAL- FAP01 masonry walls 00 nteraction 103 12/31/14 Page 25 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report No. ID Description Bldg Elev HCLPF' Failure Mode Basis Related Components (g, PGA) Analyzed

17. Generic Cabinets containing AB/CB Var.

essential relays NG003C MCC NG03C BUS CB 2047- 0.44 Functional 14C4257-CAL- NG001A, NG002B, NG004C 06 :apacity and host )05 omponent capacity FC0219 LOCAL CONTROL AB 2000- 0.61 Functional 14C4257-CAL- n/a PANEL FOR TD AFW 00 capacity and host )05 PUMP 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 Wolf Creek has performed the ESEP as an interim action in response to the NRC's 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 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 Wolf Creek response to the NRC's 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."

12/31/14 Page 26 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report The NRC's 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 GI-199 safety/risk assessment." The letter also stated that, "As a result, the staff has confirmed that the conclusions reached in GI-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 Wolf Creek was included in the fleet risk evaluation submitted in the March 12, 2014 NEI letter [14] therefore, the conclusions in the NRC's May 9 letter [15] also apply to Wolf Creek.

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 structures, systems and components (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

• 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.

12/31/14 Page 27 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report The intent of the ESEP is to perform an interim action in response to the NRC's 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 plant's SSE rather than the actual GIMRS (except for the CST and RWST, as explained previously in Section 6.6 of this report). To more fully characterize the risk impacts of the seismic ground motion represented by the GIMRS 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 Wolf Creek Seismic Hazard and GIMRS submittal [7], Wolf Creek 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. Wolf Creek will complete that evaluation in accordance with the schedule identified in NEI's letter dated April 9, 2013 [171 and endorsed by the NRC in their May 7, 2013 letter [2].

8.2 Identification of Planned Modifications This report presents the seismic evaluation results for the ESEP as applied to WCGS. A primary goal of the ESEP is to demonstrate that the HCLPF seismic capacities of ESEL items bound the RLGM seismic demand. No ESEL items had HCLPF seismic capacities below the RLGM, and, as such, no modifications are planned.

8.3 Modification Implementation Schedule Wolf Creek did not have any equipment with HCLPF seismic capacities below the RLGM and, as such, is not planning any modifications.

8.4 Summary of Regulatory Commitments Per Section 8.3, Wolf Creek does not have any planned modifications and, as such, does not have any regulatory commitments as the result of the ESEP.

12/31/14 Page 28 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station 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 FukushimaDai-lchi 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. WCNOC Overall Integrated Plan (OIP) in Response to the March 12, 2012, Commission Order EA-12-049

a. WCNOC Letter WO 13-0014, "Wolf Creek Nuclear Operating Corporation 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 28, 2013. ADAMS Accession No. ML13070A026.

b. WCNOC Letter ET 13-0027, "Wolf Creek Nuclear Operating Corporation's First Six-Month Status Report for the Implementation of Order EA 049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," August 28, 2013. ADAMS Accession No. ML13247A277.

c. WCNOC Letter ET 14-0011, "Wolf Creek Nuclear Operating Corporation's Second Six-Month Status Report for the Implementation of Order EA 049, 'Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," February 26, 2014. ADAMS Accession No. ML14064A190.

d. WCNOC Letter ET 14-0024, "Wolf Creek Nuclear Operating Corporation's Third Six-Month Status Report for the Implementation of Order EA 049, 'Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events," August 28, 2014. ADAMS Accession No. ML14246A191.

4. SAP-14-126 "Transmittal of Revision 4 of the Wolf Creek ESEL for ESEP Submittal Report", December 2014.

5. S&A Report 14C4257-RPT-003 Rev. 0, "Wolf Creek ESEL Relay Assessment,"

December 2014.

12/31/14 Page 29 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report

6. WCNOC USAR, "Wolf Creek Updated Safety Analysis Report (USAR)," Revision 27, March 2014.

7. WCNOC Letter WO 14-0042, "Wolf Creek Nuclear Operating Corporation's Seismic Hazard and Screening Report (CEUS Sites), Response NRC Request for information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident,",

March 31, 2014. ADAMS Accession No. ML14097A020.

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 Documents:

a. 14C4257-CAL-001, Revision. 2, "Generation of Scaled In-Structure Response Spectra for WCGS," December 2014.

b. 14C4257-CAL-002, Revision 0, "Seismic Capacity of CST (TAP01) and RWST (TBN01)," December 2014.

c. 14C4257-CAL-003, Revision 0, "HCLPF Analyses for Block Walls,"

December 2014.

d. 14C4257-CAL-004, Revision 0, "HCLPF Seismic Capacity Evaluations of Anchorage for Selected Equipment," December 2014.

e. 14C4257-CAL-005, Revision 0, "HCLPF Analysis of Components Based on Seismic Test Data," December 2014.

f. 14C4257-RPT-002, Revision 1, "Seismic Evaluation of Equipment at WCGS for the Expedited Seismic Evaluation Process," December 2014.

11. Wolf Creek Generating Station 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 E. J. Leeds, USNRC, "Seismic Risk Evaluations 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 Recommendation 2.1 of the Near-Term Task Force Review of Insights From the 12/31/14 Page 30 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report Fukushima Dai-Ichi Accident," May 9, 2014. ADAMS Accession No. ML14111A147.

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.

12/31/14 Page 31 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report Attachment A. Wolf Creek Generating Station ESEL 12/31/14 Page 32 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL Equipment " Operating State Item: ID ..".d_______

.... __.Dsrito__.. ..... Normal Desired' Notes/Comments[l]

Num " IDtDescription.st . State

.".."** Mechanical ESEL Items 1 TAP01 Condensate Storage Tank SG Makeup with SGs Available - Phase Operable Operable 1, Phase 2, Phase 3 2 PAL02 TDAFW Pump Not I Operating Operating SG Makeup with SGs Available - Phase 1 3 ALHVOO34 MOV 3ALHV0034

_ _ MOOpen Closed SG Makeup with SGs Available - Phase 1 4 ALHV0035 MOV Open Closed SG Makeup with SGs Available - Phase 1 5 ALFE0049 Flow Element SG Makeup with SGs Available - Phase 1 6 ALHV0012 Air Operated Valve SG Makeup with SGs Available - Phase Open Open 1, Phase 2, Phase 3 7 ALFE0004 Flow Element SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 8 ALFT0004 Flow Transmitter SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 9 ALFT0011 Flow Transmitter SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 10 ALHV0010 Air Operated Valve SG Makeup with SGs Available - Phase Open Open 1, Phase 2, Phase 3 11 ALFE0003 Flow Element SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 12 ALFTO003 Flow Transmitter SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 13 ALFT0009 Flow Transmitter SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 14 ALHV0008 Air Operated Valve SG Makeup with SGs Available - Phase Open Open 1, Phase 2, Phase 3 15 ALFE0002 Flow Element SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 16 ALFT0002 Flow Transmitter SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 17 ALFT0007 Flow Transmitter SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 18 ALHV0006 Air Operated Valve SG Makeup with SGs Available - Phase Open Open 1, Phase 2, Phase 3 19 ALFE0001 Flow Element SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 20 ALFT0001 Flow Transmitter SG Makeup with SGs Available - Phase 1, Phase 2, Phase 3 21 ABHV0005 Air Operated Valve Closed Fail Open SG Makeup with SGs Available - Phase 1 22 ABHV0048 Air Operated Valve Open Fail Closed SG Makeup with SGs Available - Phase 1 23 ABHV0006 Air Operated Valve Closed Fail Open SG Makeup with SGs Available - Phase 1 24 ABHV0049 Air Operated Valve Open Fail Closed SG Makeup with SGs Available - Phase 1 12/31/14 Page 33 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL .____:______ Equipment .. Operating State ,

Item " Normal "Desired Notes/Comments[.1]

Num IS State State 25 FCFV0310 Level Control Valve Open Closed SG Makeup with SGs Available - Phase 1 26 FCLT0010 Level Indicator SG Makeup with SGs Available - Phase 1 27 FCHV0312 Trip and Throttle Valve Closed Operating SG Makeup with SGs Available - Phase 1 28 Speed Speed Governor Governor Standby Operating SG Makeup with SGs Available - Phase 1 29 FCFV0313 Speed Governor Valve Open Operating SG Makeup with SGs Available - Phase 1 30 KFC02 AFW Pump Turbine Not Operating Operating SG Makeup with SGs Available - Phase 1 31 TEM01 Boron Injection Tank RCS Makeup with SGs not Available -

Phase 2, Phase 3 32 EMPT0947 BIT Outlet Pressure RCS Makeup with SGs not Available -

Transmitter Phase 2, Phase 3 33 EMP10947 BIT Outlet Pressure RCS Makeup with SGs not Available -

Indicator Phase 2, Phase 3 34 EMHV8801B MOTOR-OPERATED VALVE RCS Makeup with SGs not Available -

EMHV8801B Closed Open Phase 2, Phase 3 EMFE0924 ECCS FLOW TO RCS COLD- RCS Makeup with SGs not Available -

LEG 1 Phase 2, Phase 3 36 EMFE0925 ECCS FLOW TO RCS COLD- RCS Makeup with SGs not Available -

LEG 2 Phase 2, Phase 3 37 EMFE0926 ECCS FLOW TO RCS COLD- RCS Makeup with SGs not Available -

LEG 3 Phase 2, Phase 3 38 EMFE0927 ECCS FLOW TO RCS COLD- RCS Makeup with SGs not Available -

LEG 4 Phase 2, Phase 3 39 TBN01 RWST RCS Makeup with SGs not Available -

Phase 1 40 BNLT0930 RWST Level Transmitter RCS Makeup with SGs not Available -

Phase 1 41 EJFCV0610 RHR PUMP A MINIFLOW RCS Makeup with SGs not Available -

VALVE Open Closed Phase 1 42 TBGO3A Boric Acid Tank RCS Makeup with SGs Available - Phase 2, Phase 3 43 BGLT0102 BORIC ACID TANK A LEV RCS Makeup with SGs Available - Phase 2, Phase 3 44 BGLI0102 BORIC ACID TANK A LEV RCS Makeup with SGs Available - Phase I_ 1 1 2, Phase 3 45 BBPV8702A RHR TO RCS RCS Makeup with SGs not Available -

I Closed Open Phase I Electrical ESEL Items 4.16KV SWGR NB0O1 (Class This component is powered by the FLEX 1E, Train A) DG in Phase 3 as stated in Sec. 8 of the N/A N/A WC Integrated FLEX Plan 4.16 kV FDR BKR FOR RHRP- This component is powered by the FLEX A DPEJ01A (Residual Heat DG in Phase 3 as stated in Sec. 8 of the Removal Pump A) N/A N/A WC Integrated FLEX Plan 12/31/14 Page 34 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL Equipment Operating:State item.*... . .. " ID," * " "*" De*;dription Normal

. . Desired Notes/Comments[1]

Num Descrptio State SD State _

48 NB00107 4.16 kV FDR BKR FOR CCWP-A DPEG01A This component is powered by the FLEX (Component Cooling Water DG in Phase 3 as stated in Sec. 8 of the Pump A) N/A N/A WC Integrated FLEX Plan 49 NBOO110 4.16 kV FDR BKR FOR XFMR XNG03 (4160 Vto 480 Vfor Although this component is not part of LC NG003) the current FLEX Phase 3 plan, WCNOC has decided to add this to the ESEL in N/A N/A order to independently power NG03 50 NBOO113 4.16 kV FDR BKR FOR XFMR This component is powered by the FLEX XNG01 (4160 V to 480 Vfor DG in Phase 3 as stated in Sec. 8 of the LC NG001) N/A N/A WC Integrated FLEX Plan 51 NBO0109 4.16 kV FLEX GEN TIE-IN This component is powered by the FLEX POINT (BKR) FOR TRAIN A DG in Phase 3 as stated in Sec. 8 of the N/A N/A WC Integrated FLEX Plan 52 XNG01 4.16-KV/480 V LOAD This component is powered by the FLEX CENTER TRANSFORMER DG in Phase 3 as stated in Sec. 8 of the XNG01 FOR LC NG001 N/A N/A WC Integrated FLEX Plan 53 NG001 480 V LOAD CENTER NG01 This component is powered by the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 54 NG00101 MAIN BKR FOR LC NG01 This component is powered by the FLEX DG in Phase 3 as stated in Sec. 8 of the N/A N/A WC Integrated FLEX Plan 55 NG00103 FDR BKR FOR 125 VVITAL This component is powered by the FLEX BATTERY CHARGER NK021 DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 56 NG00112 FLEX 500 kW TIE INBRK This component is powered by the FLEX (Phase 2 connection point) DG in Phase 2 as stated in Sec. 8 of the N/A N/A WC Integrated FLEX Plan 57 NG00116 TIE BKR (CONNECTS NG01 This component is powered by the FLEX AND NG03) DG in Phase 2 as stated in Sec. 8 of the N/A N/A WC Integrated FLEX Plan 58 XNG03 4.16-KV/480 V LOAD CENTER TRANSFORMER Although this component is not part of XNG03 FOR LC NG003 the current FLEX Phase 3 plan, WCNOC has decided to add this to the ESEL in N/A N/A order to independently power NG03 59 NG003 480 V LOAD CENTER NG03 This component is powered by the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 60 NG00301 MAIN BKR FOR LC NG03 Although this component is not part of the current FLEX Phase 3 plan, WCNOC has decided to add this to the ESEL in I N/A N/A order to independently power NG03 12/31/14 Page 35 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL ,,.._,______ Equipment Operating. State::...

Item De -d Notes/Comments[!]

Nu.. [ ID b.m Descrption  : "oralte"ired Nmstate State _______________

61 NG00303 FDR BKR FOR 125 V VITAL This component is powered by the FLEX BATTERY CHARGER NK023 DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 62 NK021 125 V BATTERY CHARGER This component is powered by the FLEX NK021 DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 63 NK071 TRANSFER SWITCH BUS This component is powered by the FLEX NK01 BATTERY CHARGER DG, first Phase 2, then in Phase 3, as NK21/NK25 stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 64 NK001 125 VDC BUS SWITCHBOARD NK001 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 65 NK00102 FDR BKR FROM BATT CHGR This component is powered by the FLEX NK021 TO NK001 DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 66 NK00104 MAIN BREAKER FOR CNTRL AND DIST PNL NK041 (PART This component is powered during ALL OF SWBD NK001) phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 67 NK00105 MAIN BREAKER FOR CNTRL AND DIST PNL NKO51 This component is powered during ALL (PART OF SWBD NK001) phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 68 NK011 125 V BATTERY NK011 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 69 NK00101 ISOLATION BKR FOR BATTERY NK011 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 70 NK00111 FDR BKR FOR INVERTER NN011 (PART OF SWBD This component is powered during ALL NKO01) phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 71 NN011 7.5KVA INVERTER (FED FROM BATT CHARGER This component is powered during ALL NK021) phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 72 NNO01 Class 1E AC DIST SWBD NNO1 (SEP GRP 1) This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 12/31/14 Page 36 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESELE:. Equipment :Operating state. ..... .. . . * .

. ID...

teum" Normal.De"re...Descriptionents[]

NuIri State State:.. "

73 SA036A ESFAS CHI TERM This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 74 SENY0060A NEUTRON FLUX MONITORING SYSTEM This component is powered during ALL DETECTOR AMPLIFIER SENY phases of the FLEX strategy as stated in 60A N/A N/A Sec. 8 of the WC Integrated FLEX Plan 75 SENY0060B NEUTRON FLUX MONITORING SYSTEM This component is powered during ALL DETECTOR AMPLIFIER SENY phases of the FLEX strategy as stated in 60B N/A N/A Sec. 8 of the WC Integrated FLEX Plan 76 SB032A W SS PROT SYS INPUT TRN B This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 77 SB029A W SS PROT SYS INPUT TRN A This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 78 SB038 W PROCESS ANALOG PROTECTION SET CAB-01 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 79 SB029D W SS PROT SYS OUT 2 TRN A This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 80 SE054A W NUC INSTM NIS 1 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 81 SB030A SSPS TRN A #1 TEST This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 82 RPOS3AC BOP INSTRUMENTATION RACK (TERMINATION AREA) This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 83 5B078 RPV LEVEL INSTR SYS (RVLIS) PROC PROT SYS This component is powered during ALL CABINET phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 84 RP081A T/C SUBCOOLING MONITOR CABINET This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 12/31/14 Page 37 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL. Equipment Operating.&State:: .

Item Normail  : Desired:. Notes/Comments[l-]

Num ":ID DscriptionState State 85 NK041 CNTRL & INSTR DIST SWBD NK041 (CLASS 1E 125 VDC) This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 86 RL005 TURBINE GENERATOR AND FW CONSOLE This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 87 RL006 TURBINE GENERATOR AND FW CONSOLE This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 88 RP139 BAUXILIARY RELAY RACK RP139 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 89 NK051 CNTRL & INSTR DIST SWBD NK051 (CLASS 1E 125 VDC) This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 90 BBPCV0455A BBPCV0455A PORV SOLENOID FAILS TO OPEN This component is powered during ALL ON DEMAND phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 91 RL021 REACTOR AUX CNTRL PANEL This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 92 RL022 REACTOR AUX CNTRL PANEL This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 93 RP209 BAUXILIARY RELAY RACK This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 94 RP289 DC DIST PNL RP289 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 95 RP330 AUX RELAY RACK RP330 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 96 RP332 B AUXILIARY RELAY RACK This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 12/31/14 Page 38 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report

.,ESEL ,Equipment Operating State Item. Normal. Desired Notes/Comments[1]

Num ID .....Description: .. state State 97 NK051A EM'CY LIGHTING DIST SWBD NK051A (SUBPNL OF This component is powered during ALL NK051) phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 98 NK023 125 V BATTERY CHARGER This component is powered by the FLEX NK023 DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 99 NK073 TRANSFER SWITCH BUS This component is powered by the FLEX NK03 BATTERY CHARGER DG, first Phase 2, then in Phase 3, as NK23/NK25 stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 100 NK003 125 VDC BUS SWITCHBOARD NK003 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 101 NK00302 FDR BKR FROM BAnT CHGR This component is powered by the FLEX NK023 TO NK003 DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 102 NK00304 MAIN BREAKER FOR CNTRL AND DIST PNL NK043 This component is powered during ALL (PART OF SWBD NK003) phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 103 NK013 125 V BATTERY NK013 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 104 NK00301 ISOLATION BKR FOR BATTERY NK013 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 105 NK00311 FOR BKR FOR INVERTER NNO13 (PART OF SWBD This component is powered during ALL NK003) phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 106 NN013 7.5KVA INVERTER (FED FROM BATT CHARGER This component is powered during ALL NK023) phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 107 NNO03 Class 1E AC DIST SWBD NN03 (SEP GRP 3) This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 108 RP053DB BOP INSTR RACK RP053DB This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 12/31/14 Page 39 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report

.ESEL ________.... Equipment... OperatingState item Normal Desired Notes/Commentsll Num ID DeScription state state 109 SB037 W PROCESS ANALOG PROTECTION SET CAB-03 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 110 NK043 CNTRL & INSTR DIST SWBD NK043 (CLASS 1E 125 VDC) This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 111 AB007 Aux Relay Rack This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 112 NG00109 FDR BKR FOR 125 V SWING This component provides power to BATTERY CHARGER NK025 NK025 and, in turn, Separation Group N/A N/A 1.

113 NK025 125 V BATTERY CHARGER NK025 (Swing Battery The A-Train swing charger will be used Charger) N/A N/A to power Separation Group 1.

114 NG002 480 V LOAD CENTER NG02 This component is powered by the FLEX DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 115 NG00212 FLEX 500 kW TIE INBKR This component is powered by the FLEX from FD201 (Phase 2 DG, first Phase 2, then in Phase 3, as connection point) stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 116 NG00203 FDR BKR FOR 125 V VITAL This component is powered by the FLEX BATTERY CHARGER NK024 DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 117 NK024 125 V BATTERY CHARGER This component is powered by the FLEX NK024 DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 118 NK074 TRANSFER SWITCH BUS This component is powered by the FLEX NK04 BATTERY CHARGER DG, first Phase 2, then in Phase 3, as NK24/NK26 stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 119 NK004 125 VDC BUS SWITCHBOARD NK004 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 120 NK00402 FDR BKR FROM BATT CHGR This component is powered by the FLEX NK024 TO NK004 DG, first Phase 2, then in Phase 3, as stated in Sec. 8 of the WC Integrated N/A N/A FLEX Plan 121 NK014 125 V BATTERY NK014 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 12/31/14 Page 40 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL Equipment. Operating State Item:Num::

" ID ' . .. -.Description.,Sae Normal Desired "sae ".... Notes/Comments(11 Num State State ________________

122 NK00401 ISOLATION BKR FOR BATTERY NK014 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 123 NK00411 FDR BKR FOR INVERTER NN011 (PART OF SWBD This component is powered during ALL NK004) phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 124 NNO14 7.5KVA INVERTER (FED FROM BATT CHARGER This component is powered during ALL NK024) phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 125 NNO04 Class 1E AC DIST SWBD NN04 (SEP GRP 4) This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 126 SA036B ESFAS CH4 TERM This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 127 RP147B BOP Instrumentation Rack RP147B This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 128 SENY0061A NEUTRON FLUX MONITORING SYSTEM This component is powered during ALL DETECTOR AMPLIFIER SENY phases of the FLEX strategy as stated in 61A N/A N/A Sec. 8 of the WC Integrated FLEX Plan 129 SENYO061B NEUTRON FLUX MONITORING SYSTEM This component is powered during ALL DETECTOR AMPLIFIER SENY phases of the FLEX strategy as stated in 61B N/A N/A Sec. 8 of the WC Integrated FLEX Plan 130 SB032D W SSPS Train B #2 Output This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 131 SB033A SSPS Train B#1 Test This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 132 SB041 W PROCESS ANALOG PROTECTION SET CAB-04 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 133 RP053BC BOP Instrumentation Rack RPO53BC This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 12/31/14 Page 41 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL .Eqtipment Operating State Nm I.D Description Normal Desired Notes/Comments[l]

State State 134 SB079 RVLIS Process Cabinet SB079 This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 135 RP081B Subcooling Monitor Cabinet This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 136 SB148B W PROCESS PROTECTION (Fire Isolation) This component is powered during ALL phases of the FLEX strategy as stated in N/A N/A Sec. 8 of the WC Integrated FLEX Plan 12/31/14 Page 42 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station 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 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. 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 2 nd screening lane of NP-6041-SL, Table 2-4. Since the WCGS RLGM has a peak spectral acceleration of 0.93g and PGA of 0.29g [Reference 10e], the 1.2g peak spectral acceleration corresponds with a PGA of 0.38g (witness 1.2g/0.93g*0.29g=0.38g). For equipment located above 40', the equipment capacity is conservatively assigned at the RLGM level of 0.29g.

4. For the CST and RWST only (TAP01 and TBN01, respectively), the applied ground motion was based on the GMRS (PGA = 0.29).

S. As a result of the relay chatter evaluation, additional items were added to the ESEL list for evaluation.

12/31/14 Page 43 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report Table B-i: HCLPF Values ESEL HCLPF Item ID Description Bldg Elev Failure Mode Basis Number (g, PGA)

Tank and anchorage capacity evaluated in Condensate 2000- Equipment 14C4257-CAL-002.Anchorage evaluated per Storage Tank 00 Capacity 14C4257-CAL-004. Block wall evaluated per 14C4257-CAL-003.

2000- Equipment Component per se screened. Anchorage 00 Capacity evaluated per 14C4257-CAL-004.

3 ALHV0034 MOV AUX 18 >RLGM Screened SRT disposition 1988-4 ALHV0035 MOV AUX 00 >RLGM Screened SRT disposition 2000-5 ALFE0049 Flow Element AUX 00 >RLGM Screened SRT disposition 2004-6 ALHV0012 Air Operated Valve AUX 07 >RLGM Screened SRT disposition 2000-7 ALFE0004 Flow Element AUX 00 >RLGM Screened SRT disposition 2016-8 ALFT0004 Flow Transmitter AUX 01 >RLGM Screened SRT disposition 2000-9 ALFT0011 Flow Transmitter AUX 00 >RLGM Screened SRT disposition 2002-10 ALHV0010 Air Operated Valve AUX 09 >RLGM Screened SRT disposition 2000-11 ALFE0003 Flow Element AUX 00 >RLGM Screened SRT disposition 2016-12 ALFT0003 Flow Transmitter AUX 00 >RLGM Screened SRT disposition 2000-13 ALFTOO09 Flow Transmitter AUX 00 >RLGM Screened SRT disposition 2004-14 ALHV0008 Air Operated Valve AUX 00 >RLGM Screened SRT disposition 2000-15 ALFE0002 Flow Element AUX 00 >RLGM Screened SRT disposition 2016-16 ALFT0002 Flow Transmitter AUX 00 >RLGM Screened SRT disposition 2000-17 ALFTO007 Flow Transmitter AUX >RLGM Screened SRT disposition 18 ALHV0006 Air Operated Valve AUX 06 >RLGM Screened SRT disposition 0600-19 ALFEO001 Flow Element AUX 00 >RLGM Screened SRT disposition 2001-20 ALFT0001 Flow Transmitter AUX 00 >RLGM Screened SRT disposition 0027-21 ABHV0005 Air Operated Valve AUX 20 >RLGM Screened SRT disposition 2026-22 ABHV0048 Air Operated Valve AUX 00 >RLGM Screened SRT disposition 23 ABHVO006 Air Operated Valve AUX 20 >RLGM Screened SRT disposition 21026 24 ABHV0049 Air Operated Valve AUX 00 >RLGM Screened SRT disposition 25 FCFV0310 Level Control Valve >RLGM Screened SRT disposition 26 FCLTO010 Level Indicator >RLGM Screened SRT disposition 27 FCHV0312 Trip and Throttle AUX 2000- >RLGM Screened SRT disposition I Valve A 00 M S 12/31/14 Page 44 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Item ID Description Bldg Elev Failure Mode Basis Number (g, PGA) 2Speed SpedGveror2000- Equipment Item is ROB to PAL02. Component per se 28 Spveer Speed Governor AUX 00 0.38 Euipmty screened. Anchorage evaluated per Governor 00 Capacity 14C4257-CAL-004.

Item is ROB to PAL02. Component per se 29 FCFV0313 Speed Governor AUX 2000- 0.38 Equipment screened. Anchorage evaluated per AUXv0.38 Capacity 14C4257-CAL-004.

2000-Equiment Item PALO2. Component isROB toAnchorage per se 30 KFC02 AFW Pump Turbine AUX 2000- 0.38 Equipment screened. evaluated per 00 8 Capacity 14C4257-CAL-004.

Boron Injection 1974-31 TEM01 Tank AUX >RLGM Screened SRT disposition BIT Outlet Pressure 1974-32 EMPT0947 TrOutter AUX O7 >RLGM Screened SRT disposition Transmitter 00 CBT 0.20 Equipment Item is ROB to RL018. Component per se 33 EMPI0947 BIT Outlet Pressure CB 2047- 0.29 it screened. Anchorage evaluated per Indicator 06 Capacity 14C4257-CAL-004.

MOTOR-OPERATED 2002-34 EMHV8801B MOTOR-OPHV880DB AUX O0 >RLGM Screened SRT disposition VALVE EMHVE881B 00 35 EMFE0924 COLD-LEG 1 RB 06 >RLGM Screened SRT disposition ECCS FLOW COLD-EG TO106 RCS 1998-36 EMFE0925 COWD-OEG CS RB 06 >RLGM Screened SRT disposition ECCS FLOW TO2RCS COLD-LEG 1998-06 37 EMFE0926 COWD-LE RCS RB 19 >RLGM Screened SRT disposition ECCSCOLD-LEG FLOW TO3RCS 1998-06 38 EMFE0927 ECSFO ORS RB 19- >RLGM Screened SRT disposition COLD-LEG 4 06 0.32- Equipment Tank and anchorage capacity evaluated in 39 TBNO1 RWST YRD 2000- 0.32 Equit 14C4257-CAL-002.Anchorage evaluated per 00 Capacity 14C4257-CAL-004.

RWST Level 1993-40 BNLT0930 Transmitter YRD O0 >RLGM Screened SRT disposition RHR PUMP A 1968-41 EJFCV0610 MINOFLOW A AUX 1 >RLGM Screened SRT disposition MINIFLOW VALVE 01 1974-42 TBGO3A Boric Acid Tank AUX O0 >RLGM Screened SRT disposition

______________00 BORIC ACID TANK A 2047-43 BGLT0102 B AV CB 20 >RLGM Screened SRT disposition

________ LEV 06 _____

Item is ROB to RLO02. Component per se 44 BGLI0102 BORIC ACID TANK A 2047- Equipment screened. Anchorage evaluated per LEV C 06 Capacity 14C4257-CAL-004.

2007-45 BBPV8702A RHR TO RCS RB 09 >RLGM Screened SRT disposition 4.16KV SWGR Equipment capacity evaluated in 14C4257-411 SWGR 2000- Equipment CAL-005. Anchorage evaluated per 14C4257-Train A) E0 Capacity CAL-005. Block wall evaluated per 14C4257-CAL-003.

4.16 kV FDR BKR Item is ROB to NBO01. Equipment capacity FOR RHRP-A 2000- Equipment evaluated in 14C4257-CAL-005. Anchorage 47 NBOO101 DPEJ01A (Residual CB 0.36 Capacity evaluated per 14C4257-CAL-005. Block wall Heat Removal 00 Pump A) evaluated per 14C4257-CAL-003.

4.16 kV FDR BKR FOR CCWP-A Item is ROB to NB001. Equipment capacity DPEG01A 2000- Equipment evaluated in 14C4257-CAL-005. Anchorage (Component 00 Capacity evaluated per 14C4257-CAL-005. Block wall Cooling Water evaluated per 14C4257-CAL-003.

Pump A) 12/31/14 Page 45 of 51

Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Item ID Description Bldg Elev Failure Mode Basis Number (g, PGA) 4.16 kV FDR BKR Item is ROB to NBO01. Equipment capacity FOR XFMR XNG03 2000- Equipment evaluated in 14C4257-CAL-005. Anchorage (4160 V to 480 V 00 Capacity evaluated per 14C4257-CAL-005. Block wall for LC NG003) _ evaluated per 14C4257-CAL-003.

4.16 kV FDR BKR Item is ROB to NBO01. Equipment capacity FOR XFMR XNG01 2000- Equipment evaluated in 14C4257-CAL-005. Anchorage (4160 V to 480 V 00 Capacity evaluated per 14C4257-CAL-005. Block wall for LC NG001) evaluated per 14C4257-CAL-003.

4.16 kV FLEX GEN Item is ROB to NBOO1. Equipment capacity 4.1 kV1P FX NT C 2000- Equipment evaluated in 14C4257-CAL-005. Anchorage FOR TRAIN A 00 Capacity evaluated per 14C4257-CAL-005. Block wall evaluated per 14C4257-CAL-003.

4.16-KV/480 V LOAD CENTER 52 CENTER 2000- Equipment Component per se screened. Anchorage 52 XNG01 TRANSFORMER CB/CC 00 0.38 Capacity evaluated per 14C4257-CAL-004.

XNG01 FOR LC NG001 Equipment capacity evaluated in 14C4257-53 NG001 480 V LOAD CB/CC 2000- 0.29 Equipment CAL-005. Anchorage evaluated per 14C4257-CENTER NG1 C 00 0 Capacity CAL-005.

Item is ROB to NG001. Equipment capacity 54 NG00101 MAIN BKR FOR LC 2000- 0.29 Equipment evaluated in 14C4257-CAL-005. Anchorage NG01 CB 0 9 Capacity evaluated per 14C4257-CAL-005.

FDR BKR FOR 125 V 0.29 Equipment Item is ROB to NG001. Equipment capacity 55 NG00103 VITAL BAFERY CB 2000- 0.29 Equit evaluated in 14C4257-CAL-005. Anchorage CHARGER NK021 00 Capacity evaluated per 14C4257-CAL-005.

Item is ROB to NGO01. Equipment capacity 56 NG00112 FLEX 350kW TIE IN 2000- 0.29 Equipment evaluated in 14C4257-CAL-005. Anchorage CBR0.29 Capacity evaluated per 14C4257-CAL-005.

Item is ROB to NG001. Equipment capacity 57 NG00116 NG01 AND NG03) CB 00 0.29 Capacit evaluated in 14C4257-CAL-005. Anchorage evaluated per 14C4257-CAL-005.

4.16-KV/480 V LOAD CENTER 2000- Equipment Component per se screened. Anchorage 58 XNG03 TRANSFORMER CB/CC 00 0.38 Capacity evaluated per 14C4257-CAL-004.

XNG03 FOR LC NG003 Equipment capacity evaluated in 14C4257-59 NG003 480 V LOAD 2000- Equipment CAL-005. Anchorage evaluated per 14C4257-CENTER NG03 00 Capacity CAL-005. Block wall evaluated per 14C4257-CAL-003.

Item is ROB to NGO03. Equipment capacity MAIN BKR FOR LC 2000- Equipment evaluated in 14C4257-CAL-005. Anchorage NG03 00 Capacity evaluated per 14C4257-CAL-005. Block wall evaluated per 14C4257-CAL-003.

FDR BKR FOR 125 V Item is ROB to NG003. Equipment capacity 61 NG00303 VITAL BATTERY CB 0.29 Equipment evaluated in 14C4257-CAL-005. Anchorage CHARGER NK023 00 Capacity evaluated per 14C4257-CAL-005. Block wall evaluated per 14C4257-CAL-003.

Component per se screened. Anchorage 62 NK021 CHARGER NK021 20 0.38 Capacity evaluated per 14C4257-CAL-004. Block wall evaluated per 14C4257-CAL-003.

TRANSFER SWITCH 63 N071 CHARGER BUS NK01 BARTERY CB/CC 00 2016- >RLGM Screened SRT disposition NK21/NK25 125 VDC BUS Equipment capacity evaluated in 14C4257-64 NK001 SWITCHBOARD CB/CC 2016- 0.32 Equipment CAL-005. Anchorage evaluated per 14C4257-6SWB C 00 Capacity CAL-005. Block wall evaluated per 14C4257-NKI01 CAL-003.

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Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Item ID Description Bldg Elev Failure Mode Basis Number (g, PGA)

FDR BKR FROM Item is ROB to NKOO1. Equipment capacity 65 NK00102 BATT CHGR NK021 CB/CC 2016- Equipment evaluated in 14C4257-CAL-005. Anchorage 6T0 0.32 Capacity evaluated per 14C4257-CAL-005. Block wall TO__ KO0 _ _evaluated per 14C4257-CAL-003.

MAIN BREAKER FOR CNTRL AND Item is ROB to NKOO1. Equipment capacity 66 FORISTPL AN4 2016- Equipment evaluated in 14C4257-CAL-005. Anchorage NK00104 DIST PNL NK041 CB/CC 00 0.32 Capacity evaluated per 14C4257-CAL-005. Block wall (PART (PART OF SWBD NKO01) evaluated per 14C4257-CAL-003.

MAIN BREAKER Item is ROB to NKO01. Equipment capacity 67 NKO015 FOR CNTRL AND 2016- Equipment evaluated in 14C4257-CAL-005. Anchorage PNL NKO51 RDIST CB/CC 0 0.32 Capacity evaluated per 14C4257-CAL-005. Block wall (PART NKO01) evaluated per 14C4257-CAL-003.

Equipment capacity evaluated in 14C4257-68 NK01 125 VK11BATTERY CB/CC 2016-00 44 Anchorage CAL-O05. Anchorage evaluated per 14C4257-NK011 00 CAL-004. Block wall evaluated per 14C4257-CAL-003.

ISOLATION BKR Item is ROB to NKO01. Equipment capacity 2016- Equipment evaluated in 14C4257-CAL-005. Anchorage 69 N0 Capacity evaluated per 14C4257-CAL-005. Block wall NK_ __ _ _evaluated per 14C4257-CAL-003.

FDR BKR FOR Item is ROB to NKO01. Equipment capacity 70 NK00111 INVERTER NN011 2016- Equipment evaluated in 14C4257-CAL-005. Anchorage (PART OF SWBD 00 Capacity evaluated per 14C4257-CAL-005. Block wall NK001) evaluated per 14C4257-CAL-003.

7.5KVA INVERTER 2016- Equipment Component per se screened. Anchorage 71 NN011 (FED FROM BATT CB/CC 016 0.38 Equit evaluated per 14C4257-CAL-004. Block wall CHARGER NK021)Capacity evaluated per 14C4257-CAL-003.

Class 1E AC DIST 2016-72 NNO01 SWBD NNO1 (SEP CB/CC 00 >RLGM Screened SRT disposition GRP 1) 2047-73 SA036A ESFAS CHI TERM CB/CC 00 >RLGM Screened SRT disposition NEUTRON FLUX MONITORING 2026-74 SENY0060A SYSTEM DETECTOR AUX 00 >RLGM Screened SRT disposition AMPLIFIER SENY 60A NEUTRON FLUX MONITORING 2026-75 SENY0060B SYSTEM DETECTOR AUX 00 >RLGM Screened SRT disposition AMPLIFIER SENY 60B 7 B3A W SS PROT SYS 2047-76 SB032A INPUT TRN B CB/CC 20 >RLGM Screened SRT disposition W 5 PROT SYS A 2047-77 SBO29A INPUT SS A CB/CC 04 >RLGM Screened SRT disposition

______ INPUT TRN A 06 _ _ _____

W PROCESS ANALOG 2047-78 SB038 ANALOG CB/CC 06 >RLGM Screened SRT disposition PROTECTION SET 06 CAB-01 W SS PROT SYS OUT 2047-79 SB029D 2 TRN A CB/CC 06 >RLGM Screened SRT disposition 80 SE054A W NUC INSTM NIS 2047- Equipment Component per se screened. Anchorage 1 06 Capacity evaluated per 14C4257-CAL-004.

2047-81 SBO30A SSPS TRN A #1 TEST CB >RLGM Screened SRT disposition

_______1__ 06 _____ I______ I___________________

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Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Item ID Description Bldg Elev Failure Mode Basis Number (g, PGA)

SOP INSTRUMENTATION 2047- Equipment Component per se screened. Anchorage 82 RP053AC RACK CS 0.29 Capacity evaluated per 14C4257-CAL-004.

(TERMINATION AREA)

RPV LEVEL INSTR 2047-83 SB078 SYS (RVLIS) PROC CB 06 >RLGM Screened SRT disposition PROT SYS CABINET T/C SUSCOOLING 2047-84 RPO81A MONITORCABINE CB 06 >RLGM Screened SRT disposition MONITOR CABINET 06 CNTRL & INSTR Equipment capacity evaluated in 14C4257-85 NK041 DIST SWBD NK041 CB/CC 2016- 0.32 Equipment CAL-005. Anchorage evaluated per 14C4257-85LASSO1 W 125D CS 00 Capacity CAL-005. Block wall evaluated per 14C4257-(CLASS 1E 125 VDC) CAL-003.

TURBINE 2047- Equipment Component per se screened. Anchorage 86 RL005 GENERATOR AND CS 0.29 Capacity evaluated per 14C4257-CAL-004.

FW CONSOLE TURBINE 2047- Equipment Component per se screened. Anchorage 87 RL006 GENERATOR AND CS 0.29 Capacity evaluated per 14C4257-CAL-004.

FW CONSOLE 88 RP139 B AUXILIARY RELAY CS 2000- >RLGM Screened SRT disposition RACK RP139 00 CNTRL & INSTR 2016-89 NK051 DIST SWBD NK051 CB/CC 00 >RLGM Screened SRT disposition (CLASS 1E 125 VDC) _

BBPCVO455A PORV 2070-90 BBPCVO455A SOLENOID FAILS TO RB 00 >RLGM Screened SRT disposition OPEN ON DEMAND REACTOR AUX 2047- Equipment Component per se screened. Anchorage CNTRL PANEL 06 Capacity evaluated per 14C4257-CAL-004.

REACTOR AUX 2047- Equipment Component per se screened. Anchorage CNTRL PANEL 06 Capacity evaluated per 14C4257-CAL-004.

B AUXILIARY RELAY 2000-93 RP209 RACK AUX 00 >RLGM Screened SRT disposition 2047-94 RP289 DC DIST PNL RP289 AUX 06 >RLGM Screened SRT disposition AUX RELAY RACK 2000-95 RP330 RP330 AUX O0 >RLGM Screened SRT disposition S UIIRY33 REA000 96 RP332 B AUXILIARY RELAY AUX 2000 >RLGM Screened SRT disposition EM'CY LIGHTING 2016-97 NKO51A DIST SWBD NKO51A CB/CC 00 >RLGM Screened SRT disposition (SUBPNL OF NKO51)

Component per se screened. Anchorage 98 NK023 125 V BATTERY CB 00 0.38 Equipment evaluated per 14C4257-CAL-004. Block wall CHARGER NK023 C 00 Capacity evaluated per 14C4257-CAL-003.

TRANSFER SWITCH 99 NK073 BUS NK03 BATTERY 2016-CHARGER CS/CC 00 >RLGM Screened SRT disposition NK23/NK25 125 VDC BUS Equipment capacity evaluated in 14C4257-100 NK103 SWITCHBOARD CB/CC 2016- Equipment CAL-005. Anchorage evaluated per 14C4257-S00 0.32 Capacity CAL-005. Block wall evaluated per 14C4257-NKO03 CAL-003.

FDR BKR FROM Item is ROB to NK003. Equipment capacity 101 NK00302 BATOCHGR NK023 CB/CC 2016- Equipment evaluated in 14C4257-CAL-005. Anchorage 1T0 0.32 Capacity evaluated per 14C4257-CAL-005. Block wall TOI3 I I evaluated per 14C4257-CAL-003.

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Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Item ID Description Bldg Elev Failure Mode Basis Number [g, PGA)

MAIN MAI BREAKER BTRE AKER Item is ROB to NKO03. Equipment capacity FOR CNTRL AND 2016- Equipment evaluated in 14C4257-CAL-005. Anchorage 102 NK00304 DIST PNL NK043 CB/CC 0.32 Capacity evaluated per 14C4257-CAL-005. Block wall (PART OF SWBD 00 evaluated per 14C4257-CAL-00.

NK003) evaluated per 14C4257-CAL-003.

Equipment capacity evaluated in 14C4257-103 NK01 125 VK13 BATTERY CB/CC 2016-00 0.44 Anchorage CAL-005. Anchorage evaluated per 14C4257-NK013 00 CAL-004. Block wall evaluated per 14C4257-CAL-003.

ISOLATION BKR Item is ROB to NK003. Equipment capacity 104 NK00301 FOR BATTERY C8/CC 2016- Equipment evaluated in 14C4257-CAL-005. Anchorage S00 0.32 Capacity evaluated per 14C4257-CAL-005. Block wall NK013_ _evaluated per 14C4257-CAL-003.

FDR BKR FOR Item is ROB to NK003. Equipment capacity 105 NK00311 INVERTER (PARTOF NN013 2016- 0B.30 Equipment evaluated in 14C4257-CAL-005. Anchorage (PART OF SWBD 00 Capacity evaluated per 14C4257-CAL-005. Block wall NKO03) evaluated per 14C4257-CAL-003.

7.5KVA INVERTER Component per se screened. Anchorage 106 NNO13 (FED FROM BATT CB/CC 06 0.38 Capacity evaluated per 14C4257-CAL-004. Block wall 0.38GER Capcit evaluated per 14C4257-CAL-003.

Class 1E AC DIST 2016-107 NNO03 SWBD NN03 (SEP CB/CC 00 >RLGM Screened SRT disposition GRP 3)

BOP INSTR RACK 2047- Equipment Component per se screened. Anchorage RPOS3DB 06 Capacity evaluated per 14C4257-CAL-004.

W PROCESS 109 SB037 ANALOG 2047-PROTECTION SET CB/CC 06 >RLGM Screened SRT disposition CAB-03 CNTRL & INSTR Equipment capacity evaluated in 14C4257-110 NK043 DIST SWBD NK043 CB/CC 2016- Equipment CAL-005. Anchorage evaluated per 14C4257-(CLASS 1E 125 VDC) 00 Capacity CAL-005. Block wall evaluated per 14C4257-CAL-003.

2026-111 AB007 Aux Relay Rack CB 00 >RLGM Screened SRT disposition FDR BKR FOR 125 V Item is ROB to NG001. Equipment capacity 112 NG00109 SWING BATTERY CB 2000- 0.29 Equipment evaluated in 14C4257-CAL-005. Anchorage CHARGER NK025Capacity evaluated per 14C4257-CAL-005.

125 V BATTERY CHARGER NK025 2000- Equipment Component per se screened. Anchorage (Swing Battery 00 Capacity evaluated per 14C4257-CAL-004.

Charger)

Equipment capacity evaluated in 14C4257-480 V LOAD 2000- Equipment CAL-005. Anchorage evaluated per 14C4257-CENTER NG02 00 Capacity CAL-005. Block wall evaluated per 14C4257-CAL-003.

FLEX 500 kW TIE IN Item is ROB to NG002. Equipment capacity BKR from FD201 2000- Equipment evaluated in 14C4257-CAL-005. Anchorage (Phase 2 C 0 Capacity evaluated per 14C4257-CAL-005. Block wall connection point) evaluated per 14C4257-CAL-003.

FDR BKR FOR 125 V Item is ROB to NGO02. Equipment capacity 2000- Equipment evaluated in 14C4257-CAL-005. Anchorage 1VALAERY00 Capacity evaluated per 14C4257-CAL-005. Block wall CHARGERN024 I evaluated per 14C4257-CAL-003.

Component per se screened. Anchorage 117 NK024 125 V BATTERY CB 2016- 0.3 Equipment evaluated per 14C4257-CAL-004. Block wall I I Ia 0.8 I evaluated per 14C4257-CAL-003.

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Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Item ID Description Bldg Elev Failure Mode Basis Number (g, PGA)

TRANSFER SWITCH BUS NK04 BATTERY 2016-118 NK074 CHARGER CB 00 >RLGM Screened SRT disposition NK24/NK26 125 VDC BUS Equipment capacity evaluated in 14C4257-125 NSCHBUS 2016- Equipment CAL-005. Anchorage evaluated per 14C4257-NK004 00 Capacity CAL-005. Block wall evaluated per 14C4257-CAL-003.

FDR BKR FROM Item is ROB to NKO04. Equipment capacity 2016- Equipment evaluated in 14C4257-CAL-005.

12 NK004 B0 Capacity evaluated per 14C4257-CAL-005.Anchorage Block wall TO__ KO4_ _evaluated per 14C4257-CAL-003.

Equipment capacity evaluated in 14C4257-121 NK014 125 V BATTERY NO4CB 2016-00 0.44 Anchorage CAL-OOS. Anchorage evaluated per 14C4257-NK014 00 CAL-004. Block wall evaluated per 14C4257-I _CAL-003.

ISOLATION 8KR Item is ROB to NKO04. Equipment capacity ISOLATIONYBCR 2016- Equipment evaluated in 14C4257-CAL-005. Anchorage NK014 N0 Capacity evaluated per 14C4257-CAL-005. Block wall evaluated per 14C4257-CAL-003.

FDR BKR FOR Item is ROB to NKO04. Equipment capacity INVERTER NN011 2016- Equipment evaluated in 14C4257-CAL-005. Anchorage (PART OF SWBD C 0 Capacity evaluated per 14C4257-CAL-005. Block wall NKO04) evaluated per 14C4257-CAL-003.

7.5KVA INVERTER 2016- Equipment Component per se screened. Anchorage 124 NNO14 (FED FROM BATT CB 0.38 Capacity evaluated per 14C4257-CAL-004.

CHARGER NK024)

Class 1E AC DIST 2016-125 NNO04 SWBD NN04 (SEP CB 00 >RLGM Screened SRT disposition GRP 4) 2047-126 SA036B ESFAS CH4 TERM CB 06 >RLGM Screened SRT disposition BOP 2000-127 RP147B Instrumentation CB 00 >RLGM Screened SRT disposition Rack RP147B NEUTRON FLUX MONITORING 2047-128 SENYOO61A SYSTEM DETECTOR AUX 00 >RLGM Screened SRT disposition AMPLIFIER SENY 61A NEUTRON FLUX MONITORING 2047-129 SENYOO61B SYSTEM DETECTOR AUX 00 >RLGM Screened SRT disposition AMPLIFIER SENY 61B W SSPS Train B *2 2047-130 SB032D CB >RLGM Screened SRT disposition Output 06 2047-131 SB033A SSPS Train B #1 Test CB 06 >RLGM Screened SRT disposition W PROCESS ANALOG 2047-132 SB041 ANALOG CB 06 >RLGM Screened SRT disposition PROTECTION SET 06 CAB-04 BOP 2047- Equipment Component per se screened. Anchorage 133 RP053BC Instrumentation CB 0.29 Capacity evaluated per 14C4257-CAL-004.

Rack RPO53BC RVLIS Process 2047-134 SB079 Cabinet SB079 CB 06 >RLGM Screened SRT disposition 135 RPO81B C 2047- >RLGM Screened SRT disposition 135___ RP081B___ Cabinet CB 06 __________ ___________________

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Westinghouse Non-Proprietary Class 3 Wolf Creek Generating Station ESEP Final Report ESEL HCLPF Item ID Description Bldg Elev Failure Mode Basis Number (g, PGA)

W PROCESS 2000 136 SB148B PROTECTION (Fire CB 00 >RLGM Screened SRT disposition Isolation)

See STATUS 2047-Note 5 SA066B INDICATING SYS CB 06 >RLGM Screened SRT disposition RHR PMP PEJO1A Note 5 EJF150610 Miniflow Control AUX 00 >RLGM Screened SRT disposition Discharge LOCAL CONTROL Equipment capacity evaluated in 14C4257-See LOCAL COR 2002- CAL-005. Anchorage evaluated per 14C4257-Note 5 FC0219 PANEL FOR T AFW AUX 00 0.61 Anchorage CAL-005. Relay functionality evaluated per PUMP 014C4257-CAL-005.

Equipment capacity evaluated in 14C4257-CAL-005. Anchorage evaluated per 14C4257-See NG001A MCC NG01A BUS CB 2000- 0.44 Relay CAL-005. Block wall evaluated per 14C4257-CAL-003. Relay functionality evaluated per 14C4257-CAL-005.

Equipment capacity evaluated in 14C4257-See NG002B MCC NG02B BUS AUX 2026- 0.44 Relay CAL-005. Anchorage evaluated per 14C4257-Note 5 00 Functionality CAL-005. Relay functionality evaluated per 14C4257-CAL-005.

Equipment capacity evaluated in 14C4257-See NG003C MCC NG03C BUS AUX 2047- 0.44 Relay CAL-005. Anchorage evaluated per 14C4257-Note 5 00 Functionality CAL-005. Relay functionality evaluated per 14C4257-CAL-005.

Equipment capacity evaluated in 14C4257-See NG004C MCC NG04C BUS AUX 2047- 0.44 Relay CAL-005. Anchorage evaluated per 14C4257-Note 5 00 Functionality CAL-005. Relay functionality evaluated per 14C4257-CAL-005.

See LOCKOUT RELAY 2000-Note 5 RP334 RACK CB 00 >RLGM Screened SRT disposition See ESFASCH2 2047-Note 5 SA036C LOGIC/TERM CB 06 >RLGM Screened SRT disposition CABINET See W SS PROT SYS OUT 2047-See SB029C W TR O CB 20 >RLGM Screened SRT disposition Note 5 _____ 1 TRN ____ 06 ___ _____ __________________

12/31/14 Page 51 of 51