SBK-L-17136, Seismic High Frequency Confirmation Report for the Reevaluated Seismic Hazard Information

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Seismic High Frequency Confirmation Report for the Reevaluated Seismic Hazard Information
ML17241A150
Person / Time
Site: Seabrook NextEra Energy icon.png
Issue date: 08/28/2017
From: Mccartney E
NextEra Energy Seabrook
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
SBK-L-17136
Download: ML17241A150 (47)
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NEXTera ENERGY ~

SEABROOK August 28, 2017 SBK-L-17136 Docket No. 50-443 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Seabrook Station NextEra Energy Seabrook, LLC's Seismic High Frequency Confirmation Report for the Reevaluated Seismic Hazard Information

References:

1. NRC Letter, "Request for Information Pursuant to Title lO 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 oflnsights from the Fukushima Dai-Ichi Accident," March 12, 2012, ADAMS Accession Number ML12053A340
2. EPRI 3002004396, "High Frequency Program, Application Guidance for Functional Confirmation and Fragility Evaluation," July 2015
3. NRC Letter , "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
4. NRC Letter, "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 The NRC issued a 50.54(f) letter on March 12, 2012 [1], requesting information to assure that recommendations from the Fukushima Near-Term Task Force (NTTF) are addressed by all U.S . nuclear power plants. The 50.54(f) 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(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."

NextEra Energy Seabrook, LLC PO Box 300, Seabrook, NH 03874

U.S. Nuclear Regulatory Commission SBK-L-17136/Page 2 Subsequent guidance for performing a High Frequency Confirmation was provided by EPRI in Reference 2, and was endorsed by the NRC in Reference 3. Final screening identifying plants needing to perform a High Frequency Confirmation, including Seabrook Station, was provided by the NRC in Reference 4.

The enclosure to this letter describes the High Frequency Confirmation evaluation undertaken for Seabrook Station. 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 the NRC to understand the inputs used, the evaluations performed, and the decisions made as a result of the evaluations.

This letter contains no new regulatory commitments.

Should you have any questions concerning this submittal, please contact Mr. Kenneth Browne, Licensing Manager, at (603) 773-7932.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on August lB , 2017.

Sincerely, NextEra Energy Seabrook, LLC orthem Region Enclosure cc: D. Dorman, NRC Region I Administrator J. Poole, NRC Project Manager, Project Directorate 1-2 P. Cataldo, NRC Senior Resident Inspector Director, Office of Nuclear Reactor Regulation Mr. Eric E. Bowman, NRR/JLD/PPSD/HMB Mr. Perry Plummer Director Homeland Security and Emergency Management New Hampshire Department of Safety Division of Homeland Security and Emergency Management Bureau of Emergency Management

U.S. Nuclear Regulatory Commission SBK-L-17136/Page 3.

33 Hazen Drive Concord, NH 03305 perry.plummer@dos.nh.gov Mr. John Giarrusso, Jr., Nuclear Preparedness Manager The Commonwealth of Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399 John. Giarrusso@massmail.state.ma. us

Enclosure to Letter SBK-L-17136 NextEra Energy Seabrook, LLC Seabrook Station Seismic High Frequency Confirmation

Seabrook Station Seismic High Frequency Confirmation Executive Summary 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 [1]. In particular, this report provides information requested to address the High Frequency Confirmation requirements of Item (4), Enclosure 1, Recommendation 2.1: Seismic, of the March 12, 2012 letter [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 (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 50.54(f) letter requests that licensees and holders of construction permits under 10 CFR Part 50 reevaluate the seismic hazards at their sites against present-day NRC requirements and guidance. 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" [6]

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 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,"

[8] and was endorsed by the NRC in a letter dated September 17, 2015 [3]. Final screening identifying plants needing to perform a High Frequency Confirmation was provided by NRC in a letter dated October 27, 2015 [2].

This report describes the High Frequency Confirmation evaluation undertaken for Seabrook Station.

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 [8] is used for the Seabrook Station engineering evaluations described in this report.

In accordance with Reference [8], 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
  • Estimation 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 evaluations Page 1of43

Seabrook Station 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 50.54(f) letter requests that licensees and holders of construction permits under 10 CFR Part 50 reevaluate the seismic hazards at their sites against present-day NRC requirements and guidance. 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" [6]

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," [8] and was endorsed by the NRC in a letter dated September 17, 2015 [3].

Final screening identifying plants needing to perform a High Frequency Confirmation was provided by NRC in a letter dated October 27, 2015 [2].

On March 27, 2014, Seabrook Station submitted a reevaluated seismic hazard to the NRC as a part of the Seismic Hazard and Screening Report [4]. By letter dated October 27, 2015 [2], 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 Seabrook Station using the methodologies in EPRI 3002004396, "High Frequency Program, Application Guidance for Functional Confirmation and Fragility Evaluation," as endorsed by the NRC in a letter dated September 17, 2015 [3].

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 Page 2 of 43

Seabrook Station Seismic High Frequency Confirmation result of the evaluations.

1.3 APPROACH EPRI 3002004396 [8] is used for the Seabrook Station engineering evaluations described in this report. Section 4.1 of Reference [8] provided general steps to follow for the high frequency confirmation component evaluation. Accordingly, the following topics are addressed in the subsequent sections of this report:

  • Seabrook Station's 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 Seabrook Station submitted reevaluated seismic hazard information including GMRS and seismic hazard information to the NRC on March 27, 2014 [4]. In a letter dated August 12, 2015, the NRC staff concluded that the submitted GMRS adequately characterizes the reevaluated seismic hazard for the Seabrook Station site [12].

The NRC final screening determination letter concluded [2] that the Seabrook Station GMRS to SSE comparison resulted in a need to perform a High Frequency Confirmation in accordance with the screening criteria in the SPID [6].

Page 3 of 43

Seabrook Station 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 [8], 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 (AC/DC power support systems).

Within the applicable functions, the components that would need a high frequency confirmation are contact control devices subject to intermittent states in seal-in or lockout circuits. Accordingly, the objective of the review as stated in Section 4.2.1 of Reference [8] is to determine if seismic induced high frequency relay chatter would prevent the completion of the following key functions.

The information presented in this Section along with the extensive list" of references used in the selection process is provided by Reference [13].

2.1 REACTOR TRIP/SCRAM The reactor trip/SCRAM function is identified as a key function in Reference [8] to be considered in the High Frequency Confirmation. The same report also states that "the design requirements preclude the application of seal-in or lockout circuits that prevent reactor trip/SCRAM functions" and that "No high-frequency review of the reactor trip/SCRAM systems is necessary."

2.2 REACTOR VESSEL INVENTORY CONTROL The reactor coolant system/reactor vessel inventory control systems were reviewed for contact control devices in seal-in and lockout (SILO) circuits that would create a Loss of Coolant Accident (LOCA). The focus of the review was contact control devices that could lead to a significant leak path. Check valves in series with active valves would prevent significant leaks due to mis-operation of the active valve; therefore, SILO circuit reviews were not required for those active valves.

After review of the piping systems attached to the Reactor Coolant System (RCS), all active isolation valves and any upstream or downstream active valves required to be closed are included. The following components were selected as part of the inventory selection:

Letdown Isolation Valve 1-RC-LCV-460, 1-RC-V-81 Normally-open motor-operated valve 1-RC-V-81 is controlled by hand switches only. Open limit switches in the opening circuit prevent seal-in of the opening contactor auxiliary contact and no contacts prevent valve closure via the control switch. However, this requires operator actions and meets the selections criteria. Valve 1-RC-LCV-460 will be evaluated for potentially not meeting the selection criteria.

Electrical control for the normally-open solenoid-operated pilot valves is through the pressurizer level relay LY-460-DXl and rugged control and limit switches. No device would prevent valve closure either via the hand switch or pressurizer level relay signal. Thus, no devices meet the selection criteria.

Page 4 of 43

Seabrook Station Seismic High Frequency Confirmation Excess Letdown Isolation Valves 1-CS-V-175, 1-CS-V-176 Electrical control for the solenoid-operated pilot valves is via a rugged hand control switch only.

There are no chatter sensitive contact devices involved in the control of these valves. Valve 1-CS-V-176 was screened out based on the results of the evaluation of 1-CS-V-175.

Reactor Head Vent Isolation Valve 1-RC-FV-2881, 1-RC-V-323 Electrical control for the solenoid-operated pilot valve, 1-RC-FV-2881, is via a rugged hand control switch only. There are no chatter sensitive contact devices involved in the control of these valves.

Based on the results of the evaluation of 1-RC-FV-2881, Valve 1-RC-V-323 does not meet the selection criteria.

Reactor Cooling Pressure Operated Relief Valves 1-RC-PCV-456A, 1-RC-PCV-4568 Valve 1-RC-PCV-456A and 1-RC-PCV-456B are normally-closed solenoid operated valves and controlled by relays TY-413KX, PY-405CX, PY-455EX, PY-458BX, KA7. Chatter to these devices could spuriously energize the 42 relay and result in energizing the solenoid that would open the valve.

However, because there are no SILO devices the valve will return to its original position the valves and thus do not meet the selection criteria.

2.3 REACTOR VESSEL PRESSURE CONTROL The reactor vessel pressure control function is identified as a key function in Reference [8] to be considered in the High Frequency Confirmation. The same report also states that "required post event pressure control is typically provided by passive devices" and that "no specific high frequency component chatter review is required for this function."

2.4 CORE COOLING The core cooling systems were reviewed for contact control devices in seal-in and lockout circuits that would prevent at least a single train of non-AC power driven decay heat removal from functioning.

The steam Turbine-Driven Auxiliary Feedwater (TDAFW) pump was the train chosen for this analysis. The selection of contact devices for TDAFW was based on the premise that pump operation is desired, thus any SILO which would lead to pump operation is desirable and for this reason does not meet the selection criteria. Only Contact devices which could render the TDAFW system inoperative were considered.

The piping systems attached to the Feed Water (FW) is reviewed. The throttle and isolation valves and any active second valve upstream or downstream required to maintain the flow to the steam generators are included. The following components were selected as part of the inventory selection:

Emergency Feedwater Pump Steam Supply Valves 1-MS-V-393, 1-MS-V-394, 1-MS-V-395 Initiation of the TDAFW is via the opening of main steam valves 1-MS-V-393, 1-MS-V-394, and 1-MS-V-395. These normally-closed solenoid-operated pilot valves open on the following signals; 2 out of 4 low-low indication in any steam generator, safety injection signal, loss of offsite power, or AMS (ATWS Mitigation System). Chatter in the control would only open the valve, which is desired.

No vulnerable device has the potential to prevent valve opening and thus none of these valves meet the selection criteria.

Page 5 of 43

Seabrook Station Seismic High Frequency Confirmation Emergency Feedwater Valve 1-FW-FV-4214A/B, 1-FW-FV-4224A/B, 1-FW-FV-4234A/B, 1-FWFV-4244A/B To ensure proper flow of Auxiliary Feedwater, normally-open motor-operated discharge valves 1-FW-FV-4214A/B, 1-FW-FV-4224A/B, 1-FW-FV-4234A/B, 1-FW-FV-4244A/B were analyzed.

Chatter in the opening circuit is blocked by open rugged limit and control switches. Chatter in the closing circuit could spuriously energize the motor starter to the closing position. This spurious energization could be achieved via two separate paths. The first path requires 42/C and 4214-AX contacts to chatter in unison and the second path requires only Rl contacts to chatter. Relays and contacts that could spuriously energize Rl Relay have also been evaluated. If path one or two were to energize the 42#4-AX relay this would lead to MS0-1 spuriously energizing and providing a path to energize the 42/C relay. Energizing 42/C would result in a SILO ofthese valves in the undesired position. These relays meet the selection criteria for the high frequency program.

Emergency Feedwater Recirc Valve 1-FW-V-346 To maintain min flow requirements to the Auxiliary Feedwater, normally-closed motor-operated valve 1-FW-V-346 was analyzed. Valve position is controlled by rugged hand and limit switches.

Thus, this device does not meet the selection criteria.

2.5 AC/DC POWER SUPPORT SYSTEMS The AC and DC power support systems were reviewed for contact control devices in seal-in and lockout circuits that prevent the availability of DC and AC power sources. The following AC and DC power support systems were reviewed:

  • Battery Chargers,
  • Inverters - UPS,
  • EDG Ancillary systems
  • Switchgear, load centers, and MCCs Electrical power, especially DC, is necessary to support achieving and maintaining a stable plant condition following a seismic event. DC power relies on the availability of AC power to recharge the batteries. The availability of AC power is dependent upon the Emergency Diesel Generators and their ancillary support systems. EPRI 3002004396 requires confirmation that the supply of emergency power is not challenged by a SILO device. The tripping of lockout devices or circuit breakers is expected to require some level of diagnosis to determine if the trip diagnose the fault condition could substantially delay the restoration of emergency power.

In order to ensure contact chatter cannot compromise the emergency power system, control circuits were analyzed for the Emergency Diesel Generators (EDG), Battery Chargers, Vital AC Inverters, and Switchgear/Load Centers/MCCs as necessary to distribute power from the EDGs to the Battery Chargers and EDG Ancillary Systems. General information on the arrangement of safety-related AC and DC systems, as well as operation of the EDGs, was obtained from Seabrook Station UFSAR. Seabrook Station EDGs provide emergency power for the units. Seabrook Station is a single unit plant and it has two (2) divisions of Class lE loads with one EDG for each division.

The analysis necessary to identify contact devices in this category relies on conservative worst-case initial conditions and presumptions regarding event progression. The analysis considers the reactor is operating at power with no equipment failures or LOCA prior to the seismic event. The Page 6 of 43

Seabrook Station Seismic High Frequency Confirmation Emergency Diesel Generators are not operating but are available. The seismic event is presumed to cause a Loss of Offsite Power (LOOP) and a normal reactor SCRAM.

In response to bus under-voltage relaying detecting the LOOP, the Class 1E control systems must automatically shed loads, start the EDGs, and sequentially load the diesel generators as designed.

Ancillary systems required for EDG operation as well as Class 1E battery chargers and inverters must function as necessary. The goal of this analysis is to identify any vulnerable contact devices which could chatter during the seismic event, seal-in or lock-out, and prevent these systems from performing their intended safety-related function of supplying electrical power during the LOOP.

The following sections contain a description of the analysis for each element of the AC/DC Support Systems. Contact devices are identified by description and device ID. The selected contact devices for both divisions are presented in Attachment B.

Emergencv Diesel Generators The analysis of the Emergency Diesel Generators is broken down into the generator protective relaying and diesel engine control. General descriptions of these systems and controls appear in the UFSAR. The control and protective circuits for the diesel generator function differently depending on whether the diesel is stopped (immediately prior to starting), starting automatically in response to a loss of bus voltage (emergency start), or manually started (with offsite power available). Only two of these states are considered possible during the period of strong shaking, stopped prior to starting and automatically started. It is expected that under degraded voltage conditions the normal power feeder breakers would be tripped manually or automatically via the degraded voltage relaying (analyzed herein), and the diesel generator would start automatically on the loss of voltage on the bus. Manual starting during strong shaking (as only a precaution in cases where offsite power has not been effected) is not considered in this analysis.

Generator Protective Relaying The control circuits for the A54 (EDG-1A) and A74 (EDG-1B) diesel generator circuit breakers include circuit breaker lockout relays. The circuit breaker lockout relays are LOR lockout relays manufactured by Electro Switch. EPRI tested LOR/ER type lockout relays and determined that these type of lockout relays are rugged with no ability to chatter. Thus, based on the tested document under EPRI 3002002997 the Electro Switch LOR lockout relays are considered rugged. However, in the event a relay becomes energized it would trip and lock out the breaker until operator actions are taken. Chatter to the below devices could energize the breaker lockout relays and meet the criteria for selection.

  • 51V/A/B/C (A54)
  • 40
  • 51B/A/B/C (AS4)
  • 51A/B/C (A51)
  • 52S
  • 51A/B/C (A52)
  • 51V/A/B/C (A74)
  • 51A/B/C (A71)
  • 51B/A/B/C (A74)
  • 51A/B/C (A72)
  • 32
  • 40X Due to anti-pump function of the breaker, the 52Y relay could prevent automatic reclosure, and for this reason, devices that could energize the 52Y device due to chatter meet the criteria for selection. Such said devices are listed below. Also, devices that could energize the trip coil while Page 7 of 43

Seabrook Station Seismic High Frequency Confirmation S2Y is simultaneous energized were considered to meet the criteria for selection and are listed below.

  • 81Y
  • S2Y
  • PRlX
  • R43R3
  • K601A
  • RS
  • S2S In addition, the medium voltage circuit breakers associated with the generators are vulnerable and could trip during a seismic event.

Diesel Engine Control Chatter analysis for the diesel engine control was performed on the start and shutdown circuits of each EDG. For EDG-lA/B, chatter that could prevent the auto start or cause the EDG to shut down were determined to be meet the selection criteria and are listed below.

  • s
  • 4A
  • Dev-TR
  • 4B
  • OP2
  • OP3
  • ASA
  • OP4
  • ASB
  • OTH
  • CTH
  • OTH-1
  • CTH-1
  • SFR
  • EOR
  • EOS
  • T2A
  • ESl
  • T3A
  • ES2
  • TRP Load Shed and Sequencer Chatter after load shedding and during normal sequencing could lead to tripping of the nuclear EDG circuit breakers. This section evaluates loads off the 4160 Bus SE/6E that if spurious breaker closure occurred could lead to overcurrent of the EDG. Load breakers that were evaluated for this section only reviewed spurious closure of the breaker. Required loads that were evaluated for spurious breaker opening are documented in their respective sections below, cooling water and section 6.S.6 of Reference [13]. Load breakers that were evaluated in section 6.S.2 of Reference [13]

include required loads ASS, A63, A7S, A83, AR3, AR4, AQ3, AQ4 and unrequired loads AS6, AS7, AS8,AS9,ASA,A60,A61,A62,A76,A77,A78,A79,A7A,A80,A81,A82,A90,A93,AU2,AU6,AU7, and AV4. The following devices could lead to spurious breaker closure and overloading of the EDGs and therefore meet the selection criteria for inclusion in the high frequency program.

  • K644A
  • S2S
  • LR8 (K84)
  • K640B
  • PRl (K7, KlO)
  • K61SB
  • PRl (K8, KlO)
  • KA24
  • K601A
  • EPS-PRl (K7)
  • PRl (K7)
  • RTB
  • K616A
  • HR8 (K83)

Page 8 of 43

Seabrook Station Seismic High Frequency Confirmation

  • R2X (K73)
  • R4
  • K610B
  • RTA
  • K610A
  • K616B
  • K601B
  • Rl
  • PSSX EOG Ancillary Systems In order to start and operate the Emergency Diesel Generators require a number of components and systems. For the purpose of identifying electrical contact devices, only systems and components which are electrically controlled are analyzed. Information in the UFSAR was used as appropriate for this analysis.

Starting Air Based on Diesel Generator availability as an initial condition, the passive air reservoirs are presumed pressurized with sufficient volume to provide five successful engine starts. The only active components in this system required to operate are the air start solenoids. Seal in of devices 4A and 4B, captured in section 6.5.1 of Reference [13], could energize the solenoid operated air start valve, FY-AS1 and FY-AS2, and maintain them open. Chatter to the FY-SDS valve circuit would only have a temporary effect and does not meet the selection criteria.

Combustion Air Intake and Exhaust The combustion air intake and exhaust for the Diesel Generators are passive systems which do not rely on electrical control.

Lube Oil The Diesel Generators utilize engine-driven mechanical pumps and electrically controlled auxiliary pumps to supply lube oil to the engines. The engine-driven mechanical lubrication oil pumps, 1-DG-P-115A/B do not rely on electrically-powered control. Analysis of the control circuit for the prelube and auxiliary lube oil pumps, 1-DG-P-116A/B and 1-DG-P-117A/B, concluded they do not include SILO devices.

Fuel Oil The Diesel Generator Fuel Oil System is described in the Diesel Generator DBD. The Diesel Generators utilize engine-driven mechanical pumps and electrically-powered auxiliary pumps to supply fuel oil to the engines from the day tanks. The day tanks are re-supplied using Diesel Oil Transfer Pumps 1-DG-P-38A/B from the fuel storage tanks. The fuel oil header pressure is maintained by the Auxiliary Fuel Oil Pumps 1-DG-P-118A/B. Chatter analysis of the control circuits for the electrically-powered auxiliary and transfer pumps concluded they do not include SILO devices. The Fuel Oil Pumps, 1-DG-P-119A/B, are mechanical pumps which do not rely on electrical control.

Cooling Water The cooling water system consists of Jacket Water Cooler 1-DG-P-121A/B, the Air Coolant Pump 1-DG-P-231A/B, and Service Water (SW) 1-SW-P41A/B/C/D. Jacket water cools the engine cylinders, governor lube oil cooler, and turbochargers, while air coolant is used for the intercooler, outboard bearing, and lube oil cooler. Engine driven pumps operating in the jacket water and air coolant pump loop are credited when the engine is operating. These mechanical pumps do not rely on Page 9 of 43

Seabrook Station Seismic High Frequency Confirmation electrical control. The solenoid operated flow control valves, 1-DG-V-9A/B, 1-DG-V-11A/B, 1-DG-V12-A/B, and 1-DG-V13-A/B, were analyzed in section 6.5.1 of Reference [13] along with the EDG control logics. It was concluded that the flow control valves do not have any SILO devices.

Four SW pumps, 1-SW-P41A/B/C/D, provide cooling water to the heat exchangers associated with EDG-1A/B. Following load shed, these pumps are started on generator breaker closure or a safety injection signal. Chatter analysis of the generator breaker controls is included in Section 6.5.1 of Reference [13]. The low voltage circuit breakers, AR3, AR4, AQ3, and AQ4, associated with the pumps, are vulnerable and could trip during a seismic event. Chatter in the 50/51A/C overcurrent protective relays circuit could energize the 86 circuit breaker lock out relay and prevent circuit breaker closure. Overcurrent protective relay devices meet the selection criteria. Due to anti-pump function of the SW breakers, the 52Y relay could prevent automatic reclosure and for this reason, devices that could energize the 52Y device due to chatter meet the criteria for selection. Such said devices are listed below. Moreover, devices that could energize the trip coil while 52Y is simultaneously energized were considered to meet the criteria for selection and are listed below.

  • Rl
  • 94-2
  • 52Y To ensure proper flow supply from the Intake Structure to the DG heat exchangers, motor-operated discharge and supply valves 1-SW-V-2, 1-SW-V-16, 1-SW-V-18, 1-SW-V-22, 1-SW-V-29, 1-SW-V31, 1-SW-V44, 1-SW-V-46, 1-SW-V-63, and 1-SW-V-64, were analyzed. Chatter in the circuit is blocked by rugged limit, control, and torque switches and does not include SILO devices.

Ventilation Ventilation for each Diesel Generator Enclosure is provided via two supply and exhaust fans, one pair for each EDG room. In automatic mode, these fans are controlled by room temperature.

Chatter analysis of the control circuits for these fans and their associated dampers concluded they do not include SILO devices.

Battery Chargers The control circuit for the battery chargers, BC-1A/B/C/D, indicates that chatter would result in closure of the breaker. Analysis of the battery charger input power control circuit DB1, DA1, D88, and DB2 determined there are no SILO devices. Circuit analysis of the battery charger output power control circuit, DM2, DN4, DP6, DQ8, reveals that chatter to 62BLL contacts would energize the Stunt Trip Coil, 72STC, and trip the breaker. There is no auto closure function built into these breakers and reclosure after tripping would require operator actions. Thus, these devices meet the selection criteria for being included in the high frequency program.

Inverters-UPS Analysis of schematics for the UPS1-A/B/C/D breakers DR1, DN8, DP9, and DM6 revealed no vulnerable contact devices and thus chatter analysis is unnecessary.

Page 10 of 43

Seabrook Station Seismic High Frequency Confirmation Switchgear. load Centers. and MCCs Power distribution from the EDGs to the necessary electrical loads (Battery Chargers, Batteries, Inverters, Fuel Oil Pumps, Service Water Pumps, Radiator Fans, and EOG Ventilation Fans) was traced to identify any SILO devices which could lead to a circuit breaker trip and interruption in power. This effort excluded the EDG circuit breakers and the Service Water Pump circuit breakers, which are covered in separate sections, as well as component-specific contactors and their control devices, which are covered in analysis of the components.

Due to their high frequency sensitivity, the medium- and low-voltage circuit breakers in 4160V Busses and 480V Switchgear, which are supplying power to loads identified in this section, have been identified for evaluation: ASS, A63, AB2, AC2, AB6, ACS, AB6, 027, 030, A7S, A83, AD2, AE2, AES, 026, 023, DN8, DD3, DP2, ABS, A94, ADS, AX8, AX9, OMO, DB7.

The only circuit breakers affected by protective relaying (not already covered) were those that distribute power from 4160 Busses to their associated 480V stepdown transformers ASS, A63, A7S, A83. A chatter analysis of the control circuits for these circuit breakers indicates the 86 lockout and SO/Sl phase overcurrent relays could trip the circuit breaker following the seismic event.

2.6

SUMMARY

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

Page 11of43

Seabrook Station Seismic High Frequency Confirmation 3 Seismic Evaluation 3.1 HORIZONTAL SEISMIC DEMAND Per Reference [8], Sect. 4.3, the basis for calculating high-frequency seismic demand on the subject components in the horizontal direction is the Seabrook Station horizontal ground motion response spectrum (GMRS), which was generated as part of the Seabrook Station Seismic Hazard and Screening Report [4] submitted to the NRC on March 27, 2014 and accepted by the NRC on August 12, 2015 [12].

It is noted in Reference [8] 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 Ref. [8], "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." For sites founded on soil, the soil layers will shift the frequency range of seismic input towards the lower frequency range of the response spectrum by engineering judgment. Therefore, for purposes of high-frequency evaluations in this report, the GMRS is an adequate substitute for the FIRS for sites founded on soil.

The applicable buildings at Seabrook Station are founded on rock; therefore, the Control Point GMRS is representative of the input at the building foundation.

The horizontal GMRS values are provided in Table 3-1.

3.2 VERTICAL SEISMIC DEMAND As described in Section 3.2 of Reference. [8], the horizontal GMRS and site soil conditions are used to calculate the vertical GMRS (VGMRS), which is the basis for calculating high-frequency seismic demand on the subject components in the vertical direction.

The Seabrook Station soil profile is defined as a rock site. The shear wave velocity is provided in Section 2.1 of Reference [4], it is estimated between 8,000 and 10,000ft/sec.

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 [8],

Table 3-1. Based on the PGA of 0.499g and the shear wave velocity greater than 3280ft/s, the site soil class is D-Hard class.

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 [8],

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 [8], Table 3-2 values are constant between O.lHz and 15Hz.

The V/H ratios and VG MRS values are provided in Table 3-1 of this report.

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

Page 12 of 43

Seabrook Station Seismic High Frequency Confirmation Table 3-1: Horizontal and Vertical Ground Motions Response Spectra Fr~ci~~nfv <J.i~f *. *l-l~MR~(g)*.* *.s1/1f 8.at:tc> .* **vf3ooR$(gl.

0.1 0.009 0.74 0.007 0.125 0.011 0.74 0.008 0.167 0.015 0.74 0.011 0.2 0.018 0.74 0.013 0.3 0.027 0.74 0.020 0.4 0.036 0.74 0.026 0.5 0.044 0.74 0.033 0.6 0.054 0.74 0.040 0.7 0.063 0.74 0.047 0.8 0.072 0.74 0.053 0.9 0.081 0.74 0.060 1 0.089 0.74 0.066 1.25 0.118 0.74 0.087 1.5 0.147 0.74 0.109 2 0.198 0.74 0.147 2.5 0.240 0.74 0.178 3 0.291 0.74 0.215 4 0.384 0.74 0.284 5 0.469 0.74 0.347 6 0.542 0.74 0.401 7 0.609 0.74 0.451 8 0.672 0.74 0.497 9 0.730 0.74 0.540 10 0.783 0.74 0.579 12.5 0.866 0.74 0.641 15 0.927 0.74 0.686 20 1.000 0.74 0.740 25 1.040 0.74 0.770 31 1.060 0.81 0.864 35 1.060 0.87 0.922 40 1.050 0.92 0.966 45 1.020 0.97 0.989 50 0.976 0.98 0.956 60 0.853 0.99 0.844 70 0.719 0.98 0.705 80 0.611 0.93 0.568 90 0.540 0.88 0.475 100 0.499 0.85 0.424 Page 13 of 43

Seabrook Station Seismic High Frequency Confirmation 1.20 I I

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- - - GMRSH (g) - - GM RSV (g) - *- V/H Ratio 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 [8] the peak horizontal acceleration is amplified using the following two factors to determine the horizontal in-cabinet response spectrum:

  • Horizontal in-structure amplification factor AFsHto account for seismic amplification at floor elevations above the host building's foundation
  • Horizontal in-cabinet amplification factor AFc 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 [8]. The in-cabinet amplification factor, AFc is associated with a given type of cabinet construction. The three general cabinet types are identified in Reference [8] and Appendix I of EPRI NP-7148 [11] assuming 5% in-cabinet response spectrum damping. EPRI NP-7148 [11] 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 benchboard 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 [8] as follows:

  • Motor Control Centers are typical motor control center cabinets consisting of a lineup of several interconnected sections. Each section is a relatively narrow cabinet structure with Page 14 of 43

Seabrook Station Seismic High Frequency Confirmation height-to-depth ratios of about 4.5 that allow the cabinet framing to be efficiently used in flexure for the dynamic response loading, primarily in the front-to-back direction. This results in higher frame stresses and hence more damping which lowers the cabinet response. In addition, the subject components are not located on large unstiffened panels that could exhibit high local amplifications. These cabinets qualify as low amplification cabinets.

  • Switchgear cabinets are large cabinets consisting of a lineup of several interconnected sections typical of the high amplification cabinet category. Each section is a wide box-type structure with height-to-depth ratios of about 1.5 and may include wide stiffened panels.

This results in lower stresses and hence less damping which increases the enclosure response. Components can be mounted on the wide panels, which results in the higher in-cabinet amplification factors.

  • Control cabinets are in a lineup of several interconnected sections with moderate width.

Each section consists of structures with height-to-depth ratios of about 3 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.

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 AFc to account for seismic amplification within the host equipment (cabinet, switchgear, motor control center, etc.)

The in-structure amplification factor AF 5v is derived from Figure 4-4 in Reference [8]. The in-cabinet amplification factor, AFc is derived in Reference [8] and is 4.7 for all cabinet types.

Page 15 of 43

Seabrook Station Seismic High Frequency Confirmation 4 Contact Device Evaluations Per Reference [8], 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 [7], then the component seismic capacity from this program is used.

(2) If a contact device was not tested as part of [7], then one or more of the following means to determine the component capacity were used:

(a) Device-specific seismic test reports (either from the station or from the SQURTS testing program.

(b) Generic Equipment Ruggedness Spectra {GERS) capacities per [9] and [10].

(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 [8]

The selected components were divided into thirty-five (35) groups as part of the high-frequency evaluation. The definitions of these groups are based on the device type and location, enclosure type, and available documentation.

  • Group 1: Comprised of devices/components hosted in Wall Mounted Panel enclosures 1-MM-CP-914-A, 1-MM-CP-914-B. They are located in the Control Building at elevation 50 ft.

The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Fragility level in horizontal direction.

  • Group 2: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 3: Comprised of devices/components hosted in Motor Control Center enclosures 1-EDE-MCC-515, 1-EDE-MCC-615. They are located in the Control Building at elevation 21.5 ft.

The source for the component capacity is the GERS and the test criterion is defined as the Lowest level without chatter.

  • Group 4: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-11-A, 1-EDE-SWG-11-B, 1-EDE-SWG-11-C, 1-EDE-SWG-11-D. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the High Frequency Test Program and the test criterion is defined as the Test Table Capacity.
  • Group 5: Comprised of devices/components hosted in Control Panel enclosures 1-DG-CP-36, 1-DG-CP-37. They are located in the Diesel Generator Building at elevation 21.5 ft. The source for the component capacity is the GERS and the test criterion is defined as the Lowest level without chatter.
  • Group 6: Comprised of devices/components hosted in Control Panel enclosures 1-DG-CP-36, 1-DG-CP-37. They are located in the Diesel Generator Building at elevation 21.5 ft. The Page 16 of 43

Seabrook Station Seismic High Frequency Confirmation source for the component capacity is the GERS and the test criterion is defined as the Lowest level without chatter.

  • Group 7: Comprised of devices/components hosted in Control Panel enclosures 1-DG-CP-36, 1-DG-CP-37. They are located in the Diesel Generator Building at elevation 21.5 ft. The source for the component capacity is the High Frequency Test Program and the test criterion is defined as the Fragility Threshold.
  • Group 8: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the High Frequency Test Program and the test criterion is defined as the Test Table Capacity.
  • Group 9: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 10: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 11: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 12: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 13: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 14: Comprised of devices/components hosted in Control Panel enclosures 1-DG-CP-75-A, 1-DG-CP-76-A. They are located in the Diesel Generator Building at elevation 21.5 ft.

The source for the component vertical capacity is the GERS and the test criterion is defined as the Lowest level without chatter and the source for the horizontal capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).

  • Group 15: Comprised of devices/components hosted in Control Panel enclosures 1-DG-CP-36, 1-DG-CP-37. They are located in the Diesel Generator Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 16: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 17: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for Page 17 of 43

Seabrook Station Seismic High Frequency Confirmation the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).

  • Group 18: Comprised of devices/components hosted in Control Panel enclosure 1-DG-CP-
36. They are located in the Diesel Generator Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 19: Comprised of devices/components hosted in Control Panel enclosures 1-DG-CP-36, 1-DG-CP-37, 1-DG-CP-79, 1-DG-CP-80, 1-EDE-CP-248, 1-EDE-CP-249. They are located in the Diesel Generator Building at elevation 21.5 ft. The source for the component capacity is the GERS and the test criterion is defined as the Lowest level without chatter.
  • Group 20: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the GERS and the test criterion is defined as the Lowest level without chatter.
  • Group 21: Comprised of devices/components hosted in Motor Control Center enclosures 1-EDE-MCC-515, 1-EDE-MCC-615. They are located in the Control Building at elevation 21.5 ft.

The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).

  • Group 22: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 23: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 24: Comprised of devices/components hosted in Control Panel enclosures 1-MM-CP-12, 1-MM-CP-13. They are located in the Control Building at elevation 75 ft. The source for the component capacity is the Plant Document and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 25: Comprised of devices/components hosted in Control Panel enclosure 1-MM-CP-
13. It is located in the Control Building at elevation 75 ft. The source for the component capacity is the Plant Document and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 26: Not used.
  • Group 27: Comprised of devices/components hosted in Control Panel enclosures 1-DG-CP-36, 1-DG-CP-37. They are located in the Diesel Generator Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 28: Comprised of devices/components hosted in Control Panel enclosure 1-MM-CP-470. They are located in the Control Building at elevation 75 ft. The source for the component capacity is the Plant Document and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 29: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).

Page 18 of 43

Seabrook Station Seismic High Frequency Confirmation

  • Group 30: Comprised of devices/components hosted in Control Panel enclosures 1-MM-CP-297A, 1-MM-CP-297B. They are located in the Control Building at elevation 75 ft. The source for the component capacity is the Plant Document and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 31: Comprised of devices/components hosted in Control Panel enclosures 1-DG-CP-79, 1-DG-CP-80. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Document and the test criterion is defined as the Lowest level without chatter.
  • Group 32: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop ofthe Required Response Spectra (RRS).
  • Group 33: Comprised of devices/components hosted in Switchgear enclosures 1-EDE-SWG-5, 1-EDE-SWG-6. They are located in the Control Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).
  • Group 34: Comprised of devices/components hosted in Motor Control Center enclosures 1-EDE-MCC-515, 1-EDE-MCC-615. They are located in the Control Building at elevation 21.5 ft.

The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).

  • Group 35: Comprised of devices/components hosted in Control Panel enclosures 1-DG-CP-36, 1-DG-CP-37. They are located in the Diesel Generator Building at elevation 21.5 ft. The source for the component capacity is the Plant Seismic Qualification Report and the test criterion is defined as the Envelop of the Required Response Spectra (RRS).

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

Page 19 of 43

Seabrook Station Seismic High Frequency Confirmation 5 Conclusions 5.1 GENERAL CONCLUSIONS Seabrook Station 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 [8].

The evaluation identified a total of 248 components that required evaluation. As summarized in Table B-2 in Attachment B, all of the devices have adequate seismic capacity following the criteria in Section 4.6 of Reference [8].

5.2 IDENTIFICATION OF FOLLOW-UP ACTIONS As described per Section 5.1, no device requires follow up actions.

Page 20 of 43

Seabrook Station 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 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 3 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 4 Seabrook Letter SBK-L-14052, "NextEra Energy Seabrook, LLC Seismic Hazard and Screening Report (CEUS Sites) Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)

Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From the Fukushima Dai-ichi Accident", March 27, 2014, ADAMS Accession Number ML14092A413 5 EPRI 1015109. "Program on Technology Innovation: Seismic Screening of Components Sensitive to High-Frequency Vibratory Motions." October 2007 6 EPRI 1025287. "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1:

Seismic." February 2013 7 EPRI 3002002997. "High Frequency Program: High Frequency Testing Summary." September 2014 8 EPRI 3002004396. "High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation." July 2015 9 EPRI NP-7147-SL. "Seismic Ruggedness of Relays." August 1991 10 EPRI NP-7147 SQUG Advisory 2004-02. "Relay GERS Corrections." September 10, 2004 11 Procedure for Evaluating Nuclear Power Plant Relay Seismic Functionality EPRI, Palo Alto, CA:1990. NP-7148 12 NRC (F. Vega) Letter to Next Era Energy Seabrook (D. Curtland), "Seabrook Station, Unit 1- Staff Assessment of Information Provided 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-ichlAccident (TAC NO. MF3921)", August 12, 2015, ADAMS Accession Number ML15208A049 13 Seabrook Document FP101174 (JENSEN HUGHES Report 1TCR27123-SQ-RPT-002 Revision O),

"Selection of Relays and Switches for High Frequency Seismic Evaluation and Seabrook Nuclear Station", Revision 0 14 Seabrook Document FP101172 (JENSEN HUGHES Report 1TCR27123-SQ-CAL-006 Revision O),

"NTIF Recommendation 2.1 High Frequency Confirmation", Revision 0 Page 21of43

Seabrook Station Seismic High Frequency Confirmation Attachment A Representative Sample Component Evaluations For additional details regarding used references and detailed methodology, please see Reference 14.

Group Number 8 Manufacturer ELECTROSWITCH Model Number LOR/ER 1-EDE-SWG-5, 1-EDE-SWG-Enclosure ID 6

Enclosure Type Switchgear Building Control Building Floor Elevation (ft) 21.5 Building Foundation Elevation (ft) 21.5 High Frequency Test Test Source Pro ram Test Result Test Table Capacity Multi-Axis motion? No Component Capacity, SA*Horizontal (g) 22.6 Component Capacity, SA*vertical (g) 22.6 Reference EPRI 3002002997 Best Estimate of the Actual Malfunction Threshold, SAT-Horizontal (g) 23.225 Best Estimate of the Actual Malfunction Threshold, SAT-Vertical (g) 23.225 CDFM Knockdown Factor, FK 1.110 Multi-Axis to Single-Axis Correction Factor (CDFM), FMs 1.200 Effective Wide-Band Component Capacity, TRSHorizontal (g) 25.108 Effective Wide-Band Component Capacity, TRSvertica1 (g) 25.108 Spectral Acceleration - GMRS, SAGMRSH (g) 1.060 Structural Amplification Factor in the Horizontal Direction (CDFM), AFsH 1.200 Cabinet Amplification Factor in the Horizontal Direction (CDFM), AFcH 7.200 In-Cabinet Response Spectra in the Horizontal Direction (CDFM), ICRScH 9.158 (g)

Vertical Spectral Acceleration - GMRS, SAGMRsv (g) 0.966 Structural Amplification Factor in the Vertical Direction (CDFM), AFsv 1.000 Cabinet Amplification Factor in the Vertical Direction (CDFM), AFcv 4.700 In-Cabinet Response Spectra in the Vertical Direction (CDFM), ICRScv (g) 4.540 EPRI High Frequency Horizontal Seismic Margin, TRSHorizontal I ICRScH 2.742 EPRI High Frequency Vertical Seismic Margin, TRSvertical I ICRScv 5.530 Page 22 of 43

Seabrook Station Seismic High Frequency Confirmation Group Number 19 Manufacturer ITE Model Number J13 1-DG-CP-36, 1-DG-CP-37, 1-Enclosure ID DG-CP-79, 1-DG-CP-80, 1-EDE-CP-248, 1-EDE-CP-249 Enclosure Type Control Panel Building Diesel Generator Building Floor Elevation (ft) 21.5 Building Foundation Elevation (ft) 21.5 Test Source GERS Test Result Lowest level without chatter Multi-Axis motion? Yes Component Capacity, SA*Horizonta1 (g) 14.200 Component Capacity, SA*vertical (g) 14.200 Reference SQUG Advisory 2004-02 Best Estimate of the Actual Malfunction Threshold, SAT-Horizontal (g) 14.200 Best Estimate of the Actual Malfunction Threshold, SAT-Vertical (g) 14.200 CDFM Knockdown Factor, FK 1.500 Multi-Axis to Single-Axis Correction Factor (CDFM), FMs 1.000 Effective Wide-Band Component Capacity, TRSHorizonta1 (g) 9.467 Effective Wide-Band Component Capacity, TRSvertica1 (g) 9.467 Spectral Acceleration - GMRS, SAGMRSH (g) 1.060 Structural Amplification Factor in the Horizontal Direction (CDFM), AFsH 1.200 Cabinet Amplification Factor in the Horizontal Direction (CDFM), AFcH 4.500 In-Cabinet Response Spectra in the Horizontal Direction (CDFM), ICRScH 5.724 (g)

Vertical Spectral Acceleration - GMRS, SAGMRsv (g) 0.966 Structural Amplification Factor in the Vertical Direction (CDFM), AFsv 1.000 Cabinet Amplification Factor in the Vertical Direction (CDFM), AFcv 4.700 In-Cabinet Response Spectra in the Vertical Direction (CDFM), ICRScv (g) 4.540 EPRI High Frequency Horizontal Seismic Margin, TRSHorizontal / ICRScH 1.654 EPRI High Frequency Vertical Seismic Margin, TRSvertical / ICRScv 2.085 Page 23 of 43

Seabrook Station Seismic High Frequency Confirmation Attachment B Components Identified for High Frequency Confirmation Page 24 of 43

Seabrook Station Seismic High Frequency Confirmation Table B-1: Components Identified for High Frequency Confirmation Component Enclosure Floor Component Evaluation Device System Elev.

No Unit ID ID Contacts TYne Function Manufacturer Model No. ID Type Bldg. rft1 Gr. Basis for Ca pacitv Result 1-FW- Motor FV- Motor Core 1-EDE-MCC- Control Plant Seismic Capacity>

1 1 4224-A 42/C 42/C Starter Cooling 515 Center CB 21.5 34 Qualification Renart Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

2 1 4224-A 4224AX A2Y, A2X Relay Cooling AB P400Al 914A Panel CB 50 1 Qualification Renart Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

3 1 4224-A 4224AX A3Y,A3X Relay Cooling AB P400Al 914A Panel CB 50 1 Qualification Renart Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

4 1 4224-A MS0-2 A2Y, A2X Relay Cooling AB P400A1 914A Panel CB 50 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

5 1 4224-A R2A AlX, AlY Relay Cooling AB P400A1 914A Panel CB 50 1 Qualification Report Demand 1-FW-FV- 1-FYY- Auxiliary Core 1-MM-CP- Control Capacity>

6 1 4224-A 4224-4 39, 41 Relay Cooling Westinghouse NASl 297A Panel CB 75 30 Plant Document Demand 1-FW- Motor FV- Time Delay Core 1-EDE-MCC- Control Capacity>

7 1 4224-A 62-2 1, 5; 2, 6 Relay Cooling AGASTAT E7012AA 515 Center CB 21.5 3 GERS Demand 1-FW- Motor FV- Auxiliary Core 1-EDE-MCC- Control Plant Seismic Capacity>

8 1 4224-A R2 lT,1 Relav Cooling lTE 110 515 Center CB 21.5 21 Qualification Report Demand 1-FW- Motor FV- Motor Core 1-EDE-MCC- Control Plant Seismic Capacity>

9 1 4224-B 42/C 42/C Starter Cooling 615 Center CB 21.5 34 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

10 1 4224-B 4224 BX A2Y,A2X Rel av Cooling AB P400A1 914B Panel CB 50 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

11 1 4224-B 4224 BX A3Y, A3X Relay Cooling AB P400Al 914B Panel CB 50 1 Qualification Renart Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

12 1 4224-B MS0-2 A2Y, A2X Relay Cooling AB P400Al 914B Panel CB 50 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

13 1 4224-B R2B A41,A1Y Relay Cooling AB P400Al 914B Panel CB 50 1 Qualification Report Demand 1-FW-FV- 1-FYY- Auxiliary Core 1-MM-CP- Control Capacity>

14 1 4224-B 4224-2 39,41 Relay Cooling Westinghouse NASl 297B Panel CB 75 30 Plant Document Demand 1-FW- Motor FV- Time Delay Core 1-EDE-MCC- Control Capacity>

15 1 4224-B 62-2 1, 5; 2, 6 Relay Cooling AGASTAT E7012AA 615 Center CB 21.5 3 GERS Demand 1-FW- Motor FV- Auxiliary Core 1-EDE-MCC- Control Plant Seismic Capacity>

16 1 4224-B R2 lT, 1 Relay Cooling lTE )10 615 Center CB 21.5 21 Qualification Report Demand 1-FW- Motor FV- Motor Core 1-EDE-MCC- Control Plant Seismic Capacity>

17 1 4214-A 42/C 42/C Starter Cooling 515 Center CB 21.5 34 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

18 1 4214-A 4214AX A2Y,A2X Relay Cooling AB P400A1 914A Panel CB 50 1 Qualification Report Demand Page 25 of 43

Seabrook Station Seismic High Frequency Confirmation Comoonent Enclosure Floor Comoonent Evaluation Device System Elev.

No Unit ID ID Contacts Tyoe Function Manufacturer Model No. ID Type Bldg. (ft) Gr. Basis for Capacitv Result 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

19 1 4214-A 4214AX A3Y,A3X Relay Cooling AB P400A1 914A Panel CB so 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

20 1 4214-A MSQ-1 A2Y,A2X Relay Cooling AB P400A1 914A Panel CB so 1 Qualification Reoort Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

21 1 4214-A R2A A4X,A4Y Relay Cooling AB P400A1 914A Panel CB so 1 Qualification Report Demand 1-FW-FV- 1-FYY- Auxiliary Core 1-MM-CP- Control Capacity>

22 1 4214-A 4214-2 39,41 Relay Cooling Westinghouse NAS1 297A Panel CB 7S 30 Plant Document Demand 1-FW- Motor FV- Time Delay Core 1-EDE-MCC- Control Capacity>

23 1 4214-A 62-1 1, S; 2, 6 Relay Cooling AGASTAT E7012AA SlS Center CB 21.S 3 GERS Demand 1-FW- Motor FV- Auxiliary Core 1-EDE-MCC- Control Plant Seismic Capacity>

24 1 4214-A Rl 1T,1 Relay Cooling lTE 110 SlS Center CB 21.S 21 Qualification Reoort Demand 1-FW- Motor FV- Motor Core 1-EDE-MCC- Control Plant Seismic Capacity>

2S 1 4214-B 42/C 42/C Starter Cooling 61S Center CB 21.5 34 Qualification Reoort Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

26 1 4214-B 4214 BX A2Y,A2X Relay Cooling AB P400A1 914B Panel CB so 1 Qualification Reoort Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

27 1 4214-B 4214 BX A3Y,A3X Relay Cooling AB P400A1 914B Panel CB so 1 Qualification Reoort Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

28 1 4214-B MSQ-1 A2Y,A2X Relay Cooling AB P400A1 914B Panel CB so 1 Qualification Reoort Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

29 1 4214-B RlB A4X,A4Y Relav Coolin" AB P400A1 914B Panel CB so 1 Qualification Report Demand 1-FW-FV- 1-FYY- Auxiliary Core 1-MM-CP- Control Capacity>

30 1 4214-B 4214-4 39,41 Relay Cooling Westinghouse NAS1 297B Panel CB 7S 30 Plant Document Demand 1-FW- Motor FV- Time Delay Core 1-EDE-MCC- Control Capacity>

31 1 4214-B 62-1 1, S; 2, 6 Relay Cooling AGASTAT E7012AA 61S Center CB 21.S 3 GERS Demand 1-FW- Motor FV- Auxiliary Core 1-EDE-MCC- Control Plant Seismic Capacity>

32 1 4214-B Rl 1T, 1 Relay Cooling  !TE 110 61S Center CB 21.S 21 Qualification Reoort Demand 1-FW- Motor FV- Motor Core 1-EDE-MCC- Control Plant Seismic Capacity>

33 1 4244-A 42/C 42/C Starter Cooling SlS Center CB 21.5 34 Qualification Reoort Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

34 1 4244-A 4244AX A2Y,A2X Relay Cooling AB P400A1 914A Panel CB so 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

3S 1 4244-A 4244AX A3Y,A3X Rel av Cooling AB P400A1 914A Panel CB so 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

36 1 4244-A MSQ-4 A2Y,A2X Relav Coolin" AB P400A1 914A Panel CB so 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

37 1 4244-A R4A A1X,A1Y Relav Cooling AB P400A1 914A Panel CB so 1 Qualification Report Demand Page 26 of 43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Component Evaluation Device System Elev.

No Unit ID ID Contacts Tvne Function Manufacturer Model No. ID Tvpe Bld!r. (ft) Gr. Basis for Capacitv Result 1-FW-FV- 1-FYY- Auxiliary Core 1-MM-CP- Control Capacity>

38 1 4244-A 4244-4 39, 41 Relay Cooling Westinghouse NASl 297A Panel CB 7S 30 Plant Document Demand 1-FW- Motor FV- Time Delay Core 1-EDE-MCC- Control Capacity>

39 1 4244-A 62-4 1, S; 2, 6 Relay Cooling AGASTAT E7012AA SlS Center CB 21.S 3 GERS Demand 1-FW- Motor FV- Auxiliary Core 1-EDE-MCC- Control Plant Seismic Capacity>

40 1 4244-A R4 lT, 1 Relay Cooling  !TE )10 SlS Center CB 21.S 21 Qualification Renart Demand 1-FW- Motor FV- Motor Core 1-EDE-MCC- Control Plant Seismic Capacity>

41 1 4244-B 42/C 42/C Starter Cooling 61S Center CB 21.S 34 Qualification Renart Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

42 1 4244-B 4244 BX A2Y,A2X Relay Cooling AB P400Al 914B Panel CB so 1 Qualification Renart Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

43 1 4244-B 4244 BX A3Y,A3X Relay Cooling AB P400Al 914B Panel CB so 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

44 1 4244-B MSQ-4 A2Y,A2X Relay Cooling AB P400Al 914B Panel CB so 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

4S 1 4244-B R4B AlX,AlY Relay Cooling AB P400Al 914B Panel CB so 1 Qualification Report Demand 1-FW-FV- 1-FYY- Auxiliary Core 1-MM-CP- Control Capacity>

46 1 4244-B 4244-2 39,41 Relay Cooling Westinghouse NASl 297B Panel CB 7S 30 Plant Document Demand 1-FW- Motor FV- Time Delay Core 1-EDE-MCC- Control Capacity>

47 1 4244-B 62-4 1, S; 2,6 Relay Cooling AGASTAT E7012AA 61S Center CB 21.S 3 GERS Demand 1-FW- Motor FV- Auxiliary Core 1-EDE-MCC- Control Plant Seismic Capacity>

48 1 4244-B R4 lT, 1 Relay Cooling  !TE )10 61S Center CB 21.S 21 Qualification Report Demand 1-FW- Motor FV- Motor Core 1-EDE-MCC- Control Plant Seismic Capacity>

49 1 4234-A 42/C 42/C Starter Cooling SlS Center CB 21.S 34 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

so 1 4234-A 4234AX A2Y,A2X Relay Cooline: AB P400Al 914A Panel CB so 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

Sl 1 4234-A 4234AX A3Y,A3X Relay Cooling AB P400Al 914A Panel CB so 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

S2 1 4234-A MSQ-3 A2Y,A2X Relay Cooling AB P400Al 914A Panel CB so 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

S3 1 4234-A R3A A4X,A4Y Relay Cooling AB P400Al 914A Panel CB so 1 Qualification Report Demand 1-FW-FV- 1-FYY- Auxiliary Core 1-MM-CP- Control Capacity>

S4 1 4234-A 4234-2 39,41 Relay Cooling Westinghouse NASl 297A Panel CB 7S 30 Plant Document Demand 1-FW- Motor FV- Time Delay Core 1-EDE-MCC- Control Capacity>

SS 1 4234-A 62-3 1, S; 2, 6 Relay Cooling AGASTAT E7012AA SlS Center CB 21.S 3 GERS Demand 1-FW- Motor FV- Auxiliary Core 1-EDE-MCC- Control Plant Seismic Capacity>

S6 1 4234-A R3 lT,1 Relav Coo line:  !TE )10 SlS Center CB 21.S 21 Qualification Report Demand Page 27 of 43

Seabrook Station Seismic High Frequency Confirmation Comoonent Enclosure Floor Comoonent Evaluation Device System Elev.

No Unit ID ID Contacts Type Function Manufacturer Model No. ID Tvoe Bid!!. fft) Gr. Basis for Caoacitv Result 1-FW- Motor FV- Motor Core 1-EDE-MCC- Control Plant Seismic Capacity>

57 1 4234-B 42/C 42/C Starter Cooling 615 Center CB 21.5 34 Qualification Reoort Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

58 1 4234-B 4234 BX A2Y,A2X Relay Cooling AB P400A1 914B Panel CB 50 1 Qualification Reoort Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

59 1 4234-B 4234 BX A3Y,A3X Relay Cooling AB P400A1 914B Panel CB 50 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

60 1 4234-B MSQ-3 A2Y,A2X Relay Cooling AB P400A1 914B Panel CB 50 1 Qualification Report Demand 1-FW-FV- Auxiliary Core 700- 1-MM-CP- Control Plant Seismic Capacity>

61 1 4234-B R3B A4X,A4Y Relay Cooling AB P400A1 914B Panel CB 50 1 Qualification Report Demand 1-FW-FV- 1-FYY- Auxiliary Core 1-MM-CP- Control Capacity>

62 1 4234-B 4234-4 39,41 Relay Cooling Westinghouse NASl 297B Panel CB 75 30 Plant Document Demand 1-FW- Motor FV- Time Delay Core 1-EDE-MCC- Control Capacity>

63 1 4234-B 62-3 1, 5; 2, 6 Relay Cooling AGASTAT E7012AA 615 Center CB 21.5 3 GERS Demand 1-FW- Motor FV- Auxiliary Core 1-EDE-MCC- Control Plant Seismic Capacity>

64 1 4234-B R3 lT,1 Relay Cooling  !TE 110 615 Center CB 21.5 21 Qualification Report Demand AC/DC Inst & Time Power 50/518 Qvercurrent Support General 121AC53BB 1-EDE-SWG- Plant Seismic Capacity>

65 1 A63 Q>A 50; 51; SI Relay Svstems Electric 11A 5 Switchg:ear CB 21.5 10 Qualification Reoort Demand AC/DC Inst&Time Power 50/518 Qvercurrent Support General 12IAC53BB 1-EDE-SWG- Plant Seismic Capacity>

66 1 A63 d>B 50; 51; SI Relay Systems Electric llA 5 Switchgear CB 21.5 10 Qualification Reoort Demand AC/DC Inst & Time Power 50/518 Qvercurrent Support General 12IAC53BB 1-EDE-SWG- Plant Seismic Capacity>

67 1 A63 Q>C 50; 51; SI Relay Svstems Electric 11A 5 Switchl!ear CB 21.5 10 Qualification Reoort Demand AC/DC Time Power Qvercurrent Support General 12IAC77AB 1-EDE-SWG- Plant Seismic Capacity>

68 1 A54 518d>A 51; SI Relay Systems Electric 03A 5 Switchgear CB 21.5 12 Qualification Report Demand AC/DC Time Power Qvercurrent Support General 12IAC77AB 1-EDE-SWG- Plant Seismic Capacity>

69 1 A54 518d>B 51; SI Relav Svstems Electric 03A 5 Switchl!ear CB 21.5 12 Qualification Reoort Demand AC/DC Time Power Qvercurrent Support General 12IAC77AB 1-EDE-SWG- Plant Seismic Capacity>

70 1 A54 518il>C 51; SI Relay Systems Electric 03A 5 Switchgear CB 21.5 12 Qualification Report Demand AC/DC Time Power Qvercurrent Support General 1-EDE-SWG- Plant Seismic Capacity>

71 1 A54 51Vd>A 51; SI Relay Systems Electric lJCV 5 Switchgear CB 21.5 16 Qualification Report Demand AC/DC Time Power Qvercurrent Support General 1-EDE-SWG- Plant Seismic Capacity>

72 1 A54 51VcjJB 51; SI Relay Svstems Electric IJCV 5 Switch11ear CB 21.5 16 Qualification Report Demand Page 28 of 43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Component Evaluation Device System Elev.

No Unit ID ID Contacts Tvpe Function Manufacturer Model No. ID Type Bld11:. fft) Gr. Basis for Capacitv Result AC/DC Time Power Overcurrent Support General 1-EDE-SWG- Plant Seismic Capacity>

73 1 A54 51VcbC 51; SI Relay Systems Electric IJCV 5 Switche:ear CB 21.5 16 Qualification Report Demand AC/DC Power Power Directional Support General 1-EDE-SWG- Plant Seismic Capacity>

74 1 A54 32 32; SI Rel av Svstems Electric !CW 5 Switch11:ear CB 21.5 13 Qualification Report Demand AC/DC 63,64 (A51) Mech Power

63, 64 Operated Support 1-EDE-SWG- Plant Seismic Capacity>

75 1 A54 52S [A52) Switch Systems  !TE N/A 5 Switchl!ear CB 21.5 9 Qualification Report Demand 69,70 (A51), AC/DC 69,70 Mech Power (A52); Operated Support 1-EDE-SWG- Plant Seismic Capacity>

76 1 A54 52S 79,80 Switch Svstems ITE N/A 5 Switch11:ear CB 21.5 9 Qualification Report Demand AC/DC 71,72 Mech Power (A51); Operated Support 1-EDE-SWG- Plant Seismic Capacity>

77 1 A54 52S 71,71 fA52) Switch Systems  !TE N/A 5 Switchg:ear CB 21.5 9 Qualification Reoort Demand AC/DC Power Circuit Support 1-EDE-SWG- Plant Seismic Capacity>

78 1 A54 52Y 52Y Breaker Systems  !TE HK350 5 Switchl!ear CB 21.5 22 Qualification Report Demand AC/DC Power Auxiliary Support General 1-DG-CP- Control GERS /Plant Seismic Capacity>

79 1 A54 R43R4 3T,3 Relay Systems Electric CR-120BD 75A Panel DGB 21.5 14 Qualification Report Demand AC/DC Power Auxiliary Support General 1-DG-CP- Control GERS/Plant Seismic Capacity>

80 1 A54 R43R3 5T,5 Rel av Svstems Electric CR-120BD 75A Panel DGB 21.5 14 Qualification Report Demand AC/DC Power Fast Closure Support 1-EDE-SWG- Plant Seismic Capacity>

81 1 A54 RS 5,7 Relay Systems Westin11:house AR 5 Switchgear CB 21.5 32 Qualification Report Demand AC/DC Power Fast Closure Support 1-EDE-SWG- Plant Seismic Capacity>

82 1 A54 RS 2,4 Relav Svstems Westine:house AR 5 Switchl!ear CB 21.5 32 Qualification Report Demand AC/DC Power LOCASeal Support 1-EDE-SWG- High Frequency Test Capacity>

83 1 A54 RLA 14;16 Relay Systems Electroswitch LOR/ER 5 Switchgear CB 21.5 8 Program Demand AC/DC Power PRlX EPSAux Support Westinghouse Control Capacity>

84 1 A54 fK74) 2,3 Relav Svstems /ABB AR 1-DG-CP-79 Panel CB 21.5 31 Plant Document Demand SI Signal AC/DC Actuating Power Output Support Potter MDR-4121- Control Capacity>

85 1 A54 K601A 15,16 Relay Systems Brumfield 1 1-MM-CP-12 Panel CB 75 24 Plant Document Demand AC/DC Power Loss of Field Support General 1-EDE-SWG- Plant Seismic Capacity>

86 1 A54 40 40;A Relay Systems Electric CEH 5 Switchgear CB 21.5 2 Qualification Report Demand Page 29 of 43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Comoonent Evaluation Device System Elev.

No Unit ID ID Contacts Tvoe Function Manufacturer Model No. ID Tvoe Bldg, rm Gr. Basis for Caoacitv Result AC/DC Power Aux Relay to Support 1-EDE-SWG- Capacity>

87 1 AS4 40X lT,l Dev40 Systems ITE )13 s Switchgear CB 21.S 20 GERS Demand AC/DC Power Shutdown Support General Control Plant Seismic Capacity>

88 1 AS4 SA SA Relay Svstems Electric CR-120BD 1-DG-CP-36 Panel DGB 21.S lS Qualification Report Demand AC/DC Power Time Delay Support 1-EDE-SWG- Plant Seismic Capacity>

89 1 AS4 BlY 9,10 Relay Systems  !TE 62L s Switchgear CB 21.S 23 Qualification Report Demand AC/DC Mech Power SW-V- Operated Support 1-EDE-SWG- Plant Seismic Capacity>

90 1 31 S2S 61,62 Switch Svstems ITE NIA 6 Switchgear CB 21.5 9 Qualification Report Demand AC/DC Mech Power SW-V- Operated Support 1-EDE-SWG- Plant Seismic Capacity>

91 1 29 S2S 61,62 Switch Systems ITE N/A 6 Switch"ear CB 21.S 9 Qualification Reoort Demand AC/DC Mech Power SW-V- Operated Support 1-EDE-SWG- Plant Seismic Capacity>

92 1 22 S2S 61,62 Switch Systems ITE NIA s Switchgear CB 21.S 9 Qualification Report Demand AC/DC Mech Power Operated Support 1-EDE-SWG- Plant Seismic Capacity>

93 1 SW-V-2 S2S 61,62 Switch Svstems ITE NIA s Switch"ear CB 21.S 9 Qualification Reoort Demand AC/DC Time Power SO/Sl<j> Overcurrent Support General 12IAC66B4 1-EDE-SWG- Plant Seismic Capacity>

94 1 AR4 A SO; Sl; SI Relay Systems Electric A 6 Switchgear CB 21.S 11 Qualification Report Demand AC/DC Time Power SO/Sl<j> Overcurrent Support General 12IAC66B4 1-EDE-SWG- Plant Seismic Capacity>

9S 1 AR4 c SO; Sl; SI Relay Systems Electric A 6 Switchgear CB 21.S 11 Qualification Report Demand AC/DC Power Circuit Support 1-EDE-SWG- Plant Seismic Capacity>

96 1 AR4 S2Y S2Y Breaker Systems ITE HK3SO 6 Switchgear CB 21.S 22 Qualification Reoort Demand AC/DC Tripping Power Relay Bus Support 1-EDE-SWG- Plant Seismic Capacity>

97 1 AR4 94-2 2.4 UV Systems Westinghouse AR 6 Switchgear CB 21.S 32 Qualification Report Demand AC/DC Power HRS EPS Starting Support Westinghouse Control Capacity>

98 1 AR4 [K83) 6,7 Relay Systems /ABB AR 1-DG-CP-80 Panel CB 21.S 31 Plant Document Demand AC/DC Power Auxiliary Support 1-EDE-SWG- Plant Seismic Capacity>

99 1 AR4 Rl S,7 Relay Systems Westinghouse AR 6 Switchgear CB 21.S 29 Qualification Report Demand AC/DC Time Power SO/Sl<j> Overcurrent Support General 12IACS3B8 1-EDE'SWG- Plant Seismic Capacity>

100 1 ASS A SO;Sl;SI Relay Systems Electric 11A s Switchgear CB 21.S 10 Qualification Report Demand Page 30 of 43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Comoonent Evaluation Device System Elev.

No Unit ID ID Contacts Tvoe Function Manufacturer Model No. ID Type Bldg, (ft) Gr. Basis for Capacity Result AC/DC Time Power SO/Slcji Overcurrent Support General 121ACS3BB 1-EDE-SWG- Plant Seismic Capacity>

101 1 ASS B SO; Sl; SI Relay Systems Electric llA s Switchgear CB 21.S 10 Qualification Report Demand AC/DC Time Power SO/Slcji Overcurrent Support General 121ACS3B8 1-EDE-SWG- Plant Seismic Capacity>

102 1 ASS c SO;Sl;Sl Relay Systems Electric llA s Switchgear CB 21.S 10 Qualification Reoort Demand AC/DC Time Power SO/Slcji Overcurrent Support General 12IAC66B4 1-EDE-SWG- Plant Seismic Capacity>

103 1 AQ3 A SO; Sl; SI Relay Systems Electric A s Switchgear CB 21.S 11 Qualification Report Demand AC/DC Time Power SO/Slcji Overcurrent Support General 12IAC66B4 1-EDE-SWG- Plant Seismic Capacity>

104 1 AQ3 c SO; Sl; SI Relav Svstems Electric A 5 Switchgear CB 21.S 11 Qualification Reoort Demand AC/DC Power Circuit Support 1-EDE-SWG- Plant Seismic Capacity>

lOS 1 AQ3 S2Y S2Y Breaker Systems ITE HK3SO s Switchgear CB 21.S 22 Qualification Report Demand AC/DC Tripping Power Relay Bus Support 1-EDE-SWG- Plant Seismic Capacity>

106 1 AQ3 94-2 1,3 UV Svstems Westinghouse AR 5 Switchgear CB 21.S 32 Qualification Reoort Demand AC/DC Power HRB EPS Starting Support Westinghouse Control Capacity>

107 1 AQ3 (K83) 4,S Relay Systems /ABB AR 1-DG-CP-79 Panel CB 21.S 31 Plant Document Demand AC/DC Power Auxiliary Support 1-EDE-SWG- Plant Seismic Capacity>

108 1 A03 Rl S,7 Relav Svstems Westinghouse AR s Switchgear CB 21.5 29 Qualification Reoort Demand AC/DC Time Power SO/Slcji Overcurrent Support General 121AC66B4 1-EDE-SWG- Plant Seismic Capacity>

109 1 AQ4 A SO; Sl; SI Relay Systems Electric A s Switchgear CB 21.S 11 Qualification Report Demand AC/DC Time Power S0/51¢ Overcurrent Support General 121AC66B4 1-EDE-SWG- Plant Seismic Capacity>

110 1 AQ4 c SO; Sl; SI Relay Systems Electric A s Switchgear CB 21.S 11 Qualification Reoort Demand AC/DC Power Circuit Support 1-EDE-SWG- Plant Seismic Capacity>

111 1 AQ4 S2Y 52Y Breaker Systems ITE HK3SO s Switchgear CB 21.5 22 Qualification Reoort Demand AC/DC Tripping Power Relay Bus Support 1-EDE-SWG- Plant Seismic Capacity>

112 1 AQ4 94-2 2,4 UV Systems Westinghouse AR s Switchgear CB 21.5 32 Qualification Report Demand AC/DC Power HRS EPS Starting Support Westinghouse Control Capacity>

113 1 AQ4 (K83) 7,6 Relay Systems /ABB AR 1-DG-CP-79 Panel CB 21.S 31 Plant Document Demand AC/DC Power Auxiliary Support 1-EDE-SWG- Plant Seismic Capacity>

114 1 AQ4 Rl S,7 Relay Systems Westinghouse AR s Switchgear CB 21.S 29 Qualification Report Demand Page 31of43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Comnonent Evaluation Device System Elev.

No Unit ID ID Contacts Tvne Function Manufacturer Model No. ID Tvne Bldg. (ft) Gr. Basis for Canacitv Result AC/DC Power Timing Support 1-EDE-SWG- High Frequency Test Capacity>

115 1 DP6 62BLL 1,5 Relav Systems AGASTAT E7012AE llC Switchgear CB 21.5 4 Program Demand AC/DC Time Power Overcurrent Support General 121AC77AB 1-EDE-SWG- Plant Seismic Capacity>

116 1 A74 51Bcl>A 51; SJ Relay Systems Electric 03A 6 Switchgear CB 21.5 12 Qualification Report Demand AC/DC Time Power Overcurrent Support General 12IAC77A8 1-EDE-SWG- Plant Seismic Capacity>

117 1 A74 518$8 51; SI Relay Systems Electric 03A 6 Switchgear CB 21,5 12 Qualification Report Demand AC/DC Time Power Overcurrent Support General 121AC77A8 1-EDE-SWG- Plant Seismic Capacity>

118 1 A74 51BcbC 51; SI Rel av Svstems Electric 03A 6 Switchgear CB 21.5 12 Qualification Renart Demand AC/DC Time Power Overcurrent Support General 1-EDE-SWG- Plant Seismic Capacity>

119 1 A74 51VcbA 51; SJ Relay Systems Electric ncv 6 Switchgear CB 21.5 16 Qualification Reoort Demand AC/DC Time Power Overcurrent Support General 1-EDE-SWG- Plant Seismic Capacity>

120 1 A74 51 VcjJB 51; SI Relay Systems Electric IJCV 6 Switchgear CB 21.5 16 Qualification Report Demand AC/DC Time Power Overcurrent Support General 1-EDE-SWG- Plant Seismic Capacity>

121 1 A74 51V<!JC 51; SI Relay Systems Electric IICV 6 Switchgear CB 21.5 16 Qualification Report Demand AC/DC Power Power Directional Support General 1-EDE-SWG- Plant Seismic Capacity>

122 1 A74 32 32; SI Relav Svstems Electric !CW 6 Switchgear CB 21.5 13 Qualification Report Demand AC/DC Power Circuit Support 1-EDE-SWG- Plant Seismic Capacity>

123 1 A74 52Y 52Y Breaker Systems  !TE HK350 6 Switchgear CB 21.5 22 Qualification Report Demand AC/DC 63,64 (A71) Mech Power

63, 64 Operated Support 1-EDE-SWG- Plant Seismic Capacity>

124 1 A74 52S (A72) Switch Systems  !TE NIA 6 Switchgear CB 21.5 9 Qualification Reoort Demand AC/DC 70,71 Mech Power (A71); Operated Support 1-EDE-SWG- Plant Seismic Capacity>

125 1 A74 52S 70,71 (A72) Switch Systems  !TE N/A 6 Switchgear CB 21.5 9 Qualification Report Demand 69,70 (A71), AC/DC 69, 70 Mech Power (A72); Operated Support 1-EDE-SWG- Plant Seismic Capacity>

126 1 A74 52S 79,80 Switch Svstems  !TE NIA 6 Switchgear CB 21.5 9 Qualification Renart Demand AC/DC Power Auxiliary Support General 1-DG-CP- Control GERS/Plant Seismic Capacity>

127 1 A74 R43R4 3T,3 Relay Systems Electric CR-120BD 76A Panel DGB 21.5 14 Qualification Report Demand AC/DC Power Auxiliary Support General 1-DG-CP- Control GERS/Plant Seismic Capacity>

128 1 A74 R43R3 5T,5 Relay Systems Electric CR-120BD 76A Panel DGB 21.5 14 Qualification Report Demand Page 32 of 43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Comoonent Evaluation Device System Elev.

No Unit ID ID Contacts Tvoe Function Manufacturer Model No. ID Type Bid!!. fftl Gr. Basis for Capacity Result AC/DC Power PRlX EPSAux Support Westinghouse Control Capacity>

129 1 A74 (K74l 2,3 Relav Systems /ABB AR 1-DG-CP-80 Panel CB 21.5 31 Plant Document Demand AC/DC Power Fast Closure Support 1-EDE-SWG- Plant Seismic Capacity>

130 1 A74 RS 5,7 Relay Systems Westinghouse AR 6 Switchgear CB 21.5 32 Qualification RePort Demand AC/DC Power Fast Closure Support 1-EDE-SWG- Plant Seismic Capacity>

131 1 A74 RS 2,4 Relav Svstems Westin11house AR 6 Switch11ear CB 21.5 32 Qualification Report Demand AC/DC Power LOCASeal Support 1-EDE-SWG- High Frequency Test Capacity>

132 1 A74 RLA 14,16 Relay Systems Electroswitch LOR/ER 6 Switch11ear CB 21.5 8 Pro11ram Demand SI Signal AC/DC Actuating Power Output Support Potter MDR-4121- Control Capacity>

133 1 A74 K601B 15,16 Relav Svstems Brumfield 1 1-MM-CP-13 Panel CB 75 24 Plant Document Demand AC/DC Power Shutdown Support General Control Plant Seismic Capacity>

134 1 A74 SA SA Relay Systems Electric CR-120BD 1-DG-CP-37 Panel DGB 21.5 15 Qualification Report Demand AC/DC Power Loss of Field Support General 1-EDE-SWG- Plant Seismic Capacity>

135 1 A74 40 40;A Relay Systems Electric CEH 6 Switch11ear CB 21.5 2 Qualification Report Demand AC/DC Power Aux Relay to Support 1-EDE-SWG- Capacity>

136 1 A74 40X lT,l Dev40 Systems  !TE 113 6 Switchgear CB 21.5 20 GERS Demand AC/DC Aux Power Frequency Support 1-EDE-SWG- Plant Seismic Capacity>

137 1 A74 81Y 9,10 Relay Systems  !TE 62L 6 Switch11ear CB 21.5 23 Qualification Report Demand AC/DC Time Power 50/Slcj> Overcurrent Support General 12IAC53B8 1-EDE-SWG- Plant Seismic Capacity>

138 1 A75 A 50; 51; SI Relay Systems Electric llA 6 Switchgear CB 21.5 10 Qualification Report Demand AC/DC Time Power 50/Slcj> Overcurrent Support General 121AC53B8 1-EDE-SWG- Plant Seismic Capacity>

139 1 A75 B 50; 51; SI Relav Svstems Electric llA 6 Switch11ear CB 21.5 10 Qualification Report Demand AC/DC Time Power 50/Slcj> Overcurrent Support General 12IAC53B8 1-EDE-SWG- Plant Seismic Capacity>

140 1 A75 c 50; 51; SI Relay Svstems Electric llA 6 Switchgear CB 21.5 10 Qualification Reoort Demand AC/DC Time Power 50/Slcj> Overcurrent Support General 121AC66B4 1-EDE-SWG- Plant Seismic Capacity>

141 1 AR3 A 50; 51; SI Relav Svstems Electric A 6 Switchgear CB 21.5 11 Qualification Reoort Demand AC/DC Time Power 50/Slcj> Overcurrent Support General 12IAC66B4 1-EDE-SWG- Plant Seismic Capacity>

142 1 AR3 c 50; 51; SI Relav Svstems Electric A 6 Switchgear CB 21.5 11 Qualification Report Demand Page 33 of 43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Component Evaluation Device System Elev.

No Unit ID ID Contacts Tvoe Function Manufacturer Model No. ID Tvoe Bldg. (ft) Gr. Basis for Ca oacitv Result AC/DC Power Circuit Support 1-EDE-SWG- Plant Seismic Capacity>

143 1 AR3 S2Y S2Y Breaker Systems lTE HK3SO 6 Switchgear CB 21.S 22 Qualification Report Demand AC/DC Tripping Power Relay Bus Support 1-EDE-SWG- Plant Seismic Capacity>

144 1 AR3 94-2 1,3 UV Svstems Westinghouse AR 6 Switchgear CB 21.S 32 Qualification Report Demand AC/DC Power HRS EPS Starting Support Westinghouse Control Capacity>

14S 1 AR3 (K83) 4,S Relay Systems /ABB AR 1-DG-CP-80 Panel CB 21.S 31 Plant Document Demand AC/DC Power I Auxiliary Support 1-EDE-SWG- Plant Seismic Capacity>

146 1 AR3 Rl S,7 Relav Svstems Westinghouse AR 6 Switchgear CB 21.S 29 Qualification Reoort Demand AC/DC Time Power SO/Sl<jl Overcurrent Support General 12IACS3B8 1-EDE-SWG- Plant Seismic Capacity>

147 1 A83 A SO; Sl; SI Relay Systems Electric llA 6 Switchgear CB 21.S 10 Qualification Report Demand AC/DC Time Power SO/Sl<jl Overcurrent Support General 12IACS3B8 1-EDE-SWG- Plant Seismic Capacity>

148 1 A83 B SO; Sl; SI Relav Svstems Electric llA 6 Switchgear CB 21.S 10 Qualification Report Demand AC/DC Time Power SO/Sl<jl Overcurrent Support General 12IACS3B8 1-EDE-SWG- Plant Seismic Capacity>

149 1 A83 c SO; Sl; SI Relay Systems Electric llA 6 Switchgear CB 21.5 10 Qualification Report Demand AC/DC Power Timing Support 1-EDE-SWG- High Frequency Test Capacity>

lSO 1 DOS 62BLL 1,S Relav Svstems AGASTAT E7012AE 110 Switchgear CB 21.S 4 Program Demand AC/DC Power Timing Support 1-EDE-SWG- High Frequency Test Capacity>

lSl 1 DN4 62BLL 1,S Relay Systems AGASTAT E7012AE 118 Switchgear CB 21.S 4 Program Demand AC/DC Power Normal Stop Support Control High Frequency Test Capacity>

1S2 1 EDG-lA s 3,S Relay Systems AGASTAT E7022PE 1-DG-CP-36 Panel DGB 21.S 7 Program Demand AC/DC Power Tachometer Support Control Plant Seismic Capacity>

1S3 1 EDG-lA Dev-TR Dev-TR Relay Systems 1-DG-CP-36 Panel DGB 21.S 3S Qualification Report Demand AC/DC Power Support Control Capacity>

1S4 1 EDG-lA 4A 4A Start Relav Svstems  !TE ]13 1-DG-CP-36 Panel DGB 21.S 19 GERS Demand AC/DC Power Support Control Capacity>

lSS 1 EDG-lA 4B 48 Start Relay Systems  !TE )13 1-DG-CP-36 Panel DGB 21.S 19 GERS Demand AC/DC Emergency Power Device Support General Control Plant Seismic Capacity>

1S6 1 EDG-lA SE SE Relay Systems Electric CR-120BD 1-DG-CP-36 Panel DGB 21.S lS Qualification Report Demand Page 34 of 43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Component Evaluation Device System Elev.

No Unit ID ID Contacts Tvne Function Manufacturer Model No. ID Tvne Bldg. (ftl Gr. Basis for Canacitv Result AC/DC Starting Air Power Shutoff Support General Control Plant Seismic Capacity>

157 1 EDG-lA ASR ASR Relay Systems Electric CR-120BD 1-DG-CP-36 Panel DGB 21.5 15 Qualification Report Demand AC/DC Starting Air Power Valve Relay Support Control Capacity>

158 1 EDG-lA ASA ASA FY-ASl Svstems  !TE j13 1-DG-CP-36 Panel DGB 21.5 19 GERS Demand AC/DC Starting Air Power Valve Relay Support Control Capacity>

159 1 EDG-lA ASB ASB FY-AS2 Systems  !TE j13 1-DG-CP-36 Panel DGB 21.5 19 GERS Demand jacket AC/DC Coolant Power Hight Temp Support Control Capacity>

160 1 EDG-lA CTH CTH Aux Relav Svstems  !TE j13 1-DG-CP-36 Panel DGB 21.5 19 GERS Demand jacket AC/DC Coolant Power Hight Temp Support General Control Plant Seismic Capacity>

161 1 EDG-lA CTH-1 lT,1 Aux Relay Systems Electric CR-120BD 1-DG-CP-36 Panel DGB 21.5 15 Qualification Report Demand AC/DC Coolant Power DGA-PS- Pressure Support Control Plant Seismic Capacity>

162 1 EDG-lA CPS DGA-PS-CPS Switch Svstems 1-DG-CP-36 Panel DGB 21.5 18 Qualification Renart Demand AC/DC Engine Power Overs peed Support General Control Plant Seismic Capacity>

163 1 EDG-lA EOR EOR Relay Systems Electric CR-120BD 1-DG-CP-36 Panel DGB 21.S 15 Qualification Report Demand AC/DC Engine Power Overs peed Support Control Plant Seismic Capacity>

164 1 EDG-lA EOS EOS Relav Svstems 1-DG-CP-36 Panel DGB 21.5 27 Oualification Reoort Demand AC/DC Power Emergency Support Control Capacity>

165 1 EDG-lA ESl ESl Start Relay Systems  !TE j13 1-DG-CP-36 Panel DGB 21.5 19 GERS Demand AC/DC Power Emergency Support Control Capacity>

166 1 EDG-lA ES2 ES2 Start Relav Svstems  !TE j13 1-DG-CP-36 Panel DGB 21.5 19 GERS Demand AC/DC Emergency Power Start Aux Support General Control Plant Seismic Capacity>

167 1 EDG-lA ESX 3T3; 4T,4 Relay Systems Electric CR-120BD 1-DG-CP-36 Panel DGB 21.5 15 Qualification Renart Demand AC/DC Power Oil Pressure Support Control Capacity>

168 1 EDG-lA OP2 OP2 Relav Svstems  !TE 113 1-DG-CP-36 Panel DGB 21.5 19 GERS Demand AC/DC Power Oil Pressure Support Control Capacity>

169 1 EDG-lA OP3 OP3 Relay Systems  !TE j13 1-DG-CP-36 Panel DGB 21.5 19 GERS Demand AC/DC Power Oil Pressure Support Control Capacity>

170 1 EDG-lA OP4 OP4 Relay Systems  !TE j13 1-DG-CP-36 Panel DGB 21.5 19 GERS Demand Page 35 of 43

Seabrook Station Seismic High Frequency Confirmation Comoonent Enclosure Floor Comoonent Evaluation Device System Elev.

No Unit ID ID Contacts Tvoe Function Manufacturer Model No. ID Tvpe Bldg-. (ft) Gr. Basis for Capacity Result AC/DC Power Oil Temp Support Control Capacity>

171 1 EDG-lA OTH OTH Relay Systems  !TE 113 1-DG-CP-36 Panel DGB 21.S 19 GERS Demand AC/DC Power Oil Temp Support General Control Plant Seismic Capacity>

172 1 EDG-lA OTH-1 lT,1 Relav Svstems Electric CR-120BD 1-DG-CP-36 Panel DGB 21.S lS Qualification Report Demand AC/DC Starting Power Failure Support Control Capacity>

173 1 EDG-lA SFR SFR Relay Systems  !TE ]13 1-DG-CP-36 Panel DGB 21.S 19 GERS Demand AC/DC Power Shutdown Support Control Capacity>

174 1 EDG-lA SDR SDR Relay Systems  !TE 113 1-DG-CP-36 Panel DGB 21.S 19 GERS Demand AC/DC Power Starting Support Control Capacity>

17S 1 EDG-lA T2A l,S Time Relay Systems AGASTAT E7012PC 1-DG-CP-36 Panel DGB 21.S s GERS Demand AC/DC Power Starting Support Control Capacity>

176 1 EDG-lA T2B 1,S Time Relay Systems AGASTAT E7012PC 1-DG-CP-36 Panel DGB 21.S s GERS Demand AC/DC Power Alarm Set Support Control Capacity>

177 1 EDG-lA T3A l,S Relay Systems AGASTAT E7014PC 1-DG-CP-36 Panel DGB 21.S 6 GERS Demand AC/DC Power TR Control Support Control Capacity>

178 1 EDG-lA TRP TRP Power Relay Systems  !TE 113 1-DG-CP-36 Panel DGB 21.S 19 GERS Demand AC/DC Power Normal Stop Support Control High Frequency Test Capacity>

179 1 EDG-18 s 3,S Relay Svstems AGASTAT E7022PE 1-DG-CP-37 Panel DGB 21.S 7 Program Demand AC/DC Power Tachometer Support Control Plant Seismic Capacity>

180 1 EDG-18 Dev-TR Dev-TR Relay Systems 1-DG-CP-37 Panel DGB 21.5 3S Qualification Report Demand AC/DC Power Support Control Capacity>

181 1 EDG-lB 4A 4A Start Relay Systems  !TE 113 1-DG-CP-37 Panel DGB 21.5 19 GERS Demand AC/DC Power Support Control Capacity>

182 1 EDG-18 4B 4B Start Relav Svstems  !TE 113 1-DG-CP-37 Panel DGB 21.S 19 GERS Demand AC/DC Emergency Power Device Support General Control Plant Seismic Capacity>

183 1 EDG-lB SE SE Relay Systems Electric CR-120BD 1-DG-CP-37 Panel DGB 21.S lS Qualification Report Demand AC/DC Starting Air Power Shutoff Support General Control Plant Seismic Capacity>

184 1 EDG-18 ASR ASR Relay Systems Electric CR-120BD 1-DG-CP-37 Panel DGB 21.S lS Qualification Report Demand Page 36 of 43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Component Evaluation Device System Elev.

No Unit ID ID Contacts Tvoe Function Manufacturer Model No. ID Tvpe Bide:. (ft) Gr. Basis for Ca pacitv Result AC/DC Starting Air Power Valve Relay Support Control Capacity>

185 1 EDG-18 ASA ASA FY-ASl Svstems  !TE 113 1-DG-CP-37 Panel DGB 21.S 19 GERS Demand AC/DC Starting Air Power Valve Relay Support Control Capacity>

186 1 EDG-18 AS8 AS8 FY-AS2 Systems  !TE )13 1-DG-CP-37 Panel DG8 21.5 19 GERS Demand jacket AC/DC Coolant Power Hight Temp Support Control Capacity>

187 1 EDG-18 CTH CTH Aux Relav Svstems  !TE )13 1-DG-CP-37 Panel DGB 21.5 19 GERS Demand jacket AC/DC Coolant Power Hight Temp Support General Control Plant Seismic Capacity>

188 1 EDG-18 CTH-1 lT,l Aux Relav Systems Electric CR-1208D 1-DG-CP-37 Panel DG8 21.5 15 Qualification Report Demand AC/DC Coolant Power DG8-PS- Pressure Support Control Capacity>

189 1 EDG-18 CPS DGA-PS-CPS Switch Svstems ITE 113 1-DG-CP-37 Panel DG8 21.5 19 GERS Demand AC/DC Engine Power Overspeed Support General Control Plant Seismic Capacity>

190 1 EDG-18 EOR EOR Relay Systems Electric CR-120BD 1-DG-CP-37 Panel DG8 21.5 15 Qualification Report Demand AC/DC Engine Power 0Yerspeed Support Control Plant Seismic Capacity>

191 1 EDG-18 EOS EOS Relay Systems 1-DG-CP-37 Panel DG8 21.5 27 Qualification Report Demand AC/DC Power Emergency Support Control Capacity>

192 1 EDG-18 ESl ESl Start Relay Systems ITE )13 1-DG-CP-37 Panel DG8 21.5 19 GERS Demand AC/DC Power Emergency Support Control Capacity>

193 1 EDG-18 ES2 ESl Start Relay Systems  !TE )13 1-DG-CP-37 Panel DG8 21.5 19 GERS Demand AC/DC Emergency Power Start Time Support General Control Plant Seismic Capacity>

194 1 EDG-18 ESX 3T3; 4T,4 Relay Systems Electric CR-1208D 1-DG-CP-37 Panel DG8 21.5 15 Qualification Report Demand AC/DC Power Oil Pressure Support Control Capacity>

195 1 EDG-18 OP2 OPl Relay Systems  !TE )13 1-DG-CP-37 Panel DG8 21.5 19 GERS Demand AC/DC Power Oil Pressure Support Control Capacity>

196 1 EDG-18 OP3 OP2 Relay Systems  !TE 113 1-DG-CP-37 Panel DG8 21.5 19 GERS Demand AC/DC Power Oil Pressure Support Control Capacity>

197 1 EDG-18 OP4 OP3 Relay Systems  !TE )13 1-DG-CP-37 Panel DG8 21.5 19 GERS Demand AC/DC Power Oil Temp Support Control Capacity>

198 1 EDG-18 OTH OP4 Relay Systems  !TE )13 1-DG-CP-37 Panel DG8 21.5 19 GERS Demand Page 37 of 43

Seabrook Station Seismic High Frequency Confirmation Comoonent Enclosure Floor Comoonent Evaluation Device System Elev.

No Unit ID ID Contacts Tyne Function Manufacturer Model No. ID Type Bldg, (ft) Gr. Basis for Capacitv Result AC/DC Power Oil Temp Support General Control Plant Seismic Capacity>

199 1 EDG-18 OTH-1 OTH Relay Systems Electric CR-120BD 1-DG-CP-37 Panel DGB 21.5 15 Qualification Report Demand AC/DC Starting Power Failure Support Control Capacity>

200 1 EDG-18 SFR lT,1 Relav Svstems  !TE 113 1-DG-CP-37 Panel DGB 21.5 19 GERS Demand AC/DC Power Shutdown Support Control Capacity>

201 1 EDG-18 SDR SFR Relay Systems  !TE ]13 1-DG-CP-37 Panel DGB 21.5 19 GERS Demand AC/DC Power Starting Support Control Capacity>

202 1 EDG-18 T2A SDR Time Relay Systems AGASTAT E7012PC 1-DG-CP-37 Panel DGB 21.5 5 GERS Demand AC/DC Power Starting Support Control Capacity>

203 1 EDG-18 T2B 1,5 Time Relay Systems AGASTAT E7012PC 1-DG-CP-37 Panel DGB 21.5 5 GERS Demand AC/DC Power Alarm Set Support Control Capacity>

204 1 EDG-18 T3A 1,5 Rel av Svstems AGASTAT E7014PC 1-DG-CP-37 Panel DGB 21.5 6 GERS Demand AC/DC Power TR Control Support Control Capacity>

205 1 EDG-18 TRP 1,5 Power Relay Systems  !TE 113 1-DG-CP-37 Panel DGB 21.5 19 GERS Demand AC/DC Power Timing Support 1-EDE-SWG- High Frequency Test Capacity>

206 1 DMZ 62BLL 1,5 Relav Svstems AGASTAT E7012AE 11A Switchgear CB 21.5 4 Proe:ram Demand AC/DC Time Power Overcurrent Support General 121AC77A8 1-EDE-SWG- Plant Seismic Capacity>

207 1 ASl Sl<l>A 51; SI Relay Systems Electric 03A 5 Switchgear CB 21.5 12 Qualification Report Demand AC/DC Time Power Overcurrent Support General 121AC77A8 1-EDE-SWG- Plant Seismic Capacity>

208 1 A51 Sld>B 51; SI Relay Systems Electric 03A 5 Switchgear CB 21.5 12 Qualification Report Demand AC/DC Time Power Overcurrent Support General 121AC77A8 1-EDE-SWG- Plant Seismic Capacity>

209 1 AS! Sl<l>C 51; SI Relay Systems Electric 03A 5 Switchgear CB 21.5 12 Qualification Report Demand AC/DC Time Power Overcurrent Support General 121AC77A8 1-EDE-SWG- Plant Seismic Capacity>

210 1 A52 Sld>A 51; SI Relav Svstems Electric 03A 5 Switchgear CB 21.5 12 Qualification Report Demand AC/DC Time Power Overcurrent Support General 121AC77A8 1-EDE-SWG- Plant Seismic Capacity>

211 1 A52 Sl<l>B 51; SI Relay Systems Electric 03A 5 Switchgear CB 21.5 12 Qualification Report Demand AC/DC Time Power Overcurrent Support General 121AC77AB 1-EDE-SWG- Plant Seismic Capacity>

212 1 ASZ Sl<l>C 51; SI Relay Systems Electric 03A 5 Switchgear CB 21.5 12 Qualification Report Demand Page 38 of 43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Component Evaluation Device System Elev.

No Unit ID ID Contacts Tvne Function Manufacturer Model No. ID Tvne Bid!!. [ft) Gr. Basis for Capacitv Result AC/DC Time Power Overcurrent Support General 121AC77A8 1-EDE-SWG- Plant Seismic Capacity>

213 1 A71 SlcM 51; SI Relav Systems Electric 03A 6 Switchgear CB 21.5 12 Qualification Renart Demand AC/DC Time Power Overcurrent Support General 12IAC77A8 1-EDE-SWG- Plant Seismic Capacity>

214 1 A71 51QiB 51; SI Relay Systems Electric 03A 6 Switchgear CB 21.5 12 Qualification Report Demand AC/DC Time Power Overcurrent Support General 121AC77A8 1-EDE-SWG- Plant Seismic Capacity>

215 1 A71 SlcbC 51; SI Rel av Svstems Electric 03A 6 Switchi:!ear CB 21.5 12 Qualification Renart Demand AC/DC Time Power Overcurrent Support General 12IAC77A8 1-EDE-SWG- Plant Seismic Capacity>

216 1 A72 SlQiA 51; SI Relay Systems Electric 03A 6 Switchgear CB 21.5 12 Qualification Report Demand AC/DC Time Power Overcurrent Support General 12IAC77A8 1-EDE-SWG- Plant Seismic Capacity>

217 1 A72 SlcbB 51; SI Relav Svstems Electric 03A 6 Switch!lear CB 21.5 12 Qualification Renart Demand AC/DC Time Power Overcurrent Support General 121AC77A8 1-EDE-SWG- Plant Seismic Capacity>

218 1 A72 SlcjJC 51; SI Relay Systems Electric 03A 6 Switchgear CB 21.5 12 Qualification Report Demand Spray AC/DC Actuation Power Output Support Potter MDR-4121- Control Capacity>

219 1 A81 K644B 13,14; 15,16 Relav Svstems Brumfield 1 1-MM-CP-13 Panel CB 75 24 Plant Document Demand Emergency AC/DC Power Power LR8 Sequencer Support Westinghouse Control Capacity>

220 1 A81 [K84) 4,5 Relay Systems /ABB AR 1-DG-CP-80 Panel CB 21.5 31 Plant Document Demand Spray AC/DC Actuation Power Output Support Potter MDR-4121- Control Capacity>

221 1 A61 K644A 13,14; 15,16 Relav Svstems Brumfield 1 1-MM-CP-12 Panel CB 75 24 Plant Document Demand Emergency AC/DC Power Power LR8 Sequencer Support Westinghouse Control Capacity>

222 1 A61 [K84l 4,5 Relay Systems /ABB AR 1-DG-CP-79 Panel CB 21.5 31 Plant Document Demand Emergency AC/DC PRl Power Power (K7,K10 Sequencer Support Control Capacity>

223 1 A79 ) 5,6; 11,12 Relav Svstems  !TE )13 1-DG-CP-80 Panel CB 21.5 19 GERS Demand Emergency AC/DC PRl Power Power (K8,Kl0 Sequencer Support Control Capacity>

224 1 A78 ) 9,10; 15,16 Rel av Svstems  !TE 113 1-DG-CP-80 Panel CB 21.5 19 GERS Demand Emergency AC/DC PRl Power Power (K8,K10 Sequencer Support Control Capacity>

225 1 A59 ) 5,6; 11,12 Relay Systems  !TE )13 1-DG-CP-79 Panel CB 21.5 19 GERS Demand Emergency AC/DC PRl Power Power (K7,K10 Sequencer Support Control Capacity>

226 1 ASS ) 9,10; 15,16 Relay Systems  !TE )13 1-DG-CP-79 Panel CB 21.5 19 GERS Demand Page 39 of 43

Seabrook Station Seismic High Frequency Confirmation Component Enclosure Floor Component Evaluation Device System Elev.

No Unit ID ID Contacts Tvne Function Manufacturer Model No. ID Type Bldg. [ft) Gr. Basis for Capacity Result SI Signal AC/DC Actuating Power Output Support Potter MDR-4121- Control Capacity>

227 1 AS? K601A 1,2; 17,18 Relay Systems Brumfield 1 1-MM-CP-12 Panel CB 75 24 Plant Document Demand Emergency AC/DC Power Power PRl Sequencer Support Control Capacity>

22B 1 A57 (K7) 11,12 Relay Systems ITE )13 1-DG-CP-79 Panel CB 21.5 19 GERS Demand SI Signal AC/DC Actuating Power Output Support Potter MDR-4121- Control Capacity>

229 1 A62 K616A 7,B Relay Systems Brumfield 1 1-MM-CP-12 Panel CB 75 24 Plant Document Demand Emergency AC/DC Power Power R2X Sequencer Support Westinghouse Control Capacity>

230 1 A62 (1(73) 2,3 Relay Systems /ABB AR 1-DG-CP-79 Panel CB 21.5 31 Plant Document Demand SI Signal AC/DC Actuating Power Output Support Potter MDR-4121- Control Capacity>

231 1 A76 K610B 1,2; 11, 12 Relay Systems Brumfield 1 1-MM-CP-13 Panel CB 75 24 Plant Document Demand SI Signal AC/DC Actuating Power Output Support Potter MDR-4121- Control Capacity>

232 1 A56 K610A 1,2; 11, 12 Relay Systems Brumfield 1 1-MM-CP-12 Panel CB 75 24 Plant Document Demand SI Signal AC/DC Actuating Power Output Support Potter MDR-4121- Control Capacity>

233 1 A77 K601B 1,2; 17,18 Relay Systems Brumfield 1 1-MM-CP-13 Panel CB 75 24 Plant Document Demand Emergency AC/DC Power Power PRl Sequencer Support Control Capacity>

234 1 A77 (K7) 11,12 Relay Systems ITE 113 1-DG-CP-BO Panel CB 21.5 19 GERS Demand AC/DC Power Auxiliary Support General 1-EDE-SWG- Plant Seismic Capacity>

235 1 A93 PS5X 2,B Relay Systems Electric HGA 5 Switchgear CB 21.5 17 Qualification Report Demand AC/DC Mech Power Operated Support 1-EDE-SWG- Plant Seismic Capacity>

236 1 A93 52S 59,60 Switch Systems  !TE N/A 5 Switchgear CB 21.5 9 Qualification Report Demand Reactor AC/DC Protector Power System Aux. Support Potter MDR-4103- Control Capacity>

237 1 ABO K640B B,7; 9,10 Relay Systems Brumfield 1 1-MM-CP-13 Panel CB 75 25 Plant Document Demand Reactor AC/DC Protector Power System Aux. Support Potter MDR-4121- Control Capacity>

23B 1 ABO K615B 7,B; 11,12 Relay Systems Brumfield 1 1-MM-CP-13 Panel CB 75 24 Plant Document Demand AC/DC Power Isolation Support Struthers- 1-MM-CP- Control Capacity>

239 1 ABO KA24 10,11 Relay Systems Dunn 219XBX234 470 Panel CB 75 28 Plant Document Demand Emergency AC/DC Power Power EPS-PRl Sequencer Support Control Capacity>

240 1 ABO (!<7) 13,14 Relay Systems ITE )13 1-DG-CP-80 Panel CB 21.5 19 GERS Demand Page 40 of 43

Seabrook Station Seismic High Frequency Confirmation Comoonent Enclosure Floor Component Evaluation Device System Elev.

No Unit ID ID Contacts Type Function Manufacturer Model No. ID Tvoe Bld!l. (ft) Gr. Basis for Ca Pacitv Result Tower AC/DC Actuation Power Signal Aux Support 1-EDE-CP- Control Capacity>

241 1 AU6 RTB ST,S Relav Svstems lTE )13 249 Panel CB 21.5 19 GERS Demand Emergency AC/DC Power Power HRS Sequencer Support Westinghouse Control Capacity>

242 1 AU6 (KS3) 1,10 Relay Systems /ABB AR 1-DG-CP-SO Panel CB 21.5 31 Plant Document Demand AC/DC High Speed Power Auxiliary Support Westinghouse 1-EDE-SWG- Plant Seismic Capacity>

243 1 AU6 R4 5,7 Rel av Systems /ABB AR 6 Switchgear CB 21.5 33 Qualification Report Demand Tower AC/DC Actuation Power Signal Aux Support 1-EDE-CP- Control Capacity>

244 1 AU2 RTA 4T,4 Relay Systems  !TE ]13 24S Panel CB 21.5 19 GERS Demand Emergency AC/DC Power Power HRS Sequencer Support Westinghouse Control Capacity>

245 1 AU2 fKS3) 1,10 Relay Systems /ABB AR 1-DG-CP-79 Panel CB 21.5 31 Plant Document Demand AC/DC High Speed Power Auxiliary Support Westinghouse 1-EDE-SWG- Plant Seismic Capacity>

246 1 AU2 R4 5,7 Relay Systems /ABB AR 5 Switchgear CB 21.5 33 Qualification Report Demand SI Signal AC/DC Actuating Power Output Support Potter MDR-4121- Control Capacity>

247 1 AS2 K616B 7,S Relay Systems Brumfield 1 1-MM-CP-13 Panel CB 75 24 Plant Document Demand Emergency AC/DC Power Power R2X Sequencer Support Westinghouse Control Capacity>

24S 1 AS2 (K73) 2,3 Relay Systems /ABB AR 1-DG-CP-SO Panel CB 21.5 31 Plant Document Demand Note: Bldg.= Building, Gr.= Analysis Group Number Page 41of43

Seabrook Station Seismic High Frequency Confirmation Table B-2: Results of the analysis Group Building Elev. Enclosure Type Manufacturer Type/Model Number Horizontal Seismic Margin Vertical Seismic Margin 1 Control Building 50 Wall Mounted Panel AB 700-P400A1 1.429 2.086 2 Control Building 21.5 Switchgear GE CEH 1.160 1.058 3 Control Building 21.5 Motor Control Center AGASTAT E7012AA 2.184 2.203 4 Control Building 21.5 Switchgear AGASTAT E7012AE 2.383 4.807 5 Diesel Generator Building 21.5 Control Panel AGASTAT E7012PC 1.456 1.835 6 Diesel Generator Building 21.5 Control Panel AGASTAT E7014PC 1.165 1.468 7 Diesel Generator Building 21.5 Control Panel AGASTAT E7022PE 1.683 2.121 8 Control Building 21.5 Switchgear ELECTROSWITCH LOR/ER 2.742 5.530 9 Control Building 21.5 Switchgear ITE Unknown 1.160 1.058 10 Control Building 21.5 Switchgear GE 121AC53B811A 1.160 1.058 11 Control Building 21.5 Switchgear GE 121AC66B4A 1.160 1.058 12 Control Building 21.5 Switchgear GE 121AC77A803A 1.160 1.058 13 Control Building 21.5 Switchgear GE ICW 1.160 1.058 14 Diesel Generator Building 21.5 Control Panel GE CR-120BD 1.191 1.233 15 Diesel Generator Building 21.5 Control Panel GE CR-120BD 2.309 2.248 16 Control Building 21.5 Switchgear GE IJCV 1.160 1.058 17 Control Building 21.5 Switchgear GE HGA 1.160 1.058 18 Diesel Generator Building 21.5 Control Panel Unknown Unknown 2.309 2.248 19 Diesel Generator Building 21.5 Control Panel ITE J13 1.654 2.085 20 Control Building 21.5 Switchgear ITE J13 1.240 2.502 Page 42 of 43

Seabrook Station Seismic High Frequency Confirmation Group Building Elev. Enclosure Type Manufacturer Type/Model Number Horizontal Seismic Margin Vertical Seismic Margin 21 Control Building 21.5 Motor Control Center ITE J10 3.191 2.347 22 Control Building 21.5 Switchgear ITE HK350 1.160 1.058 23 Control Building 21.5 Switchgear ITE 62L 1.160 1.058 24 Control Building 75 Control Panel POTTER BRUMFIELD MDR-4121-1 1.235 2.169 25 Control Building 75 Control Panel POTTER BRUMFIELD MDR-4103-1 1.235 2.169 26 Not used.

27 Diesel Generator Building 21.5 Control Panel Unknown Unknown 2.309 2.248 28 Control Building 75 Control Panel STRUTHERS-DUNN 219XBX234 1.191 2.550 29 Control Building 21.5 Switchgear w AR 1.160 1.058 30 Control Building 75 Control Panel w NAS1 1.227 3.244 31 Control Building 21.5 Control Panel W/ABB AR 2.329 2.937 32 Control Building 21.5 Switchgear WE AR 1.160 1.058 33 Control Building 21.5 Switchgear WEST. AR 1.160 1.058 34 Control Building 21.5 Motor Control Center Unknown Unknown 3.191 2.347 35 Diesel Generator Building 21.5 Control Panel Unknown Unknown 2.309 2.248 Page 43 of 43

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