View source for 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

{{Adams
| number = ML15142A862
| issue date = 05/22/2015
| title = Expedited Seismic Evaluation Process (ESEP) - Augmented Approach to Post-Fukushima Near-Term Task Force (NTTF) 2.1 - Response to Requests for Additional Information
| author name = Gardner P
| author affiliation = Northern States Power Co, Xcel Energy
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000263
| license number = DPR-022
| contact person = 
| case reference number = L-MT-15-030
| document type = Letter type:L
| page count = 21
| project = 
| stage = Response to RAI
}}

=Text=
{{#Wiki_filter: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.
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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.
Page 3 of 11

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
                 #11 BATT                                               EC720 replaced charger, 125 VDC CHARGER FOR                                    DOOR #103 INSIDE ON NORTH WALL, 228   D20                                Energized       Energized
                 #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
                 #13 (DIV 1) 125/250VDC 248   D3A                                Energized       Energized     DOOR #109 BATTERY "A"
                 #13 (DIV 1) 125/250VDC 249   D3B                                Energized       Energized     DOOR #109 BATTERY "B"
                 #16 (DIV 2) 125/250VDC 250   D6A                                Energized       Energized     SOUTH SIDE BATTERY "A"
                 #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}}