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 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.

3).

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 Page 1 of 7 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.

L-MT-15-030 Page 2 of 7 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.

L-MT-15-030 Page 3 of 7 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 Capacity (g)

Component ID Functional 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

L-MT-15-030 Page 4 of 7 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 Capacity (g)

Host ID Cabinet Amplification Factor (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.

L-MT-15-030 Page 5 of 7 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

L-MT-15-030 Page 6 of 7 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 exchanger supports Complete further evaluation and implement modifications, if required, to increase seismic margin so that HCLPF will exceed RLGM for the components identified in this table.

Resolutions will be completed by 12/31/2016 unless a plant outage is needed to implement a modification. In that case, the outage modification will be completed prior to the end of the 2017 refueling outage.

HGA Relays 13A-K13, 14, 17, 3, 5, 29, 30, and 28 Agastat Relay K102B Instruments dPIS-13-83, and 84 Instruments PS-13-87A, B, C, and D Instruments LIS-2-3-672A, B, C, and D and LS-2-3-672E and F Instruments LS-23-74 and 75

L-MT-15-030 Page 7 of 7 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

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 Page 1 of 11 Table A MNGP ESEL (Revised)

ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments 1

E-200A RHR DIV 1 HEAT EXCHANGER Pressure Boundary 2

E-200B RHR DIV 2 HEAT EXCHANGER Pressure Boundary 3

MO-2100 RCIC TORUS SUCTION INBOARD Closed Open Interlocks w/MO2102 (See NX78225, relay 13AK19.) MO2100 (Local) on NX7822222.

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

5 RV-2103 RCIC PUMP SUCTION RELIEF VALVE Pressure boundary 6

P-207 RCIC PUMP Standby Operating 7

MO-2106 RCIC PUMP DISCHARGE OUTBOARD Closed Open Open on Rx Vessel Lvl Low 8

MO-2107 RCIC PUMP DISCHARGE INBOARD Closed Open Open on Rx Vessel Lvl Low 9

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

Open Open Close on Turbine Trip 22 HO-8 RCIC TURBINE GOVERNING VALVE Standby Operating 23 S-200 RCIC TERRY TURBINE Standby Operating 24 T-73 CV-2104 MINIMUM FLOW VALVE ACCUMULATOR TANK Pressure boundary 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

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

L-MT-15-030 Page 3 of 11 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments 68 CV-3503 HPCI TEST RETURN FLOW Energized Energized See Footnote 1.

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

70 PT-13-65 RCIC PUMP SUCTION PRESSURE Energized Energized Signal to PI-13-96 71 PI-13-96 RCIC PUMP SUCTION Control Room Indication 72 PS-13-67A RCIC LOW PUMP SUCTION PRESSURE TURBINE TRIP Energized Energized RCIC Turbine Trip 73 PT-13-60 RCIC PUMP DISCHARGE PRESSURE Energized Energized Control Room Indication 74 PI-13-93 RCIC PUMP DISCHARGE Control Room Indication 75 FS-13-57 RCIC PUMP DISCHARGE MINIMUM FLOW CONTROL Energized Energized 76 FT-13-58 RCIC PUMP DISCHARGE FLOW CONTROL Energized Energized RCIC Turbine Control Logic 77 FIC-13-91 RCIC PUMP FLOW Energized Energized Control Room Indication 78 FI-13-91 RCIC FLOW Energized Energized Control Room Indication 79 FY-13-102 RCIC PUMP FLOW LOOP ISOLATOR Energized Energized RCIC Turbine Control Logic 80 LS-7323 RCIC CONDENSER HIGH VACUUM TANK LEVEL ALARM Pressure boundary 81 dPIS-13-83 RCIC HIGH STEAM FLOW ISOLATION Energized Energized 82 dPIS-13-84 RCIC HIGH STEAM FLOW ISOLATION Energized Energized 83 PS-13-87A RCIC TURBINE STEAM SUPPLY LOW PRESS ISOLATION Energized Energized Local per NX-7822-22-3 84 PS-13-87B RCIC TURBINE STEAM SUPPLY LOW PRESS ISOLATION Energized Energized Local per NX-7822-22-3 85 PS-13-87C RCIC TURBINE STEAM SUPPLY LOW PRESS ISOLATION Energized Energized Local per NX-7822-22-3 86 PS-13-87D RCIC TURBINE STEAM SUPPLY LOW PRESS ISOLATION Energized Energized Local per NX-7822-22-3 87 TS-13-79A-1 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 88 TS-13-79A-2 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 89 TS-13-79B-1 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 90 TS-13-79B-2 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 1 HPCI valvesMO2035,MO2071andCV3503areincludedaspartoftheESEL,becausealthoughnot creditedinanyFLEXstrategy,HPCIissafetyrelatedandwouldautomaticallyinitiateintheeventofanSBO, andwouldbesecuredaspartoftheELAPprocedures. ThetestlinereturnpathtotheCSTrepresentsa potentialproblemforimplementationofFLEXstrategiesbecauseanywaterthatisdirectedfromtheTorus totheCSTwouldbelostshouldeithervalvefailtoclose.Therefore,theHPCItestlinevalveswereincluded intheESELtoensurethatifHPCIrunspriortobeingsecured;theflowisonlydirectedtothereactoror Torus.MO2035isclosedaspartofSBOprocedures.

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

L-MT-15-030 Page 5 of 11 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments 112 TS-13-81B-2 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 113 TS-13-81C-2 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 114 TS-13-81D-2 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 115 TS-13-82A-2 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 116 TS-13-82B-2 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 117 TS-13-82C-2 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 118 TS-13-82D-2 RCIC STEAM LINE HIGH AREA TEMPERATURE ISOLATION Energized Energized Local per NX-7822-22-3 119 PT-13-68 RCIC TURBINE STEAM SUPPLY PRESSURE Energized Energized Signal to PI-13-94 120 PI-13-94 RCIC TURBINE INLET Energized Energized Control Room Indication 121 SY-7321 RCIC TURBINE SPEED SIGNAL CONVERTER Control Room Indication 122 SCP-7925 RCIC TURBINE SPEED GOVERNOR EGM Control Room Indication 123 SE-7925 RCIC TURBINE SPEED MAGNETIC PICKUP Control Room Indication 124 LS-5 RCIC TURBINE OVERSPEED TRIP LEVEL SWITCH Control Room Indication 125 PT-13-70 RCIC TURBINE EXHAUST PRESSURE Control Room Indication 126 PI-13-95 RCIC TURBINE EXHAUST Control Room Indication 127 PS-13-72A RCIC HIGH TURBINE EXHAUST PRESSURE TURBINE TRIP Energized Energized Turbine Trip 128 PS-13-72B RCIC HIGH TURBINE EXHAUST PRESSURE TURBINE TRIP Energized Energized Turbine Trip 129 LT-2-3-61 REACTOR FLOODING LEVEL Energized Energized 130 PT-6-53B REACTOR PRESSURE WIDE RANGE B (REF COLUMN A)

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

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

L-MT-15-030 Page 6 of 11 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments 140 LT-2-3-72D LO LO REACTOR LVL ECCS INITIATION Energized Energized 141 LIS-2-3-672B HPCI LO LEVEL START Energized Energized 142 LIS-2-3-672D HPCI LO LEVEL START Energized Energized 143 LS-2-3-672F HPCI/RCIC HI LVL TURB TRIP Energized Energized Trip unit 144 LT-2-3-85A REACTOR VESSEL WATER LEVEL (FROM COLUMN B)

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

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

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

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

L-MT-15-030 Page 7 of 11 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 175 SV-2379 SV FOR AO-2379 TORUS TO RX BLDG VACUUM BREAKER Energized Energized Energized maintains N2 on the seal 176 AO-2380 VACUUM RELIEF DAMPER --

Included for N2 System Integrity Only 177 SV-2380 SV FOR AO-2380 TORUS VACUUM RELIEF Energized Energized Energized maintains N2 on the seal 178 AO-2381 DRYWELL PURGE INBD ISOL Included for N2 System Integrity Only 179 AO-2383 TORUS VENT Included for N2 System Integrity Only 180 AO-2386 DW PURGE EXHAUST INBD Included for N2 System Integrity Only 181 SV-4539 N2 SUPPLY TO HPV INBOARD ISOLATION A0-4539 De-energized Energized 182 SV-4540 N2 SUPPLY FOR HPV OUTBD ISOLATION AO-4540 De-energized Energized 183 SV-4541 INBOARD N2 SUPPLY TO HPV RUPTURE DISC De-energized Energized 184 SV-4542 OUTBOARD N2 SUPPLY TO HPV RUPTURE DISC De-energized Energized 185 AO-4539 HARD PIPE VENT INBOARD ISOLATION VALVE Closed Open Fail Closed 186 AO-4540 HARD PIPE VENT OUTBOARD ISOLATION VALVE Closed Open Fail Closed 187 PS-4662 ALT N2 TRAIN A SUPPLY ISOLATION/ALARM Pressure boundary 188 PS-4237 ALT N2 TRAIN B SUPPLY ISOLATION/ALARM Pressure boundary 189 LT-7338A TORUS WIDE RANGE LEVEL Energized Energized 190 LY-7338B TORUS WIDE RANGE LEVEL Energized Energized 191 LT-7338B TORUS WIDE RANGE LEVEL Energized Energized 192 PT-7251A DRYWELL WIDE RANGE PRESSURE Energized Energized 193 PLR-7251A DW PRESS-TOR LVL-DW RAD-ACCD/RNG 194 PT-7251B DRYWELL WIDE RANGE PRESSURE Energized Energized 195 PY-7251B PRIMARY CONTAINMENT WIDE RANGE PI ISOLATOR Energized Energized 196 PLR-7251B DW PRESS-TOR LVL-DW RAD-ACCD/RNG 197 TE-4073A TORUS SENSOR 1 -

SRV71H / RCIC DISCHARGE AREA Energized Energized 198 TE-4074A TORUS SENSOR 2 -

SRV71C DISCHARGE AREA Energized Energized 199 TE-4075A TORUS SENSOR 3 -

SRV71B DISCHARGE AREA Energized Energized 200 TE-4076A TORUS SENSOR 4 -

SRV71G / HPCI DISCHARGE AREA Energized Energized 201 TE-4077A TORUS SENSOR 5 -

SRV71A DISCHARGE AREA Energized Energized

L-MT-15-030 Page 8 of 11 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments 202 TE-4078A TORUS SENSOR 6 -

SRV71E DISCHARGE AREA Energized Energized 203 TE-4079A TORUS SENSOR 7 -

SRV71F DISCHARGE AREA Energized Energized 204 TE-4080A TORUS SENSOR 8 -

SRV71D DISCHARGE AREA Energized Energized 205 TE-4073B TORUS SENSOR 1 -

SRV71H / RCIC DISCHARGE AREA Energized Energized 206 TE-4074B TORUS SENSOR 2 -

SRV71C DISCHARGE AREA Energized Energized 207 TE-4075B TORUS SENSOR 3 -

SRV71B DISCHARGE AREA Energized Energized 208 TE-4076B TORUS SENSOR 4 -

SRV71G / HPCI DISCHARGE AREA Energized Energized 209 TE-4077B TORUS SENSOR 5 -

SRV71A DISCHARGE AREA Energized Energized 210 TE-4078B TORUS SENSOR 6 -

SRV71E DISCHARGE AREA Energized Energized 211 TE-4079B TORUS SENSOR 7 -

SRV71F DISCHARGE AREA Energized Energized 212 TE-4080B TORUS SENSOR 8 -

SRV71D DISCHARGE AREA Energized Energized 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 217 TE-4247A DW TEMPERATURE ELEMENT (DUAL ELEMENT A1/A2)

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

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

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

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

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

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

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

Energized Energized 225 RE-4544 HARD PIPE VENT RADIATION DETECTOR Energized Energized 226 RM-4544 HARD PIPE VENT RADIATION MONITOR Energized Energized

L-MT-15-030 Page 9 of 11 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments 227 D10 125 VDC CHARGER FOR

1. 11 BATT Energized Energized DOOR #110 INSIDE ON SOUTH WALL, EC720 replaced charger, 228 D20 125 VDC CHARGER FOR

1. 12 BATT Energized Energized DOOR #103 INSIDE ON NORTH WALL, Mod 00Q370 replaced charger 229 D52 CHARGER, D3A (13)

BATTERY Energized Energized DOOR #109 INSIDE ON NORTH WALL 230 D53 CHARGER, D3B (13)

BATTERY Energized Energized DOOR #109 INSIDE ON NORTH WALL 231 D54 CHARGER, SWING D3A, D3B (13) BATTERY Energized Energized DOOR #109 INSIDE ON NORTH WALL 232 D70 CHARGER, D6B (16)

BATTERY Energized Energized Drawing Available 233 D80 CHARGER, D6A (16)

BATTERY Energized Energized 234 D90 CHARGER, SWING D6A,D6B (16) BATTERY Energized Energized 235 Y71 DIV 1 120VAC CLASS 1E INVERTER Energized Energized 236 Y75 DIV 1 FUSED DISCONNECT SWITCH Energized Energized 237 Y70 DIV 1 UNINTERRUPTIBLE 120VAC CLASS 1E DIST PANEL Energized Energized 238 Y81 DIV 2 120VAC CLASS 1E INVERTER Energized Energized NORTH SIDE 239 Y85 DIV 2 FUSED DISCONNECT SWITCH Energized Energized 240 Y80 DIV 2 UNINTERRUPTIBLE 120VAC CLASS 1E DIST PANEL Energized Energized NORTH SIDE 241 D1

1. 11 BATTERY 125VDC Energized Energized DOOR #110 242 D11 DIV I 125VDC DISTRIBUTION CENTER Energized Energized DOOR #110 INSIDE ON SOUTH WALL 243 D2

1. 12 BATTERY 125VDC Energized Energized 244 D21 DIV I 125 VDC DISTRIBUTION PANEL Energized Energized DOOR #103 INSIDE ON NORTH WALL 245 D33 125 VDC DISTRIBUTION CENTER Energized Energized DOOR #110 INSIDE ON SOUTH WALL 246 D100 DIV 2 125/250 VDC DISTRIBUTION PANEL Energized Energized 247 D31 DIV I 125/250 VDC DISTRIBUTION PANEL Energized Energized DOOR #109 248 D3A

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

1. 13 (DIV 1) 125/250VDC BATTERY "B" Energized Energized DOOR #109 250 D6A

1. 16 (DIV 2) 125/250VDC BATTERY "A" Energized Energized SOUTH SIDE 251 D6B

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

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

L-MT-15-030 Page 11 of 11 ESEL Equipment Operating State Item Num ID Description Normal State Desired State Notes/Comments 289 13A-K29 STEAM LINE AREA HIGH TEMPERATURE De-energized De-energized 290 13A-K30 STEAM LINE AREA HIGH TEMPERATURE De-energized De-energized 291 13A-K31 STEAM LINE HIGH DP (LINE BREAK)

De-energized De-energized 292 13A-K32 RCIC AUTO ISOLATION De-energized De-energized 293 13A-K33 RCIC TURBINE EXHAUST HIGH PRESSURE TD RELAY De-energized De-energized 294 13A-K34 REACTOR HIGH WATER TURBINE TRIP De-energized De-energized 295 13A-K37 CST LOW LEVEL Energized Energized 295 13A-K28 REACTOR HIGH WATER LEVEL De-energized De-energized 297 K102A RELAY ECCS DIVISION I ANALOG TRIP CABINET De-energized De-energized 298 K102B RELAY ECCS DIVISION II ANALOG TRIP CABINET De-energized De-energized