ML17003A290

Areva, Inc. - Engineering Information Record - Arkansas Nuclear One HFE-High Frequency Confirmation Report

ML17003A290
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/20/2016
From:	Connell K, Enzinna R, Clint Jones, Kennedy B, Stewart M AREVA
To:	Office of Nuclear Reactor Regulation
Shared Package
ML17003A327	List: 0CAN121603, High Frequency Supplement to Seismic Hazard Screening Report ML17003A290
References
20004-022 51-9257562-000
Download: ML17003A290 (82)

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Control I Docume A

20004-022 (03/10/2016)

AREVA AREVA Inc.

Engineering Information Record Document No.: 51 - 9257562 - 000 Arkansas Nuclear One HFE - High Frequency Confirmation Report Page 1 of 82

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• Document No.: 51-9257562-000 AREVA Arkansas Nuclear One HFE - High Frequency Confirmation Report Safety Related? DYES IZJ NO Does this document establish design or technical requirements? D YES ~NO Does this document contain assumptions requiring verification? D YES ~NO Does this document contain Customer Required Format? IZJ YES D NO Signature e1ock Pages/Sections Name and P/LP, R/LR, M, Prepared/Reviewed/

Title/Discipline Signature A-CRF, A Date Approved or Comments p

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Benjamin Kennedy Appendix A: Sections 3 and 4; Engineer ill 20Dec16 Attachments A and B p

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Mark Stewart Sections 1.0 and 2.0 Principal Engineer 20-Dec-2016 Appendix A: Sections 1, 5, and 6; Attachment C Burton Kennedy p Appendix A: Section 2; Attachment Engineer N, PRA -~-

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Benjamin Kennedy R Sections 1.0 and 2.0 Engineer ill 20Dec16 Appendix A: Sections 1, 5, and 6; Attachment C Mark Stewa1t R Appendix A: Sections 3 and 4; 20-Dec-2016 Principal Engine~r Attachment A and B Robe1t Enzinna R Appendix A: Section 2; Attachment

~Jk.1:... B component infonnation Advisory Engineer, PRA /kl (.t.

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Kevin Conriell Enginee1ing Manager f2-(w/fr.

Cindy Jones A-CRF I Appendix A Project Manager l...u

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Note: P/LP designates Preparer (P), Lead Prepare1; (LP)

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R/LR designates Reviewer (R), Lead Revie~ (LR) .

A-CRF designates Project Manager Approver of Customer Required Fonnat (A-CRF)

A designates Approver/RTM_- Verification ofReviewer Independence Page2

Controlled Document IA 20004-022 (03/10/2016)

Document No.: 51-9257562-000 AREVA Arkansas Nuclear One HFE - High Frequency Confirmation Report Signature Block (continued)

Project Manager Approval of Customer References (N/A if not applicable)

Name Title (printed or typed) (printed or typed) Signature Date Cindy Jones bt{ /:{;-v 1-1 f

L_o '°" 1V'CL-t- 67?- ~At L Project Manager

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Controlled Document A 20004-022 (03/10/2016)

Document No.: 51-9257562-000 AREVA Arkansas Nuclear One HFE - High Frequency Confirmation Report Record of Revision Revision Pages/Sections/

No. Paragraphs Changed Brief Description I Change Authorization 000 All Initial Issue Page4

A Document No.: 51-9257562-000 AREVA Arkansas Nuclear One HFE - High Frequency Confirmation Report Table of Contents Page SIGNATURE BLOCK ..................,........................................................................................................... 2 RECORD OF REVISION ....................................................................................................................... 4 1.0 PURPOSE ................................................................................................................................. 6

2.0 REFERENCES

........................................................................................................................... 7 APPENDIX A: ARKANSAS NUCLEAR ONE (ANO) HIGH FREQUENCY CONFIRMATION REPORT ................................................................................................................A-1 Page 5

led A Document No.: 51-9257562-000 AREVA Arkansas Nuclear One HFE - High Frequency Confirmation Report 1.0 PURPOSE The purpose of this report is to provide information as requested by the Nuclear Regulatory Commission (NRC) in its March 12, 2012 letter issued to all power reactor licensees and holders of construction permits in active or deferred status (Reference [ 1]). In particular, this report provides information requested to address the High Frequency Confirmation requirements ofltem (4), Enclosure 1, Recommendation 2.1: Seismic, of the March 12, 2012 letter (Reference [1]).

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 (Reference [1]), requesting information to assure that these recommendations are addressed by all U.S. nuclear power plants. The 50.54(t) letter requests that licensees and holders of construction permits-under,10 CPR Part 50 reevaluate the seismic hazards at their sites against present-day NRC requirements and guidance. Included in the 50.54(t) letter was a request that licensees perform a "confirmation, if necessary, that SSCs, which may be affected by high-frequency ground motion, will maintain their functions important to safety."

EPRI 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic" (Reference [2]) provided screening, prioritization, and implementation details to the U.S. nuclear utility industry for responding to the NRC 50.54(t) letter. This report was developed with NRC participation and was subsequently endorsed by the NRC.

The SPID included guidance for determining which plants should perform a High Frequency Confirmation and identified the types of components that should be evaluated in the evaluation.

Subsequent guidance for performing a High Frequency Confirmation was provided in EPRI 3002004396, "High Frequency Program, Application Guidance for Functional Confirmation and Fragility Evaluation," (Reference

[3]) and was endorsed by the NRC in a letter dated September 17, 2015 (Reference [4]) . Final screening identifying plants ne~ding to perform a High Frequency Confirmation was provided by NRC in a letter dated October 27, 2015 (Reference [5]).

This report describes the High Frequency Confirmation evaluation undertaken for Arkansas Nuclear One (ANO),

Units 1 and 2. The objective of this report is to provide summary information describing the High Frequency Confirmation evaluations and results. The level of detail provided in the report is intended to enable NRC to understand the inputs used, the*evaluations performed, and the decisions made as a result of the evaluations.

EPRI 3002004396 (Reference [3]) is used for the ANO engineering evaluations described in Appendix A of this report. In accordance with Reference [3], the following topics are addressed in the subsequent sections of this report:

Process of selecting components and a list of specific components for high-frequency confirmation 1Estimation of a vertical ground motion response spectrum (GMRS)

• Estimation of in-cabinet seismic demand for subject components Estimation of in-cabinet seismic capacity for subject components Summary of subject components' high-frequency evaluation Page 6

Controlled rr1 A Document No.: 51-9257562-000 AREVA Arkansas Nuclear One HFE - High Frequency Confirmation Report

2.0 REFERENCES

References identified with an (*) are maintained within Arkansas Nuclear One (ANO) Records System and are not retrievable from AREVA Records Management. These are acceptable references per AREVA Administrative Procedure 0402-01, Attachment 8. See page 2 for Project Manager Approval of customer references.

1. NRC (E. Leeds and M. Johnson) Letter to All Power Reactor Licensees et al., "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9 .3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident," March 12, 2012, ADAMS Accession Number ML12053A340.

2. EPRl 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Re~olution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic."

February 2013.

3. EPRl 3002004396, "High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation." July 2015.

4. NRC (J. Davis) Letter to Nuclear Energy Institute (A. Mauer), "Endorsement of Electric Power Research Institute Final Draft Report 3002004396, 'High Frequency Program: Application Guidance for Functional Confirmation and Fragility.'" September 17, 2015, ADAMS Accession Number ML15218A569.

5. NRC (W. Dean) Letter to the Power Reactor Licensees on the Enclosed List, "Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident." October 27, 2015, ADAMS Accession Number ML15194A015.

6. Entergy Letter to NRC, "Seismic Hazard and Screening Report (Central Eastern United States (CEUS)

Sites), Response to NRC Request for Information (RPI) Pursuant to 10 CPR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima*Dai-ichi Accident, Arkansas Nuclear One- Units 1 and 2." March 28, 2014, ADAMS Accession Number ML14092A021.

7. EPRl 1015109, "Program on Technology Innovation: Seismic Screening of Components Sensitive to High-Frequency Vibratory Motions." October 2007.

8. EPRl 3002002997, "High Frequency Program: High Frequency Testing Summary," September 2014.

9. NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide," Appendix H, Nuclear Energy Institute, November 30, 2015.

10. *Entergy Document 93-SQ-1001-04, Revision 3, "USI A-46/IPEEE Relay Evaluation list for AN0-1."

11. *Entergy Document 93-SQ-2001-04, Revision 2, "USI A-46/IPEEE Relay Evaluation Report for AN0-2."

12. *Entergy Document 93-SQ-1001-02, Revision 0, "USI A-46/IPEEE Safe Shutdown Success Path Selection Report for AN0-1." '

13. *Entergy Document 93-SQ-2001-02, Revision 0, "U:SI A-46/IPEEE Safe Shutdown Success Path Selection Report for AN0-2."

14. *Entergy Document 93-SQ-1001-03, Revision 4, "USI A-46/IPEEE Safe Shutdown Equipment List (SSEL) Report for AN0-1."

15. *Entergy Document 93-SQ-2001-03, Revision 3, "USI A-46/IPEEE Safe Shutdown Equipment List (SSEL) Report for AN0-2."

Page?

A Document No.: 51-9257562-000 AREVA Arkansas Nuclear One HFE - High Frequency Confirmation Report

16. *Entergy Document EC 65905, EN-DC-141Attachment9.1 & 9.2, "Screening of ANO Safe Shutdown Equipment List." August 2016.

17. EPRI NP-7147-SL, "Seismic Ruggedness of Relays" August 1991.

18. EPRI NP-7147-SL, V2, "Seismic Ruggedness of Relays" April, 1995.

19. EPRI NP-7148-SL, "Procedure for Evaluating Nuclear Power Plant Relay Seismic Functionality,"

December, 1990.

20. EPRI 3002000709, "Seismic Probabilistic Risk Assessment Implementation Guide," December, 2013.

21. NRC Letter, "Arkansas Nuclear One, Units 1 and 2 - Staff Assessment oflnformation Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(£), Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review oflnsights from the Fukushima Dai-ichi Accident." December 15, 2015, ADAMS Accession Number ML15344A109.

22. EPRI TR-105988, "GERS Formulated Using Data from the SQURTS Program," Final Report, April 1996.

23. EPRI TR-105988-V2, "GERS Formulated Using Data from the SQURTS Program," Final Report, April 1999.

24. *Entergy Document EC 68207, "AN01/AN02 Outlier Relays Resolved Via Post Event Operator Actions," December 2016.

25. AREVA Document 32-9257563-001, "Arkansas Nuclear One Unit 1 HFE - Component Mounting Point Demand."

26. AREVA Document 32-9257565-001, "Arkansas Nuclear One Unit 2 HFE - Component Mounting Point Demand."

27. AREYA Document 32-9261655-001, "Arkansas Nuclear One Unit 1 HFE - HCLPF Capacity Evaluation."

\

28. AREYA Document 32-9261657-001, "Arkansas Nuclear One Unit 2 HFE - HCLPF Capacity Evaluation."

29. AREVA Document 51-9261429-001, "ANO High Frequency Chatter Assessment Supporting Documentation."

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Controlled Oocun1 nt A Document No.: 51-9257562-000 AREVA Arkansas Nuclear One HFE - High Frequency Confirmation Report APPENDIX A: ARKANSAS NUCLEAR ONE (ANO) HIGH FREQUENCY CONFIRMATION REPORT Page A-1

Controlled Docurnent Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation 1 Introduction 1.1 PURPOSE The purpose of this report is to provide information as requested by the NRC in its March 12, 2012 50.54(f) letter issued to all power reactor licensees and holders of construction permits in active or deferred status [1]. In particular, this report provides requested information to address the High Frequency Confirmation requirements of Item (4), Enclosure 1, Recommendation 2.1:

Seismic, of the March 12, 2012 letter [1].

1.2 BACKGROUND

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 (NTIF) 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 NTIF 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 S0.54(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. Included in the 50.54(f) letter was a request that licensees perform a "confirmation, if necessary, that SSCs, which may be affected by high-frequency ground motion, will maintain their functions important to safety."

EPRI 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the resolution of Fukushima Near-Term Task Force Recommendation 2.1:

Seismic" [2] provided screening, prioritization, and implementation details to the U.S. nuclear utility industry for responding to the NRC 50.54(f) letter. This report was developed with NRC participation and is endorsed by the NRC. The SPID included guidance for determining which plants should perform a High Frequency Confirmation and identified the types of components that should be evaluated in the evaluation.

Subsequent guidance for performing a High Frequency Confirmation was provided in EPRI 3002004396, "High Frequency Program, Application Guidance for Functional Confirmation and Fragility Evaluation," [3] and was endorsed by the NRC in a letter dated September 17, 2015 [4].

Final screening identifying plants needing to perform a High Frequency Confirmation was provided by NRC in a letter dated October 27, 2015 [S].

On March 28, 2014, Arkansas Nuclear One (ANO) submitted a reevaluated seismic hazard to the NRC as a part of the Seismic Hazard and Screening Report [6]. By letter dated October 27, 2015

[5], the NRC transmitted the results of the screening and prioritization review of the seismic hazards reevaluation.

This report describes the High Frequency Confirmation evaluation undertaken for ANO Units 1 and 2 using the methodologies in EPRI 3002004396, "High Frequency Program, Application Page 1of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Guidance for Functional Confirmation and Fragility Evaluation," as endorsed by the NRC in a letter dated September 17, 2015 (4).

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

1.3 APPROACH EPRI 3002004396 (3) is used for the ANO 1&2 engineering evaluations described in this report.

Section 4.1 of Reference [3] provided general steps to follow for the high frequency confirmation component evaluation. Section 4.2.2 of Reference [3] describes an alternate approach that uses the plant's Individual Plant Examination of External Events (IPEEE). This approach also corresponds with "Path 3" from NEI 12-06 Appendix H [9]. Reference [6]

establishes the adequacy of the IPEEE for AN0-1 and AN0-2, and the full-scope relay evaluations contained therein. Therefore, the selection of components for high-frequency (HF) confirmation is based on the relays identified in the IPEEE.

Accordingly, the following topics are addressed in the subsequent sections of this report:

• ANO SSE and GMRS Information

• Selection of components and a list of specific components for high-frequency confirmation

• Estimation of seismic demand for subject components

• Estimation of seismic capacity for subject components

• Summary of subject components' high-frequency evaluations

• Summary of Results 1.4 PLANT SCREENING ANO submitted reevaluated seismic hazard information including GMRS and seismic hazard information to the NRC on March 28, 2014, [6]. In a letter dated December 15, 2015 the NRC staff concluded that the submitted GMRS adequately characterizes the reevaluated seismic hazard for ANO [21).

The NRC final screening determination letter [5] concluded that the ANO GMRS to SSE comparison resulted in a need to perform a High Frequency Confirmation in accordance with the screening criteria in the SPID [2].

Page 2 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation 2 Selection of Components for High-Frequency Screening The fundamental objective of the high frequency confirmation review is to determine whether the occurrence of a seismic event could cause credited equipment to fail to perform as necessary. An optimized evaluation process is applied that focuses on achieving a safe and stable plant state following a seismic event. As described in Reference [3], this state is achieved by confirming that key plant safety functions critical to immediate plant safety are preserved (reactor trip, reactor vessel inventory and pressure control, and core cooling) and that the plant operators have the necessary power available to achieve and maintain this state immediately following the seismic event (AD/DC power support systems).

For AN0-1 & 2, the components supporting the key safety functions have been determined by the IPEEE.

The description of ~hese key safety functions, and the plant systems and success paths that are credited to achieve these functions is described in the IPEEE reports for safe shutdown success path selection

[12] [13]. The specific equipment credited in the IPEEE to achieve these success paths is captured on the safe shutdown equipment list (SSEL) [14] [15] that was created specifically for the IPEEE/USI A-46 seismic analysis. The key functions fulfilled by the IPEEE safe shutdown success paths are given in Table 2-1.

Table 2-1: IPEEE Key Functions

) Reactivity Control Reactor Pressure Control Reactor Inventory Control Decay Heat Removal The primary success paths for the ANO units are shown in Figure 2-1 and Figure 2-2 derived from [12],

Figure 2 and [13], Figure 2. The IPEEE includes alternate success paths not shown in the figures since, generally, they consist of using the redundant trains to achieve the key functions.

• Page 3 of 73

Controlled Docurn Arkansas Nuclear One: S0.54(f) NTIF 2.1 Seismic High Frequency Confirmation Automatic Control Rod REACTIVITY CONTROL Insertion (RPS & CROM) w INVENTORY CONTROL & HPI (Train A)

LONG TERM REACTIVITY CONTROL w

SG A & MSSVs/ADVs PRESSURE CONTROL w

DECAY HEAT REMOVAL HPI (Train A)

(Hot Shutdown)

I II DECAY HEAT REMOVAL LPI (Train A)

(Cold Shutdown)

Figure 2-1: AN0-1 IPEEE Primary Safe Shutdown Success Path Page 4 of 73

Controlled Docu Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Automatic Control Rod REACTIVITY CONTROL Insertion (RPS & CEDM)

Charging Pump Injection LONG TERM REACTIVITY CONTROL (Train A) w SG A & MSSVs/ADVs PRESSURE CONTROL w

HPSI (Train A)

INVENTORY CONTROL

'V DECAY HEAT REMOVAL EFW (Train A)

(Hot Shutdown)

DECAY HEAT REMOVAL LPSI (Train A)

(Cold Shutdown)

Figure 2-2: AN0-2 IPEEE Primary Safe Shutdown Success Path Page 5 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Within the applicable functions, the components that need high frequency confirmation are contact control devices subject to intermittent states in seal-in or lockout circuits. The IPEEE has already reviewed these circuits, determined if seismic induced relay chatter would prevent the completion of these key functions, and has identified the essential relays involved. Therefore, the selection of relays and contact control devices for the HF confirmation is based upon the essential relay list (ERL) developed by the IPEEE, which is contained in the AN0-1 & 2 IPEEE relay evaluation reports [10] [11].

The ERL from the IPEEE was first reviewed for current applicability, and adjustments were made to accommodate changes that have occurred since performance of the IPEEE. This revised essential relay list then comprises the components selected for HF confirmation.

2.1

SUMMARY

OF DESIGN CHANGES SINCE IPEEE Since the IPEEE is several years old, a systematic review of design changes since performance of the IPEEE was undertaken to ensure that there were none that would affect the selection of essential relays.

A summary of the applicable design changes is described below.

The purpose of this review was to verify that the relays on the IPEEE ERL for AN0-1 and AN0-2 are still applicable, and to identify any design changes that may be relevant for the HF confirmation. Design changes that affect a circuit with an essential relay were flagged for new circuit analysis.

Design changes affecting the ERL were not extensive, and were generally favorable with respect to relay chatter. One significant design change involved replacement of the 120VAC inverters at both units. The inverters along with their integral control circuits were replaced with new and improved models.

Therefore, the inverters were flagged for new circuit analysis and the essential relays from the new control circuits were added to the ERL. Other design changes, as described in the sections below, were benign with respect to relay chatter.

Each relay on the ERL was also searched in the plant data base to identify current manufacturer and model. Obsolete relays that are replaced with functionally-equivalent models from a different manufacturer do not require new circuit analysis. The current model information for all of the essential relays was determined from the plant database for use in the HF confirmation.

2.1.1 Summary of Design Changes for AN0-1 The inverters Y11, Y13, Y22, Y24 were replaced along with their integral control circuits. Several relays from the ERL were removed with this design change. The new inverters received circuit analysis to determine if there are any relays from the new control circuits that should be on the ERL. In addition,

• inverter Y28 (the UPS inverter) was eliminated and its loads added to the new Y22 inverter.

Magna blast breakers on bus A-3 were replaced with Siemens vacuum interrupter type breakers. The breakers are functionally equivalent with respect to the control circuit, so relays on the ERL are not affected except for one, the anti-pump relay 152Y, which is integral to the breaker. The new breaker has a functionally-equivalent relay.

The circuits for several components were modified to prevent spurious operation due to fire-induced hot shorts. Affected components include three valves and two sluice gates whose motor starter seal-in contacts are already on the ERL. The changes involve installation of inhibit circuits in the motor-starter circuit. The inhibit circuit adds a new normally-closed contact to the "hot" end of the motor starter Page 6 of 73

led ment Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation relay coil to keep it grounded when not in use. This contact is mechanically linked to the normally open seal-in contact in a "break before make" design. A review of these circuits determined that the new inhibit circuit does not add any new chatter failure modes of concern, nor changes any existing chatter failure modes on the ERL. Therefore, the circuit analysis concluded that the design change of the inhibit circuits was benign with respect to chatter, and did not increase nor decrease the essential relay count.

Relays from the ERL are no longer relevant for valve CV-1050 because the valve is unpowered at the MCC breaker during normal operation.

Relays for valves CV-3641 and CV-3645 are removed from the ERL because these valves have been converted to manual valves.

Obsolete speed sensors on the EDGs were replaced with functional equivalents.

Various obsolete relays have been replaced since IPEEE with functional equivalents from another manufacturer. The current relay models have been identified from the plant database.

2.1.2 Summary of Design Changes for AN0-2 The inverters 2Y11, 2Y13, 2Y22, 2Y24 were replaced along with their' integral control circuits. Several relays from the ERL were removed with this design change. The new inverters received circuit analysis to determine if there are any relays from the new control circuits that should be on the ERL.

Magna blast breakers on 4160 volt bus 2A-3 were replaced with Siemens vacuum interrupter type breakers. The breakers are functionally equivalent with respect to the control circuit, so relays on the ERL are not affected.

At AN0-2, there were also some NFPA 805 modifications to prevent fire-induced spurious actuations, but they were limited to cable rerouting, and did not involve the functional aspects of relay circuits.

Relays from the ERL are no longer relevant for valves 2CV5084-1 and 2CV5086-2 because the valves are unpowered at the MCC breaker during normal operation.

Various obsolete relays have been replaced since IPEEE with functional equivalents from another manufacturer. The current relay models have been identified from the plant database.

2.2 SSEL ENHANCEMENT The IPEEE is based on a safe shutdown equipment list (SSEL) that was created specifically for the seismic analysis [14] [15]. These references identify the equipment that is required to bring the plant to a safe shutdown condition following an earthquake and to maintain it there for a minimum of seventy-two hours.

There is another SSEL in the plant data management system (PDMS) that is more recent than the IPEEE.

This SSEL contains equipment selected to demonstrate the plant's ability to achieve post-fire safe 1

shutdown in accordance with 10 CFR 50, Appendix R. . Since this other SSEL was created specifically for Appendix R fire scenarios, it has different scope and boundary conditions, which may not be applicable to Seismic. Major differences are that Appendix R does not assume a simultaneous LOCA while the 1

Note that as of this writing, AN0-2 is an NFPA 805 plant, and AN0-1 has plans to be an NFPA 805 plant.

Page 7 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NITF 2.1 Seismic High Frequency Confirmation IPEEE does, and Appendix R mitigation is allowed to credit non-seismically qualified components. For the purpose of conservatism and completeness, the SSEL from the PDMS was reviewed to determine if there are any components on it, not on the original IPEEE SSEL, that should be considered for inclusion in the seismic analysis [16]. After screening out components that are uniquely applicable to Appendix R scenarios (e.g., non-safety-related equipment that cannot be credited for Seismic) or not applicable to HF chatter evaluation (e.g., no automatic control function), a small number of additional components were added to the HF confirmation scope. Functionally speaking, the additional components add success paths and functions that are not necessary to meet the minimum IPEEE requirements, but may in any event provide an enhanced level of redundancy. For example, this enhanced SSEL includes an additional steam supply path to the turbine-driven EFW pump, additional isolation valves, battery chargers, swing-train inverters, and potential flow diversion pathways. Circuit analysis was performed on these components to determine if there are any corresponding essential relays that could interfere with the desired function of the components. As a conservative measure, the resulting relays are included on the ERL along with the relays resulting from the IPEEE by itself.

2.3 EXAMPLES OF CIRCUIT ANALYSIS TO IDENTIFY ESSENTIAL RELAYS Circuit analysis was performed for the components that have changed or are new since the IPEEE. The "essential relays" determined from the circuit analysis are the contact control devices in seal-in or lockout circuits whose change of state may be detrimental to a key safe shutdown function.

The various EPRI guidance documents [3] [7] [8] [17] [18] [19] [20] provide the basis for the circuit analysis assumptions:

• Only the relays that are in seal-in and lock-out circuits need to be considered. This includes relays in the upstream circuit that may trigger the lock-out or seal-in function ([3] and [20]).

• Mechanically-actuated switches are considered "inherently robust." This category includes:

manually-operated control switches, power transfer switches, limit and torque switches and position switches ([3] and [19]).

• Molded case circuit breakers (MCCB) are not vulnerable to HF chatter ([3]).

• Lock-out relays are not vulnerable to HF chatter; however up-stream contacts in the control circuit that can trip the lock-out relay are of potential concern ([3]).

• Solid state relays (no mechanically moving parts) are considered inherently rugged ([3] and

[19]).

• Induction disk (rotary) relays have high seismic capacity and are considered inherently rugged

([17] and [18]). Chatter vulnerability is determined only by the seal-in contacts that may actuate the relay.

• Process switches (i.e., mechanical sensor switches) such as pressure and thermal switches (thermostats) that have contacts in these control circuits may chatter and are included in the evaluation.

• The relays of potential concern are used primarily for the direct control of power equipment such as breakers, switchgear, and valve operators. However, the breakers and power equipment are not included in the evaluation because they have not shown vulnerability to chatter ([19]). If there is chatter of breaker contacts, the short interruption of electrical current is not of sufficient duration to adversely affect the powered component (e.g., a motor). It is the Page 8 of 73

Controlled Docurn Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation upstream control circuit relays that seal-in to operate the breaker that are the primary target of this evaluation.

• Motor starters with seal-in contacts have been included in the evaluation. These are contactors that are used to start motors such as for MOVs and pumps. A contactor is considered to be a heavy-duty relay, and is distinguished from a breaker in that its contacts are moved by a solenoid type mechanism rather than charged by springs.

• For the purposes of this evaluation, the shaking from the earthquake is assumed to last 30 seconds.

2.3.1 Circuit Analysis Example 1: Unit 1 MOV with Only Handswitch Actuation Figure 2-3 depicts the opening circuit of an MOV. The valve is normally closed and opening is an undesired action. The valve is controlled remotely by handswitch in the control room and locally by pushbutton. Chatter could shut contacts 42F/a, seal-in the opening motor contactor, and drive the valve completely open. As such, this motor contactor (42F) would be included in the ERL.

Figure 2-3: Seal-in of MOV Opening Circuit

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Page 9 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation

-, 2.3.2 Circuit Analysis Example 2: Unit 2 SOV with Automatic Actuation Figure 2-4 shows powe.r scheme for an SOV which controls the position of AOV 2CV-4941-2. The solenoid must be powered to be open as indicated by the FC (fail closed) designation for 2SV-4941-2.

The solenoid must be open to keep 2CV-4941-2 open. The power to this solenoid can be interrupted by several avenues.

This arrangement interlocks the open position of CV-4941 to the position of CV-4926 though relay 63X-4926 and interposing relay 94/4941-2 and the position of CV-4928 through 2HS-4928.

The normal opening and closing of the solenoid is controlled through contacts of 63X-4857A which is in turn controlled by a VCT level switch.

The solenoid can also be closed by the ESFAS with a SIAS signal opening its associated contact.

Normally all of the aforementioned contacts would be closed to keep 2SV-4941-2 energized and CV-4941 open. The 63X contact opens and shuts from time to time to automatically control VCT level.

If the 63X contact is closed, chatter could open the contacts for 63X, SIAS, or 94/4941-2 causing the solenoid to shut. However, closed is the desired safe shutdown position for this particular valve.

If the 63X contact is open, chatter could cause it to close opening the solenoid. However, the 63X contact has no seal-in capability and would re-open in short ord~r.

In summary although there are several contact devices that participate in the control of this valve, chatter is acceptable because the safe shutdown position for this valve is closed.

Page 10 of 73

Controlled Document Arkansas Nuclear One: S0.54(f) NTIF 2.1 Seism ic High Frequency Confi rm ation Figure 2-4: SOV with Automatic Actuation Features I .._

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Page 11of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation 2.4 CONTRIBUTIONS FOR HF EVALUATION 2.4.1 Changes to the Essential Relay Lists There are several relays from the original IPEEE ERLs that are no longer applicable, due to the design changes, and do not need HF confirmation analysis. New relays were also added to the ERL from the design changes described in Section 2.1. Specifically, the new inverters added several essential relays for each unit, to replace the ones that were retired with the old inverters.

The deletions and additions produce a revised ERL.

There are some relays on the revised ERL that are not a concern for high-frequency evaluation because of a mitigating factor, such as the resolution credited in the IPEEE applies also to HF vibration. For example, the resolution took credit for an operator action in the emergency operating procedures (EOP), or the relay failure was determined to have no consequence. Since these resolutions do not exclude high-frequency vibration, they are still applicable. Only the relays pertinent to high frequency evaluation are considered further.

2.4.2 Enhanced SSEL Contribution from Appendix R A few essential relays were found from the Enhanced SSEL. These include relays associated with a redundant steam supply path to the Turbine-driven EFW pump from a se~ond steam generator (both units), spurious actuation of containment spray (potential flow diversion, both units), spurious operation of core flood tank vent valves (unit 1), spurious operation of MSIV bypass valves (unit 2), premature operation of volume control tank isolation (unit 2) and EDG overspeed switches (unit 2).

Similar to Section 2.4.1, some of these essential relays are not a concern for high frequency evaluations because of a mitigating factor, for example crediting a justifiable operator action. Only the relays pertinent to high frequency evaluation are considered further.

2.4.3 Merging the Contributions For all of the relays contributed from the revised ERL and the Enhanced SSEL, the current information from the plant data base for the model, manufacturer, and location of each relay has been documented (see Section 2.5). This is input to the civil analysis team for high-frequency confirmation (see Section 3 and 4). Some of the essential relays from the IPEEE have changed manufacturer and model from the original analysis. This is primarily due to replacement of obsolete relays with newer models. In these cases the new relay is the functional equivalent of the original relay and so does not change its status as an essential relay. The HF confirmation analysis uses the current model information.

2.5

SUMMARY

OF SELECTED COMPONENTS A list of the contact devices requiring a high frequency confirmation is provided in Attachment B.

Page 12 of 73

Controlled Docun1ent Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation 3 Seismic Evaluation 3.1 HORIZONTAL SEISMIC DEMAND Per Reference [3], Sect. 4.3, the basis for calculating high-frequency seismic demand on the subject components in the horizontal direction is the ANO horizontal ground motion response spectrum (GMRS), which was generated as part of the ANO Seismic Hazard and Screening Report [6] submitted to the NRC on March 28, 2014 and accepted by the NRC on December 15, 2015 [21].

It is noted in Reference [3] that a Foundation Input Response Spectrum (FIRS) may be necessary to evaluate buildings whose foundations are supported at elevations different than the Control Point elevation. However, for sites founded on rock, per Reference [3], "The Control Point GMRS developed for these rock sites are typically appropriate for all rock-founded structures and additional FIRS estimates are not deemed necessary for the high frequency confirmation effort."

Section 3.3 of Reference [6] notes that safety-related structures at ANO are founded on rock.

Combining this condition with the justification provided in section 3.3 of Reference [3] on when a FIRS would normally be defined, the GMRS is judged appropriate for use as the site review level ground motion for high frequency evaluations.

The horizontal GMRS values are provided in Table 3-2.

3.2 VERTICAL SEISMIC DEMAND As described in Section 3.2 of Reference [3], the horizontal GMRS and site soil conditions are used to calculate the vertical GMRS (VG MRS), which is the basis for calculating high-frequency seismic demand on the subject components in the vertical direction.

The site's soil mean shear wave velocity vs. depth profile is provided in Reference [6], Table 2.3.2-1 (Profile 1) and partially reproduced below in Table 3-1.

Page 13 of73

- - ----~---

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Table 3-1: Soil Mean Shear Wave Velocity Vs. Depth Profile

. Depth Depth Thickness, .vs*i. Vs30.

Layer '(ft) . (ml di (ft) (f:t/sec) . ~i/Vs; I [di /Vs;] (ft/s) 1 10.00 3.05 10.0 5,302 0.0019 0.0019 2 20.00 6.10 10.0 5,307 0.0019 0.0038 3 30.00 9.14 10.0 5,312 0.0019 0.0057 4 40.00 12.19 10.0 5,317 0.0019 0.0075 5 50.00 15.24 10.0 5,322 0.0019 0.0094 5,324 6 60.00 18.29 10.0 5,327 0.0019 0.0113 7 70.00 21.34 10.0 5,332 0.0019 0.0132 8 80.00 24.38 10.0 5,337 0.0019 0.0150 9 90.00 27.43 10.0 5,342 0.0019 0.0169 98.43 30.00 8.4 0.0016 0.0185 10 5,347 100.00 30.48 1.6 Using the shear wave velocity vs. depth profile, the velocity of a shear wave traveling from a depth of 30m (98.4ft} to the surface of the site (Vs30) is calculated per the methodology of Reference [3], Section 3.5.

• The time for a shear wave to travel through each soil layer is calculated by dividing the layer depth (d;) by the shear wave velocity of the layer (Vs;).

• The total time for a wave to travel from a depth of 30m to the surface is calculated by adding the travel time through each layer from depths of Om to 30m (~[d;/Vs;]).

• The velocity of a shear wave traveling from a depth of 30m to the surface is therefore the total distance (30m) divided by the total time; i.e., Vs30 = (30m)/~[d;/Vs;].

The site's soil class is determined by using the site's shear wave velocity (Vs30) and the peak ground acceleration (PGA) of the GMRS and comparing them to the values within Reference [3],

Table 3-1. Based on the PGA of 0.24g and the shear wave velocity of 5,324ft/s, the site soil class is Class B-Hard.

Once a site soil class is determined, the mean vertical vs. horizontal GMRS ratios (V/H) at each frequency are determined by using the site soil class and its associated V/H values in Reference

[3], Table 3-2.

The vertical GMRS is then calculated by multiplying the mean V/H ratio at each frequency by the horizontal GMRS acceleration at the corresponding frequency. It is noted that Reference [3],

Table 3-2 values are constant between 0.1Hz and 20Hz for Class B-Hard soil sites.

The V/H ratios and VG MRS values are provided in Table 3-2 of this report.

Figure 3-1 below provides a plot of the horizontal GMRS, V/H ratios, and vertical GMRS for ANO.

Page 14 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Table 3-2: Horizontal and Vertical Ground Motions Response Spectra Frequency (Hz) HGMRS(g) V/H Ratio. VGMRS (g) 0.10 0.02 0.68 0.01 0.13 0.02 0.68 0.02 0.15 0.03 0.68 0.02 0.20 0.04 0.68 0.03 0.25 0.05 0.68 0.03 0.30 0.06 0.68 0.04 0.35 0.07 0.68 0.05 0.40 0.08 0.68 0.05 a.so 0.10 0.68 0.07 0.60 0.11 0.68 0.08 0.70 0.13 0.68 0.09 0.80 0.13 0.68 0.09 0.90 0.14 0.68 0.10 1.00 0.16 0.68 0.11 1.25 0.18 0.68 0.12 1.50 0.20 0.68 0.13 2.00 0.22 0.68 0.15 2.50 0.25 0.68 0.17 3.00 0.29 0.68 0.20 3.50 0.32 0.68 0.22 4.00 0.35 0.68 0.24 5.00 0.40 0.68 0.27 6.00 0.43 0.68 0.29 7.00 0.45 0.68 0.31 8.00 0.47 0.68 0.32 9.00 0.48 0.68 0.33 10.00 a.so 0.68 0.34 12.50 0.51 0.68 0.35 15.00 0.51 0.68 0.34 20.00 0.48 0.68 0.33 25.00 0.45 0.70 0.32 30.00 0.42 0.75 0.32 35.00 0.39 0.81 0.32 40.00 0.36 0.86 0.31 50.00 0.30 0.90 0.27 60.00 0.27 0.92 0.24 70.00 0.25 0.91 0.23 80.00 0.24 0.87 0.21 90.00 0.24 0.82 0.20 100.00 0.24 0.80 0.19 Page 15 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation 0.60

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Figure 3-1 Plot of the Horizontal and Vertical Ground Motions Response Spectra and V/H Ratios 3.3 COMPONENT HORIZONTAL SEISMIC DEMAND Per Reference [3], the peak horizontal acceleration is amplified using the following two factors to determine the horizontal in-cabinet response spectrum :

• Horizontal in-structure amplification factor AFsH to account for seismic amplification at floor elevations above the host building' s foundation

• Horizontal in-cabinet amplification factor AFcH to account for seismic amplification within the host equipment (cabinet, switchgear, motor control center, etc.)

The in-structure amplification factor AFsH is derived from Figure 4-3 in Reference [3]. The in-cabinet amplification factor, AFcH is associated with a given type of cabinet construction. The three general cab inet types are identified in Reference [3] and Appendix I of EPRI NP-7148 [19]

assuming 5% in-cabinet response spectrum damping. EPRI NP-7148 [19] classified the cabinet types as high amplification structures such as switchgear panels and other similar large flexible panels, medium amplification structures such as control panels and control room bench board panels and low amplification structures such as motor control centers.

All of the electrical cabinets containing the components subject to high frequency confirmation (see Table B-1 in Attachment B) can be categorized into one of the in-cabinet amplification categories in Reference [3] as follows:

Page 16 of 73

Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation

• Motor Control Centers are identified on the screening evaluation work sheets (SEWS) for equipment class 1 during the USI A-46 effort. These cabinets qualify as low amplification cabinets and receive an in-cabinet amplification factor of 3.6.

• Switchgear cabinets are identified on the SEWS for equipment classes 2 and 3 during the USI A-46 effort. These cabinets qualify as high amplification cabinets and receive an in-cabinet amplification factor of 7.2. The switchgear amplification factor is used when uncertainty exists in the applicability of lower amplification cabinet categories.

• Control cabinets consist of cabinets with height-to-depth ratios of about 3 (with a maximum height of 8ft) which results in moderate frame stresses and damping. The*

response levels are mid-range between MCCs and switchgear and therefore these cabinets can be considered in the medium amplification category and receive an in-cabinet amplification factor of 4.5.

The amplification factors for the in-cabinet responses are based on the worst location within a generic cabinet. Therefore, if the relays are mounted away from this worst case location, a reduction to the amplification factor can be taken. If the relay were mounted on the floor, this amplification factor would by definition be equal to 1.0. Assuming a linear relationship from the floor to the top of the cabinet, a different amplification factor can be determined for the bottom third and middle third of the cabinet. While this reduction does not directly consider the local panel vibration modes, the use of a linear relationship (instead of a non-linear mode shape similar to a cantilever deflection) and grouping the cabinet into thirds is considered to still be conservative.

3.4 COMPONENT VERTICAL SEISMIC DEMAND The component vertical demand is determined using the. peak acceleration of the VG MRS between 15 Hz and 40 Hz and amplifying it using the following two factors:

• Vertical in-structure amplification factor AFsv to account for seismic amplification at floor elevations above the host building's foundation

• Vertical in-cabinet amplification factor AFcv to account for seismic amplification within

. the host equipment (cabinet, switchgear, motor control center, etc.)

The in-structure amplification factor AFsv is derived from Figure 4-4 in Reference [3]. The in-cabinet amplification factor, AFcv is derived in Reference [3) and is 4.7 for all cabinet types.

Page 17 of73

Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation 4 Contact Device Evaluations Per Reference [3], seismic capacities (the highest seismic test level reached by the contact device without chatter or other malfunction) for each subject contact device are determined by the following procedures:

(1) If a contact device was tested as part of the EPRI High Frequency Testing program [8],

then the component seismic capacity from this program is used.

(2) If a contact device was not tested as part of [8], then one or more of the following means to determine the component capacity were used:

(a) Device-specific seismic test reports (either from ANO or from the Seismic Qualification Reporting & Testing Standardization (SQURTS) testing program.

(b) Generic Equipment Ruggedness Spectra (GERS) capacities per [17], [18], [22], and

[23].

(c) Assembly (e.g. electrical cabinet) tests where the component functional performance was monitored.

The high-frequency capacity of each device was evaluated with the component mounting point demand from Section 3 using the criteria in Section 4.5 of Reference [3].

A summary of the high-frequency evaluation conclusions is provided in Table B-1 in Attachment B.

Page 18 of 73

Controlled Docun1ent Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation 5 Conclusions 5.1 GENERAL CONCLUSIONS ANO has performed a High Frequency Confirmation evaluation in response to the NRC's 50.54(f) letter [1] using the methods in EPRI report 3002004396 [3].

The evaluation identified a total of 394 components that required evaluation. As summarized in Table B-1 in Attachment B, devices with evaluation result of 'confirmed' have adequate seismic capacity. Components requiring further resolution following the criteria in Section 4.6 of Reference [3] are identified in Table B-1 in Attachment Band listed separately in Table C-1 of Attachment C. Furthermore, Table C-1 includes a description of the outlier resolution.

5.2 IDENTIFICATION OF FOLLOW-UP ACTIONS Operator actions referred to in outlier resolutions in Attachment C require no procedure revisions. The full details of required operator actions, including review of existing ANO procedures, are documented in Reference [24]. At AN0-1 there are a total of twenty-three (23) operator actions required at a total of four (4) locations. At AN0-2, there are a total of four (4) operator actions required at a total of four (4) locations.

For AN0-1, the comprehensive scope of operator actions required for outlier relays is listed below:

Depress two pushbuttons (one on both 'A' red and 'B' green trains)

Reset two lockout relays (one on both red and green trains)

Close ten (10) breakers located on the A3 Bus (red train)

Close nine (9) breakers located on the A4 Bus (green train)

For AN0-2, the comprehensive scope of operator actions required for outlier relays is listed below:

Reset two lockout relays (one on both red and green trains)

Close one (1) breaker located on the 2A3 Bus ('A' red train)

Close one (1) breaker located on the 2A4 Bus ('B' green train)

Procedural guidance for the operator actions defined above is provided in existing ANO procedures as detailed in Reference [24].

No additional follow up actions are required.

Page 19 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation 6 References 1 NRC (E. Leeds and M. Johnson) Letter to All Power Reactor Licensees et al., "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident," March 12, 2012, ADAMS Accession Number ML12053A340 2 EPRI 1025287. "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resqlution of Fukushima Near-Term Task Force Recommendation 2.1:

Seismic." February 2013 3 EPRI 3002004396. "High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation." July 2015 4 NRC (J. Davis) Letter to Nuclear Energy Institute (A. Mauer). "Endorsement of Electric Power Research Institute Final Draft Report 3002004396, 'High Frequency Program: Application Guidance for Functional Confirmation and Fragility."' September 17, 2015, ADAMS Accession Number ML15218A569.

5 NRC (W. Dean) Letter to the Power Reactor Licensees on the Enclosed List. "Final Determination of Licensee Seismic Probabilistic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendation 2.1 "Seismic" of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident." October 27, 2015, ADAMS Accession Number ML15194A015 6 Entergy Letter to NRC, "Seismic Hazard and Screening Report (Central Eastern United States (CEUS) Sites), Response to NRC Request for Information (RFI) Pursuant to 10 CFR 50.54(f)

Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident, Arkansas Nuclear One - Units 1 and 2." March 28, 2014, ADAMS Accession Number ML14092A021 7 EPRI 1015109. "Program on Technology Innovation: Seismic Screening of Components Sensitive to High-Frequency Vibratory Motions." Ocfober 2007 8 EPRI 3002002997. "High Frequency Program: High Frequency Testing Summary." September 2014 9 NEI 12-06, "Diverse and Flexible Coping Strategies (FLEX) Implementation Guide," Appendix H, Nuclear Energy Institute, November 30, 2015.

10 Entergy Document 93-SQ-1001-04, Revision 3, "USI A-46/IPEEE Relay Evaluation list for AN0-1," March 1996.

11 Entergy Document 93-SQ-2001-04, Revision 2, "USI A-46/IPEEE Relay Evaluation Report for AN0-2," June 1998.

12 Entergy Document 93-SQ-1001-02, Revision 0, "USI A-46/IPEEE Safe Shutdown Success Path Selection Report for AN0-1," August 1993.

13 Entergy Document 93-SQ-2001-02, Revision 0, "USI A-46/IPEEE Safe Shutdown Success Path Selection Report for AN0-2," November 1993.

Page 20 of 73

Controlled Document Arkansas Nuclear One: S0.54(f) NTIF 2.1 Seismic High Frequency Confirmation 14 Entergy Document 93-SQ-1001-03, Revision 4, "USI A-46/IPEEE Safe Shutdown Equipment List (SSEL) Report for AN0-1," April 1996.

15 Entergy Document 93-SQ-2001-03, Revision 3, "USI A-46/IPEEE Safe Shutdown Equipment List (SSEL) Report for AN0-2," April 1996.

16 EC 65905, EN-DC-141Attachment9.1 & 9.2, "Screening of ANO Safe Shutdown Equipment List," August 2016.

17 EPRI NP-7147-SL. "Seismic Ruggedness of Relays," August 1991 18 EPRI NP-7147-SL, V2, "Seismic Ruggedness of Relays" April, 1995.

19 EPRI NP-7148, "Procedure for Evaluating Nuclear Power Plant Relay Seismic Functionality,"

December, 1990.

20 EPRI 3002000709, "Seismic Probabilistic Risk Assessment Implementation Guide,"

December, 2013.

21 NRC Letter, "Arkansas Nuclear One, Units 1 and 2 - Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50, Section 50.54(f),

Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident." December 15, 2015, ADAMS Accession Number ML15344A109 22 EPRI TR-105988, "GERS Formulated Using Data from the SQURTS Program," Final Report, April 1996.

23 EPRI TR-105988-V2, "GERS Formulated Using Data from the SQURTS Program," Final Report, April 1999.

24 EC 68207, "AN01/AN02 Outlier Relays Resolved Via Post Event Operator Actions,"

December 2016.

AREVA Documents supporting the Development of this Report:

25 AREVA Document 32-9257563-001, "Arkansas Nuclear One Unit 1 HFE - Component Mounting Point Demand."

26 AREVA Document 32-9257565-001, "Arkansas Nuclear One Unit 2 HFE - Component Mounting Point Demand."

27 AREVA Document 32-9261655-001, "Arkansas Nuclear One Unit 1 HFE- HCLPF Capacity Evaluation."

28 AREVA Document 32-9261657-001, "Arkansas Nuclear One Unit 2 HFE - HCLPF Capacity Evaluation."

29 AREVA Document 51-9261429-001, "ANO High Frequency Chatter Assessment Supporting Documentation."

Page 21 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation A Representative Sample Component Evaluations A.1 Demand The Conservative Deterministic Failure Margin (CDFM) mounting point demand at each relevant elevation in terms of peak spectral accelerations from clipped in-cabinet response spectra (ICRSc) is calculated in the below table.

Component HT. above ISRS(GMRS)(g) ISRS(@Elcv.)(g) AF,H ICRS,H (g) ICRS,v(g)

AFSH AFsv AF,v Elevation Folll!dation HGMRS VGMRS Si\,H Si\ov MCC Switchgear Control Cab. MCC Switchgear Control Cab. All Cabinet 335'-0" 0' 1.20 1.00 0.506 0.344 0.607 0.344 3.6 7.2 4.5 4.7 2.186 4.372 2.732 1.617 (Folll!dation) 354'-0" 19' 1.63 1.32 0.506 0.344 0.824 0.455 3.6 7.2 4.5 4.7 2.965 5.929 3.706 2.139 368'-0" 33' 1.94 1.56 0.506 0.344 0.983 0.537 3.6 7.2 4.5 4.7 3.538 7.077 4.423 2.524 369'-0" 34' 1.97 1.58 0.506 0.344 0.994 0.543 3.6 7.2 4.5 4.7 3.579 7.159 4.474 2.551 372'-0" 37' 2.03 1.63 0.506 0.344 1.028 0.560 3.6 7.2 4.5 4.7 3.702 7.405 4.628 2.634 373'-0" 38' 2.06 1.65 0.506 0.344 1.040 0.566 3.6 7.2 4.5 4.7 3.743 7.487 4.679 2.661 386'-0" 51' 2.10 1.87 0.506 0.344 1.063 0.642 3.6 7.2 4.5 4.7 3.825 7.651 4.782 3.019 It should be noted, for the horizontal direction, the demand is dependent on the type of equipment in which the relay is mounted (i.e. MCC, switchgear, or control cabinet).

A.2 . GE CR120A02202AA Relay Evaluation The Generic Equipment Ruggedness Spectrum (GERS) for the GE CR120A series relays are presented starting on page B-43 of Reference [17]. Per Reference [17], the model tested was a CR120A02202AA, which is an exact match for the relay at AN0-1. For the CR120A02202AA relay, a high frequency capacity of 9g is used along with an FK = 1.5 (the capacity knockdown factor, FK, is determined based on the test source as provided in Table 4-2 of Reference [3]).

The table below contains the complete list of GE CRl 20A02202AA relays along with their respective capacity to demand ratios. The minimum capacity to demand ratio is 1.70 for the horizontal and 2.38 for the vertical checks.

A.3 GE 12GGP53B1A Relay Evaluation The Generic Equipment Ruggedness Spectrum (GERS) for the GE GGP53B series relays are presented starting on page B-87 of Reference [17]. Per Reference [17], the important model number characters that affect ruggedness have been identified. For the 12GGP53B1A relays, a high frequency capacity of 5g is used along with an FK = 1.5 (the knockdown factor, FK, is determined based on the test source as provided in Table 4-2 of Reference [3]).

The table below contains the complete list of GE GGP Series relays along with their respective capacity to demand ratios. The minimum capacity to demand ratio is 0.45 for the horizontal and 1.27 for the vertical checks. Both the 12GGP53B lA are outliers as they have capacity to demand ratios less than one.

Note that these relays are located in switchgear A-3 and A-4, which consist of a long line of side by side cabinets and may be able to take advantage of using the multi-axis to single axis correction factor (i.e. FMs

= 1.2). However, this factor alone would not change the outlier status of the relays.

Page 22 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation GE CRl20A02202AA Relay Margin Horizontal Vertical llOX SSELCOmponent Description RELAY 85173 P-78 suet from CST System Relay Description 42X-5173 EFW EFW PUMP P-78 CONO WATER CV-2800 CONTROL RELAY MFG Model GE Location CR120A02202AA MCC 8-Sl BLDG RAB ELEV 368 ROOM 104 COL G 1CR5c SA*

(g) 3.538 (g) 9 SAr (g)

Fk 1.5 FMs TRS 6.000 TRS/ICRSt ICRS, SA*

1.70 (g) 2.524 (g) 9 SAr (g)

F*

1.5 FMs 1

TRS 6.000 TRS/ICRS, 2.38 GE 12GGP5381A Relay Margin Horizontal Vertical TRS/ICRS, ICRS, SA* SA1

[aox SSEL Component Description RELAY System Re lay De scription MFG Model Location - ICRS, SA* SA1 F, FMs (g) (g) (g)

TRS SA,'FMJF, (g) (g) (g) (g)

F, FM, TRS SA, 'FMJF, (g)

TR5/ICR5, A3 EOG 1 Output Breaker A-308-132 fl32-DG1) EDG DIESEL GENERATOR ANTIMOTORING RELAY GE 12GGP53BlA RAB - - BLDG RAB ELEV 372 ROOM 100 COLE 7.405 1.5 3.333 0.45 2.634 5 1.5 3.333 1.27 A4 EOG 2 Output Breaker A-408-132 l!32*DG2) EOG DI ES EL GENERATOR ANTIMOTORING RELAY GE 12GGP53BlA RAB* *BLDG RAB ELEV 372 ROOM99 COLD 7.405 1.5 3.333 0.45 2.634 5 1.5 3.333 1.27 Page 23 of 73

Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation B Components Identified for High Frequency Conti rmati-on Page 24 of 73

Controlled Document Arkansas Nuclear One: S0.54(f) NTIF 2.1 Seismic High Frequency Confirmation Table B-1: Components Identified for High Frequency Confirmation Component Component Evaluation Linc Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results RAB - - BLDG RAB ELEV I I 162-A3/l TIME DELAY RELAY A3 4160 Volt Bus A-3 AMERACE CORP E7012PB003 Cl8 EPRINP-7147-SL Confirmed 386 ROOM 129 COL B UNDERVOLTAGE RELAY EDG I Output RAB - - BLDG RAB ELEV 2 1 127-A3/Xl A308 GE 12HFAl51A2F A3 EPRI 3002002997 Confirmed FORBUSA3 Breaker 372 ROOM 100 COLE UNDERVOLTAGE RELAY EDG 1 Output RAB - - BLDG RAB ELEV 3 I 127-A3/X2 A308 GE 12HFA151A2F A3 EPRI 3002002997 Confirmed FORBUSA3 Breaker 372 ROOM 100 COLE UV AUX RELAY FOR EDG 1 Output RAB - - BLDG RAB ELEV 4 1 127-A3/X3 A308 GE 12HFAl51A2F A3 EPRI 3002002997 Confirmed PRIMARY MU PMP P36A Breaker 372 ROOM IOO COLE A3 BUS UNDERVOLTAGE EDG 1 Output RAB - - BLDG RAB ELEV 5 I 127-A3/X4 A308 GE 12HFAl51A2H A3 EPRI 3002002997 Confirmed RELAY Breaker 372 ROOM 100 COLE A-308-132 DIESEL GENERATOR EDG 1 Output RAB - - BLDG RAB ELEV 6 1 A308 GE 12GGP53B1A A3 EPRINP-7147-SL Outlier (132-DGI) ANTIMOTORING RELAY Breaker 372 ROOM IOO COL E DIESEL GEN OC RELAY A-308-lSlVA EDG I Output RAB - - BLDG RAB ELEV 7 1 WITH VOLTAGE A308 GE 121JCV51A13A A3 ANO Documentation Outlier (151V-DGl-A) Breaker 372 ROOM IOO COL E RESTRAINT DIESEL GEN OC RELAY A-308-ISIVB EDG I Output RAB - - BLDG RAB ELEV 8 I WITH VOLTAGE A308 GE 12IJCV51Al3A A3 ANO Document<ition Outlier (151V-DGl-B) Breaker 372 ROOM IOO COLE RESTRAINT DIESEL GEN OC RELAY A-308-lSIVC EDG 1 Output RAB - - BLDG RAB ELEV 9 1 WITH VOLTAGE A308 GE 12IJCV51A13A A3 ANO Documentation Outlier (151V-DGl-C) Breaker 372 ROOM 100 COLE RESTRAINT Page 25 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results EDG i Output RAB - - BLDG RAB ELEV IO i 152Xl-308 AC AUX RELAY FOR A-308 A308 GE 12HGAi IJ52 A3 EPRI NP-7i47-SL Outlier Breaker 372 ROOM iOO COLE AC CIRCUIT BREAKER EDG i Output RAB - - BLDG RAB ELEV Ii i 152X-308 A308 GE 12HFA!51A2F A3 EPRI 3002002997 Confirmed RELAY FOR A-308 Breaker 372 ROOM 100 COLE K-4A-!59N DIESEL GEN NEUTRAL EDG I Output RAB - - BLDG RAB ELEV 12 I A308 GE 121AV51D2A A3 ANO Documentation Confirmed (159N-DGI) OVERVOLTAGERELAY Breaker 372 ROOM 100 COLE EDG I Output RAB - - BLDG RAB ELEV 13 I 162-DGl/l DG I LOCKOUT RELAY A308 AMERACE CORP E7012PB003 A3 EPRINP-7147-SL Confirmed Breaker 372 ROOM 100 COLE EDG I Output RAB - - BLDG RAB ELEV 14 I 162-DGl/2 DGI LOCKOUT RELAY A308 AMERACE CORP E7012PB003 A3 EPRI NP-7147-SL Confirmed Breaker 372 ROOM 100 COL E EDG I Output RAB - - BLDG RAB ELEV 15 I 186-DGI LOCKOUT RELAY FOR DG I A308 GE !2HEA62A224X2 A3 EPRI 3002002997 Confirmed Breaker 372 ROOM 100 COLE Normal Supply RAB - - BLDG RAB ELEV UNDER VOLTAGE RELAY 16 I A-3-127 A3AB A309 Bkr-AI FEED GE 121AV54EIA A3 372 ROOM 100 COLE EPRINP-7147-SL Outlier FOR BUS A-3 (A&B PHASES)

TOA3 LINE 5.4 OVERCURRENT RELAY Normal Supply RAB - - BLDG RAB ELEV 17 I A-309-151A FOR BUS TIE FOR Al AND A309 Bkr-AI FEED GE 121AC51AIOIA A3 ANO Documentation Confirmed 372 ROOM 100 COLE A3 TOA3 OVERCURRENT RELAY Normal Supply RAB - - BLDG RAB ELEV 18 I A-309-151B FORBUS TIEFORAI AND A309 Bkr-AIFEED GE 121AC51AIO!A A3 ANO Documentation Confirmed 372 ROOM 100 COLE A3 TOA3 Page 26 of 73

Controlled Document Arkansas* Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results OVERCURRENT RELAY Normal Supply 19 I A-309-151C RAB - - BLDG RAB ELEV FOR BUS TIE FOR Al AND A309 Bkr-Al FEED GE 12IAC51AIOIA A3 ANO Documentation Confirmed 372 ROOM 100 COLE A3 TOA3 Normal Supply OVERCURRENTRELAY/ RAB - - BLDG RAB ELEV 20 I A-309-ISIN A309 Bkr-Al FEED GE l 21AC77A80 I A A3 ANO Documentation Confirmed NEUTLTIE FOR A2 AND A3 372 ROOM 100 COLE TOA3 Nonna! Supply LOCKOUT RELAY FOR BUS RAB - - BLDG RAB ELEV 21 I 186-A3 A309 Bkr-Al FEED GE 12HEA62B236X2 A3 EPRI 3002002997 Confirmed A-3 372 ROOM 100 COLE TOA3 OVERCURRENT RELAY for RAB - - BLDG RAB ELEV 22 I A-310-151GS A310 A3-A4 CROSSTIE GE 12IAC77A801A A3 ANO Documentation Confirmed Bus tie A3&A4 372 ROOM 100 COLE ENGINEERED SAFEGUARD POTTER& RAB - - BLDG RAB ELEV 23 I 27-B5/X BUS A3 UNDERVOLTAGE A310 A3-A4 CROSSTIE MDR-137-8 A3 EPR! 3002002997 Confirmed BRUMFIELD 372 ROOM 100 COLE RELAY CONTROL RELAY FOR POTTER& RAB - - BLDG RAB ELEV 24 I CR-309 A310 A3-A4 CROSSTIE MDR-5138 A3 SQURTS Testing Confirmed CKTBRK A-309 BRUMFIELD 372 ROOM 100 COLE REACTOR COOLANT PUMP POTTER& RAB - - BLDG RAB ELEV 25 I HA3 A310 A3-A4 CROSSTIE MDR-137-8 A3 EPRI 3002002997 Confirmed STARTING UN RELAY BRUMFIELD 372 ROOM 100 COLE TIME DELAY RAB - - BLDG RAB ELEV 26 I 162-A4/l UNDERVOLTAGE RELAY A4 4160VoltBusA-4 AMERACE CORP E7012PB003 Cl6 EPRINP-7147-SL Confirmed 386 ROOM 129 COL B FORA4BUS REACTOR COOLANT PUMP POITER& RAB - - BLDG RAB ELEV 27 I HA4 A407 MDR-137-8 A4 EPRI 3002002997 Confirmed STARTING UN RELAY BRUMFIELD 372 ROOM 99 COLD Page 27 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results UNDER VOLTAGE AUX EDG20utput RAB - - BLDG RAB ELEV 28 I 127-A4/XI A408 GE 12HFA151A2F A4 EPRI 3002002997 Confirmed RELAY BUSA4 Breaker 372 ROOM 99 COLD UV AUX RELAY FOR EDG2 Output RAB - - BLDG RAB ELEV 29 1 127-A4/X2 A408 GE 12HFAi51A2F A4 EPRI 3002002997 Confirmed PRIMARY MU PUMP P36B Breaker 372 ROOM 100 COLE UV AUX RELAY FOR EDG2 Output RAB - - BLDG RAB ELEV 30 1 127-A4/X3 A408 GE 12HFA151A2F A4 EPRI 3002002997 Confirmed PRIMARY MU PUMP P36A Breaker 372 ROOM 99 COLD A4BUSUNDERVOLTAGE EDG20utput POTTER& RAB - - BLDG RAB ELEV 31 I 127-A4/X5 A408 MDR-5138 A4 SQURTS Testing Confirmed AUX RELAY Breaker BRUMFIELD 372 ROOM 99 COLD A-408-132 DIESEL GENERATOR EDG2 Output RAB - - BLDG RAB ELEV 32 1 A408 GE 12GGP53BlA A4 EPRI NP-7147-SL Outlier (i32-DG2) ANTIMOTORING RELAY Breaker 372 ROOM99 COLD DIESEL GEN OC RELAY A-408-151VA EDG2 Output RAB - - BLDG RAB ELEV 33 I WITH VOLTAGE A408 GE 12IJCV51Al3A A4 ANO Documentation Outlier (151VDG2-A) Breaker 372 ROOM 99 COLD RESTRAINT DIESEL GEN OC RELAY A-408-i51VB EDG2 Output RAB - - BLDG RAB ELEV 34 I WITH VOLTAGE A408 GE 12IJCV51Al3A A4 ANO Documentation Outlier (151VDG2-B) Breaker 372 ROOM 99 COLD RESTRAINT DIESEL GEN OC RELAY A-408-ISIVC EDG2 Output RAB - - BLDG RAB ELEV 35 I WITH VOLTAGE A408 GE 12IJCV51Al3A A4 ANO Documentation Outlier (15!VDG2-C) Breaker 372 ROOM99 COLD RESTRAINT EDG2 Output RAB - - BLDG RAB ELEV 36 I 152X!-408 AC AUX RELAY FOR A-408 A408 GE 12HGA11J52 A4 EPRINP-7147-SL Outlier Breaker 372 ROOM 99 COLD Page 28 of 73

Controlled Document Arkansas Nuclear One: S0.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Linc Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results A-C CIRCUIT BREAKER EDG2 Output RAB - - BLDG RAB ELEV 37 I 152X-408 A408 GE 12HFAl51A2F A4 EPRI 3002002997 Confirmed RELAY FOR A-408 Breaker 372 ROOM99 COLD Breaker anti-pump relay EDG2 Output RAB - - BLDG RAB ELEV 38 I 152Y-408 A408 GE 12HMA11B6 A4 EPRI NP-7147-SL Outlier (magnablast) Breaker 372 ROOM99 COLD DIESEL GENERATOR EDG2 Output RAB - - BLDG RAB ELEV 39 1 K-4B-159N NEUTRALOVERVOLTAGE A408 GE 121AV51D2A A4 ANO Documentation Confirmed Breaker 372 ROOM 99 COLD RELAY EDG 2 Output RAB - - BLDG RAB ELEV 40 I 162-DG2/I DG2 LOCKOUT RELAY A408 AMERACE CORP E7012PB003 A4 EPRI NP-7147-SL Confirmed Breaker 372 ROOM 100 COLE EDG20utput RAB - - BLDG RAB ELEV 41 I 162-DG2/2 DG2 LOCKOUT RELAY A408 AMERACE CORP E7012PB003 A4 EPRINP-7147-SL Confirmed Breaker 372 ROOM 100 COLE EDG2 Output RAB - - BLDG RAB ELEV 42 I 186-DG2 LOCKOUT RELAY FOR DG2 A408 GE 12HEA62A224X2 A4 EPRJ 3002002997 Confirmed Breaker 372 ROOM99 COLD UNDER VOLTAGE RELAY Normal Supply RAB - - BLDG RAB ELEV 43 I A-4-127 A4AB FOR BUS A-4 (A & B A409 Bkr-A2 FEED GE 121AV54ElA A4 372 ROOM 99 COL D EPRI NP-7147-SL Outlier PHASES) TOA4 LINE 5.5 Normal Supply OVERCURRENT RELAY RAB - - BLDG RAB ELEV 44 I A-409-151A A409 Bkr-A2 FEED GE 121AC51AIOIA A4 ANO Documentation Confirmed FOR BUS TIE A4 AND A2 372 ROOM99 COLD TOA4 Normal Supply OVERCURRENT RELAY RAB - - BLDG RAB ELEV 45 1 A-409-151B A409 Bkr-A2FEED GE 121AC51Al01A A4 ANO Documentation Confirmed FOR BUS TIE A4 AND A2 372 ROOM99 COLD TOA4 Normal Supply OVERCURRENT RELAY RAB - - BLDG RAB ELEV 46 I A-409-151C A409 Bkr-A2 FEED GE 121AC51AIOIA A4 ANO Documentation Confirmed FOR BUS TIE A4 AND A3 372 ROOM 99 COLD TOA4 Page 29 of 73

Controlled Document Arkansas Nuclear One: S0.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results Normal Supply OVERCURRENTRELAY RAB - - BLDG RAB ELEV 47 I A-409-151N A409 Bkr-A2 FEED GE 121AC77A80IA A4 ANO Documentation Confirmed FOR I NEUTRAL 372 ROOM99 COLD TOM Normal Supply LOCKOUT RELAY FOR BUS RAB - - BLDG RAB ELEV 48 I 186-M A409 Bkr-A2 FEED GE I 2HEA62B236X2 A4 EPRI 3002002997 Confirmed A4 372 ROOM 99 COLD TOM OVERCURRENT RELAY A4-A3 RAB - - BLDG RAB ELEV 49 I A-410-151GS A410 GE 121AC77A801A A4 ANO Documentation Confirmed FOR BUS TIE A3 AND A4 CROSS TIE 372 ROOM 99 COLD ENGINEERED SAFEGUARD A4-A3 POTTER& RAB - - BLDG RAB ELEV 50 I 27-B6/X BUSA4UNDERVOLTAGE MIO MDR-137-8 M EPRI 3002002997 Confirmed CROSS TIE BRUMFIELD 372 ROOM 99 COLD RELAY CONTROL RELAY FOR M-A3 POTTER& RAB - - BLDG RAB ELEV SI I CR-409 MIO MDR-Sl38 A4 SQURTS Testing Confirmed CKTBRK A-409 CROSS TIE BRUMFIELD 372 ROOM99 COLD RAB - - BLDG RAB ELEV B-S-271/BS BUS B UNDERVOLTAGE GOULD INC S2 I BSI I TYPE27N BS 372 ROOM 100 COLE EPRI 3 002002997 Confirmed (27-1/BS) RELAY DIESEL START (FORMERLY !TE)

LINE S.4 RAB - - BLDG RAB ELEV B-S-272/BS BUS B UNDERVOLTAGE GOULD INC S3 1 BS!! TYPE27N BS 372 ROOM 100 COLE EPRI 3002002997 Confirmed (27-2/BS) RELAY DIESEL START (FORMERLY !TE)

LINE S.4 TRANSFER TO RAB - - BLDG RAB ELEV S4 I 42/X4 EMERGENCY BUS B-5 B5611 GE 12HGA11J70 B56 EPRI 3002002997 Confirmed 372 ROOM 99 COLD RELAY ASCO-CONTROL RELAY FOR RAB - - BLDG RAB ELEV SS I CR2 BS611 AUTOMATIC PN 261479-2 B56 No Capacity Found Outlier transfer switch 372 ROOM 99 COLD SWITCHC Page 30 of 73

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Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results RAB - - BLDG RAB ELEV B-6-271/B6 BUS B UNDERVOLTAGE GOULD INC 56 I B611 TYPE27N B6 372 ROOM99 COLD EPRI 3002002997 Confirmed (27-l/B6) RELAY DIESEL START (FORMERLY !TE)

LINE 5.5 B-6-272/B6 RAB - - BLDG RAB ELEV BUS B UNDERVOLTAGE GOULD INC 57 I B611 TYPE27N B6 372 ROOM99 COLD EPRI 3002002997 Confirmed (27-2/B6) RELAY DIESEL START (FORMERLY !TE)

LINE 5.5 MCCB-56 BLDGRAB CV-1275 CONTACTOR SIZE T4 Out(Stop 58 I 42R-5652 CV-1275 SIEMENS 3TF44 (CRLOF4422K61) B5652 ELEV 372 ROOM 99 COL EPRI 3002002997 Confirmed I Check)

D MCCB-51 BLDGRAB CV-1405 CONT ACTOR SIZE P34NP35A Suet PIN 25-111-110-512 (CAT No.

59 1 42F-51112 CV-1405 ALLIS-CHALMER B51112 ELEV368 ROOM 104 COL EPRI 3002002997 Confirmed 1 from RB Sump 25-111-000-501)

G CV-1406 CONTACTOR SIZE PIN 25-111-110-512 (CAT No. MCCB-61 BLDGRAB 60 1 42F-6166 CV-1406 RB sump to P34B ALLIS-CHALMER B6166 EPRI 3002002997 Confirmed 1 25-111-000-501) ELEV 386 ROOM 149 COL CV-1436 CONTACTOR SIZE P34A Suet from MCCB-57 BLDGRAB 61 I 42R-5742 CV-1436 ITE/telemecanique Series 5600 B5742 EPRI 3002002997 Confirmed 1 BWST ELEV 372 ROOM 100 CV-1437 CONTACTOR SIZE MCCB-65 BLDG RAB 62 1 42R-6542 CV-1437 BWSTtoP34B ITE/telemecanique series 5600 B6542 EPRI 3002002997 Confirmed I ELEV 372 ROOM 99 MCCB-51 BLDGRAB CV-1814 CONTACTORSIZE PZE Steam Space PIN 25-111-110-512 (CAT No.

63 1 42F-5l9l CV-1814 ALLIS-CHALMER B5191 ELEV 368 ROOM 104 COL EPRI 3002002997 Confirmed 1 Sample!SOL 25-111-000-501)

G MCCB-51 BLDG RAB CV-1816 CONTACTOR SIZE PZR water Space PIN 25-111-110-512 (CAT No.

64 1 42F-5192 CV-1816 ALLIS-CHALMER B5192 ELEV 368 ROOM 104 COL EPRI 3002002997 Confirmed 1 Sample !sol 25-111-000-501)

G MCCB-62 BLDG RAB CV-1820 CONTACTOR SIZE SG E24A sample PIN 25-111-110-512 (CAT No.

65 1 42F-622l CV-1820 ALLIS-CHALMER B622l ELEV 386 ROOM 149 COL EPRI 3002002997 Confirmed 1 isol 25-111-000-501) c MCCB-62 BLDG RAB CV-1826 CONTACTOR SIZE SG 24B sample PIN 25-111-110-512 (CAT No.

66 1 42F-6244 CV-1826 ALLIS-CHALMER B6244 ELEV 386 ROOM 149 COL EPRI 3002002997 Confirmed 1 isol 25-111-000-501) c Page 31of73

Controlled Document Arkansas Nuclear One: 50.54(f) NITF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Linc Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results MCCB-51 BLDG RAB 67 1 42F-5174 CV-2416 CONTACTOR SIZE CV-2416 CFTT-2A PIN 25-111-110-512 (CAT No.

ALLIS-CHALMER B5174 ELEV368 ROOM 104 COL EPRI 3002002997 Confirmed 1 bleed/sample isol 25-111-000-501)

G MCCB-61 BLDG RAB CV-2418 CONTACTOR SIZE CFTT-2B PIN 25-111-110-512 (CAT No.

68 I 42F-6174 CV-2418 ALLIS-CHALMER B6174 ELEV386 ROOM 149 COL EPRI 3002002997 Confirmed I bleed/sample isoi 25-1I1-000-501) c MCCB-51 BLDG RAB 69 1 42R-5173 CV-2800 CONTACTOR SIZE P-7B suet from PIN 25-111-110-512 (CAT No.

CV-2800 ALLIS-CHALMER 85173 ELEV368 ROOM 104 COL EPRI 3002002997 C-0nfirmed I CST 25-111-000-501)

G EFW PUMP P-7B COND MCCB-51 BLDG RAB P-7B suet from 70 I 42X-5173 WATER CV-2800 CONTROL CV-2800 GE CR120A02202AA B5173 ELEV 368 ROOM 104 COL EPRI NP-7147-SL Confirmed CST RELAY G MCCB-61 BLDG RAB CV-2802 INTERPOSING P-7 A suet from SIEMENS-ALLIS 71 1 42RIX-6175 CV-2802 TA68 B6175 ELEV386 ROOM 149 COL ANO Documentation Confirmed RELAY CST INC c

MCCB-61 BLDG RAB 72 I 42R-6175 CV-2802 CONTACTOR SIZE CV-2802 P-7A suet from PIN 25-111-110-512 (CAT No.

ALLIS-CHALMER B6175 ELEV 386 ROOM 149 COL EPRI 3002002997 Confirmed 1 CST 25-111-000-501) c MCCB-51 BLDG RAB 73 I 42F-5134 CV-2869 CONTACTOR SIZE P-7B test recirc PIN 25-111-110-512 (CAT No.

CV-2869 ALLIS-CHALMER B5134 ELEV 368 ROOM 104 COL EPRI 3002002997 Confirmed I isol 25-111-000-501)

G P-7A test recirc MCCD-25 BLDG RAB 74 1 42F-2513 CV-2870 CONTACTOR CV-2870  !TE Class A20 D2513 EPRI 3002002997 Confirmed isoi ELEV 373 ROOM cond MCCB-22 BLDG TB 75 1 42F-2255 CV-2873 CONTACTOR CV-2873 tank/condenser  !TE Class A20 B2255 ELEV354 ROOM74 COL EPRI 3002002997 Confirmed makeup H Page 32 of 73

Controlled Document Arkansas Nuclear One: S0.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results cond 76 1 LSX-2873 RAB - - BLDG RAB ELEV BOP RELAY CV-2873 tank/condenser GE 12HGA11J52 C30 EPRI NP-7147-SL Confinned 386 ROOM 129 COL B makeup 77 1 42F-1255 cond water to MCCB-12 BLDG TB CV-2877 CONTACTOR CV-2877  !TE ClassA20 Bl255 EPRI 3002002997 Con finned storage tank reject ELEV 354 ROOM 74 COLJ cond water to RAB - - BLDG RAB ELEV 78 I LSX-2877 BOP RELAY CV-2877 GE 12HGA11J52 C30 EPRINP-7147-SL Confinned storage tank reject 386 ROOM 129 COL B MCCB-21 BLDG RAB SW RTN to Disch 79 1 42F-2144 CV-3824 CONTACTOR CV-3824  !TE Class A20 B2144/B2133 ELEV 368 ROOM 104 COL EPRI 3002002997 Con finned Flume G

ASCO-CONTROL RELAY FOR D-01 D0112 (43- MCC - transfer RAB - - BLDG RAB ELEV 80 1 CR2-I AUTOMATIC PN 261 479-2 DOI No Capacity Found Outlier (EMERGENCY) DOI) switch 372 ROOM 95 COL B SWITCHC ASCO-CONTROL RELAY FOR D-02 D0212 (43- MCC - transfer RAB - - BLDG RAB ELEV 81 1 CR2-2 AUTOMATIC PN 261 479-2 D02 No Capacity Found Outlier (EMERGENCY) D02] switch 372 ROOM 109 COLD SWITCHC K-4A-127DG1 EDG&

DIESEL GEN RUNNING RAB - - BLDG RAB ELEV 82 1 *(127-DGl K-4A accessories GE 12HFAl51A9H Ell EPRI 3002002997 Outlier RELAY 369 ROOM 87 COLC

{Kl9)) assembly EDG&

CRANK TIME DELAY TYCO RAB - - BLDG RAB ELEV 83 1 Cl07-Kl K-4A accessories E7012PC004 Cl07 EPRI NP-7147-SL Confirmed RELAY ELECTRONICS 369 ROOM87 COLB assembly EDG&

WESTINGHOUSE RAB - - BLDG RAB ELEV 84 1 Cl07-KIO ACCESSORY RELAY K-4A accessories ARD440SR Cl07 EPRI NP-7147-SL Con finned ELECCORP 369 ROOM 87 COLB assembly EDG&

TROUBLE SHUTDOWN WESTINGHOUSE RAB - - BLDG RAB ELEV 85 I Cl07-Kll K-4A accessories ARD440SR Cl07 EPRI NP-7147-SL Confinned RELAY ELECCORP 369 ROOM 87 COLB assembly EDG&

CRANK RESET TIME RAB - - BLDG RAB ELEV 86 1 CI07-K2 K-4A accessories AMERACE CORP E7022PE003 Cl07 EPRI 3002002997 Confirmed DELAY RELAY 369 ROOM 87 COLB assembly Page 33 of 73

Controlled Document Arkansas Nuclear One: S0.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Linc Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results EDG&

AUTO START AUXILIARY WESTINGHOUSE RAB - - BLDG RAB ELEV 87 I CI07-K21 K-4A accessories ARD440SR Cl07 EPRINP-7147-SL Confirmed RELAY ELECCORP 369 ROOM 87 COLB assembly EDG&

LOW OIL PRESSURE AUX WESTINGHOUSE RAB - - BLDG RAB ELEV 88 I Ci07-K22 K-4A accessories ARD440SR Cl07 EPRINP-7147-SL Confirmed SHUTDOWN RELAY ELECCORP 369 ROOM 87 COLB assembly EDG&

WESTINGHOUSE RAB - - BLDG RAB ELEV 89 I CI07-K25 OVERSPEED RELAY K-4A accessories ARD440SR Ci07 EPRI NP-7147-SL Confirmed ELECCORP 369 ROOM 87 COLB assembly EDG&

OVERCRANK TIME DELAY RAB - - BLDG RAB ELEV 90 I CI07-K4 K-4A accessories AMERACE CORP E70i2PE003 Cl07 EPRI NP-7i47-SL Confirmed RELAY '369 ROOM 87 COLB assembly EDG&

K4A FUEL PRIME i25 VDC 2 WESTINGHOUSE RAB - - BLDG RAB ELEV 91 I CI07-K42 K-4A accessories ARD440SR Ct07 EPRI NP-7147-SL Confirmed POLE RELAY ELECCORP 369 ROOM 87 COLB assembly EDG&

K4A GOVERNOR BOOST WESTINGHOUSE RAB - - BLDG RAB ELEV 92 I Ci07-K49 K-4A accessories ARD440SR Ci07 EPRI NP-7147-SL Confirmed RELAY ELECCORP 369 ROOM 87 COLB assembly EDG&

SAFETY SET UP TIME RAB - - BLDG RAB ELEV 93 i CI07-K5 K-4A accessories AMERACE CORP E7012PD003 Ci07 EPRI NP-7i47-SL Confirmed DELAY RELAY 369 ROOM 87 COLB assembly EDG&

STARTER SELECTOR WESTINGHOUSE RAB - - BLDG RAB ELEV 94 i CI07-K51 K-4A accessories ARD440SR CI07 EPRI NP-7147-SL Confirmed LATCH RELAY ELECCORP 369 ROOM 87 COLB assembly EDG&

WESTINGHOUSE RAB - - BLDG RAB ELEV 95 I CI07-K53 STARTER NO. I RELAY K-4A accessories ARD440SR CI07 EPRINP-7i47-SL Confirmed ELECCORP 369 ROOM 87 COLB assembly Page 34 of 73

Controlled Document Arkansas Nuclear One: 50.54(f] NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results EDG&

WESTINGHOUSE RAB - - BLDG RAB ELEV 96 1 CI07-K54 STARTER NO. 2 RELAY K-4A accessories ARD440SR Cl07 EPRI NP-7147-SL Outlier ELECCORP 369 ROOM 87 COLB assembly EDG&

STARTER FAILURE TIME RAB - - BLDG RAB ELEV 97 1 Ci07-K55 K-4A accessories AMERACE CORP E7012PB003 C107 EPRINP-7147-SL Confirmed DELAY RELAY 369 ROOM 87 COLB assembly EDG&

FIELD FLASH TIME DELAY RAB - - BLDG RAB ELEV 98 I CI07-K6 K-4A accessories AMERACE CORP E7012PB003 Cl07 EPRI NP-7147-SL Confirmed RELAY 369 ROOM 87 COLB assembly EDG&

WESTINGHOUSE RAB - - BLDG RAB ELEV 99 1 C107-K8 START PILOT RELAY K-4A accessories ARD440SR C107 EPRI NP-7147-SL Confirmed ELECCORP 369 ROOM 87 COLB assembly EDG&

DOI Mn LO pump P-108A RAB - - BLDG RAB ELEV 100 1 PS-5270 K-4A accessories SQUARED CO TYPE ACW-25-S8 K-4A EPRI 3002002997 Confirmed Low Pressure Start Interlock 369 ROOM 87 COLB assembly K-4B-127DG2 EDG&

DIESEL GEN RUNNING RAB - - BLDG RAB ELEV IOI 1 (!27-DG2 K-4B accessories GE 12HFAl51A9H E21 EPRl 3002002997 Outlier RELAY 369 ROOM 86 COLB (K19)) assembly EDG&

CRANK TIME DELAY TYCO RAB - - BLDG RAB ELEV 102 1 C!08-Kl K-4B accessories E7012PC004 C108 EPRI NP-7147-SL Confirmed RELAY ELECTRONICS 369 ROOM 86 COLA assembly EDG&

WESTINGHOUSE RAB - - BLDG RAB ELEV 103 1 C!08-K!O ACCESSORY RELAY K-4B accessories ARD440SR C108 EPRI NP-7147-SL Confirmed ELECCORP 369 ROOM 86 COLA assembly EDG&

TROUBLE SHUTDOWN WESTINGHOUSE RAB - - BLDG RAB ELEV 104 1 C!08-Kll K-4B accessories ARD440SR Cl08 EPRI NP-7147-SL Confirmed RELAY ELECCORP 369 ROOM 86 COLA assembly Page 35 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High .Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results EDG&

CRANK RESET TIME RAB - - BLDG RAB ELEV 105 I Cl08-K2 K-4B accessories AMERACE CORP E7022PE003 Cl08 EPRl 3002002997 Confirmed DELAY RELAY 369 ROOM 86 COLA assembly EDG&

AUTO START AUXILIARY WESTINGHOUSE RAB - - BLDG RAB ELEV 106 1 Cl08-K21 K-4B accessories ARD440SR Cl08 EPRl NP-7147-SL Confirmed RELAY ELECCORP 369 ROOM86 COLA assembly EDG&

LOW OIL PRESSURE AUX WESTINGHOUSE RAB - - BLDG RAB ELEV 107 1 Cl08-K22 K-4B accessories ARD440SR Cl08 EPRl NP-7147-SL Confirmed SHUTDOWN RELAY ELECCORP 369 ROOM 86 COLA assembly EDG&

WESTINGHOUSE RAB - - BLDG RAB ELEV 108 I Cl08-K25 OVERSPEED RELAY K-4B accessories ARD440SR CI08 EPRl NP-7147-SL Confirmed ELECCORP 369 ROOM 86 COLA assembly EDG&

OVERCRANK TIME DELAY RAB - - BLDG RAB ELEV 109 I Cl08-K4 K-4B accessories AMERACE CORP E7012PE003 CI08 EPRI NP-7147-SL Confirmed RELAY 369 ROOM 86 COLA assembly EDG&

K4B FUEL PRIME 125 VDC 2 WESTINGHOUSE RAB - - BLDG RAB ELEV 110 1 Cl08-K42 K-4B accessories ARD440SR Cl08 EPRl NP-7147-SL Con finned POLE RELAY ELECCORP 369 ROOM 86 COLA assembly EDG&

K4B GOVERNOR BOOST WESTINGHOUSE RAB - - BLDG RAB ELEV 111 1 Ci08-K49 K-4B accessories ARD440SR Cl08 EPRl NP-7147-SL Confirmed RELAY ELECCORP 369 ROOM86 COLA assembly EDG&

SAFETY SET UP TIME RAB - - BLDG RAB ELEV 112 1 Cl08-K5 K-4B accessories AMERACE CORP E7012PD003 Cl08 EPRl NP-7147-SL Confirmed DELAY RELAY 369 ROOM 86 COLA assembly EDG&

STARTER SELECTOR WESTINGHOUSE RAB - - BLDG RAB ELEV 113 1 CI08-K51 K-4B accessories ARD440SR Cl08 EPRINP-7147-SL Confirmed LATCH RELAY ELECCORP 369 ROOM 86 COLA assembly Page 36 of 73

Controlled Document Arkansas Nuclear One: 50.54(1) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Uuit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results EDG&

WESTINGHOUSE RAB - - BLDG RAB ELEV 114 1 Cl08-K53 STARTER NO. I RELAY K-4B accessories ARD440SR Cl08 EPRINP-7147-SL Confirmed ELECCORP 369 ROOM 86 COLA assembly EDG&

WESTINGHOUSE RAB - - BLDG RAB ELEV 115 1 C!08-K54 STARTER NO. 2 RELAY K-4B accessories ARD440SR Cl08 EPRI NP-7147-SL Outlier ELECCORP 369 ROOM 86 COLA assembly EDG&

STARTERFAlLURE TIME RAB - - BLDG RAB ELEV 116 I CI08-K55 K-4B accessories AMERACE CORP E7012PB003 Cl08 EPRl NP-7147-SL Confirmed DELAY RELAY 369 ROOM 86 COLA assembly EDG&

FIELD FLASH TIME DELAY RAB - - BLDG RAB ELEV 117 1 Cl08-K6 K-4B accessories AMERACE CORP E7012PB003 C108 EPRI NP-7I47-SL Confirmed RELAY 369 ROOM 86 COLA assembly EDG&

WESTINGHOUSE RAB - - BLDG RAB ELEV 118 I Cl08-K8 START PILOT RELAY K-4B accessories ARD440SR Cl08 EPRI NP-7147-SL Confirmed ELECCORP 369 ROOM 86 COLA assembly EDG&

DG2 Mn LO pump P-108B NAMCO RAB - - BLDG RAB ELEV 119 I PS-5271 K-4B accessories CAT EA 900-03004 K-4B EPRI 3002002997 Confirmed Low Pressure Start Interlock CONTROLS 369 ROOM 86 COLA assembly RAB - - BLDG RAB ELEV DECAY HEAT REMOVAL DHRPumpA 120 I 162-305/i P-34A AMERACE CORP EDSCXX0125DPAXAA Cl8 386 ROOM 129 COL BLINE ANO Documentation Confirmed PUMP P34A (LP!)

AZDEGO Breaker anti-pump relay DHRPumpB RAB - - BLDG RAB ELEV 121 I 152Y-405 P-34B GE 12HMAIIB6 A405 EPRI NP-7147-SL Outlier (magnablast) (LP!) 372 ROOM99 COLD DECAY HEAT REMOVAL DHR Pump B RAB - - BLDG RAB ELEV 122 I 162-405/1 P-34B AMERACE CORP EDSCXX0125DPAXAA Cl6 ANO Documentation Confirmed PUMPP34B (LP!) 386 ROOM 129 COL B PRIMARY MAKEUP PUMP Primary makeup RAB - - BLDG RAB ELEV 123 1 162-306/1 P-36A AMERACE CORP EDSCXX0125DPAXAA Cl8 ANO Documentation Confirmed P36A pump(HPI) 386 ROOM 129 COL B Page 37 of 73

Controlled Document Arkansas Nuclear One: 50.54(1) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results ASCO-Primary makeup RAB - - BLDG RAB ELEV 124 I PS-1250 P36A OIL PRESS SW P-36A AUTOMATIC CATSA31AR P-36A EPRI 3002002997 Confirmed pump (HPI) 335 ROOM 56 COLC SWITCH Primary makeup RAB - - BLDG RAB ELEV 125 I PSX-P36A AUX RELAY P-36A GE 12HFAl51A2H Cl8 EPRI 3002002997 Confirmed pump (HPI) 386 ROOM 129 COL B Breaker anti-pump relay Primary makeup RAB - - BLDG RAB ELEV 126 I 152Y-406 P-36C GE 12HMAllB6 A406 EPRI NP-7147-SL Outlier (magnablast) pump (HPI) 372 ROOM 99 COLD PRIMARY MAKEUP PUMP Primary makeup RAB - - BLDG RAB ELEV 127 I 162-406/1 P-36C AMERACE CORP EDSCXX0125DPAXAA C16 ANO Documentation Confirmed P36C pump(HPI) 386 ROOM 129 COL B ASCO-Primary makeup RAB - - BLDG RAB ELEV 128 1 PS*1270 P36C OIL PRESS SW P-36C AUTOMATIC CATSA31AR P-36C EPRI 3002002997 Con finned pump (HP!) 335 ROOM 54 COLC SWITCH Primary makeup RAB - - BLDG RAB ELEV 129 I PSX-P36C AUX RELAY P-36C GE 12HFAl51A2H C16 EPRI 3002002997 Confirmed pump (HPI) 386 ROOM 129 COL B RAB - - BLDG RAB ELEV 130 1 162-302 SERVICE WATER PUMP P4A P-4A SW Pump A AMERACE DSCXX0125DPAXAA C18 ANO Documentation Confim1ed 386 ROOM 129 COL B Breaker anti-pump relay RAB - - BLDG RAB ELEV 131 1 152Y-402 P-4C SWPumpC GE 12HMAllB6 A402 EPRI NP-7147-SL Outlier (magnablast) 372 ROOM 99 COLD RAB - - BLDG RAB ELEV 132 I 162-402 SERVICE WATER PUMP P4C P-4C SWPumpC AMERACE CORP EDSCXXOl25DPAXAA Cl6 ANO Documentation Confirmed 386 ROOM 129 COL B OVERCURRENT TO A-31 l-150GS RAB - - BLDG RAB ELEV 133 1 GROUND FOR EMERG FW P-7B EFWPump GE 12HFC21B1A A311 ANO Documentation Confirmed (150GS-311) 372 ROOM 100 COLE PMP P-7B EMERGENCY FEEDWATER RAB - - BLDG RAB ELEV 134 1 162-311/1 P-7B EFWPUMP AMERACE CORP EDSCXXOl25DPAXAA Cl8 ANO Documentation Confirmed PUMPP7B 386 ROOM 129 COL B DG I MAIN LO PP P-l08A LO Press Low NAMCO BLDG RAB ELEV 135 I PSL-5270 LOW DISCH PRESS PSL-5270 CAT EA900-03004 K-4A EPRI 3002002997 Confirmed Diesel SID CONTROLS 369 ROOM 87 COLB SID Page 38 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results DG2 P-108B LOW DISCH LO Press Low BLDG RAB ELEV 136 I PSL-5271 PSL-5271 SQUARED CO 9012-GAW24-Si 12 K-4B EPRI 3002002997 Confirmed PRESS Diesel SID 369 ROOM 86 COLA RAB - - BLDG RAB ELEV 137 I CR-P013 BOP RELAY PSV-1000 PZRERV GE 12HGAI IJ52 C30 EPRI NP-7147-SL Confirmed 386 ROOM 129 COL B MCC B-52 BLDG RAB SG-1 (SLUICE GATE) PIN 25-111-110-512 (CAT No.

138 I 42R-5253 SG-1 Sluice Gate ALLIS-CHALMER B5253 ELEV 368 ROOM 104 COL EPRI 3002002997 Confirmed CONTACTOR SIZE I 25-111-000-501)

G MCCB-62 BLDGRAB SG-2 (SLUICE GATE) PIN 25-111-110-512 (CAT No.

139 I 42R-6253 SG-2 Sluice Gate ALLIS-CHALMER B6253 ELEV 386 ROOM 149 COL EPRI 3002002997 Confirmed CONTACTORSIZE I 25-111-000-501) c DGI Governor RAB - - BLDG RAB ELEV 140 I SS-5210 DG I Gov. Speed Sensor SS-5210 DYNALCO CORP SST-2400A-8 TB909 ANO Documentation Confirmed speed sensor 369 ROOM 87 COLB DG I overspeed RAB - - BLDG RAB ELEV 141 I SS-5211 DG I Overspeed Trip Switch SS-521 I SQUARED CO CLASS 9007 K-4A EPRI 3002002997 Confirmed trip switch 369 ROOM 87 COLB DG2 GOVERNOR SPEED DG2 Governor RAB - - BLDG RAB ELEV 142 I SS-5220 SS-5220 DYNALCO CORP SST-2400A-8 TB910 ANO Documentation Confirmed SENSOR speed sensor 369 ROOM 86 COLA DG2 OVERSPEED TRIP DG2 ovcrspccd RAB - - BLDG RAB ELEV 143 I SS-5221 SS-5221 SQUARED CO CLASS 9007 K-4B EPRI 3002002997 Confirmed SWITCH trip switch 369 ROOM 86 COLA RAB ELEV372 ROOM 109 Yli, Yl3, 120VAC Potter & Brumfield Yll,Yi3, COLD 144 I RLI X2 Oscillator Board 4PDT 3A KHAU-17Dl8-12 EPRI 3002002997 Confirmed Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 Yi!, Yl3, 120VAC Poller & Brumfield YI!, Yl3, COLD 145 I RLI XS Synch Board 4PDT 3A KHAU-17Al8-120 SQURTS Testing Confirmed Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 Yll,Yi3, 120VAC Potter & Brumfield Yll,Yl3, COLD 146 I RL2 XS Synch Board 4PDT 3A KHAU-17Dl8-12 EPRI 3002002997 Confirmed Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD Page 39 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results RAB ELEV 372 ROOM I 09 Yi!, Yl3, 120VAC Potter & Brumfield Yll,Yl3, COLD 147 I RL3 XS Synch Board 4PDT 3A KHAU-l7D18-l2 EPRI 3002002997 Confirmed Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 YI!, Y13, l20VAC Potter & Brumfield Yll, Y13, COLD 148 I RLI Xl8 Shorting Board4PDT 3A KHAU-17Dl8-llO EPRI TR-l05988-V2 Confirmed Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM I 09 X19 Loss of DC Voltage Sense YI!, Yl3, 120VAC Yi!, Y13, COLD 149 I RLI Omron MY4-DC24S SQURTS Testing C-0nfirmed Board 4PDT 3A Y22, Y24 Instrument Inverter Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X201 Static Switch Control Yi!, Y13, 120VAC Potter & Brumfield Yi!, Y13, COLD 150 I RLI KHAU-17D18-12 EPRI 3002002997 Confirmed Board3A Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X20l Static Switch Control YI!, Yl3, l20VAC Potter & Brumfield Yll,Yl3, COLD 151 I RL2 KHAU-i7Al8-i20 SQURTS Testing Confirmed Board 4PDT 3A Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X20l Static Switch Control Yll,Yl3, 120VAC Computer Y!l,Yl3, COLD 152 I RR! 300-470 SQURTS Testing Confirmed Board Reed Relay O.SA Y22, Y24 Instrument Inverter Components Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X201 Static Switch Control Yi!, Y13, 120VAC YI!, Y13, COLD 153 I RR! Gordos Corp. FSl-1423 EPRI TR-I 05988-V2 Confirmed Board Reed Relay O.SA Y22, Y24 Instrument Inverter Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV372 ROOM 109 X202 Static Switch Auto Re- Yi!, Yl3, l20VAC Potter & Brumfield Yi!, Y13, COLD 154 I Kl KHAU-l 7D18-12 EPRI 3002002997 Confirmed transfer Board 4PDT 3A Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X202 Static Switch Auto Re- YI!, Y13, l20VAC Potter & Brumfield YI!, Y13, COLD 155 I K2 KHAU-l7Al8-l20 SQURTS Testing Confirmed transfer Board 4PDT 3A Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD Page 40 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component _;

Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results RAB ELEV372 ROOM 109 X202 Static Switch Auto Re- YI!, Yl3, 120VAC Potter & Brumfield YI!, Y13, COLD 156 I K3 KHAU-17A18-120 SQURTS Testing Confirmed transfer Board 4PDT 3A Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X202 Static Switch Auto Re- YI!, Yl3, 120VAC Potter & Brumfield Yll, Yl3, COLD 157 1 K4 KHAU-17Al8-120 SQURTS Testing Confirmed transfer Board 4PDT 3A Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X202 Static Switch Auto Re- Yll, Y13, 120VAC Potter & Brumfield Yll, Yl3, COLD 158 1 K5 KHAU-17A18-120 SQURTS Testing Confirmed transfer Board 4PDT 3A Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X202 Static Switch Auto Re- Yll, Yl3, 120VAC Potter & Brumfield Yll, Y13, COLD 159 I K6 KHAU-17A18-120 SQURTS Testing Confirmed transfer Board 4PDT 3A Y22, Y24 Instrument Inverter (Tyco) Y22, Y24 BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 120VAC Potter & Brumfield COLD 160 I RLI X2 Oscillator Board 4PDT 3A Yl5, Y25 KHAU-17D18-12 Y15, Y25 EPRI 3002002997 Confirmed Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 120VAC Potter & Brumfield COLD 161 1 RLl X5 Synch Board 4PDT 3A Y15, Y25 KHAU-17Al8-120 Yl5, Y25 SQURTS Testing Confirmed Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 120VAC Polter & Brumfield COLD 162 I RL2 X5 Synch Board 4PDT 3A Yl5, Y25 KHAU-17Dl8-12 Yl5, Y25 EPRI 3002002997 Confirmed Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 120VAC Potter & Brumfield COLD 163 I RL3 X5 Synch Board 4PDT 3A Yl5, Y25 KHAU-17D18-12 Y15, Y25 EPRI 3002002997 Confirmed Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 120VAC Potter & Brumfield COLD 164 I RLI Xl8 Shorting Board 4PDT 3A Yl5, Y25 KHAU-17Dl8-110 YIS, Y25 EPRI TR-I05988-V2 Confirmed Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD Page 41 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay JD Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results RAB ELEV 372 ROOM 109 Xl9 Loss of DC Voltage Sense 120VAC COLD 165 1 RLI YlS, Y25 Omron MY4-DC24S YlS, Y25 SQURTS Testing Confirmed Board 4PDT 3A Instrument Inverter BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV372 ROOM 109 X201 Static Switch Control 120VAC Potter & Brumfield COLD 166 1 RLl YlS, Y25 KHAU-17Dl8-12 YlS, Y25 EPRI 3002002997 Confirmed Board 3A Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X201 Static Switch Control 120VAC Potter & Brumfield COLD 167 1 RL2 YlS, Y25 KHAU-17Al8-120 YlS, Y25 SQURTS Testing Confirmed Board 4PDT 3A Instrumenl Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X201 Static Switch Control 120VAC Computer COLD 168 1 RR! YIS, Y25 300-470 YlS, Y25 SQURTS Testing Confirmed Board Reed Relay 0.5A Instrument Inverter Components BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X201 Static Switch Control 120VAC COLD 169 1 RRl Yl5, Y25 Gordos Corp. FSl-1423 YlS, Y25 EPRI TR-l05988-V2 Confirmed Board Reed Relay 0.5A Instrument Inverter BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X202 Static Switch Auto Re- 120VAC Potter & Brumfield COLD 170 1 Kl Yl5, Y25 KHAU-17Dl8-12 Yl5, Y25 EPRI 3002002997 Confirmed transfer Board 4PDT 3A Instmment Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X202 Static Switch Auto Re- 120VAC Potter & Brumfield COLD 171 1 K2 Yl5, Y25 KHAU-17A18-120 Yl5, Y25 SQURTS Testing Confirmed transfer Board 4PDT 3A Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X202 Static Switch Auto Re- 120VAC Potter & Brumfield COLD 172 1 K3 Yl5, Y25 KHAU-17Al8-120 Yl5, Y25 SQURTS Testing Confirmed transfer Board 4PDT 3A Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X202 Static Switch Auto Re- 120VAC Potter & Brumfield COLD 173 1 K4 Yl5, Y25 KHAU-17Al8-120 Yl5, Y25 SQURTS Testing Confirmed transfer Board 4PDT 3A Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD Page 42 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results RAB ELEV 372 ROOM 109 X202 Static Switch Auto Re- 120VAC Potter & Brumfield COLD 174 I KS Yl5, Y25 KHAU-17Al8-120 Y15, Y25 SQURTS Testing Confirmed transfer Board 4PDT 3A Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD RAB ELEV 372 ROOM 109 X202 Static Switch Auto Re- 120VAC Potter & Brumfield COLD 175 1 K6 Yi5, Y25 KHAU-17A18-120 Y15, Y25 SQURTS Testing Confirmed transfer Board 4PDT 3A Instrument Inverter (Tyco) BLDG RAB ELEV 372 ROOM99 COLD D-03A,D- D-03A,D- RAB ELEV372 ROOM 109 X304 AC Relay Board 4PDT 03B, Potter & Brumfield 03B, COLD 176 1 K Battery Charger KHAU-17Al8-120 SQURTS Testing Confirmed 3A D-04A,D- (Tyco) D-04A, D- RAB ELEV372 ROOM98 04B 04B COLC CORE MCCB-55 BLDGRAB FLOODING 177 I 42F-B5554 Size I motor starter CV-2417 Siemens 3TF44 (CRLOF4422K61) B5554 ELEV372 ROOM99 COL EPRI 3002002997 Confirmed TANKT-2A D

VENT CORE MCCB-55 BLDGRAB FLOODING 178 1 42F-B5543 Size l motor starter CV-2420 Siemens 3TF44 (CRLOF4422K6 I) B5543 ELEV 372 ROOM99 COL EPRI 3002002997 Con finned TANKT-2B D

VENT EFWPP TURBINEK-3 MCCD-15 BLDG RAB 179 1 42F-Dl512 CV-2663 CONTACTOR CV-2663 STEAM ITE Class A20 Dl512 ELEV 368 ROOM 104 COL EPRI 3002002997 Confirmed ADMISSION H VALVE EFWPP TURBINEK-3 AGASTATRELAY TIME DELAY RELAY FOR RAB - - BLDG RAB ELEV 180 I 62-Dl512 CV-2663 STEAM (AMERACE)E7012- E7012-PD004 D1512 EPRI NP-7147-SL Confirmed BKRD-1512 372 ROOM 109 COLD ADMISSION PD004 VALVE UNDERVOLTAGE RELAY 4.16KVESF RAB - - BLDG RAB ELEV 181 2 127-2A3/Xl 2A-3 P&B MDR-138-8 2A308 EPRI 3002002997 Confirmed FORBUS2A-3 SWITCHGEAR 372 ROOM 2100 COLD UNDERVOLTAGE RELAY 4.16KVESF RAB - - BLDG RAB ELEV 182 2 127-2A3/X2 2A-3 P&B MDR-138-8 2A308 EPRI 3002002997 Confirmed FORBUS2A-3 SWITCHGEAR 372 ROOM 2100 COLD UNDERVOLTAGE RELAY 4.16KVESF RAB - - BLDG RAB ELEV 183 2 127-2A3/X3 2A-3 P&B MDR-138-8 2A308 EPRI 3002002997 Confirmed FORBUS2A-3 SWITCHGEAR 372 ROOM 2100 COLD UNDERVOLTAGE RELAY 4.16KVESF RAB - - BLDG RAB ELEV 184 2 127-2A3/XA 2A-3 P&B MDR-138-8 2A309 EPRI 3002002997 Confirmed FORBUS2A-3 SWITCHGEAR 372 ROOM 2100 COLD Page 43 of73

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Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results UNDERVOLTAGE RELAY 4.i6KVESF RAB - - BLDG RAB ELEV 185 2 i27-2A3/XB 2A-3 P&B MDR-138-8 2A309 EPRI 3002002997 Confirmed FOR BUS2A-3 SWITCHGEAR 372 ROOM2100 COLD DIESEL AUX RELAY DIESEL GEN GENERATOR RAB - - BLDG RAB ELEV i86 2 i52-308/X 2K-4A P&B MDR-5139 2A308 EPRI 3002002997 Confirmed 2K-4A AND 372 ROOM 2i0i COLE AUXILIARIES DIESEL DIESEL GENERATOR NO i 2K-4A-i59N GENERATOR RAB - - BLDG RAB ELEV i87 2 NEUTRALOVERCURRENT 2K-4A GE i21AV51D2A 2A308 ANO Documentation Confirmed (i59N-2DGi) AND 369 ROOM 2093 COL A RELAY AUXILIARIES DIESEL GENERATOR RAB - - BLDG RAB ELEV 188 2 i59NX-i AUX RELAY EDG i 2K-4A P&B MDR-i37-8 2C33-i EPRI 3002002997 Confirmed AND 386 ROOM 2i i8 COL B AUXILIARIES SERVICE RAB EL 386, ROOM 2i18, i89 2 i62/2A302-2 SWPump2P4A 2P4A AT&C 365A300N30PX 2Ci7 SQURTS Testing Confirmed WATER PUMP COLB LOW PRESSURE SAFETY RAB EL 386, ROOM 2 i 18, i90 2 i62/2A305 LPSI Pump 2P60A 2P-60A AT&C 365A300N30PX 2Cl7 SQURTS Testing Confirmed INJECTION COLB PUMP HI PRESS SAFTY RAB EL 386, ROOM 2i i8, i91 2 i62/2A306 HPSI Pump 2P89A 2P-89A INJECTION AT&C 365A300N30PX 2Ci7 SQURTS Testing Confirmed COLB PUMP LOCKOUT RELAY FOR BUS 4.16KV ESF RAB - - BLDG RAB ELEV 192 2 i86-2A3 2A-3 GE i2HEA62B236X2 2A309 EPRI 3002002997 Confirmed 2A3 SWITCHGEAR 372 ROOM2i00 COLD DIESEL LOCKOUT RELAY FOR GENERATOR RAB - - BLDG RAB ELEV i93 2 i86-2DGi 2K-4A GE i2HEA62A223X2 2A308 EPRI 3002002997 Confirmed 2DGI AND 372 ROOM 210i COLE AUXILIARIES DIESEL AUX DIFFERENTIAL GENERATOR RAB - - BLDG RAB ELEV i94 2 i87X-2DGI 2K-4A Gould CAT Jl3P20 2El2 SQURTS Testing Outlier RELAY FOR 2DGI AND 369 ROOM 2093 COL A AUXILIARIES DIESEL AUX DIFFERENTIAL GENERATOR RAB - - BLDG RAB ELEV i95 2 187Xl-2DGI 2K-4A P&B MDR-137-8 2C33-i EPRI 3002002997 Confirmed RELAYFOR2DGi AND 386 ROOM 21 i8 COL B AUXILIARIES Page 44 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component ' Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results DIESEL TIME DELAY RELAY GENERATOR RAB - - BLDG RAB ELEV 196 2 2-2All-I 2K-4A AMERACE E7022PC004 2Ell EPRI 3002002997 Confirmed LOCKOUT AND 369 ROOM 2093 COL AUXILIARIES DIESEL TIME DELAY RELAY GENERATOR RAB - - BLDG RAB ELEV 197 2 2-2All-2 2K-4A AMERACE E7012PC004 2Ell EPRI NP-7147-SL Confirmed LOCKOUT AND 369 ROOM 2093 COL AUXILIARIES DIESEL TIME DELAY ENERGIZE GENERATOR RAB - - BLDG RAB ELEV 198 2 2-2All-3 2K-4A AMERACE E7012PC004 2Ell EPRI NP-7147-SL Confirmed RELAY LOCKOUT AND 369 ROOM 2093 COL A AUXILIARIES DIESEL TIME DELAY ENERGIZE GENERATOR RAB - - BLDG RAB ELEV 199 2 2-2All-4 2K-4A AMERACE E7012PC004 2Ell EPRI NP-7147-SL Confirmed RELAY LOCKOUT AND 369 ROOM 2093 COL A AUXILIARIES DIESEL GENERATOR RAB - - BLDG RAB ELEV 200 2 27-IX/2B5 AUX RELAY FOR BUS 2B5 2K-4A P&B MDR-137-8 2C33-I EPRI 3002002997 Confirmed AND 386 ROOM2118 COLB AUXILIARIES 2A 2A3 BUS UNDERVOLTAGE 4.16KVESF RAB - - BLDG RAB ELEV 201 2 2A-3 GE I 78A8893 G-1 2A3 ANO Documentation Confirmed 1272A3/A RELAY (B & C PHASES) SWITCHGEAR 372 ROOM 2101 COLE 2A 2A3BUSUNDERVOLTAGE 4.16KVESF RAB - - BLDG RAB ELEV 202 2 2A-3 GE 178A8893 G-1 2A3 ANO Documentation Confirmed 1272A3/B RELAY (A & B PHASES) SWITCHGEAR 372 ROOM 2101 COLE INVERSE TIME AND RAB - - BLDG RAB ELEV 2A-301- 4.16KVESF 203 2 INSTANT OVERCURRENT 2A-3 GE 12IAC51Bl04A 2A301 372 ROOM2101 COLE ANO Documentation Confirmed 150/151A SWITCHGEAR RELAY 2A-30 I LINE 5.5 AZ DEG INVERSE TIME AND RAB - - BLDG RAB ELEV 2A-301- 4.16KV ESF 204 2 INSTANT OVERCURRENT 2A-3 GE 12IAC51Bl04A 2A301 372 ROOM 2101 COLE ANO Documentation Confirmed 150/l51B SWITCHGEAR RELAY2A-301 LINE 5.5 AZ DEG INVERSE TIME AND RAB - - BLDG RAB ELEV 2A-301- 4.16KVESF 205 2 INSTANT OVERCURRENT 2A-3 GE 12IAC51BI04A 2A301 372 ROOM 2101 COLE ANO Documentation Confirmed 150/151C SWITCHGEAR RELAY2A-301 LINE 5.5 AZ DEG RAB - - BLDG RAB ELEV INSTANTANEOUS GROUND 4.16KVESF 206 2 2A-301-150GS 2A-3 GE 12HFC21BIA 2A301 372 ROOM 2101 COLE ANO Documentation Confirmed SENSOR RELAY FOR 2A-30 I SWITCHGEAR LINE 5.5 AZ DEG Page 45 of 73 L

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Linc Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results MOTOR FEEDER LONG 2A-302- SERVICE RAB - - BLDG RAB ELEV 207 2 TIME QC RELAY FOR 2A- 2P4A GE 12IAC66K19A 2A302 ANO Documentation Confirmed 150/151A WATER PUMP 372 ROOM210i COLD 302 MOTOR FEEDER LONG 2A-302- SERVICE RAB - - BLDG RAB ELEV 208 2 TIME OC RELAY FOR 2A- 2P4A GE 12IAC66K19A 2A302 ANO Documentation Confirmed 150/151B WATER PUMP 372 ROOM 2101 COLD 302 MOTOR FEEDER LONG 2A-302- SERVICE RAB - - BLDG RAB ELEV 209 2 TIME OC RELAY FOR 2A- 2P4A GE 12IAC66K19A 2A302 ANO Documentation Confirmed 150/151C WATER PUMP 372 ROOM2i01 COLD 302 INSTANTANEOUS GROUND SERVICE RAB - - BLDG RAB ELEV 210 2 2A-302-150GS 2P4A GE 12HFC21BIA 2A302 ANO Documentation Confirmed SENSOR RELAY FOR 2A-302 WATER PUMP 372 ROOM2101 COLD DIRECTIONAL GROUND ZA-308- 4.16KVESF RAB - - RAB 372 COLD 211 2 OVERCT RELAY FOR 2A- 2A-3 GE 12ICC51A7A 2A3 No Capacity Found Outlier 167G2A309 SWITCHGEAR LINE 5.5 EL RM2i00 309 DIESEL ZA-308- DIESEL GENERATOR #I GENERATOR RAB - - BLDG RAB ELEV 212 2 2K-4A Gould TYPE ITE-25V 2A308 EPRI TR-!05988 V2 Confirmed 252DGI SYNC-CHECK RELAY AND 372 ROOM2101 GOLF AUXILIARIES OVERCURRENT RELAY 4.16KV ESF RAB - - BLDG RAB ELEV 213 2 2A-309-151A 2A-3 GE 12IAC51AIOIA 2A3 ANO Documentation Con finned FOR2A-309 SWITCHGEAR 372 ROOM2100 COLD OVERCURRENT RELAY 4.16KVESF RAB - - BLDG RAB ELEV 214 2 2A-309-151B 2A-3 GE 12IAC51AIOIA 2A3 ANO Documentation Con finned FOR2A-309 SWITCHGEAR 372 ROOM2100 COLD OVERCURRENT RELAY 4.16KVESF RAB - - BLDG RAB ELEV 215 2 2A-309-151C 2A-3 GE 12IAC51AIOIA 2A3 ANO Documentation Confirmed FORZA-309 SWITCHGEAR 372 ROOM2100 COLD NEUTRAL INVERSE TIME 4.16KVESF RAB - - BLDG RAB ELEV 216 2 2A-309-151N GRND FAULT RELAY FOR 2A-3 GE 121AC77A801A 2A3 ANO Documentation Confirmed SWITCHGEAR 372 ROOM 2100 COLD 2A-309 DIRECTIONAL 4.16KVESF RAB - - BLDG RAB ELEV 217 2 2A-309-167SA OVERCURRENTRELAY 2A-3 GE 12IBC51E2A 2A3 ANO Documentation Outlier SWITCHGEAR 372 ROOM 2i00 COLD FOR 2A-309 PHASE A DIRECTIONAL 4.16KVESF RAB - - BLDG RAB ELEV 218 2 2A-309-167SB OVERCURRENT RELAY 2A-3 GE 12IBC51E2A 2A3 ANO Documentation Outlier SWITCHGEAR 372 ROOM 2 IOO COLD FOR ZA-309 PHASE B Page 46 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results DIRECTIONAL 4.16KVESF RAB - - BLDG RAB ELEV 219 2 2A-309-l67SC OVERCURRENT RELAY 2A-3 GE l2IBC51E2A 2A3 ANO Documentation Outlier SWITCHGEAR 372 ROOM 2100 COLD FOR 2A-309 PHASE C 480V ESF RAB - - BLDG RAB ELEV 2B-5-27l/2BS UNDERVOLTAGERELAY MOTOR 220 2 2B-5 ABB TYPE ITE-27N 2B5 372 ROOM 2101 COLE EPRI 3002002997 Con finned (2B-5, 27-1) FOR2B-5 CONTROL LINE 5.5 AZ DEG CENTER 480VESF 2B-5-272/2B5 RAB - - BLDG RAB ELEV UNDERVOLTAGE RELAY MOTOR 221 2 2B-5 ABB TYPE ITE-27N 2BS 372 ROOM 2101 COLE EPRI 3002002997 Con finned (2B-5, 27-l) FOR2B-5 CONTROL LINE 5.5 AZ DEG CENTER 480VESF TIME OVERCURRENT MOTOR RAB - - BLDG RAB ELEV 222 2 2B-5-Sll 2B-5 GE 121AC51A101A 2BS ANO Documentation Con finned RELAY FOR 2B-5 (PHASE C) CONTROL 372 ROOM 2101 COLE CENTER 480VESF TIME OVERCURRENT MOTOR RAB - - BLDG RAB ELEV 223 2 2B-5-5i2 2B-5 GE l21ACSIA101A 2B5 ANO Documentation Con finned RELAY FOR 2B-5 (PHASE A) CONTROL 372 ROOM 2101 COLE CENTER 480VESF GROUND FAULT RELAY MOTOR RAB - - BLDG RAB ELEV 224 2 2B-5-51N 2B-5 GE 121AC5lA10lA 2B5 ANO Documentation Confirmed FOR2B-5 CONTROL 372 ROOM 2101 COLE CENTER DIESEL Erner Diesel 2K4A (2DGI) GENERATOR RAB EL 369, ROOM 2093, Oullici'I) 225 2 2Ci07-4A 2K-4A Gould CAT Jl3P30 2Cl07 SQURTS Testing Start AND COLA AUXILIARIES DIESEL Erner Diesel 2K4A (2DG 1) GENERATOR RAB EL 369, ROOM 2093, Outlier0 l 226 2 2C107-4B 2K-4A Gould CAT J13P30 2CI07 SQURTS Testing Start AND COLA AUXILIARIES DIESEL RAB - - BLDG RAB ELEV EMER DIESEL 2K4A (2DG l) GENERATOR 227 2 2Cl07A-5 2K-4A AMERACE E7022PET004 2Cl07 369 ROOM 2093 COL LINE EPRI 3002002997 Confinned GENERATOR DIFF TRIP AND AZDEG AUXILIARIES DIESEL EMER DIESEL 2K4A (2DGI) GENERATOR RAB - - BLDG RAB ELEV Outlier( I) 228 2 2C107-5A 2K-4A Gould CAT Ji3P30 2Cl07 SQURTS Testing AUX STOPPING RELAY AND 369 ROOM 2093 COL A AUXILIARIES Page 47 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Linc Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results DIESEL Erner Diesel 2K4A (2DG I) GENERATOR RAB EL 369, ROOM 2093, 229 2 2CI07-EOR 2K-4A Gould CAT Jl3P30 2CI07 SQURTS Testing Outlier.(!)

Engine Overspeed Trip AND COL2093 AUXILIARIES DIESEL Erner Diesel 2K4A (2DG I) GENERATOR RAB EL 369, ROOM 2093, 230 2 2Cl07-ERA 2K-4A Gould CAT Jl3P30 2CI07 SQURTS Testing Outlicr(IJ Normal Speed (810 RPM) AND COLA AUXILIARIES DIESEL Erner Diesel 2K4A (2DGJ) GENERATOR RAB EL 369, ROOM 2093, 231 2 2Cl07-ES1 2K-4A Gould CAT Jl3P30 2Cl07 SQURTS Testing Outiierl 4 l 60V Undervoltage AND COLA AUXILIARIES DIESEL Erner Diesel 2K4a (2DG1) GENERATOR RAB EL 369, ROOM 2093, 232 2 2CJ07-ES2 2K-4A Gould CAT J13P30 2Cl07 SQURTS Testing Outiicrl 4 I 60V Undervollage AND COLA AUXILIARIES DIESEL Erner Diesel 2K4A (2DG 1) GENERATOR RAB EL 369, ROOM 2093, 233 2 2Cl07-LSA 2K-4A Gould CAT Jl3P30 2Ci07 SQURTS Testing Outlicr< 1)

Low Speed (250 RPM) AND COLA AUXILIARIES DIESEL Erner Diesel 2K4A (2DG I) GENERATOR RAB EL 369, ROOM 2093, 234 2 2CJ07-LSB 2K-4A Gould CAT Jl3P30 2Cl07 SQURTS Testing Ouliicrl Jacket Coolant AND COL A (STATUS ~DESIGN)

AUXILIARIES DIESEL Erner Diesel 2K4A (2DG I) GENERATOR RAB EL 369, ROOM 2093, 235 2 2Ci07-0Pl 2K-4A Gould CAT Jl3P30 2Ci07 SQURTS Testing Ouliicrl Lube Oil Pressure Sensing AND COLA AUXILIARIES DIESEL Erner Diesel 2K4A (2DG 1) GENERATOR RA"B EL 369, ROOM 2093, 236 2 2CJ07-0P2 2K-4A Gould CAT JJ3P30 2Cl07 SQURTS Testing Outiict 1l Lube Oil Pressure Sensing AND COLA AUXILIARIES DIESEL Erner Diesel 2K4A (2DGJ) GENERATOR RAB EL 369, ROOM 2093, 237 2 2Cl07-0P3 2K-4A Gould CAT Jl3P30 2Cl07 SQURTS Testing Outlicr' 1l Lube Oil Pressure Sensing AND COLA AUXILIARIES EMER DIESEL 2K4A (2DG I) DIESEL RAB - - BLDG RAB ELEV 238 2 2Cl07-Ri 2K-4A GENERATOR P&B MDR-137-8 2CJ07 EPRI 3002002997 Confim1cd AUX STOPPING RELAY 369 ROOM 2093 COL A AND I Page 48 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Linc Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results AUXILIARIES DIESEL EMER DIESEL 2K4A (2DGI) GENERATOR RAB - - BLDG RAB ELEV 239 2 2CI07-SDR 2K-4A Gould CAT Jl3P30 2CI07 SQURTS Testing Outlier<'>

SHUTDOWN RELAY AND 369 ROOM 2093 COL A AUXILIARIES DIESEL Erner Diesel 2K4A (2DG I) GENERATOR RAB EL 369, ROOM 2093, 240 2 2Cl07-SFR 2K-4A Gould CAT Jl3P30 2Cl07 SQURTS Testing OutlierC 1J Start Failure AND COLA AUXILIARIES DIESEL EMER DIESEL 2K4A (2DG l)

GENERATOR RAB - - BLDG RAB ELEV 241 2 2C107A-T2A CRANKING TIME 2K-4A AMERACE E7012PD004 2Cl07 EPRI NP-7147-SL Confirmed AND 369 ROOM 2093 LIMIT AUXILIARIES DIESEL EMER DIESEL 2K4A (2DG I)

GENERATOR RAB - - BLDG RAB ELEV 242 2 2Cl07A-T2B CRANKING TIME 2K-4A AMERACE E7012PD004 2CI07 EPRINP-7147-SL Confirmed AND 369 ROOM 2093 LIMIT AUXILIARIES DIESEL EMER DIESEL 2K4A (2DG I) GENERATOR RAB - - BLDG RAB ELEV 243 2 2Cl07A-T3A 2K-4A AMERACE E7012PDLL004 2CI07 EPRINP-7147-SL Confirmed TRIP ENABLE AND 369 ROOM 2093 AUXILIARIES DIESEL EMER DIESEL 2K4A (2DGI) GENERATOR RAB - - BLDG RAB ELEV 244 2 2C107A-T3B 2K-4A AMERACE E7012PDLL004 2CI07 EPRI NP-7147-SL Confirmed TPIP ENABLE TIMER AND 369 ROOM 2093 AUXILIARIES DIESEL EMERG DIESEL 2K4A GENERATOR RAB - - BLDG RAB ELEV 245 2 2CI07-T3X (2DGI) EDGE NOT 2K-4A P&B MDR-5139 2CI07 EPRI 3002002997 Confirmed AND 369 ROOM 2093 COL A AVAILABLE ALARM AUXILIARIES SW PUMP AUXILIARY CONTROL CROSSOVER RAB - - BLDG RAB ELEV 246 2 2CR-!418-1 2CV1418-l GE 12HGA1 I IJ9 2B54D3 EPRI 3002002997 Confirmed RELAY FOR2CV-1418-l VALVEP4B- 372 ROOM 2101 COLE P4A RAB - - BLDG RAB ELEV CHARGING PUMP 2P36A CHARGING 247 2 2CR-52A5-1 2P36A Gould CAT JIOB4012 2B52A5 335 ROOM 2040 COL C EPRI TR-105988 V2 Confirmed CONTRRELAY PUMP LINE4 Page 49 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Eleva ti on Basis for Capacity Evaluation Results DIESEL UNDERVOLTAGE RELAY 2K-4A- GENERATOR RAB - - BLDG RAB ELEV 248 2 FOR DIESEL GENERATOR 2K-4A GE 12NGV21BIA 2Eii ANO Documentation Confirmed i272DGi AND 369 ROOM 2093 COL A NO I AUXILIARIES DIESEL DIESEL GENERATOR ANTI 2K-4A- GENERATOR RAB - - BLDG RAB ELEV 249 2 MOTORING RELAY FOR 2K-4A GE i2GGP53B!A 2A308 EPRI NP-7147-SL Outlier i322DG1 AND 372 ROOM 2i0i COLE 2A308 AUXILIARIES DIESEL 2K-4A- DG OVERCURRENT RELAY GENERATOR RAB - - BLDG RAB ELEV 250 2 2K-4A GE i21JCV51Ai3A 2A308 ANO Documentation Outlier i5!V2DG!A FOR2A-308 AND 372 ROOM 2100 COLD AUXILIARIES DIESEL 2K-4A- DG OVERCURRENT RELAY GENERATOR RAB - - BLDG RAB ELEV 251 2 2K-4A GE l21JCV51A13A 2A308 ANO Documentation Outlier i51V2DGIB FOR 2A-308 AND 372 ROOM2l00 COLD AUXILIARIES DIESEL 2K-4A- DG OVERCURRENT RELAY GENERATOR RAB - - BLDG RAB ELEV 252 2 2K-4A GE 121JCV5!Al3A 2A308 ANO Documentation Outlier 15iV2DG!C FOR2A-308 AND 372 ROOM2i00 COLD AUXILIARIES DIESEL 2K-4A- DIESEL GENERATOR NO i GENERATOR RAB - - BLDG RAB ELEV 253 2 2K-4A GE i2NGV21B5A 2El2 ANO Documentation Confirmed i592DGI RUNNING RELAY AND 369 ROOM 2093 COL A AUXILIARIES DIESEL 2K-4A- DIESEL GEN i GENERATOR RAB - - BLDG RAB ELEV 254 2 2K-4A GE 12SBD! IB2A 2Eil No Capacity Found Outlier 1872DG!-A DIFFERENTIAL RELAY AND 369 ROOM 2093 COL A AUXILIARIES DIESEL 2K-4A- DIESEL GEN I GENERATOR RAB - - BLDG RAB ELEV 255 2 2K-4A GE 12SBD!IB2A 2Eil No Capacity Found Outlier 1872DGl-B DIFFERENTIAL RELAY AND 369 ROOM 2093 COL A AUXILIARIES DIESEL 2K-4A- DIESEL GEN l GENERATOR RAB - - BLDG RAB ELEV 256 2 2K-4A GE i2SBD! !B2A 2Eii No Capacity Found Outlier

!872DG!-C DIFFERENTIAL RELAY AND 369 ROOM 2093 COL A AUXILIARIES SW PUMP MCC2B-54 BLDG RAB 2CVi418-i CONTACTOR 257 2 42F-2B54D3 2CVi418-1 CROSSOVER  !TE ClassA20 2B54D3 ELEV372 ROOM2!0i COL EPRI 3002002997 Confirmed SIZE i VALVEP4B- E Page 50 of73

Controlled Document Arkansas Nuclear One: S0.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results P4A Containment Isolation System MCC2B-71 BLDG RB 258 2 42F-2B71E3 2CV5082 CONTACTOR 2CV5082 (SIS Drain from SI !TE Class A20 2871 ELEV 376 ROOM EPRI 3002002997 Confirmed TK to RWT Valve COL -

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MCC2B-52 BLDGRAB 2CV1445-I CONTACTOR Service Water to 259 2 42R-2B52F2 2CV1445-1  !TE Class A20 2B52F2 ELEV 335 ROOM 2040 COL EPRI 3002002997 Confirmed SIZE I LPSI PP Seal Cir c

SERVICE MCC2B-52 BLDGRAB 2CVl481-l CONTACTOR WATER RETURN 260 2 42R-2B52H2 2CVl481-I  !TE Class A20 2B52H2 ELEV 335 ROOM 2040 COL EPRI 3002002997 Confirmed SIZE I TO DARDANELLE c

SIS HPSl MCC2B-52 BLDG RAB 2CV5103-I CONTACTOR HEADER NO. I 261 2 42R-2B52L6 2CV5103-I  !TE Class A20 2B52L6 ELEV 335 ROOM 2040 COL EPR! 3002002997 Confirmed SIZE I ORIFICE BYPASS c

SERVICE MCC2B-54 BLDG RAB 2CVl470-I CONTACTOR Confirmed 262 2 42R-2B54E4 2CVl470-I WATER TO ITE Class A20 2B54E4 ELEV 372 ROOM 2101 COL EPR! 3002002997 SIZE I INTAKESTR. E 2P-36A/B/C MCC2B-62 BLDGRAB 2CV4840-2 CONTACTOR EPRI 3002002997 Confirmed 263 2 42R-2B62E4 2CV4840-2 FLOW CONT  !TE CiassA20 2B62E4 ELEV 354 ROOM 2073 COL SIZE I VLV A STEAM GENERATOR 2E24B EMERG MCC2B-63 BLDG RAB 2CV1050-2 CONTACTOR Confirmed 264 2 42R-2B63C2 2CVI050-2 FPTURBINE  !TE Class A20 2B63 ELEV 372 ROOM 2096 COL EPRI 3002002997 SIZE I HEADER A ISOLATION VALVE Reactor Building Containment Cooling Fan Cooling RAB EL 386, ROOM 2118, 265 2 62-53Li 2VSFIA AT&C 365A300Q30P?' 2Cl7 SQURTS Testing Confirmed 2VSF-IA (Containment COLB Cooler Fan)

CHARGING PUMP 2P36A CHARGING RAB - - BLDG RAB ELEV 266 2 62/52A5 2P36A AT&C 365A300Q30PX 2B52 SQURTS Testing Confirmed TIME DELAY RELAY PUMP 335 ROOM 2040 COL C Charging Pump & Unit Cooler CHARGING RAB EL 386, ROOM 2118, 267 2 62/52A5-l 2P36A AT&C 365A300Q30PX 2Cl8-l SQURTS Testing Confirmed 2P36N2VUC7A-i PUMP COLB Page 51of73

Controlled Document Arkansas Nuclear One: S0.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results DIESEL CONTROL RELAY FOR GENERATOR RAB - - BLDG RAB ELEV 268 2 CR-2GI04 2K-4A P&B MDR-138-8 2C33-I EPRI 3002002997 Confirmed 2DGI AND 386 ROOM 2118 COL B AUXILIARIES UNDERVOLTAGE RELAY 4.16KVESF RAB - - BLDG RAB ELEV 269 2 127-2A4/Xl 2A-4 P&B MDR-138-8 2A408 EPRI 3002002997 Confirmed FORBUS2A-4 SWITCHGEAR 372 ROOM 2100 COLD

- UNDERVOLTAGE RELAY 4.16KVESF RAB - - BLDG RAB ELEV 270 2 127-2A4/X2 2A-4 P&B MDR-138-8 2A408 EPRI 3002002997 Confirmed FORBUS2A-4 SWITCHGEAR 372 ROOM 2100 COLD UNDERVOLTAGE RELAY 4.16KVESF RAB - - BLDG RAB ELEV 271 2 127-2A4/X3 2A-4 P&B MDR-138-8 2A408 EPRI 3002002997 Confirmed FORBUS2A-4 SWITCHGEAR 372 ROOM 2100 COLD UNDERVOLTAGE RELAY 4.16KV ESF RAB - - BLDG RAB ELEV 272 2 27-2A4/XA 2A-4 P&B MDR-138-8 2A408 EPRI 3002002997 Confirmed FORBUS2A-4 SWITCHGEAR 372 ROOM 2100 COLD UNDERVOLTAGE RELAY 4.16KVESF RAB - - BLDG RAB ELEV 273 2 27-2A4/XB 2A-4 P&B MDR-138-8 2A408 EPRI 3002002997 Confirmed FORBUS2A-4 SWITCHGEAR 372 ROOM 2100 COLD DIESEL AUX RELAY DIESEL GEN GENERATOR RAB - - BLDG RAB ELEV 274 2 152-408/X 2K-4B P&B MDR-5139 2A408 EPRI 3002002997 Confirmed 2K-4B AND 372 ROOM 2101 COLE AUXILIARIES DIESEL DIESEL GENERATOR NO 2 GENERATOR RAB - - BLDG RAB ELEV 275 2 2K-4B-159N NEUTRLOVERCURRENT 2K-4B GE 121AVSID2A 2E21 ANO Documentation Confirmed AND 369 ROOM 2094 COL B RELAY AUXILIARIES DIESEL GENERATOR RAB - - BLDG RAB ELEV 276 2 159NX-2 AUX RELAY FOR 2EDG2 2K-4B P&B MDR-137-8 2C33-2 EPRI 3002002997 Confirmed AND 386 ROOM 2118 COL B

, AUXILIARIES DIESEL RAB - - BLDG RAB ELEV EMERG. FEEDWATERPUMP GENERATOR SQURTS Testing Confirmed 277 2 162/2A311 2P7B AT&C 365A300N30PX 2Cl7 386 ROOM2118 COL 2P7B AND B LINE 5 AUXILIARIES RAB - - BLDG RAB ELEV SERVICE WATER PUMP SERVICE 278 2 162/2A402-2 2P4C AT&C 365A300N30PX 2Cl6 386 ROOM 2118 COL SQURTS Testing Confirmed 2P4C WATER PUMP B

LOW PRESSURE RAB - - BLDG RAB ELEV SAFETY 279 2 162/2A405 LPSI PUMP 2P60B 2P-60B AT&C 365A300N30PX 2Cl6 386 ROOM2118 COL SQURTS Testing Confirmed INJECTION B LINES PUMP Page 52 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results LOCKOUT RELAY FOR BUS 4.16KVESF RAB - - BLDG RAB ELEV 280 2 186-2A4 2A-4 GE 12HEA62B236X2 2A409 EPRI 3002002997 Confinned 2A4 SWITCHGEAR 372 ROOM 2100 COLD DIESEL LOCKOUT RELAY FOR GENERATOR RAB - - BLDG RAB ELEV 281 2 186-2DG2 2K-4B GE 12HEA62A223X2 2A408 EPRI 3002002997 Con finned 2DG2 AND 372 ROOM 2101 COLE AUXILIARIES DIESEL AUX DIFFERENTIAL GENERATOR RAB - - BLDG RAB ELEV 282 2 187X-2DG2 2K-4B Gould CAT Jl3P20 2E21 SQURTS Testing Outlier RELAY FOR 2DG2 AND 369 ROOM 2094 COL B AUXILIARIES DIESEL AUX DIFFERENTIAL GENERATOR RAB - - BLDG RAB ELEV 283 2 187Xl-2DGI 2K-4B P&B MDR-137-8 2C33-2 EPRI 3002002997 Confinned RELAY FOR 2DGI AND 386 ROOM 2118 COLB AUXILIARIES DIESEL TIME DELAY RELAY GENERATOR RAB - - BLDG RAB ELEV 284 2 2-2Al2-l 2K-4B Amerace E7022PC003 or E7022PC004 2E21 EPRI 3002002997 Con finned LOCKOUT AND 369 ROOM 2094 AUXILIARIES DIESEL TIME DELAY RELAY GENERATOR RAB - - BLDG RAB ELEV 285 2 2-2Al2-2 2K-4B Amerace E7022PC003 or E7022PC004 2E21 EPRI 3002002997 Confirmed LOCKOUT AND 369 ROOM 2094 AUXILIARIES DIESEL TIME DELAY ENERGIZE GENERATOR RAB - - BLDG RAB ELEV 286 2 2-2Al2-3 2K-4B Thomas & Betts E7012PC004 2E21 EPRI NP-7147-SL Con finned RELAY LOCKOUT AND 369 ROOM 2094 COL B AUXILIARIES DIESEL TIME DELAY ENERGIZE GENERATOR RAB - - BLDG RAB ELEV 287 2 2-2Al2-4 2K-4B Thomas & Betts E7012PC004 2E21 EPR! NP-7147-SL Con finned RELAY LOCKOUT AND 369 ROOM 2094 COL B AUXILIARIES DIESEL GENERATOR RAB - - BLDG RAB ELEV 288 2 27-IX/2B6 AUX RELAY FOR BUS 2B6 2K-4B P&B MDR-137-8 2C33-2 EPR! 3002002997 Con finned AND 386 ROOM 2118 COLB AUXILIARIES 2A 2A4 BUS UNDERVOLTAGE 4.16KVESF RAB - - BLDG RAB ELEV 289 2 2A-4 GE 178A8893 G-1 2A4 ANO Documentation Con finned 1272A4/A RELAY (B & C PHASES) SWITCHGEAR 372 ROOM 2100 COLE Page 53 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results 2A 2A4BUSUNDERVOLTAGE 4.16KV ESF RAB - - BLDG RAB ELEV 290 2 2A-4 GE l 78A8893 G-1 2A4 ANO Documentation Con finned 1272A4/B RELAY (A & B PHASES) SWITCHGEAR 372 ROOM 2100 COLE INVERSE TIME AND 2A-401- 4.16KVESF RAB - - BLDG RAB ELEV 291 2 INSTANT OVERCURRENT 2A-4 GE 12IAC51B104A 2A401 ANO Documentation Confinned 150/151A SWITCHGEAR 372 ROOM 2100 COLD RELAY 2A-40 I INVERSE TIME AND 2A-401- 4.16KVESF RAB - - BLDG RAB ELEV 292 2 INSTANTOVERCURRENT 2A-4 GE 12IAC51Bl04A 2A401 ANO Documentation Con finned 150/151B SWITCHGEAR 372 ROOM 2100 COLD RELAY 2A-401 INVERSE TIME AND 2A-401- 4.16KV ESF RAB - - BLDG RAB ELEV 293 2 INSTANT OVERCURRENT 2A-4 GE 12IAC51Bl04A 2A401 ANO Documentation Con finned 150/151C SWITCHGEAR 372 ROOM 2100 COLD RELAY 2A-40 I INSTANTANEOUS GROUND 4.16KVESF RAB - - BLDG RAB ELEV 294 2 2A-401-150GS 2A-4 GE 12HFC21BIA 2A401 ANO Documentation Con finned SENSOR RELAY FOR 2A-40 I SWITCHGEAR 372 ROOM 2100 COLD MOTOR FEEDER LONG 2A-402- SERVICE RAB - - BLDG RAB ELEV 295 2 TIME OC RELAY FOR 2A- 2P4C GE 12IAC66Kl9A 2A402 ANO Documentation Confinned 150/151A WATER PUMP 372 ROOM 2100 COLD 402 MOTOR FEEDER LONG 2A-402- SERVICE RAB - - BLDG RAB ELEV 296 2 TIME OC RELAY FOR 2A- 2P4C GE 12IAC66Kl9A 2A402 ANO Documentation Confinned 150/151B WATER PUMP 372 ROOM 2100 COLD 402 MOTOR FEEDER LONG 2A-402- SERVICE RAB - - BLDG RAB ELEV 297 2 TIME QC RELAY FOR 2A- 2P4C GE 121AC66Kl9A 2A402 ANO Documentation Con finned 150/151C WATER PUMP 372 ROOM 2100 COLD 402 INSTANTANEOUS GROUND SERVICE RAB - - BLDG RAB ELEV 298 2 2A-402-l 50GS 2P4C GE 12HFC21BlA 2A402 ANO Documentation Confirmed SENSOR RELAY FOR ZA-402 WATER PUMP 372 ROOM 2100 COLD OVERCURRENT RELAY 4.l6KVESF RAB - - BLDG RAB ELEV 299 2 2A-409-151A 2A-4 GE 121AC51AIOIA 2A4 ANO Documentation Confirmed FOR2A-409 SWITCHGEAR 372 ROOM2100 COLD OVERCURRENT RELAY 4.l6KVESF RAB - - BLDG RAB ELEV 300 2 2A-409-151B 2A-4 GE 12IAC51AIOIA 2A4 ANO Documentation Con finned FOR2A-409 SWITCHGEAR 372 ROOM 2100 COLD OVERCURRENT RELAY 4.16KV ESF RAB - - BLDG RAB ELEV 301 2 2A-409-151C 2A-4 GE 12IAC51AIOIA 2A4 ANO Documentation Con finned FOR2A-409 SWITCHGEAR 372 ROOM 2100 COLD Page 54 of 73

Controlled Document Arkansas Nuclear One: S0.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results NEUTRAL INVERSE TIME 4.16KVESF RAB - - BLDG RAB ELEV 302 2 2A-409-151N GRNDFAULTRELAYFOR 2A-4 GE 12IAC77A801A 2A4 ANO Documentation Confirmed SWITCHGEAR 372 ROOM 2100 COLD 2A-409 2A-408-DIRECTIONAL GROUND 167G2A409 4.16KVESF RAB - - BLDG RAB ELEV 303 2 OVERCT RELAY FOR 2A- 2A-4 GE 121CC51A7A 2A4 No Capacity Found Outlier (2A-409, SWITCHGEAR 372 ROOM 2100 COLD 409 167G)

DIRECTIONAL 4.16KVESF RAB - - BLDG RAB ELEV 304 2 2A-409-167SA OVERCURRENT RELAY 2A-4 GE 12IBC5!E2A 2A4 ANO Documentation Outlier SWITCHGEAR 372 ROOM 2100 COLD FOR 2A-409 PHASE A DIRECTIONAL 4.16KVESF RAB - - BLDG RAB ELEV 305 2 2A-409-i 67SB OVERCURRENTRELAY 2A-4 GE 12IBC51E2A 2A4 ANO Documentation Outlier SWITCHGEAR 372 ROOM 2100 COLD FOR 2A-409 PHASE B DIRECTIONAL 4.16KVESF RAB - - BLDG RAB ELEV 306 2 2A-409-167SC OVERCURRENTRELAY 2A-4 GE 12IBC51E2A 2A4 ANO Documentation Outlier SWITCHGEAR 372 ROOM 2100 COLD FOR 2A-409 PHASE C DIESEL 2A-408- DIESEL GENERATOR #2 GENERATOR RAB - - BLDG RAB ELEV 307 2 2K-4B Gould TYPE ITE-25V 2A408 EPRI TR-I 05988 V2 Confirmed 252DG2 SYNC-CHECK RELAY AND 372 ROOM2100 COLF AUXILIARIES 480VESF UNDERVOLTAGERELAY MOTOR RAB - - BLDG RAB ELEV 308 2 2B-6-271/2B6 2B-6 ABB TYPE ITE-27N 2B6 EPRI 3002002997 Confirmed FOR2B-6 CONTROL 372 ROOM2100 COLD CENTER 480VESF UNDERVOLTAGERELAY MOTOR RAB - - BLDG RAB ELEV 309 2 2B-6-272/2B6 2B-6 ABB TYPE ITE-27N 2B6 EPRI 3002002997 Confirmed BUS 2B-6 CONTROL 372 ROOM 2100 COLD CENTER 480V ESF TIME OVERCURRENT MOTOR RAB - - BLDG RAB ELEV 310 2 2B-6-511 2B-6 GE 12IAC51AIOIA 2B6 ANO Documentation Confirmed RELAY FOR 2B-6 (PHASE C) CONTROL 372 ROOM 2l00 COLD CENTER 480VESF TIME OVERCURRENT MOTOR RAB - - BLDG RAB ELEV 31 I 2 2B-6-512 2B-6 GE 12IAC51AIOIA 2B6 ANO Documentation Confirmed RELAY FOR 2B-6 (PHASE A) CONTROL 372 ROOM 2100 COLD CENTER Page 55 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results 480VESF GROUND FAULT RELAY MOTOR RAB - - BLDG RAB ELEV 312 2 2B-6-51N 2B-6 GE 121AC51AIOIA 2B6 ANO Documentation Con finned FOR2B-6 CONTROL 372 ROOM 2100 COLD CENTER DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 313 2 2CI08-4A 2K-4B Gould CAT Jl3P30 2CI08 SQURTS Testing Outlicr< 1>

(2DG2) START AND 369 ROOM 2094 COL B AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 314 2 2C!08-4B 2K-4B Gould CAT Jl3P30 2Cl08 SQURTS Testing Outlier)

(20G2) START AND 369 ROOM 2094 COL B AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 315 2 2CI08A-5 (20G2) GENERATOR DIFF 2K-4B AMERACE E7022PET004 2CI08 EPRI 3002002997 Confirmed AND 369 ROOM 2094 COL TRIP AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 316 2 2C!08-5A (2DG2) AUX STOPPING 2K-4B Gould CAT Jl3P30 2Cl08 SQURTS Testing Outlicr( 1l AND 369 ROOM 2094 COL B RELAY AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 317 2 2CI08-EOR (2DG2) ENGINE 2K-4B Gould CAT Jl3P30 2Cl08 SQURTS Testing Outlier<!)

AND 369 ROOM 2094 COL B OVERSPEED TRIP AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV Outlier<I) 318 2 2CI08-ERA (2DG2) NORMAL SPEED 2K-4B Gould CAT Jl3P30 2CI08 SQURTS Testing AND 369 ROOM 2094 COL B (810 RPM)

AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 319 2 2Cl08-ESI (2DG2) 4 I 60V 2K-4B Gould CAT Jl3P30 2CI08 SQURTS Testing Oullierl AND 369 ROOM 2094 COL B UNDERVOLTAGE AUXILIARIES DIESEL EMERG DIESEL 2K4B 2DG2) GENERATOR RAB - - BLDG RAB ELEV 320 2 2CI08-ES2 2K-4B Gould CAT Jl3P30 2CI08 SQURTS Testing Outlicr0 >

4160V UNDERVOLTAGE AND 369 ROOM 2094 COL B AUXILIARIES EMERG DIESEL 2K4B DIESEL RAB - - BLDG RAB ELEV 321 2 2C!08-LSA (2DG2) LOW SPEED (250 2K-4B GENERATOR Gould CAT Jl3P30 2CI08 SQURTS Testing Outlier' 11 369 ROOM 2094 COL B RPM) AND Page 56 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 322 2 2Cl08-LSB 2K-4B Gould CAT J13P30 2Ci08 SQURTS Testing Outlier< 1>

(2DG2) JACKET COOLANT AND 369 ROOM 2094 COL B AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV Outlier<!)

323 2 2Ci08-0Pl (2DG2) LUBE OIL 2K-4B Gould CAT Jl3P30 2Ci08 SQURTS Testing AND 369 ROOM 2094 COL B PRESSURE SENSING AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV OutlicrC 1>

324 2 2Cl08-0P2 (2DG2) LUBE OIL 2K-4B Gould CAT J13P30 2Ci08 SQURTS Testing AND 369 ROOM 2094 COL B PRESSURE SENSING AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV Outlicr< 1>

325 2 2Cl08-0P3 (2DG2) LUBE OIL 2K-4B Gould CAT Jl3P30 2CI08 SQURTS Testing AND 369 ROOM 2094 COL B PRESSURE SENSING AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 326 2 2Cl08-Rl (2DG2) AUX STOPPING 2K-4B P&B MDR-137-8 2Cl08 EPRI 3002002997 Confinned AND 369 ROOM 2094 COL B RELAY AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV Outlicrll) 327 2 2Cl08-SDR 2K-4B Gould CAT Jl3P30 2Ci08 SQURTS Testing (2DG2) AND 369 ROOM 2094 COL B AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV Outlier<!)

328 2 2Cl08-SFR 2K-4B Gould CAT J13P30 2Ci08 SQURTS Testing (2DG2) START FAILURE AND 369 ROOM 2094 COL B AUXILIARIES DIESEL 2Cl08A-T2A EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 329 2 (2Cl08, TIA- (2DG2) CRANKING TIME 2K-4B AMERACE E7012PD003 2Cl08 EPRINP-7147-SL Confinncd AND 369 ROOM 2094 COL 2DG2) LIMIT AUXILIARIES DIESEL 2Ci08A-T2B EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 330 2 (2Ci08, T2B- (2DG2) CRANKING TIME 2K-4B AMERACE E7012PD003 2Ci08 EPRI NP-7147-SL Con finned AND 369 ROOM 2094 COL 2DG2) LIMIT AUXILIARIES Page 57 of 73

Controlled Document Arkansas Nuclear One: 50.54(1) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 331 2 2Cl08A-T3A 2K-4B AMERACE E7012PDLL004 2Cl08 EPR! NP-7147-SL Conlirmed (2DG2) TRIP ENABLE AND 369 ROOM 2094 COL AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 332 2 2Cl08A-T3B (2DG2) TRIP ENABLE 2K-4B AMERACE E7012PDLL004 2Cl08 EPRINP-7147-SL Confirmed AND 369 ROOM 2094 COL TIMER AUXILIARIES DIESEL EMERG DIESEL 2K4B GENERATOR RAB - - BLDG RAB ELEV 333 2 2Cl08-T3X (2DG2) EDGE NOT 2K-4B P&B MDR-5139 2Cl08 EPRI 3002002997 Confirmed AND 369 ROOM 2094 COL B AVAILABLE ALARM AUXILIARIES CHARGING PUMP 2P-36B CHARGING RAB - - BLDG RAB ELEV 334 2 2CR-62A5-l 2P36B Gould CAT JJOB4012 2B62A5 EPRI TR-105988 V2 Confirmed CNTRLRELAY PUMP 354 ROOM 2073 COL A DIESEL UNDERVOLTAGE RELAY 2K-4B- GENERATOR RAB - - BLDG RAB ELEV 335 2 FOR DIESEL GENERATOR 2K-4B GE 12NGV21BlA 2El2 ANO Documentation Confirmed 1272DG2 AND 369 ROOM 2094 COL B N02 AUXILIARIES DIESEL DIESEL GENERATOR ANTI 2K-4B- GENERATOR RAB - - BLDG RAB ELEV 336 2 MOTORING RELAY FOR 2K-4B GE 12GGP53BlA 2A408 EPRINP-7147-SL Outlier 1322DG2 AND 372 ROOM 2101 COLE 2A408 AUXILIARIES DIESEL 2K-4B- DG OVERCURRENT RELAY GENERATOR RAB - - BLDG RAB ELEV 337 2 2K-4B GE 12JJCV51A13A 2A408 ANO Documentation Outlier 151V2DG2A FOR2A-408 AND 372 ROOM2100 COLD AUXILIARIES DIESEL 2K-4B- DG OVERCURRENT RELAY GENERATOR RAB - - BLDG RAB ELEV 338 2 2K-4B GE 12IJCV51A13A 2A408 ANO Documentation Outlier 151V2DG2B FOR 2A-408 AND 372 ROOM 2100 COLD AUXILIARIES DIESEL 2K-4B- DG OVERCURRENT RELAY GENERATOR RAB - - BLDG RAB ELEV 339 2 2K-4B GE 121JCV51Al3A 2A408 ANO Documentation Outlier 151V2DG2C FORZA-408 AND 372 ROOM 2100 COLD AUXILIARIES DIESEL 2K-4B- DIESEL GENERATOR NO 2 GENERATOR RAB - - BLDG RAB ELEV 340 2 2K-4B GE 12NGV21B5A 2E22 ANO Documentation Confirmed 1592DG2 RUNNING RELAY AND 369 ROOM 2094 COL B AUXILIARIES I

Page 58 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results DIESEL 2K-4B- DIESELGEN2 GENERATOR RAB - - BLDG RAB ELEV 341 2 2K-4B GE i2SBDllB2A 2E2i No Capacity Found Outlier 1872DG2A DIFFERENTIAL RELAY AND 369 ROOM 2094 COL B AUXILIARIES DIESEL 2K-4B- DIESELGEN2 GENERATOR RAB - - BLDG RAB ELEV 342 2 2K-4B GE 12SBDI 1B2A 2E21 No Capacity Found Outlier 1872DG2B DIFFERENTIAL RELAY AND 369 ROOM 2094 COL B AUXILIARIES DIESEL 2K-4B- DIESELGEN2 GENERATOR RAB - - BLDG RAB ELEV 343 2 2K-4B GE 12SBDllB2A 2E21 No Capacity Found Outlier 1872DG2C DIFFERENTIAL RELAY AND 369 ROOM 2094 COL B AUXILIARIES MCC2B-62 BLDG RAB 2CVl474-2 CONTACTOR SWRESVRTO 344 2 42R-2B62H3 2CVl474-2 lTE Class A20 2B62H3 ELEV 354 ROOM 2073 COL EPRI 3002002997 Confirmed SIZE i 2P4C A

SERVICE MCC2B-62 BLDG RAB 2CV1480-2 CONTACTOR WATER RETURN 345 2 42R-2B62LS 2CV1480-2 ITE Class A20 2B62LS ELEV 3S4 ROOM 2073 COL EPRl 3002002997 Confirmed SIZE 1 TO A

DARDANELLE Reactor Building RAB - - BLDG RAB ELEV CONTAINMENT COOLING Cooling 346 2 62/63Ll 2VSFIC AT&C 36SA300Q30PX 2Cl6 386 ROOM2118 COL SQURTS Testing Confirmed FAN 2VSF-IC (Containment B LINES Cooler Fan)

CHARGING PUMP 2P36B CHARGING RAB - - BLDG RAB ELEV 347 2 62/62AS 2P36B AT&C 36SA300Q30PX 2B62 SQURTS Testing Confirmed TIME DELAY RELAY PUMP 3S4 ROOM 2073 COL C RAB - - BLDG RAB ELEV CHARGING PUMP & UNIT CHARGING 348 2 62/62AS-l 2P36B AT&C 36SA300Q30PX 2Cl8-2 386 ROOM 2118 COL SQURTS Testing Confirmed COOLER 2P36B/2VUC7B-2 PUMP B LINES DIESEL CONTROL RELAY FOR GENERATOR RAB - - BLDG RAB ELEV 349 2 CR-2GIOS 2K-4B P&B MDR-138-8 2C33-2 EPRI 3002002997 Confirmed 2DG2 AND 386 ROOM 2118 COL B AUXILIARIES 2Yll, BLDG RAB ELEV 2Yl3, 120VAC Poller & Brumfield 2Yll,2Yi3, 372 ROOM 2099 COLD & E 3SO 2 RLI X2 Oscillator Board 4PDT 3A KHAU-17Dl8-12 EPRI 3002002997 Confirmed 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM209i COLH Page 59 of 73

Controlled Document Arkansas Nuclear One: 50.54(f} NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results 2Yii, BLDG RAB ELEV 2Yi3, 120VAC Potter & Brumfield 2Yil, 2Y13, 372 ROOM 2099 COLD & E 351 2 RLI XS Synch Board 4PDT 3A KHAU-17Ai8-120 SQURTS Testing Confirmed 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2Yli, BLDG RAB ELEV 2Yi3, 120VAC Potter & Brumfield 2Yii, 2Yi3, 372 ROOM 2099 COLD & E 3S2 2 RL2 XS Synch Board 4PDT 3A KHAU-17D18-12 EPRI 3002002997 Confirmed 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2Yii, BLDG RAB ELEV 2Y13, 120VAC Potter & Brumfield 2Yll, 2Yi3, 372 ROOM 2099 COLD & E 353 2 RL3 XS Synch Board 4PDT 3A KHAU-17Di8-12 EPRI 3002002997 Confirmed 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2Yli, BLDG RAB ELEV 2Yi3, 120VAC Polter & Brumfield 2Yll,2Yi3, 372 ROOM 2099 COLD & E 3S4 2 RLl XI 8 Shorting Board 4PDT 3A KHAU-17Dl8-llO EPRI TR-IOS988 V2 Confirmed 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2Yli, BLDG RAB ELEV Xi9 Loss of DC Voltage Sense 2Yi3, 120VAC 2Yii,2Y13, 372 ROOM 2099 COLD & E 35S 2 RLI Omron MY4-DC24S SQURTS Testing Confirmed Board 4PDT 3A 2Y22, Instrument Inverter 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2Yil, BLDG RAB ELEV X20 I Static Switch Control 2Yi3, 120VAC Potter & Brumfield 2Yll,2Yi3, 372 ROOM 2099 COLD & E 356 2 RLI KHAU-17Dl8-12 EPRI 3002002997 Confirmed Board3A 2Y22, Instmrnent Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM2091 COLH 2Yil, BLDG RAB ELEV X20 I Static Switch Control 2Yi3, 120VAC Potter & Brumfield 2Yll, 2Yi3, 372 ROOM 2099 COLD & E 357 2 RL2 KHAU-17A18-i20 SQURTS Testing Confirmed Board 4PDT 3A 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2Yii, BLDG RAB ELEV X201 Static Switch Control 2Yl3, 120VAC Computer 2Yll, 2Yl3, 372 ROOM 2099 COLD & E 3S8 2 RR! 300-470 SQURTS Testing Confirmed Board Reed Relay 0.5A 2Y22, Instrument Inverter Components 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2Yll, BLDG RAB ELEV X201 Static Switch Control 2Yl3, 120VAC 2YIJ, 2Yl3, 372 ROOM 2099 COLD & E 359 2 RRI Gordos Corp. F81-1423 SQURTS Testing Confirmed Board Reed Relay 0.5A 2Y22, Instrument Inverter 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H Page 60 of73

Controlled Document Arkansas Nuclear One: S0.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Linc Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results 2YII, BLDG RAB ELEV X202 Static Switch Auto Re- 2Yl3, 120VAC Potter & Brumfield 2YI I, 2Yl3, 372 ROOM 2099 COLD & E 360 2 Kl KHAU-I7Dl8-12 EPRI 3002002997 Confirmed transfer Board 4PDT 3A 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2YII, BLDG RAB ELEV X202 Static Switch Auto Re- 2Y13, 120VAC Potter & Brumfield 2Yll,2YI3, 372 ROOM 2099 COLD & E 361 2 K2 KHAU-17Al8-120 SQURTS Testing Confirmed transfer Board 4PDT 3A 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2YII, BLDG RAB ELEV X202 Static Switch Auto Re- 2Yl3, 120VAC Potter & Brumfield 2YI I, 2Yl3, 372 ROOM 2099 COLD & E 362 2 K3 KHAU-17Al8-120 SQURTS Testing Con finned transfer Board 4PDT 3A 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2Yll, BLDG RAB ELEV X202 Static Switch Auto Re- 2Y13, l20VAC Potter & Brumfield 2Yll,2Yl3, 372 ROOM 2099 COLD & E 363 2 K4 KHAU-17Al8-120 SQURTS Testing Confirmed transfer Board 4PDT 3A 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2Yll, BLDG RAB ELEV X202 Static Switch Auto Re- 2Y13, 120VAC Potter & Brumfield 2YI l, 2Yl3, 372 ROOM 2099 COLD & E 364 2 KS KHAU-l7A18-120 SQURTS Testing Confirmed transfer Board 4PDT 3A 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H 2Yll, BLDG RAB ELEV X202 Static Switch Auto Re- 2Y13, l20VAC Potter & Brumfield 2Yl l, 2Yl3, 372 ROOM 2099 COLD & E 36S 2 K6 KHAU-17Al8-120 SQURTS Testing Confirmed transfer Board 4PDT 3A 2Y22, Instrument Inverter (Tyco) 2Y22, 2Y24 BLDG TB ELEV 368 2Y24 ROOM 2091 COL H BLDG RAB ELEV 2Y-1113, 120VAC Potter & Brumfield 2Y-1113,2Y- 372 ROOM 2099 COLD & E 366 2 RLl X2 Oscillator Board 4PDT 3A KHAU-17Dl8-12 EPRI 3002002997 Confirmed 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM 2091 COL H BLDG RAB ELEV 2Y-ll 13, 120VAC Potter & Brumfield 2Y-1113,2Y- 372 ROOM 2099 COLD & E 367 2 RLI XS Synch Board 4PDT 3A KHAU-17Al8-120 SQURTS Testing Confirmed 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM 2091 COL H BLDG RAB ELEV 2Y-1113, 120VAC Potter & Brumfield 2Y-1113, 2Y- 372 ROOM 2099 COLD & E 368 2 RL2 XS Synch Board 4PDT 3A KHAU-17Dl8-12 EPRI 3002002997 Confirmed 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM2091 COLH Page 61of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results BLDG RAB ELEV 2Y-1113, i20VAC Potter & Brumfield 2Y-1113,2Y- 372 ROOM 2099 COLD & E 369 2 RL3 X5 Synch Board 4PDT 3A KHAU-17Dl8-12 EPRI 3002002997 Confirmed 2Y-2224 Instrument Inverter (Tyco) 2224 BLDGTB ELEV 368 ROOM2091 COLH BLDG RAB ELEV 2Y-l 113, 120VAC Potter & Brumfield 2Y-l l 13, 2Y- 372 ROOM 2099 COLD & E 370 2 RL! XI 8 Shorting Board 4PDT 3A KHAU-17Dl8-110 EPRI TR-105988 V2 Confirmed 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM 2091 COL H BLDG RAB ELEV Xl9 Loss of DC Voltage Sense 2Y-1!13, 120VAC 2Y-1113,2Y- 372 ROOM 2099 COLD & E 371 2 RL! Omron MY4-DC24S SQURTS Testing Confirmed Board 4PDT 3A 2Y-2224 Instrument Inverter 2224 BLDG TB ELEV 368 ROOM 2091 COL H BLDG RAB ELEV X201 Static Switch Control 2Y-1113, 120VAC Potter & Brumfield 2Y-1!13,2Y- 372 ROOM 2099 COLD & E 372 2 RLl KHAU-17Dl8-12 EPRI 3002002997 Confirmed Board3A 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM 2091 COL H BLDG RAB ELEV X201 Static Switch Control 2Y-1113, 120VAC Potter & Brumfield 2Y-l l 13, 2Y- 372 ROOM 2099 COLD & E 373 2 RL2 KHAU-17Al8-120 SQURTS Testing Confirmed Board 4PDT 3A 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM 2091 COL H BLDG RAB ELEV X201 Static Switch Control 2Y-1113, 120VAC Computer 2Y-1113,2Y- 372 ROOM 2099 COLD & E 374 2 RR! 300-470 SQURTS Testing Confirmed Board Reed Relay 0.5A 2Y-2224 Instrument Inverter Components 2224 BLDG TB ELEV 368 ROOM 2091 COL H BLDG RAB ELEV X20 I Static Switch Control 2Y-1113, 120VAC 2Y-1113,2Y- 372 ROOM 2099 COLD & E 375 2 RR! Gordos Corp. F81-1423 SQURTS Testing Confirmed Board Reed Relay 0.5A 2Y-2224 Instrument Inverter 2224 BLDG TB ELEV 368 ROOM2091 COLH BLDG RAB ELEV X202 Static Switch Auto Re- 2Y-1113, 120VAC Potter & Brumfield 2Y-l i 13, 2Y- 372 ROOM 2099 COLD & E 376 2 Kl KHAU-!7Dl8-12 EPRI 3002002997 Confirmed transfer Board 4PDT 3A 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM 2091 COL H BLDG RAB ELEV X202 Static Switch Auto Re- 2Y-l 113, 120VAC Potter & Brumfield 2Y-1113,2Y- 372 ROOM 2099 COLD & E 377 2 K2 KHAU-17Al8-120 SQURTS Testing Confirmed transfer Board 4PDT 3A 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM 2091 COL H Page 62 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results BLDG RAB ELEV X202 Static Switch Auto Re- 2Y-1113, 120VAC Potter & Brumfield 2Y-i I 13, 2Y- 372 ROOM 2099 COLD & E 378 2 K3 KHAU-17Al8-120 SQURTS Testing Confirmed transfer Board 4PDT 3A 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM 2091 COL H BLDG RAB ELEV X202 Static Switch Auto Re- 2Y-lli3, 120VAC Potter & Brumfield 2Y-lli3,2Y- 372 ROOM 2099 COLD & E 379 2 K4 KHAU-17Ai8-120 SQURTS Testing Confirmed transfer Board 4PDT 3A 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM 2091 COL H BLDG RAB ELEV X202 Static Switch Auto Re- 2Y-lll3, l20VAC Potter & Brumfield 2Y-lll3,2Y- 372 ROOM 2099 COLD & E 380 2 K5 KHAU-l7A18-l20 SQURTS Testing Confirmed transfer Board 4PDT 3A 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM209l COLH BLDG RAB ELEV X202 Static Switch Auto Re- 2Y-lll3, 120VAC Potter & Brumfield 2Y-1l13, 2Y- 372 ROOM 2099 COLD & E 381 2 K6 KHAU-17A18-120 SQURTS Testing Confirmed transfer Board 4PDT 3A 2Y-2224 Instrument Inverter (Tyco) 2224 BLDG TB ELEV 368 ROOM2091 COLH 2D-31A, 2D-31A,2D- BLDG RAB ELEV 372 X304 AC Relay Board 4PDT 2D-31B, BATTERY Potter & Brumfield 3IB, ROOM 2099 COL C 382 2 K KHAU-17A18-120 SQURTS Testing Confirmed 3A 2D-32A, CHARGER (Tyco) 2D-32A,2D- BLDG RAB ELEV 372 2D-32B 32B ROOM 2097 COLD STEAM GENERATOR 2E24AEMERG MCC2B-53 BLDG TB 2CV-1000-383 2 42R-2B53B2 2CV-1000-1 CONTACTOR FPTURBINE  !TE Class A20 2B53B2 ELEV 368 ROOM 2091 COL GERS Confirmed I

HEADER H ISOLATION VALVE MCC2B-53 BLDGTB 2CV-1040- MSIV 2CVIOIO 384 2 42F-2B53BI 2CV-1040-1 CONTACTOR  !TE Class A20 2B53BI ELEV368 ROOM 2091 COL EPRI 3002002997 Confirmed 1 BYPASS H

MCC2B-63 BLDGRAB 2CV-1090- MSIV 2CV1060 385 2 42F-2B63G3 2CV-1090-2 CONTACTOR  !TE Class A20 2B63G3 ELEV 372 ROOM 2096 COL EPRI 3002002997 Confirmed 2 BYPASS A

C&VCSVCT MCC2B-54 BLDGRAB 2CV-4873-386 2 42R-2B54D4 2CV-4873-1 CONTACTOR DISCHARGE  !TE Class A20 2B54D4 ELEV372 ROOM2101 COL EPRI 3002002997 Confirmed I

VALVE E EDG 2K-4A LOW LUBE-OIL BLDG RAB ELEV 387 2 2PS-2917 A RETURN PRESSURE 2K-4A EDG2K-4A DETROIT SWITCH 222-1002 2K-4A 369 ROOM 2093 COL EPRI 3002002997 Confirmed SWITCH B Page 63 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Component Evaluation Line Supported Supported Device Component No. Unit Relay ID Relay Description Device ID Description Manufacturer Model Location Building & Elevation Basis for Capacity Evaluation Results EDG 2K-4A LOW LUBE-OIL BLDG RAB ELEV 388 2 2PS-2917B RETURN PRESSURE 2K-4A EDG2K-4A DETROIT SWITCH 222-1002 2K-4A 369 ROOM 2093 COL EPRI 3002002997 Confirmed SWITCH B EDG 2K-4A LOW LUBE-OIL BLDG RAB ELEV 389 2 2PS-2917 C RETURN PRESSURE 2K-4A EDG2K-4A DETROIT SWITCH 222-1002 2K-4A 369 ROOM 2093 COL EPRI 3002002997 Confirmed SWITCH B EDG 2K-4B LOW LUBE-OIL BLDG RAB ELEV 390 2 2PS-2967 A RETURN PRESSURE 2K-4B EDG2K-4B DETROIT SWITCH 222-1002 2K-4B 369 ROOM 2094 COL EPRI 3002002997 Confirmed SWITCH B EDG 2K-4B LOW LUBE-OIL BLDG RAB ELEV 391 2 2PS-2967B RETURN PRESSURE 2K-4B EDG2K-4B DETROIT SWITCH 222-1002 2K-4B 369 ROOM 2094 COL EPRI 3002002997 Confirmed SWITCH B EDG 2K-4B LOW LUBE-OIL BLDG RAB ELEV 392 2 2PS-2967C RETURN PRESSURE 2K-4B EDG2K-4B DETROIT SWITCH 222-1002 2K-4B 369 ROOM 2094 COL EPRI 3002002997 Confirmed SWITCH B BLDG RAB ELEV 2K-4A ENGINE OVERSPEED MICRO-SWITCH 393 2 2SS-2801 2K-4A EDG2K-4A MODEL 16-702-832 2K-4A 369 ROOM 2093 COL EPRI 3002002997 Confirmed SWITCH DIV/HONEYWELL B

BLDG RAB ELEV 2K-4B ENGINE OVERSPEED MICRO-SWITCH 394 2 2SS-2821 2K-4B EDG 2K-4B MODEL l6-702-832 2K-4B 369 ROOM 2094 COL EPRI 3002002997 Con finned SWITCH DIV/HONEYWELL c

(1) Sc1sm1c Capacity adequate for high frequency demand. The SQURTS testing noted that sigmficant drill occurred during testing. Classified as an outlier in order to evaluate potential impact of dnfl on these devices.

Page 64 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation C Resolution of Outlier Components Page 65 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Table C-1: Resolution Method for Outlier Components Component Line No. Description of Resolution I Supported Supported Device Unit Relay ID Relay Description Device ID Description Manufacturer Model I

A-308-132 I DIESEL GENERATOR Operator Action I 1 A308 EDG I Output Breaker GE 12GGP53BIA (132-DGI) ANT!MOTOR!NG RELAY I

A-308-151VA DIESEL GEN OC RELAY WITH 2 I A308 EDG 1 Output Breaker GE 12IJCV51Al3A Operator Action (151V-DG1-1).) VOLTAGE RESTRAINT A-308-151VB DIESEL GEN OC RELAY WITH 3 I A308 EDG 1 Output Breaker GE 121JCV51Al3A Operator Action (i51V-DG1-B) VOLTAGE RESTRAINT A-308-151VC DIESEL GEN OC RELAY WITH 4 1 A308 EDG I Output Breaker GE 121JCV51Al3A Operator Action (i51V-DG1-C) VOLTAGE RESTRAINT I

Ifa seismic event were to occur with a magnitude great enough to cause relay 152Xl-308

' contacts to chatter, relays) 62-DG Ill and 162-DGl/2 could potentially energize. If both 162-DG I/I and 162-DG 1/2 become energized, the diesel generator protection relays for generator differential, over current with voltage restraint and loss of field would be blocked 5 I  !52Xl-308 : AC AUX RELAY FOR A-308 A308 EDG 1 Output Breaker GE 12HGA11J52 from sending a signal to the generator lockout relay. However, due to the short time frame full voltage would be seen by 162-DGl/1 and 162-DGl/2 during relay contact chatter it is extremely unlikely that the diesel generator protective systems would be compromised during the seismic event."

UNDER VOLTAGERELAYFOR Normal Supply Bkr - A 1 Operator Action (Re-close each of the BUS A-3 breakers that tripped on undcrvoltagc as 6 1 A-3-127A3AB A309 GE 121AV54ElA BUS A-3 (A&B PHASES) FEEDTOA3 required.)

I A-408-132 DIESEL GENERATOR 7 1 A408 EDG 2 Output Breaker GE 12GGP53BlA Operator Action (132-DG2) ANT!MOTOR!NG RELAY I

A-408-151VA DIESEL GEN OC RELAY WITH 8 I A408 EDG 2 Output Breaker GE 121JCV51A13A Operator Action (151VDG2-A) VOLTAGE RESTRAINT A-408-ISIVB DIESEL GEN OC RELAY WITH 9 I A408 EDG 2 Output Breaker GE 121JCV51Al3A Operator Action (151VDG2-B) VOLTAGE RESTRAINT I

A-408-151 VC DIESEL GEN OC RELAY WITH 10 1 A408 EDG 2 Output Breaker GE 121JCV51Al3A Operator Action (151VDG2-fl VOLTAGE RESTRAINT Page 66 of73

Controlled Document Arkansas Nuclear One: S0.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Line No. Description of Resolution Supported Supported Device Unit Relay ID Relay Description Device ID Description Manufacturer Model If a seismic event were to occur with a magnitude great enough to cause relay 152Xl-408 contacts to chatter, relays 162-DG2/1 and 162-DG2/2 could potentially energize. If both l 62-DG2/l and I 62-DG2/2 become energized, the diesel generator protection relays for generator differential, over current with voltage restraint and loss of field would be blocked II I 152Xl-408 AC AUX RELAY FOR A-408 A408 EDG 2 Output Breaker GE 12HGAllJ52 from sending a signal to the generator lockout relay. However, due to the short time frame full voltage would be seen by 162-DG2/I and 162-DG2/2 during relay contact chatter it is extremely unlikely that the diesel generator protective systems would be compromised during the seismic event.

If a seismic event were to occur with a magnitude great enough to cause relay 152Y-408 contacts to chatter, contacts in series with the breaker close coil could momentarily open preventing the breaker from closing.

12 I 152Y-408 Breaker anti-pump relay (magnablast) A408 EDG 2 Output Breaker GE 12HMAllB6 This action has no impact on breaker action. During the seismic event, the seal-in contact could momentarily close. There would be no impact on the circuit unless the breaker was being closed as the seismic event was occurring.

(Resolution established based on similarity to relays 152Y-402, 152Y-405, and 152Y-406).

UNDER VOLTAGE RELAY FOR Nonna! Supply Bkr - A2 Operator Action (Re-close each of the BUS A-4 breakers that tripped on undervoltagc as 13 I A-4-127A4AB A409 GE 12JAV54EIA BUS A-4 (A & B PHASES) FEEDTOA4 required.)

With transfer switch supplying power to MCC B56 from the nonnal source, relays CR! and CR2 are deenergized. In the event a seismic event of significant enough magnitude to cause relay CRl to chatter, there would be no impact on the circuit. IfCR2 were to chatter, the momentary closure ofCR2 during a seismic event could cause the transfer switch to transfer ASCO- power to the load to the emergency power source.

CONTROL RELAY FOR transfer 14 I CR2 B5611 AUTOMATIC PN 261479-2 switch With transfer switch supplying power to MCC B56 from the emergency source, relays CR!

SWITCHC and CR2 arc dccnergizcd. In the event a seismic event of significant enough magnitude to cause relay CRI to chatter, the momentary closure ofCRl during a seismic event could cause the transfer switch to transfer power to the load to the normal power source. IfCR2 were to chatter. there would be no impact on the circuit.

Page 67 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Line No. Description of Resolution Supported Supported Device Unit Relay ID Relay Description Device ID Description Manufacturer Model Therefore, ifCRl-1energizes,43-DOI will electrically connect DI I to DOI and ifCR2-1 energizes, 43-DO I will electrically connect D 11 to D02.

CRI-1 and CR2-I arc energized by selector switch CS-I or by CST-DC I (if remote control disconnect switch CS-RD! is in "REMOTE CONNECTED".

In the event a seismic event of significant enough magnitude to cause relay CRl-1 contacts to chatter, there would be no impact on the circuit if the transfer switch is connecting the load (Dl 1) to the normal power source. If the transfer switch was connected to the emergency power source, the momentary closure of CRl-1 during a seismic event could cause the transfer switch to transfer power to the load to the normal power source.

ASCO-CONTROL RELAY FOR D-0 i D0! 12 (43- In the event a seismic event of significant enough magnitude to cause relay CR2-1 contacts 15 I CR2-I MCC - transfer switch AUTOMATIC PN 261479-2 (EMERGENCY) DOI) to chatter, there would be no impact on the circuit if the transfer switch is connecting the SWITCHC load (DI 1) to the emergency power source. If the transfer switch was connected to the normal power source, the momentary closure of CR2-1 during a seismic event could cause the transfer switch to transfer power to the load to lhe normal power source.

A review of the service manual for the ASCO AUTOMATIC TRANSFER SWITCH (Document TD A610.0470) did not stale how the contactol'll for the normal and emergency power supplies operate (make before break or break before make), so it must be assumed that there will be a momentary loss of power to the load while the transfer takes place.

It is possible for the transfer switch to transfer back and forth between the nonnal power supply and the emergency power supply for the duration of the seismic event..

The schematic for relays CRI-2 and CR2-2 in Manual Transfer Switch 43-D02 is the same ASCO-CONTROL RELAY FOR D-02 D0212 (43- schematic as for relays CRl-l and CR2-i in Manual Transfer Switch 43-DOI. Therefore the 16 I CR2-2 MCC - transfer switch AUTOMATIC PN 261 479-2 (EMERGENCY) D02] operation of relays CRl-2 and CR2-2 will be the same as described above for relays CRl-1 SWITCHC and CR2-i.

K-4A-i27DGI EDG & accessories 17 I DIESEL GEN RUNNING RELAY K-4A GE 12HFA15iA9H Operator Action (127-DG! (Kl9)) assembly If a seismic event were to occur with a magnitude great enough to cause relay K54 contacts to chatter with the diesel running, there would be no impact on the diesel generator air start system due to PS5270 being open.

EDG & accessories WESTINGHOUSE 18 I Cl07-K54 STARTER NO. 2 RELAY K-4A ARD440SR assembly ELECCORP If the diesel generator was in standby when the seismic event happened. K8 relay contact 7-8 would be open preventing any of the air start circuit from energizing.

Therefore, a seismic event would have no impact on the diesel generator.

K-4B-i27DG2 EDG & accessories 19 I DIESEL GEN RUNNING RELAY K-4B GE 12HFAl51A9H Operator Action (i27-DG2 (Kl9)) assembly Page 68 of 73

Controlled Document Arkansas Nuclear One: S0.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Line No. Description of Resolution Supported Supported Device Unit Relay ID Relay Description Device ID Description Manufacturer Model If a seismic event were to occur with a magnitude great enough to cause relay K54 contacts to chatter with the dicscI running, there would be no impact on the diesel generator air start system due to PS5271 being open.

EDG & accessories WESTINGHOUSE 20 I CI08-K54 STARTER NO. 2 RELAY K-4B ARD440SR assembly ELECCORP If the diesel generator was in standby when the seismic event happened, KS relay contact 7-8 would be open preventing any of the air start circuit from energizing.

Therefore, a seismic event would have no impact on the diesel generator.

If a seismic event were to occur with a magnitude great enough to cause relay l 52Y405 contacts to chatter, contacts in series with the breaker close coil could momentarily open preventing the breaker from closing.

21 1 152Y-405 Breaker anti-pump relay (magnabiast) P-34B DHR Pump B (LP!) GE 12HMAllB6 This action has no impact on breaker action. During the seismic event, the seal-in contact could momentarily close. There would be no impact on the circuit unless the breaker was being closed as the seismic event were occurring.

If a seismic event were to occur with a magnitude great enough to cause relay 152Y-406 contacts to chatter, contacts in series with the breaker close coil could momentarily open Primary makeup pump preventing the breaker from closing.

22 I i52Y-406 Breaker anti-pump relay (magnablast) P-36C GE i2HMAllB6 (HP!) This action has no impact on breaker action. During the seismic event, the seal-in contact could momentarily close. There would be no impact on the circuit unless the breaker was being closed as the seismic event were occurring.

If a seismic event were to occur with a magnitude great enough to cause relay 152Y-402 contacLs to chatter, contacts in series with the breaker close coil could momentarily open preventing the breaker from closing.

23 I 152Y-402 Breaker anti-pump relay (magnabiast) P-4C SWPumpC GE i2HMAllB6 This action has no impact on breaker action. During the seismic event, the seal-in contact could momentarily close. There would be no impact on the circuit unless the breaker was being closed as the seismic event were occurring.

Relay l 87X-2DG 1 energizes when any of the diesel generator 2DG l di!Terentiai relays (2K-4A-l 872DG i-A, B or C) trip. Relay has no control function or "seal in" contact, provides AUX DIFFERENTIAL RELAY FOR DIESEL GENERATOR annunciator signal only.

24 2 187X-2DG1 2K-4A Gould CAT Jl3P20 2DGI AND AUXILIARIES When l 87X-2DG 1 energizes, a normally open contact closes and sends a signal to annunciator 2Kl 26 indicating there was a DIFFERENTIAL TRIP on 2EG I.

DIRECTIONAL GROUND 4.i6KVESF 25 2 2A-308-i 67G2A309 2A-3 GE i2ICC51A7A Operator Action OVERCT RELAY FOR 2A-309 SWITCHGEAR DIRECTIONAL OVERCURRENT 4.16KV ESF 26 2 2A-309-l 67SA 2A-3 GE i21BC51E2A Operator Action RELAY FOR 2A-309 PHASE A SWITCHGEAR DIRECTIONAL OVERCURRENT 4.16KVESF 27 2 2A-309-167SB 2A-3 GE 121BC51E2A Operator Action RELAY FOR 2A-309 PHASE B SWITCHGEAR DIRECTIONAL OVERCURRENT 4.16KVESF 28 2 2A-309-l 67SC 2A-3 GE 121BC5iE2A Operator Action RELAY FOR 2A-309 PHASE C SWITCHGEAR Page 69 of 73

Controlled Document Arkansas Nuclear One: S0.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Line No. Description of Resolution Supported Supported Device Unit Relay ID Relay Description Device ID Description Manufacturer Model 29 2 2CI07-4A DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference Erner Diesel 2K4A (2DG I) Start 2K-4A Gould CAT Jl3P30 AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 30 2 2Cl07-4B Erner Diesel 2K4A (2DGI) Start 2K-4A Gould CAT Jl3P30 AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

2Cl07-5A EMER DIESEL 2K4A (2DG 1) AUX DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 31 2 2K-4A Gould CAT Jl3P30 STOPPING RELAY AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

Erner Diesel 2K4A (2DG 1) Engine DIESEL GENERATOR Drift does not apply to this relay as it is not a timing relay. A review of the reference 32 2 2Cl07-EOR 2K-4A Gould CAT Jl3P30 Overspeed Trip AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

Erner Diesel 2K4A (2DG1) Normal DIESEL GENERATOR Drift does not apply to tltis relay as it is not a timing relay. A review of the reference 33 2 2Cl07-ERA 2K-4A Gould CAT Jl3P30 Speed (810 RPM) AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

Erner Diesel 2K4A (2DG1) 4160V DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 34 2 2Cl07-ESI 2K-4A Gould CAT Jl3P30 Undervoltage AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

Erner Diesel 2K4a (2DG1) 4160V DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 35 2 2Cl07-ES2 2K-4A Gould CAT Jl3P30 Undervoltage AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

Erner Diesel 2K4A (2DG1) Low DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 36 2 2Cl07-LSA 2K-4A Gould CAT Jl3P30 Speed (250 RPM) AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

Erner Diesel 2K4A (2DG1) Jacket DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 37 2 2Cl07-LSB 2K-4A Gould CAT Jl3P30 Coolant AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

Erner Diesel 2K4A (2DG 1) Lube Oil DIESEL GENERATOR Drift does not apply to this relay as it is not a timing relay. A review oflhe reference 38 2 2Cl07-0Pl 2K-4A Gould CAT Jl3P30 Pressure Sensing AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

Erner Diesel 2K4A (2DG1) Lube Oil DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 39 2 2Cl07-0P2 2K-4A Gould CAT Jl3P30 Pressure Sensing AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

Erner Diesel 2K4A (2DG!) Lube Oil DIESEL GENERATOR Drift does not apply to this relay as it is not a timing relay. A review of the reference 40 2 2Cl07-0P3 2K-4A Gould CAT Jl3P30 Pressure Sensing AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

EMER DIESEL 2K4A (2DG I) DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 41 2 2Cl07-SDR 2K-4A Gould CAT Jl3P30 SHUTDOWN RELAY AND AUXILIARIES drawings shows this rcJay as a control reJay without a timing function.

Erner Diesel 2K4A (2DG!) Start DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 42 2 2Cl07-SFR 2K-4A Gould CAT Jl3P30 Failure AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

DIESEL GENERATOR ANTI DIESEL GENERATOR 43 2 2K-4A-l 322DG 1 2K-4A GE 12GGP53BlA Operator Action MOTORING RELAY FOR 2A308 AND AUXILIARIES 2K-4A- DG OVERCURRENT RELAY FOR DIESEL GENERATOR 44 2 2K-4A GE 12IJCV51Al3A Operator Action 151V2DG1A 2A-308 AND AUXILIARIES Page 70 of 73

Controlled Document Arkansas Nuclear One: 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation Component Linc No. Description of Resolution Supported Supported Device Unit Relay JD Relay Description Device JD Description Manufacturer Model 2K-4A- DG OVERCURRENT RELAY FOR DIESEL GENERATOR 45 2 2K-4A GE 121JCV51Al3A Operator Action 151V2DGIB 2A-308 AND AUXILIARIES 2K-4A- DG OVERCURRENT RELAY FOR DIESEL GENERATOR 46 2 2K-4A GE 121JCV51A13A Operator Action 151V2DGIC 2A-308 AND AUXILIARIES DIESEL GEN I DIFFERENTIAL DIESEL GENERATOR 47 2 2K-4A-1872DG 1-A 2K-4A GE 12SBDI IB2A Operator Action RELAY AND AUXILIARIES DIESEL GEN I DIFFERENTIAL DIESEL GENERATOR 48 2 2K-4A-1872DGl-B 2K-4A GE 12SBDllB2A Operator Action RELAY AND AUXILIARIES DIESEL GEN I DIFFERENTIAL DIESEL GENERATOR 49 2 2K-4A-1872DG1-C 2K-4A GE 12SBD1 IB2A Operator Action RELAY AND AUXILIARIES Relay l 87X-2DG2 energizes when any of the diesel generator 2DG2 difTerential relays (2K-4B-1872DG2-A, B or C) trip. Relay has no control function or "seal in" contact, provides AUX DIFFERENTIAL RELAY FOR DIESEL GENERATOR annunciator signal only.

50 2 187X-2DG2 2K-4B Gould CAT Jl3P20 2DG2 AND AUXILIARIES When l 87X-2DG2 energizes, a normally open contact closes and sends a signal to annunciator 2Kl30 indicating there was a DIFFERENTIAL TRIP on 2EG2.

2A-408-167G2A409 DIRECTIONAL GROUND 4.16KVESF 51 2 2A-4 GE 121CC51A7A Operator Action (2A-409, 167G) OVERCT RELAY FOR ZA-409 SWITCHGEAR DIRECTIONAL OVERCURRENT 4.16KVESF 52 2 2A-409-l 67SA 2A-4 GE 121BC51E2A Operator Action RELAY FOR 2A-409 PHASE A SWITCHGEAR DIRECTIONAL OVERCURRENT 4.16KVESF 53 2 2A-409-167SB 2A-4 GE 121BC51E2A Operator Action RELAY FOR 2A-409 PHASE B SWITCHGEAR DIRECTIONAL OVERCURRENT 4.16KVESF 54 2 2A-409-167SC 2A-4 GE 121BC51E2A Operator Action RELAY FOR 2A-409 PHASE C SWITCHGEAR EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 55 2 2CI08-4A 2K-4B Gould CAT Jl3P30 drawings shows this relay as a control relay without a timing function.

START AND AUXILIARIES EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 56 2 2Cl08-4B 2K-4B Gould CAT Jl3P30 drawings shows lhis relay as a control relay without a timing function.

START AND AUXILIARIES EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drill does not apply to this relay as it is not a timing relay. A review oflhe reference 57 2 2CI08-5A 2K-4B Gould CAT Jl3P30 AUX STOPPING RELAY AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drift does not apply to this relay as it is not a timing relay. A review of the reference 58 2 2Cl08-EOR 2K-4B Gould CAT Jl3P30 ENGINE OVERSPEED TRIP AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

Page 71 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Line No. Description of Resolution Supported Supported Device Unit Relay ID Relay Description Device ID Description Manufacturer Model EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drill docs not apply to this relay as it is not a timing relay. A review of the reference 59 2 2CI08-ERA 2K-4B Gould CAT J13P30 NORMAL SPEED (8 IO RPM) AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drill docs not apply to this relay as it is not a timing relay. A review of the reference 60 2 2Cl08-ESI 2K-4B Gould CAT Jl3P30 4160V UNDERVOLTAGE AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

EMERG DIESEL 2K4B 2DG2) DIESEL GENERATOR Drift does not apply to this relay as it is not a timing relay. A review of the reference 61 2 2Cl08-ES2 2K-4B Gould CAT J13P30 4160V UNDERVOLTAGE AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drifi docs not apply to this relay as it is not a timing relay. A review of the reference 62 2 2CI08-LSA 2K-4B Gould CAT J13P30 LOW SPEED (250 RPM) AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drift does not apply to this relay as it is not a timing relay. A review of the reference 63 2 2Cl08-LSB 2K-4B Gould CAT Jl3P30 JACKET COOLANT AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 64 2 2Cl08-0PI 2K-4B Gould CAT J13P30 LUBE OIL PRESSURE SENSING AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 65 2 2Cl08-0P2 2K-4B Gould CAT J13P30 LUBE OIL PRESSURE SENSING AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 66 2 2Cl08-0P3 2K-4B Gould CAT Jl3P30 LUBE OIL PRESSURE SENSING AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 67 2 2Cl08-SDR EMERG DIESEL 2K4B (2DG2) 2K-4B Gould CAT Jl3P30 AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

EMERG DIESEL 2K4B (2DG2) DIESEL GENERATOR Drift docs not apply to this relay as it is not a timing relay. A review of the reference 68 2 2CI08-SFR 2K-4B Gould CAT J13P30 START FAILURE AND AUXILIARIES drawings shows this relay as a control relay without a timing function.

DIESEL GENERATOR ANTI DIESEL GENERATOR 69 2 2K-4B-1322DG2 2K-4B GE 12GGP53B!A Operator Action MOTORING RELAY FOR 2A408 AND AUXILIARIES 2K-4B- DG OVERCURRENT RELAY FOR DIESEL GENERATOR 70 2 2K-4B GE 121JCV51Al3A Operator Action 151V2DG2A 2A-408 AND AUXILIARIES 2K-4B- DG OVERCURRENT RELAY FOR DIESEL GENERATOR 71 2 2K-4B GE 12!JCV51Al3A Operator Action

!51V2DG2B ZA-408 AND AUXILIARIES Page 72 of73

Controlled Document Arkansas Nuclear One: 50.54(f) NTIF 2.1 Seismic High Frequency Confirmation Component Line No. Description of Resolution Supported Supported Device Unit Relay ID Relay Description Device ID Description Manufacturer Model 2K-4B- DG OVERCURRENT RELAY FOR DIESEL GENERATOR 72 2 2K-4B GE 12IJCVSIAl3A Operator Action 151V2DG2C 2A-408 AND AUXILIARIES DIESEL GEN 2 DIFFERENTIAL DIESEL GENERATOR 73 2 2K-4B-1872DG2A 2K-4B GE 12SBDllB2A Operator Action RELAY AND AUXILIARIES DIESEL GEN 2 DIFFERENTIAL DIESEL GENERATOR 74 2 2K-4B-1872DG2B 2K-4B GE 12SBDllB2A Operator Action RELAY AND AUXILIARIES DIESEL GEN 2 DIFFERENTIAL DIESEL GENERATOR 75 2 2K-4B-1872DG2C 2K-4B GE 12SBD11B2A Operator Action RELAY AND AUXiLIARIES Page 73 of73