L-MT-15-030, Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Response to Requests for Additional Information

Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Response to Requests for Additional Information

ML15142A862
Person / Time
Site:	Monticello
Issue date:	05/22/2015
From:	Gardner P Northern States Power Co, Xcel Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
L-MT-15-030
Download: ML15142A862 (21)

Text

Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 May 22, 2015 L-MT-15-030 10 CFR 50.54(f)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Monticello Nuclear Generating Plant Docket No. 50-263 Renewed Facility Operating License No. DPR-22 Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) -

Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 -

Response to Requests for Additional Information

References:

1) NRC Letter, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident dated March 12, 2012. (ADAMS Accession No. ML12056A046)

2) Letter from K. Fili (NSPM) to Document Control Desk (NRC), Request Commitment Change for Response to NRC Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, L-MT-14-027, dated March 31, 2014. (ADAMS Accession No. ML14090A297)

3) Letter from K. Fili (NSPM) to Document Control Desk (NRC), Monticello Nuclear Generating Plant: Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1, L-MT-14-093, dated December 23, 2014. (ADAMS Accession No. ML14357A280)

4) Email from S. Wyman (NRC) to J. Fields (NSPM), Monticello ESEP Report Clarifications, dated April 8, 2015.

On March 12, 2012, the NRC issued Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (information request) to all NRC power reactor licensees and holders of construction permits in active or deferred status (Reference 1).

December 1 NSPM provided the ESEP the 3).

On 8, 2015, the NRC sent an email (Reference which contained requests additional information (RAis) related to the ESEP report provided in Reference 3. of this letter provides a response to the RAis provided by the NRC. provides a revised Expedited Seismic Equipment List (ESEL) that addresses discussion provided in specific RAI responses.

If there are any questions or if additional information is needed, please contact John Fields, Fukushima Response Licensing, at 763-271-6707.

Summary of Commitments This letter contains two new commitments and no revisions to existing commitments.

The response to RAI 7 contains information regarding these commitments.

I declare under penalty of perjury that the foregoing is true and correct Executed on May 2015.

Peter Gardner Site Vice President, Monticello Nuclear Generating Plant Northern States Power Company- Minnesota Enclosures cc: Administrator, Region Ill, USNRC Director of Nuclear Reactor Regulation (NRR), USNRC NRR Project Manager, MNGP, USNRC Senior Resident Inspector, MNGP, USNRC

L-MT-15-030 ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT RESPONSE TO REQUESTS FOR ADDITIONAL INFORMATION (RAIs)

FOR THE EXPEDITED SEISMIC EVALUATION PROCESS REPORT This enclosure provides responses from Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy, to requests for additional information (RAls) provided by the Nuclear Regulatory Commission (NRC) in an email dated April 8, 2015 (Reference 1).

The NRC question is provided below in italics font and the NSPM response is provided in normal font.

NRC Question 1 Please clarify if the RCIC CST suction valve should be included in the ESEP scope or discuss why it is not necessary.

NSPM Response The Reactor Core Isolation Cooling (RCIC) to Condensate Storage Tank (CST) suction path is not included in the ESEP scope as it is a secondary path in a seismic event because the CST is not seismically designed.

Following a seismic event that damages the CSTs, the torus RCIC suction valves (MO-2100 and MO-2101) open on low CST level. When these valves are fully open, CST to RCIC suction valve (MO-2102) will close via the relay interlocks described below.

Should MO-2102 fail to close, a check valve in the CST suction line will prevent flow of torus water to the CSTs. Therefore, MO-2102 is not required to close following a seismic event.

Interlocks exist between valve MO-2102 and valves MO-2100 and MO-2101, that are included in the ESEP Scope. For valve MO-2100 this interlock is by relay 13A-K18.

For valve MO-2101 the interlock is by relay 13A-K19. Both of these relays, 13A-K18 and 13A-K19, are included in the Expedited Seismic Equipment List (ESEL) (Table A-1 in the ESEP Report and also in the revised ESEL provided in Enclosure 2 to this letter).

Specifically, these relays are identified as items 285 and 286.

Page 1 of 7

L-MT-15-030 NRC Question 2 The ESEP submittal identifies the Residual Heat Removal Service Water System as a flow-path for Phase 2 Core Cooling; however, it appears that the ESEL does not contain components within this flow-path, except for the passive RHR system heat exchangers.

Confirm that no additional components within this flow-path are required to be evaluated per the ESEP guidance. For example, confirm if any motor-operated valves in the identified flow-path are required to change position and whether they are feasible to be operated manually and locally. In addition, if these motor operated valves can be operated manually, confirm that this operator manual action is the credited action as a part of the FLEX strategies and the Sequence of Events.

NSPM Response The Residual Heat Removal Service Water (RHRSW) flow path for Phase 2 includes piping and manual valves. The RHRSW valves in this flow path were included in the initial ESEL screening and were screened out based on their passive function.

Components in the same flow path which are part of other systems, including Residual Heat Removal (RHR) and Fuel Pool Cooling (FPC), are included in the initial screening and, where appropriate, in the ESEL.

NRC Question 3 In attachment A, the ESEL, there are a large number of items that have blank operating states and note/comment. Please update the table with the appropriate information.

NSPM Response NSPM provides the table in Enclosure 2 with the information requested, including:

Solenoid Valves (SV) normal and desired states, Hard Pipe Vent (HPV) Air Operated (AO) Valves normal and desired states, Safety Relief Valves (SRV) normal and desired states, Updated notes to identify components included only for pressure boundary considerations.

NRC Question 4 8 relays in the ESEL are identified as bad actors, and are assigned a functional HCLPF capacity = 0.0. Of the 18 remaining relays, 17 relays are designated with a HCLPF capacity = 0.21g, based on the anchorage capacity of the parent (i.e., rule of the box). For these 17 relays, identify the functional HCLPF capacities, and also discuss how in-cabinet amplification was considered in determining the functional capacity for each relay.

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L-MT-15-030 NSPM Response The functional capacities (High Confidence of a Low Probability of Failure (HCLPF)) of the subject 17 relays are shown in Table 4-1 below. Base capacities were drawn from EPRI NP-7147-SL, Seismic Ruggedness of Relays (Reference 2), manufacturer test data, and Seismic Qualification Utility Reports and Testing Standardization (SQURTS) reports, as appropriate.

Table 4-1 HCLPF for Relays Component ID Functional Component ID Functional Capacity (g) Capacity (g) 13A-K1 2.40 13A-K22 2.40 13A-K2 2.40 13A-K27 2.40 13A-K6 2.40 13A-K31 3.20 13A-K7 3.20 13A-K32 2.40 13A-K10 2.40 13A-K33 4.00 13A-K12 2.40 13A-K34 2.40 13A-K16 2.40 13A-K37 4.80 13A-K18 2.40 K102A 1.06 13A-K19 2.40 In lieu of cabinet amplification factors, the in-cabinet response spectra were calculated for these relays using the procedure from EPRI NP-7148-SL, Procedure for Evaluating Nuclear Power Plant Relay Seismic Functionality (Reference 3), and the GenRS software. Thus, cabinet amplification factors were not required to be determined.

NRC Question 5 12 switches in the ESEL are identified as No public capacity data available for this item. and are assigned a HCLPF capacity = 0.0. Of the remaining 37 switches, 35 switches apparently have a HCLPF capacity controlled by something other than function. For these 35 switches, identify the functional HCLPF capacities, and also discuss how in-cabinet amplification was considered in determining the functional capacity for each switch.

NSPM Response The functional capacities (HCLPF) of the 35 subject switches are listed in Table 5-1 below. Base capacities were drawn from EPRI NP-7147-SL (Reference 2),

manufacturer test data, and SQURTS testing, as appropriate. In-cabinet amplification factors were conservatively taken uniformly as 4.5 from EPRI NP-6041-SL, A Methodology for Assessment of Nuclear Power Plant Seismic Margin, Revision 1 (Reference 4), calculated using the procedure from EPRI NP-7148-SL using GenRS, or Page 3 of 7

L-MT-15-030 taken as unity if the item does not belong within a host, as appropriate. Table 5-1 below shows these results.

Table 5-1 Switch Functional HCLPF Capacities Component ID Functional Host ID Cabinet Amplification Factor Capacity (g) (Per Table Q-1, NP-6041-SL) dPIS-13-84 0.29 C-122 N/A1 TS-13-79A-1 7.16 N/A 1.02 TS-13-79A-2 7.16 N/A 1.02 TS-13-79B-1 7.16 N/A 1.02 TS-13-79B-2 7.16 N/A 1.02 TS-13-79C-1 7.16 N/A 1.02 TS-13-79C-2 7.16 N/A 1.02 TS-13-79D-1 7.16 N/A 1.02 TS-13-79D-2 7.16 N/A 1.02 TS-13-80A-1 7.16 N/A 1.02 TS-13-80B-1 7.16 N/A 1.02 TS-13-80C-1 7.16 N/A 1.02 TS-13-80D-1 7.16 N/A 1.02 TS-13-81A-1 7.16 N/A 1.02 TS-13-81B-1 7.16 N/A 1.02 TS-13-81C-1 7.16 N/A 1.02 TS-13-81D-1 7.16 N/A 1.02 TS-13-82A-1 7.16 N/A 1.02 TS-13-82B-1 7.16 N/A 1.02 TS-13-82C-1 7.16 N/A 1.02 TS-13-82D-1 7.16 N/A 1.02 TS-13-80A-2 7.16 N/A 1.02 TS-13-80B-2 7.16 N/A 1.02 TS-13-80C-2 7.16 N/A 1.02 TS-13-80D-2 7.16 N/A 1.02 TS-13-81A-2 7.16 N/A 1.02 TS-13-81B-2 7.16 N/A 1.02 TS-13-81C-2 7.16 N/A 1.02 TS-13-81D-2 7.16 N/A 1.02 TS-13-82A-2 7.16 N/A 1.02 TS-13-82B-2 7.16 N/A 1.02 TS-13-82C-2 7.16 N/A 1.02 TS-13-82D-2 7.16 N/A 1.02 PS-13-72A 3.81 C-128 4.5 PS-13-72B 3.81 C-128 4.5 Notes:

1. GenRS used to calculate the In-cabinet response spectra.

2. Item does not belong within a host; thus no in-cabinet amplification occurs.

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L-MT-15-030 NRC Question 6 There are approximately 50 ESEL items identified as inaccessible because they are inside the drywell. The licensee does NOT intend to complete a walk-by or remote visual of the inaccessible ESEL items at a later date. It is relying on A-46 walkdown results, which are around 20 years old. This appears to be inconsistent with the augmented approach proposed by EPRI and accepted by NRC. Discuss the technical basis why these approximately 50 items do not need to be looked at, in order to verify condition and re-affirm the A-46 walkdown results.

NSPM Response For inaccessible components, NSPM relied on walk downs performed to meet the A-46 issue, the Recommendation 2.3 seismic walk downs performed in 2013 and in specific cases, other information as described below. The 2013 walkdowns observed the following components and areas in the drywell: (1) inboard Main Steam Isolation Valve (MSIV) - AO-2-80A, (2) SRV - RV-2-71A, (3) area walk-bys on the 933 and 951 elevations of the drywell. There was nothing noteworthy found during these walk downs.

The ESEL equipment that was determined to be inaccessible (due to location in the drywell) included valves, accumulators and temperature elements. Each component type was assessed as follows:

For valves, the Seismic Review Team (SRT) gathered valve drawings in addition to the A-46 Screening Evaluation Work Sheets (SEWS) and pictures, and performed the valve evaluation based on the methodology presented in EPRI NP 6041-SL (Reference 4).

Temperature elements were evaluated based on A-46 walk down notes and pictures.

These components are directly attached/secured to structural components. Therefore, the SRT determined that the information was adequate for the ESEP purpose.

Accumulators were evaluated based on the A-46 notes and pictures. Typically two large U bolt connections were utilized to secure the accumulator. With the large margin of these items, the SRT determined that the information was adequate for the ESEP purpose.

NRC Question 7 Section 8.2 identifies 24 ESEL components that have a HCLPF capacity less than the RLGM; 23 are relays and switches. A more detailed analysis of capacity for the RHR Heat Exchanger E-200B anchorage, and changing the bolting material are discussed as options, but have not been implemented. 20 of the 23 relays and switches lack adequate qualification test data. Several avenues for resolution are discussed, but none have been implemented. In Section 8.4, the Licensee indicates that the 24 components Page 5 of 7

L-MT-15-030 are entered into the plant Corrective Actions Program (CAP) for resolution. The analysis and completion of the 24 components should have been part of the submittal.

There are no regulatory commitments made in the ESEP submittal. Discuss the status of the resolution for each of the 24 components, including the method being employed, the schedule for completing the resolution activities, and the schedule for implementing any required hardware modifications. Also discuss the technical basis for relying on the plant CAP for resolution, in lieu of including regulatory commitments in the ESEP submittal, consistent with the EPRI Augmented Approach guidance.

NSPM Response Below, in Table 7-1 is a summary of the 24 components identified in the ESEP report that do not have sufficient seismic capacity to withstand the Review Level Ground Motion (RLGM) and the plan and schedule for resolving each item. Each components HCLPF will exceed RLGM when the resolution activities are completed.

NRC Commitments 1 - A letter will be provided to the NRC indicating the proposed resolution applicable to each component and the expected timeframe for completion of the resolution when this information has been developed.

2 - A letter will be provided to the NRC summarizing the HCLPF results of each component and confirming the resolution of each component. This letter will be sent within 60 days of completion of the resolution activity(ies) for the final completed component from Table 7-1.

Table 7 Components Requiring Action to Verify HCLPF Capacity Values are Met Components Proposed Resolution Schedule E-200B - bolts on heat Complete further Resolutions will be exchanger supports evaluation and completed by implement 12/31/2016 unless a HGA Relays 13A-K13, 14, 17, 3, modifications, if plant outage is needed 5, 29, 30, and 28 required, to increase to implement a Agastat Relay K102B seismic margin so that modification. In that Instruments dPIS-13-83, and 84 HCLPF will exceed case, the outage RLGM for the modification will be Instruments PS-13-87A, B, C, components identified completed prior to the and D in this table. end of the 2017 Instruments LIS-2-3-672A, B, C, refueling outage.

and D and LS-2-3-672E and F Instruments LS-23-74 and 75 Page 6 of 7

L-MT-15-030 References

1) Email from S M Wyman (NRC) to J Fields (NSPM), Monticello ESEP Report Clarifications, dated April 8, 2015.

2) EPRI Report No.: NP-7147-SL, Seismic Ruggedness of Relays, August 1991

3) EPRI Report No.: NP-7148-SL, Procedure for Evaluating Nuclear Power Plant Relay Seismic Functionality, December 1990

4) EPRI Report No.: NP-6041-SL, A Methodology for Assessment of Nuclear Power Plant Seismic Margin, Revision 1 Page 7 of 7

L-MT-15-030 ENCLOSURE 2 REVISED EXPEDITED SEISMIC EQUIPMENT LIST (ESEL)

TO SUPPORT RAI RESPONSES Note: The table provided in Enclosure 2 supersedes Table A-1 from the Expedited Seismic Evaluation Process Report found in the Enclosure to NSPM letter L-MT-14-093, dated December 23, 2014 (ADAMS Accession No. ML14357A280) 11 pages follow

L-MT-15-030 Table A MNGP ESEL (Revised)

ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments RHR DIV 1 HEAT 1 E-200A -- -- Pressure Boundary EXCHANGER RHR DIV 2 HEAT 2 E-200B -- -- Pressure Boundary EXCHANGER Interlocks w/MO2102 (See NX78225, RCIC TORUS SUCTION 3 MO-2100 Closed Open relay 13AK19.) MO2100 (Local) on INBOARD NX7822222.

Interlocks w/MO2102 (See NX78225, RCIC TORUS SUCTION 4 MO-2101 Closed Open relay 13AK18.) MO2101 (Local) on OUTBOARD NX7822222.

RCIC PUMP SUCTION 5 RV-2103 -- -- Pressure boundary RELIEF VALVE 6 P-207 RCIC PUMP Standby Operating RCIC PUMP DISCHARGE 7 MO-2106 Closed Open Open on Rx Vessel Lvl Low OUTBOARD RCIC PUMP DISCHARGE 8 MO-2107 Closed Open Open on Rx Vessel Lvl Low INBOARD RCIC TEST FLOW Close on Reactor Vessel Low-low Lvl or 9 MO-2110 Closed Closed ISOLATION MO-2100 or MO-2101 Open Full RCIC TEST RETURN Close on Reactor Vessel Low-low Lvl or 10 MO-3502 Closed Closed ISOLATION MO-2100 or MO-2101 Open Full RCIC PUMP MINIMUM 11 CV-2104 Closed Open Fails Open on Loss of Air FLOW RCIC COOLING WATER 12 PCV-2092 TO BAROMETRIC -- -- Pressure boundary CONDENSER RCIC BAROMETRIC Close on Rx Vessel Lvl High/Open on Rx 13 MO-2096 CONDENSER COOLING Closed Open Vessel Lvl Low WATER SUPPLY COOLING WATER TO BAROMETRIC 14 RV-2097 -- -- Pressure boundary CONDENSER RELIEF VALVE 15 E-205 RCIC OIL COOLER -- -- Pressure boundary RCIC BAROMETRIC 16 E-203 -- -- Pressure boundary CONDENSER RCIC TURBINE BAROMETRIC 17 P-210 Standby Operating CONDENSER CONDENSATE PUMP RCIC BAROMETRIC P-211 CONDENSER VACUUM Standby Operating 18 PUMP RCIC STEAM LINE Close on High Flow/Open on Reactor MO-2076 Open Open 19 ISOLATION OUTBOARD vessel Low Level/Steam line Monitoring RCIC TURBINE STEAM Close on Rx Vessel Lvl High/Open on Rx 20 MO-2078 Closed Open SUPPLY Vessel Lvl Low RCIC TURBINE TRIP 21 MO-2080 Open Open Close on Turbine Trip RESET MOTOR (HO-7)

RCIC TURBINE 22 HO-8 Standby Operating GOVERNING VALVE 23 S-200 RCIC TERRY TURBINE Standby Operating CV-2104 MINIMUM FLOW 24 T-73 VALVE ACCUMULATOR -- -- Pressure boundary TANK 25 SV-2104 CV-2104 SOLENOID Energized Energized 26 SV-2848 CV-2848 SOLENOID De-energized De-energized 27 SV-2849 CV-2849 SOLENOID De-energized De-energized 28 SV-2082A CV-2082A SOLENOID Energized De-energized 29 SV-2082B CV-2082B SOLENOID Energized De-energized Page 1 of 11

L-MT-15-030 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments 11 CORE SPRAY PUMP 30 RV-1745 DISCHARGE RELIEF -- -- Pressure boundary VALVE 31 RV-2-71H H SRV Closed Open / Closed 32 SV-2-71H H SRV AIR OPERATOR SV De-energized Energized H SRV ASDS AIR 33 SV-2-71L De-energized Energized OPERATOR SV 34 RV-2-71C C SRV Closed Open / Closed C SRV AIR OPERATOR 35 SV-2-71C De-energized Energized SV 36 RV-2-71D D SRV Closed Open / Closed D SRV AIR OPERATOR 37 SV-2-71D De-energized Energized SV PRI STEAM SRV D 38 T-57C -- -- Pressure boundary ACCUMULATOR PRI STEAM SRV D 39 T-57D -- -- Pressure boundary ACCUMULATOR PRI STEAM SRV D 40 T-57H -- -- Pressure boundary ACCUMULATOR PRI STEAM SRV D 41 T-57F -- -- Pressure boundary ACCUMULATOR 42 RV-2-71F F SRV Closed Open / Closed F SRV AIR OPERATOR 43 SV-2-71F De-energized Energized SV F SRV ASDS AIR 44 SV-2-71M De-energized Energized OPERATOR SV 45 RV-2-71E E SRV Closed Open / Closed E SRV AIR OPERATOR 46 SV-2-71E De-energized Energized SV E SRV ASDS AIR 47 SV-2-71J De-energized Energized OPERATOR SV 48 RV-2-71A A SRV Closed Open / Closed A SRV AIR OPERATOR 49 SV-2-71A De-energized Energized SV 50 RV-2-71B B SRV Closed Open / Closed B SRV AIR OPERATOR 51 SV-2-71B De-energized Energized SV 52 RV-2-71G G SRV Closed Open / Closed 53 SV-2-71G G SRV AIR OPERATOR SV De-energized De-energized G SRV ASDS AIR 54 SV-2-71K De-energized De-energized OPERATOR SV PRI STEAM SRV G 55 T-57A -- -- Pressure boundary ACCUMULATOR PRI STEAM SRV G 56 T-57B -- -- Pressure boundary ACCUMULATOR PRI STEAM SRV G 57 T-57E -- -- Pressure boundary ACCUMULATOR PRI STEAM SRV G 58 T-57G -- -- Pressure boundary ACCUMULATOR 59 RV-3243A B SRV DISCH 8" VAC RV -- -- Pressure boundary 60 RV-7467A G SRV DISCH 8" VAC RV -- -- Pressure boundary 61 RV-7440A E SRV DISCH 8" VAC RV -- -- Pressure boundary 62 RV-3242A A SRV DISCH 8" VAC RV -- -- Pressure boundary 63 RV-7468A H SRV DISCH 8" VAC RV -- -- Pressure boundary 64 RV-3244A C SRV DISCH 8" VAC RV -- -- Pressure boundary 65 RV-3245A D SRV DISCH 8" VAC RV -- -- Pressure boundary 66 RV-7441A F SRV DISCH 8" VAC RV -- -- Pressure boundary HPCI Initiated on Lo-Lo Reactor Water or HPCI STEAM LINE High Drywell Pressure (OPEN)/Close on 67 MO-2035 Open Closed ISOLATION OUTBOARD High Flow/Close on Steam Leak. See Footnote 1.

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L-MT-15-030 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments HPCI TEST RETURN 68 CV-3503 Energized Energized See Footnote 1.

FLOW HPCI TEST RETURN 69 MO-2071 Closed Closed See Footnote 1.

ISOLATION RCIC PUMP SUCTION 70 PT-13-65 Energized Energized Signal to PI-13-96 PRESSURE 71 PI-13-96 RCIC PUMP SUCTION -- -- Control Room Indication RCIC LOW PUMP 72 PS-13-67A SUCTION PRESSURE Energized Energized RCIC Turbine Trip TURBINE TRIP RCIC PUMP DISCHARGE 73 PT-13-60 Energized Energized Control Room Indication PRESSURE 74 PI-13-93 RCIC PUMP DISCHARGE -- -- Control Room Indication RCIC PUMP DISCHARGE 75 FS-13-57 Energized Energized MINIMUM FLOW CONTROL RCIC PUMP DISCHARGE 76 FT-13-58 Energized Energized RCIC Turbine Control Logic FLOW CONTROL 77 FIC-13-91 RCIC PUMP FLOW Energized Energized Control Room Indication 78 FI-13-91 RCIC FLOW Energized Energized Control Room Indication RCIC PUMP FLOW LOOP 79 FY-13-102 Energized Energized RCIC Turbine Control Logic ISOLATOR RCIC CONDENSER HIGH 80 LS-7323 VACUUM TANK LEVEL -- -- Pressure boundary ALARM RCIC HIGH STEAM FLOW 81 dPIS-13-83 Energized Energized ISOLATION RCIC HIGH STEAM FLOW 82 dPIS-13-84 Energized Energized ISOLATION RCIC TURBINE STEAM 83 PS-13-87A SUPPLY LOW PRESS Energized Energized Local per NX-7822-22-3 ISOLATION RCIC TURBINE STEAM 84 PS-13-87B SUPPLY LOW PRESS Energized Energized Local per NX-7822-22-3 ISOLATION RCIC TURBINE STEAM 85 PS-13-87C SUPPLY LOW PRESS Energized Energized Local per NX-7822-22-3 ISOLATION RCIC TURBINE STEAM 86 PS-13-87D SUPPLY LOW PRESS Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 87 TS-13-79A-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 88 TS-13-79A-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 89 TS-13-79B-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 90 TS-13-79B-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION 1

HPCI valves MO2035, MO2071 and CV3503 are included as part of the ESEL, because although not credited in any FLEX strategy, HPCI is safetyrelated and would automatically initiate in the event of an SBO, and would be secured as part of the ELAP procedures. The test line return path to the CST represents a potential problem for implementation of FLEX strategies because any water that is directed from the Torus to the CST would be lost should either valve fail to close. Therefore, the HPCI test line valves were included in the ESEL to ensure that if HPCI runs prior to being secured; the flow is only directed to the reactor or Torus. MO2035 is closed as part of SBO procedures.

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L-MT-15-030 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments RCIC STEAM LINE HIGH 91 TS-13-79C-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 92 TS-13-79C-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 93 TS-13-79D-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 94 TS-13-79D-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 95 TS-13-80A-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 96 TS-13-80B-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 97 TS-13-80C-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 98 TS-13-80D-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 99 TS-13-81A-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 100 TS-13-81B-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 101 TS-13-81C-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 102 TS-13-81D-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 103 TS-13-82A-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 104 TS-13-82B-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 105 TS-13-82C-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 106 TS-13-82D-1 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 107 TS-13-80A-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 108 TS-13-80B-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 109 TS-13-80C-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 110 TS-13-80D-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 111 TS-13-81A-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION Page 4 of 11

L-MT-15-030 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments RCIC STEAM LINE HIGH 112 TS-13-81B-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 113 TS-13-81C-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 114 TS-13-81D-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 115 TS-13-82A-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 116 TS-13-82B-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 117 TS-13-82C-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC STEAM LINE HIGH 118 TS-13-82D-2 AREA TEMPERATURE Energized Energized Local per NX-7822-22-3 ISOLATION RCIC TURBINE STEAM 119 PT-13-68 Energized Energized Signal to PI-13-94 SUPPLY PRESSURE 120 PI-13-94 RCIC TURBINE INLET Energized Energized Control Room Indication RCIC TURBINE SPEED 121 SY-7321 -- -- Control Room Indication SIGNAL CONVERTER RCIC TURBINE SPEED 122 SCP-7925 -- -- Control Room Indication GOVERNOR EGM RCIC TURBINE SPEED 123 SE-7925 -- -- Control Room Indication MAGNETIC PICKUP RCIC TURBINE 124 LS-5 OVERSPEED TRIP LEVEL -- -- Control Room Indication SWITCH RCIC TURBINE EXHAUST 125 PT-13-70 -- -- Control Room Indication PRESSURE 126 PI-13-95 RCIC TURBINE EXHAUST -- -- Control Room Indication RCIC HIGH TURBINE 127 PS-13-72A EXHAUST PRESSURE Energized Energized Turbine Trip TURBINE TRIP RCIC HIGH TURBINE 128 PS-13-72B EXHAUST PRESSURE Energized Energized Turbine Trip TURBINE TRIP REACTOR FLOODING 129 LT-2-3-61 Energized Energized LEVEL REACTOR PRESSURE 130 PT-6-53B WIDE RANGE B (REF Energized Energized COLUMN A)

FW REACTOR PRESS TO 131 PI-6-90B -- -- Control Room Indication B LVL CONTROL REACTOR VESSEL 132 LT-2-3-85B WATER LEVEL (FROM Energized Energized COLUMN A)

REACTOR VESSEL 133 LI-2-3-85B Energized Energized WATER LEVEL LO LO REACTOR LVL 134 LT-2-3-72A Energized Energized ECCS INITIATION LO LO REACTOR LVL 135 LT-2-3-72C Energized Energized ECCS INITIATION 136 LIS-2-3-672A HPCI LO LEVEL START Energized Energized 137 LIS-2-3-672C HPCI LO LEVEL START Energized Energized HPCI/RCIC HI LVL TURB 138 LS-2-3-672E Energized Energized Trip unit TRIP LO LO REACTOR LVL 139 LT-2-3-72B Energized Energized ECCS INITIATION Page 5 of 11

L-MT-15-030 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments LO LO REACTOR LVL 140 LT-2-3-72D Energized Energized ECCS INITIATION 141 LIS-2-3-672B HPCI LO LEVEL START Energized Energized 142 LIS-2-3-672D HPCI LO LEVEL START Energized Energized HPCI/RCIC HI LVL TURB 143 LS-2-3-672F Energized Energized Trip unit TRIP REACTOR VESSEL 144 LT-2-3-85A WATER LEVEL (FROM Energized Energized COLUMN B)

REACTOR VESSEL 145 LI-2-3-85A Energized Energized WATER LEVEL REACTOR PRESSURE 146 PT-6-53A WIDE RANGE A (REF Energized Energized COLUMN B)

FW REACTOR PRESS TO 147 PI-6-90A Energized Energized Control Room Indication A LVL CONTROL RX WTR LEVEL B FUEL 148 LT-2-3-112B Energized Energized ZONE (REF COLUMN A)

LOW LOW SET REACTOR 149 PT-4067B Energized Energized PRESSURE LOW LOW SET REACTOR 150 PT-4067D Energized Energized PRESSURE RX WTR LEVEL A FUEL 151 LT-2-3-112A Energized Energized ZONE (REF COLUMN B)

LOW LOW SET REACTOR 152 PT-4067A Energized Energized PRESSURE LOW LOW SET REACTOR 153 PT-4067C Energized Energized PRESSURE HPCI COND STORAGE 154 LS-23-74 Energized Energized RCIC Pump Suction Transfer Instruments TANK INTLK HPCI COND STORAGE 155 LS-23-75 Energized Energized RCIC Pump Suction Transfer Instruments TANK INTLK ALT N2 TRAIN A 156 PCV-4897 -- -- Pressure boundary PRESSURE REGULATOR ALT N2 TRAIN A 157 PCV-4879 -- -- Pressure boundary PRESSURE REGULATOR ALT N2 TRAIN A 158 PCV-4903 -- -- Pressure boundary PRESSURE REGULATOR ALT N2 TRAIN A 159 PCV-4904 -- -- Pressure boundary PRESSURE REGULATOR ALT N2 TRAIN A 160 SV-4234 De-energized De-energized MANIFOLD ISOLATION ALT N2 TRAIN A 161 RV-4673 -- -- Pressure boundary MANIFOLD RELIEF 162 RV-4878 ALT N2 TRAIN A RELIEF -- -- Pressure boundary ALT N2 TRAIN B 163 PCV-4898 -- -- Pressure boundary PRESSURE REGULATOR ALT N2 TRAIN B 164 PCV-4881 -- -- Pressure boundary PRESSURE REGULATOR ALT N2 TRAIN B 165 PCV-4905 -- -- Pressure boundary PRESSURE REGULATOR ALT N2 TRAIN B 166 PCV-4906 -- -- Pressure boundary PRESSURE REGULATOR ALT N2 TRAIN B 167 RV-4236 -- -- Pressure boundary MANIFOLD RELIEF ALT N2 TRAIN B 168 SV-4235 De-energized De-energized MANIFOLD ISOLATION ALTERNATE N2 TRAIN B 169 RV-4880 -- -- Pressure boundary RELIEF DRYWELL & TORUS 170 AO-2377 -- -- Included for N2 System Integrity Only PURGE OTBD ISOL 171 AO-2387 DW OTBD VENT -- -- Included for N2 System Integrity Only 172 AO-2896 TORUS MAIN EXHAUST -- -- Included for N2 System Integrity Only 173 AO-2378 TORUS PURGE INBD ISOL -- -- Included for N2 System Integrity Only Page 6 of 11

L-MT-15-030 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments 174 AO-2379 VACUUM RELIEF DAMPER -- -- Included for N2 System Integrity Only SV FOR AO-2379 TORUS 175 SV-2379 TO RX BLDG VACUUM Energized Energized Energized maintains N2 on the seal BREAKER 176 AO-2380 VACUUM RELIEF DAMPER -- -- Included for N2 System Integrity Only SV FOR AO-2380 TORUS 177 SV-2380 Energized Energized Energized maintains N2 on the seal VACUUM RELIEF DRYWELL PURGE INBD 178 AO-2381 -- -- Included for N2 System Integrity Only ISOL 179 AO-2383 TORUS VENT -- -- Included for N2 System Integrity Only DW PURGE EXHAUST 180 AO-2386 -- -- Included for N2 System Integrity Only INBD N2 SUPPLY TO HPV 181 SV-4539 INBOARD ISOLATION De-energized Energized A0-4539 N2 SUPPLY FOR HPV 182 SV-4540 OUTBD ISOLATION De-energized Energized AO-4540 INBOARD N2 SUPPLY TO 183 SV-4541 De-energized Energized HPV RUPTURE DISC OUTBOARD N2 SUPPLY 184 SV-4542 De-energized Energized TO HPV RUPTURE DISC HARD PIPE VENT 185 AO-4539 INBOARD ISOLATION Closed Open Fail Closed VALVE HARD PIPE VENT 186 AO-4540 OUTBOARD ISOLATION Closed Open Fail Closed VALVE ALT N2 TRAIN A SUPPLY 187 PS-4662 -- -- Pressure boundary ISOLATION/ALARM ALT N2 TRAIN B SUPPLY 188 PS-4237 -- -- Pressure boundary ISOLATION/ALARM TORUS WIDE RANGE 189 LT-7338A Energized Energized LEVEL TORUS WIDE RANGE 190 LY-7338B Energized Energized LEVEL TORUS WIDE RANGE 191 LT-7338B Energized Energized LEVEL DRYWELL WIDE RANGE 192 PT-7251A Energized Energized PRESSURE DW PRESS-TOR LVL-DW 193 PLR-7251A -- --

RAD-ACCD/RNG DRYWELL WIDE RANGE 194 PT-7251B Energized Energized PRESSURE PRIMARY CONTAINMENT 195 PY-7251B WIDE RANGE PI Energized Energized ISOLATOR DW PRESS-TOR LVL-DW 196 PLR-7251B -- --

RAD-ACCD/RNG TORUS SENSOR 1 -

197 TE-4073A SRV71H / RCIC Energized Energized DISCHARGE AREA TORUS SENSOR 2 -

198 TE-4074A SRV71C DISCHARGE Energized Energized AREA TORUS SENSOR 3 -

199 TE-4075A SRV71B DISCHARGE Energized Energized AREA TORUS SENSOR 4 -

200 TE-4076A SRV71G / HPCI Energized Energized DISCHARGE AREA TORUS SENSOR 5 -

201 TE-4077A SRV71A DISCHARGE Energized Energized AREA Page 7 of 11

L-MT-15-030 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments TORUS SENSOR 6 -

202 TE-4078A SRV71E DISCHARGE Energized Energized AREA TORUS SENSOR 7 -

203 TE-4079A SRV71F DISCHARGE Energized Energized AREA TORUS SENSOR 8 -

204 TE-4080A SRV71D DISCHARGE Energized Energized AREA TORUS SENSOR 1 -

205 TE-4073B SRV71H / RCIC Energized Energized DISCHARGE AREA TORUS SENSOR 2 -

206 TE-4074B SRV71C DISCHARGE Energized Energized AREA TORUS SENSOR 3 -

207 TE-4075B SRV71B DISCHARGE Energized Energized AREA TORUS SENSOR 4 -

208 TE-4076B SRV71G / HPCI Energized Energized DISCHARGE AREA TORUS SENSOR 5 -

209 TE-4077B SRV71A DISCHARGE Energized Energized AREA TORUS SENSOR 6 -

210 TE-4078B SRV71E DISCHARGE Energized Energized AREA TORUS SENSOR 7 -

211 TE-4079B SRV71F DISCHARGE Energized Energized AREA TORUS SENSOR 8 -

212 TE-4080B SRV71D DISCHARGE Energized Energized AREA 213 TI-4072A DIV 1 TORUS TEMP Energized Energized 214 TI-4072B DIV 2 TORUS TEMP Energized Energized 215 TY-4072A DIV 1 TORUS TEMP Energized Energized 216 TY-4072B DIV 2 TORUS TEMP Energized Energized DW TEMPERATURE 217 TE-4247A ELEMENT (DUAL Energized Energized ELEMENT A1/A2)

DW TEMPERATURE 218 TE-4247B ELEMENT (DUAL Energized Energized ELEMENT B1/B2)

DW TEMPERATURE 219 TE-4247C ELEMENT (DUAL Energized Energized ELEMENT C1/C2)

DW TEMPERATURE 220 TE-4247D ELEMENT (DUAL Energized Energized ELEMENT D1/D2)

DW TEMPERATURE 221 TE-4247E ELEMENT (DUAL Energized Energized ELEMENT E1/E2)

DW TEMPERATURE 222 TE-4247F ELEMENT (DUAL Energized Energized ELEMENT F1/F2)

DW TEMPERATURE 223 TE-4247G ELEMENT (DUAL Energized Energized ELEMENT G1/G2)

DW TEMPERATURE 224 TE-4247H ELEMENT (DUAL Energized Energized ELEMENT H1/H2)

HARD PIPE VENT 225 RE-4544 Energized Energized RADIATION DETECTOR HARD PIPE VENT 226 RM-4544 Energized Energized RADIATION MONITOR Page 8 of 11

L-MT-15-030 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments 125 VDC CHARGER FOR DOOR #110 INSIDE ON SOUTH WALL, 227 D10 Energized Energized

1. 11 BATT EC720 replaced charger, 125 VDC CHARGER FOR DOOR #103 INSIDE ON NORTH WALL, 228 D20 Energized Energized

1. 12 BATT Mod 00Q370 replaced charger CHARGER, D3A (13) 229 D52 Energized Energized DOOR #109 INSIDE ON NORTH WALL BATTERY CHARGER, D3B (13) 230 D53 Energized Energized DOOR #109 INSIDE ON NORTH WALL BATTERY CHARGER, SWING D3A, 231 D54 Energized Energized DOOR #109 INSIDE ON NORTH WALL D3B (13) BATTERY CHARGER, D6B (16) 232 D70 Energized Energized Drawing Available BATTERY CHARGER, D6A (16) 233 D80 Energized Energized BATTERY CHARGER, SWING 234 D90 Energized Energized D6A,D6B (16) BATTERY DIV 1 120VAC CLASS 1E 235 Y71 Energized Energized INVERTER DIV 1 FUSED 236 Y75 Energized Energized DISCONNECT SWITCH DIV 1 UNINTERRUPTIBLE 237 Y70 120VAC CLASS 1E DIST Energized Energized PANEL DIV 2 120VAC CLASS 1E 238 Y81 Energized Energized NORTH SIDE INVERTER DIV 2 FUSED 239 Y85 Energized Energized DISCONNECT SWITCH DIV 2 UNINTERRUPTIBLE 240 Y80 120VAC CLASS 1E DIST Energized Energized NORTH SIDE PANEL 241 D1 #11 BATTERY 125VDC Energized Energized DOOR #110 DIV I 125VDC 242 D11 Energized Energized DOOR #110 INSIDE ON SOUTH WALL DISTRIBUTION CENTER 243 D2 #12 BATTERY 125VDC Energized Energized DIV I 125 VDC 244 D21 Energized Energized DOOR #103 INSIDE ON NORTH WALL DISTRIBUTION PANEL 125 VDC DISTRIBUTION 245 D33 Energized Energized DOOR #110 INSIDE ON SOUTH WALL CENTER DIV 2 125/250 VDC 246 D100 Energized Energized DISTRIBUTION PANEL DIV I 125/250 VDC 247 D31 Energized Energized DOOR #109 DISTRIBUTION PANEL

1. 13 (DIV 1) 125/250VDC 248 D3A Energized Energized DOOR #109 BATTERY "A"

1. 13 (DIV 1) 125/250VDC 249 D3B Energized Energized DOOR #109 BATTERY "B"

1. 16 (DIV 2) 125/250VDC 250 D6A Energized Energized SOUTH SIDE BATTERY "A"

1. 16 (DIV 2) 125/250VDC 251 D6B Energized Energized NORTH SIDE BATTERY "B" DIV 1 (RCIC) 250V DC 252 D311 MOTOR CONTROL Energized Energized CENTER CENTER 311 DIV 2 ( HPCI) 250V DC 253 D312 MOTOR CONTROL Energized Energized CENTER 312 DIV 1 (RCIC) 250V DC 254 D313 MOTOR CONTROL Energized Energized CENTER CENTER 313 RX AND CTMT COOLING 255 C-03 Energized Energized AND ISOL BENCH BOARD RWC RECIRCULATING 256 C-04 Energized Energized BENCH BOARD Page 9 of 11

L-MT-15-030 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments CHANNEL A PRIMARY 257 C-15 ISOL AND RPS VERTICAL Energized Energized NORTH OF C-05 BOARD RCIC CABLE SPR RM 258 C-30 Energized Energized CONTROL PANEL INBOARD ISOLATION 259 C-41 Energized Energized RELAY PANEL OUTBOARD ISOLATION 260 C-42 Energized Energized RELAY PANEL REACTOR VESSEL LEVEL 261 C-55 Energized Energized AND PRESSURE RACK REACTOR VESSEL LEVEL 262 C-56 Energized Energized AND PRESSURE RACK JET PUMP INSTRUMENT 263 C-121 Energized Energized RACK JET PUMP INSTRUMENT 264 C-122 Energized Energized RACK 265 C-128 RCIC INSTRUMENT RACK Energized Energized SRV LOW LOW SET DIV 1 266 C-253A Energized Energized CONTROL PANEL SRV LOW LOW SET DIV 2 267 C-253B Energized Energized CONTROL PANEL 268 C-292 ASDS BENCHBOARD Energized Energized A RHR, CORE SPRAY, ADS 269 C-32 Energized Energized CONTROL PANEL B RHR, CORE SPRAY, ADS 270 C-33 Energized Energized CONTROL PANEL ECCS DIV I ANALOG TRIP 271 C-303A Energized Energized SYSTEM ECCS DIV II ANALOG 272 C-303B Energized Energized TRIP SYSTEM REACTOR LOWLOW Energized / De-273 13A-K1 De-energized WATER LEVEL energized REACTOR LOWLOW Energized / De-274 13A-K2 De-energized WATER LEVEL energized STEAM LINE AREA HIGH 275 13A-K3 De-energized De-energized TEMPERATURE STEAM LINE AREA HIGH 276 13A-K5 De-energized De-energized TEMPERATURE MO2078 POSITION 277 13A-K6 De-energized Energized MONITOR RCIC STEAM LINE HIGH 278 13A-K7 DP (PRESSURE) STEAM De-energized De-energized LINE BREAK RELAY STEAM LINE LOW 279 13A-K10 De-energized De-energized PRESSURE GLAND SEAL VACUUM 280 13A-K12 De-energized De-energized PUMP CONTROL Energized / De-281 13A-K13 PUMP LOW FLOW De-energized energized PUMP LOW SUCTION 282 13A-K14 De-energized De-energized PRESSURE GLAND SEAL Energized / De-283 13A-K16 De-energized CONDENSER HIGH LEVEL energized TURBINE EXHAUST HIGH 284 13A-K17 De-energized De-energized PRESSURE MO2101 POSITION 285 13A-K18 De-energized De-energized MONITOR MO2100 POSITION 286 13A-K19 De-energized De-energized MONITOR 287 13A-K22 AUTO ISOLATION De-energized De-energized RCIC TRIP & THROTTLE 288 13A-K27 De-energized De-energized VALVE CLOSED Page 10 of 11

L-MT-15-030 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments STEAM LINE AREA HIGH 289 13A-K29 De-energized De-energized TEMPERATURE STEAM LINE AREA HIGH 290 13A-K30 De-energized De-energized TEMPERATURE STEAM LINE HIGH DP 291 13A-K31 De-energized De-energized (LINE BREAK) 292 13A-K32 RCIC AUTO ISOLATION De-energized De-energized RCIC TURBINE EXHAUST 293 13A-K33 HIGH PRESSURE TD De-energized De-energized RELAY REACTOR HIGH WATER 294 13A-K34 De-energized De-energized TURBINE TRIP 295 13A-K37 CST LOW LEVEL Energized Energized REACTOR HIGH WATER 295 13A-K28 De-energized De-energized LEVEL RELAY ECCS DIVISION I 297 K102A De-energized De-energized ANALOG TRIP CABINET RELAY ECCS DIVISION II 298 K102B De-energized De-energized ANALOG TRIP CABINET Page 11 of 11