{{Adams | number = ML16049A509 | issue date = 02/18/2016 | title = Farley Initial Exam 2015-301 Final Sim In-Plant JPMs | author name = | author affiliation = NRC/RGN-II/DRS | addressee name = | addressee affiliation = Southern Nuclear Operating Co, Inc | docket = 05000348, 05000364 | license number = NPF-002, NPF-008 | contact person = | document type = License-Operator, Part 55 Examination Related Material | page count = 1310 }}

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{{#Wiki_filter:FNP ILT-38 JPM Page 1 of 8 jpm a CRO-074 TITLE: Fill The SIS Accumulators ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: X SIMULATOR CONTROL ROOM PLANT PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: IC-211 (Base -188) ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS: 1. Examinee will obtain all references from the simulator. 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise. 3. Provide student with HANDOUT. 4. Allow student time to review control board. 5. Instructor will be provided to address alarms not related to evaluated task. TASK STANDARD: Upon successful completion of this JPM, the examinee will: 1. Fill the 1A SIS Accumulator. Examinee: Trainee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) Developer S Jackson Date: 4/9/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP ILT-38 JPM Page 2 of 8 EVENT DESCRIPTION ACTION DETAILS Reset into IC-211 Freeze Xe Run / Freeze Simulator Update Rods FF5 CLEAR Clear Ovation Alarms OVATION Acknowledge computer alarms SIPC Acknowledge Alarms Turn Horns ON Run / Freeze Simulator Un freeze Xe Run / Freeze Simulator FNP ILT-38 JPM Page 3 of 8 CONDITIONS When I tell you to begin, you are to FILL THE SIS ACCUMULATORS. The conditions under which this task is to be performed are: a. The Unit is at 100% power. b. The 1A accumulator level is 40% and pressure is 585 psig due to normal sampling. c. Chemistry has verified RWST boron concentration is suitable for makeup to the accumulator. d. You are directed to fill only the 1A accumulator to 45% using FNP-1-SOP-8.0. e. Continuous communications have been established. f. The Rad Side SO is standing by with a copy of the procedure and the required locked valve key. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME NOTE: Step 4.1.1.1, Verify RWST boron concentration is suitable for makeup to the accumulator, is satisfied by the initial conditions provided. If requested then provide the cue: Chemistry has verified RWST boron concentration is suitable for makeup to the accumulator. 1. 4.1.1.2 Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V- 8979) OPEN. SO directed to verify valve open. (CUE: SO reports V083 is open.) S / U *2. 4.1.1.3 Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). SO directed to open V028. (CUE: SO reports V028 open.) S / U 3. 4.1.1.4 Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. Observes HIK-947 Potentiometer fully clockwise, arrow at full right - 100%. S / U 4. 4.1.1.5 Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. Position of HV-8880 is checked. Observes green light lit, red light out. S / U *5. 4.1.1.6 Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC- V-8967). SO directed to unlock and open the hydro test pump discharge to accumulator valve V085. (CUE: SO reports V085 is open.) S / U FNP ILT-38 JPM Page 4 of 8 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *6. 4.1.1.7 Start the hydro test pump using local handswitch N1E21HS2100F. SO directed to start the hydro test pump. (CUE: SO reports the hydro test pump is started.) S / U *7. 4.1.1.8.1 Open ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091). HS for HV-8860 taken to open position. Observes red light lit, green light out. S / U *8 4.1.1.8.2 Open 1A ACCUM FILL LINE ISO Q1E21HV8878A (Q1E21V034A). HS for HV-8878A taken to open position. Observes red light lit, green light out. S / U *9. 4.1.1.9 Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947. HIK-947 is turned counterclockwise until SO reports that pressure is greater than Accumulator pressure. S / U 10. 4.1.1.10 Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, AND verify that only the desired accumulator shows an increase while filling. Accumulator levels are monitored. Observes 1A Accumulator level rising. S / U 11. 4.1.1.11 Monitor accumulator pressure indicators PI-921, 923,925, 927, 929, and 931 AND verify that only the desired accumulator shows a pressure increase while filling. Monitor accumulator pressures. Pressure should remain < 640 psig. Observes pressure rising. S / U

FNP ILT-38 JPM Page 5 of 8 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) When Accumulator level reaches 45% then: *12. 4.1.1.12.1 Adjust HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. HIK-947 taken fully clockwise. Observes HIK-947 Potentiometer fully clockwise, arrow at full right - 100%. S / U *13. 4.1.1.12.2 Close 1A ACCUM FILL LINE ISO Q1E21HV8878A (Q1E21V034A). Handswitch for HV-8878A taken to close position. Observes green light lit, red light out. S / U NOTE: Step 4.1.1.13 is N/A *14. 4.1.1.14.1 Close ACCUM FILL LINE ISO Q1E21HV8860 Q1E21V091). Handswitch for HV-8860 taken to close position. Observes green light lit, red light out. S / U *15. 4.1.1.14.2 Stop the hydro test pump. SO directed to stop the hydro test pump. (CUE: SO reports hydro test pump is stopped.) S / U 16. 4.1.1.15 Close ACCUM N2 VENT HIK 936 (Q1G21V092). ACCUM N2 VT HIK 936 (QV092) checked closed. Observes potentiometer fully counterclockwise - arrow at 0%. S / U 17. 4.1.1.16 Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. Observes HIK-947 Potentiometer fully clockwise, arrow at full right - 100. S / U *18. 4.1.1.17 Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC- V-8967). SO directed to close and lock V085. (CUE: SO reports that V085 is locked closed.) S / U FNP ILT-38 JPM Page 6 of 8 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *19. 4.1.1.18 Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). SO directed to close V028. (CUE: SO reports that V028 is closed.) S / U STOP TIME Terminate when Q1E21V028 is closed CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () preceding the element number. GENERAL REFERENCES 1. FNP-1-SOP-8.0, Version 43.0 2. K/A: 006A1.13 - 3.5 / 3.7 006A4.02 - 4.0 / 3.8 GENERAL TOOLS AND EQUIPMENT None FNP ILT-38 JPM Page 7 of 8 Critical ELEMENT justification: 1 Not Critical - Does not prevent filling the Accumulator. 2 Critical - Task completion. Required for system line up. 3-4 Not Critical - No actions taken by applicant. Check steps 5 Critical - Task completion. Required for system line up. 6 Critical - Task completion. Provides motive force for water to fill the accumulator 7, 8 Critical - Task completion. Required for system line up. 9 Critical - Task completion. Required for adequate pressure. 10, 11 Not Critical - No actions taken by applicant. 12 Critical - Task completion. Prevents overfilling Accumulator 13-15 Critical - Task completion. Proper system restoration. 16 Not Critical - No action taken by applicant. 18, 19 Critical - Task completion. Proper system restoration. COMMENTS FNP ILT-38 JPM HANDOUT Page 1 of 1 jpm a CONDITIONS When I tell you to begin, you are to FILL THE SIS ACCUMULATORS. The conditions under which this task is to be performed are: a. The Unit is at 100% power. b. The 1A accumulator level is 40% and pressure is 585 psig due to normal sampling. c. Chemistry has verified RWST boron concentration is suitable for makeup to the accumulator. d. You are directed to fill only the "1A" accumulator to 45% using FNP-1-SOP-8.0. e. Continuous communications have been established. f. The Rad Side SO is standing by with a copy of the procedure and the required locked valve key. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 1 of 72SAFETYSAFETY INJECTION SYSTEM - ACCUMULATORS RELATEDPROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORYSECTIONSContinuous: ALL

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NONE Information: UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant UNIT 1Farley Nuclear Plant FNP ILT-38 JPM Page 1 of 9 NONE Approved:David L Reed 04/10/2015 Operations Effective Date UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 2 of 72Procedure Version Description Version Number Version Description 41.0Updated procedure to requirements of NMP-OS-008-001, Operations Procedure Writing Instructions. Also revised mythology to fill and pressurize accumulators. 42.0Corrected sequence of applied cautions before steps 4.1.1.9 and 4.1.1.11. CR 353194 43.0DCP SNC540544 - Revised per mark-up provided. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 3 of 72Table of ContentsPage1.0Purpose .........................................................................................................................................42.0Initial Conditions ............................................................................................................................43.0Precautions and Limitations ..........................................................................................................44.0Instructions ....................................................................................................................................54.1Filling Accumulators at power ...........................................................................................54.2Draining Accumulators ....................................................................................................12 4.3Draining Accumulators with RCS Pressure Less Than 1000 psig...................................14 4.4Establishing a Nitrogen Atmosphere in the Accumulators ..............................................21 4.5Increasing Accumulator Nitrogen Pressure .....................................................................30 4.6Venting Accumulators .....................................................................................................334.7Pumping Accumulators to RWST With RCS Pressure Less Than 1000 psig .................354.8Complete Depressurization of All Accumulators to Support Outage Activities ................47 4.9Increasing Accumulator Nitrogen Pressure Using temporary Bottles ..............................495.0References ..................................................................................................................................536.0Records .......................................................................................................................................53APPENDIX 1 ...........................................................................................................................................54APPENDIX 2 ...........................................................................................................................................59APPENDIX 3 ...........................................................................................................................................64APPENDIX 4 ...........................................................................................................................................69 UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 4 of 721.0 Purpose This procedure provides the Initial Conditions, Precautions, Limitations, and Instructions for the operation of the Safety Injection System-Accumulators.2.0 Initial Conditions 2.1The Electrical Distribution System is energized and aligned for normal operation per FNP-1-SOP-36.0, Plant Electrical Distribution Line-Up, with exceptions noted. 2.2The accumulator valves and electrical distribution system are aligned per System Check List FNP-1-SOP-8.0A, Safety Injection System - Accumulators, with exceptions noted. 2.3The refueling water storage tank contains primary grade water borated to greater than 2300 ppm. 2.4The Nitrogen System is in service and aligned for normal operation per FNP-0-SOP-33.0, Nitrogen System. 3.0 Precautions and Limitations 3.1Accumulator pressure should be maintained between 605 and 645 psig inModes 1, 2, and 3. Do not exceed the accumulator design pressure of 700 psig. 3.2Do not allow accumulator level to exceed a high level of 55% or a low level of 35% in Modes 1, 2, and 3. 3.3Alert personnel in containment prior to venting accumulators. 3.41A, B, and C ACCUM DISCH ISO Q1E21MOV8808A, B, and C (Q1E21V038A, B, and C) should be closed when RCS pressure is less than 1000 psig and open when RCS pressure is greater than 1000 psig. 3.5The temperature of the accumulators must be kept above 70°F (the minimum temperature for pressurization) whenever the accumulators are pressurized. 3.6If any accumulator level rises significantly (approx. 5%) due to in-leakage from RCS, then sample the accumulator to verify boron concentration > 2300 ppm. 3.7Cross-connection of accumulators via N2 or Fill lines is prohibited in Modes 1, 2, or 3 (with RCS pressure greater than 1000 psig). This is because in the event of a LOCA, all cross-connected accumulators would depressurize through the faulted RCS loop. 3.8If increasing accumulator nitrogen pressure per Section 4.5 after establishing nitrogen atmosphere per section 4.4, then ensure the high pressure nitrogen banks are greater than 1000 psig prior to performing Section 4.5. 3.9Guidance in this procedure has the potential to impact reactivity. Close coordination with the control room operators is required to ensure proper reactivity management per NMP-OS-001, Reactivity Management Program. (AI 2008203128) Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 5 of 72NOTES Accumulator levels must be maintained between 35% and 55% while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). The accumulator boron concentration must be maintained between 2200 and 2500 ppm while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). The hydro test pump is a positive displacement pump, therefore a flowpath must be maintained at all times with pump running; so HIK-947 must remain open while pump is running to prevent lifting the relief valve. (CR 2008108980) CAUTIONCross-connection of accumulators via N2 or Fill lines is Prohibited in Modes 1, 2, or 3 (with RCS pressure greater than 1000 psig).4.0 Instructions 4.1Filling Accumulators at power 4.1.1Filling Accumulator 1A: 4.1.1.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.1.1.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.1.1.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.1.1.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.1.1.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. 4.1.1.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.1.7Start the hydro test pump using local handswitch N1E21HS2100F. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 6 of 724.1.1.8Perform the following: 4.1.1.8.1Open ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.1.8.2Open 1A ACCUM FILL LINE ISO Q1E21HV8878A (Q1E21V034A). CAUTIONAdjust pressure in the following step gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980) 4.1.1.9Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947.4.1.1.10Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, ANDverify that only the desired accumulator shows an increase while filling.NOTEIF accumulator pressure increases to greater than 640 psig, THEN the hydro test pump must be stopped AND the accumulator vented. CAUTIONEnsure accumulator pressure does not exceed 645 psig during filling, which is the setpoint for accumulator high pressure alarm. 4.1.1.11Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify that only the desired accumulator shows a pressure increase while filling. 4.1.1.12 WHEN the accumulator is filled to desired level, THEN perform the following: 4.1.1.12.1Adjust HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. 4.1.1.12.2Close 1A ACCUM FILL LINE ISO Q1E21HV8878A (Q1E21V034A). 4.1.1.13 IF additional accumulators are required to be filled, THEN proceed to Sections 4.1.2 OR 4.1.3. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 7 of 724.1.1.14 IF no additional accumulators require filling, THEN perform the following: 4.1.1.14.1Close ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.1.14.2Stop the hydro test pump. 4.1.1.15Close ACCUM N2 VENT HIK 936 (Q1G21V092). 4.1.1.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. 4.1.1.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.1.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).NOTEIn the following step, sampling is not required if the make up source was the RWST. 4.1.1.19 IF any accumulator level was increased more than 12% on the level indicator, THEN verify the boron concentration within 6 hours. 4.1.2Filling Accumulator 1B: 4.1.2.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.1.2.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.1.2.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.1.2.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.1.2.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. 4.1.2.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.2.7Start the hydro test pump using local handswitch N1E21HS2100F. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 8 of 724.1.2.8Perform the following: 4.1.2.8.1Open ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.2.8.2Open 1B ACCUM FILL LINE ISO Q1E21HV8878B (Q1E21V034B). 4.1.2.9Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947.CAUTIONAdjust pressure in the following step gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980) 4.1.2.10Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, to verify that only the desired accumulator shows an increase while filling.NOTEIf accumulator pressure increases to greater than 640 psig, then the hydro test pump must be stopped and the accumulator vented. 4.1.2.11Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify that only the desired accumulator shows a pressure increase while filling. CAUTIONEnsure accumulator pressure does not exceed 645 psig during filling, which is the setpoint for accumulator high pressure alarm. 4.1.2.12 WHEN the accumulator is filled to desired level, THEN perform the following: 4.1.2.12.1Adjust HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. 4.1.2.12.2Close 1B ACCUM FILL LINE ISO Q1E21HV8878B (Q1E21V034B). 4.1.2.13 IF additional accumulators are required to be filled, THEN proceed to Sections 4.1.1 or 4.1.3. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 9 of 724.1.2.14 IF no additional accumulators require filling, THEN perform the following: 4.1.2.14.1Close ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.2.14.2Stop the hydro test pump. 4.1.2.15Close ACCUM N2 VENT HIK 936 (Q1G21V092). 4.1.2.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. 4.1.2.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.2.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).NOTEIn the following step, sampling is not required if the make-up source was the RWST. 4.1.2.19 IF any accumulator level was increased more than 12% on the level indicator, THEN verify the boron concentration within 6 hours.4.1.3Filling Accumulator 1C: 4.1.3.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.1.3.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.1.3.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.1.3.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.1.3.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. 4.1.3.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.3.7Start the hydro test pump using local handswitch N1E21HS2100F. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 10 of 724.1.3.8Perform the following: 4.1.3.8.1Open ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.3.8.2Open 1C ACCUM FILL LINE ISO Q1E21HV8878C (Q1E21V034C). 4.1.3.9Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on local pressure indicator N1E21PI0947.CAUTIONAdjust pressure in the following step gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980) 4.1.3.10Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, ANDverify that only the desired accumulator shows an increase while filling.NOTEIf accumulator pressure increases to greater than 640 psig, the hydro test pump must be stopped and the accumulator vented. 4.1.3.11Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify that only the desired accumulator shows a pressure increase while filling. CAUTIONEnsure accumulator pressure does not exceed 645 psig during filling, which is the setpoint for accumulator high pressure alarm. 4.1.3.12 WHEN the accumulator is filled to desired level, THEN perform the following: 4.1.3.12.1Adjust HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. 4.1.3.12.2Close 1C ACCUM FILL LINE ISO Q1E21HV8878C (Q1E21V034C). 4.1.3.13 IF additional accumulators are required to be filled, THEN return to Sections 4.1.1 or 4.1.2. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 11 of 724.1.3.14 IF no additional accumulators require filling, THEN perform the following: 4.1.3.14.1Close ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.3.14.2Stop the hydro test pump. 4.1.3.15Close ACCUM N2 VENT HIK 936(Q1G21V092). 4.1.3.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. 4.1.3.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.3.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).NOTEIn the following step, sampling is not required if the make up source was the RWST. 4.1.3.19 IF any accumulator level was increased more than 12% on the level indicator, THEN verify the boron concentration within 6 hours. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 12 of 72CAUTIONSAccumulator levels must be maintained between 35% and 55% while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). Cross-connection of accumulators via N2 or Fill lines is Prohibited in Modes 1, 2 or 3 (with RCS pressure greater than 1000 psig).4.2Draining Accumulators:4.2.1Draining 1A Accumulator with RCS Pressure Greater Than 1000 psig: 4.2.1.1Open the following valves: ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. 4.2.1.2Open 1A ACCUM TEST LINE ISO, Q1E21HV8877A to commence draining accumulator. 4.2.1.3Monitor accumulator level indicators AND verify the water level in accumulator 1A is the only accumulator which shows a decrease in level. 4.2.1.4Monitor accumulator pressure while draining. NOTEIf pressure decreases to less than 610 psig, then draining must be secured AND accumulator pressurized. 4.2.1.5 WHEN the accumulator is drained to the desired level, THENclose the following valves: 1A ACCUM TEST LINE ISO, Q1E21HV8877A. ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. 4.2.2Draining 1B Accumulator with RCS Pressure Greater Than 1000 psig: 4.2.2.1Open the following valves: ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. 4.2.2.2Open 1B ACCUM TEST LINE ISO, Q1E21HV8877B to commence draining accumulator. 4.2.2.3Monitor accumulator level indicators AND verify the water level in accumulator 1B is the only accumulator which shows a decrease in level. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 13 of 724.2.2.4Monitor accumulator pressure while draining. NOTEIf pressure decreases to less than 610 psig, then draining must be secured and accumulator pressurized.4.2.2.5 WHEN the accumulator is drained to the desired level, THEN close the following valves: 1B ACCUM TEST LINE ISO, Q1E21HV8877B. ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. 4.2.3Draining 1C Accumulator with RCS Pressure Greater Than 1000 psig 4.2.3.1Open the following valves: ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. 4.2.3.2Open 1C ACCUM TEST LINE ISO, Q1E21HV8877C to commence draining accumulator. 4.2.3.3Monitor accumulator level indicators AND verify the water level in accumulator 1C is the only accumulator which shows a decrease in level. 4.2.3.4Monitor accumulator pressure while draining. NOTEIf pressure decreases to less than 610 psig, then draining must be secured and accumulator pressurized.4.2.3.5 WHEN the accumulator is drained to the desired level, THEN close the following valves: 1C ACCUM TEST LINE ISO, Q1E21HV8877C. ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 14 of 72NOTEDraining may be done using section 4.7, Pumping accumulators to RWST with RCS Pressure Less Than 1000 psig. If only a small level decrease is required, the accumulator may be drained via the sample system by Chemistry personnel per FNP-1-CCP-660 Sampling The Accumulators. 4.3Draining Accumulators with RCS Pressure Less Than 1000 psig 4.3.1Draining 1A Accumulator.4.3.1.1Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to start venting 1B ACCUM. 4.3.1.2Verify the RCDT system is aligned for normal operation (not cavity drain) per FNP-1-SOP-50.0, Liquid Waste Processing System. (AI 2003201775) 4.3.1.3Verify 1A ACCUM DISCH ISO, Q1E21MOV8808A is CLOSED.4.3.1.4Open 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 4.3.1.5Alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere.4.3.1.6 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092).4.3.1.7Monitor accumulator pressure during venting operation. 4.3.1.8 WHEN accumulator pressure has decreased to approximately 15 psig, THEN close the following valves: ACCUM N2 VENT HIK 936 (Q1G21V092). ACCUM N2 SUPP/VT ISO Q1E21HV8875A. 4.3.1.9Verify the following valves CLOSED: 1A ACCUM DRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). SIS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A).4.3.1.10Notify Maintenance to install spool piece in accumulator 1A drain line to RCDT pump suction. 4.3.1.11 WHENspool piece is installedTHEN, Open 1A ACCUMDRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 15 of 724.3.1.12Stop or verify stopped the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. 4.3.1.13Close the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. NOTEWhen the following lineup is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.3.1.14Open the following valves: SIS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A). RCDT LCV, Q1G21LCV1003. RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). (Located in 121' PPR) 4.3.1.15Start one of the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, then the operating RCDT pump will automatically stop. 4.3.1.16 WHEN desired accumulator level is reached, THEN perform the following: 4.3.1.16.1Stop the RCDT pump started in Step 4.3.1.15. 4.3.1.16.2Close RCDT LCV Q1G21LCV1003 (Q1G21V064).4.3.1.17Close the following valves: SIS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A). 1A ACCUM DRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 16 of 724.3.1.18Open the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. 4.3.1.19Restore the RCDT system to normal operation per FNP-1-SOP-50.0, Liquid Waste Processing System. 4.3.1.20Notify Maintenance to remove spool piece from accumulator 1A drain line to RCDT pump suction. 4.3.2Draining 1B Accumulator. 4.3.2.1Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to start venting 1C ACCUM. 4.3.2.2Verify the RCDT system is aligned for normal operation (not cavity drain) per FNP-1-SOP-50.0, Liquid Waste Processing System. (AI 2003201775) 4.3.2.3Verify 1B ACCUM DISCH ISO, Q1E21MOV8808B is CLOSED.4.3.2.4Open1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. 4.3.2.5Alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere.4.3.2.6 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092). 4.3.2.7Monitor accumulator pressure during venting operation.4.3.2.8 WHEN accumulator pressure has decreased to approximately15psig, THEN close the following valves: ACCUM N2 VENT HIK 936(Q1G21V092). 1B ACCUM N2 SUPP/VT ISO Q1E21HV8875B. 4.3.2.9Verify the following valves CLOSED: 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). SIS 1B ACCUM DRN, Q1G21V255B (1-LWP-V-7130B).4.3.2.10Notify Maintenance to install spool piece in accumulator 1B drain line to RCDT pump suction. 4.3.2.11 WHENspool piece is installed,THEN Open 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 17 of 724.3.2.12 Stop or verify stopped the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. 4.3.2.13Close the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. NOTEWhen the following line up is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.3.2.14Open the following valves: SIS 1B ACCUM DRN, Q1G21V255B (1-LWP-V-7130B). RCDT LCV, Q1G21LCV1003. RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). (Located in 121' PPR) 4.3.2.15Start one of the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, the operating RCDT pump will automatically stop. 4.3.2.16 WHEN desired accumulator level is reached, THEN perform the following: 4.3.2.16.1Stop the RCDT pump started in Step 4.3.2.15. 4.3.2.16.2Close RCDT LCV Q1G21LCV1003 (Q1G21V064).4.3.2.17Close the following valves: SIS 1B ACCUM DRN, Q1G21V255B (1-LWP-V-7130B). 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 18 of 724.3.2.18Open the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. 4.3.2.19Restore the RCDT system to normal operation per FNP-1-SOP-50.0, Liquid Waste Processing System. 4.3.2.20Notify Maintenance to remove spool piece from accumulator 1B drain line to RCDT pump suction. 4.3.3Draining 1C Accumulator: 4.3.3.1Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to start venting 1A ACCUM. 4.3.3.2 Verify that the RCDT system is aligned for normal operation (not cavity drain) per FNP-1-SOP-50.0, Liquid Waste Processing System. (AI 2003201775) 4.3.3.3Verify 1C ACCUM DISCH ISO, Q1E21MOV8808C is CLOSED. 4.3.3.4Open 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.3.3.5 Prior to venting, alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.3.3.6 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092). 4.3.3.7Monitor accumulator pressure during venting operation.4.3.3.8 WHEN accumulator pressure has decreased to approximately 15 psig, THEN close the following valves: ACCUM N2 VENT HIK 936(Q1G21V092). 1C ACCUM N2 SUPP/VT ISO Q1E21HV8875C. 4.3.3.9Verify the following valves CLOSED: 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). SIS 1C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C). 4.3.3.10Notify Maintenance to install spool piece in accumulator 1C drain line to RCDT pump suction. 4.3.3.11 WHENspool piece is installed,THEN Open 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 19 of 724.3.3.12Stop or verifystopped the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. 4.3.3.13Close the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. NOTEWHEN the following line-up is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.3.3.14Open the following valves: SIS 1C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C). RCDT LCV, Q1G21LCV1003. RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). (Located in 121' PPR) 4.3.3.15Start one of the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, the operating RCDT pump will automatically stop. 4.3.3.16 WHEN desired accumulator level is reached, THEN perform the following: 4.3.3.16.1Stop the RCDT pump started in Step 4.3.3.15. 4.3.3.16.2Close RCDT LCV Q1G21LCV1003 (Q1G21V064).4.3.3.17Close the following valves: SIS C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C). 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 20 of 724.3.3.18Open the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. 4.3.3.19Restore the RCDT system to normal operation per FNP-1-SOP-50.0, Liquid Waste Processing System. 4.3.3.20Notify Maintenance to remove spool piece from accumulator 1C drain line to RCDT pump suction. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 21 of 724.4Establishing a Nitrogen Atmosphere in the Accumulators: 4.4.1Establishing a Nitrogen Atmosphere in Accumulator 1A4.4.1.1 IF required, THEN vent accumulator 1A to zero psig per Section 4.8. 4.4.1.2Open the following valves: 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. ACCUM N2 VENT HIK-936. 4.4.1.3Fill accumulator 1A per the following steps: 4.4.1.3.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.4.1.3.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.4.1.3.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.4.1.3.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.4.1.3.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED.4.4.1.3.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.1.3.7Start the hydro test pump using local handswitch N1E21HS2100F.4.4.1.3.8Open ACCUM FILL LINE ISO, Q1E21HV8860. 4.4.1.3.9Open 1A ACCUM FILL LINE ISO, Q1E21HV8878A.CAUTIONPressure should be adjusted gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980) 4.4.1.3.10Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 22 of 724.4.1.3.11Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, ANDverifyonly the desired accumulator shows an increase while filling.NOTEIf accumulator pressure increases to greater than 640 psig, the hydro test pump must be stopped and the accumulator vented. 4.4.1.3.12Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify only the desired accumulator shows a pressure increase while filling. 4.4.1.3.13 WHEN accumulator level reaches the indicating range, THEN verify level indicators show approximately same level. 4.4.1.3.14 IF level indicators are not approximately equal, THENcontact maintenance. NOTEEnsure accumulator pressure does not exceed 645 psig during filling, which is the setpoint for accumulator high pressure alarm. 4.4.1.3.15 WHEN the accumulator is filled to approximately mid scale on the MCB level indicators ( LI 920, LI922),THENperform the following: 4.4.1.3.15.1Adjust HYDRO TEST PMP DISCH CONT VLV full open using HIK 947. 4.4.1.3.15.2Close 1A ACCUM FILL LINE ISO, Q1E21HV8878A.4.4.1.3.15.3Close 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A.4.4.1.3.15.4Close ACCUM FILL LINE ISO, Q1E21HV8860.4.4.1.3.15.5Stop the hydro test pump. 4.4.1.3.15.6Close ACCUM N2 VENT HIK 936 (Q1G21V092).4.4.1.3.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 23 of 724.4.1.3.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.1.3.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.4.1.3.19Verify ACCUM N2 VENT HIK-936 CLOSED. 4.4.1.3.20Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 25 psig. (Located in 121' PPR) 4.4.1.3.21Open the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B.4.4.1.3.22Open 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A.4.4.1.3.23Open ACCUM N2 SUPPLY ISO, Q1E21HV8880. NOTEThe intent of the following is to pressurize the accumulator to approximately 25 psig. Stop at this point and wait for I&C to complete venting the lower level taps on the accumulator instruments. After venting is complete then continue with accumulator pressurization to the normal pressure band. 4.4.1.3.24 WHEN accumulator pressure reaches approximately 25 psig, THEN perform the following:4.4.1.3.24.1Close 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 4.4.1.3.24.2Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B.4.4.1.3.24.3Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 625 PSIG. (Located in 121' PPR). 4.4.1.3.24.4Close ACCUM N2 SUPP ISO, Q1E21HV8880. 4.4.1.3.24.5HaveI&C vent the lower level taps on the accumulator instruments. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 24 of 724.4.1.3.25 IF required, THEN increase accumulator pressure to the desired value per Section 4.5. 4.4.2Establishing a Nitrogen Atmosphere in Accumulator 1B4.4.2.1 IF required, THEN vent accumulator 1B to zero psig per Section 4.8. 4.4.2.2Open the following valves: 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. ACCUM N2 VENT HIK-936. 4.4.2.3Fill accumulator 1B per the following steps: 4.4.2.3.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.4.2.3.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.4.2.3.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.4.2.3.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.4.2.3.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED.4.4.2.3.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.2.3.7Start the hydro test pump using local handswitch N1E21HS2100F.4.4.2.3.8Open ACCUM FILL LINE ISO, Q1E21HV8860. 4.4.2.3.9Open 1B ACCUM FILL LINE ISO, Q1E21HV8878B.CAUTIONPressure should be adjusted gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980) 4.4.2.3.10Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 25 of 724.4.2.3.11Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, ANDverifyonly the desired accumulator shows an increase while filling.NOTEIf accumulator pressure increases to greater than 640 psig, then the hydro test pump must be stopped and the accumulator vented. 4.4.2.3.12Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify only the desired accumulator shows a pressure increase while filling. 4.4.2.3.13 WHEN accumulator level reaches the indicating range, THEN verify level indicators show approximately same level. 4.4.2.3.14 IF level indicators are not approximately equal, THENcontact Maintenance. 4.4.2.3.15 WHEN the accumulator is filled to approximately mid scale on the MCB level indicators ( LI- 924, LI- 926), THENperform the following: 4.4.2.3.15.1Adjust HYDRO TEST PMP DISCH CONT VLV full open using HIK 947. 4.4.2.3.15.2Close 1B ACCUM FILL LINE ISO, Q1E21HV8878B.4.4.2.3.15.3Close 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B.4.4.2.3.15.4Close ACCUM FILL LINE ISO, Q1E21HV8860.4.4.2.3.15.5Stop the hydro test pump. 4.4.2.3.15.6Close ACCUM N2 VENT HIK 936 (Q1G21V092).4.4.2.3.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. 4.4.2.3.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.2.3.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 26 of 724.4.2.3.19Verify ACCUM N2 VENT HIK-936 CLOSED. 4.4.2.3.20Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 25 psig. (Located in 121' PPR) 4.4.2.3.21Open the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B.4.4.2.3.22Open 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B.4.4.2.3.23Open ACCUM N2 SUPPLY ISO, Q1E21HV8880. NOTEThe intent of the following is to pressurize the accumulator to approximately 25 psig. Stop at this point and wait for I&C to complete venting the lower level taps on the accumulator instruments. After venting is complete then continue with accumulator pressurization to the normal pressure band. 4.4.2.3.24 WHEN accumulator pressure reaches approximately 25 psig, THEN perform the following:4.4.2.3.24.1Close 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B.4.4.2.3.24.2Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B.4.4.2.3.24.3Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 625 PSIG. (Located in 121' PPR) 4.4.2.3.24.4Close ACCUM N2 SUPP ISO, Q1E21HV8880.4.4.2.3.24.5HaveI&C vent the lower level taps on the accumulator instruments. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 27 of 724.4.2.3.25 IF required, THEN increase accumulator pressure to the desired value per Section 4.5. 4.4.3Establishing a Nitrogen Atmosphere in Accumulator 1C4.4.3.1 IF required, THEN vent accumulator 1C to zero psig per Section 4.8. 4.4.3.2Open the following valves: 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. ACCUM N2 VENT HIK-936. 4.4.3.3Fill accumulator 1C per the following steps: 4.4.3.3.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.4.3.3.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.4.3.3.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.4.3.3.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.4.3.3.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED.4.4.3.3.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.3.3.7Start the hydro test pump using local handswitch N1E21HS2100F.4.4.3.3.8Open ACCUM FILL LINE ISO, Q1E21HV8860. 4.4.3.3.9Open 1C ACCUM FILL LINE ISO, Q1E21HV8878C.CAUTIONPressure should be adjusted gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980)4.4.3.3.10Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 28 of 724.4.3.3.11Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, ANDverifyonly the desired accumulator shows an increase while filling.NOTEIf accumulator pressure increases to greater than 640 psig, then the hydro test pump must be stopped and the accumulator vented. 4.4.3.3.12Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify only the desired accumulator shows a pressure increase while filling. 4.4.3.3.13 WHEN accumulator level reaches the indicating range, THEN verify level indicators show approximately same level. 4.4.3.3.14 IF level indicators are not approximately equal, THENcontact maintenance. NOTEEnsure accumulator pressure does not exceed 645 psig during filling, which is the setpoint for accumulator high pressure alarm. 4.4.3.3.15 WHEN the accumulator is filled to approximately mid scale on the MCB level indicators ( LI- 928, LI- 930), THENperform the following: 4.4.3.3.15.1Adjust HYDRO TEST PMP DISCH CONT VLV full open using HIK 947. 4.4.3.3.15.2Close 1C ACCUM FILL LINE ISO, Q1E21HV8878C.4.4.3.3.15.3Close 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C.4.4.3.3.15.4Close ACCUM FILL LINE ISO, Q1E21HV8860.4.4.3.3.15.5Stop the hydro test pump. 4.4.3.3.15.6Close ACCUM N2 VENT HIK 936 (Q1G21V092).4.4.3.3.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 29 of 724.4.3.3.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.3.3.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.4.3.3.19Verify ACCUM N2 VENT HIK-936CLOSED.4.4.3.3.20Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 25 psig. (Located in 121' PPR) 4.4.3.3.21Open the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.4.3.3.22Open 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C.4.4.3.3.23Open ACCUM N2 SUPPLY ISO, Q1E21HV8880. NOTEThe intent of the following is to pressurize the accumulator to approximately 25 psig. Stop at this point and wait for I&C to complete venting the lower level taps on the accumulator instruments. After venting is complete then continue with accumulator pressurization to the normal pressure band. 4.4.3.3.24 WHEN accumulator pressure reaches approximately 25 psig, THEN perform the following: 4.4.3.3.24.1Close 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.4.3.3.24.2Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.4.3.3.24.3Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 625 PSIG. (Located in 121' PPR) 4.4.3.3.24.4Close ACCUM N2 SUPP ISO, Q1E21HV8880. 4.4.3.3.24.5HaveI&C vent the lower level taps on the accumulator instruments.4.4.3.3.25 IF required, THEN increase accumulator pressure to the desired value per Section 4.5. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 30 of 72CAUTIONS The nitrogen cover pressure should be maintained between 605 and 645 psig while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). Cross-connection of accumulators via N2 or Fill lines is Prohibited in Modes 1, 2, or 3 (with RCS pressure greater than 1000 psig). 4.5Increasing Accumulator Nitrogen Pressure 4.5.1IF increasing accumulator nitrogen pressure after establishing nitrogen atmosphere per Section 4.4, THEN ensure the high pressure nitrogen banks are greater than 1000 psig.4.5.2Increasing 1A Accumulator Nitrogen Pressure: 4.5.2.1Ensure nitrogen atmosphere has been established in 1A accumulator.4.5.2.2Verify ACCUM N2 VENT HIK 936(Q1E21V092) closed. 4.5.2.3Open OR check open the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.2.4Open OR checkopen ACCUM N2 SUPP ISO Q1E21HV8880, (Q1E21V059). 4.5.2.5Open 1A ACCUM N2 SUPP/VT ISO Q1E21HV8875A. 4.5.2.6Monitor accumulator pressure AND verify the pressure in accumulator 1A is the only accumulator which shows an increase in pressure. 4.5.2.7 WHEN pressure increases to approximately 625 psig, THENclose 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A.(Q1E21V047A).4.5.2.8 IF pressure is to be increased in another accumulator immediately, THEN proceed to Section 4.5.3 or 4.5.4. 4.5.2.9Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.2.10Close ACCUM N2 SUPP ISO Q1E21HV8880 (Q1E21V059). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 31 of 724.5.3Increasing 1B Accumulator Nitrogen Pressure: 4.5.3.1Ensure nitrogen atmosphere has been established in 1B accumulator.4.5.3.2Verify ACCUM N2 VENT HIK 936(Q1E21V092) CLOSED.4.5.3.3Open OR checkopen the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.3.4Open OR checkopen ACCUM N2 SUPP ISO Q1E21HV8880 (Q1E21V059). 4.5.3.5Open 1B ACCUM N2 SUPP/VT ISO Q1E21HV8875B. (Q1E21V047B).4.5.3.6Monitor accumulator pressure AND verify the pressure in accumulator 1B is the only accumulator which shows an increase in pressure. 4.5.3.7 WHEN pressure increases to approximately 625 psig, THENclose 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B.4.5.3.8 IF pressure is to be increased in another accumulator immediately, THEN proceed to Section 4.5.2 or 4.5.4. 4.5.3.9Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.3.10Close ACCUM N2 SUPP ISO, Q1E21HV8880. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 32 of 724.5.4Increasing 1C Accumulator Nitrogen Pressure: 4.5.4.1Ensure that a nitrogen atmosphere has been established in 1C accumulator. 4.5.4.2Verify ACCUM N2 VENT HIK 936(Q1E21V092) CLOSED.4.5.4.3Open OR check open the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.4.4Open OR checkopen ACCUM N2 SUPP ISO Q1E21HV8880 (Q1E21V059). 4.5.4.5Open 1C ACCUM N2 SUPP/VT ISO Q1E21HV8875C (Q1E21V047C).4.5.4.6Monitor accumulator pressure AND verify the pressure in accumulator 1C is the only accumulator which shows an increase in pressure. 4.5.4.7 WHEN pressure increases to approximately 625 psig, THENclose 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C.4.5.4.8 IF pressure is to be increased in another accumulator immediately, THEN proceed to Section 4.5.2 or 4.5.3. 4.5.4.9Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.4.10Close ACCUM N2 SUPP ISO, Q1E21HV8880. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 33 of 72CAUTIONS The nitrogen cover pressure should be maintained between 605 and 645 psig while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). Cross-connection of accumulators via N2 or Fill lines is Prohibited in Modes 1, 2, or 3 (with RCS pressure greater than 1000 psig).4.6Venting Accumulators 4.6.1 Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to start venting accumulators. 4.6.2Prior to venting, alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.6.3Venting 1A Accumulator: 4.6.3.1Open 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 4.6.3.2Slowly open ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.3.3Monitor accumulator pressure AND verify the pressure in accumulator 1A is the only accumulator which shows a decrease in pressure. 4.6.3.4 WHEN pressure decreases to the desired value, THEN close ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.3.5Close 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A.4.6.4Venting 1B Accumulator: 4.6.4.1Open 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. 4.6.4.2 Slowly open ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.4.3Monitor accumulator pressure AND verify the pressure in accumulator 1B is the only accumulator which shows a decrease in pressure. 4.6.4.4 WHEN pressure decreases to the desired value, THEN close ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.4.5Close 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B.4.6.5Venting 1C Accumulator: 4.6.5.1Open 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.6.5.2 Slowly open ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.5.3Monitor accumulator pressure AND verify the pressure in accumulator 1C is the only accumulator which shows a decrease in pressure. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 34 of 724.6.5.4 WHEN pressure decreases to the desired value, THEN close ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.5.5Close 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 35 of 72NOTEThe accumulators may be pump to the RWST in any order. 4.7Pumping Accumulators to RWST With RCS Pressure Less Than 1000 psig 4.7.1 Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to vent accumulators. 4.7.2 Verify that the RCDT system is aligned for normal operation per Liquid Waste Processing System FNP-1-SOP-50.0A (with exceptions noted). 4.7.3Pumping 1A Accumulator to the RWST: 4.7.3.1 Prior to venting, alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.7.3.2 Verify 1A ACCUM DISCH ISO, Q1E21MOV8808AisCLOSED.4.7.3.3Verify 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A OPEN.4.7.3.4 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092).4.7.3.5Decrease accumulator pressure to 0 psig. 4.7.3.6Verify the following valves CLOSED: 1A ACCUM DRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). SIS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A).4.7.3.7Notify Maintenance to install spool piece in Accumulator 1A drain line to RCDT pump suction. 4.7.3.8 WHENspool piece is installedTHEN, Open 1A ACCUM DRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). 4.7.3.9Stop OR verify stopped the following RCDT pumps: 4.7.3.9.1 RCDT pump 1A. 4.7.3.9.2 RCDT pump 1B. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 36 of 724.7.3.10Close the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. NOTEWhen the following lineup is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.7.3.11Open the following valves: SIS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A). RCDT LCV, Q1G21LCV1003. 4.7.3.12Verify closed OR close the following valves: RCDT DISCH TO WHT, Q1G21V009 (1-LWP-V-7137). RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551).4.7.3.13Verify SFP purification loop is NOT in operation per FNP-1-SOP-54.0, Spent Fuel Pit Cooling And Purification System.4.7.3.14 IF RWST purification is in operation, THEN perform the following:4.7.3.14.1Stop the refueling water purification pump. 4.7.3.14.2CloseQ1G31HV033A, RWST TO RWPP AUTO ISO (MCB) 4.7.3.14.3Close Q1G31HV033B, RWST TO RWPP AUTO ISO (MCB) 4.7.3.15Open OR verifyopen the following valves: RWP PUMP DISCH LINE ISO, N1G31V008 (1-SFP-V-8792). SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B).4.7.3.16Verify RCDT PUMPS DISCH LINE ISO, Q1G21HV7136 OPEN. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 37 of 724.7.3.17Place the handswitch for RCDT PUMPS DISCH LINE ISO, Q1G21HV7136 in the AUTO position. NOTEThe operation of the refueling water purification pump is not required. SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B) should be throttled as necessary to limit flow through SFP demineralizer to < 100 GPM on FI-654. 4.7.3.18Open RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.7.3.19Open RCDT LCV, Q1G21LCV1003. 4.7.3.20Start one of the following RCDT pumps: RCDT pump 1A. OR RCDT pump 1B. NOTEThe RWP pump is not required; however, experience has shown it greatly increases flow and it is normally desired to have running. CAUTIONThe RWP pump does not have a low flow trip. 4.7.3.21 IF desired when pumping to the RWST, THEN start the RWP pump as follows:4.7.3.21.1Notify an operator at the refueling water purification pump to monitor discharge pressure of the pump. 4.7.3.21.2 IF the RWP pump discharge pressure indicator PI-3924 indicates a positive pressure due to a running RCDT pump, THEN the RWP pump may bestarted. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 38 of 72NOTETwo RCDT pumps may be required to prevent the RWP pump from cavitating. If a second RCDT pump is started, RCDT pump discharge pressure should be monitored to ensure the relief valve is not challenged (< 150 psig). CAUTIONRCDT pump discharge piping is protected from over pressurization by a relief valve at penetration 31 outside containment which discharges to the equipment drains. This relief valve can sustain seat leakage at pressures above 150 psig 4.7.3.22 IF necessary to prevent RWP pump cavitation, THEN start the second RCDT pump.NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, the operating RCDT pump will automatically stop. 4.7.3.23 WHEN draining is complete on 1A accumulator, THEN perform the following for the affected accumulator: 4.7.3.24 IF draining on all accumulators complete, THEN stop the REFUEL WATER PURIFICATION PUMP IF running. 4.7.3.24.1 IF draining on all accumulators complete, THEN secure the RCDT pump(s). 4.7.3.24.2Close SI SYS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A).4.7.3.24.3Close 1A ACCUM DRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). 4.7.3.25GoTo Section 4.7.4, 4.7.5 or 4.7.6 as required. 4.7.4Pumping 1B Accumulator to the RWST: 4.7.4.1 Prior to venting, alert personnel in Containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.7.4.2Verify 1B ACCUM DISCH ISO, Q1E21MOV8808B is CLOSED.4.7.4.3Verify 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B is OPEN.4.7.4.4 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092).4.7.4.5Decrease accumulator pressure to 0 psig. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 39 of 724.7.4.6Verify the following valves CLOSED: 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). SIS 1B ACCUM DRN, Q1G21V255B (1-LWP-V-7130B).4.7.4.7Notify Maintenance to install spool piece in accumulator 1B drain line to RCDT pump suction. 4.7.4.8 WHENspool piece is installedTHEN, Open 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). 4.7.4.9Verify RCDT pumps 1A and 1B STOPPED. 4.7.4.10Close the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. NOTEWhen the following lineup is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.7.4.11Open the following valves: SIS 1B ACCUM DRN, Q1G21V255A (1-LWP-V-7130B). RCDT LCV, Q1G21LCV1003. 4.7.4.12Verifyclosed OR close the following valves. CDT DISCH TO WHT, Q1G21V009 (1-LWP-V-7137). RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551).4.7.4.13Verify SFP purification loop is NOT in operation per FNP-1-SOP-54.0, Spent Fuel Pit Cooling And Purification System. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 40 of 724.7.4.14 IF RWST purification is in operation, THEN perform the following:4.7.4.14.1Stop the refueling water purification pump. 4.7.4.14.2CloseQ1G31HV033A, RWST TO RWPP AUTO ISO (MCB) 4.7.4.14.3Close Q1G31HV033B, RWST TO RWPP AUTO ISO (MCB) 4.7.4.15Open OR verifyopen the following valves: RWP PUMP DISCH LINE ISO, N1G31V008 (1-SFP-V-8792). SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B).4.7.4.16Verify RCDT PUMPS DISCH LINE ISO, Q1G21HV7136 OPEN.4.7.4.17Place the handswitch for RCDT PUMPS DISCH LINE ISO, Q1G21HV7136 in the AUTO position. NOTEThe operation of the refueling water purification pump is not required. SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B) should be throttled as necessary to limit flow through SFP demineralizer to < 100 GPM on FI-654. 4.7.4.18Open RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.7.4.19Open RCDT LCV, Q1G21LCV1003. 4.7.4.20Start one of the following RCDT pumps: RCDT pump 1A. OR RCDT pump 1B. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 41 of 72NOTEThe RWP pump is not required; however, experience has shown it greatly increases flow and it is normally desired to have running. CAUTIONThe RWP pump does not have a low flow trip. 4.7.4.21 IF desired when pumping to the RWST, THEN start the RWP pump as follows: 4.7.4.21.1Notify an operator at the refueling water purification pump to monitor discharge pressure of the pump. 4.7.4.21.2 IF the RWP pump discharge pressure indicator PI-3924 indicates a positive pressure due to a running RCDT pump, THEN the RWP pump may bestarted.NOTETwo RCDT pumps may be required to prevent the RWP pump from cavitating. If a second RCDT pump is started, RCDT pump discharge pressure should be monitored to ensure the relief valve is not challenged (< 150 psig). CAUTIONRCDT pump discharge piping is protected from over pressurization by a relief valve at penetration 31 outside containment which discharges to the equipment drains. This relief valve can sustain seat leakage at pressures above 150 psig. 4.7.4.22 IF necessary to prevent RWP pump cavitation, THEN start the second RCDT pump. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 42 of 72NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, the operating RCDT pump will automatically stop. 4.7.4.23 WHEN draining is complete on 1B accumulator, THEN perform the following for the affected accumulator: 4.7.4.23.1 IF draining on all accumulators complete, THEN stop the REFUEL WATER PURIFICATION PUMP,IF running. 4.7.4.23.2 IF draining on all accumulators complete, THEN secure the RCDT pump(s). 4.7.4.23.3Close SI SYS 1B ACCUM DRN, Q1G21V255B(1-LWP-V-7130B).4.7.4.23.4Close 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). 4.7.4.24Go to Section 4.7.3, 4.7.5 or 4.7.6 as required. 4.7.5Pumping 1C Accumulator to the RWST: 4.7.5.1 Prior to venting, alert personnel in Containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.7.5.2Verify 1C ACCUM DISCH ISO, Q1E21MOV8808C is CLOSED.4.7.5.3Verify 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C is OPEN.4.7.5.4 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092).4.7.5.5Decrease accumulator pressure to 0 psig. 4.7.5.6Verify the following valves CLOSED: 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). SI SYS 1C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C).4.7.5.7 Notify Maintenance to install spool piece in accumulator 1C drain line to RCDT pump suction. 4.7.5.8 WHENspool piece is installedTHEN,Open 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 43 of 724.7.5.9Verify RCDT pumps 1A and 1B STOPPED. 4.7.5.10Close the following valves: RCDT OUTLET ISO, N1G21HV7127 (N1G21V006). RCDT RECIRC ISO, N1G21HV7144 (N1G21V106). NOTEWhen the following lineup is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.7.5.11Open the following valves: SI SYS 1C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C). RCDT LCV Q1G21LCV1003 (Q1G21V064). 4.7.5.12Verifyclosed OR close the following valves: RCDT DISCH TO WHT Q1G21V009 (1-LWP-V-7137). RCDT PUMP DISCH TO RHT ISO Q1E21V315 (1-CVC-V-8551).4.7.5.13Verify SFP purification loop is NOT in operation per FNP-1-SOP-54.0, Spent Fuel Pit Cooling and Purification System.4.7.5.14 IF RWST purification is in operation, THEN perform the following: 4.7.5.14.1Stop the refueling water purification pump. 4.7.5.14.2CloseQ1G31HV033A, RWST TO RWPP AUTO ISO (MCB) 4.7.5.14.3Close Q1G31HV033B, RWST TO RWPP AUTO ISO (MCB) 4.7.5.15Open or verifyopen the following valves: RWP PUMP DISCH LINE ISO, N1G31V008 (1-SFP-V-8792). SFP PURIF OUTLET TO RWST N1G31V021B (1-SFP-V-8793B).4.7.5.16Verify RCDT PUMPS DISCH LINE ISO Q1G21HV7136 (Q1G21V006) OPEN. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 44 of 724.7.5.17Place the handswitch for RCDT PUMPS DISCH LINE ISO Q1G21HV7136 (Q1G21V006) is in the AUTO position. NOTEThe operation of the refueling water purification pump is not required. 1-SFP-V-8793B (N1G31V021B) should be throttled as necessary to limit flow through SFP demineralizer to 100 GPM on FI-654. 4.7.5.18Open RCDT DISCH TO SFPCS RWPP SUCT Q1G21V008 (1-LWP-V-7138). 4.7.5.19Open RCDT LCV Q1G21LCV1003 (Q1G21V064).4.7.5.20Start one of the following RCDT pumps: RCDT pump 1A. OR RCDT pump 1B. NOTEThe RWP pump is not required; however, experience has shown it greatly increases flow and it is normally desired to have running. CAUTIONThe RWP pump does not have a low flow trip. 4.7.5.21 IF desired when pumping to the RWST, THEN start the RWP pump as follows: 4.7.5.21.1Notify an operator at the refueling water purification pump to monitor discharge pressure of the pump. 4.7.5.21.2 IF the RWP pump discharge pressure indicator PI-3924 indicates a positive pressure due to a running RCDT pump, THEN the RWP pump may bestarted. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 45 of 72NOTETwo RCDT pumps may be required to prevent the RWP pump from cavitating. If a second RCDT pump is started,RCDT pump discharge pressure should be monitored to ensure the relief valve is not challenged (< 150 psig). CAUTIONRCDT pump discharge piping is protected from over pressurization by a relief valve at penetration 31 outside containment which discharges to the equipment drains. This relief valve can sustain seat leakage at pressures above 150 psig. 4.7.5.22 IF necessary to prevent RWP pump cavitation, THEN start the second RCDT pump.NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, the operating RCDT pump will automatically stop. 4.7.5.23 WHEN draining is complete on 1C accumulator, THEN perform the following for the affected accumulator: 4.7.5.23.1 IF draining on all accumulators complete, THEN stop the REFUEL WATER PURIFICATION PUMP,IF running. 4.7.5.23.2 IF draining on all accumulators complete, THEN secure the RCDT pump(s). 4.7.5.23.3Close SI SYS 1C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C).4.7.5.23.4Close 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). 4.7.5.24GoTo sections 4.7.3, 4.7.4 or 4.7.6 as required. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 46 of 72NOTEThe remainder of this procedure section is meant to be performed after all accumulator draining is completed. 4.7.6Realignment After Pumping to the RWST: 4.7.6.1 IF running, THEN stop the REFUEL WATER PURIFICATION PUMP. 4.7.6.2 IF running, THEN shutdown the RCDT pump(s). 4.7.6.3Realign valves as follows: 4.7.6.3.1Close RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.7.6.3.2Close RWP PUMP DISCH LINE ISO, N1G31V008 (1-SFP-V-8792). 4.7.6.3.3Close SFP PURIF OUTLET TO RWST N1G31V021B (1-SFP-V-8793B). 4.7.6.3.4Close RCDT LCV Q1G21LCV1003 (Q1G21V064).4.7.6.3.5OpenRCDT to RHT Q1E21V315 (1-CVC-V8551) 4.7.6.4Open the following valves: RCDT OUTLET ISO N1G21HV7127 (N1G21V006). RCDT RECIRC ISO N1G21HV7144 (N1G21V106). 4.7.6.5Restore the RCDT to normal operation per FNP-1-SOP-50.0, Liquid Waste Processing System. 4.7.6.6Close the following valves: ACCUM N2 VT HIK-936 (Q1E21V092). 1C ACCUM N2 SUPP/VT ISO Q1E21HV8875C (Q1E21V047C).4.7.6.7Notify Maintenance to remove spool piece from accumulator drain lines to RCDT pump suction. 4.7.6.8Realign RWST OR SFP purification as required. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 47 of 72NOTEThis section should only be used in Modes 4, 5 or 6 and is intended to maintain the accumulators in a depressurized state. Steps 4.8.3, 4.8.4 and 4.8.5 may be performed in any order.4.8Complete Depressurization of All Accumulators to Support Outage Activities 4.8.1 Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to start venting accumulators. 4.8.2Prior to venting, alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.8.3Depressurizing 1A Accumulator: 4.8.3.1Open 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 4.8.3.2 SLOWLY open ACCUM N2 VENT, HIK 936 (Q1G21V092). 4.8.3.3Monitor accumulator pressure AND verify the pressure in accumulator 1A is the only accumulator which shows a decrease in pressure. 4.8.3.4 WHEN pressure decreases to zero, THEN close ACCUM N2 VENT, HIK 936 (Q1G21V092). 4.8.3.5Close 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 4.8.4Depressurizing 1B Accumulator: 4.8.4.1Open 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. 4.8.4.2 SLOWLY open ACCUM N2 VENT, HIK 936 (Q1G21V092). 4.8.4.3Monitor accumulator pressure AND verify the pressure in accumulator 1B is the only accumulator which shows a decrease in pressure. 4.8.4.4 WHEN pressure decreases to zero, THEN close ACCUM N2 VENT, HIK 936 (Q1G21V092). 4.8.4.5Close 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 48 of 724.8.5Depressurizing 1C Accumulator: 4.8.5.1Open 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.8.5.2 SLOWLY open ACCUM N2 VENT, HIK 936 (Q1G21V092). 4.8.5.3Monitor accumulator pressure AND verify the pressure in accumulator 1C is the only accumulator which shows a decrease in pressure. 4.8.5.4 WHEN pressure decreases to zero, THEN close ACCUM N2 VENT, HIK 936(Q1G21V092). 4.8.5.5Close 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.8.6WHEN all accumulators have been depressurized,THENperform the following: 4.8.6.1Open the following valves: 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.8.6.2 Slowly open ACCUM N2 VENT, HIK 936(Q1G21V092). 4.8.7WHEN activities are complete that required complete depressurization of the accumulators, THEN perform the following:4.8.7.1Close the following valves: 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.8.7.2Close ACCUM N2 VENT, HIK 936(Q1G21V092). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 49 of 72CAUTIONSThe nitrogen cover pressure should be maintained between 605 and 645 psig while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). Cross-connection of accumulators via N2 or Fill lines is Prohibited in Modes 1, 2, or 3 (with RCS pressure greater than 1000 psig).4.9Increasing Accumulator Nitrogen Pressure Using temporary Bottles 4.9.1 Ensure a nitrogen atmosphere has been established in the accumulator(s) to be pressurized. 4.9.2 Verify ACCUM N2 VT HIK 936 (Q1E21V092) CLOSED. 4.9.3 Close the following valves: ACCUM N2 SUPPLY ROOT (Active Bank) N1E21V002A.(Aux. BLDG 155' Nitrogen Storage Rm.) ACCUM N2 SUPPLY ROOT (Reserve Bank) N1E21V002B. (Aux. BLDG 155' Nitrogen Storage Rm.) 4.9.4 Verify the following valves CLOSED: PRIP NITROGEN SUPPLY ISOLATION VALVE N1E21HV3938A. PRIP NITROGEN SUPPLY ISOLATION VALVE N1E21HV3938B.NOTEIt will take approximately 3 Nitrogen bottles to raise accumulator pressure from 610 psig to 625 psig. 4.9.5 Secure the required Nitrogen bottles near penetration 63. (121' Piping Pen Rm.)4.9.6 Install a regulator capable of supplying 650 psig pressure on one of the N2 bottles ANDconnect discharge to piping downstream of ACCUM N2 SUPP TEST DRAIN, N1E21V303B.4.9.7 Open the isolation valve on the Nitrogen bottle AND adjustthe output of the regulator to approximately 625 psig. 4.9.8 Open the following valves: ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B. ACCUM N2 SUPPLY TEST DRAIN ROOT N1E21V303A. 4.9.9 Open ACCUM N2 SUPP ISO Q1E21HV8880 (Q1E21V059). Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 50 of 724.9.10IF pressurizing 1A Accumulator, THEN perform the following: 4.9.10.1Open 1A ACCUM N2 SUPP/VT ISO Q1E21HV8875A (Q1E21V047A).4.9.10.2Monitor accumulator pressure AND verify the pressure in accumulator 1A is the only accumulator which shows an increase in pressure. 4.9.10.3 IF necessary to change out bottles while increasing pressure, THEN: 4.9.10.3.1Close ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B.4.9.10.3.2Close the isolation valve on the in use Nitrogen bottle.4.9.10.3.3Remove the regulator from the in use Nitrogen bottle.4.9.10.3.4Install the regulator on a full Nitrogen bottle.4.9.10.3.5Open the Nitrogen bottle isolation valve.4.9.10.3.6Ensure that the regulator is still set for approximately 625 psig. 4.9.10.3.7Open ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B.4.9.10.4 WHEN pressure increases to approximately 625 psig, THENclose 1A ACCUM N2 SUPP/VT ISO Q1E21HV8875A (Q1E21V047A). 4.9.11IF pressurizing 1B Accumulator, THEN perform the following: 4.9.11.1Open 1B ACCUM. N2 SUPP/VT ISO Q1E21HV8875B (Q1E21V047B).4.9.11.2Monitor accumulator pressure AND verify the pressure in accumulator 1B is the only accumulator which shows an increase in pressure. 4.9.11.3 IF necessary to change out bottles while increasing pressure, THEN: Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 51 of 724.9.11.3.1Close ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B.4.9.11.3.2Close the isolation valve on the in use Nitrogen bottle.4.9.11.3.3Remove the regulator from the in use Nitrogen bottle.4.9.11.3.4Install the regulator on a full Nitrogen bottle.4.9.11.3.5Open the Nitrogen bottle isolation valve.4.9.11.3.6Ensure that the regulator is still set for approximately 625 psig. 4.9.11.3.7Open ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B.4.9.11.4 WHEN pressure increases to approximately 625 psig, THENclose 1B ACCUM N2 SUPP/VT ISO Q1E21HV8875B (Q1E21V047B). 4.9.12IF pressurizing 1C Accumulator, THEN perform the following: 4.9.12.1Open 1C ACCUM. N2 SUPP/VT ISO Q1E21HV8875C (Q1E21V047C).4.9.12.2Monitor accumulator pressure AND verify the pressure in accumulator 1C is the only accumulator which shows an increase in pressure. 4.9.12.3 IF necessary to change out bottles while increasing pressure, THEN:4.9.12.3.1Close ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B.4.9.12.3.2Close the isolation valve on the in use Nitrogen bottle.4.9.12.3.3Remove the regulator from the in use Nitrogen bottle.4.9.12.3.4Install the regulator on a full Nitrogen bottle.4.9.12.3.5Open the Nitrogen bottle isolation valve.4.9.12.3.6Ensure that the regulator is still set for approximately 625 psig. 4.9.12.3.7Open ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 52 of 724.9.12.4 WHEN pressure increases to approximately 625 psig, THENclose 1C ACCUM N2 SUPP/VT ISO Q1E21HV8875C (Q1E21V047C). 4.9.13 Close the following valves: ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B. ACCUM N2 SUPPLY TEST DRAIN ROOT N1E21V303A. 4.9.14 Close ACCUM N2 SUPP ISO Q1E21HV8880 (Q1E21V059). 4.9.15 Open ACCUM N2 SUPPLY ROOT (Active Bank) N1E21V002A. (Aux. BLDG 155' Nitrogen Storage Rm.)4.9.16WHEN nitrogen bottles are no longer required, THEN performthe following: 4.9.16.1Ensure isolation valve on the nitrogen bottle connected for use is closed. 4.9.16.2Disconnect the regulator from ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B. 4.9.16.3Disconnect regulator from the nitrogen bottle. 4.9.16.4Remove all nitrogen bottles and the regulator from the 121 piping penetration room. 4.9.16.5Place the nitrogen bottles and regulator in the appropriate storage locations. Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 53 of 725.0 References 5.1D-175038 (Sh 1-2), Safety Injection System 5.2D-175039 (Sh 1-4), CVCS 5.3D-175042 (Sh 1), Waste Processing System 5.4D-175043, Spent Fuel Pool Cooling System 6.0 Records QARecord(X)Non-QARecord(X)Record Generated Retention Time R-Type X FNP-1-SOP-8.0 Life of plant HH6.051 UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 54 of 72APPENDIX 1 FEED AND BLEED OF ACCUMULATOR 1A TO RAISE BORON CONCENTRATION > 2300 PPM Performed by: DateReviewed by: DateThis appendix consists of 4 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 55 of 72APPENDIX 1 FEED AND BLEED OF ACCUMULATOR 1ATO RAISE BORON CONCENTRATION > 2300 PPM (Page 1 of 4) 1.0 Purpose This appendix is written to address in-leakage into 1A accumulator from the RCS and the associated concern for a reduction in boron concentration. 2.0 Precautions and Limitations 2.1Utilizing this method of Feed and Bleed, reactor coolant will backfill the accumulator discharge line up to the accumulator test line connection. 2.2A 1% increase in accumulator level = 8.3 gallons. 2.3Sample flushes should be minimized to only that required to obtain sample when sampling an accumulator that has in-leakage to prevent accumulator from filling with RCS water. 2.4Do not use extended sampling as method to drain accumulators as this would allow the accumulator to slowly fill with RCS water and dilute accumulator boron concentration.2.5Tech Specs require the accumulator be sampled within 6 hours after each solution volume increase of 1% of tank volume (approximately 12% increase in level). 3.0 Initial Conditions 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 56 of 72APPENDIX 1 FEED AND BLEED OF ACCUMULATOR 1ATO RAISE BORON CONCENTRATION > 2300 PPM (Page 2 of 4) 4.0 Instructions 4.1 Record initial Accumulator 1A boron concentration. _____ Boron concentration ppm CAUTIONSAccumulator level must be maintained between 35% and 55%; the intent of this appendix is to finish the feed and bleed at approximately 40%. Accumulator boron concentration must be maintained between 2200 and 2500 ppm; the intent of this appendix is to raise accumulator boron concentration > 2300 ppm. 4.2Aligning Accumulator 1A for Filling 4.2.1 Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. _____ 4.2.2 Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). _____ 4.2.3 Set HYDRO TEST PUMP DISCH CONT VLV, HIK 947, to OPEN._____4.2.4 Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. _____ 4.2.5 Start the hydro test pump. _____ 4.2.6 Unlock ANDopen HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). _____ 4.2.7 Open the following valves: ACCUM FILL LINE ISO, Q1E21HV8860. _____ 1A ACCUM FILL LINE ISO, Q1E21HV8878A _____ 4.3IF desired for trending purposes, THENnotify Chemistry to sample accumulator test line at start of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B) _____ 4.3.1 Record the boron concentration ppm UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 57 of 72APPENDIX 1 FEED AND BLEED OF ACCUMULATOR 1ATO RAISE BORON CONCENTRATION > 2300 PPM (Page 3 of 4) 4.4Aligning Accumulator 1A for Draining 4.4.1 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ 4.4.2 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.4.3 Open 1A ACCUM TEST LINE ISO, Q1E21HV8877A to commence draining accumulator. _____ 4.5 Adjust HYDRO TEST PUMP DISCH CONT VLV, using HIK 947 to control fill rate to match drain rate. _____ CAUTIONIf accumulator 1A level exceeds 55% or decreases below 35%, then stop feed and bleed and restore level. 4.6 Monitor Accumulator 1A, level. 4.6.1 Verify that only 1A accumulator level is changing. _____ 4.6.2 Verify all other accumulator levels remain constant. _____ CAUTIONIf accumulator 1A pressure exceeds 640 psig or decreases below 610 psig, stop feed and bleed and restore pressure. 4.7 Monitor Accumulator 1A pressures.4.7.1 Verify that 1A accumulator pressure is changing. _____ 4.7.2 Verify all other accumulator pressures remain constant. _____ 4.8 Continue Accumulator 1A feed and bleed for approximately 1 hour OR as specified by Shift Supervisor. _____ 4.9IF desired for trending purposes, THEN notify Chemistry to sample accumulator test line prior to completion of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B)_____4.9.1 Record boron concentration ppm. 4.10WHEN Accumulator 1A feed AND bleed is complete, THEN adjustHYDRO TEST PUMP DISCH CONT VLV, HIK 947 to open. _____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 58 of 72APPENDIX 1 FEED AND BLEED OF ACCUMULATOR 1ATO RAISE BORON CONCENTRATION > 2300 PPM (Page 4 of 4) 4.11 Secure Accumulator 1A draining as follows: 4.11.1 Close the following valves: 1A ACCUM TEST LINE ISO, Q1E21HV8877A. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.12 Secure Accumulator 1A filling as follows: 4.12.1 Stop the hydro test pump. _____ 4.12.2 Close the following valves: 1A ACCUM FILL LINE ISO, Q1E21HV8878A. _____ ACCUM FILL LINE ISO, Q1E21HV8860. _____ HYDRO TEST PUMP SUCT, Q1E21V028(1-CVC-V-8932) _____ 4.12.3 Lockclosed HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). _____ 4.12.4 Verify the following valves CLOSED: 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. _____ ACCUM N2 VENT, HIK 936(Q1G21V092). _____ 4.12.5 Verify HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. _____ 4.13 Notify Chemistry to sample Accumulator 1A for boron concentration ANDrecord boron concentration. _____ Boron concentration ppm. 4.14IF boron concentration < 2300 ppm, THEN perform additional feed AND bleeds. _____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 59 of 72APPENDIX 2 FEED AND BLEED OF ACCUMULATOR 1B TO RAISE BORON CONCENTRATION > 2300 PPM Performed by: DateReviewed by: DateThis appendix consists of 4 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 60 of 72APPENDIX 2 FEED AND BLEED OF ACCUMULATOR 1BTO RAISE BORON CONCENTRATION > 2300 PPM (Page 1 of 4) 1.0 Purpose This appendix is written to address in-leakage into 1B accumulator from the RCS and the associated concern for a reduction in boron concentration. 2.0 Precautions and Limitations 2.1Utilizing this method of Feed and Bleed, reactor coolant will backfill the accumulator discharge line up to the accumulator test line connection. 2.2A 1% increase in accumulator level = 8.3 gallons. 2.3Sample flushes should be minimized to only that required to obtain sample when sampling an accumulator that has in-leakage to prevent accumulator from filling with RCS water. 2.4Do not use extended sampling as method to drain accumulators as this would allow the accumulator to slowly fill with RCS water and dilute accumulator boron concentration.2.5Tech Specs require the accumulator be sampled within 6 hours after each solution volume increase of 1% of tank volume (approximately 12% increase in level). 3.0 Initial Conditions 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 61 of 72APPENDIX 2 FEED AND BLEED OF ACCUMULATOR 1BTO RAISE BORON CONCENTRATION > 2300 PPM (Page 2 of 4) 4.0 Instructions 4.1 Record initial Accumulator 1B boron concentration. _____ Boron Concentration ppm CAUTIONSAccumulator level must be maintained between 35% and 55%; the intent of this appendix is to finish the feed and bleed at approximately 40%. Accumulator boron concentration must be maintained between 2200 and 2500 ppm; the intent of this appendix is to raise accumulator boron concentration > 2300 ppm. 4.2Aligning Accumulator 1B for Filling 4.2.1 Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. _____ 4.2.2 Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). _____ 4.2.3 Set HYDRO TEST PUMP DISCH CONT VLV, HIK 947, to OPEN._____4.2.4 Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. _____ 4.2.5 Start the hydro test pump. _____ 4.2.6 Unlock ANDopen HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). _____ 4.2.7 Open the following valves: _____ ACCUM FILL LINE ISO, Q1E21HV8860. _____ 1B ACCUM FILL LINE ISO, Q1E21HV8878B _____ 4.3IF desired for trending purposes, THEN have Chemistry sampleaccumulator test line at start of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B) _____ 4.3.1 Record the boron concentration ppm UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 62 of 72APPENDIX 2 FEED AND BLEED OF ACCUMULATOR 1BTO RAISE BORON CONCENTRATION > 2300 PPM (Page 3 of 4) 4.4Aligning Accumulator 1B for Draining 4.4.1 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ 4.4.2 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.4.3 Open 1B ACCUM TEST LINE ISO, Q1E21HV8877B to commence draining accumulator. _____ 4.5 Adjust HYDRO TEST PUMP DISCH CONT VLV, using HIK 947 to control fill rate to match drain rate. _____ CAUTIONIf accumulator 1B level exceeds 55% or decreases below 35%, stop feed and bleed and restore level. 4.6 Monitor Accumulator 1B level. 4.6.1 Verify that only 1B accumulator level is changing. _____ 4.6.2 Verify all other accumulator levels remain constant. _____ CAUTIONIf accumulator 1B pressure exceeds 640 psig or decreases below 610 psig, stop feed and bleed and restore pressure. 4.7 Monitor Accumulator 1B pressures. 4.7.1 Verify that 1B accumulator pressure is changing. _____ 4.7.2 Verify all other accumulator pressures remain constant. _____ 4.8 Continue Accumulator 1B feed and bleed for approximately 1 hour or as specified by Shift Supervisor. _____ 4.9IF desired for trending purposes, THENnotify Chemistry to sample accumulator test line prior to completion of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B)_____4.9.1 Record boron concentration ppm. 4.10WHEN Accumulator 1B feed and bleed is complete, THEN adjustHYDRO TEST PUMP DISCH CONT VLV, HIK 947 to open. _____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 63 of 72APPENDIX 2 FEED AND BLEED OF ACCUMULATOR 1BTO RAISE BORON CONCENTRATION > 2300 PPM (Page 4 of 4) 4.11 Secure Accumulator 1B draining as follows: 4.11.1 Close the following valves: 1B ACCUM TEST LINE ISO, Q1E21HV8877B. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.12 Secure Accumulator 1B filling as follows: 4.12.1 Stop the hydro test pump. _____ 4.12.2 Close the following valves: 1B ACCUM FILL LINE ISO, Q1E21HV8878B. _____ ACCUM FILL LINE ISO, Q1E21HV8860. _____ HYDRO TEST PUMP SUCT Q1E21V028 (1-CVC-V-8932) _____ 4.12.3 Lock closed HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). _____ 4.12.4 Verify the following valves CLOSED: 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. _____ ACCUM N2 VENT, HIK 936(Q1G21V092). _____ 4.12.5 Verify HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. _____ 4.13 Notify Chemistry to sample Accumulator 1B for boron concentration ANDrecord boron concentration. _____ Boron concentration ppm. 4.14IF boron concentration < 2300 ppm, THEN perform additional feed and bleeds._____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 64 of 72APPENDIX 3 FEED AND BLEED OF ACCUMULATOR 1C TO RAISE BORON CONCENTRATION > 2300 PPM Performed by: DateReviewed by: DateThis appendix consists of 4 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 65 of 72APPENDIX 3 FEED AND BLEED OF ACCUMULATOR 1CTO RAISE BORON CONCENTRATION > 2300 PPM (Page 1 of 4) 1.0 Purpose This appendix is written to address in-leakage into 1C accumulator from the RCS and the associated concern for a reduction in boron concentration. 2.0 Precautions and Limitations 2.1Utilizing this method of Feed and Bleed, reactor coolant will backfill the accumulator discharge line up to the accumulator test line connection. 2.2A 1% increase in accumulator level = 8.3 gallons. 2.3Sample flushes should be minimized to only that required to obtain sample when sampling an accumulator that has in-leakage to prevent accumulator from filling with RCS water. 2.4Do not use extended sampling as method to drain accumulators as this would allow the accumulator to slowly fill with RCS water and dilute accumulator boron concentration.2.5Tech Specs require the accumulator be sampled within 6 hours after each solution volume increase of 1% of tank volume (approximately 12% increase in level). 3.0 Initial Conditions 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 66 of 72APPENDIX 3 FEED AND BLEED OF ACCUMULATOR 1CTO RAISE BORON CONCENTRATION > 2300 PPM (Page 2 of 4) 4.0 Instructions 4.1 Record initial Accumulator 1C boron concentration. _____ Boron concentration ppm CAUTIONSAccumulator level must be maintained between 35% and 55%; the intent of this appendix is to finish the feed and bleed at approximately 40%. Accumulator boron concentration must be maintained between 2200 and 2500 ppm; the intent of this appendix is to raise accumulator boron concentration > 2300 ppm. 4.2Aligning Accumulator 1C for Filling 4.2.1 Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. _____ 4.2.2 Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). _____ 4.2.3 Set HYDRO TEST PUMP DISCH CONT VLV, HIK 947, to OPEN._____4.2.4 Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. _____ 4.2.5 Start the hydro test pump. _____ 4.2.6 Unlock ANDopen HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). _____ 4.2.7 Open the following valves: ACCUM FILL LINE ISO, Q1E21HV8860. _____ 1C ACCUM FILL LINE ISO, Q1E21HV8878C _____ 4.3IF desired for trending purposes, THENnotify Chemistry to sample accumulator test line at start of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B) _____ 4.3.1 Record the boron concentration ppm UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 67 of 72APPENDIX 3 FEED AND BLEED OF ACCUMULATOR 1CTO RAISE BORON CONCENTRATION > 2300 PPM (Page 3 of 4) 4.4Aligning Accumulator 1C for Draining 4.4.1 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ 4.4.2 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.4.3 Open 1C ACCUM TEST LINE ISO, Q1E21HV8877C to commence draining accumulator. _____ 4.5 Adjust HYDRO TEST PUMP DISCH CONT VLV, using HIK 947 to control fill rate to match drain rate. _____ CAUTIONIf accumulator 1C level exceeds 55% or decreases below 35%, then stop feed and bleed and restore level. 4.6 Monitor Accumulator 1C level. 4.6.1 Verify that only 1C accumulator level is changing. _____ 4.6.2 Verify all other accumulator levels remain constant. _____ CAUTIONIf accumulator 1C pressure exceeds 640 psig or decreases below 610 psig, then stop feed and bleed and restore pressure. 4.7 Monitor Accumulator 1C pressures.4.7.1 Verify that 1C accumulator pressure is changing. _____ 4.7.2 Verify all other accumulator pressures remain constant. _____ 4.8 Continue Accumulator 1C feed and bleed for approximately 1 hour OR as specified by Shift Supervisor. _____ 4.9IF desired for trending purposes, THEN notify Chemistry to sample accumulator test line prior to completion of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B)_____4.9.1 Record boron concentration ppm. 4.10WHEN Accumulator 1C feed and bleed is complete, THEN adjustHYDRO TEST PUMP DISCH CONT VLV, HIK 947 to OPEN. _____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 68 of 72APPENDIX 3 FEED AND BLEED OF ACCUMULATOR 1CTO RAISE BORON CONCENTRATION > 2300 PPM (Page 4 of 4) 4.11 Secure Accumulator 1C draining as follows: 4.11.1 Close the following valves: 1C ACCUM TEST LINE ISO, Q1E21HV8877C. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.12 Secure Accumulator 1C filling as follows: 4.12.1 Stop the hydro test pump. _____ 4.12.2 Close the following valves: 1C ACCUM FILL LINE ISO, Q1E21HV8878C. _____ ACCUM FILL LINE ISO, Q1E21HV8860. _____ HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932) _____ 4.12.3 Lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967) closed. _____ 4.12.4 Verify the following valves CLOSED: 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. _____ ACCUM N2 VENT, HIK 936(Q1G21V092). _____ 4.12.5 Verify HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. _____ 4.13 Notify Chemistry to sample Accumulator 1C for boron concentration. ANDrecord boron concentration. _____ Boron concentration ppm. 4.14IF boron concentration < 2300 ppm, THEN perform additional feed and bleeds. _____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 69 of 72APPENDIX 4 LEAKAGE ASSESSMENT OF NITROGEN HEADER IN CTMT DURING MODES 5, 6 OR DEFUELED Performed by: DateReviewed by: DateThis appendix consists of 3 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 70 of 72APPENDIX 4 LEAKAGE ASSESSMENT OF NITROGEN HEADER IN CTMT DURING MODES 5, 6 OR DEFUELED (Page 1 of 3) 1.0 Purpose This appendix is written to perform leak assessment of nitrogen header inside CTMT to determine possible sources of CTMT air in leakage. 2.0 Precaution and Limitations None.3.0 Initial Conditions 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 71 of 72APPENDIX 4 LEAKAGE ASSESSMENT OF NITROGEN HEADER IN CTMT DURING MODES 5, 6 OR DEFUELED (Page 2 of 3) 4.0 Instructions 4.1 Verify the following valves CLOSED: 4.1.1Accumulator Nitrogen Vent Q1E21HCV936-(HIK 936) (MCB). _____ 4.1.21A ACCUM N2 SUPP/VT ISO Q1E21HV8875A (MCB). _____ 4.1.31B ACCUM N2 SUPP/VT ISO Q1E21HV8875B (MCB). _____ 4.1.41C ACCUM N2 SUPP/VT ISO Q1E21HV8875C (MCB). _____ 4.2 Verify ACCUM N2 SUPPLY ROOT (ACTIVE BANK) N1E21V002A OPEN._____4.3 Open the following valves located on the PRIP: 4.3.1ACCUM N2 SUPPLY ISOLATION N1E21HV3938A _____ 4.3.2ACCUM N2 SUPPLY ISOLATION N1E21HV3938B _____ 4.4 Open Accumulator N2 Supply ISO Q1E21HV8880 (MCB) _____ 4.5Slowlyadjust N2 Supply to Accumulator Regulator N1E21V013 to approximately 650 psig. _____ 4.6 Perform leak checks on the following components: Accum Nitrogen Vent Q1E21HCV936 (CTMT 129') _____ N2Supply HDR to Accum Relief Valve Q1E21V060 (CTMT 129') _____ N2Supply HDR to Accum. Test Conn. Q1E21V420A (CTMT 126') _____ N2Supply HDR to Accum Test Conn. ISO Q1E21V420B (CTMT 126') _____ N2Supply HDR to Accum Test Conn. N1E21V304A (CTMT 129') _____ N2Supply HDR to Accum. Test Conn. ISO N1E21V304B (CTMT 129') _____4.7 Generate work orders to have air leaks/components repaired ORreplaced._____ Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 72 of 72APPENDIX 4 LEAKAGE ASSESSMENT OF NITROGEN HEADER IN CTMT DURING MODES 5, 6 OR DEFUELED (Page 3 of 3) 4.8 Close the following valves located on the PRIP: 4.8.1ACCUM N2 SUPPLY ISOLATION N1E21HV3938A _____ 4.8.2ACCUM N2 SUPPLY ISOLATION N1E21HV3938B _____ 4.9 Close accumulator N2 supply ISO Q1E21HV8880 (MCB) _____ 4.10Slowlyadjust N2 Supply to Accumulator Regulator N1E21V013 to approximately 15 psig. _____ 4.11 Vent N2 Hdr in CTMT by opening Accumulator Nitrogen Vent Q1E21HCV936-(HIK 936) (MCB) _____ 4.12 Verify Accumulator Nitrogen Vent Q1E21HCV936-(HIK 936) CLOSED (MCB) _____ jpm b TITLE: Perform The Required Actions For Cold Leg Recirculation ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: X SIMULATOR CONTROL ROOM PLANT PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: IC-212 (Base -151) ALTERNATE PATH X TIME CRITICAL PRA JPM DIRECTIONS: 1. Examinee will obtain all references from the simulator. 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise. 3. Provide student with HANDOUT. 4. Allow student time to review control board. 5. Instructor will be provided to address alarms not related to evaluated task. TASK STANDARD: Upon successful completion of this JPM, the examinee will: 1. Perform the Required Actions For Cold Leg Recirculation. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) EXAMINER:

Developer S Jackson Date: 4/7/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP ILT-38 JPM Page 2 of 9 EVENT DESCRIPTION ACTION DETAILS Reset into IC-212 Acknowledge computer alarms Run / Freeze Simulator Acknowledge Alarms Turn Horns ON Run / Freeze Simulator FNP ILT-38 JPM Page 3 of 9 CONDITIONS When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS FOR COLD LEG RECIRCULATION. The conditions under which this task is to be performed are: a. A LBLOCA has occurred. b. ESP-1.3, Transfer to Cold Leg Recirc, has been entered and all steps through Step 6 have been completed. c. Recirculation Disconnects are Closed. d. You are directed by the Shift Supervisor to transfer to cold leg recirculation starting at Step 7 of ESP-1.3. e. A pre-job brief is not required. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME 1. 7.1 Check large break LOCA has occurred as indicated by accumulators discharged. Observes LI-920 & 922, 924 & 926, 928 & 930, TK1, TK2, TK3 ACCUMULATOR LVL indicates 0 percent. S / U 2. 7.2 Check containment sump level - GREATER THAN 3.4 ft {3.8 ft}. LI-3594A or LR-3594B checked. Observes sump level ~ 4 ft. S / U 3. 7.3 Proceed to step 7.5 Proceeds to step 7.5 S / U 4. 7.5 Verify recirculation valve disconnects - CLOSED USING ATTACHMENT 1. This is part of the initial conditions. May refer to . Observes all white lights lit. S / U *5. 7.6 Stop both RHR PUMPs. 1A and 1B RHR pump handswitches taken to stop. Observes 1A & 1B RHR pump Amps indicate '0', Both pumps green lights lit and red lights NOT lit. S / U NOTE: THE FOLLOWING ELEMENT IS THE START OF THE ALTERNATE PATH IN THE RNO COLUMN. FNP ILT-38 JPM Page 4 of 9 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 6. 7.7 Close RWST TO 1A RHR PUMP Q1E11MOV8809A. MOV-8809A handswitch taken to closed. Observes BOTH lights are out. S / U 7. 7.7 (RNO) Perform the following: 7.7.1 Stop the running A train CHG PUMP. Note: Step 7.7.2 is not critical. 7.7.2 Proceed to step 7.12 Takes 1A Charging pump HS to stop. Observes 1A CHG pump Amps indicate '0', pump green light lit and red light NOT lit.

Proceeds to step 7.12 S / U

S / U *8. 7.12 Close RWST TO 1B RHR PUMP Q1E11MOV8809B. HS for MOV-8809B taken to closed. Observes green light lit, red light out. S / U *9. 7.13 Align CTMT sump to 1B RHR PUMP. CTMT SUMP TO 1B RHR PUMP [] Q1E11MOV8811B open [] Q1E11MOV8812B open HS for MOV-8811B and MOV-8812B, taken to open. Observes red lights lit, green lights out. S / U *10. 7.14 Close RHR to RCS HOT LEGS XCON Q1E11MOV8887B. HS for MOV-8887B taken to closed. Observes green light lit, red light out. S / U *11. 7.15 Start 1B RHR PUMP. [] 1B amps > 0 HS for 1B RHR PMP taken to start. Observes pump Amp meter indicates amps, pump breaker red light lit, green light out. S / U 12. 7.16 Verify B Train LHSI flow - STABLE. 1B RHR HDR FLOW [] FI 605B FI-605B checked. Observes FI-605B stable. S / U FNP ILT-38 JPM Page 5 of 9 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 13. 7.17 Verify at least one train of RHR in operation providing recirculation flow. Checks that B train RHR is providing recirculation flow. Observes 1B RHR pump running and providing flow. S / U 14. 7.18 Verify charging pump miniflow valves - CLOSED. 1A(1B,1C) CHG PUMP MINIFLOW ISO [] Q1E21MOV8109A [] Q1E21MOV8109B [] Q1E21MOV8109C CHG PUMP MINIFLOW ISO [] Q1E21MOV8106 Indications for MOVs 8109A/B/C and 8106 checked. Observes green lights are lit and red lights are out. S / U 15. 7.19 Verify seal return flow valves - CLOSED. RCP SEAL WTR RTN ISO [] Q1E21MOV8100 closed [] Q1E21MOV8112 closed Indications for seal return flow valves MOV 8100 and 8112 checked. Observes MOV 8100 and 8112 indications green lights lit, red lights NOT lit. S / U 16. 7.20 IF 1A RHR PUMP started, THEN align charging pump suction header isolation valves based on 1B charging pump status. Observes 1A Charging pump breaker position indicators green lights lit, red lights out. Proceeds to step 7.25 S / U Note: Closing MOV-8131A & B is the critical portion of this step. *17. 7.25 IF 1B RHR PUMP started, THEN align charging pump suction header isolation valves based on 1B charging pump status. Checks position indication for CHG PMP SUCT HDR ISO VLV MOV-8130A and B. Observes valve position indicators red lights lit, green lights NOT lit. S / U . HS for MOV-8131A and B taken to close. Observes green lights lit red lights out. S / U FNP ILT-38 JPM Page 6 of 9 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *18. 7.26 Open RHR supply to B train charging pump suction. 1B RHR HX CHG PUMP. TO CHG PUMP SUCT [] Q1E11MOV8706B HS for MOV-8706B taken to open. Observes red light lit, green light out. S / U 19. 7.27 Verify B train CHG PUMP - started. Observes 1B Charging pump red light lit and Amps > 0. S / U 20. 7.28 Verify VCT level is > 5%. Observes LI-115/112 indicates > 5% level. S / U *21. 7.29 Close B train RWST to charging pump header valve. RWST TO CHG PUMP [] Q1E21LCV115D HS for LCV-115D taken to close. Observes green light lit, red light out. S / U 22. 7.30 Check one CHG PUMP in each train - STARTED.

[] A train (1A or 1B) amps > 0   [] B train (1C or 1B) amps > 0 Observes 1C pump Amps > 0, red light is lit, green light NOT lit. Observes 1A Charging pump green light lit, red light out. S  /  U    *23. 7.30.1 (RNO)  Open charging pump recirculation to RCS  cold legs valve. CHG PUMP RECIRC  TO RCS COLD LEGS  [] Q1E21MOV8885 HS for MOV-8885 handswitch taken to open. Observes valve position indicator red light lit, green light NOT lit, FI-940 HAS flow and FI-943 does NOT have flow. S  /  U    *24. 7.30.2 (RNO)  Close HHSI isolation valves.

HHSI TO RCS CL ISO [] Q1E21MOV8803A [] Q1E21MOV8803B HS for MOV-8803A and MOV-8803B taken to close. Observes green lights lit, red lights out. Proceeds to step 7.32 S / U FNP ILT-38 JPM Page 7 of 9 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) Note: Closing MOV-8133A & B is the critical portion of this step. *25. 7.32 Align charging pump discharge header isolation valves based on 1B charging pump status. Checks open MOV-8132A and B. Observes valve position indicators red lights lit, green lights NOT lit. S / U HS for MOV-8133A and B taken to close. Observes valve position indicators green lights lit, red light out. S / U 26. 7.33 Verify SI flow - STABLE Flow is checked. Observes flow indicated on FI-940, 'B' TRAIN RECIRC FLOW and FI-605B 'B' train RHR HDR flow. NO flow indicated on FI-943, A TRAIN RECIRC FLOW and FI-605A, 'A' train RHR HDR flow. S / U STOP TIME Terminate when STEP 7 is complete: SI flow is determined to be stable.

CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) preceding the element number.

GENERAL

REFERENCES:

1. FNP-1-ESP-1.3, ver 22 2. K/As: 011EA1.11 - 4.2 / 4.2 011EA1.13 - 4.1 / 4.2 GENERAL TOOLS AND EQUIPMENT:

1. Copy of ESP-1.3, ver 22 FNP ILT-38 JPM Page 8 of 9 Critical ELEMENT justification: 1 - 4 Not critical - No actions required 5 Critical - Task completion. If left running, damage could occur when 1B RHR suction is isolated. 6 Not critical - valve will not close 7 Not critical - Pump will still have suction source. 8-10 Critical - Task completion. Required line up for recirculation. 11 Critical - Task completion. Provide water source for recirculation. 12 -16 Not critical. No actions required. 17 Critical - Task completion. Provides train separation 18 Critical - Task completion. Provides suction source for Charging pump 19-20 Not critical. No actions required. 21 Critical - Task completion. System alignment. 22 Not critical. No actions required. 23-24 Critical - Task completion. System alignment for recirculation flow. 25 Critical - Task completion. Provides train separation 26 Not critical. No actions required.

COMMENTS: FNP ILT-38 JPM HANDOUT Page 1 of 1 jpm b CONDITIONS When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS FOR COLD LEG RECIRCULATION. The conditions under which this task is to be performed are: a. A LBLOCA has occurred. b. ESP-1.3, Transfer to Cold Leg Recirc, has been entered and all steps through Step 6 have been completed. c. Recirculation Disconnects are Closed. d. You are directed by the Shift Supervisor to transfer to cold leg recirculation starting at Step 7 of ESP-1.3. e. A pre-job brief is not required.

FNP-1-ESP-1.3FNP-1-ESP-1.32-09-20112-09-2011Revision 22Revision 22FARLEY NUCLEAR PLANTFARLEY NUCLEAR PLANTEVENT SPECIFIC PROCEDUREEVENT SPECIFIC PROCEDUREFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATION S S A A FF PROCEDURE USAGE REQUIREMENTS-per FNP-0-AP-6 PROCEDURE USAGE REQUIREMENTS-per FNP-0-AP-6 SECTIONS SECTIONS EE TTContinuous Use Continuous Use Continuous Use ALL ALL ALL YY Reference UseReference UseReference Use RR EEInformation UseInformation UseInformation Use LL AA T T E E D D Approved:Approved: Operations ManagerOperations ManagerDate Issued:Date Issued: 1/22/201314:30UNIT 1DavidL.Reed(for)02/10/11 FNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22Table of ContentsTable of Contents Procedure ContainsProcedure Contains Number of PagesNumber of Pages Body..................................19 Body..................................19 Attachment 1...........................3 Attachment 1...........................3Page 1 of 1Page 1 of 11/22/201314:30UNIT 1 FNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22A.A.A.PurposePurposePurposeThis procedure provides the necessary instructions for transferringThis procedure provides the necessary instructions for transferringthe safety injection system and containment spray system to thethe safety injection system and containment spray system to therecirculation mode.recirculation mode.B.B.B.Symptoms or Entry ConditionsSymptoms or Entry ConditionsSymptoms or Entry ConditionsI.I.This procedure is entered when RWST level is less than 12.5 ft; fromThis procedure is entered when RWST level is less than 12.5 ft; fromthe following:the following:a.a.FNP-1-EEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, step 15FNP-1-EEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, step 15b.b.FNP-1-ESP-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, step 1FNP-1-ESP-1.2, POST LOCA COOLDOWN AND DEPRESSURIZATION, step 1c.c.FNP-1-ECP-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAMFNP-1-ECP-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAMGENERATORS, step 13GENERATORS, step 13d.d.FNP-1-FRP-C.2, RESPONSE TO DEGRADED CORE COOLING, step 1FNP-1-FRP-C.2, RESPONSE TO DEGRADED CORE COOLING, step 1e.e.FNP-1-FRP-C.3, RESPONSE TO SATURATED CORE COOLING, step 1FNP-1-FRP-C.3, RESPONSE TO SATURATED CORE COOLING, step 1f.f.FNP-1-FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, step 20FNP-1-FRP-H.1, RESPONSE TO LOSS OF SECONDARY HEAT SINK, step 20g.g.A Foldout PageA Foldout PagePage 1 of 19Page 1 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22****************************************************************************************************************************************************************************CAUTIONCAUTION::To ensure that SI recirculation flow is maintained at all times, theTo ensure that SI recirculation flow is maintained at all times, thefollowing steps should be performed without delay.following steps should be performed without delay.********************************************************************************************************************************************************************************************************************************************************************************************************************************************************CAUTIONCAUTION::No Function Restoration Procedure should be implemented until step 7No Function Restoration Procedure should be implemented until step 7has been completed.has been completed.********************************************************************************************************************************************************************************************************************************************************************************************************************************************************CAUTIONCAUTION::Switchover to recirculation may cause high radiation levels in theSwitchover to recirculation may cause high radiation levels in theauxiliary building.auxiliary building.**************************************************************************************************************************************************************************** 111[CA] Check RWST level - GREATER[CA] Check RWST level - GREATER[CA] Check RWST level - GREATER11IFIF alignment for recirculation alignment for recirculationTHAN 4.5 ft.THAN 4.5 ft.THAN 4.5 ft.is is NOTNOT imminent, imminent, THENTHEN stop any pump taking stop any pump takingsuction from the RWST.suction from the RWST.CHG PUMPCHG PUMP[][]1A1A[][]1B1B [][]1C1CRHR PUMPRHR PUMP[][]1A1A [][]1B1B[][]CS RESET CS RESET TRN A(B) containment sprayTRN A(B) containment spraysignals - RESET (Annunciatorsignals - RESET (AnnunciatorEE4 clear).EE4 clear). CS PUMPCS PUMP[][]1A1A[][]1B1BPage 2 of 19Page 2 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22NOTE:NOTE:The intent of Step 2 is to differentiate between a steam line breakThe intent of Step 2 is to differentiate between a steam line breakevent (with SI terminated and RWST drain down only from containmentevent (with SI terminated and RWST drain down only from containmentspray operation) and a loss of reactor coolant event (RWST drain downspray operation) and a loss of reactor coolant event (RWST drain downfrom one or more ECCS pumps).from one or more ECCS pumps). 222Check SI in service.Check SI in service.Check SI in service.22Perform the following.Perform the following.Check HHSI flow - GREATERCheck HHSI flow - GREATER2.12.1Reset containment sump to RHRReset containment sump to RHRTHAN 0 gpm.THAN 0 gpm.valve switches.valve switches.A TRNA TRNCTMT SUMP TO RHR CTMT SUMP TO RHR HHSI FLOWHHSI FLOWPUMP RESETPUMP RESET[][]FI 943FI 943[][]A TRNA TRN[][]B TRNB TRNOROR2.22.2Proceed to step 8.Proceed to step 8.Check any RHR PUMP - STARTEDCheck any RHR PUMP - STARTEDIN SI MODE.IN SI MODE.Started RHR PUMP Started RHR PUMP 1A 1A 1B 1B RWST TO RWST TO 1A(1B) RHR PUMP 1A(1B) RHR PUMP Q1E11MOV Q1E11MOV [] 8809A[] 8809A[] 8809B[] 8809B open open open open 1C(1A) RCS LOOP 1C(1A) RCS LOOP TO 1A(1B) RHR PUMPTO 1A(1B) RHR PUMP Q2E11MOV Q2E11MOV [] 8701A[] 8701A[] 8702A[] 8702A closed closed closed closed [] 8701B[] 8701B[] 8702B[] 8702B closed closed closed closed Page 3 of 19Page 3 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22 333Verify SI - RESET.Verify SI - RESET.Verify SI - RESET.33Perform the following:Perform the following:[][]MLB-1 1-1 not lit (A TRN)MLB-1 1-1 not lit (A TRN)3.13.1IFIF any train will any train will NOTNOT reset reset[][]MLB-1 11-1 not lit (B TRN)MLB-1 11-1 not lit (B TRN)using the MCB SI RESETusing the MCB SI RESETpushbuttons, pushbuttons, THENTHEN place the affected train place the affected trainS821 RESET switch to RESET.S821 RESET switch to RESET.(SSPS TEST CAB.)(SSPS TEST CAB.)3.23.2IFIF a failure exists in SSPS a failure exists in SSPSsuch that SI cannot be reset, such that SI cannot be reset, THENTHEN reset SI using reset SI usingFNP-1-SOP-40.0, RESPONSE TOFNP-1-SOP-40.0, RESPONSE TOINADVERTENT SI INADVERTENT SI ANDAND INABILITY INABILITYTO RESET TO RESET OROR BLOCK SI, Appendix BLOCK SI, Appendix2.2. 444Verify at least one train ofVerify at least one train ofVerify at least one train ofPRF in operation usingPRF in operation usingPRF in operation usingFNP-1-SOP-60.0, PENETRATIONFNP-1-SOP-60.0, PENETRATIONFNP-1-SOP-60.0, PENETRATIONROOM FILTRATION SYSTEM inROOM FILTRATION SYSTEM inROOM FILTRATION SYSTEM inconjunction with the remainingconjunction with the remainingconjunction with the remainingsteps of this procedure.steps of this procedure.steps of this procedure. 555Check CCW to RHR heatCheck CCW to RHR heatCheck CCW to RHR heat55Open any closed CCW to RHR heatOpen any closed CCW to RHR heatexchangers MOVs - OPEN.exchangers MOVs - OPEN.exchangers MOVs - OPEN.exchanger valve(s) exchanger valve(s) ANDAND continue continuewith this procedure whilewith this procedure whileCCW TO CCW TO valves stroke open.valves stroke open.1A(1B) RHR HX1A(1B) RHR HX[][]Q1P17MOV3185A openQ1P17MOV3185A openCCW TO CCW TO [][]Q1P17MOV3185B openQ1P17MOV3185B open1A(1B) RHR HX1A(1B) RHR HX[][]Q1P17MOV3185A openQ1P17MOV3185A open[][]Q1P17MOV3185B openQ1P17MOV3185B open 666Establish only one CHG PUMP inEstablish only one CHG PUMP inEstablish only one CHG PUMP ineach train - RUNNING.each train - RUNNING.each train - RUNNING.[][]A Train (1A or 1B) amps > 0A Train (1A or 1B) amps > 0[][]B Train (1C or 1B) amps > 0B Train (1C or 1B) amps > 0Page 4 of 19Page 4 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22****************************************************************************************************************************************************************************CAUTIONCAUTION::Pump damage will occur if a charging pump or RHR pump is started in aPump damage will occur if a charging pump or RHR pump is started in atrain in which a flow path from the containment sump to the RCStrain in which a flow path from the containment sump to the RCScannot be established or maintained.cannot be established or maintained.**************************************************************************************************************************************************************************** 777Align ECCS for cold legAlign ECCS for cold legAlign ECCS for cold legrecirculation.recirculation.recirculation.7.17.1Check large break LOCA hasCheck large break LOCA has7.17.1Proceed to step 7.4.Proceed to step 7.4.occurred as indicated byoccurred as indicated byaccumulators discharged.accumulators discharged.7.27.2Check containment sump level -Check containment sump level -7.27.2IFIF both containment sump level both containment sump levelGREATER THAN 3.4 ft {3.8 ft}.GREATER THAN 3.4 ft {3.8 ft}.indications less than 3.4 ftindications less than 3.4 ft{3.8 ft}, {3.8 ft}, CTMT SUMP CTMT SUMP THENTHEN go to FNP-1-ECP-1.1, LOSS go to FNP-1-ECP-1.1, LOSSLVLLVLOF EMERGENCY COOLANTOF EMERGENCY COOLANT[][]LI 3594ALI 3594ARECIRCULATION.RECIRCULATION.POST ACCIDENT POST ACCIDENT CTMT WTR LVLCTMT WTR LVL[][]LR 3594BLR 3594B7.37.3Proceed to step 7.5.Proceed to step 7.5.7.47.4Check containment sump level -Check containment sump level -7.47.4IFIF both containment sump level both containment sump levelGREATER THAN 2.5 ft {2.9 ft}.GREATER THAN 2.5 ft {2.9 ft}.indications less than 2.5 ftindications less than 2.5 ft{2.9 ft}, {2.9 ft}, CTMT SUMP CTMT SUMP THENTHEN go to FNP-1-ECP-1.1, LOSS go to FNP-1-ECP-1.1, LOSSLVLLVLOF EMERGENCY COOLANTOF EMERGENCY COOLANT[][]LI 3594ALI 3594ARECIRCULATION.RECIRCULATION.POST ACCIDENT POST ACCIDENT CTMT WTR LVLCTMT WTR LVL[][]LR 3594BLR 3594B7.57.5Verify recirculation valveVerify recirculation valvedisconnects - CLOSED USINGdisconnects - CLOSED USINGATTACHMENT 1.ATTACHMENT 1.7.67.6Stop both RHR PUMPs.Stop both RHR PUMPs.Step 7 continued on next page.Step 7 continued on next page.Page 5 of 19Page 5 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 227.77.7Close RWST TO 1A RHR PUMPClose RWST TO 1A RHR PUMP7.77.7Perform the following.Perform the following.Q1E11MOV8809A.Q1E11MOV8809A.7.7.17.7.1Stop the running A trainStop the running A trainCHG PUMP.CHG PUMP.7.7.27.7.2Proceed to step 7.12.Proceed to step 7.12.7.87.8Align CTMT sump to 1A RHRAlign CTMT sump to 1A RHR7.87.8Perform the following.Perform the following.PUMP.PUMP.7.8.17.8.1Stop the running A trainStop the running A trainCTMT SUMP CTMT SUMP CHG PUMP.CHG PUMP.TO 1A RHR PUMPTO 1A RHR PUMP[][]Q1E11MOV8811A openQ1E11MOV8811A open7.8.27.8.2Proceed to step 7.12.Proceed to step 7.12.[][]Q1E11MOV8812A openQ1E11MOV8812A open7.97.9Close RHR to RCS HOT LEGS XCONClose RHR to RCS HOT LEGS XCONQ1E11MOV8887A.Q1E11MOV8887A.7.107.10Start 1A RHR PUMP.Start 1A RHR PUMP.7.107.10Perform the following.Perform the following.RHR PUMPRHR PUMP7.10.17.10.1Stop the running A trainStop the running A train[][]1A amps > 01A amps > 0CHG PUMP.CHG PUMP.7.10.27.10.2Proceed to step 7.12.Proceed to step 7.12.7.117.11Verify A Train LHSI flow -Verify A Train LHSI flow -STABLE.STABLE.1A 1A RHR HDR RHR HDR FLOWFLOW[][]FI 605AFI 605A7.127.12Close RWST TO 1B RHR PUMPClose RWST TO 1B RHR PUMP7.127.12Perform the following.Perform the following.Q1E11MOV8809B.Q1E11MOV8809B.7.12.17.12.1Stop the running B trainStop the running B trainCHG PUMP.CHG PUMP.7.12.27.12.2Proceed to step 7.17.Proceed to step 7.17.7.137.13Align CTMT sump to 1B RHRAlign CTMT sump to 1B RHR7.137.13Perform the following.Perform the following.PUMP.PUMP.7.13.17.13.1Stop the running B trainStop the running B trainCTMT SUMP CTMT SUMP CHG PUMP.CHG PUMP.TO 1B RHR PUMPTO 1B RHR PUMP[][]Q1E11MOV8811B openQ1E11MOV8811B open7.13.27.13.2Proceed to step 7.17.Proceed to step 7.17.[][]Q1E11MOV8812B openQ1E11MOV8812B openStep 7 continued on next page.Step 7 continued on next page.Page 6 of 19Page 6 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 227.147.14Close RHR to RCS HOT LEGSClose RHR to RCS HOT LEGSXCON Q1E11MOV8887B.XCON Q1E11MOV8887B.7.157.15Start 1B RHR PUMP.Start 1B RHR PUMP.7.157.15Perform the following.Perform the following.RHR PUMPRHR PUMP7.15.17.15.1Stop the running B trainStop the running B train[][]1B amps > 01B amps > 0CHG PUMP.CHG PUMP.7.15.27.15.2Proceed to step 7.17.Proceed to step 7.17.7.167.16Verify B Train LHSI flow -Verify B Train LHSI flow -STABLE.STABLE.1B 1B RHR HDR RHR HDR FLOWFLOW[][]FI 605BFI 605BStep 7 continued on next page.Step 7 continued on next page.Page 7 of 19Page 7 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 227.177.17Verify at least one train ofVerify at least one train of7.177.17Perform the following:Perform the following:RHR in operation providingRHR in operation providingrecirculation flow.recirculation flow.7.17.17.17.1Check A Train RHRCheck A Train RHRavailable:available:1A RHR Pump1A RHR PumpCTMT SUMP TO 1A RHR PUMPCTMT SUMP TO 1A RHR PUMPQ1E11MOV8811AQ1E11MOV8811ACTMT SUMP TO 1A RHR PUMPCTMT SUMP TO 1A RHR PUMPQ1E11MOV8812AQ1E11MOV8812A1A RHR HX TO CHG PUMP1A RHR HX TO CHG PUMPSUCT Q1E11MOV8706ASUCT Q1E11MOV8706ACCW TO 1A RHR HXCCW TO 1A RHR HXQ1P17MOV3185AQ1P17MOV3185A7.17.27.17.2IFIF A Train RHR components A Train RHR componentsavailable foravailable forrecirculation flowpath, recirculation flowpath, THENTHEN start an A Train start an A TrainCharging Pump and returnCharging Pump and returnto step 7.8.to step 7.8.7.17.37.17.3Check B Train RHRCheck B Train RHRavailable:available:1B RHR Pump1B RHR PumpCTMT SUMP TO 1B RHR PUMPCTMT SUMP TO 1B RHR PUMPQ1E11MOV8811BQ1E11MOV8811BCTMT SUMP TO 1B RHR PUMPCTMT SUMP TO 1B RHR PUMPQ1E11MOV8812BQ1E11MOV8812B1B RHR HX TO CHG PUMP1B RHR HX TO CHG PUMPSUCT Q1E11MOV8706BSUCT Q1E11MOV8706BCCW TO 1B RHR HXCCW TO 1B RHR HXQ1P17MOV3185BQ1P17MOV3185B7.17.47.17.4IFIF B train RHR components B train RHR componentsavailable foravailable forrecirculation flowpath, recirculation flowpath, THENTHEN start a B Train start a B TrainCharging Pump and returnCharging Pump and returnto step 7.13.to step 7.13.7.17.57.17.5IFIF no RHR train is no RHR train isavailable, available, THENTHEN check RWST level check RWST levelgreater than 4.5 ft greater than 4.5 ft ANDANDstart any availablestart any availablecharging pump aligned tocharging pump aligned tothe RWST.the RWST.Step 7 continued on next page.Step 7 continued on next page.Page 8 of 19Page 8 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 227.17.67.17.6Go to FNP-1-ECP-1.1, LOSSGo to FNP-1-ECP-1.1, LOSSOF EMERGENCY COOLANTOF EMERGENCY COOLANTRECIRCULATION.RECIRCULATION.****************************************************************************************************************************************************************************CAUTIONCAUTION::The charging pumps should be stopped if RCS pressure rises to greaterThe charging pumps should be stopped if RCS pressure rises to greaterthan their shutoff head.than their shutoff head.********************************************************************************************************************************************************************************************************************************************************************************************************************************************************CAUTIONCAUTION::The charging pump miniflows should The charging pump miniflows should NOTNOT be reopened to satisfy be reopened to satisfyminiflow criteria while the charging pump suctions are aligned to theminiflow criteria while the charging pump suctions are aligned to theRHR pumps.RHR pumps.****************************************************************************************************************************************************************************7.187.18Verify charging pump miniflowVerify charging pump miniflowvalves - CLOSED.valves - CLOSED.1A(1B,1C) CHG PUMP 1A(1B,1C) CHG PUMP MINIFLOW ISOMINIFLOW ISO[][]Q1E21MOV8109AQ1E21MOV8109A[][]Q1E21MOV8109BQ1E21MOV8109B[][]Q1E21MOV8109CQ1E21MOV8109CCHG PUMP CHG PUMP MINIFLOW ISOMINIFLOW ISO[][]Q1E21MOV8106Q1E21MOV81067.197.19Verify seal return flowVerify seal return flowvalves - CLOSED.valves - CLOSED.RCP SEAL WTRRCP SEAL WTRRTN ISORTN ISO[][]Q1E21MOV8100 closedQ1E21MOV8100 closed[][]Q1E21MOV8112 closedQ1E21MOV8112 closedStep 7 continued on next page.Step 7 continued on next page.Page 9 of 19Page 9 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 227.207.20IFIF 1A RHR PUMP started, 1A RHR PUMP started, 7.207.20IFIF 1A RHR PUMP 1A RHR PUMP NOTNOT started, started, THENTHEN align charging pump align charging pumpTHENTHEN perform the following. perform the following.suction header isolationsuction header isolationvalves based on 1B chargingvalves based on 1B charging7.20.17.20.1Verify the A train CHGVerify the A train CHGpump status.pump status.PUMP stopped.PUMP stopped.7.20.27.20.2Proceed to step 7.25.Proceed to step 7.25.1B Charging1B ChargingAligned AsAligned AsAligned AsAligned As Pump Pump A Train A Train B Train B Train Not Not Status Status pump pump pump pump Available Available CHG PUMP CHG PUMP SUCTION SUCTION HDR ISO HDR ISO Q1E21MOV Q1E21MOV [] 8130A [] 8130A [] 8130A [] 8130A [] 8130A [] 8130A open open closed closed closed closed [] 8130B [] 8130B [] 8130B [] 8130B [] 8130B [] 8130B open open closed closed closed closed [] 8131A [] 8131A [] 8131A [] 8131A [] 8131A [] 8131A closed closed open open closed closed [] 8131B [] 8131B [] 8131B [] 8131B [] 8131B [] 8131B closed closed open open closed closed 7.217.21Open RHR supply to A trainOpen RHR supply to A train7.217.21Perform the following.Perform the following.charging pump suction.charging pump suction.7.21.17.21.1Stop the running A trainStop the running A train1A RHR HX 1A RHR HX CHG PUMP.CHG PUMP.TO CHG PUMP SUCTTO CHG PUMP SUCT[][]Q1E11MOV8706AQ1E11MOV8706A7.21.27.21.2Proceed to step 7.25.Proceed to step 7.25.7.227.22Verify A train CHG PUMP - Verify A train CHG PUMP - started.started.7.237.23Verify VCT level - GREATERVerify VCT level - GREATERTHAN 5%.THAN 5%.7.247.24Close A train RWST toClose A train RWST to7.247.24Perform the following.Perform the following.charging pump header valve.charging pump header valve.7.24.17.24.1Stop the running A trainStop the running A trainRWST RWST CHG PUMP.CHG PUMP.TO CHG PUMPTO CHG PUMP[][]Q1E21LCV115BQ1E21LCV115B7.24.27.24.2Close RHR supply to AClose RHR supply to Atrain charging pumptrain charging pumpsuction.suction.1A RHR HX 1A RHR HX TO CHG PUMP SUCTTO CHG PUMP SUCT[][]Q1E11MOV8706AQ1E11MOV8706AStep 7 continued on next page.Step 7 continued on next page.Page 10 of 19Page 10 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 227.257.25IFIF 1B RHR PUMP started, 1B RHR PUMP started, 7.257.25IFIF 1B RHR PUMP 1B RHR PUMP NOTNOT started, started, THENTHEN align charging pump align charging pumpTHENTHEN perform the following. perform the following.suction header isolationsuction header isolationvalves based on 1B chargingvalves based on 1B charging7.25.17.25.1Verify the B train CHGVerify the B train CHGpump status.pump status.PUMP stopped.PUMP stopped.7.25.27.25.2Proceed to step 7.30.Proceed to step 7.30.1B Charging1B ChargingAligned AsAligned AsAligned AsAligned As Pump Pump A Train A Train B Train B Train Not Not Status Status pump pump pump pump Available Available CHG PUMP CHG PUMP SUCTION SUCTION HDR ISO HDR ISO Q1E21MOV Q1E21MOV [] 8130A [] 8130A [] 8130A [] 8130A [] 8130A [] 8130A open open closed closed closed closed [] 8130B [] 8130B [] 8130B [] 8130B [] 8130B [] 8130B open open closed closed closed closed [] 8131A [] 8131A [] 8131A [] 8131A [] 8131A [] 8131A closed closed open open closed closed [] 8131B [] 8131B [] 8131B [] 8131B [] 8131B [] 8131B closed closed open open closed closed 7.267.26Open RHR supply to B trainOpen RHR supply to B train7.267.26Perform the following.Perform the following.charging pump suction.charging pump suction.7.26.17.26.1Stop the running B trainStop the running B train1B RHR HX 1B RHR HX CHG PUMP.CHG PUMP.TO CHG PUMP SUCTTO CHG PUMP SUCT[][]Q1E11MOV8706BQ1E11MOV8706B7.26.27.26.2Proceed to step 7.30.Proceed to step 7.30.7.277.27Verify B train CHG PUMP - Verify B train CHG PUMP - started.started.7.287.28Verify VCT level - GREATERVerify VCT level - GREATERTHAN 5%.THAN 5%.Step 7 continued on next page.Step 7 continued on next page.Page 11 of 19Page 11 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 227.297.29Close B train RWST toClose B train RWST to7.297.29Perform the following.Perform the following.charging pump header valve.charging pump header valve.7.29.17.29.1Stop the running B trainStop the running B trainRWST RWST CHG PUMP.CHG PUMP.TO CHG PUMPTO CHG PUMP[][]Q1E21LCV115DQ1E21LCV115D7.29.27.29.2Close RHR supply to BClose RHR supply to Btrain charging pumptrain charging pumpsuction.suction.1B RHR HX 1B RHR HX TO CHG PUMP SUCTTO CHG PUMP SUCT[][]Q1E11MOV8706BQ1E11MOV8706B7.29.37.29.3Proceed to step 7.30.Proceed to step 7.30.****************************************************************************************************************************************************************************CAUTIONCAUTION::Injecting through 'A' train and 'B' train flowpaths simultaneouslyInjecting through 'A' train and 'B' train flowpaths simultaneouslywith only one charging pump running could result in pump runoutwith only one charging pump running could result in pump runoutconditions. Therefore, in Step 7.30 RNO the HHSI valves should beconditions. Therefore, in Step 7.30 RNO the HHSI valves should beclosed without delay after MOV8885 is opened.closed without delay after MOV8885 is opened.****************************************************************************************************************************************************************************7.307.30Check one CHG PUMP in eachCheck one CHG PUMP in each7.307.30IFIF an A train CHG PUMP an A train CHG PUMPtrain - STARTED.train - STARTED.started,started,THENTHEN proceed to step 7.32 proceed to step 7.32 [][]A train (1A or 1B) amps > 0A train (1A or 1B) amps > 0IF NOTIF NOT, establish B train, establish B train[][]B train (1C or 1B) amps > 0B train (1C or 1B) amps > 0injection per the following.injection per the following.7.30.17.30.1Open charging pumpOpen charging pumprecirculation to RCS coldrecirculation to RCS coldlegs valve.legs valve.CHG PUMP RECIRC CHG PUMP RECIRC TO RCS COLD LEGSTO RCS COLD LEGS[][]Q1E21MOV8885Q1E21MOV88857.30.27.30.2Close HHSI isolationClose HHSI isolationvalves.valves.HHSI TOHHSI TORCS CL ISORCS CL ISO[][]Q1E21MOV8803AQ1E21MOV8803A[][]Q1E21MOV8803BQ1E21MOV8803B7.30.37.30.3Proceed to step 7.32.Proceed to step 7.32.Step 7 continued on next page.Step 7 continued on next page.Page 12 of 19Page 12 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 227.317.31Open charging pumpOpen charging pumprecirculation to RCS coldrecirculation to RCS coldlegs valve.legs valve.CHG PUMP RECIRC CHG PUMP RECIRC TO RCS COLD LEGSTO RCS COLD LEGS[][]Q1E21MOV8885Q1E21MOV88857.327.32Align charging pump dischargeAlign charging pump dischargeheader isolation valves basedheader isolation valves basedon 1B charging pump status.on 1B charging pump status.1B Charging Pump1B Charging Pump Aligned As Aligned As Aligned As Aligned As Not Not Status Status A Train pumpA Train pumpB Train pumpB Train pumpAvailable Available CHG PUMP CHG PUMP DISCH HDR ISO DISCH HDR ISO Q1E21MOV Q1E21MOV [] 8132A [] 8132A [] 8132A [] 8132A [] 8132A [] 8132A open open closed closed closed closed [] 8132B [] 8132B [] 8132B [] 8132B [] 8132B [] 8132B open open closed closed closed closed [] 8133A [] 8133A [] 8133A [] 8133A [] 8133A [] 8133A closed closed open open closed closed [] 8133B [] 8133B [] 8133B [] 8133B [] 8133B [] 8133B closed closed open open closed closed 7.337.33Verify SI flow - STABLE.Verify SI flow - STABLE.7.337.33IFIF at least one train of flow at least one train of flowfrom the containment sump tofrom the containment sump toA TRNA TRNthe RCS can the RCS can NOTNOT be beHHSI FLOWHHSI FLOWestablished or maintained, established or maintained, [][]FI 943FI 943THENTHEN go to FNP-1-ECP-1.1, go to FNP-1-ECP-1.1,LOSS OF EMERGENCY COOLANTLOSS OF EMERGENCY COOLANTHHSI HHSI RECIRCULATION.RECIRCULATION.B TRN RECIRC B TRN RECIRC FLOWFLOW[][]FI 940FI 9401A(1B) 1A(1B) RHR HDR RHR HDR FLOWFLOW[][]FI 605AFI 605A [][]FI 605BFI 605BPage 13 of 19Page 13 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22****************************************************************************************************************************************************************************CAUTIONCAUTION::Any charging pump with suction aligned to an RHR pump should beAny charging pump with suction aligned to an RHR pump should bestopped prior to stopping the RHR pump.stopped prior to stopping the RHR pump.********************************************************************************************************************************************************************************************************************************************************************************************************************************************************CAUTIONCAUTION::Charging pump or spray pump damage will occur if suction is lost andCharging pump or spray pump damage will occur if suction is lost andthe pump is not secured.the pump is not secured.****************************************************************************************************************************************************************************NOTE:NOTE:Erratic pump parameters (flow, discharge pressure, amps, etc.) areErratic pump parameters (flow, discharge pressure, amps, etc.) areindications of pump cavitation.indications of pump cavitation.Step 8 is a continuous action step which applies any time ECCSStep 8 is a continuous action step which applies any time ECCSpumps are aligned to the sump.pumps are aligned to the sump. 888Verify ECCS pumps not affectedVerify ECCS pumps not affectedVerify ECCS pumps not affected88IFIF both trains are affected both trains are affectedby sump blockage.by sump blockage.by sump blockage.such that at least one train ofsuch that at least one train ofSI recirculation flow cannot beSI recirculation flow cannot be8.18.1[CA] Monitor ECCS pump suction[CA] Monitor ECCS pump suctionmaintained, maintained, conditions - NO INDICATION OFconditions - NO INDICATION OFTHENTHEN go to FNP-1-ECP-1.3, LOSS go to FNP-1-ECP-1.3, LOSSCAVITATION.CAVITATION.OF EMERGENCY COOLANTOF EMERGENCY COOLANTRECIRCULATION CAUSED BY SUMPRECIRCULATION CAUSED BY SUMPCHG PUMPCHG PUMPBLOCKAGE. BLOCKAGE. [][]1A1A [][]1B1B [][]1C1C RHR PUMPRHR PUMP [][]1A1A [][]1B1B CS PUMPCS PUMP [][]1A1A[][]1B1BPage 14 of 19Page 14 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22NOTE:NOTE:Containment spray pumps that have been secured due to RWST level lessContainment spray pumps that have been secured due to RWST level lessthan 4.5 ft should not be started in the following step.than 4.5 ft should not be started in the following step. 999[CA] Check containment spray.-[CA] Check containment spray.-[CA] Check containment spray.-IN OPERATION.IN OPERATION.IN OPERATION.9.19.1Check any containment sprayCheck any containment spray9.19.1Verify all availableVerify all availablepump - STARTED.pump - STARTED.containment spray pumps -containment spray pumps -RUNNING.RUNNING.CS PUMPCS PUMP[][]1A1A[][]1B1B9.29.2Check containment spray flowCheck containment spray flow9.29.2Perform the following.Perform the following.in both trains - GREATER THANin both trains - GREATER THAN0 gpm.0 gpm.9.2.19.2.1IFIF RWST - GREATER THAN RWST - GREATER THAN4.5 ft, 4.5 ft, CS FLOWCS FLOWTHENTHEN verify containment verify containment[][]FI 958AFI 958Aspray pump suction alignedspray pump suction aligned[][]FI 958BFI 958Bfor injection.for injection.RWST TORWST TO 1A(1B) CS PUMP1A(1B) CS PUMP[][]Q1E13MOV8817A openQ1E13MOV8817A open[][]Q1E13MOV8817B openQ1E13MOV8817B open9.2.29.2.2Verify containment sprayVerify containment spraypump discharge aligned.pump discharge aligned.CS PUMP TO SPRAY HDR ISOCS PUMP TO SPRAY HDR ISO[][]Q1E13MOV8820A openQ1E13MOV8820A open[][]Q1E13MOV8820B openQ1E13MOV8820B open9.2.39.2.3IFIF unable to establish unable to establishspray flow in a train, spray flow in a train, THENTHEN secure containment secure containmentspray pump in affectedspray pump in affectedtrain.train.[][]CS RESET CS RESET TRN A(B) containment sprayTRN A(B) containment spraysignals - RESETsignals - RESET(Annunciator EE4 clear).(Annunciator EE4 clear).[][]CTMT SPRAY PUMP 1A(B) - CTMT SPRAY PUMP 1A(B) - STOPPED in affected trainSTOPPED in affected trainPage 15 of 19Page 15 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22 101010[CA] [CA] [CA] WHENWHENWHEN RWST level less than RWST level less than RWST level less than4.5 ft, 4.5 ft, 4.5 ft, THENTHENTHEN align containment spray align containment spray align containment sprayfor recirculation.for recirculation.for recirculation.10.110.1Reset PHASE B CTMT ISO.Reset PHASE B CTMT ISO.[][]MLB-3 1-1 not litMLB-3 1-1 not lit[][]MLB-3 6-1 not litMLB-3 6-1 not lit10.210.2Open containment spray pumpOpen containment spray pump10.210.2IFIF unable to open a unable to open acontainment sump suctioncontainment sump suctioncontainment sump suctioncontainment sump suctionisolation valves.isolation valves.isolation valve, isolation valve, THENTHEN perform the following: perform the following:CTMT SUMP CTMT SUMP TO 1A(1B) CS PUMPTO 1A(1B) CS PUMP10.2.110.2.1Secure containment spraySecure containment spray[][]Q1E13MOV8826AQ1E13MOV8826Apump in affected train.pump in affected train.[][]Q1E13MOV8827AQ1E13MOV8827A[][]Q1E13MOV8826BQ1E13MOV8826B[][]CS RESET CS RESET [][]Q1E13MOV8827BQ1E13MOV8827BTRN A(B) containment sprayTRN A(B) containment spraysignals - RESETsignals - RESET(Annunciator EE4 clear).(Annunciator EE4 clear). [][]CTMT SPRAY PUMP 1A(B) - CTMT SPRAY PUMP 1A(B) - STOPPED in affected trainSTOPPED in affected train10.2.210.2.2Verify closed BOTHVerify closed BOTHcontainment sump suctioncontainment sump suctionisolation valves inisolation valves inaffected train.affected train.CTMT SUMP CTMT SUMP TO 1A CS PUMPTO 1A CS PUMP[][]Q1E13MOV8826AQ1E13MOV8826A[][]Q1E13MOV8827AQ1E13MOV8827ACTMT SUMP CTMT SUMP TO 1B CS PUMPTO 1B CS PUMP[][]Q1E13MOV8826BQ1E13MOV8826B[][]Q1E13MOV8827BQ1E13MOV8827BStep 10 continued on next page.Step 10 continued on next page.Page 16 of 19Page 16 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 2210.310.3Close containment spray pumpClose containment spray pump10.310.3IFIF unable to isolate RWST unable to isolate RWSTRWST suction isolation valves.RWST suction isolation valves.suction in a train, suction in a train, THENTHEN perform the following: perform the following:RWST TORWST TO1A(1B) CS PUMP1A(1B) CS PUMP10.3.110.3.1Secure containment spraySecure containment spray[][]Q1E13MOV8817AQ1E13MOV8817Apump in affected train.pump in affected train.[][]Q1E13MOV8817BQ1E13MOV8817B[][]CS RESET CS RESET TRN A(B) containment sprayTRN A(B) containment spraysignals - RESETsignals - RESET(Annunciator EE4 clear).(Annunciator EE4 clear). [][]CTMT SPRAY PUMP 1A(B) - CTMT SPRAY PUMP 1A(B) - STOPPED in affected trainSTOPPED in affected train10.3.210.3.2Close containment sprayClose containment spraypump containment sumppump containment sumpsuction isolation valves insuction isolation valves inaffected train.affected train.CTMT SUMP CTMT SUMP TO 1A CS PUMPTO 1A CS PUMP[][]Q1E13MOV8826AQ1E13MOV8826A[][]Q1E13MOV8827AQ1E13MOV8827ACTMT SUMP CTMT SUMP TO 1B CS PUMPTO 1B CS PUMP[][]Q1E13MOV8826BQ1E13MOV8826B[][]Q1E13MOV8827BQ1E13MOV8827B10.410.4WHENWHEN containment spray aligned containment spray alignedfor recirc, for recirc, THENTHEN start containment spray start containment spraypumps pumps IFIF secured due to RWST secured due to RWSTlevel less than 4.5 ft.level less than 4.5 ft.CS PUMPCS PUMP[][]1A1A [][]1B1B10.510.5[CA] [CA] WHENWHEN containment spray containment sprayrecirculation flow has beenrecirculation flow has beenestablished for at least 8established for at least 8hours, hours, ANDAND containment containmentpressure is less than 16 psig,pressure is less than 16 psig,THENTHEN stop both CS PUMPs. stop both CS PUMPs.Step 10 continued on next page.Step 10 continued on next page.Page 17 of 19Page 17 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22****************************************************************************************************************************************************************************CAUTIONCAUTION::If Q1E11MOV8809A & B are not closed, any makeup to the RWST would beIf Q1E11MOV8809A & B are not closed, any makeup to the RWST would bepumped into the RCS by the RHR pumps rather than increasing RWSTpumped into the RCS by the RHR pumps rather than increasing RWSTlevel. This could result in containment flooding.level. This could result in containment flooding.****************************************************************************************************************************************************************************10.610.6Makeup to the RWST asMakeup to the RWST asnecessary.necessary.10.6.110.6.1Makeup to the RWST inMakeup to the RWST inaccordance withaccordance withFNP-1-SOP-2.3, CHEMICAL ANDFNP-1-SOP-2.3, CHEMICAL ANDVOLUME CONTROL SYSTEMVOLUME CONTROL SYSTEMREACTOR MAKEUP CONTROLREACTOR MAKEUP CONTROLSYSTEM.SYSTEM.OROR10.6.210.6.2Consult TSC staff toConsult TSC staff todetermine alternate methoddetermine alternate methodof makeup to the RWST.of makeup to the RWST. 111111[CA] Determine criteria to be[CA] Determine criteria to be[CA] Determine criteria to beused for TRANSFER TOused for TRANSFER TOused for TRANSFER TOSIMULTANEOUS COLD SIMULTANEOUS COLD SIMULTANEOUS COLD ANDANDAND HOT LEG HOT LEG HOT LEGRECIRCULATION requirements.RECIRCULATION requirements.RECIRCULATION requirements.11.111.1Check FNP-1-EEP-1, LOSS OFCheck FNP-1-EEP-1, LOSS OF11.111.1Consult TSC to determineConsult TSC to determineREACTOR OR SECONDARY COOLANTREACTOR OR SECONDARY COOLANTTRANSFER TO SIMULTANEOUS COLDTRANSFER TO SIMULTANEOUS COLDprocedure in effect.procedure in effect.ANDAND HOT LEG RECIRCULATION HOT LEG RECIRCULATIONrequirements.requirements. 121212Go to procedure and step inGo to procedure and step inGo to procedure and step ineffect.effect.effect.-END- -END- Page 18 of 19Page 18 of 191/22/201314:30UNIT 1 FNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22/2-09-2011Revision 22/2-09-2011STARTSTART STEPSTEP CONTINUOUS ACTIONCONTINUOUS ACTION 1 [CA] Check RWST level - GREATER THAN 4.5 ft. 1 [CA] Check RWST level - GREATER THAN 4.5 ft. 1[R] IF alignment for recirculation is NOT imminent, 1[R] IF alignment for recirculation is NOT imminent, THEN stop any pump taking suction from the RWST. THEN stop any pump taking suction from the RWST. 8 8.1 [CA] Monitor ECCS pump suction conditions - NO INDICATION OF 8 8.1 [CA] Monitor ECCS pump suction conditions - NO INDICATION OF CAVITATION. CAVITATION. 9 [CA] Check containment spray.- IN OPERATION. 9 [CA] Check containment spray.- IN OPERATION. 10 [CA] WHEN RWST level less than 4.5 ft, THEN align containment spray 10 [CA] WHEN RWST level less than 4.5 ft, THEN align containment spray for recirculation. for recirculation. 10.5 [CA] WHEN containment spray recirculation flow has 10.5 [CA] WHEN containment spray recirculation flow has been established for at least 8 hours, AND containment been established for at least 8 hours, AND containment pressure is less than 16 psig, THEN stop both CS PUMPs. pressure is less than 16 psig, THEN stop both CS PUMPs.Page 19 of 19Page 19 of 191/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22ATTACHMENT 1ATTACHMENT 1 111Close the followingClose the followingClose the followingdisconnects.disconnects.disconnects. 'B' Train Disconnects 'B' Train Disconnects Disconnect Disconnect Description Description PositionPosition Key Key Location Location TPNS No. TPNS No. Q1R18B033-BQ1R18B033-BDisconnect FV-T2 MOV 8884-B Disconnect FV-T2 MOV 8884-B ON ON Z-91 Z-91 Q1R18B034-BQ1R18B034-BDisconnect FV-J2 MOV 8132B-BDisconnect FV-J2 MOV 8132B-B ON ON Z-89 Z-89 Q1R18B035-BQ1R18B035-BDisconnect FV-S2 MOV 8808B-BDisconnect FV-S2 MOV 8808B-B ON ON Z-86 Z-86 139' hallway139' hallwayacross from across from Q1R18B036-BQ1R18B036-BDisconnect FV-B2 MOV 8889-B Disconnect FV-B2 MOV 8889-B ON ON Z-88 Z-88 chemistry chemistry sample room sample room Q1R18B041-BQ1R18B041-BDisc for MOV 8130B-B Disc for MOV 8130B-B ON ON Z-408 Z-408 Q1R18B042-BQ1R18B042-BDisc for MOV 8131B-B Disc for MOV 8131B-B ON ON Z-412 Z-412 Q1R18B043-BQ1R18B043-BDisc for MOV 8133B-B Disc for MOV 8133B-B ON ON Z-416 Z-416 Page 1 of 3Page 1 of 31/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22ATTACHMENT 1ATTACHMENT 1 222Close the followingClose the followingClose the followingdisconnects.disconnects.disconnects. 'A' Train Disconnects 'A' Train Disconnects Disconnect Disconnect Description Description PositionPosition Key Key Location Location TPNS No. TPNS No. Q1R18B030-AQ1R18B030-ADisconnect FU-J2 MOV 8132A-ADisconnect FU-J2 MOV 8132A-A ON ON Z-203 Z-203 Q1R18B029-AQ1R18B029-ADisconnect FU-R2 MOV 8886-A Disconnect FU-R2 MOV 8886-A ON ON Z-90 Z-90 Q1R18B038-AQ1R18B038-ADisc for MOV 8130A-A Disc for MOV 8130A-A ON ON Z-405 Z-405139' hallway139' hallwayacross from across from Q1R18B039-AQ1R18B039-ADisc for MOV 8131A-A Disc for MOV 8131A-A ON ON Z-410 Z-410MCC 1A MCC 1A Q1R18B040-AQ1R18B040-ADisc for MOV 8133A-A Disc for MOV 8133A-A ON ON Z-415 Z-415 Q1R18B031-AQ1R18B031-ADisconnect FU-Z3 MOV 8808C-ADisconnect FU-Z3 MOV 8808C-A ON ON Z-85 Z-85 Q1R18B032-AQ1R18B032-ADisconnect FU-Z2 MOV 8808A-ADisconnect FU-Z2 MOV 8808A-A ON ON Z-84 Z-84 333Verify recirculation valves MCBVerify recirculation valves MCBVerify recirculation valves MCBindication - POWER AVAILABLE.indication - POWER AVAILABLE.indication - POWER AVAILABLE.CHG PUMP CHG PUMP SUCTION HDR ISOSUCTION HDR ISO[][]Q1E21MOV8130AQ1E21MOV8130A[][]Q1E21MOV8130BQ1E21MOV8130B[][]Q1E21MOV8131AQ1E21MOV8131A[][]Q1E21MOV8131BQ1E21MOV8131BCHG PUMP CHG PUMP DISCH HDR ISODISCH HDR ISO[][]Q1E21MOV8132AQ1E21MOV8132A[][]Q1E21MOV8132BQ1E21MOV8132B[][]Q1E21MOV8133AQ1E21MOV8133A[][]Q1E21MOV8133BQ1E21MOV8133B1A(1B,1C) ACCUM 1A(1B,1C) ACCUM DISCH ISODISCH ISO[][]Q1E21MOV8808AQ1E21MOV8808A[][]Q1E21MOV8808BQ1E21MOV8808B[][]Q1E21MOV8808CQ1E21MOV8808CStep 3 continued on next page.Step 3 continued on next page.Page 2 of 3Page 2 of 31/22/201314:30UNIT 1 StepStepStepAction/Expected ResponseAction/Expected ResponseAction/Expected ResponseResponse NOT ObtainedResponse NOT ObtainedResponse NOT ObtainedFNP-1-ESP-1.3FNP-1-ESP-1.3TRANSFER TO COLD LEG RECIRCULATIONTRANSFER TO COLD LEG RECIRCULATIONRevision 22Revision 22ATTACHMENT 1ATTACHMENT 1CHG PUMP RECIRC CHG PUMP RECIRC TO RCS HOT LEGSTO RCS HOT LEGS[][]Q1E21MOV8884Q1E21MOV8884[][]Q1E21MOV8886Q1E21MOV8886RHR TO RCS RHR TO RCS HOT LEGS ISOHOT LEGS ISO[][]Q1E11MOV8889Q1E11MOV8889 444Notify control room ofNotify control room ofNotify control room ofrecirculation valve disconnectrecirculation valve disconnectrecirculation valve disconnectstatus.status.status.-END- -END- Page 3 of 3Page 3 of 31/22/201314:30UNIT 1 FNP ILT-38 JPM Page 1 of 6 jpm c. CRO-343G TITLE: Return Service Water To Normal As Required In Response To A Spurious Safety Injection ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: X SIMULATOR CONTROL ROOM PLANT PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: IC-213 (Base -167) ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS: 1. Examinee will obtain all references from the simulator. 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise. 3. Provide student with HANDOUT. 4. Allow student time to review control board. 5. Instructor will be provided to address alarms not related to evaluated task. TASK STANDARD: Upon successful completion of this JPM, the examinee will: 1. Return Service Water To Normal As Required In Response To A Spurious Safety Injection Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)

Developer S Jackson Date: 4/7/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP ILT-38 JPM Page 2 of 6

EVENT DESCRIPTION ACTION DETAILS Reset into IC-213 Acknowledge computer alarms Run / Freeze Simulator Raise Charging flow in Manual to prevent DE1 from coming into alarm Acknowledge Alarms Turn Horns ON Run / Freeze Simulator FNP ILT-38 JPM Page 3 of 6 CONDITIONS When I tell you to begin, you are to RETURN SERVICE WATER TO NORMAL AS REQUIRED IN RESPONSE TO A SPURIOUS SAFETY INJECTION. The conditions under which this task is to be performed are:

a. The Unit has experienced a spurious safety injection. b. ESP-1.1 is in progress and has been completed through Step 29.6.6. c. You are directed to perform Step 30 of ESP-1.1. d. The emergency buses are energized from offsite power. e. A pre-job brief is not required. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME *1. 30.1 Open SW to RCP motor air cooler valve.

SW TO RCP MTR AIR CLRS [] Q1P16MOV3135 HS for MOV-3135 taken to open. Observes red light lit, green light out. S / U *2. 30.2 Open SW from RCP motor air cooler valves. SW FROM RCP MTR AIR CLRS [] Q1P16MOV3131 [] Q1P16MOV3134 HS for MOV-3131 & 3134 taken to open. Observes red lights lit, green lights out. S / U *3. 30.3 Restore SW to blowdown and BTRS chillers. SW TO BLDN HX & BTRS CHLRS [] Q1P16MOV3149 HS for MOV-3149 & 3150 taken to open. Observes red lights lit, green lights out. S / U SW FROM BLDN HX & BTRS CHLRS [] Q1P16MOV3150 FNP ILT-38 JPM Page 4 of 6 *4. 30.4.1 Open A train isolation valves. SW TO TURB BLDG ISO A TRN [] Q1P16V515 [] Q1P16V516 HS for V515 and V516 taken to open. Observes red lights lit, green lights out. S / U *5. 30.4.2 Open B train isolation valves. SW TO TURB BLDG ISO B TRN [] Q1P16V514 [] Q1P16V517 HS for V514 and V517 taken to open. Observes red lights lit, green lights out. S / U 6. 30.5 Verify only two SW PUMPs in each train - STARTED.

[] A train (1A, 1B, 1C)  [] B train (1D, 1E, 1C) Observes red light lit, green light out for 1A, 1B, 1D, 1E SW pumps.

1C (A train) SW pump will have green light lit, red light out. Pressure indicated on PI-3001A & B, SW TO CCW HX HDR PRESS. S / U STOP TIME Terminate when service water pumps are aligned as required. CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number. GENERAL

REFERENCES:

1. FNP-1-ESP-1.1, Version 25.0 2. K/A: 062AA1.02 - 3.2 / 3.3 076A4.02 - 2.6 / 2.6 GENERAL TOOLS AND EQUIPMENT:

1. FNP-1-ESP-1.1, Version 25.0 FNP ILT-38 JPM Page 5 of 6 Critical ELEMENT justification: 1 - 5 Critical - Task completion. Required to restore cooling water flow. 6 Not critical. No action required.

COMMENTS: FNP ILT-38 JPM HANDOUT Page 1 of 1 jpm c CONDITIONS When I tell you to begin, you are to RETURN SERVICE WATER TO NORMAL AS REQUIRED IN RESPONSE TO A SPURIOUS SAFETY INJECTION. The conditions under which this task is to be performed are:

a. The Unit has experienced a spurious safety injection. b. ESP-1.1 is in progress and has been completed through Step 29.6.6. c. You are directed to perform Step 30 of ESP-1.1. d. The emergency buses are energized from offsite power. e. A pre-job brief is not required.

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UNIT 11/22/201314:31

UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31

UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 UNIT 11/22/201314:31 FNP ILT-38 JPM Page 1 of 7 jpm d CRO-043 TITLE: Start 1A RCP ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: X SIMULATOR CONTROL ROOM PLANT PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: IC-214 (Base - 126) ALTERNATE PATH X TIME CRITICAL PRA JPM DIRECTIONS: 1. Examinee will obtain all references from the simulator. 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise. 3. Provide student with HANDOUT. 4. Allow student time to review control board. 5. Instructor will be provided to address alarms not related to evaluated task. TASK STANDARD: Upon successful completion of this JPM, the examinee will: 1. Start 1A RCP. 2. Stop 1A RCP due to high bearing temperature. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) Developer S Jackson Date: 4/7/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 EXAMINER: FNP ILT-38 JPM Page 2 of 7 EVENT DESCRIPTION ACTION DETAILS Reset into IC-214 Acknowledge computer alarms Start Scalar Timer per SOP 39.0 Section 4.7.1 Run / Freeze Simulator Acknowledge Alarms Turn Horns ON Booth operator must take control of charging and raise Pzr level due to a falling level when the simulator is placed in run. FNP ILT-38 JPM Page 3 of 7 CONDITIONS When I tell you to begin, you are to START 1A RCP. The conditions under which this task is to be performed are: a. The Plant is in Mode 5 with RCS temperature at 183°F. b. A bubble is established in the Pressurizer. c. 1B RCP is running. d. RCS pressure is 345 psig. e. UOP-1.1, Startup of Unit from Cold Shutdown to Hot Standby, Step 5.14.22 directs 1A RCP startup IAW SOP-1.1, Reactor Coolant System. f. SOP-1.1 has been completed through step 11 of Section 4.1. g. You have been directed by the Shift Supervisor to continue the startup of the 1A RCP per SOP-1.1, starting at step 12 of Section 4.1. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME Section 4.1 *1. 12 Start the 1A RCP Oil Lift Pump. Adequate oil pressure is indicated by the white light coming ON. HS for 1A RCP oil lift pump taken to start. Observes red light lit, green light out. White light comes on a few seconds later. S / U 2. 13 Verify that the 1A RCP SEAL LEAKOFF valve Q1E21HV8141A is OPEN. ................ Observes red light lit, green light out. S / U 3. 14 Verify that 1A RCP No. 1 Seal Leakoff Flow rate is within the limits of Figure 1. Determines Seal leakoff flow rate within limits of Figure 1. S / U 4. 15. Verify that the SEAL WTR INJ FLTR HI P annunciator DC4 is clear. Observes DC4 is NOT lit. S / U Note: Applicant may go to DD1 which directs raising seal injection flow using HIK-186. *5. 16 Verify that the RCP SEAL INJ FLOW LO annunciator DD1 is clear............................. Adjusts HIK-186, SEAL WTR INJECTION potentiometer clockwise to raise flow > alarm setpoint & observes DD1 is clear. S / U FNP ILT-38 JPM Page 4 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 6. 17 Verify that all RCP No. 1 Seal P's are greater than 210 psid. Observes PI-156A, 155A, 154A - 1A, 1B, 1C RCP #1 SEAL PRESS are all > 210 psid. S / U 7. 18 Verify that the RCP #1 SEAL LO P annunciator DC3 is clear. Observes DC3 is clear. S / U 8. 19 Verify that the Oil Lift Pump for RCP 1A has run for at least 2 minutes, and is producing adequate pressure (white light ON). Observes white light is lit and 2 minutes have elapsed. S / U *9. 20. Start 1A RCP. Verify that all loop 1A flow instruments show an increasing flow rate. .............................................................................................................................. Places 1A RCP Pump hand switch to start & observes pump breaker indicator red light lit, FI-414, 415, and 416 show increasing flow rate. S / U 10. 21 Verify that RCP 1A amperage decreases to a normal operating range of 900 amps cold and 700 amps hot. ............................................................................... 1A RCP AMPMETER checked & observes Amp meter indicates ~850 amps. S / U 11. 22 Verify that the 1A RCS LOOP FLOW LO annunciator EF1 is clear. ............................ Observes EF1 is clear. S / U 12. 23 After at least 1 minute of 1A RCP operation, stop the Oil Lift Pump. After at least 1 minute of RCP operation then the 1A RCP Oil Lift Pump hand switch taken to stop and observes pump breaker indicator green light lit, red light out. S / U 13. 24 Observe RCP operating parameters very closely during the initial several minutes after starting. Special attention should be given to indications relating to seal performance. RCS flow, amps, seal injection flow and bearing temperatures checked & observes all parameter normal except RCP bearing temperatures. S / U Note: HG1 will alarm and applicant refers to the ARP. This begins the ALTERNATE PATH. FNP ILT-38 JPM Page 5 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 14. HG1 - 1 Continuously monitor 1A RCP bearing temperatures. Observes IPC to monitor RCP bearing temperatures. S / U Note: Element 15 b) is critical. Applicant may stop 1A RCP before 195°F based on temperature rising.

15. HG1-2 IF any 1A RCP motor bearing temperature exceeds 195°F, THEN perform the following actions: a) Trip the reactor, AND go to FNP-1-EEP- 0.0, REACTOR TRIP OR SAFETY INJECTION.

b) Stop 1A RCP.

c) Perform the actions required by FNP AOP-4.0, LOSS OF REACTOR COOLANT FLOW. .

This step is N/A

HS for 1A RCP taken to stop. Observes green light lit and red light out. CUE: Another operator will continue with the procedure. The JPM is complete.

S / U

STOP TIME Terminate when 1A RCP is secured. CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) before the element number.

FNP ILT-38 JPM Page 6 of 7 GENERAL REFERENCES 1. FNP-1-SOP-1.1, ver 49.1 2. FNP-1-UOP-1.1, ver 103 3. FNP-1-ARP-1.4, ver 55.0 4. FNP-1-ARP-1.8, ver 36.0 5. K/As: 003A1.02 - 2.9 / 2.9 003A2.03 - 2.7 / 3.1 GENERAL TOOLS AND EQUIPMENT 1. Provide: Marked up SOP-1.1 Critical ELEMENT justification: 1 Critical - Required to prevent RCP damage. 2-4 Not critical - No actions required. 5 Critical - Required for proper seal cooling 6-8 Not critical - No actions required. 9 Critical - Task completion 10-11 Not critical - No actions required. 12 Not critical - Will not prevent RCP from running 13, 14 Not critical - No actions required. 15 Critical - Required to prevent RCP damage COMMENTS FNP ILT-38 JPM HANDOUT Page 1 of 1 CONDITIONS When I tell you to begin, you are to START 1A RCP. The conditions under which this task is to be performed are: a. The Plant is in Mode 5 with RCS temperature at 183°F. b. A bubble is established in the Pressurizer. c. 1B RCP is running. d. RCS pressure is 345 psig. e. UOP-1.1, Startup of Unit from Cold Shutdown to Hot Standby, Step 5.14.22 directs 1A RCP startup IAW SOP-1.1, Reactor Coolant System. f. SOP-1.1 has been completed through step 11 of Section 4.1. g. You have been directed by the Shift Supervisor to continue the startup of the 1A RCP per SOP-1.1, starting at step 12 of Section 4.1. .

UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 1 of 81SAFETYSTARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY RELATEDPROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORYSECTIONSContinuous: ALL

Reference:

NONE Information: NONE Approved: David L. Reed Effective Date: February 20, 2015 Operations UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 2 of 81Procedure Version Description Version Number Version Description 97.0 CR 511531 - Added IC 2.12, modified 2.11 to check both MCCs aligned to normal source per SOP-36.3, pg15 CR 656952 - Deleted requested steps, modified 5.3.3.1, 2 (now 5.3.2.1, 2) to designate CHM sampling procedure which contains the analysis requirements Converted step 5.2.20 to a caution (5.2.16.3), deleted duplicate step 5.3.1 Added records section 97.1Reinstated broken Cross Reference in Appendix 5, step 3.2. CR 715274 98.0CR# 721257 pg 41 added NOTE prior to 5.14, added substep 5.14.24 pg 42 added NOTE prior to 5.17, added substep 5.17.11 pg 43 added step 5.17.1.2 and substeps99.0Added step 5.4.2, found in Unit 2 procedure, applicable here also. 100.0Deleted # from steps 2.4.9, 2.4.17, 2.4.18 & 2.8 as NOT Applicable. Added reference to UOP-2.4 in step 5.4.3. 101.0Implemented changes per CR 723006. Implemented changes per LDCR 2012011. 101.1Implemented changes per CR 739472. 102.0Implemented changes per CR 482410 and CR 698730 Replaced reference to EMP-1906.01 with NMP-MA-018.103.0CR 826059 - Modified the following steps: pg 16 - P&L 3.1 - changed 225 deg to 212 deg pg 24 - TS ref 4.8 - changed 225 deg to 212 deg pg 41 - Caution 5.14.23 - changed 225 deg to 212 deg pg 42 - Note 5.14.24, 5.14.25 - changed 225 deg to 212 deg pg 42 - Step 5.14.24 - Changed from conditional to STOP, added prior to 210 deg pg 43 - Note 5.17 - changed 225 deg to 212 deg pg 43 - Step 5.17 - changed 220 deg to 210 deg pg 44 - Step 5.17.2 - changed 225 deg to 212 deg CR 845049 - Ver 103.0 Del Step 5.20 per CR UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 3 of 81Table of ContentsPage1.0Purpose .........................................................................................................................................42.0Initial Conditions ............................................................................................................................53.0Precautions and Limitations ........................................................................................................164.0Technical Specifications ..............................................................................................................245.0Instructions ..................................................................................................................................256.0RECORDS ..................................................................................................................................62Figure 1 - Residual Heat Removal And Reactor Coolant Pump Limitations During Heatup And Cooldown ....................................................................................................63Figure 2 - No. 1 Seal Normal Operating Range ..........................................................................64Appendix 1 - Steam Generator Draining And Refilling For Chemical Contaminant Removal ..........................................................................................................................65Appendix 2 - Aligning Nitrogen Supply For Steam Generator Draining And Filling For Chemical Contaminant Removal (DELETED) .................................................................68Appendix 3 - Defeating The Auxiliary Feedwater Pumps' Auto-Starts And SGBD Isolation ...........................................................................................................................69Appendix 4 - Reinstating The Auxiliary Feedwater Pump Auto-Start And SGBD Isolation Functions .........................................................................................................................72Appendix 5 - Loss Of RCS Flow With Solid Plant Conditions .....................................................75 UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 4 of 811.0 Purpose This procedure provides the Initial Conditions, Precautions, Technical Specification Requirements and Instructions for the startup of unit from a Cold Shutdown condition to a Hot Standby condition. 1.1Each Step should be initialed as it is performed, and the date and time recorded where space is provided. The step may be initialed by the individual performing the step or by an individual who knows the specified step is in fact complete. For example: If individual based on knowledge and review is aware the condensate and feedwater system has been placed in operation as required by a procedural step, then the individual may initial for performance of this action even though he/she did not physically place the system in operation. ______ (Initials ______ / ______ (Date/Time) 1.2If this procedure is required to be used beginning at plant conditions other than Cold Shutdown, then the Shift Supervisor will review all Initial Conditions and all Instructions up to the existing plant conditions. Initial conditions and Instructions that are not applicable due to plant conditions will be marked N/A and initialed by the Shift Supervisor; all other items will require normal sign-off required by step 1.1. 1.3The Initial Conditions that are denoted with an asterisk (*) should be completed prior to commencing RCS heatup to facilitate reactor startup to minimum load; however these items, if required, may be completed during RCS heatup or at the hot standby condition.1.4Per NMP-OS-007-001, CONDUCT OF OPERATIONS STANDARDS AND EXPECTATIONS, Unit Operating Procedures have many tasks which may be performed concurrently. The Shift Supervisor may allow procedural steps to be performed out of sequence if it does not result in omission of required work, violate the intent of the procedure, or create an unsafe plant condition. 1.5If a steam space has not been formed in the pressurizer, then the Initial Conditions denoted with a pound symbol (#) must be completed prior to drawing a steam space in the pressurizer, other Initial Conditions must be completed prior to entry to Mode 4 unless otherwise noted. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 5 of 812.0 Initial Conditions 2.1The version of this procedure has been verified to be the current version. (OR 1-98-498) ______2.2The version of this procedure has been verified to be the correct unit for the task. (OR 1-98-498) ______ 2.3Unless otherwise specified, plant systems are aligned for automatic control. ______ 2.3.1If required by plant conditions, then a system may be placed in manual control.2.4The RCS and associated systems are in the following condition: 2.4.1#The RCS has been filled and vented per one of the following procedures: FNP-1-SOP-1.3, Reactor Coolant System Filling and Venting-Vacuum Method ______ ______ / ______ FNP-1-SOP-1.10, Reactor Coolant System Fill and Vent Following Partial Drain ______ ______ / ______ FNP-1-SOP-1.11, Reactor Coolant System Filling and Venting-Dynamic Method, ______ ______ / ______ 2.4.2The RCS water chemistry is within the limits specified in FNP-0-CCP-202, Water Chemistry Specifications. ______ ______ / ______ CHEM2.4.3*The steam generators levels are being maintained in the wide range or in wet lay-up. ______ 2.4.4Steam generator water chemistry is within the limits specified in FNP-0-CCP-202, Water Chemistry Specifications, for RCS temperature greater than 200F. ______ ______ / ______ CHEM UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 6 of 812.4.5The RHR system is aligned for operation per FNP-1-SOP-7.0, Residual Heat Removal System, with the RHR pumps running as required to maintain RCS temperature 100-180°F. 2.4.6#The CVCS valves are aligned for normal operation per checklist FNP-1-SOP-2.1A, Chemical and Volume Control System Plant Startup and Operation, with exceptions noted.2.4.7The RCS is being maintained between 50-375 psig as follows: LP LTDN PRESS PK 145 controlling pressure ______ One charging pump in service ______ Two charging pump breakers are racked out and tagged ______ Low pressure letdown in service ______ All three (3) letdown orifice isolation valves open ______ 2.4.8#VCT pressure is being maintained at a minimum of 18 psig as follows: 2.4.8.1 VCT has a nitrogen or hydrogen atmosphere established. 2.4.8.2 If a nitrogen atmosphere exists in the VCT, then the nitrogen regulator to the VCT N1E21V322 (1-CVC-PCV-8155) is adjusted to greater than or equal to 18 psig. 2.4.8.3 If a hydrogen atmosphere exists in the VCT, then the hydrogen regulator to the VCT N1E21V323 (1-CVC-PCV-8156) is adjusted to greater than or equal to 18 psig. 2.4.9FNP STP-35.1C, ENABLING ROD CONTROL SYSTEM SURVEILLANCE CHECKLIST, has been completed prior to enabling rod control. (Keff must be less than 0.99) ______ ______ / ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 7 of 812.4.10#Control rod positions are maintained within the following guidance: ______ ______ / ______ All Control bank rods are fully inserted. The shutdown bank can be fully withdrawn or inserted when the RCS is borated to the cold shutdown condition. The shutdown banks must be at the fully withdrawn position whenever reactivity is being changed by boron dilution, xenon concentration changes, RCS temperature changes or control bank rod movement, Except The RCS has been borated to the cold shutdown concentration OR The RCS has been borated to the hot, xenon-free concentration and is being maintained at no-load TAVG. 2.4.11#IF a pressurizer steam space has NOT been established in accordance with an appropriate procedure, THEN following equipment conditions exist.PRESSURIZER HEATERS DE-ENERGIZED: 1A PRZR HTR GROUP BACKUP OFF 1B PRZR HTR GROUP BACKUP OFF 1C PRZR HTR GROUP VARIABLE OFF 1D PRZR HTR GROUP BACKUP OFF 1E PRZR HTR GROUP BACKUP OFF PRESSURIZER SPRAY VALVES IN MANUAL: 1A LOOP SPR VLV PK 444C CLOSED.1B LOOP SPR VLV PK 444D CLOSED 2.4.12#The reactor makeup control is in automatic and set for blended flow equal to RCS boron concentration per FNP-1-SOP-2.3, Chemical And Volume Control System Reactor Makeup Control System. ______ 2.4.13#The pressurizer power operated relief valves are aligned as follows: PRZR PORV Q1B31PCV444B in AUTO indicates CLOSED. ______ PRZR PORV Q1B31PCV445A in AUTO indicates CLOSED. ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 8 of 812.4.14#The following conditions exist for the pressurizer relief tank. 2.4.14.1 Pressurizer relief tank is filled to the operating level. ______ 2.4.14.2 Pressurizer relief tank aligned for normal operation per one of the following: FNP-1-SOP-1.2, Reactor Coolant Pressure Relief System ______ OR FNP-1-SOP-1.3, Reactor Coolant System Filling And Venting ______ OR FNP-1-SOP-1.11, Reactor Coolant System Filling And Venting - Dynamic Method ______ 2.4.14.3 Verify closed the PRT manual vent N1B13V004 (1-RC-V-8048). ______ 2.4.14.4 Verify the blind flange is installed on PRT manual vent N1B13V004 (1-RC-V-8048). ______ 2.4.15An RHT is in service per FNP-1-SOP-2.4, Chemical and Volume Control System Boron Recycle System, with the specified volume available for each listed evolution. 2.4.15.1 #An RHT has a capacity of at least 10,000 gallons to receive discharge from the RCS during formation of a pressurizer steam space. ______ ______ / ______ 2.4.15.2 An RHT has a capacity of at least 50,000 gallons to receive discharge from the RCS during heat up. ______ ______ / ______ 2.4.16#Manway covers are installed on all RHTs to be used during plant startup. _____ 2.4.17Main Steam Isolation Valves and the bypass valves CLOSED status lights are illuminated: ______ ______ / ______ N1H11ZI2111E1A1B1CMS ISO 3369A CLOSED 3369B CLOSED 3369C CLOSED MS ISO BYP 3368A CLOSED 3368B CLOSED 3368C CLOSED MS ISO BYP 3976A CLOSED 3976B CLOSED 3976C CLOSED MS ISO 3970A CLOSED 3970B CLOSED 3970C CLOSED UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 9 of 812.4.18The main steam isolation bypass warm-up valves are closed: ______ ______ / ______ 1A MS BYP WARMUP VLV, N1N11V019A 1B MS BYP WARMUP VLV, N1N11V019B 1C MS BYP WARMUP VLV, N1N11V019C 2.4.19#RX VESSEL LKOF ISO Q1B13HV8032 is open. ______ NOTES The following step may be performed any time prior to starting the first RCP. The intent of sampling in the following Step is to ensure the boron concentration is sufficient to prevent a dilution accident when starting the first RCP. Instrument lines should be adequately flushed prior to obtaining sample. (SOER 94-2) 2.4.20IF no RCPs are in operation, THEN Chemistry in coordination with I&C has performed the following: 2.4.20.1 Obtained an RCS sample from one flow transmitter per loop. ______ 2.4.20.2 Analyzed samples from each RCS loop. 2.4.20.3 Record each intermediate leg boron concentration.(SOER 94-2) ______ ______ / ______ "A" Loop boron: ppm "B" Loop boron: ppm "C" Loop boron: ppm 2.4.20.4 Verify each intermediate leg boron concentration is greater than or equal to the required cold shutdown boron concentration. ______ 2.4.21IF any RCS loop boron concentration is less than cold shutdown boron concentration, THEN drain the intermediate leg of that loop per FNP-1-SOP-1.5, Draining the Reactor Coolant System Via the RCDT, Appendix 3. ______ ______ / ______ 2.4.22IF the Reactor Trip Breakers are closed AND the rod control system is capable of rod withdrawal, THEN verify the current RCS boron concentration is greater than the ARO critical boron concentration (Curve 1A) [NEL-01-0093] [AIT # 2001201049] ______ ______ / ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 10 of 812.5The following systems are in operation and aligned per the respective system operating procedure and system checklist: 2.5.1#The electrical distribution system is energized and aligned for normal operation per FNP-1-SOP-36.0, Plant Electrical Distribution Line-up, with exceptions noted.2.5.2*The river water building HVAC system is in operation per FNP-0-SOP-52.0, River Water Building Heating and Ventilation, with exceptions noted.2.5.3The river water system is in operation and aligned per FNP-0-SOP-25.0, River Water System, with exceptions noted.2.5.4The river water system auxiliaries are aligned and in operation per FNP-0-SOP-25.2, River Water Auxiliary Systems, with exceptions noted.2.5.5The service water building HVAC system is in operation per FNP-0-SOP-53.0, Service Water Building Heating and Ventilation, with exceptions noted.2.5.6#The service water system is in operation and aligned per FNP-1-SOP-24.0, Service Water System, with exceptions noted.2.5.7#The service water system auxiliaries are aligned and in operation per FNP0-SOP-24.2, Service Water Auxiliary Systems, with exceptions noted.2.5.8#The compressed air system is in service and aligned for normal operation per the following checklists with exceptions noted. FNP-1-SOP-31.0A, Turbine Building Compressed Air System FNP-1-SOP-31.0B, Auxiliary Building Instrument Air System 2.5.9The auxiliary building HVAC system is in operation and aligned per FNP-1-SOP-58.0, Auxiliary Building HVAC System, with exceptions noted.2.5.10The control room HVAC system is in operation and aligned per FNP-0-SOP-56.0, Control Room HVAC System, with exceptions noted.2.5.11*The turbine building HVAC system is in operation and aligned per FNP-1-SOP-57.0, Turbine Building HVAC System, with exceptions noted.2.5.12#The reactor makeup water system is in service and aligned for normal operation per FNP-1-SOP-4.0, Reactor Makeup Water System, with exceptions noted. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 11 of 812.5.13*The demineralized water system is in service per FNP-1-SOP-5.0, Demineralized Makeup Water System, with exceptions noted.2.5.14*Prior to reaching mode 3 with RCS pressure greater than 1000 psig and the accumulator discharge valves closed, the accumulators are filled and pressurized per FNP-1-SOP-8.0, Safety Injection System - Accumulators.2.5.15The high head injection system is aligned for normal operation per FNP-1-SOP-8.1A, High Head Safety Injection System, with exceptions noted.2.5.16#The component cooling system is in service and aligned for operation per FNP-1-SOP-23.0, Component Cooling Water System, with exceptions noted.2.5.17*The hydrogen seal oil system is in service per FNP-1-SOP-28.3, Hydrogen Seal Oil System, with exceptions noted.2.5.18*The generator hydrogen system is in service and aligned for normal operation per FNP-1-SOP-27.0, Generator Gas and Monitoring System, with exceptions noted.2.5.19The diesel generator fuel oil system is aligned for normal operation per FNP-0-SOP-42.0, Diesel Generator Fuel Oil Storage and Transfer System, with exceptions noted.2.5.20The diesel generator building HVAC is in service per FNP-0-SOP-43.0, Diesel Generator Building HVAC, with exceptions noted.2.5.21The diesel generators are aligned for automatic start operation per FNP-0-SOP-38.0, Diesel Generators, with exceptions noted.2.5.22#The nuclear instrumentation system is aligned for operation per FNP-1-SOP-39.0, Nuclear Instrumentation System, with exceptions noted.2.5.23The reactor control and protection system is aligned for operation per FNP-1-SOP-40.0, Reactor Control and Protection System, prior to exceeding 200°F. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 12 of 812.5.24*The control rod position indication system is aligned for normal operation per FNP-1-SOP-41.0, Control Rod Drive and Position Indication System, with exceptions noted.2.5.25The radiation monitoring system is aligned for normal operation per FNP-1-SOP-45.0, Radiation Monitoring System, with exceptions noted.2.5.26#The liquid waste processing system is aligned for operation per FNP-1-SOP-50.0, Liquid Waste Processing System, with exceptions noted.2.5.27#The LWP sump pumps are aligned for operation per FNP-1-SOP-50.2, Liquid Waste Processing System Containment and Auxiliary Building Sump Operation, with exceptions noted.2.5.28The penetration room filtration system is aligned for normal operation per FNP-1-SOP-60.0, Penetration Room Filtration System, with exceptions noted.2.5.29The fire protection system is aligned for normal operation per the following procedures with exceptions noted. FNP-1-SOP-61.1, Fire Protection Water Systems FNP-0-SOP-61.1A, Fire Protection Wayer - Service Water AND Diesel Building FNP-0-SOP-61.2, High Pressure CO2 System FNP-0-SOP-61.3, Fire Protection - Low Pressure CO2 Systems FNP-1-SOP-61.4, Fire Protection - Halon System 2.5.30*The control rod drive system is aligned for normal operation per FNP-1-SOP-41.0, Control Rod Drive and Position Indication System, with exceptions noted.2.5.31*The Circulating Water canal make-Up is being controlled as follows:2.5.31.1 Control Valve, Q1P16V560, is in the OPEN position. 2.5.31.2 Canal level is being maintained by use of manual N1P16V748, CW CANAL SW SUPP MANUAL ISO. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 13 of 812.6The following systems are aligned for operation per their respective system checklists:2.6.1Prior to Mode 3 entry the Auxiliary feedwater system is aligned per the checklist FNP-1-SOP-22.0A, Auxiliary Feedwater System, with exceptions noted. _____ ______ / ______ 2.6.2Containment spray system per checklist FNP-1-SOP-9.0A, Containment Spray System, with exceptions noted. _____ ______ / ______ 2.6.3Post LOCA CTMT pressurization and vent system per checklist FNP-1-SOP-10.0A, Post LOCA Containment Pressurization and Vent Ssystem, with exceptions noted. _____ ______ / ______ 2.6.4Containment purge, and pre-access filtration system per checklist FNP-1-SOP-12.2A, Containment Purge and Pre-Access Filtration System, with exceptions noted. _____ ______ / ______ 2.6.5Steam generator blowdown system per the following checklists with exceptions noted. FNP-1-SOP-16.1A, Steam Generator Blowdown Processing System _____ ______ / ______ FNP-1-SOP-16.2A, Steam Generator Blowdown System Demineralizers _____ ______ / ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 14 of 812.6.6*Main and Reheat steam system per checklist FNP-1-SOP-17.0A, Main and Reheat System.2.6.7*Feedwater heaters extraction, vents and drains per checklist FNP-1-SOP-20.0A, Feedwater Heaters Extraction Vents & Drains, with exceptions noted.2.6.8*Condensate and feedwater per checklist FNP-1-SOP-21.0A, Condensate and Feedwater System, with exceptions noted.2.6.9Boron thermal regeneration system per checklist FNP-1-SOP-3.0A, Boron Thermal Regeneration System, with exceptions noted.2.6.10*Circulating water system per checklist FNP-1-SOP-26.0A, Circulating Water System, with exceptions noted.2.6.11*The main turbine per checklist FNP-1-SOP-28.1A, Turbine Generator Operation, with exceptions noted.2.6.12*Lube oil transfer, purification and storage per checklist FNP-1-SOP-28.2A, Main Lube Oil Transfer, Purification and Storage System, with exceptions noted.2.6.13*Gland sealing steam system per checklist FNP-1-SOP-28.4A, Gland Sealing Steam System, with exceptions noted.2.6.14*Condenser air removal system per checklist FNP-1-SOP-28.5A, Condenser Air Removal System, with exceptions noted.2.6.15Nitrogen system per checklist FNP-0-SOP-33.0A, Bulk Nitrogen Storage System, with exceptions noted.2.6.16Hydrogen-Oxygen systems per checklist with exceptions noted. FNP-0-SOP-34.0A,Hydrogen Storage Area - Shared FNP-0-SOP-34.0B, Hydrogen Distribution System Unit 1 FNP-0-SOP-34.0D, Oxygen Distribution System Shared. 2.6.17#Waste gas system per checklist FNP-1-SOP-51.0A, Waste Gas System, with exceptions noted.2.6.18Liquid waste system is aligned per the following checklists with exceptions noted: FNP-1-SOP-50.0A, Reactor Coolant Drain Collection and Discharge System ______ FNP-1-SOP-50.0C, Floor Drain Tank and Waste Monitor Tank Demineralizer ______ FNP-1-SOP-50.0D, Chemical Drain Tank ______ FNP-1-SOP-50.0E, Laundry and Hot Shower Tank ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 15 of 81NOTEAnnunciators EF4, RCP UV SINGLE INPUT ALERT and EF5, RCP BUS UF SINGLE INPUT ALERT would be in alarm if an applicable knife switch was open. The access cover can not be installed with an open knife switch. 2.7The cover for accessing the knife switches for 4160V buses 1A, 1B, 1C undervoltage/underfrequency testing are verified in place AND sealed. ______ ______ / ______ 2.8Verify all main steam pipe hanger spring cans are unblocked. ______ ______ / ______ MM 2.9Verify all outstanding FNP-0-ETP-4179s are complete. FNP-0-ETP-4179, Main Steam Pipe Hanger Blocking ______ ______ / ______ ES 2.10The N-16 Primary to Secondary Leak Detection System has been placed in service per FNP-1-SOP-69.0, N-16 Primary to Secondary Leak Detection System. ______ ______ / ______ 2.111F 600V MCC is aligned to the normal source perFNP-1-SOP-36.3, 600, 480, AND 208/120 Volt AC Electrical Distribution System. ______ ______ / ______ 2.121G 600V MCC is aligned to the normal source perFNP-1-SOP-36.3, 600, 480, AND 208/120 Volt AC Electrical Distribution System. ______ ______ / ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 16 of 813.0 Precautions and Limitations 3.1RHR pumps shall NOT be operated in cooldown operation at RCS temperatures greater than 212°F. If any RHR pump is operated in cooldown operation with RCS temperature greater than 212°F, then declare the associated train of ECCS inoperable and do not enter Mode 3 until all portions of RHR piping is less than 212°F. One train of ECCS must be operable in Mode 4. (TS 3.5.3) (CR 2010106118) 3.2Prior to starting any RCP, consideration should be given to raising applicable bus voltage to the upper limit of its acceptable band (3900 - 4200 volts). This consideration is due in part to a known issue with the RCP motor protective relaying causing inappropriate trips during motor starting. This issue is exaggerated when bus voltage is low and/or other large loads are already in service on the applicable bus and/or transformer, i.e. Circ Water Motors. (AI 2010200391) 3.3Temperatures and Pressures: 3.3.1The RHR system must be isolated from the RCS before the following: RCS temperature reaches 350°F, Or RCS pressure reaches 427 psig, Or The pressurizer temperature reaches 475°F. 3.3.2Do not isolate RHR from the RCS until all RCS cold legs are > 275°F. 3.3.3Power must be removed from B Train RCS loop isolation valves when RCS temperature greater than 350°F due to the potential for a fire induced cable failure opening both valves.(CR 2005103659) 3.3.4Do not operate the RCPs when the number 1 seal differential pressure is less than 210 psid or VCT pressure is less than 18 psig. 3.3.5Do not exceed RCP seal injection temperature of 130°F. 3.3.6Maintain RCS heatup rates within limits of the Pressure Temperature Limits Report, Figure 2-1. 3.3.7The maximum allowable heatup rate for the pressurizer is 100°F/hr. 3.3.8Whenever the pressurizer is being cooled or filled, the temperature differential between the pressurizer and the RCS must not exceed 320°F. Monitor the pressurizer liquid, surge line and loop B hot leg temperatures to ensure that a pressurizer outsurge is taking place. This will prevent thermal stratification from taking place. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 17 of 813.3.9During periods when the RCS temperature is low with a bubble in the pressurizer, increases to the pressurizer level should be done in a gradual manner. Consideration should be made to performing small batch makeups (less than 150 gallons) along with energization of additional heaters prior to increasing the pressurizer level (CR 442638) 3.3.10Prior to starting or stopping a RHR pump with the RCS under solid plant pressure control and the RHR system aligned for letdown, place LP LTDN PRESS PK 145 in MANUAL to prevent RCS pressure fluctuations. 3.3.11At least one CRDM cooling fan must be in service when the RCS temperature is greater than 350°F. 3.3.12During approach to normal operating temperature and pressure for Hot Standby conditions, plant equipment controlling RCS temperature and pressure should be monitored diligently for proper and expected responses. 3.3.13The following precautions apply to the operation of the RCPs: 3.3.13.1 With a steam space in the pressurizer 1B RCP is the preferred pump to run for optimum pressurizer spray flow and pressure control. 3.3.13.2 FNP-1-UOP-1.1, Appendix 5, is required to be performed prior to starting any RCP when all RCPs have been idle for more than 5 minutes with seal water flow established during solid plant operations. 3.3.13.3 At least one RCP should be running when the RCS temperature is greater than 160°F. 3.3.13.4 The number of operating RCPs is limited to one at RCS temperatures less than 110F. A second pump may be started for the purpose of maintaining continuous flow while taking the operating pump out of service.3.3.13.5 A RCP shall not be started with one or more of the RCS cold leg temperatures less than or equal to 275oF unless one of the following conditions exists:The pressurizer water volume is less than 24% wide range cold pressurizer level indication. (LI 462), ORThe secondary water temperature of each steam generator is less than 50oF above each of the RCS cold leg temperatures. 3.3.14RCS pressure must be maintained within limits of Figure 1 while running RCPs to assure RCP NPSH requirements. 3.3.15During steam plant warm-up, draw steam slowly and regulate feedwater additions carefully to avoid rapid cooling of the RCS. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 18 of 813.3.16Any seal injection throttle valve adjustments should be verified acceptable per SR 3.5.5.1 with the "strongest" and "weakest" charging pump supplying flow within 4 hours. Engineering Support can supply information as to the strongest and weakest pumps 3.3.16.1 If it is not feasible to run FNP-1-STP-8.0, RCP Seal Controlled Leakage Test, using either the strongest or weakest pump (i.e. pump not capable of running or breaker racked out), then the surveillance should be run with the two available charging pumps 3.3.16.2 Generate an administrative LCO for the inoperable pump to ensure FNP-1-STP-8.0, RCP Seal Controlled Leakage Test, is run when the pump is returned to service. 3.3.17After any significant change in charging flow, the reactor coolant pump seal flow should be checked and adjusted if necessary. 3.3.18Adjusting individual RCP seal flows at RCS pressures between 2215 and 2255 psig will requiring perform FNP-1-STP-8.0, RCP Seal Controlled Leakage Test, for both the strongest and weakest charging pumps within 4 hours. This will ensure that total flow is within the limits of Technical Specification 3.5.5. 3.3.19Do not exceed primary to steam generator differential pressure of 1600 psid. 3.3.20RCP SEAL WTR BYP Q1E21HV8142 must be operated as follows: 3.3.20.1 During RCS pressurization or during cooldown and depressurization, the number 1 seal bypass valve should be left closed. The number 1 seal leakoff bypass valve should only be opened under the following conditions:a. The RCP bearing temperature (seal inlet temperature) or number 1 seal leakoff temperature approaches it's alarm setpointANDb. The RCS is greater than 100 psig, but less than 1000 psig, ANDc. The number 1 seal leakoff valve is open ANDd. The number 1 seal leakoff flow rate is less than 1 gpm, ANDe. Seal injection water flow rate to each pump is greater than 6 gpm. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 19 of 813.3.20.2 During RCS pressurization, the number 1 seal water bypass valve and the number 1 seal leak-off valve should remain closed until the RCS pressure is 100 psig (minimum), at which time the bypass valve may be opened (if necessary) only after the number one seal leak-off valves have been opened. 3.3.20.3 During normal operation, the bypass valve should remain closed. 3.3.20.4 The seal bypass valve should never be opened during a loss of injection water.3.3.21In Mode 3 with less than two RCPs operating, the rod control system must be disabled for rod withdrawal. 3.3.22The RCPs are not designed for "start-stop" operations. Too frequent starting may damage the motor windings. To prevent such damage the following maximum starting duty should be observed: 3.3.22.1 Only one RCP is to be started at any one time. 3.3.22.2 After any running period allow a minimum a 30 minute idle period before attempting a restart. 3.3.22.3 After any attempted start failure, allow a minimum 30 minute idle period before attempting a restart 3.3.22.4 After three starts or attempted starts have been made within a two hour period, allow a 60 minute idle period before attempting an additional start. 3.3.23Prior to exceeding 200F in the RCS, ensure the MSIVs are Tagged Closed, if conditions on the secondary side require a main steam clearance. 3.3.24If a known primary to secondary leak exists, contact the Shift Radiochemist to implement FNP-0-CCP-645, Main Steam Abnormal Environmental Release prior to running the TDAFW pump or operating the SG atmospheric relief valves during heat up. 3.3.25The RCS loops are considered to be "not filled" per Technical Specification 3.4.8 if RCS pressure has NOT been maintained greater than 100 psig since the most recent RCS filling and venting. 3.3.26Prior to raising pressure following Mode 3 entry, review the FNP-1-SOP-1.1, Reactor Coolant System precautions concerning RCP seals. 3.3.27Prior to entry into Mode 4, ensure Maintenance has the RTD Cross-Calibration data acquisition test equipment functionally tested, hooked up and ready to proceed with data-taking before the plant enters Mode 4 so that no RCS heat up delays will be encountered at the 250°F temperature plateau point.TE 513300 UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 20 of 813.4Chemistry:3.4.1Before the RCS or pressurizer exceeds 180°F the chemistry requirements as specified in FNP-0-CCP-202, Water Chemistry Specifications, must be met. 3.4.2The mixed bed demineralizer should be removed from operation when hydrazine is added to the RCS and should not be returned to operation until the hydrazine and resulting ammonia have been reduced to less than 1 ppm total (hydrazine plus ammonia). 3.4.3The boron concentration in the pressurizer should not be less than the RCS loops by more than 50 ppm. Following a change of boron concentration in the RCS, the pressurizer spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the pressurizer heaters when there is a steam space in the pressurizer. 3.4.4The flow rate through the RCS shall be determined to be greater than 3000 gpm prior to the start of and at least once per hour during a reduction in the RCS boron concentration. This data should be recorded in the miscellaneous section of FNP-1-STP-1.0, Operations Daily and Shift Surveillance Requirements. 3.4.5At least once RCP must be in operation prior to performing any RCS dilution or boration. (SOER 94-2) 3.4.6Large volume RCS dilutions or RCS feed and bleed operations that are performed after the RCS exceeds 180°F, but prior to establishing a hydrogen atmosphere in the VCT, should be coordinated with Chemistry personnel. Such additions of water to the RCS from the RMWST could cause the RCS to exceed the dissolved oxygen limits of Technical Requirement 13.4.1. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 21 of 813.5Reactivity Control: 3.5.1The shutdown banks must be at the fully withdrawn position whenever reactivity is being changed by: Boron dilution Xenon concentration changes RCS temperature changes Control bank rod movement. 3.5.1.1 This precaution is not applicable for the following conditions: The RCS has been borated to the cold shutdown concentrationORThe RCS boron concentration is greater than the ARO critical boron concentration (Curve 1A) [NEL-01-0093] [AIT#2001201049]3.5.2In the source range reactivity must not be changed by more than one controlled method at a time. An exception to this is control rod operability testing. 3.5.3The reactor shutdown margin must be maintained as required by Technical Specifications 3.1.1. 3.5.4A minimum of one source range channel shall be in operation with the source range high flux trip operable under the following conditions: The reactor is shutdown. Fuel is in the reactor. Rod control system is enabled. 3.5.5The high flux at shutdown alarm shall be operable when the reactor is shutdown with fuel in the reactor. 3.5.6Criticality must be anticipated any time the control rods are being withdrawn or RCS boron dilution is in progress. 3.5.7If the count rate on either source range channel unexpectedly increases by a factor of two or more during a boron concentration change the operation must be stopped immediately. The operation should remain suspended until the cause of the increase has been determined, and core reactivity has been evaluated by the Shift Supervisor. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 22 of 813.5.8Before withdrawing any rod bank from the fully inserted position, the group step counters and rod position indicators for that bank must be at zero steps. 3.5.9With no RCP in operation, one reactor makeup water pump shall be tagged out to the Shift Supervisor to prevent an inadvertent dilution while on RHR. 3.5.10At least one RCP must be in operation prior to performing any RCS dilution or boration except as noted in Step 3.5.10.1 below.(SOER 94-02)3.5.10.1 IF no RCP is in operation and at least one RHR pump is on service providing 3000 gpm flow, THEN chemicals may be added to the RCS provided an evaluation of the effects of a small volume dilution to the RCS with potentially inadequate mixing has been performed and with Shift Supervisor concurrence. The evaluation should consider shutdown margin for present conditions and the affected volume of RCS. Boron samples should be obtained and analyzed to ensure adequate shutdown margin is maintained 3.5.11In Modes 5, 4, and 3 (RCS temp less than 541F):When the rod control system is capable of rod withdrawal, the RCS boron concentration must be maintained greater than or equal to the ARO critical boron concentration for the existing temperature (Curve 1A) [NEL-01-0093] [AIT # 2001201049] [AIT # 2001201049]. 3.5.12In Mode 3 (RCS temp 541F):When the rod control system is capable of rod withdrawal, the PR High Flux - Low Setpoint (25% RTP) trip is required to be available. [NEL-01-0093] [AIT # 2001201048] 3.5.13Guidance in this procedure has the potential to impact reactivity. Close coordination with the control room operators is required to ensure proper reactivity management per NMP-OS-001, Reactivity Management Program. (AI 2008203128) 3.6Atmospheric Relief Valve operation 3.6.1During plant heat-up, IF the atmospheric relief valves are set for nominal system pressure of 1035 psig (POT setting of 8.25) in AUTO, THEN as RCS temperature approaches 547°F, the atmospheric relief valve response should be closely monitored to ensure no single atmospheric is more responsive than the rest. CR 2010118624 UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 23 of 813.7Restoration from IMP-0.7 and SG level (TE 592318) When restoring SSPS to normal configuration per FNP-1-IMP-0.7, DISABLE SSPS OUTPUTS FOR MODES 5 & 6, the SS must ensure that Steam Generator Lo-Lo bistables are not lit if the AFW Pumps are available. During SSPS restoration from IMP-0.7, AFW Pumps and FCV's will respond to actuation signals if the SG Lo-Lo- level bistables meet proper coincidence. At 28% SG NR level, AFW FCV's and TDAFWP steam admission valves will open. MDAFW Pump Auto/Defeat switches are only associated with the start from a trip of the both SGFP's and do not prevent a start from a Steam Generator Lo-Lo- level signal. The SS should obtain a peer check if a decision is made to waive the requirement for bistables NOT ILLUMINATED in that portion of FNP-1-IMP-0.7 restoration, (section 7.2). IF any Steam Generator Lo-Lo- level bistable is lit AND the SS waives the requirement for it to not be lit due to the AFW pumps not being available, THEN an Admin Tracking item should be initiated to ensure unintended AFW pump auto-start does not occur when the AFW pumps become available. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 24 of 814.0 Technical Specifications 4.1Technical Specifications for entering Mode 4 check list FNP-1-STP-35.1E must be completed prior to exceeding RCS temperature of 200°F, based on the absolute late date of the most limiting surveillance. 4.2Technical Specifications for entering Mode 3, checklist FNP-1-STP-35.1D, must be completed prior to exceeding RCS temperature of 350°F, based on the absolute late date of the most limiting surveillance. 4.3The RCS temperature and pressure, and pressurizer temperature shall be determined to be within limits by performing FNP-1-STP-35.0, Reactor Coolant System Pressure and Temperature/Pressurizer Temperature Limits Verification. 4.4The flow rate through the RCS shall be determined to be greater than 3000 gpm prior to the start and at least once per hour during a reduction in RCS boron concentration by recording the required data per FNP-1-STP-1.0, Operations Daily and Shift Surveillance Requirements, miscellaneous section. 4.5Mode 5 (loops filled) RHR requirements: Two trains of RHR are OPERABLE with one train in service. An alternative to this requirement allowed by Technical Specifications is "Three filled Reactor Coolant loops and at least two Steam Generator levels greater than or equal to 75% of wide range indication may be substituted for one operable RHR loop." The RCS loops must be intact (capable of being pressurized) and filled, otherwise gases can come out of solution and accumulate in the SG U-bend region preventing natural circulation cooling capability, which is the basis for this alternative. RCS loop operability requirements per Tech. Spec. 3.4.7 require a Steam Generator wide range level of greater than or equal to 75% wide range indication.4.6When in Mode 3 reactor coolant pump seal injection flow shall be within Technical Specification 3.5.5 limits. 4.7In Mode 3, Tech Spec 3.3.3 requires 2 channels of RCS Hot Leg Temperature and RCS Cold Leg Temperature to be operable. The performance of RTD cross calibration testing makes the associated channel RCS temperature instruments inoperable. Tech Spec 3.3.4 requires Loop A RCS Hot Leg Temperature and RCS Cold Leg Temperature to be operable in Mode 3. 4.8Operation of a train of RHR aligned in cooldown operation with RCS temperatures greater than 212°F will result in inoperability of the associated train of ECCS. One train of ECCS is required while in Mode 4. Mode 3 entry will be prohibited until all portions of RHR piping is less than 212°F. One train of ECCS must be operable in Mode 4. (TS 3.5.3) (CR 2010106118) UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 25 of 815.0 Instructions 5.1IF any RCP is in operation, THEN mark step 0 N/A AND proceed to step 5.3.____________ / ______ NOTES For pressurizer spray and pressurizer pressure control 1B is the preferred pump to start first.The Precautions and Limitations for starting a RCP should be reviewed inFNP-1-SOP-1.1.CAUTIONPrior to starting a RCP, consideration should be given to raising the 230 kV bus voltage such that the emergency 4160 volt buses are approaching the 4200 volt limit to preclude spurious RCP breaker trip. (AI2010200391) 5.2Start a Reactor Coolant Pump as follows: 5.2.1 Verify RHR loop suction valves OPEN prior to starting the first RCP during solid plant operation: 1C RCS LOOP TO 1A RHR PUMP Q1E11MOV8701A ______ 1C RCS LOOP TO 1A RHR PUMP Q1E11MOV8701B ______ 1A RCS LOOP TO 1B RHR PUMP Q1E11MOV8702A ______ 1A RCS LOOP TO 1B RHR PUMP Q1E11MOV8702B ______ ______ / ______ 5.2.2IF a loss of RCS flow with solid plant condition occurs, THENrefer to FNP-1-UOP-1.1, Appendix 5, prior to starting an RCP with solid plant conditions. ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 26 of 81NOTEAn oil lift pump may need to operate for several minutes (more than 5) before enoughpressure is developed to actuate the pressure switch that will illuminate the white light. The length of run time may vary due to oil temperature, secured time and pressure switch sensitivities. (AI12011201221) 5.2.3 Start a RCP OIL LIFT PUMP for the RCP to be started. Q1B41P002A ______ Q1B41P002B ______ Q1B41P002C ______ 5.2.3.1Allow the lift pump to run at least two minutes prior to starting the RCP. ______ 5.2.3.2Verify that the associated white indicator light is energized, signifying adequate oil pressure available. (greater than than 600 psig) ______ 5.2.4 Verify VCT pressure greater than or equal to 18 psig. ______ 5.2.5 Verify the following alarms clear for the pump to be started: 5.2.5.1 RCP THRM BARR CCW FLOW HI annunciator DD2. ______ 5.2.5.2 CCW FLOW FROM RCP OIL CLRS LO annunciator DD3. ______ 5.2.5.3 Standpipe annunciators clear. DA1 1A RCP STANDPIPE LVL LO ______ DA2 1B RCP STANDPIPE LVL LO ______ DA3 1C RCP STANDPIPE LVL LO ______ 5.2.5.4 Oil reservoir HI annunciators clear: HG1 RCP 1A BRG UPPER/LOWER OIL RES HI LVL ______ HG2 RCP 1B BRG UPPER/LOWER OIL RES HI LVL ______ HG3 RCP 1C BRG UPPER/LOWER OIL RES HI LVL ______ 5.2.5.5 Oil reservoir LO annunciators clear: HH1 RCP 1A BRG UPPER/LOWER OIL RES LO LVL ______ HH2 RCP 1B BRG UPPER/LOWER OIL RES LO LVL ______ HH3 RCP 1C BRG UPPER/LOWER OIL RES LO LVL ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 27 of 815.2.6 Verify that each intermediate leg boron concentration is greater than or equal to the required cold shutdown boron concentration. Boron concentrations are recorded in step 2.4.20.3. _____ ______ / ______ 5.2.7 Verify RCP SEAL WTR BYP Q1E21HV8142 is CLOSED. ______ 5.2.8 Adjust SEAL WTR INJECTION HIK 186 as necessary to maintain seal injection flow of 6-8 gpm on the lowest indicating seal injection flow meter. ______ CAUTIONThe Tech Spec maximum lift pressure for the RHR pump suction relief valves is 450 psig, however, due to setpoint tolerances these valves could lift as low as 427 psig. 5.2.9 Adjust CHG FLOW FK 122 as required to smoothly raise RCS pressure.______5.2.10WHEN RCS pressure greater than 100 psig, THENopen RCP SEAL LEAKOFF valves: Q1E21HV8141A _____ Q1E21HV8141B _____ Q1E21HV8141C _____ ______ / ______ CAUTIONThrottling RHR TO LTDN HX HIK 142 excessively can cause loss of ability to control pressure transients with LP LTDN PRESS PK-145. 5.2.11 Adjust the following valves as necessary to maintain RCS pressure 325-375 psig. LP LTDN PRESS PK 145 ______ RHR TO LTDN HX HIK-142 ______ 5.2.12 Perform the following for the RCP to be started: 5.2.12.1Verify RCP No. 1seal P greater than 210 psid on the following indicators:5.2.12.2 1A RCP #1SEAL PRESS PI-156A _____ 5.2.12.3 1B RCP #1SEAL PRESS PI-155A _____ 5.2.12.4 1C RCP #1SEAL PRESS PI-154A _____ ______ / ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 28 of 815.2.12.5Verify RCP No. 1 seal leak rate is within the limits of Figure 2. RCP SEAL LKOF HIGH RANGE recorder N1E21FR154A _____ 1A RCP SEAL LEAKOFF LOW RANGE indication FI-156B _____ 1B RCP SEAL LEAKOFF LOW RANGE indication FI-155B _____ 1C RCP SEAL LEAKOFF LOW RANGE indication FI-154B _____ ______ / ______ 5.2.13IF necessary, THENoperate RCP SEAL WTR BYP Q1E21HV8l42 in accordance with the following guidance: ______ During RCS pressurization or during cooldown and depressurization, the number 1 seal bypass valve should be left closed. The number 1 seal bypass valve should only be opened under the following conditions: The RCP bearing temperature (seal inlet temperature) or number 1 seal leak-off temperature approaches it's alarm setpoint, AND The RCS is greater than 100 psig, but less than 1000 psig, AND The number 1 seal leak-off valve is open, AND The number 1 seal leak-off flow rate is less than 1 gpm, AND The seal injection water flow rate to each pump is greater than 6 gpm. During RCS pressurization, the number 1 seal bypass valve and the number 1 seal leak-off valve should remain closed until the RCS pressure is 100 psig (minimum), at which time the bypass valve may be opened (if necessary) only after the number 1 seal leak-off valves have been opened. During normal operation, the bypass valve should remain closed. The seal bypass valve should never be opened during a loss of injection water. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 29 of 815.2.14 Verify one of the following: Cold pressurizer level less than 24% _____ ______ / ______ Pressurizer level (LI-462) OR All steam generator shell temperatures less than 50°F above the associated RCS cold leg temperature _____ ______ / ______ SG 1A TE3188D __________ RCS Cold Leg 1A _________ SG 1B TE3188E __________ RCS Cold Leg 1B _________ SG 1C TE3188F __________ RCS Cold Leg 1C _________ 5.2.15 Verify RCP start will not exceed the maximum starting duty of the RCPs: ______ Only one RCP is to be started at any one time. After any running period allow a minimum a 30 minute idle period before attempting a restart. After any attempted start failure, allow a minimum 30 minute idle period before attempting a restart. After three starts or attempted starts have been made within a two hour period, allow a 60 minute idle period before attempting an additional start. 5.2.16 Perform the following for the pump to be started: 5.2.16.1Verify pressure is stabilized between 325-375 psig ______ 5.2.16.2Verify the oil lift pump has been started for at least 2 minutes. Q1B41P002A with white indicator light energized. ______ Q1B41P002B with white indicator light energized ______ Q1B41P002C with white indicator light energized ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 30 of 81CAUTIONStarting an RCP will affect RCS heatup rate. The heat up limits set by Tech SpecsPTLR Figure 2-1 must be adhered to.5.2.16.3Start the designated reactor coolant pump; verify that all loop flow instruments show an increasing flow rate for the RCP started. 1A RCP, Q1B41P001A ______ 1B RCP, Q1B41P001B ______ 1C RCP, Q1B41P001C ______ 5.2.16.4Verify that RCP amperage decreases to a normal operating range of 900 amps cold and 700 amps hot for the RCP started. 1A RCP, RX COOLANT AMPS _____ 1B RCP, RX COOLANT AMPS _____ 1C RCP, RX COOLANT AMPS _____ 5.2.16.5Verify that the RCS LOOP FLOW LO annunciator is clear. 1A RCS LOOP FLOW LO annunciator EF1 is clear. _____ 1B RCS LOOP FLOW LO annunciator EF2 is clear. _____ 1C RCS LOOP FLOW LO annunciator EF3 is clear. _____ 5.2.17IF RCS is solid, THENadjust CHG FLOW FK 122 to establish approximately 60 gpm letdown flow. ______ 5.2.18IF 1A or 1B RCP was started, THEN open the appropriate spray valve to re-circulate the pressurizer. 1A RCP LOOP SPR VLV PK 444C _____ ______ / ______ 1B RCP LOOP SPR VLV PK 444D _____ ______ / ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 31 of 815.2.19WHEN a minimum of one minute of RCP operation has elapsed, THEN stop the RCP OIL LIFT PUMP for the pump started: Q1B41P002A ______ Q1B41P002B ______ Q1B41P002C ______ NOTEIf additional RCP's are to be started, performance of the following step may be delayed until allRCP's are running. This is due to ALARA concerns for entering containment. 5.2.20 Verify RCP termination box strip heaters are de-energized by performing the following for the running pumps: ______ Open BKR 11, 1A RCP termination box strip heater, in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT) to de-energize the strip heater for 1A RCP. Open BKR 9, 1B RCP termination box strip heater, in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT) to de-energize the strip heater for 1B RCP. Open BKR 7, 1B RCP termination box strip heater, in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT) to de-energize the strip heater for 1C RCP. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 32 of 815.3 Perform the following to accomplish the chemistry sampling requirements: 5.3.1IF both trains of RHR are NOT in service, AND requested by CHM, THENstart the idle RHR pump per FNP-1-SOP-7.0, Residual Heat Removal System. _____ ______ / ______ 5.3.2WHEN a minimum of five minutes of operation with a RCP and both trains of RHR in-service has elapsed (IF requested by CHM at step 5.3.1), THEN notify Chemistry to perform the following:5.3.2.1Sample the reactor coolant system per FNP-1-CCP-203, Chemistry And Environmental Group Considerations During Operational Transients. ______ ______ / ______ CHEM 5.3.2.2Sample the pressurizer liquid space perFNP-1-CCP-203,Chemistry And Environmental Group Considerations During Operational Transients. ______ ______ / ______ CHEM 5.3.2.3 IF necessary, THENtake corrective action to return the coolant chemistry within specifications required by FNP-0-CCP-202, Water Chemistry Specifications. ______ ______ / ______ CHEM UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 33 of 81NOTEIf this start-up is for maintenance activities that did not require reducing RCS temperature less than 180 degrees, Section 5.4 is N/A. 5.4Prior to exceeding 180°F, perform the following: 5.4.1 Adjust RHR as required to maintain RCS temperature between175-180°F. _____ 5.4.2 Request EM restore the auto close signal for the RHR Loop Suction Valves per FNP-1-SOP-7.0, Appendix 13. _____ 5.4.3 Clear the caution tagout that was initiated per FNP-1-UOP-2.2 OR FNP-1-UOP-2.4 for the power supply breakers to RHR Loop Suction Valves. _____ 5.4.4 Verify power supply breakers to RHR loop suction valves are CLOSED. BKR FU-T5, 1C RCS LOOP TO 1A RHR PUMP Q1E11MOV8701A. _____ BKR FU-G2, 1A RCS LOOP TO 1B RHR PUMP Q1E11MOV8702A. _____ BKR FV-V2, 1C RCS LOOP TO 1A RHR PUMP Q1E11MOV8701B _____ BKR FV-V3, 1A RCS LOOP TO 1B RHR PUMP Q1E11MOV8702B. _____ _____ / _____ 5.5 Commence Mode 4 surveillance requirements of FNP-1-STP-1.0, Operations Daily and Shift Surveillance Requirements _____ 5.6IF a steam space is already established in the pressurizer, THENmark steps 5.7 through 5.11 N/A AND proceed to step 5.12. _____ 5.7 Verify RCS chemistry is within the limits specified in FNP-0-CCP-202, Water Chemistry Specifications, prior to establishing a steam space in the pressurizer.__________ / _____ 5.7.1WHEN RCS chemistry is within the specification of FNP-0-CCP-202, Water Chemistry Specifications, THEN one RHR pump may be shutdown if required. ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 34 of 81NOTERCS oxygen concentration MUST be less than 0.1 ppm prior to exceeding 250°F.5.8IF necessary to reduce to the RCS oxygen concentration below 0.1 ppm, THEN perform the following. 5.8.1 Remove the mixed bed demineralizer from service. _____ _____ / _____ NOTEIt is not necessary to hold following chemical addition. 5.8.2 Add hydrazine to the RCS as necessary per FNP-1-SOP-2.5, RCS Chemical Addition, VCT Gas Control and Demineralizer Operation. _____ _____ / _____ 5.9 Verify pressurizer spray valves CLOSED. 1A LOOP SPR VLV PK 444C. ______ 1B LOOP SPR VLV PK 444D. ______ 5.10 Energize the pressurizer heaters as follows: 5.10.1 Place the handswitch for the following heater groups to ON: 1A PRZR HTR GROUP BACKUP ______ 1B PRZR HTR GROUP BACKUP ______ 1C PRZR HTR GROUP VARIABLE ______ 1D PRZR HTR GROUP BACKUP ______ 1E PRZR HTR GROUP BACKUP ______ 5.10.2IF desired to maximize the output of the 1C PRZR HTR GROUP VARIABLE heaters, THEN place PK 444A in MANUAL with 65% demanded output. ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 35 of 81NOTEContinue with plant heat-up to 190-200°F while performing step 5.11. 5.11WHEN pressurizer temperature increases to the saturation temperature for 375 psig (approximately 442°F) as indicated by increasing RCS pressure or letdown flow, THENestablish a steam space in the pressurizer as follows: 5.11.1 Decrease charging flow to minimum. ______ 5.11.2 Adjust SEAL WTR INJECTION HIK 186 as required to maintain 6-13 gpm seal flow to each RCP. ______ 5.11.3 Operate pressurizer heaters and/or spray valves to maintain RCS pressure 325-375 psig. 1A PRZR HTR GROUP BACKUP ON-AUTO-OFF ______ 1B PRZR HTR GROUP BACKUP ON-AUTO-OFF ______ 1C PRZR HTR GROUP VARIABLE ON-AUTO-OFF ______ 1D PRZR HTR GROUP BACKUP ON-AUTO-OFF ______ 1E PRZR HTR GROUP BACKUP ON-AUTO-OFF ______ 1B LOOP SPRAY VLV PK 444D ______ 1A LOOP SPRAY VLV PK 444C ______ 5.11.4 Adjust LP LTDN PRESS PK 145 to maintain approximately 120 gpm. ______ 5.11.5WHEN VCT level increases to 81%, THENverify VCT HI LVL DIVERT VLV Q1E21LCV115A in the fully diverted position. _____ _____ / _____ 5.11.6IF desired, THEN place excess letdown in operation to expedite formation of a steam space in the pressurizer per FNP-1-SOP-2.7, Chemical and Volume Control System Excess Letdown. _____ 5.11.7WHEN pressurizer level reaches 21%, THEN perform the following: 5.11.7.1Place CHG FLOW FK-122 in AUTO. _____ _____ / _____ 5.11.7.2Verify pressurizer level is maintained at approximately 21%. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 36 of 81NOTEPerformance of certain sections of STP-158, Reactor Coolant System Pressure Isolation Valve Leak Test, will require isolating an individual train of RHR. Ensure compliance with Technical Specifications and actions required for inoperable Low Temperature Overpressure Protection System (3.4.12) and an inoperable train of RHR (3.4.7) when applicable. Three filled and vented RCS loops, capable of being pressurized and at least two Steam Generators having levels greater than or equal to 75 % wide range indication (with an available source of makeup water) may be substituted for one RHR loop. 5.12IF the purpose of this shutdown has been for refueling OR flow has been put through the hot leg injection lines, THEN perform FNP-1-STP-158, Reactor Coolant System Pressure Isolation Valve Leak Test as follows:NOTEThe pre-shift briefing will stress management's expectations of closely monitoring RCS temperature to prevent a mode change due to temperature rise, and the actions to be taken if temperature control becomes a problem. 5.12.1A pre-job briefing is held concerning performance of FNP-1-STP-158.0, Reactor Coolant System Pressure Isolation Valve Leak Test. _____ _____ / _____ 5.12.2 Station ORdesignate personnel for the purpose of operating the RHR loop suction valve power supply breakers in the event the off service train of RHR is required to be placed in service. _____ 5.12.3 Secure up to two of the three RCPs as necessary to control temperature. IF possible, THENmaintain B RCP running. _____ 5.12.4IF temperature control is still a problem after securing two RCPs, THEN notify the test coordinator to secure the test lineup AND place the train of RHR, which was being tested, in service. _____ 5.13 Review the "Work In Progress File(s)" for any activities in progress that could effect the pending Mode change. TE 651930. _____ 5.14 Prior to exceeding 200°F in the RCS the following items must be completed: 5.14.1 Verify RCS chemistry is within the limits specified in FNP-0-CCP-202, Water Chemistry Specifications. _____ _____ / _____ 5.14.2 Notify the Facilities Group to remove covers from the ECCS sump suction screens. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 37 of 815.14.3 Record on FNP-1-STP-35.1, Unit Startup Technical Specification Verification, Technical Specifications Surveillance Requirements for Mode 4 operation based on the absolute late date of the most limiting surveillance per one of the following check lists in FNP-1-STP-35.1: Checklist E, FNP-1-STP-35.1E, Mode 4 Surveillance Check List, _____ _____ / _____ OR Appendix A, Explanation Of Codes In Report _____ _____ / _____ 5.14.4The Shift Manager has granted permission for Mode 4 entry. (CR2010106404) _____ _____ / _____ NOTEIf substituting three filled Reactor Coolant loops and at least two Steam Generators having levels greater than or equal to 75% wide range indication for an inoperable RHR loop (as noted in Tech. Spec. 3.4.7), then a Steam Generator level of greater than or equal to 75% wide range must be used to take credit for those Steam Generators. 5.14.5IF in wet layup, THEN coordinate with Chemistry AND begin reducing steam generator level to establish approximately 80% wide range indication. _____ _____ / _____ 5.14.6IF required, THEN remove the nitrogen blanket from each steam generator per FNP-1-SOP-16.3, Steam Generator Filling and Draining. _____ _____ / _____ 5.14.7 Notify ES that approach to 200°F in the RCS is imminent AND that necessary RTD cross calibration data required at temperatures of 250, 350, 450 and 540 degrees must be obtained. (AI 2009204992) _____ _____ / _____ 5.14.8 Perform FNP-1-STP-10.1, ECCS MOV POWER ISOLATION VERIFICATION. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 38 of 815.14.9 Remove tags AND rack in containment spray pumps. 1A Containment Spray Pump supply breaker Q1R15BKRDF11 (DF-11 CS PUMP 1A Q1E13M001A-A) _____ 1B Containment Spray Pump supply breaker Q1R15BKRDG11 (DG-11 CS PUMP 1B Q1E13M001B-B) _____ 5.14.10WHEN RCS temperature is greater than 180°F, but prior to RCS temperature of 200°F, THEN perform the following to enable a maximum of two charging pumps to be capable of injecting into the RCS: 5.14.10.1Remove tags AND rack in the charging pumps breakers removed from service (Mark N/A the pump to remain tagged): Q1R15BKRDF06 1A CHG PUMP Q1E21M001A-A _____ Q1R15BKRDF07 1B CHG PUMP A TRN Q1E21M001B-AB _____ Q1R15BKRDG07 1B CHG PUMP B TRN Q1E21M001B-AB _____ Q1R15BKRDG06 1C CHG PUMP Q1E21M001C-B _____ 5.14.10.2Verify charging pump surveillances, STPs 4.1 through 4.3, are current per checklist FNP-1-STP-35.1E. _____ _____ / _____ 5.14.11 Remove tag ANDrackin the breaker for the RMW pump previously removed from service: Q1R17BKRFAF2, 1A REACTOR MAKEUP WATER PUMP Q1P12M001A-A _____ Q1R17BKRFBM3, 1B REACTOR MAKEUP WATER PUMP Q1P12M001B-B _____ 5.14.12 Remove tags ANDclose breakers for the CTMT sump to RHR pump suction valves: FU-R4 CTMT SUMP TO 1A RHR PUMP--Q1E11MOV8811A _____ FU-V5 CTMT SUMP TO 1A RHR PUMP-- Q1E11MOV8812A _____ FV-B5 CTMT SUMP TO 1B RHR PUMP-- Q1E11MOV8811B _____ FV-T4 CTMT SUMP TO 1B RHR PUMP-- Q1E11MOV8812B _____ 5.14.13IF tygon hoses are installed, THENremove all tygon hoses from all steam generator wide range level transmitters. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 39 of 815.14.14IF NOT previously performed, THEN deactivate CTMT main purge as follows: 5.14.14.1Verify CTMT PURGE SUPP/EXH FANS & DAMPERS N1P13M002/1 Q1P13HV3203B & A handswitch on the MCB is in STOP. _____ _____ / _____ 5.14.14.2Verify CTMT PURGE DMPRS handswitch HS-3196 in CLOSE. _____ 5.14.14.3Verify CTMT PURGE DMPRS handswitch HS-3198 in CLOSE. _____ 5.14.14.4 On Containment Purge indication panel N1H11ZI2111B check the following: Purge Supply Fan is OFF _____ Purge Exhaust Fan is OFF _____ HV-3197 CLOSED _____ HV-3196 CLOSED _____ HV-3198D CLOSED _____ HV-3198A CLOSED _____ HV-3198C CLOSED _____ HV-3198B CLOSED _____ HV-3203B CLOSED _____ HV-3203A CLOSED _____ 5.14.14.5 In Termination Cabinet Q1H25L008-A, Panel 1, open the following links (reference D-177236, 177237, 177204): 1TB1-19_____EM or I&C 1TB1-20_____EM or I&C 1TB1-22_____EM or I&C 1TB1-23_____EM or I&C 1TB1-60_____EM or I&C5.14.14.6 In Termination Cabinet Q1H25L029-B, Panel 1, open the following link (reference D-177199): 1TB1-44 _____EM or I&C UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 40 of 815.14.15 Verify the MSIVs have been TAGGED CLOSED to prevent steam being carried over to the turbine building, if conditions on the secondary side require a main steam clearance. _____ _____ / _____ NOTEIf this startup is not following a refueling outage and no work activities have taken place in the pressurizer cubicle, step 5.14.16 is N/A. 5.14.16 Ensure critical insulation/lagging has been installed in the pressurizer cubicle (while the cubicle is still reasonably habitable), or exceptions have been approved by outage management. [Lessons Learned 6329] _____ _____ / _____ 5.14.17 Start the containment dome recirculation fans in HIGH (LOW) speed. 1A CTMT DOME RECIRC FAN N1T40M001A _____ 1B CTMT DOME RECIRC FAN N1T40M001B _____ 1C CTMT DOME RECIRC FAN N1T40M001C _____ 1D CTMT DOME RECIRC FAN N1T40M001D _____ 5.14.18 De-energize the containment jib cranes. For Jib crane N1T31K004 open supply breaker N1R17BKRFCM4L _____ For Jib crane N1T31K005 open supply breaker N1R17BKRFDH7L _____ For Jib crane N1T31K006 open supply breaker N1R17BKRFCS3R _____ 5.14.19 Verify R-11/12 in-service and aligned per FNP-1-SOP-45.0, Radiation Monitoring System. _____ 5.14.20 Verify that RCS oxygen concentration is less than 0.1 ppm. ______ CHEM______ / ______5.14.21FNP-1-STP-1.0, Operations Daily and Shift Surveillance Requirements, is current for Mode 4. ______ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 41 of 815.14.22 Start the non-running RCPs per FNP-1-SOP-1.1, Reactor Coolant System. ______ ______ / ______ Do not allow VCT pressure to decrease below 18 psig. Do not exceed the heat up rate specified in PTLR Figure 2-1. CAUTIONS RHR system should not normally be isolated from the RCS until all RCS cold leg temperatures are greater than 275°F. The exception to this is found at step 5.17.2. To prevent overheating of the RHR heat exchangers during the RCS heatup, CCW must be aligned to any RHR HX whose pump is running or that is supplying low pressure letdown. Steam Generator level must be maintained greater than or equal to 75% wide range indication in at least one Steam Generator with an operating Reactor Coolant Pump prior to entering Mode 4 with RHR secured. This assumes that at least one train of RHR is operable and aligned for cooldown operation. RHR pumps shall not be operated in cooldown operation at RCS temperatures greater than 212°F. If any RHR pump is operated in cooldown operation with RCS temperature greater than 212°F, then declare the associated train of ECCS inoperable, AND do not enter Mode 3 until all portions of RHR piping is less than 212°F. (CR 2010106118) 5.14.23IF RHR pumps are to be stopped, THEN align normal letdown as follows:5.14.23.1Verify that the CVCS Letdown flowpath through all available orifices is established. _____ NOTEIf possible when securing a RHR pump for the last time prior to Mode 4 entry, the pump shaft should be observed locally for smooth coast down of the pump. If the shaft exhibits jerky motion, stops abruptly, or unusual scraping or grinding noises are heard, it could be an indication of casing ring cap screws in contact with the pump impeller. SS should be notified immediately. (IN 2003-03, Vogtle LER 2-2002-01) 5.14.23.2Verify 1A (1B) RHR PUMP STOPPED. _____ 5.14.23.3 Simultaneously, slowly close RHR TO LTDN HX HIK 142 while adjusting LP LTDN PRESS PK 145 in AUTO or MANUAL to attempt to maintain letdown flowrate approximately constant. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 42 of 815.14.23.4Verify the following valves CLOSED: 1A RHR HX TO CVCS LETDOWN ISO 1-RHR-V-8720A (Q1E11V013A). _____ 1B RHR HX TO CVCS LETDOWN ISO 1-RHR-V-8720B (Q1E11V013B). _____ NOTEThe intent of the following substep is to monitor for any uncontrolled heatup of the RHR loop(s) after both pumps have been stopped. One train of RHR must remain operable for ECCS injection, thus the designated train RCS suction valves will be closed at Step 5.17.2.1 to prevent heatup above 212°F and the LTOP Tech Spec 3.4.12 will be entered. The train chosen to isolate should be coordinated with Step 5.14.25 for the pump which is chosen for defeating auto start capabilities.5.14.24Prior to 210F,stop the running RHR pump(s). _____ 5.14.24.1 WHEN both RHR pumps STOPPED, monitor both trains of RHR HX Inlet and Outlet temperatures for any continuing, uncontrolled heatup coincident with continued RCS heatup. _____ NOTEOperation of a train of RHR in cool down operation when RCS temperature is between 212°F and 350°F will result in the associated train of ECCS being declared inoperable. One train of ECCS must be operable in Mode 4. (TS 3.5.3) (CR 2010106118) 5.14.25 Defeat the RHR Pump SI auto start per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM for one RHR Pump. _____ Indicate pump defeated. 1A RHR Pump 1B RHR Pump UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 43 of 81NOTEIf the current shutdown was for a refueling outage, a Hydrogen atmosphere in the VCT should not be established until after completion of FNP-1-STP-32.1, Accumulator Discharge Check Valves Leakage Test. 5.15WHEN plant conditions permit, THEN establish a Hydrogen atmosphere in the VCT as follows: 5.15.1 Verify that FNP-1-STP-32.1, Accumulator Discharge Check Valves Leakage Test, has been completed satisfactorily, or is not required for the current shutdown. _____ ______ / ______ 5.15.2 Coordinate with Chemistry ANDestablish a hydrogen atmosphere in the VCT per FNP-1-SOP-2.5, RCS Chemical Addition, VCT Gas Control and Demineralizer Operation. _____ ______ / ______ 5.16WHEN RCS temperature reaches 200°F, THENperform FNP-1-STP-61.0, Reactor Coolant Pump and RHR Loop Operability Verification. _____ NOTEThe intent of the following substeps is to monitor for any uncontrolled heatup of the RHR loop(s) after both pumps have been stopped. One train of RHR must remain operable for ECCS injection, thus the designated train RCS suction valves will be closed to preventheatup above 212°F and the LTOP Tech Spec will be entered. The train chosen to isolate should be coordinated with Step 5.14.25 for the pump which is chosen for defeating auto start capabilities.CAUTIONS Operation of the atmospheric relief will affect RCS heat up rate. Ensure that RCS pressure is maintained 350-425 psig. Operation of the SG atmospheric relief valves with a known primary to secondary leak requires implementation of FNP-0-CCP-645, Main Steam Environmental Release. If required by SG leakage, the Shift Radiochemist should be contacted in advance to allow generation of a release permit and to calculate projected dose rates. 5.17WHEN RCS temperature approaches 210F, THEN verify bothRHR pumps are off. (See caution prior step 5.14.23) {AI2009210071} _____ 5.17.1WHEN both RHR pumps STOPPED, monitor both trains of RHR HX Inlet and Outlet temperatures for any continuing, uncontrolled heatup coincident with continued RCS heatup. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 44 of 81NOTEIn the following step, one train of RHR must remain operable for ECCS and the opposite train of loop suctions must remain OPEN for LTOP Tech Specs.5.17.2IF either train of RHR HX Inlet or Outlet temperature continues to rise, THEN prior to reaching 212°F on the train designated for ECCS injection per Step 5.14.25, perform the following for the RHR train which will remain operable for ECCS injection: 5.17.2.1Close the designated pair of loop suction valves: 1C RCS LOOP TO 1A RHR PUMP Q1E11MOV8701A. _____ 1C RCS LOOP TO 1A RHR PUMP Q1E11MOV8701B. _____ OR 1A RCS LOOP TO 1B RHR PUMP Q1E11MOV8702A. _____ 1A RCS LOOP TO 1B RHR PUMP Q1E11MOV8702B. _____ 5.17.2.2Enter the LTOP LCO 3.4.12 for the isolated RHR loop. _____ 5.18 Notify ES of approach to 250F to enable collection of RTD cross calibration data. (AI 2009204992) _____ ______ / ______ 5.19WHEN RCS temperature is greater than 275°F, THENperform the following to enable all charging pumps to be capable of injecting into the RCS: 5.19.1 Remove tags AND rack in any charging pumps breakers still removed from service (Mark N/A pumps previously tagged in): Q1R15BKRDF06 1A CHG PUMP Q1E21M001A-A _____ Q1R15BKRDF07 1B CHG PUMP A TRN Q1E21M001B-AB _____ Q1R15BKRDG07 1B CHG PUMP B TRN Q1E21M001B-AB _____ Q1R15BKRDG06 1C CHG PUMP Q1E21M001C-B _____ 5.20 Commence Mode 3 surveillance requirements of FNP-1-STP-1.0, Operations Daily and Shift Surveillance Requirements _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 45 of 81CAUTIONSteam Generator level must be maintained greater than or equal to 75% wide range indication in at least one Steam Generator with an operating Reactor Coolant Pump while in Mode 4 with RHR secured. This assumes that at least one train of RHR is operable and aligned for cool down operation. 5.21As RCS temperature increases, perform the following: 5.21.1IF it is desired to hold for steam generator chemical contaminant removal, THEN perform the following: 5.21.1.1Maintain RCS temperature 335-345°F. _____ 5.21.1.2Maintain steam generator narrow range water level 61-69% using AFW and at least one S/G with an operating RCP must be maintained greater than or equal to 75% wide range level. _____ 5.21.1.3Maintain maximum allowable steam generator blowdown flow. _____ 5.21.1.4Maintain RCS temperature with Atmospheric Relief Valves. _____ CAUTIONIf a steam generator is drained below 28% narrow range prior to completing the initial conditions of Appendix 1, an ESF auto-start of the AFW system will occur. 5.21.1.5 IF it is desired to drain and refill the steam generators following chemical contaminant removal, THEN refer to Appendix 1. _____ _____ / _____ NOTEPressurizer Loop Seal Drains Q1B13V030A can be accessed from the intermediate platform inside the PZR cubicle. (Q1B13V030A does not have a handle; a wrench is required to operate this valve.) Q1B13V030B&C are accessed from the opening on the 155' elevation.5.21.2 Verify Pressurizer Loop Seal Drains TORQUED CLOSED. Q1B13V030A, 1A PRZR SAFETY RELIEF LOOP SEAL DRN ISO _____ Q1B13V030B, 1B PRZR SAFETY RELIEF LOOP SEAL DRN ISO _____ Q1B13V030C, 1C PRZR SAFETY RELIEF LOOP SEAL DRN ISO _____ _____ / _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 46 of 81NOTEThe following step has an STP that is a Mode 1-3 requirement due every 18 months and must be performed prior to Mode 3. If the due date will be before the next refueling outage, this STP may be performed during the 340F temperature hold. 5.21.3IF not performed in the previous 18 months and it will be due the next refueling outage, THEN perform FNP-1-STP-45.14, Pressurizer PORV Operability Test. _____ _____ / _____ NOTEPerformance of the following step is not required at this time; however, the main steam system should be placed in service prior to reaching 547°F Tavg.5.21.4 Align the main steam system per FNP-1-SOP-17.0, Main and Reheat Steam._____5.22Prior to exceeding 350°F (entering Operational Mode 3) the following items must be completed: CAUTIONThe RCPs are not designed for start-stop operations. 5.22.1 Maintain RCS temperature below 350°F by removing reactor coolant pumps from service while observing the following: 5.22.1.1 Before starting or stopping any reactor coolant pumps, review Precautions and Limitations in Section 3.2, in Section 3.3 and FNP-1-SOP-1.1. _____ 5.22.1.2Maintain at least one reactor coolant pump running. _____ 5.22.1.3 IF required THENoperate the atmospheric relief valves as necessary. _____ 5.22.2Prior to performing step 5.23.3, maintain steam generator and reactor coolant system conditions as follows: 5.22.2.1 In Mode 4 maintain steam generator levels equal to or greater than 75% wide range indication in at least two RCS loops with a reactor coolant pump running is at least one of the loops. _____ 5.22.2.2 Before entering Mode 3, maintain steam generator levels greater than or equal to 30% narrow range indication in at least two RCS loops with operating reactor coolant pumps. Only one reactor coolant pump is required if the rod control system is disabled. (Tech Spec 3.4.5) _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 47 of 815.22.3WHEN RCS temperature greater than 275°F, THEN align RHR for ECCS Standby Alignment per FNP-1-SOP-7.0, Residual Heat Removal System.__________ / _____ 5.22.4 Restore the RHR Pump SI auto start that was defeated in step 5.14.25 per FNP-1-SOP-7.0, Residual Heat Removal System. _____ _____ / _____ 5.22.5 Perform FNP-1-STP-11.14, RHR Mechanical Stops. _____ _____ / _____ 5.22.6 Verify containment sump level wide range instrumentation. LQI-3594A ON-OFF-FULL REF switch in ON position Power ON light illuminated. _____ _____ / _____ LQI-3594B ON-OFF-FULL REF switch in ON position Power ON light illuminated. _____ _____ / _____ 5.22.7 Review the "Work In Progress File(s)" for any activities in progress that could effect the pending Mode change. TE 651930. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 48 of 81NOTETo address concerns regarding the possibility of an inadvertent rod withdrawal while subcritical, which were detailed in NASL-00-016 the following criteria should be applied in Modes 3-6: If rod control is enabled, then RCS boron concentration must be maintained equal to or greater than the requirements of Curve 1A, unless reactor startup is imminent.If Rod Control is not enabled, then heatup and RCS dilution may proceed in parallel, so long as boron concentration is sufficient to insure shutdown margin requirements are met, and Power Range Excore NIS low power trip available. CAUTIONAt least one RCP must be running prior to changing the boron concentration in the RCS. (SOER 94-02) 5.22.8IF necessary, THEN conduct a boron dilution of the RCS to one of the following conditions whichever is greater. [NEL-01-0093] [AIT #2001201049] Cold shutdown boron concentration _____ _____ / _____ ARO critical boron concentration (Curve 1A) _____ _____ / _____ Estimated critical boron concentration _____ _____ / _____ 5.22.9IF not completed within last 24 hours, THEN record on FNP-1-STP-35.1, Unit Startup Technical Specification Verification, completion of Technical Specification Surveillance requirements for Mode 3 operation per check list FNP-1-STP-35.1D. _____ _____ / _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 49 of 815.22.10The Shift Manager has granted permission for Mode 3 entry. (CR 2010106404) _____ _____ / _____ 5.22.11 Start a CRDM cooling fan. 1A CRDM CLG FAN N1T47M001A _____ 1B CRDM CLG FAN N1T47M001B _____ _____ / _____ 5.22.12WHEN all RCS cold leg temperatures are greater than 275°F, ANDRHR system have been removed from operation per FNP-1-SOP-7.0, Residual Heat Removal System, THENperform the following: 5.22.12.1Verify 1A RCS LOOP TO 1B RHR PUMP Q1E11MOV8702A is CLOSED _____ 5.22.12.2Verify 1A RCS LOOP TO 1B RHR PUMP Q1E11MOV8702B is CLOSED _____ 5.22.12.3Verify 1C RCS LOOP TO 1A RHR PUMP Q1E11MOV8701A is CLOSED _____ 5.22.12.4Verify 1C RCS LOOP TO 1A RHR PUMP Q1E11MOV8701B is CLOSED _____ 5.22.13 Verify the Inadequate Core Cooling Monitoring System in operation per FNP-1-SOP-68.0, Inadequate Core Cooling Monitoring System, with exceptions noted. _____ _____ / _____ 5.22.14 Place the RCS solid control selector switch to the DEFEAT position. _____ 5.22.15WHEN RCP number 1 seal leak-off increases to 1 gpm for each pump, THENperform the following: 5.22.15.1 IF RCP SEAL WTR BYP Q1E21HV8142 is open, THEN close the valve. _____ _____ / _____ 5.22.15.2Verify seal leak-off flow remains above 1 gpm. _____ _____ / _____ 5.22.16IF less than 2 RCPs are operating, THEN verify the rod control system is disabled for rod withdrawal prior to entering Mode 3. _____ _____ / _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 50 of 815.22.17 Verify AFW to steam generator stop valves OPEN: Q1N23MOV3350A, 1A SG STOP VLV _____ Q1N23MOV3350B, 1B SG STOP VLV _____ Q1N23MOV3350C, 1C SG STOP VLV _____ _____ / _____ 5.22.18 Verify AFW to steam generator stop valves supply breakers are LOCKED OPEN. (Master "Z" Key) Q1N23MOV3350A breaker Q1R17BKRFUU4 _____ Q1N23MOV3350B breaker Q1R17BKRFUU5 _____ Q1N23MOV3350C breaker Q1R17BKRFUI2 _____ 5.22.19 Ensure reactor coolant pump seal injection flows are within the limits of Technical Specification 3.5.5 prior to entering Mode 3. _____ _____ / _____ NOTES As RCS pressure increases, the operator must closely monitor RCP #1 seal leakoff for evidence of a shutdown seal actuation. Leakoff flow will trend up as RCS pressure increases. If a shutdown seal has actuated, it is expected that the upward trend will slow and begin to fall as seal dP reaches ~600-800 psid and the polymer ring begins clamping on the sleeve. Accumulators must be unisolated prior to exceeding 1000 psig RCS pressure. Accumulators are required to be operable in Mode 3 greater than 1000 psig RCS pressure.5.22.20 Increase RCS pressure to 925-975 psig, which must be completed before opening accumulator discharge MOVs per step 5.23.20.5. _____ _____ / _____ 5.22.20.1Verify that FNP-1-STP-32.1, Accumulator Discharge Check Valves Leakage Test, has been completed satisfactorily, or is not required for the current shutdown. _____ _____ / _____ 5.22.20.2Verify that RCP SEAL WTR BYP Q1E21HV8142 CLOSED prior to exceeding 1000 psig. _____ _____ / _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 51 of 81NOTEThe supply breakers disconnect switches for the accumulator discharge valves are locked open at all times except when valve operation is required. 5.22.20.3Obtain a Master "Z" key from the Shift Support Supervisor. _____ 5.22.20.4Unlock and close the following disconnects: Q1R18B032-A - 1A ACCUM DISCH ISO Q1E21MOV8808A. _____ Q1R18B031-A - 1C ACCUM DISCH ISO Q1E21MOV8808C. _____ Q1R18B035-B - 1B ACCUM DISCH ISO Q1E21MOV8808B. _____ _____ / _____ 5.22.20.5Open the following valves: 1A ACCUM DISCH ISO Q1E21MOV8808A _____ 1B ACCUM DISCH ISO Q1E21MOV8808B _____ 1C ACCUM DISCH ISO Q1E21MOV8808C _____ 5.22.20.6INDEPENDENTLY VERIFY the following valves are OPEN: 1A ACCUM DISCH ISO Q1E21MOV8808A _____ IV 1B ACCUM DISCH ISO Q1E21MOV8808B _____ IV 1C ACCUM DISCH ISO Q1E21MOV8808C _____ IV5.22.20.7Open ANDlock open the following breaker disconnects. Q1R18B032-A - 1A ACCUM DISCH ISO Q1E21MOV8808A _____ Q1R18B031-A - 1C ACCUM DISCH ISO Q1E21MOV8808C _____ Q1R18B035-B - 1B ACCUM DISCH ISO Q1E21MOV8808B _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 52 of 815.22.20.8INDEPENDENTLY VERIFY the following breaker disconnects are LOCKED OPEN: Q1R18B032-A - 1A ACCUM DISCH ISO Q1E21MOV8808A _____ IV Q1R18B031-A - 1C ACCUM DISCH ISO Q1E21MOV8808C _____ IV Q1R18B035-B - 1B ACCUM DISCH ISO Q1E21MOV8808B _____ IV5.22.21 Perform FNP-1-STP-31.0, Accumulator Motor Operated Valve Power Isolation Verification. _____ _____ / _____ 5.22.22Before entering Mode 3, verify steam generator levels greater than or equal to 30% narrow range indication in at least two RCS loops with operating reactor coolant pumps. Only one reactor coolant pump is required if the rod control system is disabled. (Tech Spec 3.4.5) _____ _____ / _____ 5.22.23 Notify ES of approach to 350°F to enable collection of RTD cross calibration data. (AI 2009204992) _____ _____ / _____ NOTEMOV 8706A & MOV 8706B are required to be closed with power locked out in Modes 4 and 5. These MOVs must be energized within 4 hours of entering Mode 3.(Ref. SR 3.5.3.2 and other Administrative Controls). 5.23 Continue to increase RCS temperature and pressure within limits of PTLR Figure 2-1 while limiting the differential pressure across the Steam Generator Tubes to less than 1600 psid. (AI 2007202326) _____ _____ / _____ NOTEAt least 5 gpm SGBD flow from each steam generator should be maintained to provide sufficient flow to sample system. 5.23.1IF desired, THEN reduce SGBD flow to 5 gpm per steam generator to enhance RCS heat-up. _____ _____ / _____ 5.23.2 Verify FNP-1-STP-1.0, Operations Daily and Shift Surveillance Requirements, is current for Mode 3. _____ _____ / _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 53 of 81NOTEStep 5.25.2 must be performed within 4 hours after RCS temperature reaches 350F.5.24WHEN RCS temperature reaches 350F, THEN perform the following: 5.24.1 Verify FNP-1-STP-61.0, Reactor Coolant Pump and RHR Loop Operability Verification, is current for Mode 3 (greater than or equal to 350°F)._____5.24.2Within 4 hours after RCS temperature exceeds 350F,unlockANDclose the following breakers: Q1R17BKRFVE4, 1B RHR HX TO CHG PUMP SUCT Q1E21MOV8706B _____ Q1R17BKRFUF5, 1A RHR HX TO CHG PUMP SUCT Q1E21MOV8706A _____ 5.24.3 Open the following breakers: (CR 2005103659) Q1R17BKRFVV3, 1A RCS LOOP TO 1B RHR PUMP Q1E11MOV8702B _____ Q1R17BKRFVV2, 1C RCS LOOP TO 1A RHR PUMP Q1E11MOV8701B _____ 5.24.4 INDEPENDENTLY VERIFY the following breakers are CLOSED: Q1R17BKRFVE4, 1B RHR HX TO CHG PUMP SUCT Q1E21MOV8706B _____ IV Q1R17BKRFUF5, 1A RHR HX TO CHG PUMP SUCT Q1E21MOV8706A _____ IV 5.24.5 INDEPENDENTLY VERIFY the following breakers are OPEN: Q1R17BKRFVV3, 1A RCS LOOP TO 1B RHR PUMP Q1E11MOV8702B _____ IV Q1R17BKRFVV2, 1C RCS LOOP TO 1A RHR PUMP Q1E11MOV8701B _____ IV UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 54 of 815.25While continuing with the remaining steps, as the RCS heatup continues, notify ES of the following to enable collection of RTD cross calibration data. (AI 2009204992) 5.25.1RCS temperature approaching 450°F. _____ _____ / ____ 5.25.2RCS temperature approaching 540°F. _____ _____ / ____ 5.26IF required, THEN prior to reaching 547°F perform the following in preparation for turbine generator and steam dump operation. IF steps are NOT required prior to 547°F, THEN performed as required. 5.26.1 Place the circulating water system in operation per FNP-1-SOP-26.0, Circulating Water System. _____ 5.26.1.1 The Circ Water Make Up Control Valve, Q1P16V560, should operated in accordance with Appendix 1, SW to CW Canal LCV, Q1P16V560, Operation _____ _____ / _____ 5.26.1.2 If desired, the make-up control valve can be adjusted to cause a slowly increasing canal level, and the Circulating Water Canal Isolation Valve, Q1P16V550, can be closed as required to reduce canal level to the lower end of the control band and then reopened. _____ _____ / _____ 5.26.2 Perform main turbine lube oil pump and EH fluid pump operational checks per the following: 5.26.2.1 FNP-1-SOP-28.1 Section 4.1, Turbine Generator Operation. _____ _____ / _____ 5.26.2.2 FNP-1-SOP-28.9 Section 4.1, EH Fluid System Operation. _____ _____ / _____ 5.26.3 Perform steam generator feed pump pre-start test on 1A and 1B feed pumps per FNP-1-SOP-21.0, Condensate and Feedwater System. _____ _____ / _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 55 of 815.26.4 Place the condensate system in operation, using 1 condensate pump, per FNP-1-SOP-21.0, Condensate and Feedwater System. _____ _____ / _____ 5.26.5 Place the gland sealing system in operation per FNP-1-SOP-28.4, Gland Sealing Steam System. _____ _____ / _____ 5.26.5.1Verify the Unit 1 condenser inlet, N1P20V548, CLOSED. _____ 5.26.6 Establish condenser vacuum per FNP-1-SOP-28.5, Condenser Air Removal System. _____ _____ / _____ 5.26.7 Establish nitrogen purge flow to the condenser per FNP-1-SOP-21.0, Condensate and Feedwater System. _____ _____ / _____ NOTEHeaters will automatically de-energize and energize as the cooling tower fans are started and stopped if the heater breakers are closed per FNP-1-SOP-26.0A. 5.26.8At the 1A cooling tower local control station/panel, performthe following: Start fans on 600V LC 1U, if not already running. _____ _____ / _____ Start fans on 600V LC 1V, if not already running. _____ _____ / _____ Start fans on LC # 11, if not already running. _____ _____ / _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 56 of 81NOTEThe letdown flow will increase with increasing RCS pressure. 5.27Prior to reaching high letdown flow limit of 140 gpm, perform the following: 5.27.1 Adjust letdown pressure control valve controller PK-145 within the normal operating pressure band of 260-450 psig. _____ _____ / _____ 5.27.2 Isolate a letdown orifice isolation valve to limit letdown flow to less than or equal to 135 gpm as required, LTDN ORIF ISO 60 GPM Q1E21HV8149B _____ _____ / _____ LTDN ORIF ISO 60 GPM Q1E21HV8149C _____ _____ / _____ 5.28IF excess letdown was placed in operation, THENremove from operation per FNP-1-SOP-2.7, Chemical and Volume Control System Excess Letdown. _____ NOTEAt least two Reactor Coolant Loops shall be operable and in operation with Steam Generator levels greater than or equal to 30% narrow range indication with the Rod Control System operational. If the Rod Control System is inoperable as provided in Tech Spec 3.4.5, only one Reactor Coolant Pump is required to be in operation. 5.29 Maintain steam generator levels in the normal operating range (61-69%) by operation of the motor driven auxiliary feed pumps per FNP-1-SOP-22.0, Auxiliary Feedwater System. _____ 5.30IF this shutdown has been for refueling, THENperform FNP-1-STP-32.1, Accumulator Discharge Check Valves Leakage Test. _____ _____ / _____ 5.31WHEN RCS pressure exceeds 2000 psig, THEN verify the following: 5.31.1Pressurizer PRESS SI and PORV BLOCK P-11 annunciator HD2 is clear. _____ 5.31.2Pressurizer SAFETY INJECTION TRAIN A BLOCKED is clear on the BYP & PERMISSIVE status panel. _____ 5.31.3Pressurizer SAFETY INJECTION TRAIN B BLOCKED is clear on the BYP & PERMISSIVE status panel. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 57 of 81NOTEAny throttle valve adjustments should be verified acceptable per SR 3.5.5.1 with the "strongest" and "weakest" charging pump supplying flow within 4 hours. Engineering Support can supply information as to the strongest and weakest pumps. If it is not feasible to run FNP-1-STP-8.0, RCP Seal Controlled Leakage Test, using either the strongest or weakest pump (i.e. pump not capable of running or breaker racked out), then, the surveillance should be run with the two available charging pumps and an admin LCO written for the inoperable pump to ensure FNP-1-STP-8.0, RCP Seal Controlled Leakage Test, is run when the pump is returned to service. CAUTIONAfter RCS pressure exceeds 2000 psig, any significant changes in charging flow, particularly charging pump swaps, shall be followed with a check of RCP seal flow, using the guidance for swapping charging pumps given in FNP-1-SOP-2.1, Chemical and Volume Control System Plant Startup and Operation. 5.32WHEN RCS pressure exceeds 2000 psig, THEN perform the following: 5.32.1 Open SEAL WTR INJECTION HIK 186 fully. _____ 5.32.2 Verify seal injection flow to RCPs is within the limits of Technical Specification 3.5.5. _____ _____ / _____ 5.32.3IF required, THENadjust RCP SEAL WATER INJ THROTTLE valves. Q1E21V116A 1A RCP SEAL WATER INJ THROTTLE VLV _____ Q1E21V116B 1B RCP SEAL WATER INJ THROTTLE VLV _____ Q1E21V116C 1C RCP SEAL WATER INJ THROTTLE VLV _____ 5.32.4 Verify the RCP SEAL WATER INJ THROTTLE valves are sealed in position:(NRC Cmt. 0004355) (CR 2010113165 & 2010118146) Q1E21V116A 1A RCP SEAL WATER INJ THROTTLE VLV _____ Q1E21V116B 1B RCP SEAL WATER INJ THROTTLE VLV _____ Q1E21V116B 1B RCP SEAL WATER INJ THROTTLE VLV _____ 5.32.5 Independentlyverify the RCP SEAL WATER INJ THROTTLE valves are sealed in position: (NRC Cmt. 0004355) (CR2010113165 & 2010118146) Q1E21V116A 1A RCP SEAL WATER INJ THROTTLE VLV _____ Q1E21V116B 1B RCP SEAL WATER INJ THROTTLE VLV _____ Q1E21V116C 1C RCP SEAL WATER INJ THROTTLE VLV _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 58 of 81NOTEFNP-1-STP-8.0, RCP Seal Injection Leakage Test (Step 5.35) must be performed within 4 hours of the RCS pressure stabilizing at greater than or equal to 2215 psig and less than or equal to 2255 psig. 5.33WHEN RCS pressure approaches normal operating pressure (2235 psig), THENperform the following: 5.33.1 Place pressurizer backup heaters in automatic. 1A PRZR HTR GROUP BACKUP in AUTO _____ 1B PRZR HTR GROUP BACKUP in AUTO _____ 1D PRZR HTR GROUP BACKUP in AUTO _____ 1E PRZR HTR GROUP BACKUP in AUTO _____ 5.33.2 Place pressurizer spray valves in automatic. 1A LOOP SPR VLV PK 444C in AUTO. _____ 1B LOOP SPR VLV PK 444D in AUTO _____ 5.33.3 Verify RCS pressure maintained at the normal operating pressure. _____ 5.34Within 4 hours after the reactor coolant system pressure stabilizes at greater than or equal to 2215 psig and less than or equal 2255 psig, THENperform FNP-1-STP-8.0, RCP Seal Controlled Leakage Test for the strongest AND weakest charging pumps. FNP-1-STP-8.0, RCP Seal Controlled Leakage Test for the strongest charging pump. _____ _____ / _____ FNP-1-STP-8.0, RCP Seal Controlled Leakage Test for the weakest charging pump. _____ _____ / _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 59 of 815.35As RCS heatup continues, perform the following: 5.35.1Prior to reaching 541F in the RCS, ensure the Power Range Flux Low Setpoint (25%RTP) trip is available, if the rod control system is enabled and capable of rod withdrawal. _____ _____ / _____ 5.35.2 Perform FNP-1-STP-9.0, RCS Leakage Test if not performed within last 72 hours. _____ 5.35.3WHEN RCS temperature exceeds 545°F, THEN verify the following Steamline block lights clear on the Bypass and Permissive status panel: Steamline Isolation Safety Injection Train A _____ _____ / _____ Steamline Isolation Safety Injection Train B _____ _____ / _____ 5.35.4Prior to reaching 547Fperform the following: 5.35.4.1Place the steam dump system in the steam pressure mode per FNP-1-SOP-18.0, Steam Dump System, with the pressure controller set at 1005 psig setpoint. _____ _____ / _____ 5.35.4.2 IF the steam dumps or main condenser are not available, THENmaintain the RCS between 545 and 549F with the steam generator atmospheric relief valves. _____ _____ / _____ NOTEIF no maintenance was performed on the TDAFWP AND the surveillance tests listed below are current, THEN step 5.36.5 is not applicable. 5.35.5 Perform the following TDAFWP surveillance tests within 24 hours of steam generator pressures reaching greater than or equal to 1005 psig. 5.35.5.1 FNP-1-STP-22.23 Turbine Driven Auxiliary Feedwater Pump Trip and Throttle Valve Mechanism and Indication Test. _____ _____ / _____ 5.35.5.2 FNP-1-STP-22.16, Turbine Driven Auxiliary Feedwater Pump Quarterly In-Service Test, and Operability Test. _____ _____ / _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 60 of 81NOTEPressurizer Loop Seal Drains Q1B13V030A can be accessed from the intermediate platform inside the PZR cubicle. (Q1B13V030A does not have a handle; a wrench is required to operate this valve.) Q1B13V030B&C are accessed from the opening on the 155' elevation.5.35.6IF PZR loop seal leakage is evident based on: A review of PRT parameters: PRT LVL LI-470 PRT TEMP TI-471 PRT PRESS PI-472 ORBy pressurizer safety loop seal temperature indicators: TI-469 A PRZR CODE SAFETY TAILPIPE TEMP INDICATOR TI-467 B PRZR CODE SAFETY TAILPIPE TEMP INDICATOR TI-465 C PRZR CODE SAFETY TAILPIPE TEMP INDICATOR THENtorque shut Pressurizer Loop Seal drain valvesANDcheck for leak-by. Q1B13V030A, 1A PRZR SAFETY RELIEF LOOP SEAL DRN ISO _____ _____ / _____ Q1B13V030B, 1B PRZR SAFETY RELIEF LOOP SEAL DRN ISO _____ _____ / _____ Q1B13V030C, 1C PRZR SAFETY RELIEF LOOP SEAL DRN ISO _____ _____ / _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 61 of 81NOTEThe following test is only required if the RCS had been opened for refueling or maintenance.5.35.7WHEN reactor coolant temperature is at approximately Normal Operating Temperature (NOT), THEN conduct reactor coolant system leak test per FNP-1-SOP-1.4, Reactor Coolant System Leak Test. _____ _____ / _____ 5.36IF required, THEN reduce letdown flow to 60 gpm by the following: 5.36.1 Close one 60 gpm letdown orifice valve per FNP-1-SOP-2.1, Chemical and Volume Control System Plant Startup and Operation. Q1E21HV8149B, LTDN ORIF ISO 60 GPM _____ Q1E21HV8149C, LTDN ORIF ISO 60 GPM _____ 5.36.2 Perform FNP-1-STP-8.0, RCP Seal Controlled Leakage Test immediately to verify the requirements of Technical Specification SR 3.5.5.1. _____ _____ / _____ NOTEAt least two Reactor Coolant Loops shall be operable and in operation with Steam Generator levels greater than or equal to 30% narrow range indication with the Rod Control System operational. If the Rod Control System is inoperable as provided in Tech Spec 3.4.5, only one Reactor Coolant Pump is required to be in operation. 5.37 Maintain steam generator levels 61-69% with the MDAFWP. _____ 5.38 Sample steam generators AND adjust chemistry within the specifications for power operation required by FNP-0-CCP-202, Water Chemistry Specifications.__________ / _____ _____CHEM_____ / _____ 5.39IF not already established, THEN establish a hydrogen atmosphere in the VCT. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 62 of 815.40 PRIOR to Mode 2, flush the cation bed to remove suspended solids and to minimize the volume needed to borate the bed if required by CHEMISTRY. _____ _____ / _____ _____CHEM_____ / _____ 5.41IF required, THENperform the following TDAFWP surveillance test procedures. FNP-1-STP-21.3 TDAFWP Steam Supply Valves In-Service Test _____ FNP-1-STP-22.6 Auxiliary Feedwater Pump Train B Functional Test _____ FNP-1-STP-22.7 Auxiliary Feedwater Pump Train A Functional Test _____ FNP-1-STP-22.10 Turbine Driven Auxiliary Feedwater Pump Blackout Start Test _____ FNP-1-STP-22.13 Turbine Driven Auxiliary Feedwater Pump Check Valves Flow Verification _____ FNP-1-STP-22.20 TDAFW Pump Steam Admission Valves Air Accumulator Test _____ 5.42Return SGBD flow to normal per Chemistry requirements. _____ _____ / _____ __________________________________________Shift Supervisor Review 6.0 RECORDS Documents created using this procedure will become QA Records when completed unless otherwise stated. The procedures and documents are considered complete when issued in DMS. QA Record (X) Non-QA Record (X)Record Generated Retention Time R-Type X FNP-1-UOP-1.1 LP H06.055 UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 63 of 81Figure 1 Residual Heat Removal And Reactor Coolant Pump Limitations During Heatup And Cooldown UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 64 of 81Figure 2 No. 1 Seal Normal Operating Range NOTEFor No. 1 Seal differential pressure greater than 400 psid, use RCS pressure in psig. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 65 of 81APPENDIX 1 STEAM GENERATOR DRAINING AND REFILLING FOR CHEMICAL CONTAMINANT REMOVAL Performed by: DateReviewed by: DateThis Appendix consists of 3 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 66 of 81APPENDIX 1 STEAM GENERATOR DRAINING AND REFILLING FOR CHEMICAL CONTAMINANT REMOVAL (Page 1 of 2) 1.0 Purpose To provide guidance for Steam Generator draining and refilling for chemical contaminant removal during shutdown of Unit. 2.0 Initial Conditions 2.1The version of this appendix has been verified to be the current version. (OR 1-98-498) _____ 2.2The version of this appendix has been verified to be the correct unit for the task. (OR 1-98-498) _____ 3.0 Draining Steam Generators 3.1 Verify SGBD is in operation per FNP-1-SOP-16.1, Steam Generator Blowdown Processing System. _____ 3.2 Verify SG wide range LT 477, LT 487 and LT 497 are in service and indicating on LR 477. _____ 3.3 Verify the following have been defeated by completing Appendix 3: 3.3.1AFW pump auto start. _____ 3.3.2SGBD isolation signals. _____ 3.4MSIVs are CLOSED per FNP-1-SOP-17.0, Main and Reheat Steam. _____3.5 Ensure RHR loop and RCS loop operability requirements are met per Tech. Spec. 3.4.6 and 3.4.7. _____ NOTEThe following steps may be performed in any order 3.6IF nitrogen addition is desired, THEN go to FNP-1-SOP-16.3, the section for establishing and removing nitrogen pressure from steam generator 1A (1B, 1C). _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 67 of 81APPENDIX 1 STEAM GENERATOR DRAINING AND REFILLING FOR CHEMICAL CONTAMINANT REMOVAL (Page 2 of 2) NOTEAFW FCVs will open on lo-lo SG level and TDAFW pump steam admission valves will open.3.7 Drain the steam generator(s) as desired per FNP-1-SOP-16.3, Steam Generator Filling and Draining using the following: Steam Generator Blowdown _____ Steam Generator Shell Drain Pump _____ 4.0 Refilling Steam Generator(s) 4.1 Verify SG wide range LT 477, 487 and 497 are in service. _____ 4.2 Verify SG wide range LT 477, 487 and 497 are indicating on LR-477. _____ 4.3 Isolate N2 supply to the desired SG(s) per FNP-1-SOP-16.3. _____ 4.4 Verify the auto-start of the 1A MDAFWP is defeated per Appendix 3. _____ NOTEIf SG level is maintained greater than 12%, filling and draining of the SG may be performed, as required to aid in decontamination of the secondary water. CAUTIONDo not add auxiliary feedwater to a SG if wide range level is less than 12% and RCS temperature is greater than or equal to 200°F. 4.5 Verify that SG level is greater than 12% wide range. _____ 4.6 Fill the SG per the instructions in the applicable section of FNP-1-SOP-16.3. _____ 4.7WHEN flushing is complete, THEN fill the SG to its normal level as determined by the Shift Supervisor using 1A MDAFWP per FNP-1-SOP-22.0, Auxiliary Fedwater System. _____ 4.8WHEN flushing is complete in all SGs AND SG levels are greater than 28% narrow range, THEN perform Appendix 4 to restore the MDAFW Pump auto-start capability. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 68 of 81APPENDIX 2 ALIGNING NITROGEN SUPPLY FOR STEAM GENERATOR DRAINING AND FILLING FOR CHEMICAL CONTAMINANT REMOVAL (DELETED)Verified by: DatePerformed by: DateReviewed by: DateThis Appendix consists of 0 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 69 of 81APPENDIX 3 DEFEATING THE AUXILIARY FEEDWATER PUMPS' AUTO-STARTS AND SGBD ISOLATION Verified by: DatePerformed by: DateReviewed by: DateThis Appendix consists of 2 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 70 of 81APPENDIX 3 DEFEATING THE AUXILIARY FEEDWATER PUMPS' AUTO-STARTS AND SGBD ISOLATION (Page 1 of 2) 1.0 Purpose To defeat the Auxiliary Feedwater Pump Auto-Starts and SGBD Isolation functions. 2.0 Initial Conditions 2.1The version of this appendix has been verified to be the current version. (OR 1-98-498)_____2.2The version of this appendix has been verified to be the correct unit for the task. (OR 1-98-498) _____ 3.0 Instructions 3.1 Defeat the MDAFWP's auto-start on a dual Main Feed Pump trip by verifying the following: 3.1.11A MDAFWP Auto-Defeat switch in DEFEAT _____ 3.1.21B MDAFWP Auto-Defeat switch in DEFEAT _____ 3.2 Verify TDAFWP TRIP & THRTL VLV Q1N12MOV3406 CLOSED. _____ 3.3 Defeat the 1A MDAFWP auto-start on low-low SG level as follows: 3.3.1In the SOLID STATE PROTECTION SYSTEM TRAIN "A" LOGIC CABINET,place the INPUT ERROR INHIBIT switch to INHIBIT. _____ 3.3.2In the SOLID STATE PROTECTION SYSTEM TRAIN "A" OUTPUT CABINET on the OUTPUT RELAY TEST PANEL, place the MODE SELECTOR switch to TEST. _____ 3.3.3In SOLID STATE PROTECTION SYSTEM TRAIN A OUTPUT CABINET (rear section), have I&C lift the black field lead from terminal #1 or #2 on terminal block TB 632 (Ref. D-177186/1, D-177357). _____ I&CWire No. 3.3.4In the SOLID STATE PROTECTION SYSTEM TRAIN "A" OUTPUT CABINETonthe OUTPUT RELAY TEST PANEL, place the MODE SELECTOR switch to OPERATE AND verify the OPERATE lamp is ON. _____ 3.3.5In SOLID STATE PROTECTION SYSTEM TRAIN A LOGIC CABINET, place the INPUT ERROR INHIBIT switch to NORMAL. _____ 3.3.6 Close and lock SOLID STATE PROTECTION SYSTEM TRAIN A LOGIC CABINET and OUTPUT CABINET doors. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 71 of 81APPENDIX 3 DEFEATING THE AUXILIARY FEEDWATER PUMPS' AUTO-STARTS AND SGBD ISOLATION (Page 2 of 2) 3.4 Verify 1B MDAFWP supply breaker Q1R15BKRDG10, Racked Out. _____ 3.5 Have EM defeat the SGBD isolation on low-low SG level by jumpering the following terminals in 1A MDAFWP supply breaker Q1R15BKRDF10 per NMP-MA-018, PLANT ELECTRICAL COMPONENT TEMPORARY CONFIGURATION CONTROL. (Ref. D-177186/1) Relay SGBX, contacts 5 and 6 (Terminal Block TE, right side, Terminals 3 & 4) _____ EM Relay SGBX, contacts 7 and 8 (Terminal Block TE, right side, Terminals 5 & 6) _____ EM Relay SGBX, contacts 9 and 10 (Terminal Block TE, right side, Terminals 7& 8) _____ EM 3.6 Have EM defeat the SGBD sample isolation on AFW Pump auto-start by performing one of the following: (Ref. D-177186/1, D-177394/3, D-177844) In 1A MDAFWP breaker Q1R15BKRDF10, open link at Terminal Block TF, Terminal 3, for wire 95-7F. _____ EMOR In 1A MDAFWP breaker Q1R15BKRDF10, open link at Terminal Block TF, Terminal 4, for wire 95-8F. _____ EM3.7 Verify 1A MDAFWP supply breaker Q1R15BKRDF10 is racked in. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 72 of 81APPENDIX 4 REINSTATING THE AUXILIARY FEEDWATER PUMP AUTO-START AND SGBD ISOLATION FUNCTIONS Verified by: DatePerformed by: DateReviewed by: DateThis Appendix consists of 2 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 73 of 81APPENDIX 4 REINSTATING THE AUXILIARY FEEDWATER PUMP AUTO-START AND SGBD ISOLATION FUNCTIONS (Page 1 of 2) 1.0 Purpose To reinstate the Auxiliary Feedwater Pump Auto-Start and SGBD Isolation functions. 2.0 Initial Conditions 2.1The version of this appendix has been verified to be the current version. (OR 1-98-498)_____2.2The version of this appendix has been verified to be the correct unit for the task. (OR 1-98-498) _____ 2.3Both MDAFW Pumps Auto-Defeat switches on the BOP are in DEFEAT. _____ 3.0 Instructions CAUTIONEnsure that all SG levels are in the normal operating range before performing this appendix.3.1 Open TDAFWP TRIP & THRTL VLV Q1N12MOV3406. _____ 3.2 Notify EM to reinstate the SGBD isolation by removing jumpers as follows: 3.2.1In 1A MDAFWP breaker Q1R15BKRDF10, remove jumper from SGBX relay contacts 5 and 6 (Terminal Block TE, right side, Terminals 3 and 4) per NMP-MA-018, PLANT ELECTRICAL COMPONENT TEMPORARY CONFIGURATION CONTROL. _____ EM3.2.2In 1A MDAFWP breaker Q1R15BKRDF10, remove jumper from SGBX relay contacts 7 and 8 (Terminal Block TE, right side, Terminals 5 and 6) per NMP-MA-018, PLANT ELECTRICAL COMPONENT TEMPORARY CONFIGURATION CONTROL. _____ EM3.2.3In 1A MDAFWP breaker Q1R15BKRDF10, remove jumper from SGBX relay contacts 9 and 10 (Terminal Block TE, right side, Terminals 7 and

8) per NMP-MA-018, PLANT ELECTRICAL COMPONENT TEMPORARY CONFIGURATION CONTROL. _____ EM UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 74 of 81APPENDIX 4 REINSTATING THE AUXILIARY FEEDWATER PUMP AUTO-START AND SGBD ISOLATION FUNCTIONS (Page 2 of 2) 3.3 Notify EM to verify SGBD sample isolation is reinstated for 1A MDAFWP auto-start by verifying both of the following links inside breaker Q1R15BKRDF10 are closed: 3.3.1 Close link at Terminal Block TF, Terminal 3, for wire 95-7F. _____ EM3.3.2 Close link at Terminal Block TF, Terminal 4, for wire 95-8F. _____ EM3.4 Rack in 1B MDAFWP supply breaker Q1R15BKRDG10. _____ 3.5 Reinstate the 1A MDAFWP supply auto-start on low-low SG level as follows: 3.5.1In SOLID STATE PROTECTION SYSTEM TRAIN A LOGIC CABINET, place the INPUT ERROR INHIBIT switch to INHIBIT. _____ 3.5.2In SOLID STATE PROTECTION SYSTEM TRAIN A OUTPUT CABINET on the OUTPUT RELAY TEST PANEL, place the MODE SELECTOR switch to TEST. _____ 3.5.3In SOLID STATE PROTECTION SYSTEM TRAIN A OUTPUT CABINET (rear section), have I&C land the black field lead from terminal #1 or #2 on terminal block TB 632 that was lifted in Appendix3, step 3.3.(Ref. D-177186/1, D-177357). _____ I&C3.5.4In SOLID STATE PROTECTION SYSTEM TRAIN A OUTPUT CABINET on the OUTPUT RELAY TEST PANEL, place the MODE SELECTOR switch to OPERATE ANDverify that the OPERATE lamp is on. _____ 3.5.5In SOLID STATE PROTECTION SYSTEM TRAIN A LOGIC CABINET, place the INPUT ERROR INHIBIT switch to NORMAL. _____ 3.5.6 Close ANDlock SOLID STATE PROTECTION SYSTEM TRAIN A LOGIC CABINET and OUTPUT CABINET doors. _____ 3.6 Verify 1A MDAFWP supply breaker Q1R15BKRDF10 racked in. _____

UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 75 of 81 APPENDIX 5 LOSS OF RCS FLOW WITH SOLID PLANT CONDITIONS Performed by: DateReviewed by: DateThis Appendix consists of 6 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 76 of 81APPENDIX 5 LOSS OF RCS FLOW WITH SOLID PLANT CONDITIONS (Page 1 of 6) 1.0 Purpose To provide guidance for a loss of RCS flow with solid plant conditions. 2.0 Initial Conditions 2.1The version of this appendix has been verified to be the current version. (OR 1-98-498)_____2.2The version of this appendix has been verified to be the correct unit for the task. (OR 1-98-498) _____ 2.3Plant is in Mode 5 with solid plant conditions and RCPs are tripped with seal injection temperature less than RCS temperature. _____ 3.0 Instructions CAUTIONIf RCS flow is lost for greater than five minutes with seal injection flow while the plant is solid, the starting of a reactor coolant pump could cause a pressure excursion. 3.1IF the following conditions are met: No RCPs are running. Seal injection temperature is less than RCS temperature. FNP-1-SOP-1.1, Reactor Coolant System, requirements are satisfied. A reactor coolant pump has been idle for 30 minutes. THENstart a RCP which has been idle for 30 minutes, within 5 minutes of the loss of flow condition per FNP-1-UOP-1.1, Steps 5.2.1 through 5.2.15. _____ 3.2IF plant startup is in progress with the following AND RCS chemistry is within specifications for RCS temperature greater than 180F, THEN performSection 3.3, IF NOT, perform Section 3.4 and 3.5. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 77 of 81APPENDIX 5 LOSS OF RCS FLOW WITH SOLID PLANT CONDITIONS (Page 2 of 6) CAUTIONDo not perform this section if RCS temperature is less than 130F.3.3 Establish a pressurizer steam space as follows: 3.3.1 Adjust charging and letdown flow as required to establish RCS pressure at 325-375 psig with LP LTDN PRESS PK 145 in AUTO. _____ 3.3.2 Energize all pressurizer heaters. 1A PRZR HTR GROUP BACKUP ON _____ 1B PRZR HTR GROUP BACKUP ON _____ 1C PRZR HTR GROUP VARIABLE ON _____ 1D PRZR HTR GROUP BACKUP ON _____ 1E PRZR HTR GROUP BACKUP ON _____ 3.3.3 Maintain RCS pressure 325-375 psig. _____ 3.3.4WHEN pressurizer temperature increases to the saturation temperature for 375 psig (approximately 442F) as indicated by increasing RCS pressure or letdown flow, THENestablish a steam space in the pressurizer as follows: 3.3.4.1Decrease charging flow to minimum. _____ 3.3.4.2Adjust SEAL WTR INJECTION HIK 186 as required to maintain 6-13 gpm seal flow to each RCP. _____ 3.3.4.3Operate pressurizer heaters as necessary to maintain RCS pressure 325-375 psig. 1A PRZR HTR GROUP BACKUP ON-AUTO OFF _____ 1B PRZR HTR GROUP BACKUP ON-AUTO OFF _____ 1C PRZR HTR GROUP VARIABLE ON-AUTO OFF _____ 1D PRZR HTR GROUP BACKUP ON-AUTO OFF _____ 1E PRZR HTR GROUP BACKUP ON-AUTO OFF _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 78 of 81APPENDIX 5 LOSS OF RCS FLOW WITH SOLID PLANT CONDITIONS (Page 3 of 6) 3.3.4.4Adjust LP LTDN PRESS PK 145 to maintain approximately 120 gpm. _____ 3.3.4.5 WHEN VCT level increases to 81%, THENverify VCT HI LVL DIVERT VLV Q1E21LCV115A in the fully diverted position. _____ 3.3.4.6 IF desired, THEN place excess letdown in operation to expedite formation of a steam space in the pressurizer per FNP-1-SOP-2.7, Chemical and Volume Control System Excess Letdown. _____ NOTEThe preferred method for maintaining pressurizer level in the step below is with CHG FLOW FK-122 in AUTO. However, if auto control is not available or desired, then charging flow may be controlled in manual using the MA station, or using FCV-122 bypass control per FNP-1-SOP-2.1, Section 4.6. 3.3.4.7 WHEN pressurizer level reaches 21%, THEN place CHG FLOW FK 122 in AUTO. _____ 3.3.4.8Verify pressurizer level is maintained at approximately 21%. _____ 3.3.4.9Remove excess letdown from operation if in service per FNP-1-SOP-2.7, Chemical and Volume Control System Excess Letdown. _____ 3.3.4.10Adjust LP LTDN PRESS PK 145 to establish the desired letdown flow._____3.3.5IF RCS temperature is greater than 160F, THENstart at least one RCP per FNP-1-SOP-1.1, Reactor Coolant System. _____ 3.3.6Startup of unit from cold shutdown to hot standby may be performedper FNP-1-UOP-1.1, Startup of Unit from Cold Shutdown to Hot Standby._____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 79 of 81APPENDIX 5 LOSS OF RCS FLOW WITH SOLID PLANT CONDITIONS (Page 4 of 6) NOTEThe provisions of FNP-1-UOP-1.1, Step 1.2, should be used to N/A conditions and steps already completed by this procedure. 3.4 Establish RCS flow with solid plant conditions as follows: CAUTIONRCS and pressurizer temperature must be less than 225F.3.4.1 Adjust charging and letdown flow as necessary to reduce RCS pressure to 50-100 psig with LP LTDN PRESS PK 145 in AUTO. _____ 3.4.2WHEN RCS pressure is less than 100 psig, THENclose RCP SEAL LEAKOFF valves: Q1E21HV8141A. _____ Q1E21HV8141B _____ Q1E21HV8141C _____ 3.4.3 Maintain seal injection flow. _____ 3.4.4 Place the standby train of CCW in service per FNP-1-SOP-23.0, Component Cooling Water System. _____ 3.4.5 Maintain low press letdown aligned to the train that was initially inservice while performing the next steps. _____ 3.4.6 Place the standby train of RHR in service per FNP-1-SOP-7.0, Residual Heat Removal System. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 80 of 81APPENDIX 5 LOSS OF RCS FLOW WITH SOLID PLANT CONDITIONS (Page 5 of 6) 3.4.7 Secure CCW to the RHR Hx that low pressure letdown is aligned, to increase VCT by temperature to greater than 80F.3.4.7.1 IF A train is aligned, THENclose CCW TO 1A RHR HX Q1P17MOV3185A _____ 3.4.7.2 IF B train is aligned, THEN close CCW TO 1B RHR HX Q1P17MOV3185B _____ 3.4.7.3 IF additional heat input is required to raise VCT temperature, THENclose the following manual valves as required: Q1P17V034--SEAL WTR HX CCW INLET ISO _____ Q1P17V031--LTDN HX CCW INLET ISO _____ 3.4.8 Adjust the standby train of RHR as necessary to maintain RCS temperature less than 100F. _____ 3.4.9 Maintain RCS pressure at 50-100 psig for at least two hours to allow injection water to thermalize with the RCS loop temperature. _____ NOTEThe number of operating RCPs is limited to one at RCS temperatures less than 110F, with the exception that a second pump may be started for the purpose of maintaining continuous flow while taking the operating pump out of service (Ref. TS 3.4.7 and 3.4.8). 3.4.10 Start at least one RCP per FNP-1-UOP-1.1 step 5.2.1 through 5.2.15. _____ 3.5Returning system to normal: 3.5.1 Establish CCW to the RHR HX that Lo Press Letdown is aligned to by opening: 3.5.1.1 IF A train is aligned, THENopen CCW TO 1A RHR HX Q1P17MOV3185A _____ 3.5.1.2 IF B train is aligned, THEN open CCW TO 1B RHR HX Q1P17MOV3185B _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-UOP-1.1 103.0 6/3/2015 11:34:15 STARTUP OF UNIT FROM COLD SHUTDOWN TO HOT STANDBY Page Number 81 of 81APPENDIX 5 LOSS OF RCS FLOW WITH SOLID PLANT CONDITIONS (Page 6 of 6) 3.5.2IF CCW to the letdown and seal water heat exchangers manual valves were closed, THEN open the following valves. Q1P17V034--SEAL WTR HX CCW INLET ISO _____ Q1P17V031--LTDN HX CCW INLET ISO _____ 3.5.3IF CCW to the letdown and seal water heat exchangers manual valves was secured, THEN open these valves. _____ 3.5.4IF desired, THEN secure the standby train of RHR per FNP-1-SOP-7.0, Residual Heat Removal System. _____ 3.5.5IF desired, THEN secure the standby train of CCW per FNP-1-SOP-23.0, Component Cooling Water System. _____ Printed 12/22/2014 at 08:52:00 FARLEY Unit 1 SAFETY RELATEDFNP-1-SOP-1.1Reactor Coolant System VERSION 49.1 PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous ALL Reference NONE Information NONE Approval: David L Reed 12/08/2014 Approved By Date Effective Date: OPERATIONS Responsible Department Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 2 of 37 Printed 12/22/2014 at 08:52:00 VERSION SUMMARY PVR 49.0 DESCRIPTION Converted to new fleet template, deleted P&L that was for cycle 25 only, CR 787558, Added records section PVR 49.1 DESCRIPTION Updated to force repagination Corrected Unit number P&L 25.c, 4th bullet, Att 3 Step 34 Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 3 of 37 Printed 12/22/2014 at 08:52:00 TABLE OF CONTENTS SECTION ..........................................................................................................................................PAGE1.0 PURPOSE ....................................................................................................................................42.0 INITIAL CONDITIONS ..................................................................................................................43.0 PRECAUTION AND LIMITATIONS ..............................................................................................54.0 INSTRUCTIONS .........................................................................................................................114.1 1A RCP STARTUP. ....................................................................................................................114.2 1B RCP STARTUP. ....................................................................................................................134.3 1C RCP STARTUP. ....................................................................................................................164.4 1A RCP SHUTDOWN .................................................................................................................184.5 1B RCP SHUTDOWN. ................................................................................................................184.6 1C RCP SHUTDOWN. ...............................................................................................................194.7 PRZR HEATER OPERATION. ...................................................................................................205.0 RECORDS ..................................................................................................................................2

16.0 REFERENCES

...........................................................................................................................217.0 COMMITMENTS, OPEN ITEMS, AND ACTION ITEMS ............................................................22FIGURE1 No. 1 Seal Normal Operating Range ..........................................................................................23ATTACHMENT 1 OPERATION OF AN UNCOUPLED RCP MOTOR ....................................................................242 ROTATING A RCP BY HAND ....................................................................................................30 3 PRESSURIZER HEATER OPERATION TO SUPPORT FNP-1-STP-938, PRESSURIZER HEATER CAPACITY CHECK ..........................................................................32 Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 4 of 37 Printed 12/22/2014 at 08:52:00 1.0 PURPOSEThis procedure provides Initial Conditions, Precautions, and instructions for the operation of the Reactor Coolant System. 2.0 INITIAL CONDITIONS 1. The Reactor Coolant System (RCS) has been filled, vented per FNP-1-SOP-1.3, Reactor Coolant System Filling And Venting - Vacuum Method, or FNP-1-SOP-1.11, Reactor Coolant System Filling And Venting - Dynamic Method, and is aligned per system check list FNP-1-SOP-1.1A with exceptions noted. Pressurizer spray valves Q1B31PCV444C and Q1B31PCV444D may be in manual or automatic control. ........................................... 2. The electrical distribution system is energized and aligned for normal operation per FNP-1-SOP-36.0, Plant Electrical Distribution Line-Up, with exceptions noted. ........................................................................................................................... 3. The compressed air system is aligned and in service per FNP-1-SOP-31.0, Compressed Air System. ............................................................................................. 4. The Service Water System (SW) is aligned and in service for normal operations per FNP-1-SOP-24.0, Service Water System. ........................................... 5. Component Cooling Water (CCW) is supplying Reactor Coolant Pumps per FNP-1-SOP-23.0, Component Cooling Water System.................................................6. The reactor coolant pressure relief system and Reactor Coolant Drain Tank (RCDT) are available to receive discharge from the RCS per FNP-1-SOP-1.2, Reactor Coolant Pressure Relief System, and FNP-1-SOP-50.0, Liquid Waste Processing System. ..................................................................................................... 7. The Pressurizer (PRZR) heater distribution panels are aligned per system check list FNP-1-SOP-1.1B, with exceptions noted. .................................................... 8. CVCS charging (CHG) and letdown (LTDN) flows have been established and seal water is being supplied to RCP's in accordance with FNP-1-SOP-2.1, Chemical and Volume Control System Plant Startup And Operation...........................

Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 5 of 37 Printed 12/22/2014 at 08:52:00 3.0 PRECAUTION AND LIMITATIONS 1. The RCS (except the pressurizer) shall be limited to a maximum heatup of 100°F in any one hour period and a maximum cooldown of 100°F in any one hour period at all times. ................................................................................................ 2. The pressurizer temperature shall be limited to a maximum cooldown of 200°Fin any one hour period, a maximum heatup of 100°F in any one hour period, and a maximum spray water temperature differential of 320°F at all times. ................ 3. A Residual Heat Removal (RHR) pump or a RCP must be operating to provide reactor coolant recirculation and thorough mixing during boron concentration changes, chemical addition or any time the RCS temperature exceeds 140°F.a. Verify the desired boron concentration in the RCS and PRZR has been achieved prior to securing the only running RCP. (SOER 94-02) .................... b. At least one RCP must be in operation prior to performing any RCS dilution or boration except as noted in Precaution and Limitation 3.c below. (SOER 94-02) ....................................................................................... c. IF no RCP is in operation and at least one RHR pump is on service providing 3000 gpm flow, THEN chemicals may be added to the RCS provided an evaluation of the effects of a small volume dilution to the RCS with potentially inadequate mixing has been performed and with Shift Supervisor concurrence. The evaluation should consider shutdown margin for present conditions and the affected volume of RCS. Boron samples should be obtained and analyzed to ensure adequate shutdown margin is maintained. ........................................................................ 4. RCS pressure and temperature are limited to maximum of 375 psig and 350°Frespectively when the RHR system is valved into the RCS. ........................................ 5. RCP's shall not be operated continuously until the RCS has been filled and vented in accordance with FNP-1-SOP-1.3, Reactor Coolant System Filling And Venting - Vacuum Method, or FNP-1-SOP-1.11, Reactor Coolant System Filling And Venting - Dynamic Method. ........................................................................ 6. DO NOT attempt to start a RCP unless its oil lift pump has been delivering oil to the upper thrust shoes for at least two minutes. Observe the oil lift pumps indicating lights to verify correct oil pump motor operation and oil pressure. The oil lift pumps should run at least 1 minute after the RCP's are started. An interlock will prevent starting a RCP until 600 psig oil pressure is established. ........... 7. Shift Supervisor's approval must be obtained prior to removing any seal wires or changing the position of any throttle valves. ............................................................ 8. RCP seal water injection flow of 6 gpm or CCW to the RCP thermal barrier must be continuously supplied when RCS temperature exceeds 150°F. .................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 6 of 37 3.0 PRECAUTION AND LIMITATIONS (continued) Printed 12/22/2014 at 08:52:00 9. Maintain RCP CCW and seal injection water supply temperature less than 105°F and 130°F respectively. .................................................................................... 10. IF CCW flow to the RCP motor bearing oil coolers is lost, THEN pump operation may be continued until the motor upper or lower bearing temperature reaches 195°F (approximately 2 minutes after cooling water flow stops). .................. 11. For RCP operations, a pressure differential of 210 psid must be maintained across RCP No. 1 seals. .............................................................................................. 12. The following precautions apply in the case of a RCP #1 seal failure. DO NOT restart an RCP with an indicated No. 1 seal failure. ........................... Refer To FNP-1-ARP-1.4, Main Control Board Annunciator Panel "D", for guidance if No. 1 seal leakoff flow is abnormally low (Ann. DC1) or abnormally high (Ann. DC2). ............................................................................. 13. The No. 1 seal bypass valve should NOT be opened unless either the pump bearing temperature (seal inlet temperature) or the No. 1 seal leakoff temperature approaches its alarm level. The No. 1 seal bypass valve should then be opened only if all of the following conditions are met: Reactor coolant system pressure is greater than l00 psig AND less than l000 psig. ........................................................................................................... No. 1 seal leakoff valve is open. ........................................................................ No. 1 seal leakoff flowrate is less than one gpm. .............................................. Seal injection water flow rate to each pump is greater than 6 gpm. .................. 14. For RCP operations, the required minimum back pressure of 15 psig on the RCP No. 1 seals is ensured by maintaining a pressure of at least 18 psig in the VCT. ............................................................................................................................. 15. An oil lift pump may need to operate for several minutes (more than 5) before enough pressure is developed to actuate the pressure switch that will illuminate the white light. The length of run time may vary due to oil temperature, secured time and pressure switch sensitivities. (AI12011201221) ........ 16. Following a change of boron concentration of 50 ppm or greater in the RCS, the PRZR spray must be operated to equalize the concentration throughout the system. Automatic operation of the spray should be initiated by manual operation of the PRZR heaters when there is a bubble in the PRZR. .......................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 7 of 37 3.0 PRECAUTION AND LIMITATIONS (continued) Printed 12/22/2014 at 08:52:00 17. The following precautions apply to the operation of the RCP's: IF all RCP's have been idle for more than 5 minutes with seal water flow established during solid plant operations, THEN Refer To FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby, Attachment 5, prior to starting an RCP. ............................................................. At least one RCP should be running when the RCS temperature is greater than 160°F. ........................................................................................... The number of operating RCPs is limited to one at RCS temperatures less than 110°F, with the exception that a second pump may be started for the purpose of maintaining continuous flow while taking the operating pump out of service. .......................................................................... Verify open 1C and 1A RCS LOOP TO 1A AND 1B RHR PUMP valves Q1E11MOV8701A and B and Q1E11MOV¬8702A and B prior to starting an RCP during solid plant operation. .................................................... IF one or more of the RCS cold leg temperatures is less than 275°F, THEN a RCP shall not be started unless the PRZR water volume is < 24% wide range cold PRZR level indication OR the secondary water temperature of each steam generator is < 50°F above each of the RCS cold leg temperatures. ............................................................ 18. The RCP's are not designed for "start stop" operations. Too frequent starting may damage the motor windings. To prevent such damage, the following maximum starting duty should be observed: Only one RCP is to be started at any one time. ................................................. After any running period OR after any attempted start that fails, allow a minimum 30 minute idle period before attempting a restart. .............................. DO NOT exceed three starts or attempted starts in a two hour period. IFthree starts OR attempted starts have been made within a two hour period, THEN allow a 60 minute idle period before attempting an additional start. .................................................................................................. 19. Continuous spray line flow is provided by normal leakage past the seat of the spray valves. This minimum flow will prevent the spray and surge lines from cooling below operating temperature and will also aid in maintaining uniform water chemistry and temperature conditions within the PRZR..................................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 8 of 37 3.0 PRECAUTION AND LIMITATIONS (continued) Printed 12/22/2014 at 08:52:00 20. To minimize temperature transients to the PRZR during plant heatup or cooldown operations, the following precautions should be observed when PRZR spray flow is initiated: IF the temperature difference between the PRZR and the spray fluid is greater than 320°F, THEN spray should not be used. ...................................... Auxiliary spray should only be used during plant cooldown. Auxiliary spray flow should be initiated slowly by opening RCS PRZR AUX SPR Q1E21HV8145 (Q1E21V245) and gradually increasing CHG line flow. ............ 21. IF CCW will be secured to the RCP motor oil coolers for longer than 2 months, THEN contact Maintenance to have the oil coolers drained and dried per RCP Technical Manual Technical Bulletin 81-02. ......................................... 22. IF an RCP is to be secured for greater than one month, THEN its termination box strip heaters should be energized. ........................................................................ 23. Prior to starting a RCP, consideration should be given to raising the 230 kV bus voltage such that the emergency 4160 volt buses are approaching the 4200 volt limit to preclude spurious RCP breaker trip. (AI2010200391) ...................... 24. Guidance in this procedure has the potential to impact reactivity. Close coordination with the control room operators is required to ensure proper reactivity management per NMP-OS-001, Reactivity Management Program. (Al 2008203128) .......................................................................................................... 25. The following precautions apply to the RCP seals: a. It is critical that the alarms indicating loss of all seal cooling are heeded and the RCP(s) immediately tripped. There is no way to prevent a shutdown seal from actuating. The shaft must be stopped before the shutdown seal actuates, otherwise it will not seal properly. The greater the No. 1 seal leak off at the moment cooling is lost, the faster the RCP must be tripped to assure the shaft is stopped. A 5 gpm leaking No. 1 seal requires the RCP to be tripped within 2 minutes of losing CCW and seal injection. ..................................................................................................... b. For a motor trip that is performed as a response to a Loss of All Seal Cooling event, the oil lift MUST be OFF. Having the oil lift system on will delay the RCP shaft from coming to a complete stop. The SHIELD Shutdown Seal is designed to seal on a stationary shaft. Operating the oil lift system jeopardizes the protection the SHIELD would otherwise provide. .............................................................................................................. Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 9 of 37 3.0 PRECAUTION AND LIMITATIONS (continued) 25. (continued) Printed 12/22/2014 at 08:52:00 c. Refer to FNP-1-AOP-4.1, Abnormal Reactor Coolant Pump Seal Leakage, when any of the following conditions exist: Operator determination that a loss of all seal cooling to one or more RCPs has occurred. ....................................................................... Annunciator DC2, RCP #1 SEAL LKOF FLOW HI, is in alarm. Alarm setpoint is 5.0 GPM....................................................................... Annunciator DC1, RCP #1 SEAL LKOF LO, is in alarm. Alarm setpoint is 0.95 GPM. .............................................................................. Annunciators DA5, DB5, OR DC5; 1A(1B,1C) RCP #2 SEAL LKOF FLOW HI, is in alarm. Alarm setpoint is 0.75 GPM. ...................... ............................... d. IF a RCP's Lower Seal Water Bearing temperature reaches 225F, THEN that RCP must be shutdown immediately. .................................. e. If at any time the seal package reaches 250°F, it is likely the shutdown seal has actuated. If #1 leakoff temperature of 235ºF is reached, the RCP trouble-shooting guide must be referenced to determine if the shutdown seal has actuated. Westinghouse should be contacted for further guidance in determining the status of the shutdown seal. ...................... f. If 250ºF is exceeded, the shutdown seal must be replaced. If 250ºF is exceeded while the shaft was rotating, until it is replaced the operator is to assume the shutdown seal has actuated and that it cannot be relied upon in a loss of all seal cooling event. ............................................................. g. The shutdown seal is a thermally actuated device. Caution shall be taken if welding or machining near the seal housing with the seals still installed. Heat created by these operations may elevate the temperature of the shutdown seal to the point of actuation. A fire in the proximity of the seal housing may also result in the shutdown seal actuating. ........................................................................................................... h. It is unlikely that the inadvertent actuation of a shutdown seal on an operating RCP at NOT/NOP would result in a leak tight seal (immediate drop to 0 gpm leakoff followed by recovery to 1-1.5 gpm over 5-30 seconds). It is expected #1 seal leakoff flow will steadily decrease to below the alarm set point over a 10-30 minute period. Westinghouse should be contacted for further guidance in determining the status of the shutdown seal. ................................................................................................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 10 of 37 3.0 PRECAUTION AND LIMITATIONS (continued) 25. (continued) Printed 12/22/2014 at 08:52:00 i. Closure of the #1 seal leakoff line will impede the operator's ability to determine if the shutdown seal has actuated. Alternate means such as calculated flow into the RCDT must be used. .................................................... j. Isolating cooling to the seals (CCW and seal injection) too early during a plant shutdown could cause the SDS to actuate. Without cooling to the RCP seal package, the heat stored in the RCP can be conducted through its housing to the SDS. ......................................................................... k. Do not restart an RCP with an indicated No. 1 seal failure. ............................... l. Prior to restoring pump to operation after being secured due to high temperature limitations, the SDS must be evaluated. If the temperature exceeded 250°F it is likely the SDS actuated and must be replaced. ............... m. Maintain RCP CCW and seal injection water supply temperature less than 105F and 130F respectively....................................................................n. RCP seal water injection flow of 6 gpm or CCW to the RCP thermal barrier must be continuously supplied when RCS temperature exceeds 150F. ................................................................................................................ o. After any significant change in charging flow, the RCP seal injection flow should be checked and adjusted, as necessary, to maintain injection flow rates between 6 gpm and 13 gpm to each RCP. ....................................... p. For RCP operations, the required minimum back pressure of 15 psig on the RCP No. 1 seals is ensured by maintaining a pressure of at least 18 psig in the VCT. ............................................................................................ q. For RCP operations, a pressure differential of 210 psid must be maintained across RCP No. 1 seals. ................................................................. Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 11 of 37 Printed 12/22/2014 at 08:52:00 4.0 INSTRUCTIONS NOTES Initial startup of a RCP will be performed in accordance with FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby, OR FNP-1-SOP-1.3, Reactor Coolant System Filling And Venting. FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby, covers the initial startup of a RCP with the reactor coolant system in solid water operation and ensures all pumps are running prior to entry into mode 4. Starting of additional pumps may be performed by this procedure following the start of the first RCP. ............................................................................................................................................ Initial startup of a RCP may also be performed during Plant Shutdown per this procedure (FNP-1-SOP-1.1) when sent here from FNP-1-UOP-2.2, Shutdown Of Unit From Hot Standby To Cold Shutdown, Attachment 5. FNP-1-UOP-2.2, Attachment 5 references this procedure (FNP-1-SOP-1.1) to start a RCP during shutdown, either solid plant or with a bubble in the pressurizer. ............................................................................. CAUTION Prior to starting a RCP, consideration should be given to raising the 230 kV bus voltage such that the emergency 4160 volt buses are approaching the 4200 volt limit to preclude spurious RCP breaker trip. (AI2010200391) ...................................................................................... 4.1 1A RCP STARTUP. 1.Verify RCP seal flow established per FNP-1-SOP-2.1, Chemical And Volume Control System Plant Startup And Operation. .............................................................. 2.Verify VCT pressure > 18 psig. ................................................................................... 3. IF RHR is aligned to the RCS, THEN verify RCS pressure is 325-375 psig. ............. 4. IF RHR is NOT aligned to the RCS, THEN verify RCS pressure 350 psig. ............. 5.Verify that the 1A RCP STANDPIPE LVL LO annunciator DA1 is clear......................6.Verify that the RCP THRM BARR CCW FLOW HI annunciator DD2 is clear. ............ 7.Verify that the CCW FLOW FROM RCP OIL CLRS LO annunciator DD3 is clear. ............................................................................................................................ 8.Verify that the RCP 1A BRG UPPER/LOWER OIL RES HI LVL annunciator HG1 is clear. ................................................................................................................ 9.Verify that the RCP 1A BRG UPPER/LOWER OIL RES LO LVL annunciator HH1 is clear. ................................................................................................................. 10. WHEN one or more of the RCS cold leg temperatures is less than 275°F, THEN record PRZR level and steam generator T as per FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby. .................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 12 of 37 4.1 1A RCP STARTUP. (continued) Printed 12/22/2014 at 08:52:00 NOTES The oil lift pump must be operated for at least 2 minutes prior to starting the RCP..................... An oil lift pump may need to operate for several minutes (more than 5) before enough pressure is developed to actuate the pressure switch that will illuminate the white light. The length of run time may vary due to oil temperature, secured time and pressure switch sensitivities. (AI12011201221) ......................................................................................... 11. IF evidence of a "cocked" #1 RCP seal exists, THEN with OPS Shift Manager approval,Proceed To Attachment 1, Starting the 1A RCP to Correct a Cocked #1 Seal Condition 12.Start the 1A RCP Oil Lift Pump. Adequate oil pressure is indicated by the white light coming ON. ................................................................................................. 13.Verify that the 1A RCP SEAL LEAKOFF valve Q1E21HV8141A is OPEN. ................ 14.Verify that 1A RCP No. 1 Seal Leakoff Flow rate is within the limits of Figure 1. ........ 15.Verify that the SEAL WTR INJ FLTR HI P annunciator DC4 is clear. ....................... 16.Verify that the RCP SEAL INJ FLOW LO annunciator DD1 is clear............................17.Verify that all RCP No. 1 Seal P's are greater than 210 psid. ................................... 18.Verify that the RCP #1 SEAL LO P annunciator DC3 is clear. .................................. 19.Verify that the Oil Lift Pump for RCP 1A has run for at least 2 minutes, and is producing adequate pressure (white light ON). ............................................................ 20.Start 1A RCP. Verify that all loop 1A flow instruments show an increasing flow rate. ..............................................................................................................................21.Verify that RCP 1A amperage decreases to a normal operating range of 900 amps cold and 700 amps hot. ............................................................................... 22.Verify that the 1A RCS LOOP FLOW LO annunciator EF1 is clear. ........................... CAUTIONS The RCP seal water bypass valve Q1E21HV8142, should only be opened IF No. 1 seal leakoff flow rate is < 1 gpm AND RCS pressure is < 1000 psig. During RCS heatup/pressurization or cooldown/depressurization, the seal water bypass valve, Q1E21HV8142, may be left closed unless pump bearing temperature or No. 1 seal outlet temperature approach their alarm levels. .......................................................................... During normal operation, the seal water bypass valve should remain closed. ........................... 23. After at least 1 minute of 1A RCP operation, stop the Oil Lift Pump. .......................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 13 of 37 4.1 1A RCP STARTUP. (continued) Printed 12/22/2014 at 08:52:00 NOTE # 1 Seal Injection flow should be maintained at ~ 8 gpm to each RCP. ............................................. 24.Observe RCP operating parameters very closely during the initial several minutes after starting. Special attention should be given to indications relating to pump seal performance. .......................................................................................... NOTE If additional RCP's are to be started, performance of the following step may be delayed until all RCP's are running. This is due to ALARA concerns for entering containment. ............................ 25.Open BKR 11, 1A RCP termination box strip heater, in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT) to de-energize the strip heater. ............................. NOTES Initial startup of a RCP will be performed in accordance with FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby, OR FNP-1-SOP-1.3, Reactor Coolant System Filling And Venting. FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby, covers the initial startup of a RCP with the reactor coolant system in solid water operation and ensures all pumps are running prior to entry into mode 4. Starting of additional pumps may be performed by this procedure following the start of the first RCP. ............................................................................................................................................ Initial startup of a RCP may also be performed during Plant Shutdown per this procedure (FNP-1-SOP-1.1) when sent here from FNP-1-UOP-2.2, Shutdown Of Unit From Hot Standby To Cold Shutdown, Attachment 5. FNP-1-UOP-2.2, Attachment 5 references this procedure (FNP-1-SOP-1.1) to start a RCP during shutdown, either solid plant or with a bubble in the pressurizer. ............................................................................. CAUTION Prior to starting a RCP, consideration should be given to raising the 230 kV bus voltage such that the emergency 4160 volt buses are approaching the 4200 volt limit to preclude spurious RCP breaker trip. (AI2010200391) ...................................................................................... 4.2 1B RCP STARTUP. 1.Verify RCP seal flow established per FNP-1-SOP-2.1, Chemical And Volume Control System Plant Startup And Operation. .............................................................. 2.Verify VCT pressure > 18 psig. ................................................................................... 3. IF RHR is aligned to the RCS, THEN verify RCS pressure is 325-375 psig. ............. 4. IF RHR is NOT aligned to the RCS, THEN verify RCS pressure 350 psig. ............. 5.Verify that the 1B RCP STANDPIPE LVL LO annunciator DA2 is clear......................6.Verify that the RCP THRM BARR CCW FLOW HI annunciator DD2 is clear. ............ Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 14 of 37 4.2 1B RCP STARTUP. (continued) Printed 12/22/2014 at 08:52:00 7.Verify that the CCW FLOW FROM RCP OIL CLRS LO annunciator DD3 is clear. ............................................................................................................................ 8.Verify that the RCP 1B BRG UPPER/LOWER OIL RES HI LVL annunciator HG2 is clear. ................................................................................................................ 9.Verify that the RCP 1B BRG UPPER/LOWER OIL RES LO LVL annunciator HH2 is clear. ................................................................................................................. 10. WHEN one or more of the RCS cold leg temperatures is less than 275°F, THEN record Przr level and steam generator T as per FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby. .................... NOTES The oil lift pump must be operated for at least 2 minutes prior to starting the RCP..................... An oil lift pump may need to operate for several minutes (more than 5) before enough pressure is developed to actuate the pressure switch that will illuminate the white light. The length of run time may vary due to oil temperature, secured time and pressure switch sensitivities. (AI12011201221) ......................................................................................... 11.Start the 1B RCP Oil Lift Pump. Adequate oil pressure is indicated by the white light coming ON. ................................................................................................. 12.Verify that the 1B RCP SEAL LEAKOFF valve Q1E21HV8141B is OPEN. ................ 13.Verify that 1B RCP No. 1 Seal Leakoff Flow rate is within the limits of Figure 1. ........ 14.Verify that the SEAL WTR INJ FLTR HI P annunciator DC4 is clear. ....................... 15.Verify that the RCP SEAL INJ FLOW LO annunciator DD1 is clear............................16.Verify that all RCP No. 1 Seal P's are greater than 210 psid. ................................... 17.Verify that the RCP #1 SEAL LO P annunciator DC3 is clear. .................................. 18.Verify that the Oil Lift Pump for RCP 1B has run for at least 2 minutes, and is producing adequate pressure (white light ON). ............................................................ 19.Start 1B RCP. Verify that all loop 1B flow instruments show an increasing flow rate. ..............................................................................................................................20.Verify that RCP 1B amperage decreases to a normal operating range of 900 amps cold and 700 amps hot. ............................................................................... 21.Verify that the 1B RCS LOOP FLOW LO annunciator EF2 is clear. ........................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 15 of 37 4.2 1B RCP STARTUP. (continued) Printed 12/22/2014 at 08:52:00 CAUTIONS The RCP seal water bypass valve Q1E21HV8142, should only be opened IF No. 1 seal leakoff flow rate is < 1 gpm AND RCS pressure is < 1000 psig. During RCS heatup/pressurization or cooldown/depressurization, the seal water bypass valve, Q1E21HV8142, may be left closed unless pump bearing temperature or No. 1 seal outlet temperature approach their alarm levels. ......................................................................... During normal operation, the seal water bypass valve should remain closed. ............................ 22. After at least 1 minute of 1B RCP operation, stop the Oil Lift Pump. .......................... NOTE # 1 Seal Injection flow should be maintained at ~ 8 gpm to each RCP. ............................................. 23.Observe RCP operating parameters very closely during the initial several minutes after starting. Special attention should be given to indications relating to pump seal performance. .......................................................................................... NOTE If additional RCP's are to be started, performance of the following step may be delayed until all RCP's are running. This is due to ALARA concerns for entering containment. ............................ 24.Open BKR 9, 1B RCP termination box strip heater, in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT) to de-energize the strip heater. ............................. Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 16 of 37 Printed 12/22/2014 at 08:52:00 NOTES Initial startup of a RCP will be performed in accordance with FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby, OR FNP-1-SOP-1.3, Reactor Coolant System Filling And Venting. FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby, covers the initial startup of a RCP with the reactor coolant system in solid water operation and ensures all pumps are running prior to entry into mode 4. Starting of additional pumps may be performed by this procedure following the start of the first RCP. ............................................................................................................................................ Initial startup of a RCP may also be performed during Plant Shutdown per this procedure (FNP-1-SOP-1.1) when sent here from FNP-1-UOP-2.2, Shutdown Of Unit From Hot Standby To Cold Shutdown, Attachment 5. FNP-1-UOP-2.2, Attachment 5 references this procedure (FNP-1-SOP-1.1) to start a RCP during shutdown, either solid plant or with a bubble in the pressurizer. ............................................................................. CAUTION Prior to starting a RCP, consideration should be given to raising the 230 kV bus voltage such that the emergency 4160 volt buses are approaching the 4200 volt limit to preclude spurious RCP breaker trip. (AI2010200391) ...................................................................................... 4.3 1C RCP STARTUP. 1.Verify RCP seal flow established per FNP-1-SOP-2.1, Chemical And Volume Control System Plant Startup And Operation. .............................................................. 2.Verify VCT pressure > 18 psig. ................................................................................... 3. IF RHR is aligned to the RCS, THEN verify RCS pressure is 325-375 psig. ............. 4. IF RHR is NOT aligned to the RCS, THEN verify RCS pressure 350 psig. ............. 5.Verify that the 1C RCP STANDPIPE LVL LO annunciator DA3 is clear. .................... 6.Verify that the RCP THRM BARR CCW FLOW HI annunciator DD2 is clear. ............ 7.Verify that the CCW FLOW FROM RCP OIL CLRS LO annunciator DD3 is clear. ............................................................................................................................ 8.Verify that the RCP 1C BRG UPPER/LOWER OIL RES HI LVL annunciator HG3 is clear. ................................................................................................................ 9.Verify that the RCP 1C BRG UPPER/LOWER OIL RES LO LVL annunciator HH3 is clear. ................................................................................................................. 10. WHEN one or more of the RCS cold leg temperatures is less than 275°F, THEN record Przr level and steam generator T as per FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby. .................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 17 of 37 4.3 1C RCP STARTUP. (continued) Printed 12/22/2014 at 08:52:00 NOTES The oil lift pump must be operated for at least 2 minutes prior to starting the RCP..................... An oil lift pump may need to operate for several minutes (more than 5) before enough pressure is developed to actuate the pressure switch that will illuminate the white light. The length of run time may vary due to oil temperature, secured time and pressure switch sensitivities. (AI12011201221) .......................................................................................... 11.Start the 1C RCP Oil Lift Pump. Adequate oil pressure is indicated by the white light coming ON. ................................................................................................. 12.Verify that the 1C RCP SEAL LEAKOFF valve Q1E21HV8141C is OPEN.................13.Verify that 1C RCP No. 1 Seal Leakoff Flow rate is within the limits of Figure 1. ....................................................................................................................... 14.Verify that the SEAL WTR INJ FLTR HI P annunciator DC4 is clear. ....................... 15.Verify that the RCP SEAL INJ FLOW LO annunciator DD1 is clear............................16.Verify that all RCP No. 1 Seal P's are greater than 210 psid. ................................... 17.Verify that the RCP #1 SEAL LO P annunciator DC3 is clear. .................................. 18.Verify that the Oil Lift Pump for RCP 1C has run for at least two minutes, and is producing adequate pressure (white light ON). ........................................................ 19.Start 1C RCP. Verify that all loop 1C flow instruments show an increasing flow rate. ..............................................................................................................................20.Verify that RCP 1C amperage decreases to a normal operating range of 900 amps cold and 700 amps hot. ............................................................................... 21.Verify that the 1C RCS LOOP FLOW LO annunciator EF3 is clear. ........................... CAUTIONS The RCP seal water bypass valve Q1E21HV8142, should only be opened IF No. 1 seal leakoff flow rate is < 1 gpm AND RCS pressure is < 1000 psig. During RCS heatup/pressurization or cooldown/depressurization, the seal water bypass valve, Q1E21HV8142, may be left closed unless pump bearing temperature or No. 1 seal outlet temperature approach their alarm levels. ......................................................................... During normal operation, the seal water bypass valve should remain closed. ........................... 22. After at least 1 minute of 1C RCP operation, stop the Oil Lift Pump. .......................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 18 of 37 4.3 1C RCP STARTUP. (continued) Printed 12/22/2014 at 08:52:00 NOTE # 1 Seal Injection flow should be maintained at ~ 8 gpm to each RCP. ............................................. 23.Observe RCP operating parameters very closely during the initial several minutes after starting. Special attention should be given to indications relating to pump seal performance. .......................................................................................... NOTE If additional RCP's are to be started, performance of the following step may be delayed until all RCP's are running. This is due to ALARA concerns for entering containment. ............................ 24.Open BKR 7, 1B RCP termination box strip heater, in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT) to de-energize the strip heater. ............................. 4.4 1A RCP SHUTDOWN NOTE RCP shutdown should be performed in conjunction with the applicable UOP. .................................. 1. IF plant is in Mode 3, THEN verify that the reactor trip breakers are open OR the rod drive MG sets are shutdown to prevent rod withdrawal prior to having more than one RCP secured (Refer To Technical Specification 3.4.5)........................2.Verify the desired boron concentration in the RCS and PRZR has been achieved prior to securing the only running RCP. (SOER 94-02) ................................ 3.Place 1A RCP control switch to TRIP position.............................................................4.Verify the 1A RCP motor current decreases to approximately 0 amps. ...................... NOTE If additional RCP's are to be stopped, performance of the following step may be delayed until all RCP's are stopped. This is due to ALARA concerns for entering containment. ................... 5. IF 1A RCP is to remain stopped for greater than 1 month, THEN closeBKR 11, 1A RCP termination box strip heater, in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT) to energize the strip heater. ............................................ 4.5 1B RCP SHUTDOWN. NOTE RCP shutdown should be performed in conjunction with the applicable UOP. .................................. 1. IF plant is in Mode 3, THEN verify that the reactor trip breakers are open OR the rod drive MG sets are shutdown to prevent rod withdrawal prior to having more than one RCP secured (Refer To Technical Specification 3.4.5)........................ Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 19 of 37 4.5 1B RCP SHUTDOWN. (continued) Printed 12/22/2014 at 08:52:00 2.Verify the desired boron concentration in the RCS and PRZR has been achieved prior to securing the only running RCP. (SOER 94-02) ................................ 3.Place 1B RCP control switch to TRIP position.............................................................4.Verify the 1B RCP motor current decreases to approximately 0 amps. ...................... NOTE If additional RCP's are to be stopped, performance of the following step may be delayed until all RCP's are stopped. This is due to ALARA concerns for entering containment.` .................. 5. IF 1B RCP is to remain stopped for greater than 1 month, THEN close BKR 9, 1B RCP termination box strip heater, in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT) to energize the strip heater ............................................. 4.6 1C RCP SHUTDOWN. NOTE RCP shutdown should be performed in conjunction with the applicable UOP. .................................. 1. IF plant is in Mode 3, THEN verify that the reactor trip breakers are open OR the rod drive MG sets are shutdown to prevent rod withdrawal prior to having more than one RCP secured (Refer To Technical Specification 3.4.5)........................2.Verify the desired boron concentration in the RCS and PRZR has been achieved prior to securing the only running RCP. (SOER 94-02) ................................ 3.Place 1C RCP control switch to TRIP position. ........................................................... 4.Verify the 1C RCP motor current decreases to approximately 0 amps. ...................... NOTE If additional RCP's are to be stopped, performance of the following step may be delayed until all RCP's are stopped. This is due to ALARA concerns for entering containment .................... 5. IF 1C RCP is to remain stopped for greater than 1 month, THEN close BKR 7, 1C RCP termination box strip heater, in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT) to energize the strip heater ............................................. Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 20 of 37 Printed 12/22/2014 at 08:52:00 4.7 PRZR HEATER OPERATION. NOTE PRZR heaters should be operated in conjunction with unit operating procedures. ............................ CAUTION Maintain RCS pressure in accordance with temperature/pressure limits of Technical Specification. ......................................................................................................................................1. Manual PRZR heater operation. a.Energize 1A (B, D, E) PRZR HTR GROUP BACKUP by placing the control switch to the ON position. ...................................................................... b.De-energize 1A (B, D, E) PRZR HTR GROUP BACKUP by placing the control switch to the OFF position. .................................................................... c. WHEN the need for manual control has passed, THEN place 1A (B, D, E) PRZR HTR GROUP BACKUP control switch to the AUTO position. ............ NOTE The following step will cause annunciator HD4 PZR HTR CONT TRBL. ........................................... d.De-energize 1C PRZR HTR GROUP VARIABLE by placing control switch to OFF (spring Return To neutral). ......................................................... 2. Normal automatic PRZR heater operation. a.Verify 1A, 1B, 1D and 1E PRZR HTR GROUP BACKUP control switches to the AUTO position. .......................................................................... b.Place 1A PRZR HTR GRP BLOCKING BYPASS SWITCH to BLOCK. ............ c.Place 1C PRZR HTR GROUP VARIABLE control switch to the ON position (Spring returns to neutral). ................................................................... d.Monitor PRZR variable heater operation, verify PRZR pressure maintained at approximately 2235 psig. ............................................................ Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 21 of 37 4.7 PRZR HEATER OPERATION. (continued) Printed 12/22/2014 at 08:52:00 3. Pressurizer Heater GRP 1A operation during LOSP or SI/LOSP. NOTE DCP 88-1-4773 modified the PRZR HTR GROUP 1A supply breaker EA-11 control circuit to block automatic heater energizing when offsite power is unavailable. The intent of the BLOCK/BYPASS switch is to regain automatic heater energizing of the 1A heaters after appropriate diesel generator load management actions have been completed. (Ref. D-177109) ..............................................................................................................................................a. WHEN required to energize PRZR HTR GROUP 1A during an LOSP, THEN place PRZR HTR GRP 1A BLOCKING BYPASS SW to BYPASS. ........................................................................................................... b. WHEN offsite power has been restored, THEN return the PRZR HTR GRP 1A BLOCKING BYPASS SW to BLOCK. .................................................. 5.0 RECORDSDocuments created using this procedure will become QA Records when completed unless otherwise stated. The procedures and documents are considered complete when issued in DMS. QA Record (X) Non-QA Record (X) Record Generated Retention Time R-Type X FNP-1-SOP-1.1 LP HH6.051

6.0 REFERENCES

1. PROCEDURES a. FNP-1-ARP-1.4, Main Control Board Annunciator Panel "D" b. FNP-1-SOP-1.1A, Reactor Coolant System c. FNP-1-SOP-1.1B, Reactor Coolant System d. FNP-1-SOP-1.2, Reactor Coolant Pressure Relief System e. FNP-1-SOP-1.3, Reactor Coolant System Filling And Venting f. FNP-1-SOP-1.11, Reactor Coolant System Filling And Venting - Dynamic Method g. FNP-1-SOP-2.1, Chemical and Volume Control System Plant Startup and Operation Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 22 of 37

6.0 REFERENCES

(continued)  1. (continued) Printed 12/22/2014 at 08:52:00 h. FNP-1-SOP-23.0, Component Cooling Water System i. FNP-1-SOP-24.0, Service Water System j. FNP-1-SOP-31.0, Compressed Air System k. FNP-1-SOP-36.0, Plant Electrical Distribution Line-Up l. FNP-1-SOP-50.0, Liquid Waste Processing System m. FNP-1-UOP-1.1, Startup Of Unit From Cold Shutdown To Hot Standby, Attachment 5 n. FNP-1-UOP-2.2, Shutdown Of Unit From Hot Standby To Cold Shutdown, Attachment 5 o. RCP Technical Manual Technical Bulletin 81-02 p. Technical Specification 3.4.5 2. DRAWINGS a. D-175037, sh. 1, 2, 3 Reactor Coolant System b. D-175039, sh. 1, 2 Chemical and Volume Control System

c. D-175002, sh. 2, Component Cooling Water d. D-175003, sh. 2, Service Water e. D-176152, 176157, Containment Penetration Schedule f. Technical Manual: U-258242, Controlled Leakage Seal Reactor Coolant Pump g. FSAR - Vol. VI - Section5.5h. PCN B88-1-5259 i. PCN B88-1-4773 7.0 COMMITMENTS, OPEN ITEMS, AND ACTION ITEMS a. SOER 94-02 b. AI2010200391 END OF PROCEDURE TEXT Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 23 of 37 Printed 12/22/2014 at 08:52:00 FIGURE 1 Page 1 of 1 No. 1 Seal Normal Operating Range Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 24 of 37 Printed 12/22/2014 at 08:52:00 ATTACHMENT 1 Page 1 of 6 OPERATION OF AN UNCOUPLED RCP MOTOR 1.0 PURPOSE This attachment provides Initial Conditions, Precautions, and Instructions for the operation of an uncoupled RCP motor 2.0 INITIAL CONDITIONS 1. The electrical distribution system is energized and aligned for normal operation per FNP-1-SOP-36.0, Plant Electrical Distribution Line-Up, with exceptions noted. ........................................................................................................................... 2. The compressed air system is aligned and in service per FNP-1-SOP-31.0, Compressed Air System, with exceptions noted. ......................................................... 3. The Service Water System (SW) is aligned and in service per FNP-1-SOP-24.0, Service Water System, with exceptions noted. ............................... 4. Component Cooling Water (CCW) is supplying Reactor Coolant Pump oil coolers per FNP-1-SOP-23.0, Component Cooling Water System, with exceptions noted. ......................................................................................................... 3.0 PRECAUTIONS AND LIMITATIONS 1. DO NOT attempt to start a RCP unless its oil lift pump has been delivering oil to the upper thrust shoes for at least 2 minutes. Observe the oil lift pumps indicating lights to verify correct oil pump motor operation and oil pressure. The oil lift pumps should run at least 1 minute after the RCPs are started. An interlock will prevent starting a RCP until 600 psig oil pressure is established. ........... 2. Maintain RCP CCW supply temperature < 105°F. ............................................................. 3. IF CCW flow to the RCP motor bearing oil coolers is lost, THEN pump operation may be continued until the motor upper or lower bearing temperature reaches 195F (approximately 2 minutes after cooling water flow stops). ...................

Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 25 of 37 UATTACHMENT 1 Page 2 of 6 OPERATION OF AN UNCOUPLED RCP MOTOR 3.0 PRECAUTIONS AND LIMITATIONS (continued) Printed 12/22/2014 at 08:52:00 4. The RCPs are not designed for "start-stop" operations. Too frequent starting may damage the motor windings. To prevent such damage, the following maximum starting duty should be observed: a. Only one RCP is to be started at any one time. b. After any running period OR after any attempted start that fails, allow a minimum 30 minute idle period before attempting a restart. c. DO NOT exceed three starts or attempted starts in a 2 hour period. IFthree starts OR attempted starts have been made within a two hour period, THEN allow a 60 minute idle period before attempting an additional start. 5. IF CCW will be secured to the RCP motor oil coolers for longer than 2 months, THEN contact Maintenance to have the oil coolers drained and dried per RCP Technical Manual Technical Bulletin 81-02. 6. IF an RCP is to be secured for greater than one month, THEN its termination box strip heaters should be energized. 4.0 INSTRUCTIONS 4.1 1A RCP Motor Startup (uncoupled) NOTE Annunciator DD3 may be in alarm due to CCW being isolated to another RCP. ............................... 1.Check that the CCW FLOW FROM RCP OIL CLRS LO annunciator DD3 is clear. ............................................................................................................................ 2. IF annunciator DD3 is NOT clear, THEN locally verify adequate CCW flow to the RCP motor to be run. ............................................................................................. 3.Check that the RCP 1A BRG UPPER/LOWER OIL RES HI LVL annunciator HG1 is clear. ................................................................................................................ 4.Check that the RCP 1A BRG UPPER/LOWER OIL RES LO LVL annunciator HH1 is clear. ................................................................................................................. 5. Locally verify that RCP 1A motor upper and lower oil reservoir level is in the normal operating band. ................................................................................................ Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 26 of 37 UATTACHMENT 1 Page 3 of 6 OPERATION OF AN UNCOUPLED RCP MOTOR 4.1 1A RCP Motor Startup (uncoupled) (continued) Printed 12/22/2014 at 08:52:00 NOTE The oil lift pump must be operated for at least 2 minutes prior to starting the RCP. .......................... 6.Start the 1A RCP Oil Lift Pump. Adequate oil pressure is indicated by the white light coming ON. ................................................................................................. 7.Verify that the Oil Lift Pump for RCP 1A has run for at least 2 minutes, and is producing adequate pressure (white light ON). ............................................................ 8.Start 1A RCP motor. .................................................................................................... 9.Verify that RCP 1A amperage decreases to approximately 200 amps. ...................... 10. After at least one minute of 1A RCP motor operation, stop its Oil Lift Pump. ............. 11.Observe RCP operating parameters very closely during the initial several minutes after starting and periodically throughout the run. The Plant Computer should be used for trending motor bearing temperatures. ........................................... NOTE Electrical Maintenance should be contacted for guidance on operation of termination box strip heaters based on length of desired uncoupled run, tagging in place, outage length, etc. Reference Attachment 1 Section 3.0 Step 6. ..................................................................................... 12. IF desired THEN verify 1A RCP termination box strip heaters de-energized by opening the appropriate breaker 11 in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT). ........................................................................................ 4.2 1B RCP Motor Startup (uncoupled) NOTE Annunciator DD3 may be in alarm due to CCW being isolated to another RCP. ............................... 1.Check that the CCW FLOW FROM RCP OIL CLRS LO annunciator DD3 is clear. ............................................................................................................................ 2. IF annunciator DD3 is NOT clear, THEN locally verify adequate CCW flow to the RCP motor to be run. ............................................................................................. 3.Check that the RCP 1BC BRG UPPER/LOWER OIL RES HI LVL annunciator HG2 is clear. ................................................................................................................ 4.Check that the RCP 1B BRG UPPER/LOWER OIL RES LO LVL annunciator HH2 is clear. ................................................................................................................. Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 27 of 37 UATTACHMENT 1 Page 4 of 6 OPERATION OF AN UNCOUPLED RCP MOTOR 4.2 1B RCP Motor Startup (uncoupled) (continued) Printed 12/22/2014 at 08:52:00 5. Locally verify that RCP 1B motor upper and lower oil reservoir level is in the normal operating band. ................................................................................................ NOTE The oil lift pump must be operated for at least 2 minutes prior to starting the RCP. .......................... 6.Start the 1B RCP Oil Lift Pump. Adequate oil pressure is indicated by the white light coming ON. ................................................................................................. 7.Verify that the Oil Lift Pump for RCP 1B has run for at least 2 minutes, and is producing adequate pressure (white light ON). ............................................................ 8.Start 1B RCP motor. .................................................................................................... 9.Verify that RCP 1B amperage decreases to approximately 200 amps. ...................... 10. After at least one minute of 1B RCP motor operation, stop its Oil Lift Pump. ............. 11.Observe RCP operating parameters very closely during the initial several minutes after starting and periodically throughout the run. The Plant Computer should be used for trending motor bearing temperatures. ........................................... NOTE Electrical Maintenance should be contacted for guidance on operation of termination box strip heaters based on length of desired uncoupled run, tagging in place, outage length, etc. Reference Attachment 1 Section 3.0 Step 6. ..................................................................................... 12. IF desired THEN verify 1B RCP termination box strip heaters de-energized by opening breaker 9 in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT). ......... 4.3 1C RCP Motor Startup (uncoupled) NOTE Annunciator DD3 may be in alarm due to CCW being isolated to another RCP. ............................... 1.Check that the CCW FLOW FROM RCP OIL CLRS LO annunciator DD3 is clear. ............................................................................................................................ 2. IF annunciator DD3 is NOT clear, THEN locally verify adequate CCW flow to the RCP motor to be run. ............................................................................................. 3.Check that the RCP 1C BRG UPPER/LOWER OIL RES HI LVL annunciator HG3 is clear. ................................................................................................................ Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 28 of 37 UATTACHMENT 1 Page 5 of 6 OPERATION OF AN UNCOUPLED RCP MOTOR 4.3 1C RCP Motor Startup (uncoupled) (continued) Printed 12/22/2014 at 08:52:00 4.Check that the RCP 1C BRG UPPER/LOWER OIL RES LO LVL annunciator HH3 is clear. ................................................................................................................. 5. Locally verify that RCP 1C motor upper and lower oil reservoir level is in the normal operating band. ................................................................................................ NOTE The oil lift pump must be operated for at least 2 minutes prior to starting the RCP. .......................... 6.Start the 1C RCP Oil Lift Pump. Adequate oil pressure is indicated by the white light coming ON. ................................................................................................. 7.Verify that the Oil Lift Pump for RCP 1C has run for at least 2 minutes, and is producing adequate pressure (white light ON). ............................................................ 8.Start 1C RCP motor. .................................................................................................... 9.Verify that RCP 1C amperage decreases to approximately 200 amps. ...................... 10. After at least one minute of 1C RCP motor operation, stop its Oil Lift Pump. ............. 11.Observe RCP operating parameters very closely during the initial several minutes after starting and periodically throughout the run. The Plant Computer should be used for trending motor bearing temperatures. ........................................... NOTE Electrical Maintenance should be contacted for guidance on operation of termination box strip heaters based on length of desired uncoupled run, tagging in place, outage length, etc. Reference Attachment 1 Section 3.0 Step 6. ..................................................................................... 12. IF desired THEN verify 1C RCP termination box strip heaters de-energized by opening breaker 7 in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT). ......... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 29 of 37 UATTACHMENT 1 Page 6 of 6 OPERATION OF AN UNCOUPLED RCP MOTOR Printed 12/22/2014 at 08:52:00 4.4 1A RCP Motor Shutdown (uncoupled) 1.Stop 1A RCP motor by placing control switch to TRIP position. ................................ 2.Verify the 1A RCP motor current decreases to approximately zero amps. ................. NOTE Electrical Maintenance should be contacted for guidance on operation of termination box strip heaters based on length of desired uncoupled run, tagging in place, outage length, etc. Reference Attachment 1 Section 3.0 Step 6. ..................................................................................... 3. IF desired, THEN verify 1A RCP termination box strip heaters energized for any RCP that is to remain stopped for greater than 1 month by closingbreaker 11 in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT). ...................... 4.5 1B RCP Motor Shutdown (uncoupled) a.Stop 1B RCP motor by placing control switch to TRIP position. ...................... 2.Verify the 1B RCP motor current decreases to approximately zero amps. ................. NOTE Electrical Maintenance should be contacted for guidance on operation of termination box strip heaters based on length of desired uncoupled run, tagging in place, outage length, etc. Reference Attachment 1 Section 3.0 Step 6. ..................................................................................... 3. IF desired, THEN verify 1B RCP termination box strip heaters energized for any RCP that is to remain stopped for greater than 1 month by closingbreaker 9 in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT). ........................ 4.6 1C RCP Motor Shutdown (uncoupled) 1.Stop 1C RCP motor by placing control switch to TRIP position. ................................ 2.Verify the 1C RCP motor current decreases to approximately zero amps. ................. NOTE Electrical Maintenance should be contacted for guidance on operation of termination box strip heaters based on length of desired uncoupled run, tagging in place, outage length, etc. Reference Attachment 1 Section 3.0 Step 6. ..................................................................................... 3. IF desired, THEN verify 1C RCP termination box strip heaters energized for any RCP that is to remain stopped for greater than 1 month by closingbreaker 7 in 120 V 1G receptacle panel N1T51L002B (129 ft CTMT). ........................ Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 30 of 37 Printed 12/22/2014 at 08:52:00 ATTACHMENT 2 Page 1 of 2 ROTATING A RCP BY HAND 1.0 PURPOSE This attachment provides Initial Conditions, Precautions, and Instructions for manually rotating a RCP. 2.0 INITIAL CONDITIONS 1. The RCP to be rotated by hand is tagged out. Indicate which RCP below. 1A RCP .............................................................................................................. 1B RCP .............................................................................................................. 1C RCP..............................................................................................................2. RCP seal flow established per FNP-1-SOP-2.1, Chemical And Volume Control System Plant Startup And Operation. 3.0 PRECAUTIONS AND LIMITATIONS 1. DO NOT use any type of mechanical advantage on the RCP to perform the rotation by hand. 2. The Anti-Reverse-Rotation Device will prevent rotation in the clockwise direction (when looking down on the RCP from above). Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 31 of 37 UATTACHMENT 2 Page 2 of 2 ROTATING A RCP BY HAND Printed 12/22/2014 at 08:52:00 4.0 INSTRUCTIONS 1.Start the RCP Oil Lift Pump for the RCP to be rotated by hand. Adequate oil pressure is indicated by the white light coming ON......................................................2. Locally check the RCP upper and lower oil reservoir levels adequate. ....................... NOTES Body placement must be carefully considered to avoid unnecessary back strain while rotating the RCP manually. It may be practical to use a push/pull method with both hands applied to coupling bolts on either side of the RCP shaft. ................................................ The RCP can only be rotated counterclockwise, when viewed from the motor. .......................... 3.Grasp the coupling bolts and rotate the RCP shaft. .................................................... 4.Rotate the RCP through several rotations. .................................................................. 5.Report to the control room any deficiencies noted. ..................................................... a. Have completion recorded in the Control Room Log. ...................................... 6.Secure the RCP Oil Lift Pump for the RCP rotated by hand. ...................................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 32 of 37 Printed 12/22/2014 at 08:52:00 ATTACHMENT 3 Page 1 of 6 PRESSURIZER HEATER OPERATION TO SUPPORT FNP-1-STP-938, PRESSURIZER HEATER CAPACITY CHECK 1.0 PURPOSE This attachment provides a methodology to support EM in the performance of obtaining necessary data to verify the PZR heater groups can maintain the required heating capacity. Sequence of operation of heater groups allows EM to obtain all data on Rad-side before going to Non-rad side of Auxiliary Building. 2.0 INITIAL CONDITIONS 1. Pressurizer pressure control is in automatic. (Spray valves and heaters). .................. 2. Cycling (Proportional) Heaters are the only heater group energized. .......................... 3. The plant is stable. ....................................................................................................... 4. The IPC is available and operable. .............................................................................. 3.0 PRECAUTIONS AND LIMITATIONS 1. All Precautions and Limitations of Main Body of SOP apply. ...................................... Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 33 of 37 UATTACHMENT 3 Page 2 of 6 PRESSURIZER HEATER OPERATION TO SUPPORT FNP-1-STP-938, PRESSURIZER HEATER CAPACITY CHECK Printed 12/22/2014 at 08:52:00 4.0 INSTRUCTIONSNOTE Reference is listed in Table 1 for PK-444A Controller Demand Functions. ........................................ Table 1 PK-444A ControllerDemand Function70.0% Backup Heaters ON 67.5% Backup Heaters OFF 65.0% Proportional heaters Full ON 57.5% Reference Pressure (2235 psig) 50.0% Proportional heaters Full OFF 45.0% Spray Valves Full Closed 20.0% Spray Valves Full Open 17.5% PORV 444B Closed 7.5% PORV 444B Open 1.Establish a trend on the IPC of PZR pressure (suggest PC0482). ........................ ______2.Establish a band for pressure control. ________ psig to ________ psig. 3.Record the demand indicated on the following: PK-444A ___________ PK-444C___________ PK-444D___________ 4.Recordthe steady state RCS pressure ______________________ psig.5.Place PK-444A in MANUAL. ................................................................................... ______6.Raise demand on PK-444A to a value between 65-67.0%. ..................................... ______NOTE Only one spray valve will be utilized to control PZR pressure. ........................................................... 7.Place one of the Spray valves in MANUAL. Indicate which valve used. ................______ PK-444C, 1A LOOP SPRAY VALVE PK-444D, 1B LOOP SPRAY VALVE Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 34 of 37 UATTACHMENT 3 Page 3 of 6 PRESSURIZER HEATER OPERATION TO SUPPORT FNP-1-STP-938, PRESSURIZER HEATER CAPACITY CHECK 4.0 INSTRUCTIONS (continued) Printed 12/22/2014 at 08:52:00 8.Raise the demand on the spray valve in MANUAL as necessary to compensate for the increased output on the cycling (proportional) heater group, maintaining RCS pressure stable. ............................................................... ______9.Maintain stable conditions until EM report that they have obtained their data. ....... ______10. IF the REP. Task is for A PZR Htr. group, THENperformthe following: a. N/A Step 11 through Step 28. ....................................................................... ______b.Go To Step 29. .............................................................................................. ______11. IF the REP. Task is for B PZR Htr. group, THENperformthe following: a. N/A Step 12 through Step 40. ....................................................................... ______Go To Step 41. .............................................................................................. ______12.Place the 1D Back-Up heater group in ON. ............................................................ ______NOTE The following step will keep some voltage applied to the Cycling (Proportional) Heaters. ................ 13.Lower demand on PK-444A until demand is approximately 2-3% less than the value recorded in Step 3. ........................................................................................ ______14.Adjust the demand on the spray valve in MANUAL as necessary to maintain a steady trend of RCS pressure. ................................................................................ ______15.Maintain stable conditions until EM report that they have obtained their data. ...... ______16.Place the 1E Back-Up heater group in ON. ............................................................ ______17. WHEN RCS Pressure starts to trend up, THENsecure the 1D B/U HTR Group. ...................................................................................................................... ______18.Adjust the demand on the spray valve in MANUAL as necessary to maintain a steady trend of RCS Pressure. ............................................................................... ______19.Maintain stable conditions until EM reports they have obtained their data. ............ ______20.Begin raising demand on PK-444A to the demand value recorded in Step 3. ...... ______ Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 35 of 37 UATTACHMENT 3 Page 4 of 6 PRESSURIZER HEATER OPERATION TO SUPPORT FNP-1-STP-938, PRESSURIZER HEATER CAPACITY CHECK 4.0 INSTRUCTIONS (continued) Printed 12/22/2014 at 08:52:00 21. WHEN RCS Pressure starts to rise, THEN secure the 1E B/U HTR Group. ..........______22.Adjust the demand on the spray valve in MANUAL as necessary to maintain a steady trend of RCS pressure. ................................................................................ ______23. WHEN RCS pressure returns to the stable value recorded in Step 4, THENcheck the spray valve in MANUAL has returned to a demand approximately the same as what was recorded in Step 3. ............................................................. ______24. WHEN RCS Pressure returns to the stable value recorded in Step 4, THENcheck PK-444A has returned to a demand approximately the same value as what was recorded in Step 3. .................................................................................. ______25.Return the spray valve in MANUAL to AUTO. ........................................................ ______26.Place PK-444A in AUTO. ........................................................................................ ______27.Check that pressurizer pressure control is operating satisfactorily. ........................______28. N/A Step 29 through Step 54. ................................................................................. ______29.Place the 1A Back-Up heater group in ON. ............................................................ ______30.Lower demand on PK-444A until demand is approximately 2-3% less than the value recorded in Step 3. ........................................................................................ ______31.Adjust the demand on the spray valve in MANUAL as necessary to maintain a steady trend of RCS pressure. ................................................................................ ______32.Maintain stable conditions until EM report that they have obtained their data. ...... ______33.Begin raising demand on PK-444A to the demand value recorded in Step 3. ...... ______34. WHEN RCS Pressure starts to rise, THENsecure the 1A B/U HTR Group. ..........______35.Adjust the demand on the spray valve in MANUAL as necessary to maintain a steady trend of RCS pressure. ................................................................................ ______ Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 36 of 37 UATTACHMENT 3 Page 5 of 6 PRESSURIZER HEATER OPERATION TO SUPPORT FNP-1-STP-938, PRESSURIZER HEATER CAPACITY CHECK 4.0 INSTRUCTIONS (continued) Printed 12/22/2014 at 08:52:00 36. WHEN RCS pressure returns to the stable value recorded in Step 4, THEN check the spray valve in MANUAL has returned to a demand approximately the same as what was recorded in Step 3. ............................................................. ______37. WHEN RCS Pressure returns to the stable value recorded in Step 4, THEN check PK-444A has returned to a demand approximately the same value as what was recorded in Step 3. .................................................................................. ______38.Return the spray valve in MANUAL to AUTO. ........................................................ ______39.Place PK-444A in AUTO. ........................................................................................ ______40.Check that pressurizer pressure control is operating satisfactorily. ........................______41.Place the 1B Back-Up heater group in ON. ............................................................ ______42.Lower demand on PK-444A until demand is approximately 2-3% less than the value recorded in Step 3. ........................................................................................ ______43.Adjust the demand on the spray valve in MANUAL as necessary to maintain a steady trend of RCS Pressure. ............................................................................... ______44.Maintain stable conditions until EM reports they have obtained their data. ............ ______45.Begin raising demand on PK-444A to the demand value recorded in Step 3. ...... ______46. WHEN RCS Pressure starts to trend up, THENsecure the 1B B/U HTR Group. ..................................................................................................................... ______47.Adjust the demand on the spray valve in MANUAL as necessary to maintain a steady trend of RCS pressure. ................................................................................ ______48.Begin raising demand on PK-444A to the demand value recorded in Step 3. ...... ______49.Adjust the demand on the spray valve in MANUAL as necessary to maintain a steady trend of RCS pressure. ................................................................................ ______ Reactor Coolant System FNP-1-SOP-1.1 FARLEY Version 49.1 Unit 1 Page 37 of 37 UATTACHMENT 3 Page 6 of 6 PRESSURIZER HEATER OPERATION TO SUPPORT FNP-1-STP-938, PRESSURIZER HEATER CAPACITY CHECK 4.0 INSTRUCTIONS (continued) Printed 12/22/2014 at 08:52:00 50. WHEN RCS pressure returns to the stable value recorded in Step 4, THEN check the spray valve in MANUAL has returned to a demand approximately the same as what was recorded in Step 3. ............................................................. ______51. WHEN RCS Pressure returns to the stable value recorded in Step 4, THEN check PK-444A has returned to a demand approximately the same value as what was recorded in Step 3. .................................................................................. ______52.Return the spray valve in MANUAL to AUTO. ........................................................ ______53.Place PK-444A in AUTO. ........................................................................................ ______54.Check that pressurizer pressure control is operating satisfactorily. ........................______ 06/02/15 13:26:43 FNP-1-ARP-1.4 UNIT 1 Version 55.0 FARLEY NUCLEAR PLANT ANNUNCIATOR RESPONSE PROCEDURE FNP-1-ARP-1.4SAFE TYMAIN CONTROL BOARD ANNUNCIATOR PANEL D RE LAT EDPROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORYSECTIONSContinuous: ALL

Reference:

NONE Information: NONE Approved: David L. Reed February 20, 2015 Operations Manager Effective Date UNIT 1 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 TABLE OF CONTENTS Procedure Contains Number of Pages Annunciator Window Panel ......................2 DA1 ...........................................................1 DA2 ...........................................................1 DA3 ...........................................................1 DA4 ...........................................................2 DA5 ...........................................................1 DB4 ...........................................................1 DB5 ...........................................................1 DC1 ...........................................................1 DC2 ...........................................................1 DC3 ...........................................................1 DC4 ...........................................................2 DC5 ...........................................................1 DD1 ...........................................................3 DD2 ...........................................................1 DD3 ...........................................................1 DE1 ...........................................................1 DE2 ...........................................................1 DE3 ...........................................................1 DE4 ...........................................................1 DE5 ...........................................................1 DF1 ...........................................................1 DF2 ...........................................................1 DF3 ...........................................................4 DF4 ...........................................................1 DF5 ...........................................................1 DG1 ...........................................................1 DG2 ...........................................................1 DG3 ...........................................................1 DG4 ...........................................................1 DG5 ...........................................................1 DH2 ...........................................................1 DH3 ...........................................................1 DH4 ...........................................................1 DH5 ...........................................................1 DJ2 ............................................................2 DJ3 ............................................................1 DJ4 ............................................................1 DJ5 ............................................................1 DK1 ...........................................................1 DK2 ...........................................................1 DK3 ...........................................................1 DK4 ...........................................................1 DK5 ...........................................................1 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 2 Version 55.0 UNIT 1 MAIN CONTROL BOARD PANEL D A1 B1 C1 D1 E1 1A RCP RCP RCP REGEN HX STANDPIPE #1 SEAL SEAL INJ LTDN FLOW LVL LKOF FLOW FLOW DISCH TEMP LO LO LO HI A2 B2 C2 D2 E2 1B RCP RCP RCP LTDN ORIF STANDPIPE #1 SEAL THRM BARR ISO VLV LVL LKOF FLOW CCW FLOW IN LO HI HI LOCAL CONT A3 B3 C3 D3 E3 1C RCP RCP CCW FLOW LTDN ORIF STANDPIPE #1 SEAL FROM RCP ISO VLV REL LVL LOP OIL CLRS LINE TEMP LO LO HI A4 B4 C4 D4 E4 RMWST RCP SEAL WTR LTDN HX DEGAS SYS SEAL WTR INJ FLTR OUTLET TRBL BYP FLOW HIP PRESS LO HI A5 B5 C5 D5 E5 1A RCP 1B RCP 1C RCP LTDN HX #2 SEAL #2 SEAL #2 SEAL OUTLET LKOF FLOW LKOF FLOW LKOF FLOW FLOW HI HI HI HI 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 2 of 2 Version 55.0 UNIT 1 MAIN CONTROL BOARD PANEL D F1 G1 H1 J1 K1 LTDN TO BTRS LTDN TOTAL RX DEMIN REHT HX MKUP FLOW DIVERTED- OUTLET TEMP DEV TEMP HI HI HI-LO F2 G2 H2 J2 K2 LTDN BTRS CHLR BABT BA FLOW DIVERTED DISCH HDR COMPR TEMP DEV TO RHT- TEMP TRBL HI-LO HI-LO VCT LVL HI HI F3 G3 H3 J3 K3 VCT BTRS CHLR CHLR 1A OR 1B AUTO MKUP LVL SRG TK PKG BA XFER START HI-LO LVL IN PUMP IN SIGNAL HI-LO LOCAL CONT LOCAL CONT BLOCKED F4 G4 1A H4 1A J4 1A K4 1A VCT BAT BAT BAT BAT PRESS LVL LVL TEMP TEMP HI-LO LO-LO HI-LO LO HI F5 G5 1B H5 1B J5 1B K5 1B VCT BAT BAT BAT BAT TEMP LVL LVL TEMP TEMP HI LO-LO HI-LO LO HI RECORDSQARecord(X)Non-QARecord(X)Record Generated R-TYPE None H06.005 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DA1 SETPOINT: 9 inches A1 1A RCP STANDPIPE LVL ORIGIN: 1A RCP Standpipe Level Switch (N1E21LSL0406B-N) LO PROBABLE CAUSE 1. 1A Reactor Coolant Pump #3 Seal normal leakage. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Open RMW TO PRT ISO Q1B13HV8028 2. Open 1A RCP STANDPIPE FILL ISO N1E21HV8168A 3. Fill standpipe until the alarm clears 4. Close 1A RCP STANDPIPE FILL ISO N1E21HV8168A 5. Close RMW TO PRT ISO Q1B13HV8028. NOTE: A normally functioning seal will require a Standpipe refill every 12 to 48 hours.Seals that require a Standpipe refill in 10 hours or less may be worn or damaged.6. Record filling of RCP Standpipe in Control Room Log.

References:

A-177100, Sh. 181; A-181541; D-175039, Sh. 1; D-177858; D-177091, Sh. 2; PCN B91-1-7687; PLS Document; U-258242 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DA2 SETPOINT: 9 inches A2 1B RCP STANDPIPE ORIGIN: 1B RCP Standpipe Level Switch (N1E21LSL0407B-N) LVL LO PROBABLE CAUSE 1. 1B Reactor Coolant Pump #3 Seal normal leakage. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Open RMW TO PRT ISO Q1B13HV8028 2. Open 1B RCP STANDPIPE FILL ISO N1E21HV8168B 3. Fill standpipe until the alarm clears 4. Close 1B RCP STANDPIPE FILL ISO N1E21HV8168B 5. Close RMW TO PRT ISO Q1B13HV8028. NOTE: A normally functioning seal will require a Standpipe refill every 12 to 48 hours.Seals that require a Standpipe refill in 10 hours or less may be worn or damaged.6. Record filling of RCP Standpipe in Control Room Log.

References:

A-177100, Sh. 182; A-181541; D-175039, Sh. 1; D-177858; D-177091, Sh. 2; PCN B91-1-7687; PLS Document; U-258242 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DA3 SETPOINT: 9 inches A3 1C RCP STANDPIPE LVL ORIGIN: 1C RCP Standpipe Level Switch (N1E21LSL0408B-N) LO PROBABLE CAUSE 1. 1C Reactor Coolant Pump #3 Seal normal leakage. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Open RMW TO PRT ISO Q1B13HV8028 2. Open 1C RCP STANDPIPE FILL ISO N1E21HV8168C 3. Fill standpipe until the alarm clears 4. Close 1C RCP STANDPIPE FILL ISO N1E21HV8168C 5. Close RMW TO PRT ISO Q1B13HV8028. NOTE: A normally functioning seal will require a Standpipe refill every 12 to 48 hours.Seals that require a Standpipe refill in 10 hours or less may be worn or damaged.6. Record filling of RCP Standpipe in Control Room Log.

References:

A-177100, Sh. 183; A-181541; D-175039, Sh. 1; D-177858; D-177091, Sh. 2; PCN B91-1-7687; PLS Document; U-258242 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 2 Version 55.0 UNIT 1 LOCATION DA4 SETPOINT: A4 1. SETPOINT: 1. HI-HI Level (20'11" +/- 1") in Vacuum Degasifier. RMWST 2. LO Level (3' 6" +/- 3") in Reactor Makeup Water DEGAS SYS 3. Vacuum Degasifier Discharge Strainer HI P(1 PSID +/- 0.5 PSID) TRBL 4. Vacuum Degasifier LO Vacuum (5" Hg +/- 1" Hg VAC) 5. Seal Water Catch Tank HI Level 6. Radwaste AHU Supply Fan not running ORIGIN:

1. Vacuum Degasifier Level Switch N1P28LS535

2. RMW Storage Tank Low Level Alarm Relay IN. 345-1 (N1P12LA514) from N1P12LT502 3. Vacuum Degasifier Discharge Strainer Differential Pressure Switch N1P28DPS531 4. Vacuum Degasifier Vacuum Switch N1P28PS537

5. Seal Water Catch Tank Level Switch N1P28LS543

6. RAD WASTE AHU SUPP FAN Breaker EC-06 Cell Switch or Auxiliary Switch PROBABLE CAUSE 1. HI-HI Level in the Vacuum Degasifier due to malfunction of level control valve N1P28V545 by itself or in conjunction with an improper valve lineup, a loss of degasifier transfer pump N1P28P505, or a clogged degasifier discharge strainer N1P28F505. 2. Low Level in RMW Storage Tank due to level control valve Q1P12V501 malfunction, a piping rupture or improper valve lineup. 3. High Vacuum Degasifier Discharge Strainer (N1P28F505) P due to clogged strainer or improper DPS Valve Lineup. 4. Low Vacuum in the Vacuum Degasifier due to system vacuum leak, vacuum pump failure, loss of seal water to vacuum pumps, or improper valve lineup. 5. High Level in the seal water catch tank due to excessive seal water flow, improper valve lineup, loss of vacuum in degasifier or failure of level control valve N1P28V588. 6. RAD WASTE AHU SUPP FAN Breaker (EC-06) tripped open or breaker not racked in.

06/02/15 13:26:43 FNP-1-ARP-1.4 Page 2 of 2 Version 55.0 UNIT 1 LOCATION DA4 NOTE: This alarm can be deactivated by a toggle switch on the degasifier local control panel. This alarm should be deactivated when the degasifier is shut down and activated when the degasifier is running. AUTOMATIC ACTION 1. Supply Pump and Vacuum Pumps #1 and #2 tripped by N1P28LS536 on HI-HI Level (20' 11" +/- 1") in Degasifier. 2. Supply Pump tripped by N1P12LA514 on Low Level (3' 6" +/- 3") in RMW Storage Tank. 3. Transfer Pump tripped on N1P28DPS531 on HI P (1.0 psid +/- 0.5 psid) across the Vacuum Degasifier Discharge Strainer. 4. Vacuum Pumps #1 and #2 tripped by N1P28PS537 on Low Vacuum (5" Hg +/- 1" Hg VAC) in the Degasifier or by EC-06 when RAD WASTE AHU SUPP FAN trips OFF. OPERATOR ACTION 1. Have appropriate plant personnel investigate and determine cause for alarm condition. 2. IF alarm condition is due to low vacuum in the degasifier OR loss of the Rad Waste AHU SUPP Fan, THEN secure the transfer pump to prevent transferring oxygenated water to the RMW Storage Tank. 3. IF alarm condition is due to low level in the RMW Storage Tank, THEN secure the vacuum pumps. 4. IF valid alarm condition exists, THEN commence shutdown of Degasifier Unit.5. Have appropriate plant personnel identify and correct cause for alarm condition.6. Return system to service upon correction of cause for alarm condition.

References:

A-177100, Sh. 184; D-170862; D-173468; U-187763; PCN SE 79-525, Rev. 8 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DA5 SETPOINT: 0.75 GPM A5 1A RCP #2 SEAL ORIGIN: 1A RCP #2 Seal Leakoff Flow Switch (N1E21FSH160-N) LKOF FLOW HI PROBABLE CAUSE 1. #2 Seal hanging open. 2. Damage to #2 Seal. AUTOMATIC ACTION NONEOPERATORACTION1. Refer to FNP-1-AOP-4.1 ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE.2. Submit a condition report. 3. Refer to Technical Specifications, LCO 3.5.5 condition A for LCO requirements.

References:

A-177100, Sh. 185; A-181541; D-175039, Sh. 1; U-258242; PLS Document; Technical Specifications; Westinghouse Tech Bulletin ESBU-TB-93-01-R1 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DB4 SETPOINT: 1.1 GPM B4 RCP SEAL WTR ORIGIN: RCP SEAL WTR BYPASS Q1E21HV8142 must be BYP FLOW fully open in addition to one of the following: LO 1. 1A RCP Seal Bypass Flow Switch (N1E21FIS156-N) 2. 1B RCP Seal Bypass Flow Switch (N1E21FIS155-N) 3. 1C RCP Seal Bypass Flow Switch (N1E21FIS154-N) PROBABLE CAUSE 1. RCP SEAL WTR RTN ISO Q1E21MOV8100 or Q1E21MOV8112 closed.2. Low or Loss of Seal Water Injection flow with low Reactor Coolant System Pressure. 3. Improper setting of SEAL WTR INJECTION HIK-186. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Ensure proper setting of SEAL WTR INJECTION HIK-186. 2. IF required, THEN increase seal water injection flow to clear the alarm. 3. Monitor RCP'S Lower Radial Bearing Temperatures. 4. Refer to FNP-1-SOP-1.1, REACTOR COOLANT SYSTEM.

References:

A-177100, Sh. 189; D-175039, Sh. 1; D-177848;U-258242; PLS Document 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DB5 SETPOINT: 0.75 GPM B5 1B RCP #2 SEAL ORIGIN: 1B RCP #2 Seal leakoff Flow Switch (N1E21FSH159-N) LKOF FLOW HI PROBABLE CAUSE 1. #2 Seal Hanging open. 2. Damage to #2 Seal. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Refer to FNP-1-AOP-4.1 ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE. 2. Submit a condition report. 3. Refer to Technical Specifications, LCO 3.5.5 condition A for LCO requirements

References:

A-177100, Sh. 190; A-181541; D-175039, Sh. 1; U-258242; PLS Document; Technical Specifications; Westinghouse Tech Bulletin ESBU-TB-93-01-R1 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DC1 SETPOINT: 0.95 GPM C1 RCP #1 SEAL ORIGIN: LKOF FLOW 1. 1A RCP #1 Seal Leakoff Flow Transmitter (N1E21FT156B-N) LO 2. 1B RCP #1 Seal Leakoff Flow Transmitter (N1E21FT155B-N) 3. 1C RCP #1 Seal Leakoff Flow Transmitter (N1E21FT154B-N) PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. A differential pressure of less than 200 PSID across the #1 Seal. 2. Excessive leakage of the #2 Seal.

3. Damage to the #1 Seal.

4. Volume Control Tank pressure higher than normal.

5. Improper setting of SEAL WTR INJECTION HIK 186.

6. Shutdown Seal Actuation AUTOMATIC ACTION NONEOPERATORACTION1. Compare the indications of the following instruments to determine if an instrument failure has occurred or if a seal problem has developed. RCP SEAL LKOF HIGH RANGE recorder N1E21FR154A RCP SEAL LEAKOFF LOW RANGE indicators FI-156B, 155B, 154B. #1SEAL PRESSURE indicators PI-156A, 155A, 154A. SHAFT SEAL FLOW FI-130A, 127A, 124A. Additionally, trends in Excess Letdown parameters could be indicative of an instrument malfunction or a seal problem. EXC LTDN HX OUTLET TEMP, TI-139 EXC LTDN HX OUTLET PRESS PI-138 2. Refer to FNP-1-AOP-4.1 ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE for an actual seal problem. 3. Submit a condition report. 4. Refer to Technical Specifications, LCO 3.5.5 condition A, for LCO requirements.

References:

A-177100, Sh. 191; D-175039, Sh. 1; U-175986; U-176002; U-176032; U-258242; PLS Document; Technical Specifications; Westinghouse Tech Bulletin ESBU-TB-93-01-R1 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DC2 SETPOINT: 5 GPM C2 RCP #1 SEAL ORIGIN: LKOF FLOW 1. 1A RCP #1 Seal Leakoff Flow Transmitter (N1E21FT156A-N) HI 2. 1B RCP #1 Seal Leakoff Flow Transmitter (N1E21FT155A-N) 3. 1C RCP #1 Seal Leakoff Flow Transmitter (N1E21FT154A-N) PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. Loss of Injection Water followed by High Seal Temperature. 2. High Temperature of the injection water supply.

3. Damage to the #1 Seal.

4. #1 Seal Ring Cocked

5. Instrument failure AUTOMATIC ACTION NONE OPERATOR ACTION 1. Compare the indications of the following instruments to determine if an instrument failure has occurred or if a seal problem has developed. RCP SEAL LKOF HIGH RANGE recorder N1E21FR154A RCP SEAL LEAKOFF LOW RANGE indicators FI-156B, 155B, 154B. #1SEAL PRESSURE indicators PI-156A, 155A, 154A. SHAFT SEAL FLOW FI-130A, 127A, 124A. LOWER SEAL WATER BRG TEMP computer points TE0131, TE0128, TE0125 SEAL WATER OUTLET TEMP computer points TE0132, TE0129, TE0126 Additionally, trends in Excess Letdown parameters could be indicative of an instrument malfunction or a seal problem. EXC LTDN HX OUTLET TEMP, TI-139 EXC LTDN HX OUTLET PRESS PI-138 2. Refer to FNP-1-AOP-4.1 ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE for an actual seal problem 3. Submit a condition report. 4. Refer to Technical Specifications, LCO 3.5.5 condition A, for LCO requirements.

References:

A-177100, Sh. 192; D-175039, Sh. 1; U-175986; U-176032; U258242; PLS Document; Technical Specifications; Westinghouse letter ALA-88-811; Westinghouse Tech Bulletin ESBU-TB-93-01-R1; PCN B93-1-8652 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DC3 SETPOINT: 210 PSI C3 RCP #1 SEAL ORIGIN:LOP 1. 1A RCP #1 Seal P Transmitter (N1E21PT156-N) 2. 1B RCP #1 Seal P Transmitter (N1E21PT155-N) 3. 1C RCP #1 Seal P Transmitter (N1E21PT154-N) PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. Low Reactor Coolant System pressure. 1. 1A, 1B or 1C RCP SEAL LEAKOFF Q1E21HV8141A, B, or C closed. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Compare the indications of the following instruments to determine if an instrument failure has occurred or if a seal problem has developed. #1SEAL PRESSURE indicators PI-156A, 155A, 154A. RCP SEAL LKOF HIGH RANGE recorder N1E21FR154A RCP SEAL LEAKOFF LOW RANGE indicators FI-156B, 155B, 154B. SHAFT SEAL FLOW FI-130A, 127A, 124A. Additionally, trends in Excess Letdown parameters could be indicative of an instrument malfunction or a seal problem. EXC LTDN HX OUTLET TEMP, TI-139 EXC LTDN HX OUTLET PRESS PI-138 2. Refer to FNP-1-AOP-4.1 ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE for an actual seal problem 3. Submit a condition report. 4. Refer to FNP-1-SOP-1.1, REACTOR COOLANT SYSTEM 5. Refer to Technical Specifications, LCO 3.5.5 condition A, for LCO Requirements.

References:

A-177100, Sh. 193; D-175039, Sh. 1; U-175985; U-176001; U-176031; U-258242; PLS Document; Technical Specifications 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 2 Version 55.0 UNIT 1 LOCATION DC4 SETPOINT: 20 PSID C4 SEAL WTR INJ FLTR ORIGIN:HIP 1. Diff. Pressure Switch (N1E21PIS0157A-N) 2. Diff. Pressure Switch (N1E21PIS0157B-N) PROBABLE CAUSE 1. Seal Water Injection Filter 1A or 1B clogged. 2. High seal injection flow rate.

3. Chg Flow Q1E21FCV122 failed closed. AUTOMATIC ACTION NONECAUTIONS: To prevent possible over pressurization and failure of a clogged seal injection filter, no attempt to raise seal injection flow should be made while annunciator is in. Seal injection must not be isolated if CCW cooling to the thermal barrier is not available. NOTE: Performance of the following steps may result in isolation of seal injection. This may be necessary to preclude possible collapse of a seal injection filter that may result from excessive P.OPERATOR ACTION 1. IF seal injection flow rate is high, THEN reduce to normal value. 2. IF alarm NOT cleared by previous step, THEN dispatch appropriate personnel to perform the following: 2.1 observe actual Seal Injection Filter P.2.2 IF filter P is visibly rising, THEN isolate all seal injection flow by closing the following valves: 1A SEAL WATER INJ FILTER INLET Q1E21V127A AND Q1E21V127C 1A SEAL WATER INJ FILTER OUTLET Q1E21V130A AND Q1E21V130C 1B SEAL WATER INJ FILTER INLET Q1E21V127B AND Q1E21V127D 1B SEAL WATER INJ FILTER OUTLET Q1E21V130B AND Q1E21V130D2.3 IF P is stable, THEN place the standby seal injection filter in service per FNP-1-SOP-2.1.

06/02/15 13:26:43 FNP-1-ARP-1.4 Page 2 of 2 Version 55.0 UNIT 1 OPERATOR ACTION CONT'D NOTE: Per the Westinghouse Technical Manual, RCP operation without seal injection is limited to 24 hours. This is a conservative recommendation intended to limit the probability of a combined loss of CCW cooling and injection flow. 3. IF seal injection has been isolated, THEN perform the following: 3.1 Closely monitor RCP parameters. 3.2 Determine the cause of filter clogging, replace clogged filters, and return seal injection to service as soon as possible. 4. IF on-service filter has been swapped, THEN perform the following: 4.1 Closely monitor P until it stabilizes. 4.2 IF P with standby filter in service does NOT stabilize at < 20 psid, THEN isolate all seal injection flow by closing the following valves: 1A SEAL WATER INJ FILTER INLET Q1E21V127A AND Q1E21V127C 1A SEAL WATER INJ FILTER OUTLET Q1E21V130A AND Q1E21V130C 1B SEAL WATER INJ FILTER INLET Q1E21V127B AND Q1E21V127D 1B SEAL WATER INJ FILTER OUTLET Q1E21V130B AND Q1E21V130D5. IF seal injection filters were swapped, THEN notify appropriate personnel to replace the clogged filter.

References:

A-177100, Sh. 194; D-175039, Sh. 2; PLS Document; Westinghouse Tech Bulletin NSD-TB-91-07-R1 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DC5 SETPOINT: 0.75 GPM C5 1C RCP #2 SEAL LKOF FLOW ORIGIN: 1C RCP #2 Seal Leakoff Flow Switch (N1E21FSH158-N) HI PROBABLE CAUSE 1. #2 Seal hanging open. 2. Damage to #2 seal. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Refer to FNP-1-AOP-4.1 ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE for an actual seal problem. 2. Submit a condition report. 3. Refer to Technical Specifications, LCO 3.5.5 condition A for LCO requirements

References:

A-177100, Sh. 195; A-181541; D-175039, Sh. 1; U-258242; PLS Document; Technical Specifications; Westinghouse Tech Bulletin ESBU-TB-93-01-R1. 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 3 Version 55.0 UNIT 1 LOCATION DD1 SETPOINT: 6.7 GPM D1 RCP SEAL INJ ORIGIN: FLOW 1. 1A RCP Seal Water Injection Flow Transmitter (Q1E21FT0130-N) LO 2. 1B RCP Seal Water Injection Flow Transmitter (Q1E21FT0127-N) 3. 1C RCP Seal Water Injection Flow Transmitter (Q1E21FT0124-N)PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. All Charging Pumps stopped. 2. Improper setting on SEAL WTR INJECTION HIK-186.

3. Clogging seal injection filter. AUTOMATIC ACTION NONEOPERATOR ACTION 1. IF a loss of seal injection flow has occurred AND a loss of Component Cooling Water to the Thermal Barrier Heat Exchanger has occurred AND at least one method of seal cooling cannot be immediately restored, THEN go to FNP-1-AOP-4.1, ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE. 2. Determine the cause of the alarm. 3. For a CVCS malfunction, go to FNP-1-AOP-16.0, CVCS MALFUNCTION 4. Monitor RCP lower bearing temperatures and #1 Seal Leakoff Flows. CAUTION: No attempt to raise seal injection flow should be made if annunciator DC4, SEAL WTR INJ FLTR HI P, is in alarm to prevent possible over pressurization and failure of a clogged seal injection filter. 5. IF seal injection flow is low AND annunciator DC4, Seal WTR INJ FLTR HIP, is NOT in alarm, THEN re-establish proper injection flow by opening SEAL WTR INJECTION HIK-186.

06/02/15 13:26:43 FNP-1-ARP-1.4 Page 2 of 3 Version 55.0 UNIT 1 LOCATION DD1 OPERATOR ACTION CONT'D 6. IF operation of SEAL WTR INJECTION HIK-186 is erratic and operation via the bypass is desired, THEN refer TO FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION, Section 4.16 for guidance. 7. Check the on-service Seal Injection Filter P.CAUTIONS: RCP's with #1 Seal Leakoff less than 2.5 gpm may develop lower bearing and seal temperatures that exceed 225F within 1 to 2 hours following a loss of seal injection. Long term operation of the RCP under loss of seal injection conditions increases the risk of a loss of all seal cooling incident if the CCW system supply to the RCP thermal barrier should also fail. RCS water being cooled by the RCP thermal barrier contains particulate matter, since it is not filtered, which can have an impact on the long term operability of the RCP seals. Particulate matter which will deposit in the seal package as the result of a loss of seal injection will be radioactive and will impact dose to received by workers during repair efforts. 8. IF a Loss of Seal Injection Flow has occurred, THEN; a) Ensure that RCP, Component Cooling Water inlet temperature remains below 105°F. b) Ensure that at least one Charging Pump is running. c) Carefully re-establish the Injection Water Flow, reducing the RCP Lower Bearing Temperatures at a maximum rate of 1°F per minute, using SEAL WTR INJECTION HIK 186, or by establishing flow via HI-186 bypass using FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION, Section 4.16 for guidance. 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 3 of 3 Version 55.0 UNIT 1 LOCATION DD1 OPERATOR ACTION CONT'D CAUTION: If at any time the seal package reaches 250°F, it is likely the Shutdown Seal has actuated and must be replaced. Closure of the #1 seal leakoff line will impede the operator's ability to determine if the Shutdown Seal has actuated. Alternate means such as calculated flow into the RCDT must be used. 9. IF a Loss of Seal Injection Flow has occurred, THEN; a) IF the bearing or seal water outlet temperature for any operating RCP reaches 225F, THEN: 1. Manually trip the reactor, and perform the next steps concurrently with FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. 2. Secure the affected RCP. 3. WHEN RCP has come to a complete stop as indicated by minimum RCS flow in the affected loop, THEN close the 1A (B or C) RCP Seal Leakoff Q1E21HV8141A (B or C) for the affected RCP. 4. IF 1A or 1B RCP is secured, THEN close the pressurizer spray valve for the affected RCP (PK-444C for 1A RCP, PK-444D for 1B RCP) b) Monitor lower bearing or seal water outlet temperatures of any operating RCPs paying particular attention to those RCPs with pre-event seal leakoffs of < 2.5 gpm. 1. IF bearing or seal water outlet temperature of any operating RCP reaches 190F, and continues to rise, THEN initiate a controlled reactor shutdown using the guidance of FNP-1-UOP-3.1, POWER OPERATION or FNP-1-AOP-17.1, RAPID TURBINE POWER REDUCTION, as deemed necessary. 2. WHEN the reactor is shutdown, THEN secure the affected RCP. 3. WHEN RCP has come to a complete stop as indicated by minimum RCS flow in affected loop, THEN close the 1A (B or C) RCP Seal Leakoff Q1E21HV8141A (B or C) for the affected pump. 4. IF 1A or 1B RCP is secured, THEN close the pressurizer spray valve for the affected RCP (PK-444C for 1A RCP, PK-444D for 1B RCP).

References:

A-177100, Sh. 196; D-175039, Sh. 1 & 2; PLS Document; U-175985; U-176001; U-176031; U-258242. {CMT 0003153} {CMT 0005756} {CMT 0007558} {CR-1-2000-257} 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DD2 SETPOINT: 160 2 GPM D2 RCP THRM BARR CCW FLOW ORIGIN: 49x, Aux. Contact activated by Flow Switch HI (Q1P17FISH3045-A) PROBABLE CAUSE 1. Rupture of a RCP Thermal Barrier Heat Exchanger. AUTOMATIC ACTION 1. Closes CCW FROM RCP THRM BARR Q1P17HV3045. NOTE: Failure of a RCP #1 Seal may result in isolation of CCW to the Thermal Barrier Heat Exchangers due to local boiling in the Thermal Barrier of the affected pump, caused by High #1 Seal Leakoff Flow. OPERATOR ACTION 1. IF a loss of seal injection flow has occurred AND a loss of Component Cooling Water to the Thermal Barrier Heat Exchanger has occurred AND at least one method of seal cooling cannot be immediately restored, THEN go to FNP-1-AOP-4.1, ABNORMAL REACTOR COOLANT PUMP SEAL LEAKAGE. 2. Determine the cause of the alarm. 3. Closely monitor seal injection water flows, Seal Injection Water Temperatures and RCP Lower Bearing Temperatures. NOTE: Proper RCP Seal Injection Water Flow and Seal Injection Water Temperature should provide adequate cooling for the RCP's Seals and Lower Bearings. 4. Notify appropriate personnel 5. Shutdown the plant and repair the affected Thermal Barrier Heat Exchanger as soon as possible.

References:

A-177100, Sh. 197; B-175968, Pg. 6; D-175002, Sh. 2;D-177854; U-258242 NEL 98-0327 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DD3 SETPOINT: 100 + 10 GPM D3 - 0 CCW FLOW ORIGIN: FROM RCP 1. Flow Switch (Q1P17FISL3048A-N) OIL CLRS 2. Flow Switch (Q1P17FISL3048B-N) LO 3. Flow Switch (Q1P17FISL3048C-N) PROBABLE CAUSE NOTE: Following entry into Mode 6 during a refueling outage, it is common to receive alarm DD3 due to low discharge pressure on the O/S pump when aligned to the SFP and RHR HXs, and the RHR seal and charging pump oil coolers. AI 2009203964 1. Loss of Component Cooling Water. 2. Loss of Component Cooling Water Flow to the RCP's due to Phase "B" isolation signal. 3. Improper valve lineup. AUTOMATIC ACTION NONEOPERATORACTION1. Determine the cause of the alarm. 2. IF a loss of Component Cooling Water has occurred, THEN perform the actions required by FNP-1-AOP-9.0, LOSS OF COMPONENT COOLING WATER. 3. Closely monitor the RCP's Motor Bearing Temperatures. NOTE: On a complete Loss of CCW Flow to RCP Motor Bearing Oil Coolers, the bearing temperature will exceed 195°F in approximately 2 minutes. 4. IF any RCP Motor Bearing Temperature exceeds 195°F, THEN: A. IF the Reactor is critical, THEN trip the reactor. B. Stop the RCP. C. Perform the actions required by FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION.D. Perform action of FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW as time allows. 5. Correct the cause of the alarm and return flow to normal.

References:

A-177100, Sh. 198; B-175968, Pg. 6 & 7; D-175002, Sh. 2; U-258242 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DE1 SETPOINT: 365FE1 REGEN HX LTDN FLOW DISCH TEMP ORIGIN: Temperature Bistable TB-140 from HI Temperature Element (N1E21TE140-N) PROBABLE CAUSE 1. Low Charging Flow. AUTOMATIC ACTION NONEOPERATOR ACTION CAUTION: If actual VCT level is low, refer to annunciator DF3. (SOER 97-1) 1. Determine actual letdown flow temperature as indicated by TI-140 (REGEN HX Outlet Temp) on the MCB. 2. Monitor charging and letdown flows and temperatures. 3. IF the cause is determined to be a CVCS malfunction, THEN go to FNPAOP-16.0, CVCS MALFUNCTION. 4. Refer to FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION. 5. IF operating at a minimum Charging Flow rate, THEN; a) Verify that the Letdown Flow is being cooled below 380°F. b) Adjust Charging or Letdown Flow, if required, to lower the temperature. 6. Correct the cause of the alarm and return the system to normal as soon as possible.

References:

A-177100, Sh. 201; D-175039, Sh. 1; U-175992; PLS Document 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DE2 SETPOINT: Not Applicable E2 LTDN ORIF ISO VLV ORIGIN: IN 1. Selector Switch (Q1E21HS8149AC-A) LOCAL CONT 2. Selector Switch (Q1E21HS8149BC-A) 3. Selector Switch (Q1E21HS8149CC-A) PROBABLE CAUSE 1. The Selector Switch at the Hot Shutdown Panel is in the Local position for one or more of the following valves: a) Q1E21HV8149A b) Q1E21HV8149B c) Q1E21HV8149C AUTOMATIC ACTION NONEOPERATOR ACTION 1. No action is necessary if alarm is due to preplanned operational or maintenance activities; otherwise send appropriate personnel to determine the cause of the alarm. 2. Return the valve to Remote Control as soon as possible.

References:

A-177100, Sh. 202; D-175039, Sh.1; D-177376; D-177377; D-177378 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DE3 SETPOINT: 165 +/- 2FE3 LTDN ORIF ISO VLV REL ORIGIN: Temperature Bistable TB-141 from Temperature LINE TEMP Element (N1E21TE141-N) HI PROBABLE CAUSE 1. LTDN ORIF OUTLET REL VLV, Q1E21V255, leaking or lifted. 2. LP LTDN PRESS PK-145 malfunction. AUTOMATIC ACTION NONEOPERATOR ACTION CAUTION: If actual VCT level is low, refer to annunciator DF3. (SOER 97-1) 1. Monitor the LTDN ORIF ISO REL line to PRT Temperature (TI-141) and LTDN HX Outlet Press (PI- l45). 2. IF the high temperature is due to LP LTDN press PK-145 malfunctions, THEN place valve controller in manual and adjust as required. 3. IF temperature continues to rise rapidly indicating a lifted relief valve, THEN close LTDN ORIF ISO 45 (60) GPM Q1E21HV8149A, B AND C. NOTE: Transients that will require boration or dilution should be avoided if letdown has been secured. 4. IF a ramp is in progress, THEN place turbine load on HOLD. 5. Go to FNP-1-AOP-16.0, CVCS MALFUNCTION to address the loss of letdown flow.

References:

A-177100, Sh. 203; D-175039, Sh. 1; U-176024; PLS Document 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DE4 SETPOINT: 462 PSIG E4 LTDN HX OUTLET ORIGIN: Pressure Bistable PB-145 from PRESS Pressure Transmitter (Q1E21PT145) HI PROBABLE CAUSE 1. LP LTDN PRESS PK-145 malfunction. 2. All three Letdown Orifice Isolation Valves open. AUTOMATIC ACTION NONEOPERATOR ACTION CAUTION: If actual VCT level is low, refer to annunciator DF3. (SOER 97-1) 1. Monitor LTDN HX Outlet Flow (FI-150) and LTDN HX Outlet Press (PI-145).2. Ensure proper orifice isolation valve selection. 3. IF the high pressure is due to LP LTDN PRESS PK-145 malfunction, THEN place valve controller in manual and attempt to reduce the pressure.4. IF pressure can NOT be controlled manually with LP LTDN PK-145, THEN close LTDN ORIF ISO 45 (60) GPM Q1E21HV8149A, B, and C. NOTE: Transients that will require boration or dilution should be avoided if letdown has been secured. 5. IF a ramp is in progress, THEN place turbine load on HOLD. 6. Go to FNP-1-AOP-16.0, CVCS MALFUNCTION to address the loss of letdown flow.

References:

A-177100, Sh. 204; D-175039, Sh. 1&2; U-176018; PLS Document 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 2 Version 55.0 UNIT 1 LOCATION DE5 SETPOINT: 140 GPM E5 LTDN HX OUTLET ORIGIN: Flow Bistable FB-150 from FLOW Flow Transmitter (Q1E21FT150) HI PROBABLE CAUSE 1. All three Letdown Orifice Isolation Valves open. 2. LP LTDN PRESS PK-145 failed open. AUTOMATIC ACTION NONENOTES: The normal flow rate for letdown is 60 GPM and the maximum is 135 GPM. FSAR Table 9.3.5 At 135°F ann DF1 should alarm and TCV-143 should divert to the VCT. OPERATOR ACTION 1. Monitor the following: LTDN HX Outlet Flow (FI-150) LTDN HX Outlet Press (PI-145). 2. Ensure proper orifice isolation valve selection. 3. IF LP LTDN PRESS PK-145 has failed, THEN place valve controller in manual and attempt to reduce letdown flow below 135 GPM. 4. IF proper letdown flow can NOT be maintained, THEN close LTDN ORIF ISO 45 (60) GPM Q1E21HV8149A, B, and C. NOTE: Transients that will require boration or dilution should be avoided if letdown has been secured. 5. IF a ramp is in progress, THEN place turbine load on HOLD. 6. Go to FNP-1-AOP-16.0, CVCS MALFUNCTION to address the loss of letdown flow.

References:

A-177100, Sh. 205; D-175039, Sh. 1&2; U-176019; PLS Document U-258631; PCN B-87-1-4353 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DF1 SETPOINT: 135FF1 LTDN TO DEMIN ORIGIN: 1-TY-143X Auxiliary Relay actuated by DIVERTED- Temperature Bistable (N1E21TB143) TEMP HI PROBABLE CAUSE 1. Low or Loss of CCW Flow to the Letdown Heat Exchanger. 2. Letdown Flow greater than Charging Flow. AUTOMATIC ACTION 1. Letdown High Temperature Divert Valve Q1E21TCV143 diverts Letdown Flow to the VCT. {CMT 0008644} OPERATOR ACTION 1. Verify Q1E21TCV143 has diverted letdown flow to VCT to bypass demins 2. Monitor charging and letdown flows and temperatures. 3. Take manual control of LTDN HX Outlet Temp TK-144 and attempt to increase CCW flow to the Letdown Heat Exchanger. 4. Adjust charging or letdown flow as required to reduce the letdown flow temperature. 5. IF cause for the elevated temperature has been corrected, THEN refer to FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION to return TCV143 to DEMIN. 6. IF letdown temperature can NOT be reduced, THEN close LTDN ORIF ISO 45 (60) GPM Q1E21HV8149A, B, and C. NOTE: Transients that will require boration or dilution should be avoided if letdown has been secured. 7. IF a ramp is in progress, THEN place turbine load on HOLD 8. Go to FNP-1-AOP-16.0, CVCS MALFUNCTION to address the loss of letdown flow.

References:

A-177100, Sh. 206; D-175039, Sh.2; D-177091; D-177375; U-175997; PLS Document 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DF2 SETPOINT: 81% Level F2 LTDN DIVERTED ORIGIN: 1-LY-115AX Auxiliary Relay actuated TO RHT- by Level Bistable (NlE2lLBll5A) VCT LVL HI PROBABLE CAUSE 1. Letdown flow greater than charging flow. 2. Normal Primary Plant heatup.

3. LT-115 failed high.

4. LCV-115A selected to VCT.

5. CVCS makeup addition in progress. AUTOMATIC ACTION 1. VCT HI LVL DIVERT VLV Q1E21LCV115A diverts Letdown Flow to the Recycle Holdup Tank. OPERATOR ACTION 1. Determine actual VCT level as indicated by LI-115 and LI-112B on the MCB.2. Verify that VCT HI LVL Divert VLV Q1E21LCV115 has diverted flow to the Recycle Holdup Tank. 3. Verify proper charging and letdown flows. 4. Observe CHG HDR PRESS indicator PI-121 and the running Charging Pump Motor Ammeter to ensure proper pump operation. (SOER 97-1) 5. IF LT-115 has failed high, THEN; a) Place VCT divert valve 115A in the VCT mode b) Manually makeup to VCT for VCT level control c) IF VCT level decreases to 5%, THEN open RWST to charging pump suctions and close VCT outlet isolations d) The following automatic actions are inhibited 1) Auto VCT/RCS makeup 2) Auto opening of RWST to charging pump suction on VCT low level3) Auto VCT outlet isolations closing on lo VCT level e) Initiate steps to have the instrumentation repaired (SOER 97-1

References:

A-177100, Sh. 207; D-175039, Sh. 2; PLS Document; U-169636; U-175989 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 4 Version 55.0 UNIT 1 LOCATION DF3 SETPOINT: 1. High: 76% Level F3 2. Low: 15% Level VCT LVL ORIGIN: 1. Level Bistable LB-115D from Level HI-LO Transmitter (Q1E21LT115) 2. Level Bistable LB-112B from Level Transmitter (Q1E21TC112) PROBABLE CAUSE NOTE: Zinc Addition System (ZAS) injection will result in a continuous addition of as much as 1.7 gallons per hour to the VCT, when the system is in service. 1. High Level VCT HI LVL DIVERT VLV Q1E21LCV115 malfunction or positioned to the VCT position. Makeup Flow and/or Letdown flow rate greater than Charging Flow rate. LT-115 or LT-112 failed high. Normal plant heat-up. CVCS makeup addition in progress. 2. Low Level Makeup Control not in automatic. VCT HI LVL DIVERT VLV Q1E21LCV115 malfunction or positioned to the Holdup Tank position. Chemical and Volume Control System leak. LT-115 or LT-112 failed Low. AUTOMATIC ACTION 1.LT-112 Modulates LCV-115A from fully closed at VCT level of 71% to fully open at VCT level of 81%. Shifts charging pumps suction to RWST at 5% VCT Lo-Lo level (with LT-115), Hi alarms at 76%, Lo alarms at 15%. 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 2 of 4 Version 55.0 UNIT 1 LOCATION DF3AUTOMATIC ACTION (Cont'd)2.LT-115 LT-115 fully diverts LCV-115A at 81% VCT level. Shifts charging pumps suction to RWST at 5% VCT Lo-Lo level (with LT-112) Starts auto makeup at 20% VCT level; stops auto makeup at 40% VCT level Hi alarms at 76%, Lo alarms at 15%. OPERATOR ACTION 1. Determine if level is high or low as indicated by LI-115 and LI-112B on the MCB.{CMT 0006813} 2. IF actual level is high, THEN: 2.1 Stop makeup. 2.2 Place VCT HI LVL Divert VLV Q1E21LCV115A to the HU TK position until the desired level is reached. 2.3 Have CHM secure ZAS. {CMT 0006813} 3. IF actual level is low, THEN 3.1 Initiate makeup. 3.2 Turn VCT HI LVL Divert VLV Q1E21LCV115A to the VCT position.3.3 IF necessary, THEN notify appropriate personnel to locate and isolate system leakage. {CMT 0006813} 3.4 IF desired, and with SS permission, align charging pump suction to the RWST as follows: 3.4.1 RWST TO CHG PUMP [ ] Q1E31LCV115B open. [ ] Q1E21LCV115D open. 3.4.2 VCT OUTLET ISO

 [ ] Q1E21LCV115C closed.   [ ] Q1E21LCV115E closed. 3.4.3 Refer to FNP-1-AOP-1.0, FNP-1-AOP-2.0 and/or  FNP-1-AOP-17.1 as appropriate. 3.5 IF level indication is lost OR it is suspected that the lower level tap has been uncovered, THEN ensure level instruments are properly vented after level has been recovered and stabilized. {AI 2006203596}

06/02/15 13:26:43 FNP-1-ARP-1.4 Page 3 of 4 Version 55.0 UNIT 1 LOCATION DF3 OPERATOR ACTION CONT'D 4. IF the alarm is due to a Charging or Letdown malfunction, THEN go to FNP-1-AOP-16.0, CVCS MALFUNCTION to address the loss of letdown flow.5. Observe CHG HDR PRESS indicator PI-121 and the running Charging Pump Motor Ammeter to ensure proper pump operation. (SOER 97-1) {CMT 0006813} 6. Refer to FNP-1-SOP-2.3, CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR MAKEUP CONTROL SYSTEM. NOTE: The following automatic actions are inhibited: Opening of RWST to charging pump suctions on lo-lo VCT level. Closing of VCT outlet isolations. Auto VCT/RCS makeup. 7. IF LI-115 has failed high, THEN: 7.1 Place VCT HI LVL DIVERT VLV Q1E21LCV115A in the VCT position. 7.2 Manually makeup for VCT level control. 7.3 IF VCT level decreases to 5%, THEN align charging pump suction to the RWST as follows: 7.3.1 RWST TO CHG PUMP

  [ ] Q1E31LCV115B open.    [ ] Q1E21LCV115D open. 7.3.2 VCT OUTLET ISO 
  [ ] Q1E21LCV115C closed.    [ ] Q1E21LCV115E closed. 7.3.3 Refer to FNP-1-AOP-1.0, FNP-1-AOP-2.0 and/or  FNP-1-AOP-17.1 as appropriate.

06/02/15 13:26:43 FNP-1-ARP-1.4 Page 4 of 4 Version 55.0 UNIT 1 LOCATION DF3 NOTE: The following automatic actions are inhibited: Opening of RWST to charging pump suctions on lo-lo VCT level. Closing of VCT outlet isolations. 8. IF LI-112 has failed high, THEN: 8.1 Place Q1E21LCV115A, VCT HI LVL DIVERT VLV in the VCT position.8.2 Manually makeup to VCT, as required to restore level. 8.3 Place LK-112 VCT level controller to manual and adjust to 0 demand. 8.4 Control VCT level by ONE of the following methods: 8.4.1 Alternately place Q1E21LCV115A, VCT HI LVL DIVERT VLV between VCT, AUTO, and RHT positions, as required. 8.4.2 Place Q1E21LCV115A, VCT HI LVL DIVERT VLV in AUTO and manually adjust LK112 VCT level controller to maintain level. 8.5 IF VCT level decreases to 5%, THEN align charging pump suction to the RWST by the following: 8.5.1 RWST TO CHG PUMP [ ] Q1E31LCV115B open. [ ] Q1E21LCV115D open. 8.5.2 VCT OUTLET ISO

  [ ] Q1E21LCV115C closed.    [ ] Q1E21LCV115E closed. 8.5.3 Refer to FNP-1-AOP-1.0, FNP-1-AOP-2.0 and/or  FNP-1-AOP-17.1 as appropriate. 9. IF LI-115 has failed low, THEN: 9.1 Manually makeup for VCT level control. 9.2 Take manual control of the make-up system. 10. IF LI-112 has failed low, THEN: 10.1 Take LK-112 VCT level controller to manual and adjust as necessary10.2 IF necessary, THEN position VCT HI LVL DIVERT VLV Q1E21LCV115A hand switch to desired position. 11. IF LI-112 or LI-115 has failed, THEN initiate steps to have the instrumentation repaired.  (SOER 97-1

References:

A-177100, Sh. 208; D-175039, Sh. 2; PLS Document; U-169636; U-175989; U-260610 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DF4 SETPOINT: 1. High: 65 PSIG F4 2. Low: 12 PSIG VCT PRESS ORIGIN: 1. Pressure Bistable PB-117A from HI-LO Pressure Transmitter (N1E21PT117) 2. 1-PY-117BX Auxiliary Relay from Pressure Transmitter (N1E21PT117) PROBABLE CAUSE NOTE: Zinc Addition System (ZAS) injection will result in a continuous addition of as much as 1.7 gallons per hour to the VCT, when the system is in service. 1. High Pressure a) High VCT Level. b) H2 or N2 Pressure Regulator malfunction. 2. Low Pressure a) H2 or N2 Pressure Regulator malfunction. b) Vent valve malfunction (Q1E21PCV8157 or Q1G22PCV7800) c) Volume Control Tank, pressure control system leak. AUTOMATIC ACTION 1. Closes Volume Control Tank Purge Isolation Valve Q1G22PCV1092. OPERATOR ACTION 1. Determine if pressure is high or low as indicated by PI-117, on the MCB. 2. Monitor VCT level and pressure. 3. IF the VCT level is high, THEN refer to FNP-1-SOP-2.3, CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR MAKEUP CONTROL SYSTEM.4. IF VCT level is normal, THEN refer to FNP-1-SOP-2.5, RCS CHEMICAL ADDITION, VCT GAS CONTROL AND DEMINERALIZER OPERATION.5. Notify appropriate personnel to locate and isolate system leakage if necessary.6. IF the low pressure event is a result of a VCT low level, in which the level indication is lost OR it is suspected that the lower level tap has been uncovered, THEN ensure the level instruments are properly vented after the event. {AI2006203596}

References:

A-177100, Sh. 209; D-175039, Sh. 2; D-175042, Sh. 5; PLS Document; D-177303; D-177514; U-260610; U-176006 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DF5 SETPOINT: 111FF5 VCT TEMP ORIGIN: Temperature Bistable TB-116 from HI Temperature Element (N1E21TE116) PROBABLE CAUSE 1. Letdown flow greater than Charging flow. 2. Low CCW flow to the Letdown Heat Exchanger, Excess Letdown Heat Exchanger or Seal Water Heat Exchanger 3. LTDN HX OUTLET TEMP TK 144 malfunction. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Monitor VCT TEMP TI-116, Letdown HX Outlet Flow FI-150 and LTDN HX TEMP Divert TI-143. 2. Determine the cause of the alarm. 3. IF the cause is low CCW flow, THEN refer to FNP-1-SOP-23.0, COMPONENT COOLING WATER SYSTEM. 4. Adjust charging or letdown flow as required to reduce the Letdown Flow Temperature. 5. Adjust LTDN HX Outlet TEMP TK-144 as required to maintain VCT Temperature < 111°F. 6. IF the elevated VCT temperature is determined to be from letdown, THEN isolate letdown before exceeding 130F seal injection flow. 7. Refer to FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION. 8. Correct the cause of the alarm as soon as possible.

References:

A-177100, Sh. 210; D-175039, Sh. 2; PLS Document;U-176005; U-206610 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DG1 SETPOINT: 155°F G1 BTRS LTDN REHT HX OUTLET TEMP ORIGIN: Temperature Bistable TB-381 from HI Temperature Element (N1G12TE381) PROBABLE CAUSE 1. Malfunction of LTDN REHT HX OUTLET TEMP TK-381A controller. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine actual LTDN REHT HX Outlet TEMP as indicated by TI-381, on the MCB. 2. Take manual control of LTDN REHT HX Outlet TEMP TK-381A and attempt to reduce the temperature by closing the valve. 3. IF temperature can NOT be reduced, THEN place the BTRS Mode SEL Switch N1G12HS2102G to the off position. 4. IF Letdown Reheat Heat Exchanger Outlet Temperature reaches 160°F, THEN verify that LTDN HI TEMP Divert VLV Q1E21TCV143 diverts letdown flow to the VCT. 5. Refer to FNP-1-SOP-3.0, BORON THERMAL REGENERATION SYSTEM.6. Notify appropriate personnel to locate and correct the fault. 7. Return the Boron Thermal Regeneration System to normal.

References:

A-177100, Sh. 211; D-175039, Sh. 2; D-175040; D-177519; D-177176; PLS Document; U-176012; U-260610 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DG2 SETPOINT: 115°F G2 BTRS DISCH HDR ORIGIN: Temperature Bistable TB-386 from TEMP Temperature Element (N1G12TE386) HI PROBABLE CAUSE 1. Letdown Chiller Heat Exchanger, CVCS RTN HDR TEMP TK-386 malfunction. 2. Chilled Water Package tripped. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine actual BTRS RTN HDR Temperature as indicated by TI-386, on the MCB. 2. Take manual control of CVCS RTN HDR TEMP TK-386, and attempt to reduce the temperature by opening the valve. 3. IF temperature can NOT be reduced, THEN place the BTRS Mode SEL Switch N1G12HS2102G to the OFF position. 4. Refer to FNP-1-SOP-3.0, BORON THERMAL REGENERATION SYSTEM.5. Notify appropriate personnel to locate and correct the fault. 6. Return the Boron Thermal Regeneration System to normal.

References:

A-177100, Sh. 212; D-175040; D-177176; PLS Document;U-176021; U-260610 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DG3 SETPOINT: 1. High: 85% Level G3 2. Low: 45% Level BTRS CHLR SRG TANK ORIGIN: Level Bistable LB-380 from Level LVL Transmitter (N1G12LT380) HI-LO PROBABLE CAUSE 1. High Level a) Letdown Chiller Heat Exchanger tube rupture. b) Demineralized Water Supply Valve open for filling Surge Tank. 2. Low Level a) Chilled Water Piping leak or rupture. b) Normal system usage. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine if level is high or low as indicated by Chiller SRG TK LVL LI-380, on the MCB. 2. IF level is high AND the surge tank is NOT being filled, THEN place the BTRS Mode SEL Switch N1G12HS2102G to the OFF position. 3. IF level is low, THEN; A) Notify appropriate personnel to makeup water to the surge tank from the Demineralized Water System (1-BTR-V-7034). B) IF level is decreasing rapidly OR can NOT be restored, THEN place the BTRS Mode SEL Switch N1G12HS2102G to the OFF position. 4. Refer to FNP-1-SOP-3.0, BORON THERMAL REGENERATION SYSTEM.5. Notify appropriate personnel to locate and correct the cause of the alarm. 6. Return the Boron Thermal Regeneration System to normal.

References:

A-177100, Sh. 213; D-175040; D-177176; PLS Document; U-176028; U-260610 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DG4 SETPOINT: 65% Level G4 1A BAT ORIGIN: 1. Level Bistable LB-106C from Level Transmitter LVL (N1E21LT106) LO-LO 2. Level Bistable LB-161C from Level Transmitter (N1E21LT161) NOTE: The minimum required borated water volume for Modes 1 through 4 is 57% (TRS 13.1.7.4; 11,336 gallons in the BAT). The minimum required borated water volume for Modes 5 and 6 is 8% (TRS 13.1.6.6; 2,000 gallons in the BAT). PROBABLE CAUSE 1. 1A Boric Acid Tank Low-Low level due to Boration of the Reactor Coolant System. 2. Boric Acid System Tank or Piping rupture. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine actual tank level as indicated by 1A Boric Acid TK LVL LI-106 and LI-161, on the MCB. 2. IF alarm is due to Reactor Coolant System boration, THEN shift Boric Acid Transfer Pump suction to 1B Boric Acid Tank when the desired level is reached in accordance with FNP-1-SOP-2.6, CVCS BORIC ACID SYSTEM.3. IF a system rupture is indicated, THEN notify plant personnel to locate and isolate the leaking pipe or component. 4. Refill 1A Boric Acid Tank, in accordance with FNP-1-SOP-2.6, CVCS BORIC ACID SYSTEM, as soon as possible. 5. Refer to TRM, TR 13.1, for LCO Requirements.

References:

A-177100, Sh. 214; D-175039, Sh. 3; PLS Document; Technical Specifications; TRM; U-175987; U-176003; U-260610 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DG5 SETPOINT: 65% Level G5 1B BAT ORIGIN: 1. Level Bistable LB-108C from Level Transmitter LVL (N1E21LT108) LO-LO 2. Level Bistable LB-163C from Level Transmitter (N1E21LT163) NOTE: The minimum required borated water volume for Modes 1 through 4 is 57% (TRS 3.1.7.4; 11,336 gallons in the BAT). The minimum required borated water volume for Modes 5 and 6 is 8% (TRS 13.1.6.6; 2,000 gallons in the BAT). PROBABLE CAUSE 1. 1B Boric Acid Tank Low-Low level due to Boration of the Reactor Coolant System. 2. Boric Acid System Tank or Piping Rupture. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine actual tank level as indicated by 1B Boric Acid TK LVL LI-108 and LI-163, on the MCB 2. IF alarm is due to Reactor Coolant System boration, THEN shift Boric Acid Transfer Pump suction to 1A Boric Acid Tank when the desired level is reached in accordance with FNP-1-SOP-2.6, CVCS BORIC ACID SYSTEM.3. IF a system rupture is indicated, THEN notify plant personnel to locate and isolate the leaking pipe or component. 4. Refill 1B Boric Acid Tank, in accordance with FNP-1-SOP-2.6, CVCS BORIC ACID SYSTEM, as soon as possible. 5.Refer to TRM, TR 13.1, for LCO Requirements.

References:

A-177100, Sh. 215; D-175039, Sh. 3; PLS Document; Technical Specifications; TRM; U-175988; U-176004; U-260610 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DH2 SETPOINT: 1. Motor Temperature: Factory Set H2 CHLR 2. Low Oil Temperature: 130°F COMPR 3. High Oil Temperature: 140°F TRBL 4. Low Suction Pressure: 26 PSIG 5. High Discharge Pressure: 150 PSIG 6. Oil Pressure differential: 50 PSID 7. High Discharge Temperature: 230°F ORIGIN: Auxiliary Relay X, located in Chiller Compressor Starter Cabinet 1A or 1B PROBABLE CAUSE 1. Lube Oil Heater not energized when Chiller Unit is off. 2. Low cooling water flow

3. Non-condensables in the line or dirty condenser tubes.

4. Low system loading.

5. Lube Oil Strainer plugged. AUTOMATIC ACTION 1. 1A or 1B Chiller Compressor will stop and remain off until the reset is pushed.OPERATOR ACTION NOTE: BTRS Chiller Compressors are no longer used. 1. Notify appropriate personnel to investigate and correct the cause of the alarm.

References:

A-177100, Sh. 217; D-175040; U-213686; D-177230; D-177233; D-177234; U-167985; U-167986; U-209129; U-209130 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DH3 SETPOINT: Not Applicable H3 CHLR PKG IN ORIGIN: Auxiliary Relay CSSX, located in Chiller Panel 1A or 1B LOCAL CONT PROBABLE CAUSE 1. The Selector Switch for 1A or 1B BTRS Chiller Package in the Local position.AUTOMATIC ACTION NONEOPERATOR ACTION 1. No action is necessary if alarm is due to preplanned operational or maintenance activities; otherwise send appropriate personnel to determine the cause of the alarm. 2. Return the Chiller Package to Remote Control as soon as possible.

References:

A-177100, Sh. 218; D-175040; U-213686; D-177230; D-177234 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DH4 SETPOINT: 1. High: 94% Level H4 1A 2. Low: 74% Level BAT LVL ORIGIN: 1. Level Bistable LB-106A or LB-161A from HI-LO Level Transmitters (N1E21LT106 and N1E21LT161) 2. Level Bistables LB-106B or LB-161B from Level Transmitters (N1E21LT106 and N1E21LT161) PROBABLE CAUSE 1. High Level a) Normal filling from the Recycle Evaporator or Batching Tank. 2. Low Level a) Boration of the Reactor Coolant System. b) Boric Acid System Tank or Piping rupture. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine if level is high or low as indicated by 1A Boric ACID TK LVL LI-106 and LI-161, on the MCB. 2. IF level is high, THEN stop filling the tank. 3. IF level is low, THEN; a) Determine the cause of the alarm. b) IF a system rupture is indicated, THEN notify appropriate personnel to locate and isolate the leaking pipe or component. 4. Refill 1A Boric Acid Tank, in accordance with FNP-1-SOP-2.6, CVCS BORIC ACID SYSTEM, as soon as possible. 5. Refer to TRM, TR 13.1, for LCO Requirements.

References:

A-177100, Sh. 219; D-175039, Sh. 3; PLS Document; Technical Specifications; TRM; U-175987; U-176003; U-260610 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DH5 SETPOINT: 1. High: 94% Level H5 1B 2. Low: 74% Level BAT LVL ORIGIN: 1. Level Bistable LB-108A or LB-163A from HI-LO Level Transmitters (N1E21LT108 and N1E21LT163) 2. Level Bistables LB-108B or LB-163B from Level Transmitters (N1E21LT108 and N1E21LT163) PROBABLE CAUSE 1. High Level a) Normal filling from the Recycle Evaporator or Batching Tank. 2. Low Level a) Boration of the Reactor Coolant System. b) Boric Acid System Tank or Piping rupture. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine if level is high or low as indicated by 1B Boric Acid TK LVL LI-108 and LI-163, on the MCB. 2. IF level is high, THEN stop filling the tank. 3. IF level is low, THEN; a) Determine the cause of the alarm. b) IF a system rupture is indicated, THEN notify appropriate personnel to locate and isolate the leaking pipe or component. 4. Refill 1B Boric Acid Tank, in accordance with FNP-1-SOP-2.6, CVCS BORIC ACID SYSTEM, as soon as possible. 5. Refer to TRM, TR 13.1, for LCO Requirements.

References:

A-177100, Sh. 220; D-175039, Sh. 3; PLS Document; Technical Specifications; TRM; U-175988; U-176004; U-260610 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 2 Version 55.0 UNIT 1 LOCATION DJ2 SETPOINT: 1. High: 120°F J2 2. Low: 70°F BABT TEMP ORIGIN: Temperature Switch (N1E21TIS100) HI-LO PROBABLE CAUSE 1. Malfunction of STM TO BABT N1E21TCV100, IF in service. 2. Loss of Steam Supply. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine if batching tank temperature is high or low as indicated by TIS-100, locally at the tank. 2. IF temperature is high, THEN verify closed STM to BABT N1E21TCV100.3. IF temperature is low AND it is desired to align steam to the BABT, THEN; a) Verify that Auxiliary Steam is available for heating batching tank. b) Open STM to BABT N1E21TCV100. 4. IF temperature is low AND steam is not available to the BABT, THEN; a) IF the BABT temperature >65°F as indicated by TIS-100, locally at the tank, THEN BABT may be transferred to BAT on recirc. b) Check the temperature of the BAT on recirc >70°F for continued batching operations. c) IF BABT temperature < 65°F, AND BAT on recirc > 70°F, THEN the contents of the BABT may be transferred to the BAT on recirc. d) For each subsequent BABT addition to the on recirc BAT, items 4a), 4b) and 4c) must be performed to ensure the BAT temperature does not go less than 65°F due to batching evolutions. 5. Refer to FNP-1-SOP-2.6, CHEMICAL AND VOLUME CONTROL SYSTEM BORIC ACID SYSTEM. 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 2 of 2 Version 55.0 UNIT 1 LOCATION DJ2 OPERATOR ACTION CONT'D 6. Verify Boric Acid Batching Tank Condensate Return Unit is functioning properly.7. IF steam aligned to the BABT, THEN Batching Tank Temperature can be maintained manually by closely monitoring tank temperature and opening or closing STM TO BABT N1E21TCV100. 8. IF the alarm is due to a system malfunction, THEN notify appropriate personnel to determine and correct the cause of the alarm as soon as possible.

References:

A-177100, Sh. 222; D-175039, Sh. 3; D-175006; D-177869; PLS Document 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DJ3 SETPOINT: Not Applicable J3 1A OR 1B BA XFER PUMP IN ORIGIN: 1. Selector Switch (Q1E21HS360lAA-A) LOCAL CONT 2. Selector Switch (Q1E21HS360lBB-B) PROBABLE CAUSE 1. The Selector Switch for 1A or 1B Boric Acid Transfer Pump located on Hot Shutdown Panel or Selector Switch Box, in the Local position. AUTOMATIC ACTION NONEOPERATOR ACTION 1. No action is necessary if alarm is due to preplanned operational or maintenance activities; otherwise send appropriate personnel to determine the cause of the alarm. 2. Return Boric Acid Transfer Pump control to Remote as soon as possible.

References:

A-177100, Sh. 223; D-177224, Sh. 1 & 2 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DJ4 SETPOINT: 70°F J4 1A BAT TEMP ORIGIN: Temperature Switch (N1E21TIS107-N) LO PROBABLE CAUSE 1. Auxiliary Building temperature is less than 70°F. AUTOMATIC ACTION NONEOPERATOR ACTION NOTE: The TRM minimum tank temperature is 65°F. 1. Determine actual tank temperature as indicated by TIS-107, locally at the tank.2. IF required, THEN notify appropriate personnel to determine and correct the cause of the alarm. 3. Refer to TRM, TR 13.1, for LCO Requirements.

References:

A-177100, Sh. 224; A-181541; D-175039, Sh. 3; U-260331; PLS Document; Technical Specifications; TRM 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DJ5 SETPOINT: 70°F J5 1B BAT TEMP ORIGIN: Temperature Switch (N1E21TIS109-N) LO PROBABLE CAUSE 1. Auxiliary Building temperature is less than 70°F. AUTOMATIC ACTION NONEOPERATOR ACTION NOTE: The TRM minimum tank temperature is 65°F. 1. Determine actual tank temperature as indicated by TIS-109, locally at the tank.2. IF required, THEN notify appropriate personnel to determine and correct the cause of the alarm. 3. Refer to TRM, TR 13.1, for LCO Requirements.

References:

A-177100, Sh. 225; A-181541; D-175039, Sh. 3; U-260331; PLS Document; Technical Specifications; TRM 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DK1 SETPOINT: +/- 8 GPM K1 TOTAL RX MKUP FLOW DEV ORIGIN: 1-MUX7 Auxiliary Relay Contact, actuated HI-LO by Flow Transmitter (N1E21FT168) PROBABLE CAUSE 1. Total Makeup greater or less than that called for by flow controller after 75 +/- 11.25 seconds. Caused by malfunction of RMW TO BLENDER Q1E21FCV114B or 1A and 1B Reactor Makeup Water Pump tripped. AUTOMATIC ACTION 1. Closes MKUP TO CHG PUMP SUCTION HDR Q1E21FCV113B. 2. Closes MKUP TO VCT Q1E21FCV114A. OPERATORACTION1. Take manual control of the makeup system in accordance with FNP-1-SOP-2.3, CVCS REACTOR MAKEUP CONTROL SYSTEM, and monitor Volume Control Tank Level. IF the cause of the alarm is known and the makeup system is being controlled by the operator, THEN it is permissible to open MKUP TO VCT Q1E21FCV114A and MKUP TO CHG PUMP SUCTION HDR Q1E21FCV113B by placing their respective hand switches in open as necessary to complete the desired makeup. 2. Determine the cause of the alarm. 3. Notify appropriate personnel to correct the cause of the alarm. 4. Return the Makeup System to Automatic as soon as possible.

References:

A-177100, Sh. 226; D-175039, Sh. 2; D-177097; D-177098; D-177509; D-177510; D-177511; U-176206; PLS Document 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DK2 SETPOINT: +/- 2 GPM K2 BA FLOW DEV HI-LO ORIGIN: 1-MUX6 Auxiliary Relay Contact, actuated by Flow Transmitter (Q1E21FT113) PROBABLE CAUSE 1. Boric Acid flow greater or less than that called for by flow controller after 75 +/- 11.25 seconds. Caused by malfunction of BORIC ACID TO BLENDER Q1E21FCV113A or 1A or 1B Boric Acid Transfer Pump tripped.AUTOMATIC ACTION 1. Closes MKUP TO CHG PUMP SUCTION HDR Q1E21FCV113B. 2. Closes MKUP TO VCT Q1E21FCV114A. OPERATOR ACTION 1. Take manual control of the makeup system in accordance with FNP-1-SOP-2.3, CVCS REACTOR MAKEUP CONTROL SYSTEM, and monitor Volume Control Tank Level OR 2 IF the cause of the alarm is known and the makeup system is being controlled by the operator or in Automatic, THEN it is permissible to open MKUP TO VCT Q1E21FCV114A and MKUP TO CHG PUMP SUCTION HDR Q1E21FCV113B by placing their respective hand switches in open as necessary to complete the desired makeup. 3. Determine the cause of the alarm. 4. Notify appropriate personnel to correct the cause of the alarm. 5. Return the Makeup System to Automatic as soon as possible.

References:

A-177100, Sh. 227; D-175039, Sh. 2; D-177097; D-177098; D-177509; D-177510; D-177379; PLS Document; U-176025 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DK3 SETPOINT: 20% VCT Level K3 AUTO MKUP START SIGNAL ORIGIN: 1. 1-LY-115CX Auxiliary Relay actuated BLOCKED by Level Transmitter (Q1E21LT115) 2. Selector Switch (N1E21HS2100Q) PROBABLE CAUSE 1. MKUP MODE SEL SWITCH not in AUTO position and Volume Control Tank level less than 20%. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Makeup to the Reactor Coolant System in accordance with FNP-1-SOP-2.3, CVCS REACTOR MAKEUP CONTROL SYSTEM.

References:

A-177100, Sh. 228; D-175039, Sh. 2; D-177097; D-177303; PLS Document 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DK4 SETPOINT: 125°F K4 1A BAT TEMP ORIGIN: Temperature Switch (N1E21TIS107-N) HI PROBABLE CAUSE 1. High Temperature of Boric Acid added to tank during filling. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine actual tank temperature as indicated by TIS-107, locally at the tank.2. Refer to FNP-1-SOP-2.6, CHEMICAL AND VOLUME CONTROL SYSTEM, BORIC ACID SYSTEM. 3. IF required, THEN notify appropriate personnel to determine and correct the cause of the alarm.

References:

A-177100, Sh. 229; A-181541; D-175039, Sh. 3; U-260331; PLS Document 06/02/15 13:26:43 FNP-1-ARP-1.4 Page 1 of 1 Version 55.0 UNIT 1 LOCATION DK5 SETPOINT: 125°F K5 1B BAT TEMP ORIGIN: Temperature Switch (N1E21TIS109-N) HI PROBABLE CAUSE 1. High Temperature of Boric Acid added to tank during filling. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine actual tank temperature as indicated by TIS-109, locally at the tank.2. Refer to FNP-1-SOP-2.6, CHEMICAL AND VOLUME CONTROL SYSTEM, BORIC ACID SYSTEM. 3. IF required, THEN notify appropriate personnel to determine and correct the cause of the alarm.

References:

A-177100, Sh. 230; A-181541; D-175039, Sh. 3; U-260331; PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 UNIT 1 Version 36.0 FARLEY NUCLEAR PLANT ANNUNCIATOR RESPONSE PROCEDURE FNP-1-ARP-1.8SAFE TYMAIN CONTROL BOARD ANNUNCIATOR PANEL H RE LAT EDPROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORYSECTIONSContinuous: ALL

Reference:

NONE Information: NONE Approved: David L Reed Effective Date: 05/21/2015 Operations 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 TABLE OF CONTENTS Procedure Contains Number of Pages Annunciator Window Panel ......................2 HA1 ...........................................................1 HA2 ...........................................................1 HA3 ...........................................................1 HA4 ...........................................................1 HA5 ...........................................................2 HB1 ...........................................................1 HB2 ...........................................................1 HB4 ...........................................................1 HB5 ...........................................................1 HC1 ...........................................................3 HC2 ...........................................................1 HC3 ...........................................................1 HC4 ...........................................................1 HC5 ...........................................................1 HD1 ...........................................................3 HD2 ...........................................................1 HD3 ...........................................................1 HD4 ...........................................................1 HD5 ...........................................................1 HE1 ...........................................................1 HE2 ...........................................................1 HE3 ...........................................................1 HE4 ...........................................................2 HE5 ...........................................................2 HF1 ...........................................................1 HF2 ...........................................................1 HF3 ...........................................................1 HF4 ...........................................................1 HF5 ...........................................................1 HG1 ...........................................................2 HG2 ...........................................................2 HG3 ...........................................................2 HG4 ...........................................................1 HG5 ...........................................................2 HH1 ...........................................................2 HH2 ...........................................................2 HH3 ...........................................................2 HH4 ...........................................................2 HH5 ...........................................................1 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 1 Version 36.0 UNIT 1 VERSION SUMMARY Version 36.0 DESCRIPTION CR 10064507 - HH5, modified step 2 to check RCDT parameters for increasing trends RecordsNo records are generated from this procedure 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 MAIN CONTROL BOARD ANNUNCIATOR PANEL HA1 B1 C1 D1 E1 PRZR LVL PRZR PRZR PRESS PRZR PRESS REL VLV HI LVL HI HI-LO REL VLV 445A 444B/445A RX TRIP OR OPEN ALERT B/U HTRS ON A2 B2 C2 D2 E2 PRZR LVL PRZR PRZR PRZR PRESS SAFETY VLV DEV HI LVL DEV HI-LO PRESS SI 8010A/B/C B/U HTRS ON LO ALERT PORV BLOCK OPEN P-11 A3 C3 D3 E3 PRZR LVL LO PRZR PRESS PRZR CONT PRT HTRS OFF LO PRESS OUTPUT TEMP HI LTDN SEC SI ALERT HI A4 B4 C4 D4 E4 PRZR PRZR PRZR HTRS PRZR HTR PRT LVL SAFETY VLV SPRAY LINE IN CONT TRBL HI-LO TEMP HI LOOP 1A/1B LOCAL CONT TEMP LO A5 B5 C5 D5 E5 PRZR PORV PRZR PRZR PRZR HTR PRT PRESS TEMP HI SRG LINE VAP OR LIQ BKR HI TEMP LO TEMP HI TRIPPED 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 MAIN CONTROL BOARD ANNUNCIATOR PANEL HF1 G1 H1 RX COOLANT RCP 1A BRG RCP 1A BRG LOOPS UPPER/LOWER UPPER/LOWER TAVG DEV OIL RES OIL RES HI-LO HI LVL LO LVL F2 G2 H2 RX COOLANT RCP 1B BRG RCP 1B BRG LOOPS UPPER/LOWER UPPER/LOWER T DEV OIL RES OIL RES HI-LO HI LVL LO LVL F3 G3 H3 TAVG/TREF RCP 1C BRG RCP 1C BRG DEV UPPER/LOWER UPPER/LOWER OIL RES OIL RES HI LVL LO LVL F4 G4 H4 RX COOLANT OMS RCP LOOPS REL VLV VIB 1A, 1B OR 1C PATH CLOSED TRBL TAVG LO-LO AT LO TEMP F5 G5 H5 RX COOLANT SOLID RX VESSEL LOOPS RCS PRESS FLANGE LKOF TAVG HI HI TEMP HI 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HA1 SETPOINT: 92% of Span A1 PRZR LVL ORIGIN: Pressurizer High Water Level Bistables from HI PRZR Level Transmitters LT-459, LT-460 or LT-461 RX TRIP 1/3 Detectors ALERT PROBABLE CAUSE 1. Pressurizer Level Instrument or Control System malfunction. 2. Charging or Letdown System malfunction.

3. Void formation in the Reactor Coolant System. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Determine actual pressurizer water level as indicated by LI-459, LI-460 AND LI-461, on the MCB. 2.IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION. 3.IF a charging OR letdown system malfunction exists, THEN go to FNP-1-AOP-16.0 CVCS MALFUNCTION. 4.Refer to Technical Specifications section on Instrumentation for LCO Requirements.

References:

A-177100, Sh. 356; U-260610; U-198768; U-266647 PLS Document; Technical Specifications 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HA2 SETPOINT: 5% of Span above Level Program A2 PRZR LVL ORIGIN: Level Bistable LB-459D from Level Transmitter DEV HI LT-459 or LT-461 and TY-408 median TAVG. B/U HTRS ON PROBABLE CAUSE 1. Pressurizer Level Instrument or Control System malfunction. 2. Plant Transient while in manual rod control.

3. Rod Control System malfunction.

4. Charging or Letdown System malfunction. AUTOMATIC ACTION 1. Pressurizer Backup Heaters energize. OPERATOR ACTION 1.Place turbine load on HOLD. 2.Check pressurizer level indications and determine the actual level deviation.3.IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION. 4.Ensure that the pressurizer backup heaters are energized. 5.IF required, THEN take manual control of CHG FLOW FK 122 and decrease charging flow to return pressurizer level to the program band. 6.Determine the cause of the level deviation by checking: 5.1 Charging flow 5.2 Letdown flow 5.3 BTRS flow 5.4 Charging pump status 7.IF the alarm was caused by a plant transient, THEN control the transient and return Pressurizer Level to normal. 8. IF a charging OR letdown system malfunction exists, THEN go to FNP-1-AOP-16.0, CVCS MALFUNCTION.

References:

A-177100, Sh. 357; U-260610; D-177109; D-177111; D-177112; D-177113; U-266647 PLS Document; Technical Specifications 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HA3 SETPOINT: 15% of Level Span A3 PRZR LVL LO ORIGIN: Level Bistable LB-459C or LB-460C from Level HTRS OFF Transmitters LT-459 and LT-460 respectively (or LT-461 when selected in place of LT-459 or LT-460). LTDN SEC PROBABLE CAUSE 1. Pressurizer Level Instrument or Control System malfunction. 2. Charging System malfunction.

3. Primary Coolant leak.

4. Plant Transient. AUTOMATIC ACTION 1. Pressurizer backup AND proportional heaters de-energized. 2. LB459C closes LTDN LINE ISO Q1E21LCV459 and LB460C closes LTDN LINE ISO Q1E21LCV460. 3. LTDN ORIF ISO VALVES Q1E21HV8149A, B & C close. OPERATOR ACTION 1.Check indications and determine actual pressurizer level and pressure. 2.Ensure that the automatic actions have occurred. 3.IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION. 4.IF actual level is low, THEN take actions as necessary to increase charging flow and maintain pressurizer level. 5.IF a primary coolant leak is indicated, THEN perform the actions required by the appropriate AOP or EEP. a) FNP-1-AOP-1.0, RCS LEAKAGE. b) FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION c) FNP-1-AOP-2.0, STEAM GENERATOR TUBE LEAKAGE 6. IF a charging OR letdown system malfunction exists, THEN go to FNP-1-AOP-16.0, CVCS MALFUNCTION.

References:

A-177100, Sh. 358; U-260610; D-177179; D-177376; D-177377; D-177378; D-177585; D-177586; U-266647 PLS Document; Technical Specifications 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HA4 SETPOINT: Ambient 20FA4 PRZR ORIGIN: 1. Temp. Bistable TB-465 from Temp. Element SAFETY VLV TE-465 monitoring valve Q1B13V031C. TEMP HI 2. Temp. Bistable TB-467 from Temp. Element TE-467 monitoring valve Q1B13V031B. 3. Temp. Bistable TB-469 from Temp. Element TE-469 monitoring valve Q1B13V031A. PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. A Pressurizer Safety Valve has lifted or is leaking. 2. Instrument failure. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Determine which valve has lifted or is leaking, by utilizing TI-465, TI-467 and TI-469, located on the MCB. 2.Monitor pressurizer pressure and level and pressurizer relief tank pressure, level and temperature. 3.IF a safety valve has lifted due to high system pressure, THEN verify that the safety valve re-seats when system pressure has been reduced. 4.IF a safety valve has lifted due to an instrument failure, THEN refer to annunciator HC1, PRZR PRESS HI-LO. 5.IF a safety valve has lifted and reseats, and subsequently lifts and reseats at approximately the same RCS pressure, THEN maintain RCS pressure less than lift pressure AND comply with Tech Specs 3.4.1 and 2.1.1 limits. 6.IF a Safety Valve is leaking OR does NOT re-seat, THEN: a) Perform the actions required by FNP-1-AOP-1.0, RCS LEAKAGE. b) Refer to the Technical Specifications and TRM for LCO Requirements related to RCS leakage and safety valve operation. 7.IF the alarm was due to an instrument fault, THEN notify appropriate personnel to determine the cause and correct the fault. 8.Refer to FNP-0-SOP-0, GENERAL INSTRUCTIONS TO OPERATIONS PERSONNEL, for reporting requirements.

References:

A-177100, Sh. 359; D-175037, Sh. 2; U-266647 PLS Document; Technical Specifications, Technical Requirements Manual 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HA5 SETPOINT: Ambient 20FA5 PRZR PORV ORIGIN: Temp. Bistable TB-463 from Temp. Element TE-463 TEMP HI PROBABLE CAUSE 1. One or both PRZR PORVs Q1B31PCV444B and Q1B31PCV445A has lifted or is leaking.2. Instrument failure. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Verify an actual temperature alarm by utilizing TI-463 and comparing the indication to containment ambient temperature. 2.Monitor pressurizer pressure and level and pressurizer relief tank pressure, level and temperature. 3.IF a relief valve has lifted due to high system pressure, THEN ensure that the relief valve closes when system pressure has been reduced. 4.IF a relief valve has lifted due to an instrument failure AND actual PRZR pressure is low, THEN close the affected valve in manual and refer to annunciator window HC1, PRZR PRESS HI-LO. NOTE: Technical Specification 3.4.11 addresses operation with a PRZR PORV ISO valve closed. 5 IF the alarm is determined to be caused by relief valve leakage, THEN isolate both relief valves by closing both PRZR PORV ISOs Q1B31MOV8000A & B and determine the leaking valve as follows: a) Allow relief line temperature to decrease sufficiently that temperature changes can be observed. b) Open PRZR PORV ISO Q1B31MOV8000A and monitor the relief line temperature. c) IF temperature does NOT increase, THEN no further action is necessary. d) IF a temperature rise is observed, THEN close PRZR PORV ISO Q1B31MOV8000A and open PRZR PORV ISO Q1B31MOV8000B. e) Verify that the relief line temperature decreases to ambient 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 LOCATION HA5 OPERATOR ACTION (Cont.) 6. IF the alarm was due to an instrument fault, THEN notify appropriate personnel to determine the cause and correct the fault. 7. Refer to FNP-0-SOP-0, GENERAL INSTRUCTIONS TO OPERATIONS PERSONNEL, for reporting requirements.

References:

A-177100, Sh. 360; D-175037, Sh. 2; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HB1 SETPOINT: 70% of Level Span B1 PRZR ORIGIN: Level Bistable LB-460C from Level Transmitter LVL HI LT-460 or LT-461 PROBABLE CAUSE 1. Pressurizer Level Instrument or Control System malfunction. 2. Charging or Letdown System malfunction.

3. Void formation in the Reactor Coolant System. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Determine actual pressurizer water level as indicated by LI-459, LI-460 AND LI-461, on the MCB. 2.IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION 3.IF a charging OR letdown system malfunction exists, THEN go to FNP-1-AOP-16.0, CVCS MALFUNCTION 4.Refer to Technical Specifications 3.3.1 and 3.4.9 for LCO requirements.

References:

A-177100, Sh. 361; U-260610; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HB2 SETPOINT: 5% of span below Level Program B2 PRZR ORIGIN: Level Bistable LB- LVL DEV Transmitter LT-459 (or LT-461 when selected in place of LT-459) and TY459 level program (derived from TY-408 median TAVG) LO PROBABLE CAUSE 1. Pressurizer Level Instrument or Control System malfunction. 2. Plant Transient.

3. Rod Control System malfunction.

4. Charging or Letdown System malfunction.

5. RCS leakage. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Place turbine on HOLD. 2.Check pressurizer level indications and determine the actual level deviation. 3.IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION4.IF required, THEN take manual control of CHG FLOW FK 122 and increase charging flow to return pressurizer level to the program band. 5.Determine the cause of the level deviation by checking: Charging Flow; Letdown Flow, and if applicable BTRS Flow. 6.IF the alarm was caused by a plant transient, THEN control the transient and return Pressurizer level to normal. 7.IF a charging OR letdown system malfunction exists, THEN go to FNP-1-AOP-16.0, CVCS MALFUNCTION 8. Maintain pressurizer level at the program level until the affected component(s) can be restored to normal operation. 9. IF a primary coolant leak OR rupture is indicated, THEN perform the actions of the appropriate AOP or EEP. a) FNP-1-AOP-1.0, RCS LEAKAGE.

b) FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION c) FNP-1-AOP-2.0, STEAM GENERATOR TUBE LEAKAGE

References:

A-177100, Sh. 362; U-260610; U-266647 PLS Document; Technical Specifications; West 7300 Dwgs 7378D53, 7378D71, 7378D66 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HB4 SETPOINT: 500FB4 PRZR ORIGIN: 1. Loop 1A: Temp Bistable TB-451 from TE-451 SPRAY LINE 2. Loop 1B: Temp Bistable TB-452 from TE-452 LOOP 1A/1B TEMP LO PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. Insufficient Spray Flow. 2. Loop 1A or 1B idle.

3. Instrument malfunction.

4. Normal cooldown / depressurization. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Determine the actual spray line temperature and to which spray loop the alarm is attributed as indicated by TI-451 and TI-452, on the MCB. 2.Monitor pressurizer vapor temperature (TI-454 on MCB), spray line temperatures and cold leg reactor coolant temperatures. 3.IF the alarm is due to Loop 1A OR 1B being idle, THEN ensure that the spray valve for the affected loop is closed to preclude backflow from the operating loop which would deplete the total spray flow to the pressurizer. CAUTION: Spray Flow should not be initiated if the temperature difference between the Pressurizer and the spray fluid is greater than 320°F. 4.Energize sufficient pressurizer backup heaters to initiate spray flow to maintain spray line temperature. 5.IF the alarm is due to insufficient spray flow, THEN determine and correct the cause for the decreased flowrate. 6.Refer to TRM 13.4.2 for LCO requirements.

References:

A-177100, Sh. 364; U-260610; D-175037, Sh. 2; U-266647 PLS Doc; Technical Requirements Manual 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HB5 SETPOINT: 500FB5 PRZR ORIGIN: Temp. Bistable TB-450 from Temp. Element TE-450 SRG LINE TEMP LO PROBABLE CAUSE 1. Insufficient Spray Flow. 2. Loop 1A or 1B idle.

3. Instrument malfunction.

4. Normal cooldown / depressurization. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Determine the actual surge line temperature as indicated by TI-450, on the MCB.2.Monitor pressurizer vapor temperature, surge line temperatures and cold leg reactor coolant temperatures. 3.IF the alarm is due to Loop 1A OR 1B being idle, THEN ensure that the spray valve for the affected loop is closed to preclude backflow from the operating loop into the idle loop which would deplete the total spray flow to the pressurizer. CAUTION: Spray Flow should not be initiated if the temperature difference between the Pressurizer and the spray fluid is greater than 320°F. 4.Energize sufficient pressurizer backup heaters to initiate spray flow to maintain spray line temperature. 5.IF the alarm is due to insufficient spray flow, THEN determine and correct the cause for the decreased flowrate. 6.Refer to TRM 13.4.2 for LCO requirements.

References:

A-177100, Sh. 365; U-260610; D-175037, Sh. 2; U-266647 PLS Document; Technical Requirements Manual 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 3 Version 36.0 UNIT 1 LOCATION HC1 SETPOINT: 1. High Pressure: 2310 PSIG C1 2. Low Pressure: 2185 PSIG PRZR PRESS HI-LO ORIGIN: 1. Pressure Bistable PB-445C (high) from Pressure Transmitter PT-445.

2. Pressure Bistable PB-445B (low) from Pressure Transmitter PT-445. PROBABLE CAUSE 1. High Pressure a) Malfunction of Pressurizer Heaters and/or Spray Valves.

b) Plant Transient c) Rod Control System malfunction 2. Low Pressure a) Primary Coolant leakage or rupture b) Malfunction of Pressurizer Heaters and/or Spray Valves. c) Power Operated Relief Valve leakage or malfunction. d) Plant Transient e) Rod Control System malfunction f) Uncontrolled or excessive cooldown g) Normal cooldown / depressurization 3. Instrument failure AUTOMATIC ACTION NONEOPERATOR ACTION 1. Check pressurizer pressure indications and determine if pressure is high or low.2. Check the status of the following and take manual control as necessary: 2.1 Pressurizer spray valves. 2.2 Pressurizer power operated relief valves (PORVs). 2.3 Pressurizer heaters.

3. IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION.

06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 3 Version 36.0 UNIT 1 LOCATION HC1 OPERATOR ACTION (cont.) NOTE:WHEN transitioning to FNP-1-EEP-0.0 AND at the Shift Supervisors direction, it is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0.0. While the other team member verifies a Reactor Trip, THEN trips the appropriate RCP(s) before finishing the Immediate Operator Actions of FNP-1-EEP-0.0. (AI 2004200019) Westinghouse analysis and industry experience has shown that a failed open spray valve will require stopping two RCPs to stop spray flow. 4. IF pressurizer pressure is decreasing due to a mechanically stuck open spray valve PCV-444 C(D), THEN perform the following. 4.1 Trip the reactor prior to pressure reaching 2100 PSIG, AND go to FNP-1-EEP-0.0, REACTOR TRIP OR SAFETY INJECTION. (AI-2004200019)4.2 Verify 1A and 1B RCPs secured. 5. IF pressurizer pressure is decreasing due to a stuck open PORV, THEN close the associated PORV block valve. 6. Maintain reactor coolant system pressure at 2235 psig with the affected component(s) in manual control until automatic operation can be restored. 7. IF a Power Operated Relief Valve is leaking OR is malfunctioning, THEN isolate the affected relief valve and refer to Tech. Spec. 3.4.11 for LCO requirements. 8. IF the pressurizer power operated relief valves operated, THEN: a) Refer to FNP-1-SOP-1.2, REACTOR COOLANT PRESSURE RELIEF SYSTEM, for cooldown of the pressurizer relief tank. b) Refer to FNP-0-SOP-0, GENERAL INSTRUCTIONS TO OPERATIONS PERSONNEL, for reporting requirements. 9. IF the alarm was caused by a plant transient, THEN control the transient and return pressurizer pressure to normal. 10. IF a rod control system malfunction exists, THEN take MANUAL rod control in accordance with FNP-1-AOP-19.0, MALFUNCTION OF ROD CONTROL SYSTEM. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 3 of 3 Version 36.0 UNIT 1 LOCATION HC1 OPERATOR ACTION (cont.) 11. IF plant is in MODES 3, 4 or 5 AND pressurizer spray valve PCV-444C (D) fails open and cannot be closed, THEN verify 1A AND 1B RCPs secured.12. IF a primary coolant leak OR rupture is indicated, THEN perform the actions of the appropriate AOP or EEP. a) FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION b) FNP-1-AOP-1.0, RCS LEAKAGE c) FNP-1-AOP-2.0, STEAM GENERATOR TUBE LEAKAGE 13. Refer to Technical Specification 3.4.11 for LCO Requirements

References:

A-177100, Sh. 366; U-260610; D-175037, Sh. 2; U-266647 PLS Document; Westinghouse Dwg 7378D44; Technical Specifications 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HC2 SETPOINT: 1. High Pressure: 2385 PSIG C2 2. Low Pressure: 1865 PSIG PRZR a) Time Constant: Lead 10 seconds HI-LO PRESS Lag 1 second ALERT ORIGIN: 1. High Pressure Bistables PT-455, PT-456 and PT-457. 1/3 coincidence 2. Low Pressure Rate Compensated Bistables from PT-455, PT-456 and PT-457 1/3 coincidence PROBABLE CAUSE 1. High Pressure a) Pressurizer Pressure Control System malfunction. b) High Pressure from a rapid decrease in turbine power.

2. Low Pressure a) Primary Coolant leakage or rupture.

b) Pressurizer Spray or Relief Valve failed open. c) Pressurizer Heater or Pressure Control System malfunction. d) Normal cooldown / depressurization.

3. Instrument failure or in test. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Check pressurizer pressure indications and determine if pressure is high or low. 2.IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION.3.Monitor pressurizer pressure, level and pressure control system parameters. 4.IF actual pressure is 1865 PSIG or 2385 PSIG, THEN verify reactor trip and go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. 5.IF either the pressurizer heaters, spray valves OR power operated relief valves are malfunctioning, THEN take manual control of the affected component. Refer to annunciator window HC1, PRZR PRESS HI-LO. 6.IF a PORV is leaking OR has failed to close, THEN isolate the affected relief valve. 7.IF a Power Operated Relief Valve has opened, THEN refer to FNP-0-SOP-0.0, INSTRUCTIONS TO OPERATIONS PERSONNEL, for reporting requirements.

References:

A-177100, Sh. 367; U-260610; U-198768; U-266647 PLS Document; Technical Specifications; D-175037, Sh. 2. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HC3 SETPOINT: 1850 PSIG C3 PRZR PRESS ORIGIN: Pressure Bistables PB-455D, PB-456D and PB-457D LO Pressure Transmitters PT-455, PT-456, and PT-457 SI ALERT 1/3 Detectors PROBABLE CAUSE 1. Reactor Coolant System leakage or rupture. 2. Pressurizer Spray or Power Operated Relief Valve failed open.

3. Pressure Control System malfunction

4. Instrument failure or in test.

5. Normal cooldown / depressurization. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Check pressurizer pressure indications and determine the actual pressure. 2.IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION. 3.Check indications of pressurizer level, pressure, spray and relief valves and attempt to determine the cause of the low pressure. 4.IF actual pressure is 1850 PSIG, THEN verify safety injection and go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. 5.IF a pressurizer pressure control system failure is indicated, THEN take manual control of the affected component. Refer to annunciator window HC1, PRZR PRESS HI-LO. 6.IF a Power Operated Relief Valve is leaking OR has failed to close, THEN isolate the affected relief valve. 7.Refer to the Technical Specifications for LCO requirements.

References:

A-177100, Sh. 368; U-260610; U-198768; U-266647 PLS Document; Technical Specifications 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HC4 SETPOINT: Not Applicable C4 PRZR HTRS ORIGIN: 1. Heater Group 1A Selector Switch IN 2. Heater Group 1B Selector Switch LOCAL CONT PROBABLE CAUSE 1. The Selector Switch for Pressurizer Heaters Group 1A or 1B, located on Hot Shutdown Panel A or C, in the Local position. AUTOMATIC ACTION NONEOPERATOR ACTION 1.No action is necessary if the alarm is due to preplanned operational or maintenance activities; otherwise send appropriate personnel to determine the cause of the alarm. 2.Return the selector switch to the Remote position as soon as possible.

References:

A-177100, Sh. 369; D-177109; D-177111 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HC5 SETPOINT: 666FC5 PRZR ORIGIN: 1. Vapor Temperature: Temperature Bistable VAP OR LIQ TB-454 from Temperature Element TE-454. TEMP HI 2. Liquid Temperature: Temperature Bistable TB-453 from Temperature Element TE-453. PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. Pressurizer Pressure Control System malfunction. 2. Instrument failure. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Determine the actual temperature as indicated on TI-453 and TI-454, on the MCB. 2.Monitor pressurizer temperature, pressure and level. NOTE: For a temperature of 666°F, pressure should be approximately 2445 PSIG. 3.Make a comparison between pressurizer pressure and the highest reading pressurizer temperature instrument and determine if an actual temperature increase is indicated. 4.IF pressure is high, THEN manually initiate pressurizer spray to reduce pressure.5.Refer to annunciator window HC1, PRZR PRESS HI-LO. 6.IF the alarm was due to an instrument OR component failure, THEN notify appropriate personnel to determine the cause and correct the fault.

References:

A-177100, Sh. 370; U-260610; D-175037, Sh. 2; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 3 Version 36.0 UNIT 1 LOCATION HD1 SETPOINT: 1. High Pressure: 2335 PSIG D1 2. Low Pressure: 70% indicated demand on Master PRZR PRESS Pressure Controller PC444A (equivalent to a REL VLV 445A nominal pressure of 2210 PSIG) OR B/U HTRS ON ORIGIN: 1. Pressure Bistable PB-445A from Pressure Transmitter PT-445A. 2. Pressure Bistable PB-444F from Pressure Transmitter PT-444 via Master Pressure Controller PC444A.PROBABLE CAUSE 1. High Pressure a) Malfunction of Pressurizer Heaters and/or Spray Valves. b) Plant Transient c) Rod Control System malfunction 2. Low Pressure a) Primary Coolant leakage or rupture b) Malfunction of Pressurizer Heaters and/or Spray Valves. c) Power Operated Relief Valve leakage or malfunction. d) Plant Transient e) Rod Control System malfunction f) Uncontrolled or excessive cooldown 3. Instrument failure AUTOMATIC ACTION 1. At 2335 PSIG, PRZR PORV Q1B31PCV445A opens with handswitch in 'AUTO'.2. At 70% Master Pressure Controller demand (i.e. 30% controller output equivalent to a nominal pressure of 2210 PSIG), Backup Heater groups in 'AUTO' energize. OPERATOR ACTION 1. Check actual pressurizer pressure indications to determine the cause of the alarm. 2. Check the status of the following and take manual control as necessary: 2.1 Pressurizer spray valves. 2.2 Pressurizer power operated relief valves. 2.3 Pressurizer heaters. 3. IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 3 Version 36.0 UNIT 1 LOCATION HD1 OPERATOR ACTION (cont.) NOTE:WHEN transitioning to FNP-1-EEP-0.0 AND at the Shift Supervisors direction, It is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0.0. While the other team member verifies a Reactor Trip, THEN trips the appropriate RCP(s) before finishing the Immediate Operator Actions of FNP-1-EEP-0.0. (AI 2004200019) Westinghouse analysis and industry experience has shown that a failed open spray valve will require stopping two RCPs to stop spray flow. 4. IF pressurizer pressure is decreasing due to a mechanically stuck open spray valve PCV-444 C(D), THEN perform the following: 4.1 Trip the reactor prior to pressure reaching 2100 PSIG, AND go to FNP-1-EEP-0.0, REACTOR TRIP OR SAFETY INJECTION.(AI-2004200019)4.2 Verify 1A and 1B RCPs secured. 5. IF pressurizer pressure is decreasing due to a stuck open PORV, THEN close the associated PORV block valve. 6. Maintain reactor coolant system pressure at 2235 psig with the affected component(s) in manual control until automatic operation can be restored. 7. IF a Power Operated Relief Valve is leaking OR is malfunctioning, THEN isolate the affected relief valve and refer to Tech. Spec. 3.4.11 for LCO requirements. 8. IF the pressurizer power operated relief valves operated, THEN: a) Refer to FNP-1-SOP-1.2, REACTOR COOLANT PRESSURE RELIEF SYSTEM, for cooldown of the pressurizer relief tank. b) Refer to FNP-0-SOP-0, GENERAL INSTRUCTIONS TO OPERATIONS PERSONNEL, for reporting requirements. 9. IF a Rod Control System malfunction exists, THEN take MANUAL rod control in accordance with FNP-1-AOP-19.0, MALFUNCTION OF ROD CONTROL SYSTEM. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 3 of 3 Version 36.0 UNIT 1 LOCATION HD1 OPERATOR ACTION (cont.) 10. IF plant is in Modes 3, 4 or 5 AND pressurizer spray valve PCV-444C (D) fails open and cannot be closed, THEN verify 1A and 1B RCPs secured. 11. IF a primary coolant leak OR rupture is indicated, THEN perform the actions of the appropriate AOP or EEP. a)FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION b)FNP-1-AOP-1.0, RCS LEAKAGE c)FNP-1-AOP-2.0, STEAM GENERATOR TUBE LEAKAGE 12. IF B/U heaters automatically energized with pressure above 2210 psig, THEN verify the pressurizer master controller potentiometer setting using the plant curve book.

References:

A-177100, Sh. 371; U-260610; D-177109; D-177111; D-177112; D-177113; D-177381; Technical Specifications. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HD2 SETPOINT: 1. 2000 PSIG D2 PRZR PRESS ORIGIN: 1. Pressure Bistable PB-455B, PB-456B and SI PB-457B from Pressure Transmitters PT-455, PORV BLOCK PT-456, and PT-457. 2/3 Detectors P-11 PROBABLE CAUSE 1. Normal Primary System cooldown. 2. Primary Coolant leak. AUTOMATIC ACTION NOTE: Power Operated Relief Valves can be operated in Manual. 1. PRZR PORVs Q1B31PCV444B and Q1B31PCV445A are automatically blocked to prevent opening on decreasing pressure. OPERATOR ACTION 1. Check pressurizer pressure indications and determine the actual pressure. 2. IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION. 3. IF the alarm is NOT due to plant cooldown OR a primary coolant leak is indicated, THEN perform the actions required by the appropriate AOP or EEP:a) FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. b) FNP-1-AOP-1.0, RCS LEAKAGE. c) FNP-1-AOP-2.0, STEAM GENERATOR TUBE LEAKAGE. 4. IF the alarm occurred as a result of reducing pressure during a normal plant cooldown, THEN BLOCK the pressurizer pressure safety injection in accordance with FNP-1-UOP-2.2, SHUTDOWN OF UNIT FROM HOT STANDBY TO COLD SHUTDOWN.

References:

A-177100, Sh. 372; U-260610; U-198768; D-177381; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HD3 SETPOINT: Master Controller at 7.5% demand indicated Master D3 Controller Demand Signal. (representing a nominal PRZR CONT pressurizer pressure 100 PSI above the Master PRESS OUTPUT Controller reference potentiometer setting) HI ORIGIN: Pressure Bistable PB-444E from Pressure Transmitter PT-444 via Master Pressure Controller PC444A. PROBABLE CAUSE 1. Step Load Reduction. 2. Rod Control System Malfunction.

3. Pressure Control System malfunction.

4. Instrument failure or in test. AUTOMATIC ACTION 1. PORV PCV444B opens at 7.5% demand on the Master Pressure Controller PC444A (92.5% controller output equivalent to a nominal 2335 psig). 2. Pressurizer spray valves in automatic should be fully open. OPERATOR ACTION 1.Monitor for possible PORV lifting. 2.Check pressurizer pressure indications and determine the actual pressure. 3.IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION.4.Check the status of the following and take manual control as necessary: Pressurizer Sprays;Power Operated Relief Valves; Pressurizer Heaters 5. IF the alarm is caused by a rod control system malfunction, THEN take MANUAL rod control in accordance with FNP-1-AOP-19.0, MALFUNCTION OF ROD CONTROL SYSTEM. 6.Maintain reactor coolant system pressure at 2235 psig with the affected component(s) in manual control until automatic operation can be restored. 7.IF a Power Operated Relief Valve is leaking OR is malfunctioning, THEN isolate the affected relief valve and refer to Tech. Spec. 3.4.11 for LCO requirements. 8.IF the pressurizer power operated relief valves operated, THEN: a) Refer to FNP-1-SOP-1.2, REACTOR COOLANT PRESSURE RELIEF SYSTEM, for cooldown of the pressurizer relief tank. b) Refer to FNP-0-SOP-0, GENERAL INSTRUCTIONS TO OPERATIONS PERSONNEL, for reporting requirements. 9. IF alarm actuated with pressurizer pressure less than 2335 psig, THEN verify the pressurizer master controller potentiometer setting using the plant curve book

References:

A-177100, Sh. 373; U-260610; U-266647 PLS Document; Westinghouse 7300 Dwg 7378D55; Technical Specifications 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HD4 SETPOINT: Not Applicable D4 PRZR HTR CONT TRBL ORIGIN: Relay (RY1) located in Pressurizer Heater Controller PROBABLE CAUSE 1. Blown fuse. 2. Faulty diode.

3. SCR failure / cabinet high temperature.

4. 1C pressurizer heater group supply breaker open. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Place group 1C PRZR HTR GROUP VARIABLE switch in the "OFF" position.2.Control pressurizer pressure manually, using the other banks of heaters. Refer to annunciator window HC1, PRZR PRESS HI-LO. 3.Notify appropriate personnel to locate and correct the fault. 4.Return pressurizer heaters group 1C to service as soon as possible.NOTE: Loss of power to the 1C pressurizer heater group will cause this alarm. WHEN the cause of the alarm has been corrected, THEN the 1C variable pressurizer heater group supply breaker must be closed to clear the alarm. 5.To restore the 1C heater group momentarily place the 1C PRZR HTR GROUP VARIABLE switch to the "ON" position.

References:

A-177100, Sh. 374; U-211006; U-198805, U198707 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HD5 SETPOINT: Variable Current/Time D5 PRZR HTR ORIGIN: 1. Group 1A: 74 Relay in Breaker EA11 Control BKR Circuit. TRIPPED 2. Group 1B: 74 Relay in Breaker EC11 Control Circuit. 3. Group 1C: Alarm Switch in Breaker EM04 Control Circuit.

4. Group 1D: 74 Relay in Breaker EM05 Control Circuit.

5. Group 1E: 74 Relay in Breaker EN05 Control Circuit. PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. One or more groups of Pressurizer Heater Breakers tripped on overcurrent. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Determine which pressurizer heater group breaker has tripped. 2.Refer to annunciator window HC1, PRZR PRESS HI-LO. 3.IF required, THEN limit plant transients until the heaters can be returned to normal. 4.Notify appropriate personnel to determine and correct the cause of the breaker trip. 5.Refer to Technical Specification 3.4.9 for LCO requirements.

References:

A-177100, Sh. 375; D-177107; D-177109; D-177111; D-177112; D-177113; Technical Specifications 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HE1 SETPOINT: Not Applicable E1 REL VLV 444B/445A ORIGIN: Valve Position Switch (33) from PRZR PORV OPEN Q1B31PCV444B OR Q1B31PCV445A PROBABLE CAUSE 1. One or both PRZR PORVs Q1B31PCV444B and Q1B31PCV445A has lifted. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Check pressurizer relief valve discharge line temperature indication and relief valve position indications to determine if a relief valve has lifted. 2.Monitor pressurizer pressure and level and reactor coolant system temperatures. 3.IF a relief valve has lifted due to high system pressure, THEN ensure that the relief valve closes when system pressure has been reduced. 4.IF a relief valve lifted due to instrument failure AND actual pressure is low, THEN close the affected valve in manual and refer to annunciator window HC1, PRZR PRESS HI-LO. 5.IF a relief valve fails to close following an actuation, THEN place the control handswitch for the affected relief valve to the closed position. 6.IF a PRZR PORV fails to reseat OR does NOT close when the control handswitch is placed in the closed position, THEN isolate the affected relief valve by closing valve Q1B31MOV8000A to isolate PRZR PORV PCV-445A and/or valve Q1B31MOV8000B to isolate PRZR PORV PCV-444B. 7.Refer to Technical Specification 3.4.11 for LCO requirements. 8.WHEN plant conditions permit, THEN notify appropriate personnel to determine and correct the cause of the relief valve failing to close. 9.IF a PRZR PORV opened, THEN refer to FNP-0-SOP-0, GENERAL INSTRUCTIONS TO OPERATIONS PERSONNEL, for reporting requirements.

References:

A-177100, Sh. 376; B-181608, Sh. 16 & 17; D-175037, Sh. 2; PCN 90-1-6387; Technical Specification 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HE2 SETPOINT: Not Applicable E2 SAFETY VLV ORIGIN: Pressurizer Safety Valve Position Limit Switches 8010A/B/C 1. Q1B13ZS2034 OPEN 2. Q1B13ZS2035 3. Q1B13ZS2036 PROBABLE CAUSE NOTE: The safety valve lift setpoint is 2485 psig.1. One or more Pressurizer Safety Valves has lifted. AUTOMATIC ACTION NONE OPERATOR ACTION 1.Check pressurizer safety valve discharge line temperature indications and safety valve position indications to determine if a safety valve has lifted and which valve lifted. 2.Monitor pressurizer pressure and level and reactor coolant system temperatures. 3.IF a safety valve has lifted due to high system pressure, THEN verify that the safety valve reseats when system pressure has been reduced. 4.IF a safety valve fails to close following an actuation, THEN refer to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. 5.IF a safety valve has lifted due to an instrument failure, THEN refer to annunciator window HC1, PRZR PRESS HI-LO. 6.IF a safety valve has lifted and reseats, and subsequently lifts and reseats at approximately the same RCS pressure, THEN maintain RCS pressure less than lift pressure AND comply with Tech Specs 3.4.1 and 2.1.1 limits. 7.Following an actuation, IF a safety valve fails to fully reseat OR is leaking, THEN: a) Start additional charging pumps and increase charging flow as necessary to maintain pressurizer level. b) Refer to FNP-1-AOP-1.0, RCS LEAKAGE. 8.IF plant conditions permit, THEN notify appropriate personnel to determine and correct the cause of the safety valve failing to close or reseat properly. 9.Refer to TRM 13.4.4, and Tech Spec 3.4.10 for LCO requirements. 9. IF a PRZR SAFETY VLV opened, THEN refer to FNP-0-SOP-0, GENERAL INSTRUCTIONS TO OPERATIONS PERSONNEL, for reporting requirements.

References:

A-177100, Sh. 377; D-181774, Sh. 2; D-175037, Sh. 2; Technical Specification 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HE3 SETPOINT: 125FE3 PRT ORIGIN: Temperature Bistable TB-471 from Temperature TEMP HI Element TE-471 PROBABLE CAUSE 1. One of the following valves lifted or is leaking into the Pressurizer Relief Tank in excessive quantities. a) Pressurizer Safety Valves b) Pressurizer Power Operated Relief Valves c) CVCS Letdown Relief Valve 2. Instrument malfunction.

3. During Shutdown conditions, an RHR Suction or Discharge Relief Valve lifted. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine the actual temperature as indicated by TI-471, on the MCB. 2. Monitor pressurizer pressure and pressurizer relief tank pressure, level and temperature. 3. Check for high or increasing temperature indications downstream of the pressurizer safety valves, power operated relief valves, and CVCS letdown relief valve. 4. IF a pressurizer safety valve OR power operated relief valve has actuated, THEN verify that the valve closes when system pressure is reduced. 5. IF a pressurizer safety valve is leaking OR fails to close following an actuation, THEN perform the actions required by FNP-1-AOP-1.0, RCS LEAKAGE. NOTE: Technical Specification 3.4.11 addresses operation with a PRZR PORV ISO valve closed. 6. IF a PRZR PORV is leaking OR fails to close following an actuation, THEN: 6.1 Isolate the relief valves by closing both PRZR PORV ISOs Q1B31MOV8000A & B. 6.2 Refer to FNP-1-ARP-1.8, HA5, to determine the leaking valve. 7. IF the CVCS letdown relief valve is leaking OR has lifted, THEN go to FNP-1-AOP-16.0 CVCS MALFUNCTION. 8. IF an RHR system suction OR discharge relief valve is determined to be leaking, THEN isolate the affected RHR Train PER FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM9. Commence cooling the contents of the pressurizer relief tank (PRT) in accordance with FNP-1-SOP-1.2, REACTOR COOLANT PRESSURE RELIEF SYSTEM. 10. IF the alarm was caused by an instrument OR component failure, THEN notify appropriate personnel to determine the cause and correct the fault

References:

A-177100, Sh. 378; U-260610; D-175037, Sh. 2; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HE4 SETPOINT: 1. High Level: 78% E4 2. Low Level: 68% PRT LVL HI-LO ORIGIN: 1. Level Bistable LB-470A from Level Transmitter LT-470. 2. Level Bistable LB-470B from Level Transmitter LT-470. PROBABLE CAUSE 1. High Level One of the following valves has lifted or is leaking into the Pressurizer Relief Tank. a) Pressurizer Safety Valves. b) Pressurizer Power Operated Relief Valves. c) CVCS Letdown Relief Valve. d) CVCS seal Return Relief Valve. e) CVCS Charging Pump Suction Relief Valves. f) RHR System Suction or Discharge Relief Valves, during Shutdown conditions.2. Low Level a) Leakage from the Pressurizer Relief Tank to the Reactor Coolant Drain Tank. 3. Instrument malfunction. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Determine if the level is high or low as indicated by LI-470, on the MCB. 2. Monitor pressurizer pressure and pressurizer relief tank pressure, level and temperature. 3. IF level is high, THEN: 3.1 Check for high or increasing temperature indications downstream of the pressurizer safety valves, power operated relief valves and CVCS Ltdn relief valve. 3.2 IF a pressurizer safety valve OR power operated relief valve has actuated, THEN verify that the valve closes when system pressure is reduced. 4. IF level is low, THEN ensure that PRT DRN ISO N1B31HV8031 is shut. 5 IF a pressurizer safety valve is leaking OR fails to close following an actuation, THEN perform the actions required by FNP-1-AOP-1.0, RCS LEAKAGE. NOTE: Technical Specification 3.4.11 addresses operation with a PRZR PORV ISO valve closed. 6. IF a PRZR PORV is leaking OR fails to close following an actuation, THEN: a) Isolate the relief valves by closing both PRZR PORV ISOs Q1B31MOV8000A & B. b) Refer to FNP-1-ARP-1.8, HA5, to determine the leaking valve. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 LOCATION HE4 OPERATOR ACTION (cont.) 7. IF the CVCS letdown relief valve is leaking OR has lifted, THEN go to FNP-1-AOP-16.0 CVCS MALFUNCTION. 8. IF an RHR system suction OR discharge relief valve is determined to be leaking, THEN isolate the affected RHR Train in accordance with FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM. 9. IF the level increase is due to leakage from the charging system suction relief OR the seal return relief valve, THEN isolate the affected valve if possible. 10. Fill or drain the pressurizer relief tank (PRT) in accordance with FNP-1-SOP-1.2, REACTOR COOLANT PRESSURE RELIEF SYSTEM, as required to return level to normal. 11. IF the alarm was caused by an instrument OR component failure, THEN notify appropriate personnel to determine the cause and correct the fault.

References:

A-177100, Sh. 379; U-260610; D-175037, Sh. 2; U-266647 PLS Document; FNP-1-IMP-201.28 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HE5 SETPOINT: 7.5 PSIG E5 PRT PRESS ORIGIN: Pressure Bistable PB-472 from Pressure Transmitter HI PT-472 PROBABLE CAUSE 1. One of the following valves has lifted or is leaking into the Pressurizer Relief Tank. a) Pressurizer Safety Valves. b) Pressurizer Power Operated Relief Valves. c) CVCS Letdown Relief Valve. d) CVCS Seal Return Relief Valve. e) CVCS Charging Pump Suction Relief Valves. f) RHR System Suction or Discharge Relief Valves, during Shutdown conditions. 2. Nitrogen Regulator malfunction. 3. Instrument malfunction. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Determine the actual pressure as indicated by PI-472, on the MCB. 2.Monitor pressurizer pressure and pressurizer relief tank pressure, level and temperature. 3.Check for high or increasing temperature indications downstream of the pressurizer safety valves, power operated relief valves and CVCS letdown relief valve. 4.IF a pressurizer safety valve OR power operated relief valve has actuated, THEN verify that the valve closes when system pressure is reduced. 5.IF a nitrogen regulator malfunction exists, THEN isolate the nitrogen supply to the pressurizer relief tank in accordance with FNP-1-SOP-1.2, REACTOR COOLANT PRESSURE RELIEF SYSTEM. 6.IF a Pressurizer Safety Valve is leaking OR fails to close following an actuation, THEN perform the actions required by FNP-1-AOP-1.0, RCS LEAKAGE. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 LOCATION HE5 OPERATOR ACTION (cont) NOTE: Technical Specification 3.4.11 addresses operation with a PRZR PORV ISO valve closed.7.IF a PRZR PORV is leaking OR fails to close following an actuation, THEN: a) Isolate the relief valves by closing both PRZR PORV ISOs Q1B31MOV8000A & B. b) Refer to FNP-1-ARP-1.8/HA5, to determine the leaking valve. 8.IF the CVCS letdown relief valve is leaking OR has lifted, THEN go toFNP-1-AOP-16.0, CVCS MALFUNCTION. NOTE: Consideration may be given to reference FNP-1-AOP-12.0, RHR SYSTEM MALFUNCTION, specifically step 8.0, for additional guidance to that provided by SOP-7.0 in the following step. 9.IF an RHR system suction OR discharge relief valve is determined to be leaking, THEN isolate the affected RHR per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM.10.IF the pressure increase is due to leakage from the charging system suction relief OR the seal return relief valve, THEN isolate the affected valve if possible. 11.Return the pressurizer relief tank (PRT) pressure to normal in accordance with FNP-1-SOP-1.2, REACTOR COOLANT PRESSURE RELIEF SYSTEM. 12.IF the alarm was caused by an instrument OR component failure, THEN notify appropriate personnel to determine the cause and correct the fault.

References:

A-177100, Sh. 380; U-260610; D-175037, Sh. 2; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HF1 SETPOINT: 3F Deviation from TAVG Median F1 RX COOLANT ORIGIN: Temperature Bistables TB-408A, TB-408B and LOOPS TB-408C each fed by median selected TAVG, Cold TAVG DEV Leg Temperature Detectors TE-412D, TE-422D, HI-LO TE-432D and Hot Leg Loop Average Temperature Detectors TE-412B1, B2, B3, TE-422B1, B2, B3 and TE-432B1, B2, B3 PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. Unbalanced Steam Flows from the Steam Generators. 2. Uneven Feedwater Flows to the Steam Generators.

3. Loss of Flow in a Reactor Coolant Loop.

4. Instrument failure. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Check loop temperature indications and determine which loop has the temperature deviation. 2. Monitor reactor coolant, steam and feed system flows: a) IF an imbalance in steam OR feedflow exists, THEN determine the cause of the imbalance. b) IF possible, THEN correct the imbalance to clear the alarm. 3. IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION. 4. IF a loss of flow has occurred, THEN refer to FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW.

References:

A-177100, Sh. 381; U-260610; U-266647 PLS Document; PCN B88-1-5259 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HF2 SETPOINT: 6F Deviation from T median F2 RX COOLANT ORIGIN: Temperature Bistables TB-409A, TB-409B and LOOPS TB-409C each fed from median selected T, Cold T DEV Leg Temperature Detectors TE-412D, TE-422D, HI-LO TE-432D and Hot Leg Temperature Detectors TE-412B1, B2, B3, TE-422B1, B2, B3 and TE-432B1, B2, B3 PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. Unbalanced Steam Flows from the Steam Generators. 2. Uneven Feedwater Flows to the Steam Generators.

3. Loss of Flow in a Reactor Coolant Loop.

4. Instrument failure. AUTOMATIC ACTION NONEOPERATOR ACTION 1. Check loop temperature indications and determine which loop has the temperature deviation. 2. Monitor reactor coolant, steam and feed system flows: a) IF an imbalance in steam OR feedflow exists, THEN determine the cause of the imbalance. b) IF possible, THEN correct the imbalance to clear the alarm. 3. IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION. 4. IF a loss of flow has occurred, THEN refer to FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW.

References:

A-177100, Sh. 382; U-260610; U-266647 PLS Document; PCN B88-1-5259; PCN B88-1-5301 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HF3 SETPOINT:5FF3 TAVG/TREF ORIGIN: Temperature Bistables TB-408D, fed from median DEV selected TAVG and Turbine Impulse selected chamber pressure. PROBABLE CAUSE NOTE: Zinc Addition System injection will result in a continuous RCS dilution of as much as 1.7 gph, which may raise TAVG if not compensated for. This annunciator has REFLASH capability. 1. Load Transient while in Manual Rod Control. 2. Rod Control System malfunction.

3. Instrument loop failure.

4. Primary Plant Cooldown below 547°F (TREF Bottom Limit) 5. RCS dilution or boration. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Monitor loop temperature indications and turbine impulse pressure indications and verify an actual average temperature deviation. 2.IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION. 3.IF in manual rod control, THEN control the power transient and match TAVG with TREF.4.IF a rod control system malfunction exists, THEN take manual rod control in accordance with FNP-1-AOP-19.0, MALFUNCTION OF ROD CONTROL SYSTEM. 5.IF the alarm is due to a plant startup OR cooldown in progress, THEN no action is required. 6.Refer to Technical Specifications for LCO requirements.

References:

A-177100, Sh. 383; U-260610; U-266647 PLS Document; Technical Specifications; PCN B88-1-5259 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HF4 SETPOINT: 543FF4 RX COOLANT ORIGIN: Temperature Bistables TB-412E, TB-422E and LOOPS TB-432E from Cold Leg Temperature Detectors 1A, 1B OR 1C TE-412D, TE-422D, TE-432D and the average of the TAVG LO-LO three Hot Leg Temperature Detectors on each loop TE-412B1, B2, B3, TE-422B1, B2, B3 and TE-432B1, B2, B3 PROBABLE CAUSE NOTE: This annunciator has REFLASH capability. 1. Failure of the Rod Control System on an Up-Power Maneuver. 2. Loss of Flow in a Reactor Coolant Loop.

3. Excessive Feedwater addition to Steam Generators during Startup.

4. Primary Plant Cooldown below 543°F.

5. Instrument failure. AUTOMATIC ACTION 1. Lo-Lo TAVG, 2/3 coincidence, blocks automatic Steam Dump operation. OPERATOR ACTION 1. Check loop temperature indications and verify an actual low-low TAVG condition. 2. IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION.3. Monitor reactor coolant, steam and feed system flows. 4. IF a rod control system malfunction exists, THEN take manual rod control in accordance with FNP-1-AOP-19.0, MALFUNCTION OF ROD CONTROL SYSTEM. 5. IF a loss of flow has occurred, THEN refer to FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW. 6. IF the alarm was caused by feedwater addition to the Steam Generators during startup, THEN decrease the feedwater addition rate and restore loop temperatures to normal. 7. IF the alarm is due to plant cooldown below 543°F, THEN no action is required. 8. Refer to Technical Specifications 3.4.2 for LCO requirements.

References:

A-177100, Sh. 384; U-260610; U-198768; U-266647 PLS Document; PCN B88-1-5259 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HF5 SETPOINT: 4F above Full Load Tavg F5 RX COOLANT ORIGIN: Temperature Bistables TB-412D, TB-422D and LOOPS TB-432D from Cold Leg Temperature Detectors TAVG HI TE-412D, TE-422D, TE-432D and the average of the three Hot Leg Temperature Detectors on each loop TE-412B1, B2, B3, TE-422B1, B2, B3 and TE-432B1, B2, B3 PROBABLE CAUSE NOTE: Zinc Addition System injection will result in a continuous RCS dilution of as much as 1.7 gph, which may raise TAVG if not compensated for. 1.Load Reduction while in Manual Rod Control. 2.Rod Control System malfunction.

3. Instrument failure.

4. RCS dilution. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Check loop temperature indications and verify an actual high TAVGcondition.2.IF an instrument failure has occurred, THEN go to FNP-1-AOP-100, INSTRUMENT MALFUNCTION 3.IF a rod control system malfunction exists, THEN take manual rod control in accordance with FNP-1-AOP-19.0, MALFUNCTION OF ROD CONTROL SYSTEM. 4.IF rod control is in manual, THEN reduce the load transient and match TAVGwith TREF.5.Refer to Technical Specifications, section 3.3.1 and 3.3.2 for LCO requirements.

References:

A-177100, Sh. 385; U-260610; U-266647 PLS Document; PCN B88-1-5259 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HG1 SETPOINT: 1.25 inches above Normal Level G1 RCP 1A BRG ORIGIN: 1. Upper Reservoir: Level Switch LS-417 UPPER/LOWER 2. Lower Reservoir: Level Switch LS-419 OIL RES HI LVL PROBABLE CAUSE 1. Inleakage of Component Cooling Water. 2. Excessive heating of oil after pump start.

3. Instrument malfunction. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Continuously monitor 1A RCP bearing temperatures. NOTE: WHEN transitioning to FNP-1-EEP-0.0 AND at the Shift Supervisors direction, it is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0.0. While the other team member verifies a Reactor Trip, THEN trips the appropriate RCP(s) before finishing the Immediate Operator Actions of FNP-1-EEP-0.0. (AI 2004200019) 2.IF any 1A RCP motor bearing temperature exceeds 195°F, THEN perform the following actions: a) Trip the reactor, AND go to FNP-1-EEP-0.0, REACTOR TRIP OR SAFETY INJECTION. b) Stop 1A RCP. c) Perform the actions required by FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW. d) Manually close pressurizer spray valve, PK 444C 3.At the direction of the Operations Manager, reduce power as necessary to permit a containment entry. 4.As soon as practical make a containment entry to determine the cause for the bearing oil reservoir high level and the extent of any damage. 5.IF instrument malfunction was the cause of the alarm, THEN perform the following actions:

a) Notify appropriate personnel. b) Determine the cause and correct the instrument fault. c) Return the instrument to normal as soon as possible. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 LOCATION HG1 OPERATOR ACTION (cont.) 6.Correct the cause and any damage that has resulted. 7.Return the Reactor Coolant Pump to service as soon as possible. 8.IF the cause of the alarm can NOT be corrected AND a determination has been made to continue operating, THEN perform the following: 8.1 Monitor the following parameters at an increased frequency to be determined by the Operations Shift Manager: CCW Surge Tank Level 1A RCP bearing temperatures 8.2 Initiate a CR for Maintenance to defeat the input from LS-417 or LS-419 to restore alarm capability for the LS that is not causing the alarm by jumpering the appropriate terminals in annunciator cabinet "1D" N1H25L040D-N per the following: RESERVOIRLEVELSWITCHTERMINALSDRAWINGA177100Upper N1B41LS0417 SP-37A (H61A) SP-37B (H61B) Sh. 386 Lower N1B41LS0419 SP-37B (H71A) SP-37C (H71B) Sh. 386 & 391 8.3 Initiate a second CR for Maintenance to remove the jumper installed per step 8.2 when the jumper is no longer required. 8.4 Place caution tag stating which input to the alarm is defeated near annunciator window HG1. Caution tag cover sheet shall reference the CR in step 8.3.

References:

A-177100, Sh. 386 and 391; A-181541 Sh. F-H and F-4; U-258242; D-175037, Sh. 3; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HG2 SETPOINT: 1.25 inches above Normal Level G2 RCP 1B BRG ORIGIN: 1. Upper Reservoir: Level Switch LS-427 UPPER/LOWER 2. Lower Reservoir: Level Switch LS-429 OIL RES HI LVL PROBABLE CAUSE 1. Inleakage of Component Cooling Water. 2. Excessive heating of oil, after pump start.

3. Instrument malfunction. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Continuously monitor RCP 1B bearing temperatures. NOTE: WHEN transitioning to FNP-1-EEP-0.0 AND at the Shift Supervisors direction, it is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0.0. While the other team member verifies a Reactor Trip, THEN trips the appropriate RCP(s) before finishing the Immediate Operator Actions of FNP-1-EEP-0.0. (AI 2004200019) 2.IF any 1B RCP motor bearing temperature exceeds 195°F, THEN perform the following actions: a) Trip the reactor, AND go to FNP-1-EEP-0.0, REACTOR TRIP OR SAFETY INJECTION. b) Stop 1B RCP. c) Perform the actions required by FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW. d) Manually close pressurizer spray valve, PK 444D 3.At the direction of the Operations Manager, reduce power as necessary to permit a containment entry. 4.As soon as practical make a containment entry to determine the cause for the bearing oil reservoir high level and the extent of any damage. 5.IF instrument malfunction was the cause of the alarm, THEN perform the following actions:

a) Notify appropriate personnel. b) Determine the cause and correct the instrument fault. c) Return the instrument to normal as soon as possible. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 LOCATION HG2 OPERATOR ACTION (cont.) 6.Correct the cause and any damage that has resulted. 7.Return the Reactor Coolant Pump to service as soon as possible. 8.IF the cause of the alarm can NOT be corrected AND a determination has been made to continue operating, THEN perform the following: 8.1 Monitor the following parameters at an increased frequency to be determined by the Operations Shift Manager: 8.1.1CCW Surge Tank Level 8.1.21B RCP bearing temperatures 8.2 Initiate a CR for Maintenance to defeat the input from LS-427 or LS-429 to restore alarm capability for the LS that is not causing the alarm by jumpering the appropriate terminals in annunciator cabinet "1D" N1H25L040D-N per the following: RESERVOIRLEVELSWITCHTERMINALSDRAWINGA177100Upper N1B41LS0427 SP-42A (H62A) SP-42B (H62B) Sh. 387 Lower N1B41LS0429 SP-42B (H72A) SP-42C (H72B) Sh. 387 & 392 8.3 Initiate a second CR for Maintenance to remove the jumper installed per step 8.2 when the jumper is no longer required. 8.4 Place caution tag stating which input to the alarm is defeated near annunciator window HG2. Caution tag cover sheet shall reference the CR in step 8.3.

References:

A-177100, Sh. 387 and 392; D-175037, Sh. 3; U-258242; A-181541 Sh. F-H and F-4; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HG3 SETPOINT: 1.25 inches above Normal Level G3 RCP 1C BRG ORIGIN: 1. Upper Reservoir: Level Switch LS-437 UPPER/LOWER 2. Lower Reservoir: Level Switch LS-439 OIL RES HI LVL PROBABLE CAUSE 1. Inleakage of Component Cooling Water. 2. Excessive heating of oil, after pump start.

3. Instrument malfunction. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Continuously monitor RCP 1C bearing temperatures. NOTE: WHEN transitioning to FNP-1-EEP-0.0 AND at the Shift Supervisors direction, it is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0.0. While the other team member verifies a Reactor Trip, THEN trips the appropriate RCP(s) before finishing the Immediate Operator Actions of FNP-1-EEP-0.0. (AI 2004200019) 2.IF any RCP 1C motor bearing temperature exceeds 195°F, THEN perform the following actions: a) Trip the reactor, AND go to FNP-1-EEP-0.0, REACTOR TRIP OR SAFETY INJECTION. b) Stop RCP 1C. c) Perform the actions required by FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW. 3.At the direction of the Operations Manager, reduce power as necessary to permit a containment entry. 4.As soon as practical make a containment entry to determine the cause for the bearing oil reservoir high level and the extent of any damage. 5.IF instrument malfunction was the cause of the alarm, THEN perform the following actions:

a) Notify appropriate personnel. b) Determine cause and correct the instrument fault. c) Return the instrument to normal as soon as possible. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 LOCATION HG3 OPERATOR ACTION (cont) 6.Correct the cause and any damage that has resulted. 7.Return the Reactor Coolant Pump to service as soon as possible. 8.IF the cause of the alarm can NOT be corrected AND a determination has been made to continue operating, THEN perform the following: 8.1Monitor the following parameters at an increased frequency to be determined by the Operations Shift Manager: 8.1.1CCW Surge Tank Level 8.1.21C RCP bearing temperatures 8.2Initiate a CR for Maintenance to defeat the input from LS-437 or LS-439 to restore alarm capability for the LS that is not causing the alarm by jumpering the appropriate terminals in annunciator cabinet "1D" N1H25L040D-N per the following: RESERVOIRLEVELSWITCHTERMINALSDRAWINGA177100Upper N1B41LS0437 SP-44A (H63A) SP-44B (H63B) Sh. 388 Lower N1B41LS0439 SP-44B (H73A) SP-44C (H73B) Sh. 388 & 393 8.3Initiate a second CR for Maintenance to remove the jumper installed per step 8.2 when the jumper is no longer required. 8.4Place caution tag stating which input to the alarm is defeated near annunciator window HG3. Caution tag cover sheet shall reference the CR in step 8.3.

References:

A-177100, Sh. 388 and 393; D-175037, Sh. 3; U-258242; A-181541, Sh. F-H and F-4; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HG4 SETPOINT: Valve leaving Full Open position. G4 OMS ORIGIN: 1. MOV Limit Switch from any of the following REL VLV valves: PATH CLOSED a) Q1E11MOV8701A AT LO TEMP b) Q1E11MOV8702A c) Q1E11MOV8701B d) Q1E11MOV8702B

2. RCS Solid Control Handswitch not in "Defeat" (N1H11HS2121-N) PROBABLE CAUSE 1. Closure of one or more of the RHR System valves. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Determine if the valves were inadvertently closed. 2.IF the valves were inadvertently closed, THEN open the valves, per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM. 3.Refer to Technical Specifications 3.4.12 for LCO requirements.

References:

A-177100, Sh. 389; D-177569; D-177572; D-177838; D-177839; Technical Specifications. 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HG5 SETPOINT: 425 PSIG G5 SOLID ORIGIN: Pressure Bistable PB-403AB from Pressure RCS PRESS Transmitter PT-402 or PT-403 HI (RCS Solid Control Handswitch N1H11HS2121 must be selected to PT 402 or 403) PROBABLE CAUSE 1. Reactor Coolant System heatup. 2. Insufficient Letdown Flow.

3. Inadvertent closure of RHR Suction from RCS Valves Q1E11MOV8701A (B) and/or Q1E11MOV8702A (B). 4. Malfunction of one of the following valves: a) Letdown Pressure Control Valve Q1E21PCV145.

b) Charging Flow Control Valve Q1E21FCV122. c) RHR to Letdown Flow Control Valve Q1E21HCV142. 5. Instrument malfunction AUTOMATIC ACTION NOTE: IF RCS Pressure increases to 700 PSIG AND power is available to the MOV's, THEN RHR suction from RCS valves Q1E11MOV8701A & B and Q1E11MOV8702A & B will automatically close. OPERATOR ACTION 1. Check indications and determine actual reactor coolant system pressure. 2. IF the high pressure is due to an inadvertent closure of valves Q1E11MOV8701A (B) OR Q1E11MOV8702A (B), THEN: a) Stop the running charging pump. b) IF the RCS loop suction valves have closed for a running RHR pump, THEN secure that RHR pump AND perform the actions specified in FNP-1-AOP-12.0, RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION.c) Increase letdown flow to maximum. IF required, THEN swap LP LETDOWN to the opposite RHR Train using FNP-1-SOP-7.0, RHR SYSTEM.NOTE:d) WHEN pressure has decreased to 400 PSIG, THEN reopen valves Q1E11MOV8701A (B) and Q1E11MOV8702A (B). 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 LOCATION HG5 OPERATOR ACTION (cont) 3.IF the high pressure is caused by reduced letdown flow, THEN: a.IF PK 145 has failed, THEN take manual control of LP LTDN PRESS PK 145 and increase letdown flow to reduce pressure. b.Verify open RHR TO LTDN HX HIK 142. Control as necessary to establish the desired letdown flowrate. c.Adjust CHG FLOW FK 122 to decrease charging flow to the desired value.4.IF the high pressure is caused by excessive charging flow, THEN: a.Adjust CHG FLOW FK 122 to decrease charging flow to the desired value.b.IF charging flow can NOT be reduced promptly, THEN isolate charging flow by closing CHG PUMP TO REGENERATIVE HX Q1E21MOV8107 or Q1E21MOV8108. c.Adjust LP LTDN PRESS PK 145 as required. 5.IF an RHR relief valve has lifted, THEN closely monitor PRT parameters. 6.IF the high pressure was caused by an instrument OR component failure, THEN perform the following: a.IF available, THEN select the alternate channel. b.Notify appropriate personnel to determine the cause and correct the fault. 7.WHEN conditions allow, THEN re-establish charging and letdown flow per FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION and FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM

References:

A-177100, Sh. 390; U-260610; D-175037, Sh. 1 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HH1 SETPOINT: 1.25 inches below Normal Level H1 RCP 1A BRG ORIGIN: 1. Upper Reservoir: Level Switch LS-417 UPPER/LOWER 2. Lower Reservoir: Level Switch LS-419 OIL RES LO LVL PROBABLE CAUSE 1. Sight glass rupture. 2. Oil Leakage.

3. Instrument malfunction. AUTOMATIC ACTION NONE OPERATOR ACTION1. Continuously monitor 1A RCP bearing temperatures. NOTE: WHEN transitioning to FNP-1-EEP-0.0 AND at the Shift Supervisors direction, it is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0.0. While the other team member verifies a Reactor Trip, THEN trips the appropriate RCP(s) before finishing the Immediate Operator Actions of FNP-1-EEP-0.0. (AI 2004200019) 2. IF any 1A RCP motor bearing temperature exceeds 195°F, THEN perform the following actions:a) Trip the reactor, AND go to FNP-1-EEP-0.0, REACTOR TRIP OR SAFETY INJECTION.b) Stop 1A RCP. c) Perform the actions required by FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW. d) Manually close pressurizer spray valve, PK 444C. 3. Generate a condition report to document the time of the initial alarm. 4. Start an admin tracking sheet to document anytime the alarm clears and for any future alarms.

06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 LOCATION HH1 OPERATOR ACTION (cont) NOTE: The intent of the following step is to observe if the alarm will initially clear, and to monitor how long the alarm will stay clear. This should give some indication of the leak magnitude. It is not intended to continuously raise CCW temperature to it maximum limit to keep the alarm clear. (CR2003003074)5. Initially raise CCW temperature 5°F and to try and clear the alarm 6. At the direction of the Operations Manager, reduce power as necessary to permit a containment entry. 7. As soon as practical make a containment entry to determine the cause for the bearing oil reservoir low level and the extent of any damage. 8. IF instrument malfunction was the cause of the alarm, THEN perform the following actions:a) Notify appropriate personnel. b) Determine the cause and correct the instrument fault. c) Return the instrument to normal as soon as possible. 9. Correct the cause and any damage that has resulted. 10. Return the Reactor Coolant Pump to service as soon as possible. 11. IF the cause of the alarm can NOT be corrected AND a determination has been made to continue operating, THEN perform the following: 11.1 Monitor the following parameters at an increased frequency to be determined by the Operations Shift Manager: 11.1.1 CCW Surge Tank Level 11.1.2 1A RCP bearing temperatures 11.2 Initiate a CR for Maintenance to defeat the input from LS-417 or LS-419 to restore alarm capability for the LS that is not causing the alarm by jumpering the appropriate terminals in annunciator cabinet "1D" N1H25L040D-N per the following:RESERVOIRLEVELSWITCHTERMINALSDRAWINGA177100Upper N1B41LS0417 SP-38A (H61C) SP-38B (H61D) Sh. 391 & 386 Lower N1B41LS0419 SP-38B (H71C) SP-38C (H71D) Sh. 391 11.3 Initiate a second CR for Maintenance to remove the jumper installed per step 11.2 when the jumper is no longer required. 11.4 Place caution tag stating which input to the alarm is defeated near annunciator window HH1. Caution tag cover sheet shall reference the CR in step 11.3.

References:

A-177100, Sh. 386 and 391; U-258242; D-175037, Sh. 3; A-181541, Sh F-H and F-4; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HH2 SETPOINT: 1.25 inches below Normal Level H2 RCP 1B BRG ORIGIN: 1. Upper Reservoir: Level Switch LS-427 UPPER/LOWER 2. Lower Reservoir: Level Switch LS-429 OIL RES LO LVL PROBABLE CAUSE 1. Sight glass rupture. 2. Oil Leakage.

3. Instrument malfunction. AUTOMATIC ACTION NONE OPERATOR ACTION 1. Continuously monitor RCP 1B bearing temperatures. NOTE: WHEN transitioning to FNP-1-EEP-0.0 AND at the Shift Supervisors direction, it is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0.0. While the other team member verifies a Reactor Trip, THEN trips the appropriate RCP(s) before finishing the Immediate Operator Actions of FNP-1-EEP-0.0. (AI 2004200019) 2. IF any 1B RCP motor bearing temperature exceeds 195°F, THEN perform the following actions:a) Trip the reactor, AND go to FNP-1-EEP-0.0, REACTOR TRIP OR SAFETY INJECTION.b) Stop 1B RCP. c) Perform the actions required by FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW. d) Manually close pressurizer spray valve, PK 444D. 3. Generate a condition report to document the time of the initial alarm. 4. Start an admin tracking sheet to document anytime the alarm clears and for any future alarms.

06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 NOTE: The intent of the following step is to observe if the alarm will initially clear, and to monitor how long the alarm will stay clear. This should give some indication of the leak magnitude. It is not intended to continuously raise CCW temperature to it maximum limit to keep the alarm clear. (CR2003003074)5. Initially raise CCW temperature 5°F and to try and clear the alarm 6. At the direction of the Operations Manager, reduce power as necessary to permit a containment entry. 7. As soon as practical make a containment entry to determine the cause for the bearing oil reservoir low level and the extent of any damage. 8. IF instrument malfunction was the cause of the alarm, THEN perform the following actions:a) Notify appropriate personnel. b) Determine the cause and correct the instrument fault. c) Return the instrument to normal as soon as possible. 9. Correct the cause and any damage that has resulted. 10. Return the Reactor Coolant Pump to service as soon as possible.

11. IF the cause of the alarm can NOT be corrected AND a determination has been made to continue operating, THEN perform the following: 11.1 Monitor the following parameters at an increased frequency to be determined by the Operations Shift Manager:

11.1.1 CCW Surge Tank Level 11.1.2 1B RCP bearing temperatures 11.2 Initiate a CR for Maintenance to defeat the input from LS-427 or LS-429 to restore alarm capability for the LS that is not causing the alarm by jumpering the appropriate terminals in annunciator cabinet "1D" N1H25L040D-N per the following:RESERVOIRLEVELSWITCHTERMINALSDRAWINGA177100Upper N1B41LS0427 SP-43A (H62C) SP-43B (H62D) Sh. 392 & 387 Lower N1B41LS0429 SP-43B (H72C) SP-43C (H72D) Sh. 392 11.3 Initiate a second CR for Maintenance to remove the jumper installed per step 11.2 when the jumper is no longer required. 11.4 Place caution tag stating which input to the alarm is defeated near annunciator window HH2. Caution tag cover sheet shall reference the CR in step 11.3.

References:

A-177100, Sh. 387 and 392; U-258242; D-175036, Sh. 3; A-181541, Sh. F-H and F-4; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HH3 SETPOINT: 1.25 inches below Normal Level H3 RCP 1C BRG ORIGIN: 1. Upper Reservoir: Level Switch LS-437 UPPER/LOWER 2. Lower Reservoir: Level Switch LS-439 OIL RES LO LVL PROBABLE CAUSE

1. Sight glass rupture.

2. Oil Leakage.

3. Instrument malfunction. AUTOMATIC ACTION NONE OPERATOR ACTION

1. Continuously monitor RCP 1C bearing temperatures. NOTE: WHEN transitioning to FNP-1-EEP-0.0 AND at the Shift Supervisors direction, it is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0.0. While the other team member verifies a Reactor Trip, THEN trips the appropriate RCP(s) before finishing the Immediate Operator Actions of FNP-1-EEP-0.0. (AI 2004200019) 2. IF any 1C RCP motor bearing temperature exceeds 195°F, THEN perform the following actions:a) Trip the reactor, AND go to FNP-1-EEP-0.0, REACTOR TRIP OR SAFETY INJECTION.b) Stop 1C RCP. c) Perform the actions required by FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW. 3. Generate a condition report to document the time of the initial alarm. 4. Start an admin tracking sheet to document anytime the alarm clears and for any future alarms.

06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 NOTE: The intent of the following step is to observe if the alarm will initially clear, and to monitor how long the alarm will stay clear. This should give some indication of the leak magnitude. It is not intended to continuously raise CCW temperature to it maximum limit to keep the alarm clear. (CR2003003074)5. Initially raise CCW temperature 5°F and to try and clear the alarm 6. At the direction of the Operations Manager, reduce power as necessary to permit a containment entry. 7. As soon as practical make a containment entry to determine the cause for the bearing oil reservoir low level and the extent of any damage. 8. IF instrument malfunction was the cause of the alarm, THEN perform the following actions:a) Notify appropriate personnel. b) Determine the cause and correct the instrument fault. c) Return the instrument to normal as soon as possible. 9. Correct the cause and any damage that has resulted. 10. Return the Reactor Coolant Pump to service as soon as possible. 11. IF the cause of the alarm can NOT be corrected AND a determination has been made to continue operating, THEN perform the following: 11.1 Monitor the following parameters at an increased frequency to be determined by the Operations Shift Manager: 11.1.1 CCW Surge Tank Level 11.1.2 1C RCP bearing temperatures 11.2 Initiate a CR for Maintenance to defeat the input from LS-437 or LS-439 to restore alarm capability for the LS that is not causing the alarm by jumpering the appropriate terminals in annunciator cabinet "1D" N1H25L040D-N per the following:RESERVOIRLEVELSWITCHTERMINALSDRAWINGA177100Upper N1B41LS0437 SP-45A (H63C) SP-45B (H63D) Sh. 393 & 388 Lower N1B41LS0439 SP-45B (H73C) SP-45C (H73D) Sh. 393 11.3 Initiate a second CR for Maintenance to remove the jumper installed per step 11.2 when the jumper is no longer required. 11.4 Place caution tag stating which input to the alarm is defeated near annunciator window HH3. Caution tag cover sheet shall reference the CR in step 11.3

References:

A-177100, Sh. 388 and 393; U-258242; D-175037, Sh. 3; A-181541, Sh. F-H and F-4; U-266647 PLS Document 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 2 Version 36.0 UNIT 1 LOCATION HH4 SETPOINT: Shaft Vibration - 15 mils H4 Frame Vibration - 3 mils RCP (4 for RCP 1A; 3.3 for RCP 1C) VIB ORIGIN: Bently Nevada Series 3300 Vibration Monitoring TRBL Equipment. (139 Elec. Pen. Rm.) PROBABLE CAUSE 1. Pump damage. 2. Loss of NPSH.

3. Instrument malfunction. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Monitor RCS flow, subcooling conditions and RCP run current to determine if low NPSH conditions exist. 2.Monitor seal injection flow to insure a seal problem is not causing the increased vibration. 3.Monitor RCP bearing temperatures. 4.Dispatch appropriate personnel to the 139' EPR to observe vibration monitoring equipment to determine affected pump, vibration level, and rate of increase. 5.IF Westinghouse has not been previously notified of an abnormal vibration on a RCP, THEN notify Westinghouse of the RCP vibration. (Ref. Westinghouse Infogram IG95008A) NOTE: For a gradual increase where plant management and Westinghouse have been able to consult, the guidance in the following steps may be altered per plant management direction. The guidance in the following steps is N/A if an obvious instrument malfunction has resulted in this alarm. WHEN transitioning to FNP-1-EEP-0.0 AND at the Shift Supervisors direction, it is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0.0. While the other team member verifies a Reactor Trip, THEN trips the appropriate RCP(s) before finishing the Immediate Operator Actions of FNP-1-EEP-0.0. (AI 2004200019) 6. IF shaft vibration is 15 MILS AND the rate of increase in vibration exceeds 1 MIL per hour OR shaft vibration under any conditions exceeds 20 MILS, THEN perform the following:

06/02/15 13:28:40 FNP-1-ARP-1.8 Page 2 of 2 Version 36.0 UNIT 1 LOCATION HH4 OPERATOR ACTION (cont.) 6.1 Trip the reactor, AND go to FNP-1-EEP-0.0, REACTOR TRIP OR SAFETY INJECTION. 6.2 Stop the affected RCP. 6.3 Perform the actions required by FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW, as applicable. CAUTION: Operation of the RCP at frame vibration levels above 5 MILS could result in RCP internal and/or attached piping damage. 7. IF frame vibration reaches the 5 MIL limit, without an excessive rate of increase, THEN preparations for an orderly plant shutdown should begin, pending a management and Westinghouse review of the vibration. 7.1 IF frame vibration has reached 5 MILS and the rate of increase exceeds 0.2 MIL per hour, THEN perform the following: NOTE: WHEN transitioning to FNP-1-EEP-0.0 AND at the Shift Supervisors direction, it is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0.0. While the other team member verifies a Reactor Trip, THEN trips the appropriate RCP(s) before finishing the Immediate Operator Actions of FNP-1-EEP-0.0. (AI 2004200019) 7.1.1 Trip the reactor, AND go to FNP-1-EEP-0.0, REACTOR TRIP OR SAFETY INJECTION. 7.1.2 Stop the affected RCP 7.1.3 Perform the actions required by FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW, as applicable. 8. WHEN vibration levels are below setpoint AND it is desired to reset the vibration alarm at the Bently Nevada panel, THEN perform the following: 8.1 Depress the RESET pushbutton located on the front of the System Monitor module. 8.2 Checkindividual vibration monitor module alarms have reset.

References:

A-177100, Sh. 394; PCN 80-707; PCN B87-1-4230; PCN B90-1-6387; U-214849; Westinghouse Letter ALA-96-0574, U-266375 06/02/15 13:28:40 FNP-1-ARP-1.8 Page 1 of 1 Version 36.0 UNIT 1 LOCATION HH5 SETPOINT: Ambient 50FH5 RX VESSEL ORIGIN: Temperature Bistable TB-401 from Temperature FLANGE LKOF Element TE-401 TEMP HI PROBABLE CAUSE 1. Leakage past O-Ring Seal on Reactor Vessel Flange. 2. Instrument malfunction. AUTOMATIC ACTION NONEOPERATOR ACTION 1.Determine the actual reactor vessel flange leakoff temperature as indicated by TI-401, on the MCB. 2.Perform the following to determine if actual flange leakage exists: Compare indicated flange leakoff temperature with containment temperature. Monitor RCDT pressure for increasing trend.Monitor RCDT level for increasing trend. 3.IF reactor vessel flange leakage is indicated, THEN CLOSE RX VESSEL LKOF ISO Q1B13HV8032. 4.Refer to Technical Specifications 3.4.13 for LCO requirements on operational leakage. 5.At the earliest opportunity, make a containment entry and determine if one or both seal rings are leaking.

References:

A-177100, Sh. 395; D-175037, Sh. 1; U-266647 PLS Document; Technical Specifications. ILT-38 JPM Page 1 of 7 JPM DIRECTIONS: 1. Examinee will obtain all references from the simulator. 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise. 3. Provide student with HANDOUT. 4. Allow student time to review control board. 5. Instructor will be provided to address alarms not related to evaluated task. TASK STANDARD: Upon successful completion of this JPM, the examinee will: 1. Verify Phase B Containment Isolation and PRF start. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) EXAMINER: Developer S Jackson Date: 4/8/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 jpm e CRO-406B MOD TITLE: Verify Phase B Containment Isolation And Containment Spray Initiation ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: X SIMULATOR CONTROL ROOM PLANT PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: IC-215 (Base -073) ALTERNATE PATH X TIME CRITICAL PRA X ILT-38 JPM Page 2 of 7 EVENT DESCRIPTION ACTION DETAILS Reset into IC- 215 Reset into IC-73 inserted faults and ran a LOCA until desired starting point reached. Acknowledge computer alarms Run / Freeze Simulator Acknowledge Alarms Turn Horns ON Run / Freeze Simulator ILT-38 JPM Page 3 of 7 CONDITIONS When I tell you to begin, you are to PERFORM THE ACTIONS OF EEP-0.0, REACTOR TRIP OR SAFETY INJECTION. The conditions under which this task is to be performed are: a. A LOCA has occurred. b. EEP-0.0 steps 1 through 5 are complete. c. You are directed continue with step 6 of EEP-0.0 d. A pre-job brief is not required. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) _____ START TIME 1. 6 [CA] Check containment pressure - HAS REMAINED LESS THAN 27 psig. CTMT PRESS [] PR 950 Observes Containment pressure has NOT remained less than 27 psig and proceeds to 6 (RNO). S / U *2. 6.1 (RNO) Verify PHASE B CTMT ISO - ACTUATED.

[] MLB-3 1-1 lit  [] MLB-3 6-1 lit Observes MLB-3 1-1/6-1 NOT LIT and Takes both CS/PH B HS's to Actuate. Observes MLB-3 1-1/6-1 lit but not all valves actuate (See ELEMENT 4 below). S  /  U    *3. 6.2 (RNO)  Stop all RCPs RCP  [] 1A  [] 1B  [] 1C Take HS's for 1A, 1B & 1C RCPs to stop. Observes greenlights lit, red lights out, 0 amps and loop flow falling. S  /  U ILT-38 JPM            Page 4 of 7     EVALUATION CHECKLIST        RESULTS: ELEMENTS: STANDARDS: (CIRCLE)  Note: Applicant may try the CS handswitches again which will produce no additional help. Note:  MLB-3: 4-3 and 9-3, 1A and 1B PRF RECIRC DAMPER, will be closed (green light lit, red and white lights not lit) until they modulate open to limit Penetration room pressure to > -2 IN WC. 4. 6.3.1 (RNO)  Check All MLB-3 lights lit. Checks MLB-3 lights & observes all light lit except:

NOT lit: 1-2, 3-2, 4-1, 4-3, 8-2, 9-1, 9-3 S / U NOTE: This begins the ALTERNATE PATH. 5. 6.3.2 (RNO) IF any MLB-3 light NOT lit, THEN verify PHASE B CTMT ISO using ATTACHMENT 5, PHASE B CONTAINMENT ISOLATION. Proceeds to Attachment 5 S / U NOTE: The order of performance of the following elements is not critical. Step 1 of Attachment 5 directs the verification of associated component status for light not lit. The applicant may open MOV-3361A and B if they are not modulated open at this time. *6. Close Q1P19HV3611, IA TO CTMT (BOP) HS for HV-3611 taken to close. Observes green light lit, red light out, MLB-3, 1-2 lit. S / U Note: Performing EITHER element 7 or 8 satisfies success criteria for having ONE train of CCW from the Thermal Barrier isolated. *7. Close Q1P17HV3045, CCW FROM RCP THRM BARR HS for HV-3045 taken to close. Observes green light lit, red light out, MLB-3, 3-3 lit. S / U *8. Close Q1P17HV3184, CCW FROM RCP THRM BARR HS for HV-3184 taken to close. Observes green light lit, red light out, MLB-3, 8-1 lit. S / U ILT-38 JPM Page 5 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) Note: Starting either 1A or 1B PRF EXH fan satisfies success criteria for having ONE train of PRF on service. *9. Starts Q1E15M001A, 1A PRF EXH FAN HS for 1A PRF EXH FAN taken to START and released when red light is lit and green light is out. S / U *10. Starts Q1E15M001B, 1B PRF EXH FAN HS for 1A PRF EXH FAN taken to START and released when red light is lit and green light is out. S / U _____ STOP TIME Terminate when all Elements are complete. CRITICAL ELEMENTS: Critical Elements are denoted by an asterisk (*) before the element number. GENERAL

REFERENCES:

1. FNP-1-EEP-0.0, ver 46.1 2. PRA/IPE Human Reliability Analysis Notebook operator actions 3.6.10 and 3.6.11 3. K/As: WE14EA1.1 - 3.7 / 3.7 103A3.01 - 3.9 / 4.2 GENERAL TOOLS AND EQUIPMENT: 1. Provide a copy of FNP-1-EEP-0.0, ver 46 ILT-38 JPM Page 6 of 7 Critical ELEMENT justification: 1 Not critical - Check step 2 Critical - Starts Containment Spray. 3 Critical - Prevents RCP damage. 4-5 Not critical - No actions taken. 6 Critical- Isolates Containment. 7 or 8 Critical- Isolates Containment. 9 or 10 Critical - Allows proper filtration of any penetration room leakage. COMMENTS:

ILT-38 JPM HANDOUT Page 1 of 1 jmp e CONDITIONS When I tell you to begin, you are to PERFORM THE ACTIONS OF EEP-0.0, REACTOR TRIP OR SAFETY INJECTION. The conditions under which this task is to be performed are: a. A LOCA has occurred. b. EEP-0.0 steps 1 through 5 are complete. c. You are directed continue with step 6 of EEP-0.0 d. A pre-job brief is not required.

FNP-1-EEP-0.0 FOLDOUT PAGE REACTOR TRIP OR SAFETY INJECTION Revision 46.1 Step Action/Expected Response Response Not Obtained 1 Monitor RCP criteria 1.1 Greater than 16°F {45°F} subcooled in CETC mode. 1.1 IF HHSI flow greater than 0 gpm, THEN stop all RCPs. 2 Monitor switchover criteria 2.1 CST level greater than 5.3 ft 2.1 Align AFW pumps suction to SW using FNP-1-SOP-22.0 3 Monitor charging miniflow criteria (during SI) 3.1 RCS pressure less than 1900 psig 3.1 Verify miniflow valves open 3.2 RCS pressure greater than 1300 psig 3.2 Verify miniflow valves closed 4 Monitor adverse containment criteria 4.1 CTMT pressure less than 4 psig and radiation less than 105 R/hr 4.1 Utilize bracketed adverse CTMT condition numbers 5 Ruptured SG AFW isolation 5.1 Manually stop AFW flow to a S/G if BOTH conditions listed below occur: Level increases in an uncontrolled manner or radiation in that S/G is abnormal AND Narrow range level - GREATER than 31% {48%} 6 Monitor SFP conditions 6 Perform Attachment 10 Check Annunciator EH1, SFP TEMP HI CLEAR Check Annunciator EH2, SFP LEVEL HI-LO CLEAR IF applicable THEN check time to restore power is LESS THAN the time TO REACH 200°F in the SFP using Unit 1 Core Physics Curve Book, PCB-1-VOL1-CRV79 FNP ILT-38 JPM Page 1 of 7 jpm f CRO-NEW TITLE: Place The Standby CCW Hx On Service On "A" Train ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: X SIMULATOR CONTROL ROOM PLANT PROJECTED TIME: 10 MIN SIMULATOR IC NUMBER: IC-216 (Base -12) ALTERNATE PATH X TIME CRITICAL PRA JPM DIRECTIONS: 1. Examinee will obtain all references from the simulator. 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise. 3. Provide student with HANDOUT. 4. Allow student time to review control board. 5. Instructor will be provided to address alarms not related to evaluated task. TASK STANDARD: Upon successful completion of this JPM, the examinee will: 1. Respond to a loss of the On Service CCW train in Mode 3. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary)

Developer S Jackson Date: 4/9/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP ILT-38 JPM Page 2 of 7 EVENT DESCRIPTION ACTION DETAILS Reset into IC-216 Acknowledge computer alarms Run / Freeze Simulator Acknowledge Alarms Turn Horns ON Run / Freeze Simulator FNP ILT-38 JPM Page 3 of 7 CONDITIONS When I tell you to begin, you are to PLACE THE STANDBY CCW HX ON SERVICE ON "A" TRAIN. The conditions under which this task is to be performed are: a. The plant is in Mode 3. b. 'A' TRAIN is the ON-SERVICE TRAIN. c. 1B CCW Hx is on service and the 1C CCW Hx is aligned for standby operation on the 'A' train per SOP-23.0C. d. You are directed to swap the on service 'A' Train CCW HX from the 1B Hx to the 1C Hx per SOP-23.0 Section 4.4. e. The Rover is briefed and standing by. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME 1. 4.4.1 Ensure 1B CCW HX is aligned to the A Train CCW and A Train SW per Appendix 23.0C. This is in the initial conditions. If the applicant asks the SS (CUE: 1B CCW HX is aligned to the A Train CCW and A Train SW per Appendix 23.0C S / U 2. 4.4.2 Verify SW FROM 1C CCW HX Q1P16FV3009C handswitch is in MOD. Observes Q1P16FV3009C handswitch is in MOD S / U 3. 4.4.3 Verify 1C CCW HX DISCH FCV HIC 3009C is demanding the valve to be fully closed (100% demand). Observes 1C CCW HX DISCH FCV HIC 3009C is at the top of the scale - 100% S / U 4. 4.4.4. Locally verify closed SW FROM 1C CCW HX Q1P16FV3009C. Calls SO to locally verify Q1P16FV3009C closed. (SO CUE: Q1P16FV3009C is closed) S / U Note: When MOV3130C opens it will trigger the tripping of the 1C CCW pump. This begins the alternate path. *5. 4.4.5 Open SW TO 1C CCW HX Q1P16MOV3130C. MOV3130C handswitch is taken to open. Red light lights and green light is out. S / U FNP ILT-38 JPM Page 4 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) Note: The steps below are from AA3 Operator Action. 6. 1 Check 1C CCW PUMP has tripped Observes the green and amber light lit and red light out for 1C CCW pump S / U 7. 2 Verify standby pump running, if aligned to affected train. Takes 1B CCW pump switch to START, green light stays lit and red light stays out. S / U 8. 3 Perform the actions required by FNP AOP-9.0, LOSS OF COMPONENT COOLING WATER. Proceeds to AOP-9.0. S / U Note: The following steps are from AOP-9.0, Loss of Component Cooling Water. 9. 1 Verify CCW pump started in affected train. Takes 1B CCW pump switch to START, green light stays lit and red light stays out. S / U 10. 1.1 (RNO) Verify CCW pump started in the non- affected train. Observes 1A CCW pump red light lit and green light. S / U *11. 1.2 (RNO) IF CCW pump running in non-affected train, THEN start charging pump in non- affected train. Takes the 1C Charging pump HS to the START position then release and observes the red light lit and green light out with amps indicated. S / U *12. 1.3 (RNO) IF charging pump started in non-affected train, THEN stop charging pump in affected train. Takes 1A Charging pump HS to the STOP position then release and observes green light lit and red light out with zero amps. S / U Note: The RCP bearing temperatures may exceed 195°F by this time. 13. 2 [CA] Check cooling adequate for continued plant support. affected train. Observes no CCW pumps are running in the A train. S / U FNP ILT-38 JPM Page 5 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 2.1(RNO) IF the ON SERVICE train is affected, THEN perform the following: On service train is affected 14. 2.1.1 (RNO) IF the reactor is critical, THEN trip the reactor and perform, FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION, while continuing with this procedure. This step is N/A S / U *15. 2.1.2 (RNO) Verify all Reactor Coolant pumps stopped. Takes the 1A, 1B and 1C RCP HS's to STOP then release and observes green lights lit and red lights out with zero amps on all 3 RCPs and falling flow on all 3 loops. S / U 16. 2.1.3 (RNO) IF in Mode 3 or 4, THEN perform FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW while continuing with procedure. Goes to AOP-4.0 S / U Note: the steps below are from AOP-4.0, Loss of Reactor Coolant Flow and are Immediate Actions 17. 1 Check 1A and 1B RCPs - RUNNING. Observes ALL RCPs - green lights lit and red lights out S / U 18. 1 (RNO) Manually close pressurizer spray valve for affected RCP. [ ] 1A RCS loop spary valve PK-444C [ ] 1B RCS loop spray valve PK-444D Depresses the 'LOWER' demand button for PK-444C and PK-444D until demand = 0. S/U 19. 2 [CA] Maintain SG narrow range level stable at approximately 65% using: [ ] Auxiliary Feedwater Control Valves. Adjusts HIC 3227AA, 3227BA and 3227CA MDAWFP TO 1A,1B, 1C SG FLOW CONT to maintain SG water level. Applicant may isolate AFW to the SGs S / U FNP ILT-38 JPM Page 6 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) STOP TIME Terminate when the Immediate Actions of AOP-4.0 are complete. CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number. GENERAL REFERENCES 1. FNP-1-SOP-23.0, ver 94.2 2. FNP-1-ARP-1.1, ver 56 3. FNP-1-AOP-9.0, ver 25 4. FNP-1-AOP-4.0, ver 20 5. K/As: 008A2.01 - 3.3 / 3.6 026AA1.02 - 3.2 / 3.3

GENERAL TOOLS AND EQUIPMENT 1. FNP-1-SOP-23.0, ver 94.2 2. FNP-1-ARP-1.1, ver 55.1 3. FNP-1-AOP-9.0, ver 25 4. FNP-1-AOP-4.0, ver 19 Critical ELEMENT justification: 1 - 4 Not critical - Check steps. 5 Critical - Task completion. 6 Not critical - Check step. 7 Not critical - Pump does not start. 8 Not critical - No action required. 9 Not critical - Pump does not start. 10 Not critical - No action required. 11 Critical - Maintains seal injection and Pressurizer level. 12 Critical - Prevent Damage to the Charging pump. 13 Not critical - Check step. 14 Not critical - Step is N/A 15 Critical - Prevent Damage to the RCP's 16 Not critical - No operator action. 17 Not critical - Check step. 18 Not critical - with no RCPs running there is no negative impact on pressure control. 19 Not critical - SG overfill did not occur in twice the validation time. COMMENTS FNP ILT-38 JPM HANDOUT Page 1 of 1 jpm f CONDITIONS When I tell you to begin, you are to PLACE THE STANDBY CCW HX ON SERVICE ON "A" TRAIN. The conditions under which this task is to be performed are:

a. The plant is in Mode 3. b. 'A' TRAIN is the ON-SERVICE TRAIN. c. 1B CCW Hx is on service and the 1C CCW Hx is aligned for standby operation on the 'A' train per SOP-23.0C. d. You are directed to swap the on service 'A' Train CCW HX from the 1B Hx to the 1C Hx per SOP-23.0 Section 4.4. e. The Rover is briefed and standing by.

UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 1 of 170 SAFETYCOMPONENT COOLING WATER SYSTEM RELATEDPROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORYSECTIONSContinuous: ALL

Reference:

NONE Information: NONE

Approved:

David L Reed (for) 02/17/2014 Operations Manager Effective Date UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 2 of 170 Procedure Version Description Version Number Version Description 91.1Added checkboxes to notes & cautions. Corrected referenced step contained in App. 7, step 4.30. CR 396287 91.2Deleted reference to FNP-1-SOP-54.0 P&L 3.19.2 from step 2.18.3 due to same information is available in step 2.18.2. CR433685 92.0CR - 435885, TE361447 - Revised order of App 13 steps 4.2.5 thru 4.2.8 per CR/TE - brc 92.1 CR 448381 - Added P&L 2.38 to specify special PPE requirements while handling potassium chromate. CR 358592 - Added step 3.4.1 to Appendix 23.0B and 23.0C to provide a conditional statement to check the in service CCW HX. 93.0Added figures 1 & 2. Deleted CV requirement from numerous steps that no longer meet the definition requiring CV. 93.1Added P&L 2.39 for CCW processing time limits per CR 609985 Relocated Disconnect Figures To Appendix s CR # 641637 94.0Implemented changes to support DCP SNC 66497. 94.1Per CR703187, added steps to enhance CCW drum processing. Revised the procedure to include the appropriate records section 94.2Added information that minimum recirc time for chemical mixing is 72 hours. CR 769516 UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 3 of 170 Table of Contents Page1.0Purpose ......................................................................................................................................... 52.0PRECAUTIONS AND LIMITATIONS ............................................................................................ 53.0INITIAL CONDITIONS ................................................................................................................. 104.0INSTRUCTIONS ......................................................................................................................... 114.1"A" Train CCW System Startup for Normal Operation .....................................................114.2"B" Train CCW System Startup for Normal Operatio .......................................................124.3"A" Train on Service, Shifting to the Standby HX 1 .........................................................134.4"A" Train on Service, Shifting to the Standby HX 1 .........................................................144.5"B" Train on Service, Shifting to the Standby HX 1 .........................................................154.6"B" Train on Service, Shifting to the Standby HX 1A .......................................................164.7Shifting CCW Pumps on the On Service Train ................................................................174.8Operation of Off Service CCW Train - Train A ................................................................184.9Operation of Off Service CCW Train - Train B ................................................................194.10Aligning CCW for Plant Cooldown with "A" Trai ..............................................................214.11Aligning CCW for Plant Cooldown with "B" Trai ..............................................................214.12Aligning Additional CCW Cooling to the SFP HX--"A" Trai ..............................................224.13Aligning Additional CCW Cooling to the SFP HX--"B" Trai ..............................................234.14Removing_CCW from Plant Cooldown Lineup-"A" Train On Servic .............................244.15Removing CCW from Plant Cooldown Lineup-"B" Train On servic ...............................244.16Shifting On Service Train from "A" Train to "B" Trai ........................................................254.17Shifting On Service Train from "B" Train to "A" Trai ........................................................254.18Normal Makeup to CCW Surge Tank ..............................................................................254.19Emergency Makeup to CCW Surge Tank .......................................................................264.20Chemical Mixing ..............................................................................................................264.21Lowering Surge Tank Level .............................................................................................274.22Venting the CCW Heat Exchangers, SW Side ................................................................274.23Alternate Method of Opening CCW FROM RCP THRM BARR Q1P17HV3045 with High P Suspected (OR 2 99 603) ..........................................................................294.24Alternate Method of Opening CCW FROM RCP THRM BARR Q1P17HV3184 with High P Suspected (OR 2 99 603) ..........................................................................32 UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 4 of 170 4.25Restoring CCW Flow to the RCP Thermal Barriers after an Extended (> 4 hour) Loss: ................................................................................................................................3

45.0REFERENCES

............................................................................................................................ 376.0Records ....................................................................................................................................... 37APPENDIX 23.0ACHEMICAL MIXING ....................................................................................38APPENDIX 23.0B SHIFTING ON SERVICE TRAIN FROM TRAIN A TO TRAIN B................42APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM TRAIN B TO TRAIN A ...............60APPENDIX 1 B TRAIN CCW SURGE TANK FEED AND BLEED ..........................................77APPENDIX 2A TRAIN CCW SURGE TANK FEED AND BLEED ...........................................85APPENDIX 3CCW PROCESSING USING TEMPORARY DEMIN LINER (Deleted by Version 93.0) ...................................................................................................................92APPENDIX 4 FEED AND BLEED OF THE ON SERVICE CCW TRAIN (Deleted by Version 93.0) ...................................................................................................................93APPENDIX 5 PROCESSING CONTAINERS OF WASTE CCW USING TEMPORARY DEMIN LINER .................................................................................................................94APPENDIX 6 CCW SYSTEM REFILL FROM DRUMS .........................................................101APPENDIX 7 PROCESSING WASTE CCW USING TEMPORARY DEMIN LINER DIRECTLY FROM SYSTEM .........................................................................................104APPENDIX 8 ALIGNING B TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH B TRAIN SW OUT OF SERVICE .......................................................................................................................111APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE ...............................119APPENDIX 10 RETURNING 1A CCW PUMP TO SERVICE AFTER MAINTENANCE ........130APPENDIX 11 RETURNING 1B CCW PUMP TO SERVICE AFTER MAINTENANCE ........135APPENDIX 12 RETURNING 1C CCW PUMP TO SERVICE AFTER MAINTENANCE ........141APPENDIX 13  ALIGNING A TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH A TRAIN SW OUT OF SERVICE  ......................................................................................................................146APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE ......................153APPENDIX 15 ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1C CCW PUMP  ......................................................................................................................163APPENDIX 16 ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1A CCW PUMP  ......................................................................................................................167 UNIT 1 Farley Nuclear Plant    Procedure Number Ver FNP-1-SOP-23.0  94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 5 of 170  1.0 Purpose This procedure provides Initial Conditions, Precautions and Limitations, and Instructions for operation of the Component Cooling Water System (CCW). 2.0 PRECAUTIONS AND LIMITATIONS 2.1At least two independent component cooling water loops shall be OPERABLE while in operational modes 1, 2, 3, and 4. 2.2CCW is normally lined up so that   One CCW pump and one CCW heat exchanger is in operation supplying the on-service train and the secondary heat exchangers. The remaining pump and heat exchanger are valved into a closed loop with the redundant safety train. The off-service train is normally in operation in modes 1-4 supplying the operating charging pump, with the non-operating SFP HX flowpath aligned and CCW to the RHR HX isolated.  (Reference RER 1080944901) 2.3Control circuitry does not allow auto start of two pumps in the same train. In order for 1B CCW pump to be started by the ESS or LOSP sequencers; the train to which it is aligned must have the train dedicated pump supply breaker racked out. 2.4In order to maintain a train operable with the dedicated pump/breaker inoperable AND racked in, the cell switch should be jumpered for the swing breaker to ensure the swing breaker will close on an auto start signal with the dedicated pump breaker racked in. Additionally, a link should be opened in the autostart circuitry of the dedicated pump to prevent an autostart of the dedicated train breaker. This arrangement should remain in place until such time the dedicated breaker is declared operable or surveillance testing is started.  (AI 2008205335) 2.5Do not operate more than one CCW pump through one CCW heat exchanger. 2.6During normal operation of an operating train, component cooling heat exchanger outlet temperature should be maintained between 60°F and 105°F.

(CR 2004000155) 2.7If the CCW HX outlet temperature is maintained below 60°F for extended periods of time and is supplying cooling to the SECURED charging pump, then notify ES and begin sampling the Charging Pump oil for water and contaminants twice per month (reference Westinghouse Letter BPC-88-549). (AI 2009200595) UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 6 of 170 2.8The following is required during plant cooldown Component cooling water outlet temperature should not exceed 120°F. The off-service train is to be used for RHR. 2.9Frequent starting may damage the component cooling water pump motors. Limit pump starts as follows: Two successive starts from ambient temperature. One start from rated temperature. Subsequent starts: allow 30 minutes running time or 60 minutes idle time between starts. 2.10The off-service train CCW pump must be running before starting the off-service train charging pump or RHR pump. 2.11When the off-service CCW train is not in operation, the off-service train RHR Heat Exchange supply MOV should be maintained open to prevent lifting CCW system relief valves on pump auto starts. CCW TO 1A RHR HX Q1P17MOV3185A CCW TO 1B RHR HX Q1P17MOV3185B 2.12CCW pump flow should be greater than 2100 gpm. If pump flow falls below 2100 gpm, then the flow must be maintained greater than 1000 gpm. The time with flow less than 2100 gpm must be limited to less than 100 hours per month. (ABN 97-01080) The pump miniflow is sized to pass 1000 gpm. 2.13If the CCW pump miniflow is closed, such as for in-service testing, then at least 2 of the following 3 flow paths shall be aligned for pump discharge flow. The RHR heat exchanger The SFP heat exchanger The miscellaneous header This alignment will ensure greater than 2100 gpm flow with allowance for spurious MOV closure (ABN 97-0-1080). 2.14CCW surge tank level must be maintained above 13 inches. 2.15Reactor makeup water should only be used as an emergency source of makeup water to the CCW surge tank. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 7 of 170 2.16If the CCW surge tank vents are closed for reasons other than an actual high radiation alarm, then with Shift Supervisor concurrence, the CCW surge tank vents should be cycled once every shift (eight hours) and documented in the Control Room Log. 2.17The SW FROM CCW HX flow control valves, Q1P16FCV3009A, B & C have mechanical valve travel Open and Close stops. The Open Stop for Q1P16FCV3009A is set by the manual handwheel and should not be moved from a nominal setting of 45 open. The Open Stop for Q1P16FCV3009C is set by the manual handwheel and should not be moved from a nominal setting of 47 open. The Open Stop for Q1P16FCV3009B is set by the manual handwheel and should not be moved from a nominal setting of 47 open. If the Open Stop has been moved or one of the Open Stop hex nuts loosened, then a flow test may be required to reset the position of the Open Stop. (DCP-92-2-7928 / DCP 1070138701) 2.18CCW flow to the SFP HX's should be regulated as follows: 2.18.1When in Modes 1 - 4, then the CCW outlet valve for the SFP HX should be throttled to limit CCW flow to 1500 gpm through the SFP HX with a RHR HX on service on that train. 2.18.2If desired to lower SFP temperature while in Modes 5, 6 or defueled, then throttle CCW flow through the on service RHR HX and raise CCW flow in the SFP HX as necessary. This special condition will be documented by an admin LCO. The limit must be reinstated prior to entering Mode 4. The limit is reinstated by establishing CCW flow through the RHR HX and then verifying flow through the SFP HX is 1500 gpm with that train being the ON SERVICE TRAIN. 2.18.3When the core is off loaded into the SFP, then CCW flow to the SFP HX should be maintained in accordance with FNP-1-SOP-54.0, Spent Fuel Pit Cooling and PURIFICATION SYSTEM. 2.18.4CCW flow rates in excess of 3100 gpm through the SFP HX should be avoided. Flows exceeding 3100 gpm for brief periods, such as during performance of STPs is acceptable. (AIT 2002200675) UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 8 of 170 2.19IF core offload begins < 140 hours after shutdown, THEN the CCW inlet temperature to the SFP HX should be maintained < 105°F. 2.20IF core offload begins < 140 hours after shutdown, core offload is prohibited when CCW inlet temperature to the SFP HX exceeds 105°F. 2.21Service water supply to the standby CCW HX must be closed except when shifting the standby CCW HX. This ensures adequate SW flow is available to the on-service CCW HX and other vital loads in the event of an accident coincident with a loss of air. (AI 2004204513) 2.22CCW supply valve to SFP heat exchanger must remain open whenever CCW supply valve to RHR heat exchanger in the same train is closed. 2.23If possible, SFP cooling should be aligned opposite from a train that is carrying both the miscellaneous header and an in-service RHR HX. 2.24Component cooling water flow to an idle RCP should not be isolated unless reactor coolant system temperature less than 150°F. 2.25If CCW will be secured to the RCP motor oil coolers for longer than 2 months, then contact Maintenance to have the oil coolers drained and dried per RCP Technical Manual Technical Bulletin 81-02. 2.26CCW FROM RCP THRM BARR Q1P17HV3184 may experience hydraulic sticking while opening similar to Q1P17HV3045 and Section 4.22 should be used for guidance. If this occurs, closely monitor RCP bearing temperatures and seal injection flow. When the valve opens verify these parameters return to normal. (CR #2000005361) 2.27When CCW is to be drained from the system with the intent to reuse, then appropriately labeled and clean 55 gallon two bunghole drums should be obtained from the Storeroom (Main Warehouse) or FAC Group. (CIR 2-94-010) 2.28All hoses and pumps to be used in draining or pumping reusable CCW should be flushed with demin water before use. (CIR 2-94-010) 2.29All CCW intended for reuse will be sampled by Chemistry and the sample results obtained prior to placing in the CCW system. (CIR 2-94-010) 2.30Guidance in this procedure has the potential to impact reactivity. Close coordination with the control room operators is required to ensure proper reactivity management per NMP-OS-001, REACTIVITY MANAGEMENT PROGRAM. (AI 2008203128) UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 9 of 170 2.31To eliminate the requirement for Appendix R Kaowool raceway fire barriers for certain raceways in fire areas 2-006 Zone 1 and 2-020, Kaowool Fire Protection Administrative Controls have to be implemented when the swing CCW pump is placed in service for a corresponding dedicated Train pump that is not available. Therefore, when Train A or Train B CCW pump is made unavailable and the swing pump is placed in service on that Train, then the following Kaowool FP administrative controls must be established: Begin tracking (e.g., LCO) the amount of time the swing component is in service for the unavailable dedicated Train component. If the swing component remains in service for the unavailable dedicated Train component for more than 30 days, then hourly fire watches must be established in the appropriate fire area per FNP-0-SOP-0.4 Table 13 until the unavailable dedicated Train pump is available. 2.32Pipe internals can be potentially degraded. Proceed with caution. Do not subject vent/drain piping to any undue stress during removal of pipe cap/plug. (AI2009202698). 2.33Changes to CCW temperature will have an effect on RCP seal leakoff flow rates. If desired to adjust CCW temperature due to RCP seal leakoff flow rate concerns, the guidance in Sections 4.1 and 4.2 concerning adjustment of FCV's 3009 as desired may be used. However, CCW heat exchanger outlet temperature should be maintained between 60°F and 105°F per P&L 2.6. 2.34While in modes 1-4, both trains of CCW room coolers should not be removed from service at the same time. 2.35Any operations involving manipulation of the 4kV disconnect switches associated shall include visual confirmation of the following: 2.35.1The main contacts are in the required state, open or closed. (One contact per phase.) Refer to figure 1 and 2. 2.35.2 The arcing contacts are in the required state, open or closed. (One contact per phase.) Refer to figure 1 and 2. 2.36To maintain SFP temperature as low as possible during the core off load, consideration should be given to maximizing CCW cooling to the SFP HX(s) early in the fuel transfer to the SFP. Throttle CCW flow to the on service RHR HX(s) as required to maintain appropriate cooling to the on-service train(s) of RHR during core off load. CCW flow rates in excess of 3100 GPM through the SFP HX should be avoided. (1R23 OLL103 CR2010114600) 2.37When SW is isolated to a CCW HX, (ie, standby heat exchanger), Chemistry shall be notified of the isolated heat exchanger so they may begin monitoring chlorine levels in the idle heat exchanger. (TE 289687) 2.38Proper personal protection equipment (PPE) must be worn while handling potasium chromate to prevent eye and skin contact. The minimum requirement for PPE is safety glasses with side shields, laboratory coat, and chemical-resistant gloves. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 10 of 170 2.39Notify Chemistry whenever chromated water is drained from a system and drummed. There is a 72 hr. requirement to process the water once the decision has been made to not reuse the water. The NPDES permit requires Chemistry to sample the water during processing, and the samples are shipped off site for various analyses. CCW samples contain Tritium, and must be shipped as radioactive material. There is a 7 day time limit on the total suspended solids analysis, starting at the time the sample is pulled. 3.0 INITIAL CONDITIONS 3.1The electrical distribution system is energized and aligned for normal operation per FNP-1-SOP-36.0, PLANT ELECTRICAL DISTRIBUTION LINE-UP, with exceptions noted. 3.2The compressed air system is in normal operation per FNP-1-SOP-31.0, COMPRESSED AIR SYSTEM. 3.3The component cooling water system valves and electrical distribution systems are aligned per system checklist FNP-1-SOP-23.0A, with exceptions noted. {CMTs 0008598 & 0008599} 3.4The component cooling water system is filled and vented, with the component cooling surge tank filled to a level of approximately 42 inches. 3.5The service water system is in normal operation per FNP-1-SOP-24.0, SERVICE WATER SYSTEM. 3.6The demineralized water system and/or the reactor makeup water system is aligned to the component cooling water surge tank per FNP-1-SOP-5.0, DEMINERALIZED MAKEUP WATER SYSTEM, and/or FNP-1-SOP-4.0, REACTOR MAKEUP WATER SYSTEM. 3.7Radiation monitors R-17A and R-17B are in normal operation per FNP-1-SOP-45.0, RADIATION MONITORING SYSTEM. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 11 of 170 4.0 INSTRUCTIONS 4.1A Train CCW System Startup for Normal Operation NOTEIf required, then the standby pump may be started in place of the on service pump. 4.1.1 Verify 1B CCW pump and 1B CCW HX are aligned to A Train per Appendix 23.0C. 4.1.2 Check 1B CCW HX CCW OUTLET ISO, Q1P17V008B is closed. Q1P17V008B may be open if standby heat exchanger in service per Section 4.3 or 4.5. 4.1.3 Verify that SW FROM 1C CCW HX Q1P16FV3009C OR SW FROM 1B CCW HX Q1P16FV3009B handswitch is in MOD. 4.1.4 Throttle 1C CCW HX DISCH FCV HIC 3009C OR 1B CCW HX DISCH FCV HIC 3009B as necessary to control CCW temperature. 4.1.5 Verify on-service CCW HX outlet valve Q1P17V008C or Q1P17V008B open. 4.1.6 Verify open CCW TO 1A RHR HX Q1P17MOV3185A. CAUTIONDO NOT operate more than one CCW pump through one CCW heat exchanger. 4.1.7 Start 1C or 1B CCW PUMP. 4.1.8 Verify flow increase on FI 3043CA OR BA, for the on-service heat exchanger. 4.1.9 Monitor CCW FROM CCW HX TEMP TI 3024C OR TI 3024B to ensure CCW temperature is maintained less than 105°F. 4.1.10 Monitor service water header pressure while adjusting HIC 3009C or B. 4.1.11After system is stable then CCW TO 1A RHR HX Q1P17MOV3185A may be closed. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 12 of 170 4.2"B" Train CCW System Startup for Normal Operation NOTEIF required, THEN the standby pump may be started in place of the on service pump. 4.2.1 Verify 1B CCW pump and 1B CCW HX are aligned to B Train per Appendix 23.0B 4.2.2 Check 1B CCW HX CCW OUTLET ISO, Q1P17V008B closed. Q1P17V008B may be open if standby heat exchanger in service per Section 4.4 or 4.6. 4.2.3 Verify that SW FROM 1A CCW HX Q1P16FV3009A OR SW FROM 1B CCW HX Q1P16FV3009B handswitch is in MOD. 4.2.4 Throttle 1A CCW HX DISCH FCV HIC 3009A OR 1B CCW HX DISCH FCV HIC 3009B as necessary to control CCW temperature. 4.2.5 Verify on-service CCW HX outlet valve Q1P17V008A OR Q1P17V008B open. 4.2.6 Verify open CCW TO 1B RHR HX Q1P17MOV3185B. CAUTIONDO NOT operate more than one CCW pump through one CCW heat exchanger. 4.2.7 Start 1A OR 1B CCW PUMP. 4.2.8 Verify flow increase on FI 3043AA OR BA, for the on-service heat exchanger. 4.2.9 Monitor CCW FROM CCW HX TEMP TI3024A or TI3024B to ensure CCW temperature is maintained less than 105°F. 4.2.10 Monitor service water header pressure while adjusting HIC 3009A or HIC 3009B 4.2.11After system is stable then CCW TO 1B RHR HX Q1P17MOV3185B may be closed. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 13 of 170 4.3A Train on Service, Shifting to the Standby HX 1B 4.3.1 Ensure 1B CCW HX is aligned to the A Train CCW and A Train SW per Appendix 23.0C. 4.3.2 Verify SW FROM 1B CCW HX Q1P16FV3009B handswitch is in MOD. 4.3.3 Verify 1B CCW HX DISCH FCV HIC 3009B is demanding the valve to be fully closed (100% demand). 4.3.4Locally verify closed SW FROM 1B CCW HX Q1P16FV3009B. 4.3.5 Open SW TO 1B CCW HX Q1P16MOV3130B. 4.3.6 Adjust 1B CCW HX DISCH FCV, HIC 3009B to obtain approximately 2000 gpm SW flow on FI 3009BA 4.3.7 Open 1B CCW HX CCW OUTLET ISO, Q1P17V008B to place 1B CCW HX on service. 4.3.8 Verify flow increase on FI 3043BA. CAUTIONCCW temperature should be maintained as stable as possible to minimize effects on the following: Reactivity changes due to changes in letdown temperature RCP Oil Levels 4.3.9 Throttle open 1B CCW HX DISCH FCV HIC 3009B while throttling closed 1C CCW HX DISCH FCV HIC 3009C Maintain existing service water pressure. Ensure CCW temperature is maintained less than 105°F. (120°F if aligned for plant cooldown.) Locally check 1B CCW HX DISCH FCV 3009B responds to controller demand. (CR 2009107460) 4.3.10After temperature stabilized with 1B HX on service, place 1C CCW HX in Standby by closing 1C CCW HX OUTLET VLV Q1P17V008C. 4.3.11 Verify flow on FI 3043CA decreases. 4.3.12 Verify 1C CCW HX DISCH FCV HIC 3009C fully closed. 4.3.13 Close SW TO 1C CCW HX Q1P16MOV3130C. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 14 of 170 NOTEOpening the breaker in the following step is only required when CCW is required to be operable. Breaker may be left closed in Mode 5 or 6 if an Admin LCO is written to ensure it is opened prior to Mode 4. 4.3.14 Open power supply breaker Q1R17BKRFVD5, SW TO 1B CCW HX Q1P16MOV3130B. 4.3.15 Notify Chemistry of current alignment of CCW HX's, for monitoring purposes. 4.4A Train on Service, Shifting to the Standby HX 1C 4.4.1 Ensure 1B CCW HX is aligned to the A Train CCW and A Train SW per Appendix 23.0C. 4.4.2 Verify SW FROM 1C CCW HX Q1P16FV3009C handswitch is in MOD. 4.4.3 Verify 1C CCW HX DISCH FCV HIC 3009C is demanding the valve to be fully closed (100% demand). 4.4.4Locally verify closed SW FROM 1C CCW HX Q1P16FV3009C. 4.4.5 Open SW TO 1C CCW HX Q1P16MOV3130C. 4.4.6 Adjust 1C CCW HX DISCH FCV, HIC 3009C to obtain approximately 2000 gpm SW flow on FI 3009CA 4.4.7 Open 1C CCW HX CCW OUTLET ISO, Q1P17V008C to place 1C CCW HX on service. 4.4.8 Verify flow increase on FI 3043CA. CAUTIONCCW temperature should be maintained as stable as possible to minimize effects on the following: Reactivity changes due to changes in letdown temperature RCP Oil Levels 4.4.9 Throttle open 1C CCW HX DISCH FCV HIC 3009C while throttling closed 1B CCW HX DISCH FCV HIC 3009B. Maintain existing service water pressure. Ensure CCW temperature is maintained less than 105°F. (120°F if aligned for plant cooldown.) Locally check 1C CCW HX DISCH FCV 3009C responds to controller demand. (CR 2009107460) UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 15 of 170 4.4.10After temperature stabilized with 1C HX on service, place 1B CCW HX in Standby by closing 1B CCW HX OUTLET VLV Q1P17V008B. 4.4.11 Verify flow decrease on FI 3043BA. 4.4.12 Verify SW FROM 1B CCW HX Q1P16FV3009B fully closed. 4.4.13 Close power supply breaker Q1R17BKRFVD5, SW TO 1B CCW HX Q1P16MOV3130B. 4.4.14 Close SW TO 1B CCW HX Q1P16MOV3130B. 4.4.15 Notify Chemistry of current alignment of CCW HX's, for monitoring purposes. 4.5"B" Train on Service, Shifting to the Standby HX 1B 4.5.1 Ensure CCW HX 1B is aligned to the B Train CCW and B Train Service Water per Appendix FNP-1-SOP-23.0B. 4.5.2 Verify SW FROM 1B CCW HX Q1P16FV3009B handswitch is in MOD. 4.5.3 Verify 1B CCW HX DISCH FCV HIC 3009B is demanding the valve to be fully closed (100% demand). 4.5.4Locally verify closed SW FROM 1B CCW HX Q1P16FV3009B. 4.5.5 Open SW TO 1B CCW HX Q1P16MOV3130B. 4.5.6 Adjust 1B CCW HX DISCH FCV, HIC 3009B to obtain approximately 2000 gpm SW flow on FI 3009BA. 4.5.7 Open 1B CCW HX CCW OUTLET ISO, Q1P17V008B. 4.5.8 Verify flow increases on FI 3043BA. CAUTIONCCW temperature should be maintained as stable as possible to minimize effects on the following: Reactivity changes due to changes in letdown temperature RCP Oil Levels 4.5.9 Throttle open 1B CCW HX DISCH FCV HIC 3009B while throttling closed 1A CCW HX DISCH FCV HIC 3009A. Maintain existing service water pressure. Ensure CCW temperature is maintained less than 105°F. (120°F if aligned for plant cooldown.) Locally check 1B CCW HX DISCH FCV 3009B responds to controller demand. (CR 2009107460) UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 16 of 170 4.5.10After temp stabilized with 1B HX on service, place 1A CCW HX in Standby by closing 1A CCW HX OUTLET VLV Q1P17V008A. 4.5.11 Verify flow decreases on FI 3043AA. 4.5.12 Verify 1A CCW HX DISCH FCV HIC 3009A fully closed. 4.5.13 Close SW TO 1A CCW HX Q1P16MOV3130A. 4.5.14 Notify Chemistry of current alignment of CCW HX's, for monitoring purposes. 4.6"B" Train on Service, Shifting to the Standby HX 1A 4.6.1 Ensure 1B CCW HX is aligned to the B Train CCW and B Train Service Water per Appendix 23.0B. 4.6.2 Verify SW FROM 1A CCW HX Q1P16FV3009A handswitch is in MOD. 4.6.3 Verify 1A CCW HX DISCH FCV HIC 3009A is demanding the valve to be fully closed (100% demand). 4.6.4Locally verify closed SW from 1A CCW HX Q1P16FV3009A. 4.6.5 Open SW TO 1A CCW HX Q1P16MOV3130A. 4.6.6 Adjust 1A CCW HX DISCH FCV, HIC 3009A to obtain approximately 2000 gpm SW flow on FI 3009AA 4.6.7 Open 1A CCW HX CCW OUTLET ISO, Q1P17V008A to place 1A HX on service. 4.6.8 Verify flow increases on FI 3043AA. CAUTIONCCW temperature should be maintained as stable as possible to minimize effects on the following: Reactivity changes due to changes in letdown temperature RCP Oil Levels 4.6.9 Throttle open 1A CCW HX DISCH FCV HIC 3009A while throttling closed 1B CCW HX DISCH FCV HIC 3009B. Maintain existing service water pressure. Ensure CCW temperature is maintained less than 105°F. (120°F if aligned for plant cooldown.) Locally check 1A CCW HX DISCH FCV 3009A responds to controller demand. (CR 2009107460) UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 17 of 170 4.6.10After temperature stabilized with HX 1A on service, place 1B CCW HX in Standby by closing 1B CCW HX CCW OUTLET ISO, Q1P17V008B. 4.6.11 Verify flow decrease on FI 3043BA. 4.6.12 Verify 1B CCW HX DISCH FCV HIC 3009B fully closed. 4.6.13 Close SW TO 1B CCW HX Q1P16MOV3130B. 4.6.14 Notify Chemistry of current alignment of CCW HX's, for monitoring purposes. 4.7Shifting CCW Pumps on the On-Service Train 4.7.1 Monitor CCW flow annunciators and RCP thermal barrier valves during and after this evolution.NOTEStep 4.7.2 or Step 4.7.3 is performed to minimize the pressure transient which could otherwise result in CCW to Thermal Barrier HX isolation. 4.7.2IF A Train is the on service train, THEN open CCW TO 1A RHR HX Q1P17MOV3185A. 4.7.3IF B Train is the on service train, THEN open CCW TO 1B RHR HX Q1P17MOV3185B. CAUTIONSThe operation of two pumps through on HX is NOT allowed. CCW temperature should be maintained as stable as possible to minimize effects on the following: Reactivity changes due to changes in letdown temperature RCP Oil Levels 4.7.4Simultaneously start the Standby CCW pump and stop the on service CCW pump. 4.7.5 Verify the proper flow response on the appropriate flow indicator. FI 3043AA FI 3043BA, FI 3043CA UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 18 of 170 4.7.6IF A Train is the on service train, THEN close CCW TO 1A RHR HX Q1P17MOV3185A unless required to support RHR operation. 4.7.7IF B Train is the on service train, THEN close CCW TO 1B RHR HX Q1P17MOV3185B unless required to support RHR operation. 4.7.8IF placing 1B CCW pump in service to replace an inoperable CCW pump, THEN perform one of the following. (Otherwise 1B CCW pump will not sequence on following a SI/LOSP) 4.7.8.1 Rackout the supply breaker for the inoperable pump. 4.7.8.2 Perform APPENDIX 15, ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1C CCW PUMP. 4.7.8.3 Perform APPENDIX 16, ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1A CCW PUMP NOTEThe off-service train is normally in operation in modes 1-4 supplying the operating charging pump, with the non-operating SFP HX flowpath aligned and CCW to the RHR HX isolated. (Reference RER 1080944901) 4.8Operation of Off-Service CCW Train - Train A 4.8.1 Verify the off-service train A, SW FROM 1C CCW HX Q1P16FV3009C handswitch in MOD. 4.8.2 Throttle 1C CCW HX DISCH FCV HIC 3009C as necessary to control CCW temperature. 4.8.3 Verify the off-service train 1C CCW HX CCW OUTLET ISO, Q1P17V008C is open. 4.8.4 Verify open CCW TO 1A RHR HX Q1P17MOV3185A. 4.8.5 Start the off-service train 1C CCW PUMP. 4.8.6 Verify flow increases on FI 3043CA. 4.8.7 Monitor CCW HX outlet temperature to ensure CCW temperature is maintained less than 105°F (120°F IF aligned for plant cooldown). NOTECCW TO 1A RHR HX Q1P17MOV3185A should remain open, if swapping the on service train is in progress, to prevent system pressure spike when CCW trains are cross connected during swap. (1-95-063) Minimize operating time with CCW flow > 6000 gpm. 4.8.8IF operation of A Train RHR NOT anticipated, THEN close CCW TO 1A RHR HX Q1P17MOV3185A. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 19 of 170 4.8.9IF it is desired to secure the 1C CCW pump, THEN check that conditions exist to allow securing the 1C CCW pump. 4.8.9.1 Check for the following conditions: Spent fuel pool cooling is aligned to B Train. 1A RHR pump is not running. 1A charging pump or 1B charging pump (if aligned to A Train) not running. No other reasons exist to maintain 1C CCW pump running. 4.8.9.2 IF above conditions are NOT met, THEN notify the Shift Supervisor that 1C CCW pump is required for plant operations. 4.8.10IF these conditions are satisfied, THEN the 1C CCW Pump may be stopped. 4.8.11IF the 1C CCW pump is stopped, THEN open CCW TO 1A RHR HX Q1P17MOV3185A. NOTEThe off-service train is normally in operation in modes 1-4 supplying the operating charging pump, with the non-operating SFP HX flowpath aligned and CCW to the RHR HX isolated. (Reference RER 1080944901) 4.9Operation of Off-Service CCW Train - Train B 4.9.1 Verify the off-service train B, SW FROM 1A CCW HX Q1P16FV3009A handswitch in MOD. 4.9.2 Throttle 1A CCW HX DISCH FCV HIC 3009A as necessary to control CCW temperature. 4.9.3 Verify the off-service train 1A CCW HX CCW OUTLET ISO, Q1P17V008A is open. 4.9.4 Verify open CCW TO 1B RHR HX Q1P17MOV3185B. 4.9.5 Start the off-service train 1A CCW PUMP. 4.9.6 Verify flow increases on FI 3043AA. 4.9.7 Monitor CCW HX outlet temperature to ensure CCW temperature is maintained less than 105°F (120°F IF aligned for plant cooldown). UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 20 of 170 NOTECCW TO 1B RHR HX Q1P17MOV3185B should remain open, if swapping the on service train is in progress, to prevent system pressure spike when CCW trains are cross connected during swap. (1-95-063) Minimize operating time with CCW flow > 6000 gpm. 4.9.8IF operation of B Train RHR NOT anticipated, THEN close CCW TO 1B RHR HX Q1P17MOV3185B. 4.9.9IF it is desired to secure the 1A CCW pump, THEN check that conditions exist to allow securing the 1A CCW pump. 4.9.9.1 Check for the following conditions: Spent fuel pool cooling is aligned to A Train. 1B RHR pump is NOT running. 1C charging pump or 1B charging pump (if aligned to B Train) NOT running. No other reasons exist to maintain 1A CCW pump running. 4.9.9.2 IF above conditions are NOT met, THEN notify the Shift Supervisor that 1A CCW pump is required for plant operations. 4.9.10IF these conditions are satisfied, THEN the 1A CCW Pump may be stopped. 4.9.11IF the 1A CCW pump is stopped, THEN open CCW TO 1B RHR HX Q1P17MOV3185B. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 21 of 170 4.10Aligning CCW for Plant Cooldown with A Train NOTEPlant cooldown may require operation of four service water pumps. 4.10.1 Start additional service water pumps as required per FNP-1-SOP-24.0, SERVICE WATER SYSTEM. 4.10.2IF placing 1A RHR pump in service in the off-service train, THEN verify Train A CCW in operation per Section 4.8. 4.10.3 Verify open Train A CCW TO 1A RHR HX Q1P17MOV3185A (Q1P17V029A). CAUTIONDo not exceed a spent fuel pool water temperature of 120°F. 4.10.4IF desired to increase CCW flow through the RHR HX OR to limit flow through CCW HX, THEN close CCW TO 1B SFP HX Q1P17MOV3094B. 4.11Aligning CCW for Plant Cooldown with B Train NOTEPlant cooldown may require operation of four service water pumps. 4.11.1 Start additional service water pumps as required per FNP-1-SOP-24.0, SERVICE WATER SYSTEM. 4.11.2IF placing 1B RHR pump in service in the off-service train, THEN verify Train B CCW in operation per Section 4.9. 4.11.3 Verify open off-service Train B CCW TO 1B RHR HX Q1P17MOV3185B. CAUTIONDo not exceed a spent fuel pool water temperature of 120°F. 4.11.4IF desired to increase CCW flow through the RHR HX OR to limit flow through CCW HX, THEN close off-service train B CCW TO 1A SFP HX Q1P17MOV3094A. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 22 of 170 NOTEDuring the performance of the following section, Precaution and Limitation 2.18 should be referenced. 4.12Aligning Additional CCW Cooling to the SFP HX--A Train 4.12.1The plant is in Modes 5, 6 OR defueled AND it has become necessary to provide additional cooling to the A Train SFP HX. 4.12.2 Throttle closed 1A RHR HX CCW OUTLET ISO, Q1P17V028A AND / OR throttle open 1B SFP HX CCW OUTLET ISO, Q1P17V016B as required. 4.12.3 Initiate an admin LCO per Precaution and Limitation 2.18.2. 4.12.4During core reload OR prior to Mode 4 entry, reestablish the 1500 gpm limit as follows: 4.12.4.1 Verify open Train A CCW To 1A RHR HX Q1P17MOV3185A. 4.12.4.2 Verify open Train A CCW TO 1B SFP HX Q1P17MOV3094B. 4.12.4.3 Throttle 1B SFP HX CCW OUTLET ISO, Q1P17V016B, as required to limit flow through the SFP HX to 1500 gpm. 4.12.4.4 Verify open 1A RHR HX CCW OUTLET ISO, Q1P17V028A and seal in position. 4.12.4.5 Verify 1B SFP HX CCW OUTLET ISO, Q1P17V016B, throttled as required to limit flow through the SFP HX to 1500 gpm, and seal in position. 4.12.5Independently Verify the following: 1B SFP HX CCW OUTLET ISO, Q1P17V016B sealed throttled. 1A RHR HX CCW OUTLET ISO, Q1P17V028A sealed open. CCW TO 1A RHR HX Q1P17MOV3185A open. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 23 of 170 NOTEDuring the performance of the following section, Precaution and Limitation 2.18 should be referenced. 4.13Aligning Additional CCW Cooling to the SFP HX--"B" Train 4.13.1The plant is in Modes 5, 6 OR defueled AND it has become necessary to provide additional cooling to the B Train SFP HX. 4.13.2 Throttle closed 1B RHR HX CCW OUTLET ISO, Q1P17V028B AND / OR throttle open 1A SFP HX CCW OUTLET ISO, Q1P17V016A as required. 4.13.3 Initiate an admin LCO per Precaution and Limitation 2.18.2.4.13.4During core reload OR prior to Mode 4 entry, reestablish the 1500 gpm limit as follows: 4.13.4.1 Verify open Train B CCW TO 1B RHR HX Q1P17MOV3185B. 4.13.4.2 Verify open Train B CCW TO A SFP HX Q1P17MOV3094A. 4.13.4.3 Verify open 1B RHR HX CCW OUTLET ISO, Q1P17V028B and seal in position. 4.13.4.4 Verify 1A SFP HX CCW OUTLET ISO, Q1P17V016A, throttled as required to limit flow through the SFP HX to 1500 gpm, and seal in position. 4.13.5Independently verify the following: A SFP HX CCW OUTLET ISO, Q1P17V016A sealed throttled. 1B RHR HX CCW OUTLET ISO, Q1P17V028B sealed open. CCW TO 1B RHR HX Q1P17MOV3185B open. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 24 of 170 4.14Removing CCW from Plant Cooldown Lineup-A Train On Service 4.14.1 Verify open CCW TO 1B SFP HX Q1P17MOV3094B. 4.14.2 Close CCW TO 1A RHR HX Q1P17MOV3185A. 4.14.3IF required, THEN secure the off-service B Train CCW train as follows: 4.14.3.1 Stop the 1A CCW PUMP. 4.14.3.2 Open B Train CCW TO 1A SFP HX Q1P17MOV3094A if closed. 4.14.3.3 Verify open B Train CCW TO 1B RHR HX Q1P17MOV3185B. 4.14.3.4 Verify fully open off-service train RHR HX CCW OUTLET VLV Q1P17V028B. 4.15Removing CCW from Plant Cooldown Lineup-"B" Train On service 4.15.1 Verify open CCW TO 1A SFP HX Q1P17MOV3094A. 4.15.2 Close CCW TO 1B RHR HX Q1P17MOV3185B. 4.15.3IF required, THEN secure the off-service CCW train as follows: 4.15.3.1 Stop 1C CCW PUMP. 4.15.3.2 Open CCW TO 1B SFP HX Q1P17MOV3094B if closed. 4.15.3.3 Verify open CCW TO 1A RHR HX Q1P17MOV3185A. 4.15.3.4 Verify fully open RHR HX CCW OUTLET VLV Q1P17V028A. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 25 of 170 4.16Shifting On-Service Train from A Train to B Train 4.16.1 Notify Shift Chemist that on service train will be shifted. 4.16.2 Shift train alignment from A Train to B Train by performing Appendix 23.0B. 4.17Shifting On-Service Train from B Train to A Train 4.17.1 Notify Shift Chemist that on service train will be shifted. 4.17.2 Shift train alignment from B Train to A Train by performing Appendix FNP-1-SOP-23.0C. 4.18Normal Makeup to CCW Surge Tank 4.18.1 Notify Shift Chemist that the CCW surge tank is to be made up to. 4.18.2 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 4.18.3 Monitor CCW surge tank level indications. LI-3027A LI-3027B 4.18.4 Maintain level between 35 inches and 50 inches. 4.18.5IF desired, THEN open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A to add makeup to A portion of CCW surge tank. 4.18.6IF desired, THEN open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B to add makeup to B portion of CCW surge tank. 4.18.7WHEN makeup addition is completed, THEN close appropriate valve(s). MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A. MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 26 of 170 4.19Emergency Makeup to CCW Surge Tank CAUTIONReactor makeup water should only be used as an emergency source of makeup water to the CCW surge tank. 4.19.1 Close CCW SRG TK DEMIN INLET ISO, N1P11V045. 4.19.2 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 4.19.3 Monitor CCW surge tank level indications. LI-3027A LI-3027B 4.19.4 Maintain level between 35 inches and 50 inches. 4.19.5IF desired, THEN open MKUP TO CCW FROM RMW Q1P17MOV3031A to add makeup to the A portion of the CCW surge tank. 4.19.6IF desired, THEN open MKUP TO CCW FROM RMW Q1P17MOV3031B to add makeup to the B portion of the CCW surge tank. 4.19.7WHEN makeup addition is completed, THEN close appropriate valve(s). MKUP TO CCW FROM RMW Q1P17MOV3031A MKUP TO CCW FROM RMW Q1P17MOV3031B 4.19.8 Open CCW SRG TK DEMIN INLET ISO, N1P11V045. 4.20Chemical Mixing 4.20.1 Perform Appendix FNP-1-SOP-23.0A for chemical mixing. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 27 of 170 4.21Lowering Surge Tank Level 4.21.1 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 4.21.2 Uncap and attach a suitable fitting and hose to CCW SRG TK A TRN DRN, Q1P17V113A and route to a drum. 4.21.3 Open CCW SRG TK A TRN DRN, Q1P17V113A to lower surge tank level. Ensure that the drum does not overflow. 4.21.4 Close CCW SRG TK A TRN DRN, Q1P17V113A when the desired level is obtained, remove the hose and fitting and replace the pipe cap. 4.22Venting the CCW Heat Exchangers, SW Side CAUTIONPipe internals can be potentially degraded. Proceed with caution. Do not subject vent/drain piping to any undue stress during removal of pipe cap/plug. (AI2009202698). 4.22.1 Verify the tube side vents and drains closed per Table 1. Table 1 HX 1A HX 1B HX 1C Tube side drain Q1P16V005B Q1P16V005D Q1P16V005F Tube side drain Q1P16V005A Q1P16V005C Q1P16V005E Tube side vent Q1P16V004A Q1P16V004B Q1P16V004C SW inlet drain Q1P16V257A Q1P16V257B Q1P16V257C SW outlet vent Q1P16V004D Q1P16V004E Q1P16V004F 4.22.2 Verify the applicable HX DISCH FCV closed. 1A CCW HX DISCH FCV HIC 3009A 1B CCW HX DISCH FCV HIC 3009B 1C CCW HX DISCH FCV HIC 3009C UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 28 of 170 4.22.3 Throttle open appropriate valve as required to provide a source of water for the venting operation. 1A CCW HX DISCH FCV HIC 3009A 1B CCW HX DISCH FCV HIC 3009B 1C CCW HX DISCH FCV HIC 3009C 4.22.4 Open the tube side vent per Table 1 until air free water issues, then close and cap. 4.22.5 Open the SW outlet vent per Table 1 until air free water issues, then close and cap 4.22.6 Close the appropriate valve service water flow control valve. 1A CCW HX DISCH FCV HIC 3009A 1B CCW HX DISCH FCV HIC 3009B 1C CCW HX DISCH FCV HIC 3009C 4.22.7 Align the heat exchangers for service or standby operation as required. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 29 of 170 NOTEReference Tech Spec 3.6.3 and TRM 13.6.2 for Containment Isolation Valves. 4.23Alternate Method of Opening CCW FROM RCP THRM BARR Q1P17HV3045 with High P Suspected (OR 2-99-603) 4.23.1IF MCB handswitch does not open CCW FROM RCP THRM BARR Q1P17HV3045, AND high P is the suspected cause, THEN wait approximately 10~15 minutes or as determined by the Shift Supervisor and re-attempt to open the valve. This may be repeated for up to 3 hours to allow the pressure to equalize. CAUTIONDo not use any mechanical leverage on CCW FROM RCP THRM BARR Q1P17HV3045 handwheel. Damage to the pin which connects the handwheel to the valve stem may result. (OR 2-98-320) 4.23.2IF requested by the Shift Supervisor, THEN open CCW FROM RCP THRM BARR Q1P17HV3045 with the manual handwheel as follows: 4.23.2.1 Fail air to CCW FROM RCP THRM BARR Q1P17HV3045. 4.23.2.2 Open CCW FROM RCP THRM BARR Q1P17HV3045 with the manual handwheel. 4.23.2.3 Restore air to CCW FROM RCP THRM BARR Q1P17HV3045. 4.23.2.4 Return the handwheel for CCW FROM RCP THRM Q1P17HV3045 to the neutral position. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 30 of 170 CAUTIONDo not open or attempt to open CCW FROM RCP THRM BARR Q1P17HV3045 while CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161 or RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173 is open. 4.23.3IF requested by the Shift Supervisor, THEN equalize pressure around CCW FROM RCP THERMAL BARRIERS CHECK VALVE Q1P17V106 (downstream of CCW FROM RCP THRM BARR Q1P17HV3045 and Q1P17HV3184) as follows. 4.23.3.1 Uncap and attach a hose which has been tested to 150 psig to CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161 (1" valve) (Pen 46 - 121' PPR). 4.23.3.2 Uncap RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173 (3/4" valve) (Pen 43 - 121' PPR). Do not attach hose yet. 4.23.3.3 Verify closed CCW FROM RCP THRM BARR Q1P17HV3045. NOTE"Cracking open" in the following step is defined as open sufficient to permit flow. This may be achieved by "feel" as the valve comes off the closed seat, as well as possible flow noise. (AI 2008205965) CAUTIONTo minimize flow perturbations in the CCW return header when opening CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161, slowly open the valve and only as much as necessary to slowly fill the hose. 4.23.3.4 Route hose to a suitable container AND fill hose with CCW by slowly cracking open CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161. 4.23.3.5 WHEN hose is filled with CCW, THEN close CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161. 4.23.3.6 Attach hose to RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173. 4.23.3.7 Open CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161. 4.23.3.8 Open RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 31 of 170 NOTEThis flow path requires backflow through a Kerotest stop-check valve. Monitor for evidence of the Kerotest valve sticking closed. 4.23.3.9 Monitor for evidence of proper pressure equalization (momentary flow noise or pipe/valve vibration, etc.). 4.23.3.10 WHEN pressure has equalized, THEN close RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173. 4.23.3.11 Close CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161. 4.23.3.12 Attempt opening CCW FROM RCP THRM BARR Q1P17HV3045 per steps 4.25.1and/or 4.25.2. 4.23.3.13 WHEN pressure equalization is complete, THEN remove hose, using a suitable container and absorbent material or other appropriate means to contain residual CCW pressure and fluid in the hose. 4.23.3.14 Verify closed and cap RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173. 4.23.3.15 Verify closed and cap CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161. 4.23.3.16 Collect and dispose of waste CCW in accordance with FNP-0-SHP-30, WASTE DISPOSAL. 4.23.4IF unable to open CCW FROM RCP THRM BARR Q1P17HV3045 from the handwheel or the MCB, THEN write a CR to have the condition investigated. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 32 of 170 NOTEReference Tech Spec 3.6.3 and TRM 13.6.2 for Containment Isolation Valves. 4.24Alternate Method of Opening CCW FROM RCP THRM BARR Q1P17HV3184 with High P Suspected (OR 2-99-603) 4.24.1IF MCB handswitch does not open CCW FROM RCP THRM BARR (Q1P17HV3184, AND high P is the suspected cause, THEN wait approximately 10~15 minutes or as determined by the Shift Supervisor and re-attempt to open the valve. This may be repeated for up to 3 hours to allow the pressure to equalize. NOTEA containment entry will need to be done to use the manual handwheel on Q1P17HV3184. CAUTIONDo not use any mechanical leverage on CCW FROM RCP THRM BARR Q1P17HV3045 (Q1P17HV3184) handwheel. Damage to the pin which connects the handwheel to the valve stem may result. (OR 2-98-320) 4.24.2IF requested by the Shift Supervisor, THEN open CCW FROM RCP THRM BARR Q1P17HV3184 with the manual handwheel as follows: 4.24.2.1 Fail air to CCW FROM RCP THRM BARR Q1P17HV3184. 4.24.2.2 Open CCW FROM RCP THRM BARR Q1P17HV3184 with the manual handwheel. 4.24.2.3 Restore air to CCW FROM RCP THRM BARR Q1P17HV3184. 4.24.2.4 Return the handwheel for CCW FROM RCP THRM Q1P17HV3184 to the neutral position. CAUTIONDo not open or attempt to open CCW FROM RCP THRM BARR Q1P17HV3184 while CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161 or RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173 is open. 4.24.3IF requested by the Shift Supervisor, THEN equalize pressure around CCW FROM RCP THERMAL BARRIERS CHECK VALVE Q1P17V106 (downstream of CCW FROM RCP THRM BARR Q1P17HV3045 and Q1P17HV3184) as follows. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 33 of 170 4.24.3.1 Uncap and attach a hose which has been tested to 150 psig to CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161 (1" valve) (Pen 46 - 121' PPR). 4.24.3.2 Uncap RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173 (3/4" valve) (Pen 43 - 121' PPR). Do not attach hose yet. NOTEWhen verifying Q1P17HV3184 closed, Q1P17HV3045 will be required to be open. 4.24.3.3 Verify closed CCW FROM RCP THRM BARR Q1P17HV3184. NOTE"Cracking open" in the following step is defined as open sufficient to permit flow. This may be achieved by "feel" as the valve comes off the closed seat, as well as possible flow noise. (AI 2008205965) CAUTIONTo minimize flow perturbations in the CCW return header when opening CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161, slowly open the valve and only as much as necessary to slowly fill the hose. 4.24.3.4 Route hose to a suitable container AND fill hose with CCW by slowly cracking open CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161. 4.24.3.5 WHEN hose is filled with CCW, THEN close CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161. 4.24.3.6 Attach hose to RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173. 4.24.3.7 Open CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161. 4.24.3.8 Open RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173. NOTEThis flow path requires backflow through a Kerotest stop-check valve. Monitor for evidence of the Kerotest valve sticking closed. 4.24.3.9 Monitor for evidence of proper pressure equalization (momentary flow noise or pipe/valve vibration, etc.). 4.24.3.10 WHEN pressure has equalized, THEN close RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173. 4.24.3.11 Close CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161. 4.24.3.12 Attempt opening CCW FROM RCP THRM BARR Q1P17HV3184 per Steps 4.25.1 and/or 4.25.2. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 34 of 170 4.24.3.13 WHEN pressure equalization is complete, THEN remove hose, using a suitable container and absorbent material or other appropriate means to contain residual CCW pressure and fluid in the hose. 4.24.3.14 Verify closed and cap RCP'S THRM BARR CCW RTN TEST CONN Q1P17V173. 4.24.3.15 Verify closed and cap CCW DISCH EXC LTDN & RCDT HXS DRN Q1P17V161. 4.24.3.16 Collect AND dispose of waste CCW in accordance with FNP-0-SHP-30, WASTE DISPOSAL. 4.24.4IF unable to open CCW FROM RCP THRM BARR Q1P17HV3184 from the handwheel OR the MCB, THEN write a CR to have the condition investigated. NOTESReference Tech Spec 3.6.3 and TRM 13.6.2 for Containment Isolation Valves. Thermal expansion of water in the thermal barrier may cause an excessive pressure in the return line requiring the high pressure isolation function of HV3184 to be defeated. 4.25Restoring CCW Flow to the RCP Thermal Barriers after an Extended (> 4 hour) Loss: 4.25.1 Verify closed CCW FROM THERMAL BARR Q1P17HV3045. 4.25.2 Verify open CCW FROM THERMAL BARR Q1P17HV3184. If valve cannot be opened from the MCB, then use Step 4.25.3 or 4.25.4 to open. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 35 of 170 CAUTIONDo not use any mechanical leverage on CCW FROM RCP THRM BARR Q1P17HV3184 handwheel. Damage to the pin which connects the handwheel to the valve stem may result. (OR 2-98-320) 4.25.3IF requested by the Shift Supervisor, THEN have I&C defeat the high pressure isolation function of CCW FROM RCP THRM BARR Q1P17HV3184. NOTECCW FROM RCP THRM BARR Q1P17HV3184 should open when the lead is lifted in the following step. 4.25.3.1 In termination cabinet Q1H25L031B lift lead C-2 (red wire) from 1TB1-25. (ref. D177855) 4.25.3.2 Verify open CCW FROM RCP THRM BARR Q1P17HV3184. IF open, THEN GO TO Step 4.25.5. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 36 of 170 4.25.4IF requested by the Shift Supervisor, THEN open CCW FROM RCP THRM BARR Q1P17HV3184 with the manual handwheel as follows: 4.25.4.1 Fail air to CCW FROM RCP THRM BARR Q1P17HV3184. 4.25.4.2 Open CCW FROM RCP THRM BARR Q1P17HV3184 with the manual handwheel. 4.25.4.3 Restore air to CCW FROM RCP THRM BARR Q1P17HV3184. 4.25.4.4 Return the handwheel for CCW FROM RCP THRM Q1P17HV3184 to the neutral position. NOTERCP Seal Parameters and R-17 A/B should be monitored during the following steps. 4.25.5 Fail air to CCW FROM RCP THRM BARR Q1P17HV3045. NOTE"Crack open" in the following step is defined as open sufficient to permit flow. This may be achieved by "feel" as the valve comes off the closed seat, as well as possible flow noise. The concern is the CCW is at ambient conditions, which may be elevated much higher than normal and any rapid changes may introduce a water hammer in the system causing potential damage. (AI 2008205965) 4.25.6To initiate a slow cool down of the thermal barrier, crack open CCW FROM RCP THRM BARR Q1P17HV3045 with manual handwheel until flow can be heard. If desired, flow can be monitored at Q1P17FISH3045 (Rm 218, BTRS Chiller Room). 4.25.7After about 30 minutes, slowly open CCW FROM RCP THRM BARR Q1P17HV3045 to full open position. 4.25.8 Restore air to CCW FROM RCP THRM BARR Q1P17HV3045. 4.25.9 Return the handwheel for CCW FROM RCP THRM Q1P17HV3045 to the neutral position. 4.25.10IF leads lifted per Step 4.25.3, THEN perform the following: 4.25.10.1 In termination cabinet Q1H25L031B, have I&C verify PS-1 (N1P17PSH3184A-B), PS-2 (N1P17PSH3184B-B) and PS-3 (N1P17PSH3184C-C) contacts are open by checking continuity. Measure from lifted wire C2 to 1TB1-24. (ref. D177855) 4.25.10.2 Re-land lead C-2 (red wire) at 1TB1-25. UNIT 1 Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEM Page Number 37 of 170

5.0 REFERENCES

5.1CCW pump technical manual U-169494A 5.2DBA calculation SM-ES-89-1499-007, Service Water System Flow Balance Evaluation 5.3FSAR-Chapter 9, section 9.2 5.4D-175002 Sheets 1 & 2 Component Cooling Water System 5.5D-175003, Sheet 1, Service Water System 5.6D-175023, Process Flow Diagram Component Cooling Water System 5.7U-176880, Assembly Drawing For FV-3009B 5.8U-732963, Assembly Drawing For FV-3009A/3009C 5.9U-176892 Outline drawing of butterfly valve w/piston, actuator, and access 5.10B91-1-7431, Deletion of Lo-Lo Surge Tank Level Pump Trip 5.11RER 1080944901 5.12Westinghouse Letter BPC-88-549 on page 47 of U277513 5.13DCP SNC 66497 6.0 Records QA Record (X)Non-QARecord (X) RecordGeneratedRetentionTimeR-Type X FNP-1-SOP-23.0Life of Plant HH6.051 UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 38 of 170

APPENDIX 23.0A CHEMICAL MIXING

Performed by: Date

Verified by: Date

Approved by: Date

This appendix consists of 3 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 39 of 170 APPENDIX 23.0A CHEMICAL MIXING (Page 1 of 3) CAUTIONOnly one chemical mixing isolation may be open at any time. Simultaneous opening of chemical mixing isolations in opposite trains will result in a loss of two independent CCW loops due to cross-connecting trains through the mixing valves. 1.0 PURPOSE To provide guidance for mixing chemicals in the CCW system. 2.0 INITIAL CONDITIONS 2.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ Initial 2.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 3.0 PRECAUTION AND LIMITATIONS 3.1Only one chemical mixing isolation may be open at any time. Simultaneous opening of chemical mixing isolations in opposite trains will result in a loss of two independent CCW loops due to cross-connecting trains through the mixing valves. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 40 of 170 APPENDIX 23.0A CHEMICAL MIXING (Page 2 of 3) 4.0 INSTRUCTIONS 4.1 Perform the following: 4.1.1 Determine the train that is to be chemically mixed; consult with the Shift Chemist. _____ A Train "B" Train 4.1.2 Verify closed CCW SRG TK CHEM ADD, Q1P17V114. _____ 4.1.3 Check the running CCW PUMP. _____ 1A CCW Pump 1B CCW Pump 1C CCW Pump 4.2IF B CCW pump is the running pump, THEN check that B CCW pump is aligned to the proper train designated in Step 4.1.1. _____ 4.3IF 1A CCW pump is the running pump THEN perform the following: 4.3.1 Verify that 1B CCW PUMP CHEM MIXING ISO, Q1P17V278B is closed. _____ 4.3.2 Verify that 1C CCW PUMP CHEM MIXING ISO, Q1P17V278C is closed. _____ 4.3.3 Open 1A CCW PUMP CHEM MIXING ISO, Q1P17V278A. _____ NOTEMinimum of 72 hours required to ensure adequate mixing in the CCW system. 4.3.4 Inform the Shift Chemist of the start time for chemical mixing. _____ 4.3.4.1 Record start time: 4.3.5WHEN either of the following criteria satisfied, THEN close 1A CCW PUMP CHEM MIXING ISO, Q1P17V278A: Shift Chemist has obtained the required sample. Minimum required 72 hours mixing time has lapsed AND chemical mixing no longer required. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 41 of 170 APPENDIX 23.0A CHEMICAL MIXING (Page 3 of 3) 4.4IF 1B CCW pump is the running pump THEN perform the following: 4.4.1 Verify that 1A CCW PUMP CHEM MIXING ISO, Q1P17V278A is closed. _____ 4.4.2 Verify that 1C CCW PUMP CHEM MIXING ISO, Q1P17V278C is closed. _____ 4.4.3 Open 1B CCW PUMP CHEM MIXING ISO, Q1P17V278B. _____ NOTEMinimum of 72 hours required to ensure adequate mixing in the CCW system. 4.4.4 Inform the Shift Chemist of the start time for chemical mixing. _____ 4.4.4.1 Record start time: 4.4.5WHEN either of the following criteria satisfied, THEN close 1B CCW PUMP CHEM MIXING ISO, Q1P17V278B: Shift Chemist has obtained the required sample. Minimum required 72 hours mixing time has lapsed AND chemical mixing no longer required. 4.5IF 1C CCW pump is the running pump THEN perform the following: 4.5.1 Verify that 1A CCW PUMP CHEM MIXING ISO, Q1P17V278A is closed. _____ 4.5.2 Verify that 1B CCW PUMP CHEM MIXING ISO, Q1P17V278B is closed. _____ 4.5.3 Open 1C CCW PUMP CHEM MIXING ISO, Q1P17V278C. _____ NOTEMinimum of 72 hours required to ensure adequate mixing in the CCW system. 4.5.4 Inform the Shift Chemist of the start time for chemical mixing. _____ 4.5.4.1 Record start time: 4.5.5WHEN either of the following criteria satisfied, THEN close 1C CCW PUMP CHEM MIXING ISO, Q1P17V278C: Shift Chemist has obtained the required sample. Minimum required 72 hours mixing time has lapsed AND chemical mixing no longer required. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 42 of 170 APPENDIX 23.0B SHIFTING ON SERVICE TRAIN FROM TRAIN A TO TRAIN B Performed by Date Verified By: Date Reviewed by: Date This appendix consists of 17 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 43 of 170 Appendix 23.0B (Page 1 of 17) 1.0 PURPOSE 1.1Provides guidance for shifting the on service train from A Train to B Train. 1.2Provides guidance for a separate check of 1B CCW pump alignment to B Train. 2.0 PRECAUTIONS AND LIMITATIONS 2.1Shifting train alignment for 1B CCW pump and HX also shifts the miscellaneous header. 2.2The operation of two pumps through one HX is not allowed. 2.3CCW temperature should be maintained as stable as possible due to the effects on reactivity due to changes in letdown temperature. Also, changing CCW temperature could affect RCP oil levels which could cause level annunciators to come in. (AI 2005201097) 2.4Minimize operating time with CCW flow > 6000 gpm. 2.5It is desirable, if time permits, to allow the oncoming CCW temperature to increase to where it is equal or higher than the off-going train. This will minimize the reactivity effect and impact on RCP oil levels.(AI2008200245) 2.6CCW TO 1B RHR HX Q1P17MOV3185B should remain open, while swapping the on-service train, to prevent system pressure spike when CCW trains are cross-connected during swap. (1-95-063) 2.7In order for 1B CCW pump to be started by the ESS or LOSP sequencers; the train to which it is aligned must have the train dedicated pump supply breaker racked out. 2.8When the 4160VC disconnects are operated, it is important to visually ensure(with a flashlight) that all three "Stabs" have either opened up or closed successfully due to the disconnect operation. Any operations involving manipulation of the 4kV disconnect switches associated shall include visual confirmation of the following: 2.8.1The main contacts are in the required state, open or closed. (One contact per phase.) Refer to figure 1 and 2. 2.8.2 The arcing contacts are in the required state, open or closed. (One contact per phase.) Refer to figure 1 and 2. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 44 of 170 Appendix 23.0B (Page 2 of 17) 3.0 INITIAL CONDITIONS 3.1The version of this appendix has been verified to be the current version. (OR 1-98-498 _____ Initial 3.2The appendix has been verified to be for the correct unit for the task. (OR 1-98-498) _____ Initial 3.3IF only performing a line up check of 1B CCW pump to B Train, THEN perform Section 9.0 of this appendix and the remaining portion of the appendix is N/A. _____ Initial 3.41C CCW heat exchanger is in service prior to shifting the on service train from A Train to B Train. 3.4.1IF the 1C CCW heat exchanger is in service, THEN check the following: Check open 1C CCW HX CCW OUTLET ISO, Q1P17V008C. _____ Initial Check closed 1B CCW HX CCW OUTLET ISO, Q1P17V008B _____ Initial Check proper flow on FI 3043CA, HX 1C CCW FLOW _____ Initial 3.4.2IF the 1C CCW heat exchanger is NOT in service, THEN place 1C CCW heat exchanger in service per Section 4.4 of FNP-1-SOP-23.0. _____ Initial 3.51C CCW pump is in service prior to shifting the on service train from A Train to B Train. _____ Initial IF required to place 1C CCW pump in service, THEN perform procedure Section 4.7 _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 45 of 170 Appendix 23.0B (Page 3 of 17) 4.0 1A CCW PUMP AND HEAT EXCHANGER ALIGNMENT 4.1 Verify SW FROM 1A CCW HX Q1P16FV3009A handswitch in MOD. _____ Initial 4.2 Throttle 1A CCW HX DISCH FCV HIC 3009A as necessary to control CCW temperature. _____ Initial 4.3 Verify the 1A CCW HX CCW OUTLET ISO, Q1P17V008A is open. _____ Initial CAUTIONCCW TO 1B RHR HX Q1P17MOV3185B should remain open, while swapping the on-service train, to prevent system pressure spike when CCW trains are cross-connected during swap. (1-95-063) 4.4 Verify open CCW TO 1B RHR HX Q1P17MOV3185B. _____ Initial NOTEMinimize operating time with CCW flow > 6000 gpm. 4.5 Start the 1A CCW PUMP if not already running in the off-service train. _____ Initial 4.6 Verify proper flow on FI 3043AA, 1A CCW HX FLOW. _____ Initial 4.7 Monitor CCW HX outlet temperature to ensure CCW temperature is maintained less than 105°F (120°F IF aligned for plant cooldown). _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 46 of 170 Appendix 23.0B (Page 4 of 17) NOTESCCW temperature should be maintained stable as possible to minimize effects on the following: Reactivity changes due to changes in letdown temperature RCP oil levels. 4.8IF time permits, THEN allow oncoming CCW temperature to increase to a value equal to or slightly higher than the off going train by performing the following: 4.8.1 Monitor the following CCW FROM CCW HX TEMP indications: TI-3042A TI-3042C 4.8.2 Throttle 1A CCW HX DISCH FCV HIC 3009A as necessary to increase oncoming CCW temperature. _____ Initial 4.8.3IF desired, THEN shift on service SFP cooling loops per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. _____ Initial 4.9IF the actual valve alignment for the train swap is delayed, THEN CCW TO 1B RHR HX Q1P17MOV3185B may be closed. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 47 of 170 Appendix 23.0B (Page 5 of 17) CAUTIONS Minimize the time required to perform this section of this procedure since Trains A and B will be hydraulically cross connected during the performance of these steps. CCW temperature should be maintained stable as possible to minimize effects on the following: Reactivity changes due to changes in letdown temperature RCP oil levels. 5.0 COMPONENT COOLING WATER ALIGNMENT 5.1WHEN ready to perform valve manipulation for the train swap, THEN verify CCW TO 1B RHR HX Q1P17MOV3185B OPEN. _____ Initial 5.2 Notify control room personnel to perform the following during CCW valve alignment: 5.2.1 Monitor CCW surge tank levels closely. CCW Surge Tank LI-3027AA CCW Surge Tank LI-3027BA 5.2.2Be ready to make up to the surge tank if required. _____ Initial 5.2.3 Monitor the following CCW flow indications: FI3043AA HX 1A CCW FLOW FI3043CA HX 1C CCW FLOW 5.2.4IF flow is lost, THEN immediately notify personnel performing the procedure to take corrective action. _____ Initial 5.3 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110C. _____ Initial 5.4 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 48 of 170 Appendix 23.0B (Page 6 of 17) 5.5 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003A. _____ Initial 5.6 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003B. _____ Initial 5.7 Open CCW SUPPLY HDR XCONN, Q1P17V009A. _____ Initial 5.8 Open CCW SUPPLY HDR XCONN, Q1P17V009B. _____ Initial 5.9 Close CCW SUPPLY HDR XCONN, Q1P17V009C. _____ Initial 5.10 Close CCW SUPPLY HDR XCONN, Q1P17V009D. _____ Initial 5.11 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003C. _____ Initial 5.12 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003D. _____ Initial 5.13 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110D. _____ Initial 5.14 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110E. _____ Initial 5.15IF desired THEN CCW TO 1B RHR HX Q1P17MOV3185B may be closed. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 49 of 170 Appendix 23.0B (Page 7 of 17) 6.0 SERVICE WATER ALIGNMENT 6.1 Close 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002D. _____ Initial 6.2 Close 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002C. _____ Initial 6.3 Close 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008E. _____ Initial 6.4 Close 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008D. _____ Initial 6.5 Open 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002B. _____ Initial 6.6 Open 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002A. _____ Initial 6.7 Open 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008C. _____ Initial 6.8 Open 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 50 of 170 Appendix 23.0B (Page 8 of 17) NOTES The miscellaneous header is now aligned to B Train. The off service train is normally in operation in modes 1-4 supplying the operating charging pump, with the non-operating SFP HX flowpath aligned and CCW to the RHR HX isolated. (Reference RER 1080944901) 6.9IF it is desired to secure the 1C CCW pump, THEN check that conditions exist to allow securing the 1C CCW pump: 6.9.1 Check for the following conditions: Spent fuel pool cooling is aligned to B Train. _____ Initial 1A RHR pump is NOT running. _____ Initial 1A charging pump or 1B charging pump (If aligned to A Train) are NOT running. _____ Initial No other reasons exist to maintain 1C CCW pump running. _____ Initial 6.9.2IF above conditions are NOT met, THEN notify the Shift Supervisor that 1C CCW pump is required for plant operations. _____ Initial 6.9.3IF these conditions are satisfied, THEN the 1C CCW Pump may be stopped. _____ Initial 6.9.4IF the 1C CCW pump is stopped, THEN open CCW TO 1A RHR HX Q1P17MOV3185A. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 51 of 170 Appendix 23.0B (Page 9 of 17) 7.0 ELECTRICAL ALIGNMENT 7.1 Perform the following for breaker Q1R15BKRDF05: 7.1.1 Rack-out breaker Q1R15BKRDF05. _____ Initial 7.1.2 Turn key # RE-14265 in the mechanical interlock on circuit breaker Q1R15BKRDF05. _____ Initial 7.1.3 Remove key # RE-14265. _____ Initial 7.2 Perform the following for 1B CCW pump 4KV disconnect switch 1A (Q1R18A004A-A): 7.2.1 Insert key # RE-14265 into the mechanical interlock on 1B CCW pump 4KV disconnect switch 1A (Q1R18A004A-A). _____ Initial 7.2.2 Turn key # RE-14265. Key # RE-14265 is now held in place. _____ Initial 7.2.3 Open disconnect switch Q1R18A004A-A. _____ Initial 7.2.4 Check the position indicator reads SW OPEN. _____ Initial 7.2.5With the aid of a flashlight, perform the following: 7.2.5.1 Check that a visible air gap exists between the main contacts on all three phases. _____ Initial 7.2.5.2 Check that a visible air gap exists between the arcing contacts on all three phases. _____ Initial 7.2.6 Turn key # RE-14224 in its mechanical interlock. _____ Initial 7.2.7 Remove key # RE-14224. 1A disconnect switch is now locked in the open position. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 52 of 170 Appendix 23.0B (Page 10 of 17) 7.3 Perform the following for 1B CCW pump 4KV disconnect switch 1A (Q1R18A004B-B) 7.3.1 Insert key # RE-14224 into its mechanical interlock on 1B CCW pump 4KV disconnect switch 1B (Q1R18A004B-B). _____ Initial 7.3.2 Turn key # RE-14224. Key # RE-14224 is now held in place. _____ Initial 7.3.3 Close disconnect switch, Q1R18A004B-B). _____ Initial 7.3.4 Check the position indicator reads SW CLOSED. _____ Initial 7.3.5With the aid of a flashlight, perform the following: 7.3.5.1 Check that NO air gap exists for the main contacts on all three phases. (Contacts closed.) _____ Initial 7.3.5.2 Check that NO air gap exists for the arcing contacts on all three phases. (Contacts closed.) _____ Initial 7.3.6 Turn key # RE-14291 in its mechanical interlock. _____ Initial 7.3.7 Remove key # RE-14291. 1B disconnect switch is now locked in the closed position. _____ Initial CAUTIONBreaker Q1R15BKRDG05 has alternate DC control power supplied through fuses in C-HSDP when 1B CCW PUMP LOCAL-REMOTE switch on C-HSDP is in LOCAL. 7.4 Verify LOCAL-REMOTE switch 1B CCW PUMP B TRN Q1P17P001B on C-HSDP in REMOTE. _____ Initial 7.5 Insert key # RE-14291 into its mechanical interlock on circuit breaker Q1R15BKRDG05. _____ Initial 7.6 Turn key# RE-14291. Key # RE-14291 is now held in place. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 53 of 170 Appendix 23.0B (Page 11 of 17) 7.7 Rack circuit breaker Q1R15BKRDG05 to the connected position. _____ Initial 7.8 Close DC control power switch for Q1R15BKRDG05 and verify breaker spring charges. _____ Initial 7.91B CCW Hx and pump are now aligned to B Train, IF desired, THEN place 1B CCW pump and heat exchanger in service. _____ Initial 7.10 Notify Shift Chemist CCW on service train has been shifted from Train A to Train B. _____ Initial NOTEThe next step preferred action is to place the 1B CCW Pump on-service. If extenuating circumstances preclude placing the pump on-service, then bumping the pump is allowed with the shift supervisor's permission. CAUTIONCCW temperature should be maintained stable as possible to minimize effects on the following: Reactivity changes due to changes in letdown temperature RCP oil levels 8.0 1B CCW PUMP OPERABILITY CHECK 8.1 Perform one of the following steps. 8.1.1 Place 1B CCW Pump in service per Section 4.7 Shifting CCW Pumps on the On-Service Train. _____ Initial 8.1.2 Bump 1B CCW Pump as follows: 8.1.2.1 Open CCW TO 1B RHR HX Q1P17MOV3185B. _____ Initial 8.1.2.2 Bump the 1B CCW pump. _____ Initial 8.1.2.3 Close CCW TO 1B RHR HX Q1P17MOV3185B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 54 of 170 Appendix 23.0B (Page 12 of 17) NOTEThis section does not apply unless the only intent is to check the alignment of the 1B CCW pump to the B train as directed by initial condition 3.3. 9.0 1B CCW PUMP B TRAIN ALIGNMENT CHECK 9.1IF any component is not in the expected position, THEN report it to the Shift Supervisor immediately. 9.2 Check breaker Q1R15BKRDF05 is racked out. _____ Initial 9.3 Check the mechanical interlock key is removed from breaker Q1R15BKRDF05. _____ Initial 9.4 Check 1B CCW pump 4KV disconnect switch 1A, Q1R18A004A-A, is locked open with mechanical interlock key #RE-14265 held in place. _____ Initial 9.4.1 Check the position indicator (Q1R18A004A-A) reads SW OPEN. _____ Initial 9.4.2With the aid of a flashlight, perform the following: 9.4.2.1 Check that a visible air gap exists between the main contacts on all three phases. _____ Initial 9.4.2.2 Check that a visible air gap exists between the arcing contacts on all three phases. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 55 of 170 Appendix 23.0B (Page 13 of 17) 9.5 Check that 1B CCW pump 4KV disconnect switch 1B, Q1R18A004B-B is locked closed with mechanical interlock key #RE-14224 held in place. _____ Initial 9.5.1 Check Disconnect switch Q1R18A004B-B reads "SW CLOSED." _____ Initial 9.5.2With the aid of a flashlight, perform the following: 9.5.2.1 Check that NO air gap exists for the main contacts on all three phases. (Contacts closed.) _____ Initial 9.5.2.2 Check that NO air gap exists for the arcing contacts on all three phases. (Contacts closed.) _____ Initial 9.6 Check that 1B CCW breaker Q1R15BKRDG05 is racked to the connect position with mechanical interlock key #RE-14291 held in place. _____ Initial 9.7 Check that breaker Q1R15BKRDG05 is charged. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 56 of 170 Appendix 23.0B (Page 14 of 17) 9.8 Check the status of the following CCW valves. CCW PUMPS SUCT HDR XCONN, Q1P17V110C--Open _____ Initial CCW PUMPS SUCT HDR XCONN, Q1P17V110B--Open _____ Initial CCW PUMPS DISCH HDR XCONN, Q1P17V003A--Open _____ Initial CCW PUMPS DISCH HDR XCONN, Q1P17V003B--Open _____ Initial CCW SUPPLY HDR XCONN, Q1P17V009A-Open _____ Initial CCW SUPPLY HDR XCONN, Q1P17V009B--Open _____ Initial CCW SUPPLY HDR XCONN, Q1P17V009C--Closed _____ Initial CCW SUPPLY HDR XCONN, Q1P17V009D-Closed _____ Initial CCW PUMPS DISCH HDR XCONN, Q1P17V003C--Closed _____ Initial CCW PUMPS DISCH HDR XCONN, Q1P17V003D--Closed _____ Initial CCW PUMPS SUCT HDR XCONN, Q1P17V110D--Closed _____ Initial CCW PUMPS SUCT HDR XCONN, Q1P17V110E--Closed _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 57 of 170 Appendix 23.0B (Page 15 of 17) 9.9 Check the status of the following SW valves: 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002D--Closed. _____ Initial 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002C--Closed. _____ Initial 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008E--Closed. _____ Initial 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008D--Closed. _____ Initial 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002B--Open _____ Initial 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002A--Open _____ Initial 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008C--Open _____ Initial 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008B-Open _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 58 of 170 Appendix 23..0B Page 6 of 17 FIGURE 1 Typical 4kV Disconnect shown in OPEN condition. Correct Contact Configuration Two Phases shown. Main Contact Arcing Contact Main Contact Arcing Contact UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 59 of 170 Appendix 23.0B Page 17 of 17 FIGURE 2 Typical 4kV Disconnect shown in OPEN condition. Incorrect Contact Configuration Two Phases shown. Main contacts open but arcing contact on right is closed (no air gap) Arcing Contact Arcing Contact Main Contact Main Contact UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 60 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM TRAIN B TO TRAIN A Performed by Date Verified By: Date Reviewed by: Date This appendix consists 16 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 61 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 1 of 16) 1.0 PURPOSE 1.1Provides guidance for shifting the on service train from B train to A train. 1.2Provides guidance for a separate check of 1B CCW pump alignment to A train. 2.0 PRECAUTIONS AND LIMITATIONS 2.1Shifting train alignment for 1B CCW pump and HX also shifts the miscellaneous header. 2.2The operation of two pumps through one HX is not allowed. 2.3CCW temperature should be maintained as stable as possible due to the effects on reactivity due to changes in letdown temperature. Also, changing CCW temperature could affect RCP oil levels which could cause level annunciators to come in. (AI 2005201097) 2.4Minimize operating time with CCW flow > 6000 gpm. 2.5It is desirable, if time permits, to allow the oncoming CCW temperature to increase to where it is equal or higher than the off-going train. This will minimize the reactivity effect and impact on RCP oil levels. (AI2008200245) 2.6CCW TO 1A RHR HX Q1P17MOV3185A should remain open, while swapping the on-service train, to prevent system pressure spike when CCW trains are cross-connected during swap. (1-95-063) 2.7In order for 1B CCW pump to be started by the ESS or LOSP sequencers; the train to which it is aligned must have the train dedicated pump supply breaker racked out. 2.8Any operations involving manipulation of the 4kV disconnect switches associated shall include visual confirmation of the following: 2.8.1The main contacts are in the required state, open or closed. (One contact per phase.) Refer to figure 1 and 2. 2.8.2The arcing contacts are in the required state, open or closed. (One contact per phase.) Refer to figure 1 and 2. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 62 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 2 of 16) 3.0 INITIAL CONDITIONS 3.1The version of this appendix has been verified to be the current version. (OR 1-98-498) _____ Initial 3.2The appendix has been verified to be for the correct unit for the task. (OR 1-98-498) _____ Initial 3.3IF only performing a line up check of 1B CCW pump to A train, THEN perform Section 9.0 of the appendix and the remaining portion of the appendix is N/A. _____ Initial 3.41A CCW heat exchanger is in service prior to shifting the on service train from "B" Train to A Train. 3.4.1IF the 1A CCW heat exchanger is in service, THEN check the following: Check open 1A CCW HX CCW OUTLET ISO, Q1P17V008A. _____ Initial Check closed 1B CCW HX CCW OUTLET ISO, Q1P17V008B _____ Initial Check proper flow on FI 3043AA, HX 1ACCW FLOW. _____ Initial 3.4.2IF the 1A CCW heat exchanger is NOT in service, THEN place 1A CCW heat exchanger in service per Section 4.6 of FNP-1-SOP-23.0. _____ Initial 3.51A CCW pump is in service prior to shifting the on service train from "B" Train to A Train. _____ Initial 3.5.1IF required to place 1A CCW pump in service, THEN perform procedure Section 4.7. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 63 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 3 of 16) 4.0 1C CCW PUMP AND HEAT EXCHANGER ALIGNMENT 4.1 Verify SW FROM 1C CCW HX Q1P16FV3009C handswitch in MOD. _____ Initial 4.2 Throttle 1C CCW HX DISCH FCV HIC 3009C as necessary to control CCW temperature. _____ Initial 4.3 Verify the 1C CCW HX CCW OUTLET ISO, Q1P17V008C is open. _____ Initial CAUTIONCCW TO 1A RHR HX Q1P17MOV3185A should remain open, while swapping the on-service train, to prevent system pressure spike when CCW trains are cross-connected during swap. (1-95-063) 4.4 Verify open CCW TO 1A RHR HX Q1P17MOV3185A. _____ Initial NOTEMinimize operating time with CCW flow > 6000 gpm. 4.5 Start the 1C CCW PUMP if not already running in the off-service train. _____ Initial 4.6 Verify proper flow on FI 3043CA, 1C CCW HX FLOW. _____ Initial 4.7 Monitor CCW HX outlet temperature to ensure CCW temperature is maintained less than 105°F (120°F IF aligned for plant cooldown). _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 64 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 4 of 16) NOTEThe following actions will minimize the reactivity effect and impact on RCP oil levels. 4.8IF time permits, THEN allow oncoming CCW temperature to increase to a value equal to or slightly higher than the off going train by performing the following: _____ Initial 4.8.1 Monitor the following CCW FROM CCW HX TEMP indications: TI-3042A TI-3042C 4.8.2 Throttle 1C CCW HX DISCH FCV HIC 3009C as necessary to increase oncoming CCW temperature. _____ Initial 4.8.3IF desired, THEN shift on service SFP cooling loops per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. _____ Initial 4.9IF the actual valve alignment for the train swap is delayed, THEN CCW TO 1A RHR HX Q1P17MOV3185A may be closed. _____ Initial CAUTIONSMinimize the time required to perform this section of this procedure since Trains A and B will be hydraulically cross connected during the performance of these steps. CCW temperature should be maintained stable as possible to minimize effects on the following: Reactivity changes due to changes in letdown temperature RCP oil levels. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 65 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 5 of 16) 5.0 COMPONENT COOLING WATER ALIGNMENT 5.1WHEN ready to perform valve manipulation for the train swap, THEN verify open CCW TO 1A RHR HX Q1P17MOV3185A. _____ Initial 5.2 Notify control room personnel to perform the following during CCW valve alignment, as required: _____ Initial 5.2.1 Monitor CCW surge tank levels closely. CCW Surge Tank LI-3027AA CCW Surge Tank LI-3027BA 5.2.2 Be ready to make up to the surge tank if required. _____ Initial 5.2.3 Monitor the following CCW flow indications: FI3043AA HX 1A CCW FLOW FI3043CA HX 1C CCW FLOW 5.2.4IF flow is lost, THEN immediately notify personnel performing the procedure to take corrective action. _____ Initial 5.3 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110D. _____ _ Initial 5.4 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110E. _____ Initial 5.5 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003D. _____ Initial 5.6 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003C. _____ Initial 5.7 Open CCW SUPPLY HDR XCONN, Q1P17V009C. _____ _ Initial 5.8 Open CCW SUPPLY HDR XCONN, Q1P17V009D. _____ Initial 5.9 Close CCW SUPPLY HDR XCONN, Q1P17V009B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 66 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 6 of 16) 5.10 Close CCW SUPPLY HDR XCONN, Q1P17V009A. _____ Initial 5.11 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003A. _____ Initial 5.12 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003B. _____ Initial 5.13 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110B. _____ Initial 5.14 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110C. _____ Initial 5.15IF desired THEN close CCW TO 1A RHR HX Q1P17MOV3185A. _____ Initial 6.0 SERVICE WATER ALIGNMENT 6.1 Close 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002B. _____ Initial 6.2 Close 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002A. _____ Initial 6.3 Close 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008C. _____ Initial 6.4 Close 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008B. _____ Initial 6.5 Open 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002D. _____ Initial 6.6 Open 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002C. _____ Initial 6.7 Open 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008E. _____ Initial 6.8 Open 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008D. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 67 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 7 of 16) NOTES The miscellaneous header is now aligned to A Train. The off service train is normally in operation in modes 1-4 supplying the operating charging pump, with the non-operating SFP HX flowpath aligned and CCW to the RHR HX isolated. (Reference RER 1080944901) 6.9IF it is desired to secure the 1A CCW pump, THEN check that conditions exist to allow securing the 1A CCW pump. 6.9.1 Check for the following conditions: Spent fuel pool cooling is aligned to A Train. _____ Initial 1B RHR pump is NOT running. _____ Initial 1C charging pump or 1B charging pump (If aligned to B Train) are NOT running. _____ Initial No other reasons exist to maintain 1A CCW pump running. _____ Initial 6.9.2IF above conditions are NOT met, THEN notify the Shift Supervisor that 1A CCW pump is required for plant operations _____ Initial 6.9.3IF these conditions are satisfied, THEN the 1A CCW Pump may be stopped. _____ Initial 6.9.4IF the 1A CCW pump is stopped, THEN open CCW TO 1B RHR HX Q1P17MOV3185B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 68 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 8 of 16) 7.0 ELECTRICAL ALIGNMENT CAUTIONBreaker Q1R15BKRDG05 has alternate DC control power supplied through fuses in C-HSDP when 1B CCW PUMP LOCAL-REMOTE switch on C-HSDP is in LOCAL. 7.1 Verify LOCAL-REMOTE switch on C-HSDP for 1B CCW PUMP in REMOTE. _____ Initial 7.2 Perform the following for breaker Q1R15BKRDG05: 7.2.1 Rackout breaker Q1R15BKRDG05. _____ Initial 7.2.2 Turn key #RE-14291 in the mechanical interlock on circuit breaker Q1R15BKRDG05. _____ Initial 7.2.3 Remove key #RE-14291. _____ Initial 7.3 Perform the following for 1B CCW pump 4KV disconnect switch 1B (Q1R18A004B-B). 7.3.1 Insert key #RE-14291 into the mechanical interlock on 1B CCW pump 4KV disconnect switch 1B (Q1R18A004B-B). _____ Initial 7.3.2 Turn key #RE-14291. Key #RE-14291 is now held in place. _____ Initial 7.3.3 Open disconnect switch Q1R18A004B-B. _____ Initial 7.3.4 Check the position indicator reads SW OPEN. _____ Initial 7.3.5With the aid of a flashlight, perform the following: 7.3.5.1 Check that a visible air gap exists between the main contacts on all three phases. _____ Initial 7.3.5.2 Check that a visible air gap exists between the arcing contacts on all three phases. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 69 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 9 of 16) 7.3.6 Turn key #RE-14224 in its mechanical interlock on 1B disconnect switch. _____ Initial 7.3.7 Remove key #RE-14224. 1B disconnect switch is now locked in the open position. _____ Initial 7.4 Perform the following for 1B CCW pump 4 KV disconnect switch 1A (Q1R18A004A-A). 7.4.1 Insert key #RE-14224 into its mechanical interlock on 1B CCW pump 4 KV disconnect switch 1A (Q1R18A004A-A). _____ Initial 7.4.2 Turn key #RE-14224. Key E-14224 is held in place. _____ Initial 7.4.3 Close disconnect switch, Q1R18A004A-A. _____ Initial 7.4.4 Check the position indicator reads SW CLOSED. _____ Initial 7.4.5With the aid of a flashlight, perform the following: 7.4.5.1 Check that NO air gap exists for the main contacts on all three phases. (Contacts closed.) _____ Initial 7.4.5.2 Check that NO air gap exists for the arcing contacts on all three phases. (Contacts closed.) _____ Initial 7.4.6 Turn key #RE-14265 in its mechanical interlock. _____ Initial 7.4.7 Remove key #RE-14265. 1A disconnect switch is now locked in the closed position. _____ Initial 7.5 Insert key #RE-14265 into its mechanical interlock on circuit breaker Q1R15BKRDF05. _____ Initial 7.6 Turn key #RE-14265. Key #RE-14265 is now held in place. _____ Initial 7.7 Rack circuit breaker Q1R15BKRDF05 to the connected position. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 70 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 10 of 16) 7.8 Close DC control power switch for Q1R15BKRDF05 and verify breaker spring charges. _____ Initial 7.91B CCW HX and pump are now aligned to A Train, IF desired, THEN place 1B CCW pump and heat exchanger in service. _____ Initial 7.10 Notify Shift Chemist CCW on service train has been shifted from Train B to Train A. _____ Initial NOTEThe next step preferred action is to place the 1B CCW Pump on-service. If extenuating circumstances preclude placing the pump on-service, then bumping the pump is allowed with the shift supervisor's permission. CAUTIONSCCW temperature should be maintained stable as possible to minimize effects on: Reactivity changes due to changes in letdown temperature RCP oil levels 8.0 1B CCW PUMP OPERABILITY CHECK 8.1 Perform one of the following steps: 8.1.1 Place 1B CCW Pump in service per Section 4.7 Shifting CCW Pumps on the On-Service Train. _____ Initial 8.1.2 Bump 1B CCW Pump as follows: 8.1.2.1 Verify open CCW TO 1A RHR HX Q1P17MOV3185A. _____ Initial 8.1.2.2 Bump the 1B CCW pump. _____ Initial 8.1.2.3 Close CCW TO 1A RHR HX Q1P17MOV3185A. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 71 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 11 of 16) NOTEThis section does not apply unless the only intent is to check the alignment of the 1B CCW pump to the A train as directed by initial condition 3.3. 9.0 CHECK 1B CCW PUMP ALIGNMENT TO A TRAIN 9.1IF any component is not in the expected position, THEN report it to the Shift Supervisor immediately. _____ Initial 9.2 Check breaker Q1R15BKRDG05 is racked out. _____ Initial 9.3 Check the mechanical interlock key is removed from breaker Q1R15BKRDG05. _____ Initial 9.4 Check 1B CCW pump 4KV disconnect switch 1A, Q1R18A004B-B, is LOCKED OPEN with mechanical interlock key #RE-14291 held in place. _____ Initial 9.4.1 Check the position indicator Q1R18A004B-B reads SW OPEN. _____ Initial 9.4.2With the aid of a flashlight, perform the following: 9.4.2.1 Check that a visible air gap exists between the main contacts on all three phases. _____ Initial 9.4.2.2 Check that a visible air gap exists between the arcing contacts on all three phases. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 72 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 12 of 16) 9.5 Check 1B CCW pump 4KV disconnect switch 1A, Q1R18A004A-A is LOCKED CLOSED with mechanical interlock key #RE-14224 in place. _____ Initial 9.5.1 Check the position indicator Q1R18A004B-B reads SW CLOSED. _____ Initial 9.5.2With the aid of a flashlight, perform the following: 9.5.2.1 Check that NO air gap exists for the main contacts on all three phases. (Contacts closed.) _____ Initial 9.5.2.2 Check that NO air gap exists for the arcing contacts on all three phases. (Contacts closed.)_____ Initial 9.6 Check 1B CCW breaker Q1R15BKRDF05 is racked to the connect position with mechanical interlock key #RE-14265 held in place. _____ Initial 9.7 Check that breaker Q1R15BKRDF05 is charged. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 73 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 13 of 16) 9.8 Check the status of the following CCW valves. CCW PUMPS SUCT HDR XCONN, Q1P17V110D-Open _____ Initial CCW PUMPS SUCT HDR XCONN, Q1P17V110E--Open _____ Initial CCW PUMPS DISCH HDR XCONN, Q1P17V003D--Open _____ Initial CCW PUMPS DISCH HDR XCONN, Q1P17V003C--Open _____ Initial CCW PUMPS DISCH HDR XCONN, Q1P17V003C--Open _____ Initial CCW SUPPLY HDR XCONN, Q1P17V009C--Open _____ Initial CCW SUPPLY HDR XCONN, Q1P17V009D--Open _____ Initial CCW SUPPLY HDR XCONN, Q1P17V009B--Close _____ Initial CCW SUPPLY HDR XCONN, Q1P17V009A--Close _____ Initial CCW PUMPS DISCH HDR XCONN, Q1P17V003A--Close _____ Initial CCW PUMPS DISCH HDR XCONN, Q1P17V003B--Close _____ Initial CCW PUMPS SUCT HDR XCONN, Q1P17V110B--Close _____ Initial CCW PUMPS SUCT HDR XCONN, Q1P17V110C--Close _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 74 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN (Page 14 of 16) 9.9 Check the status of the following SW valves. 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002B--Close _____ Initial 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002A--Close _____ Initial 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008C--Close _____ Initial 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008B--Close _____ Initial 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002D--Open _____ Initial 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002C--Open _____ Initial 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008E--Open _____ Initial 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008D --Open _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 75 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN Page 15 of 16 FIGURE 1 Typical 4kV Disconnect shown in OPEN condition. Correct Contact Configuration Two Phases shown. Main Contact Arcing Contact Main Contact Arcing Contact UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 76 of 170 APPENDIX 23.0C SHIFTING ON SERVICE TRAIN FROM B TRAIN TO A TRAIN Page 16 of 16 FIGURE 2 Typical 4kV Disconnect shown in OPEN condition. Incorrect Contact Configuration Two Phases shown. Main contacts open but arcing contact on right is closed (no air gap) Arcing Contact Arcing Contact Main Contact Main Contact APPENDIX 23.0A CHEMICAL MIXING UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 77 of 170 APPENDIX 1 B TRAIN CCW SURGE TANK FEED AND BLEED

Performed by: Date

Verified by: Date

Reviewed by: Date

This appendix consists of 7 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 78 of 170 APPENDIX 1 B TRAIN CCW SURGE TANK FEED AND BLEED (Page 1 of 7) 1.0 PURPOSE This appendix provides guidance for the feed and bleed evolution of the Unit One B Train Component Cooling Water (CCW) System. 2.0 PRECAUTIONS AND LIMITATIONS 2.1Continuously monitor CCW Surge Tank level. IF CCW Surge Tank level can NOT be maintained between 35" to 48", THEN suspend feed and bleed activities. 2.2Frequently monitor Floor Drain Tank level during feed and bleed. 2.3Close CCW from 1A SFP HX vent, Q1P17V015A, immediately upon notification by Control Room or sounding of Plant Emergency Alarm. 2.4Only one chemical mixing isolation may be open at any time. Simultaneous opening of chemical mixing isolations in opposite trains will result in a loss of two independent CCW loops due to cross-connecting trains through the mixing valves. 2.5To extend the life of resin, temporary demineralizers should be isolated with water maintained in them when not in use. 2.6All components used for this connection are required to be pressure tested to 150 psig which provides assurance that the system can withstand CCW system pressure. All hoses are to have banded fittings. 2.7To preclude the risk of NPDES non-compliance, the discharge from the temporary demineralizer will be contained in drums or other suitable container until completion of Chemistry sample results. Once Chemistry has confirmed that the demin effluent is acceptable for release to the environment, discharge to the environment may take place. 3.0 INITIAL CONDITIONS 3.1Procedures Verifications (OR 1-98-498) 3.1.1The version of this procedure has been verified to be the current version. _____ Initial 3.1.2The procedure has been verified to be the correct unit for the task. _____ Initial 3.2Individuals have been briefed by the Shift Supervisor and are aware that unavailability time' will be accumulated for the duration of this appendix. An Admin. LCO has been generated. (LCO 3.7.7) _____ SS Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 79 of 170 APPENDIX 1 B TRAIN CCW SURGE TANK FEED AND BLEED (Page 2 of 7) 3.3A Train CCW is the on-service train. _____ Initial 3.4"B" Train CCW is operating supplying flow to 1A SFP HX. _____ Initial 3.5Connect a hose pressure tested to 150 psi from CCW to 1A SFP HX vent, Q1P17V015A to inlet throttle valve attached to temporary demineralizers. _____ Initial 3.6Direct communication is established between the Control Room and Temporary Demineralizer area (New Fuel area). _____ Initial 3.7Establish communication between control room and demin water to surge tank makeup valve. _____ Initial 3.8A Train RHR Pump, Charging Pump, Service Water Pump and Diesel Generators operable. _____ Initial 3.9Temporary demin liner aligned, and ready for processing, per Figure 1. _____ Initial 3.10Suitable container(s) available to receive the demin effluent. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 80 of 170 APPENDIX 1 B TRAIN CCW SURGE TANK FEED AND BLEED (Page 3 of 7) 4.0 INSTRUCTIONS 4.1 Notify Chemistry personnel CCW feed and bleed is commencing. _____ Initial CAUTIONOnly one chemical mixing isolation may be open at any time. Simultaneous opening of chemical mixing isolations in opposite trains will result in a loss of two independent CCW loops due to cross-connecting trains through the mixing valves. 4.2 Open the chemical mixing valve for the running B Train CCW pump as follows: 4.2.1 Verify CCW SRG TK CHEM ADD, Q1P17V114 CLOSED. _____ Initial 4.2.2 Check 1A CCW PUMP RUNNING. _____ Initial 4.2.3 Verify 1C CCW PUMP CHEM MIXING ISO,Q1P17V278C CLOSED. _____ Initial 4.2.4 Verify 1B CCW PUMP CHEM MIXING ISO,Q1P17V278B CLOSED. _____ Initial 4.2.5 Open 1A CCW PUMP CHEM MIXING ISO, Q1P17V278A. _____ Initial 4.2.6 Close CCW SRG TK DEMIN INLET ISO, N1P11V045. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 81 of 170 APPENDIX 1 B TRAIN CCW SURGE TANK FEED AND BLEED (Page 4 of 7) 4.3 Open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B. _____ Initial 4.4 Verify inlet and outlet valve attached to the temporary demineralizers CLOSED. _____ Initial 4.5 Open CCW from 1A SFP HX vent Q1P17V015A. _____ Initial CAUTIONSteps 4.6 and 4.7 should be performed simultaneously to maintain CCW Surge Tank between 35" to 48" while obtaining a feed and bleed flow rate of approximately 20 gpm. 4.6 Throttle CCW SRG TK DEMIN INLET ISO, N1P11V045 as required to provide makeup flow slightly greater than bleed flow so that level can be controlled by cycling makeup MOV at infrequent intervals. (minimizing valve cycles lessens the possibility of tripping overloads in supply breaker.) _____ Initial 4.7 Open outlet valve and throttle open inlet valve attached to the temporary demineralizer as required. _____ Initial NOTETo monitor demineralizer effluent place a sheet of white paper behind the effluent path for comparison to verify water is clear with no yellow tint. 4.8Frequently monitor the demineralizer effluent. Secure feed & bleed if yellow water is detected. _____ Initial 4.9WHEN the approximate amount of gallons have been fed and bled according to CHM instructions, THEN close the following valves: 4.9.1CCW from 1A SFP HX vent Q1P17V015A _____ Initial 4.9.2MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B _____ Initial 4.9.3Inlet valve attached to the temporary demineralizers _____ Initial 4.9.4Outlet valve attached to the temporary demineralizers _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 82 of 170 APPENDIX 1 B TRAIN CCW SURGE TANK FEED AND BLEED (Page 5 of 7) 4.10 Open CCW SRG TK DEMIN INLET ISO, N1P11V045. _____ Initial 4.11 Notify Chemistry personnel CCW feed and bleed evolution is secured. _____ Initial 4.12 Remove the temporary hose connection Q1P17V015A, CCW from 1A SFP HX vent. _____ Initial 4.13 Replace the cap downstream ofQ1P17V015A, CCW from 1A SFP HX vent. _____ Initial 4.14WHEN chemical mixing is no longer required, THEN close 1A CCW PUMP CHEM MIXING ISO, Q1P17V278A. ______ Initial 4.15 INDEPENDENTLY VERIFY the following valves are CLOSED: 4.15.1CCW from 1A SFP HX vent Q1P17V015A _____ Initial 4.15.2MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B _____ Initial 4.15.31A CCW PUMP CHEM MIXING ISO, Q1P17V278A _____ Initial 4.16 INDEPENDENTLY VERIFY that CCW SRG TK DEMIN INLET ISO, N1P11V045 is OPEN. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 83 of 170 APPENDIX 1 B TRAIN CCW SURGE TANK FEED AND BLEED (Page 6 of 7) 4.17 Attach label(s) to any container(s) containing the processed effluent. _____ 4.17.1The labels should include the following: Date / Time stamp from this appendix. Source of CCW processed. Date Chemistry sample requested. 4.18Request Chemistry perform sample analysis of the demin effluent stored in the temporary container(s). _____ 4.19WHEN Chemistry sample analysis has been obtained, THEN perform the following as applicable. 4.19.1IF the sample results are satisfactory for disposal, THEN pump the contents of the containers labeled per step 4.17 into the nearest sump for processing. _____ 4.19.2IF the sample results indicated further processing, THEN perform the following: 4.19.2.1 Contact Operations Supervision for guidance as to how to process the contents of the containers. _____ 4.19.2.2 Remove all labels attached per step 4.17. _____ 4.20 Label the containers to be processed as necessary to prevent inadvertent disposal. _____ UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 84 of 170 APPENDIX 1 B TRAIN CCW SURGE TANK FEED AND BLEED (Page 7 of 7) Figure 1 Temporary DemineralizerINOUT66666From CCW Source(a portable pump taking suction from containerized waste CCW)Approx. 8 ft. Section Red Rubber HoseApprox. 4 ft. Section Red Rubber HoseIn Line Johnson ScreenFlow Direction Shown on Sightglass with Arrow(REQUIRED)0000gpmFlow Rate Meter & Flow Totalizer(OPTIONAL)Flow Direction Stamped In Metal on Totalizer(OPTIONAL)Demin Effluent Discharge to Temporary ContainerNOTE:The in line Johnson Screen serves as an additional barrier to prevent putting resin into the floor drain system. The temporary demineralizer should not be placed in service without it. The flow indicator and totalizer are optional depending on the need to monitor flowrate and total gallons processed. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 85 of 170

APPENDIX 2 A TRAIN CCW SURGE TANK FEED AND BLEED

Performed by: Date

Verified by: Date

Reviewed by: Date

This appendix consists of 6 pages

UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 86 of 170 APPENDIX 2 A TRAIN CCW SURGE TANK FEED AND BLEED (Page 1 of 6) 1.0 PURPOSE This appendix provides guidance for the feed and bleed evolution of the Unit One A Train Component Cooling Water (CCW) System. 2.0 PRECAUTIONS AND LIMITATIONS 2.1Continuously monitor CCW Surge Tank level. IF CCW Surge Tank level can NOT be maintained between 35" to 48", THEN suspend feed and bleed activities. 2.2Frequently monitor Floor Drain Tank level during feed and bleed. 2.3Close 1B SFP HX CCW OUTLET LINE VT, Q1P17V015B, immediately upon notification by Control Room or sounding of Plant Emergency Alarm. 2.4Only one chemical mixing isolation may be open at any time. Simultaneous opening of chemical mixing isolations in opposite trains will result in a loss of two independent CCW loops due to cross-connecting trains through the mixing valves. 2.5To extend the life of resin, temporary demineralizers should be isolated with water maintained in them when not in use. 2.6All components used for this connection are required to be pressure tested to 150 psig which provides assurance that the system can withstand CCW system pressure. All hoses are to have banded fittings. 2.7To preclude the risk of NPDES non-compliance, the discharge from the temporary demineralizer will be contained in drums or other suitable container until completion of Chemistry sample results. Once Chemistry has confirmed that the demin effluent is acceptable for release to the environment, discharge to the environment may take place. 3.0 INITIAL CONDITIONS 3.1Procedures Verifications (OR 1-98-498) 3.1.1The version of this procedure has been verified to be the current version. _____ Initial 3.1.2The procedure has been verified to be the correct unit for the task. _____ Initial 3.2Individuals have been briefed by the Shift Supervisor and are aware that unavailability time' will be accumulated for the duration of this appendix. An Admin. LCO has been generated. (LCO 3.7.7) _____ SS Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 87 of 170 APPENDIX 2 A TRAIN CCW SURGE TANK FEED AND BLEED (Page 2 of 6) 3.3 "B" Train CCW is the on-service train. _____ Initial 3.4A Train CCW is operating supplying flow to 1B SFP HX. _____ Initial 3.5 Connect a hose pressure tested to 150 psi from 1B SFP HX CCW OUTLET LINE VT, Q1P17V015B to inlet throttle valve attached to temporary demineralizer. _____ Initial 3.6 Direct communication is established between the Control Room and Temporary Demineralizer area (New Fuel area). _____ Initial 3.7 Establish communication between control room and demin water to surge tank makeup valve. _____ Initial 3.8"B" Train RHR Pump, Charging Pump, Service Water Pump and Diesel Generators operable. _____ Initial 3.9Temporary demin liner aligned, and ready for processing, per Figure 1. _____ Initial 3.10Suitable container(s) available to receive the demin effluent. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 88 of 170 APPENDIX 2 A TRAIN CCW SURGE TANK FEED AND BLEED (Page 3 of 6) 4.0 INSTRUCTIONS 4.1 Notify Chemistry personnel CCW feed and bleed is commencing. _____ Initial CAUTIONOnly one chemical mixing isolation may be open at any time. Simultaneous opening of chemical mixing isolations in opposite trains will result in a loss of two independent CCW loops due to cross-connecting trains through the mixing valves. 4.2 Open the chemical mixing valve for the running A Train CCW pump as follows: 4.2.1 Verify closed CCW SRG TK CHEM ADD, Q1P17V114. _____ Initial 4.2.2 Check running the 1C CCW PUMP. _____ Initial 4.2.3 Verify closed 1A CCW PUMP CHEM MIXING ISO, Q1P17V278A. _____ Initial 4.2.4 Verify closed 1B CCW PUMP CHEM MIXING ISO, Q1P17V278B. _____ Initial 4.2.5 Open 1C CCW PUMP CHEM MIXING ISO, Q1P17V278C. _____ Initial 4.2.6 Close CCW SRG TK DEMIN INLET ISO, N1P11V045. _____ Initial 4.3 Open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A. _____ Initial 4.4 Verify closed inlet and outlet valves attached to the temporary demineralizers. _____ Initial 4.5 Open 1B SFP HX CCW OUTLET LINE VT, Q1P17V015B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 89 of 170 APPENDIX 2 A TRAIN CCW SURGE TANK FEED AND BLEED (Page 4 of 6) CAUTIONSteps 4.6 and 4.7 should be performed simultaneously to maintain CCW Surge Tank between 35" to 48" while obtaining a feed and bleed flow rate of approximately 20 gpm. 4.6 Throttle CCW SRG TK DEMIN INLET ISO, N1P11V045 as required to provide makeup flow slightly greater than bleed flow so that level can be controlled by cycling makeup MOV at infrequent intervals. (minimizing valve cycles lessens the possibility of tripping overloads in supply breaker.) _____ Initial 4.7 Open outlet valve and throttle open inlet valve attached to the temporary demineralizer as required. _____ Initial NOTETo monitor demineralizer effluent, place a sheet of white paper behind the effluent path for comparison to verify water is clear with no yellow tint. 4.8Frequently monitor demineralizer effluent. Secure feed and bleed if yellow water is detected. _____ Initial 4.9WHEN the feed and bleed has been completed, THEN close the following valves: 4.9.11B SFP HX CCW OUTLET LINE VT, Q1P17V015B _____ Initial 4.9.2MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A _____ Initial 4.9.3Inlet valves attached to the temporary demineralizers. _____ Initial 4.9.4Outlet valves attached to the temporary demineralizers. _____ Initial 4.10 Open CCW SRG TK DEMIN INLET ISO, N1P11V045. _____ Initial 4.11 Notify Chemistry personnel CCW feed and bleed evolution is secured. _____ Initial 4.12 Remove the temporary hose connection and cap 1B SFP HX CCW OUTLET LINE VT, Q1P17V015B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 90 of 170 APPENDIX 2 A TRAIN CCW SURGE TANK FEED AND BLEED (Page 5 of 6) 4.13WHEN chemical mixing is no longer required, THEN close 1C CCW PUMP CHEM MIXING ISO, Q1P17V278C. _____ Initial 4.14 INDEPENDENTLY VERIFY the following valves are CLOSED: _____ Initial 4.14.11B SFP HX CCW OUTLET LINE VT, Q1P17V015B _____ Initial 4.14.2MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A _____ Initial 4.14.31C CCW PUMP CHEM MIXING ISO, Q1P17V278C _____ Initial 4.15 INDEPENDENTLY VERIFY that CCW SRG TK DEMIN INLET ISO, N1P11V045 is OPEN. _____ Initial 4.16 Attach label(s) to any container(s) containing the processed effluent. _____ 4.16.1The labels should include the following: Date / Time stamp from this appendix. Source of CCW processed. Date Chemistry sample requested. 4.17Request Chemistry perform sample analysis of the demin effluent stored in the temporary container(s). _____ 4.18WHEN Chemistry sample analysis has been obtained, THEN perform the following as applicable. 4.18.1IF the sample results are satisfactory for disposal, THEN pump the contents of the containers labeled per step 4.17 into the nearest sump for processing. _____ 4.18.2IF the sample results indicated further processing, THEN perform the following: 4.18.2.1 Contact Operations Supervision for guidance as to how to process the contents of the containers. _____ 4.18.2.2 Remove all labels attached per step 4.17. _____ 4.18.2.3 Label the containers to be processed as necessary to prevent inadvertent disposal. _____ UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 91 of 170 APPENDIX 2 A TRAIN CCW SURGE TANK FEED AND BLEED (Page 6 of 6) FIGURE 1 Temporary DemineralizerINOUT66666From CCW Source(a portable pump taking suction from containerized waste CCW)Approx. 8 ft. Section Red Rubber HoseApprox. 4 ft. Section Red Rubber HoseIn Line Johnson ScreenFlow Direction Shown on Sightglass with Arrow(REQUIRED)0000gpmFlow Rate Meter & Flow Totalizer(OPTIONAL)Flow Direction Stamped In Metal on Totalizer(OPTIONAL)Demin Effluent to Temporary ContainerNOTE:The in line Johnson Screen serves as an additional barrier to prevent putting resin into the floor drain system. The temporary demineralizer should not be placed in service without it. The flow indicator and totalizer are optional depending on the need to monitor flowrate and total gallons processed. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 92 of 170 APPENDIX 3 CCW PROCESSING USING TEMPORARY DEMIN LINER APPENDIX 3 CCW PROCESSING USING TEMPORARY DEMIN LINER (Deleted by Version 93.0 UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 93 of 170 APPENDIX 4 FEED AND BLEED OF THE ON SERVICE CCW TRAIN (Deleted by Version 93.0) Thidiitf6 UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 94 of 170 APPENDIX 5 PROCESSING CONTAINERS OF WASTE CCW USING TEMPORARY DEMIN LINER APPENDIX 5 PROCESSING CONTAINERS OF WASTE CCW USING TEMPORARY DEMIN LINER Performed by: Date Reviewed by: Date This appendix consists of 5 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 95 of 170 APPENDIX 5 PROCESSING CONTAINERS OF WASTE CCW USING TEMPORARY DEMIN LINER (Page 1 of 5) 1.0 PURPOSE 1.1The purpose of this Appendix is to allow processing of containerized waste CCW using a temporary demin liner discharging to suitable container. It is intended that all CCW waste generated on the non-rad side be processed on the non-rad side and all CCW waste generated on the rad side be processed on the rad side. 1.2The intent is to always process waste CCW recovered from the non-rad thru the liner in the LER. If CCW is recovered from the rad side, then the intent is to process this water thru the demin located on the rad side. {CR 2007106648} 2.0 PRECAUTIONS AND LIMITATIONS 2.1To extend the life of resin, temporary demineralizers should be isolated with water maintained in them when not in use. 2.2The empty drums must to be staged correctly in order to effectively use the non-rad side demin rigs. Consult the Pre-job brief sheets for recommendations concerning drum staging. (AI2009201680) 2.3The empty drums to receive the demineralizer effluent will be rinsed during the CCW processing. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 96 of 170 APPENDIX 5 PROCESSING CONTAINERS OF WASTE CCW USING TEMPORARY DEMIN LINER 3.0 INITIAL CONDITIONS 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ Initial 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 3.3CCW containers are staged in a location convenient to the temporary demin liner, and a suitable temporary pump is available. _____ Initial 3.4A temporary liner with resin is available to process CCW per Figure 1. _____ Initial 3.5Suitable container(s) available to receive the demin effluent. _____ Initial 3.6Verify that the liner is in place in an area that does not interfere with other work activities, have liner moved as necessary. _____ Initial 3.7Notify HP of intent to process waste water via TEMPORARY DEMIN LINER. (CR 2009111090, 2009106771) _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 97 of 170 APPENDIX 5 PROCESSING CONTAINERS OF WASTE CCW USING TEMPORARY DEMIN LINER (Page 2 of 5) 4.0 INSTRUCTIONS 4.1 Connect AND route hose from temporary demin effluent to an empty, clean container. _____ Initial 4.2 Commence processing the first pass of resin effluent by performing the following: 4.2.1 Open the outlet valve. _____ Initial 4.2.2 Throttle open the inlet valve. _____ Initial 4.2.3 Start the temporary pump. _____ Initial 4.3 Sample the first pass of resin effluent. _____ CHM 4.4 Secure the effluent flow by performing the following: 4.4.1 Secure the temporary _____ Initial 4.4.2 Close the inlet valve. _____ Initial 4.4.3 Close the outlet valve. _____ Initial 4.5 Determine discharge path for processed effluent as follows: 4.5.1 Check sample for visible chromates. IF visible chromates are present, THEN recommend replacement of the portable demineralizer resin, and repeat of steps 4.1 through 4.5. _____ CHM Visible chromates present (circle one) YES / NO 4.6 Route outlet hose from temporary demineralizer to the suitable container(s). _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 98 of 170 APPENDIX 5 PROCESSING CONTAINERS OF WASTE CCW USING TEMPORARY DEMIN LINER (Page 3 of 5) 4.7 Initiate continuous processing of containerized CCW by performing the following, as required: 4.7.1 Open the inlet valve on the temporary demineralizer. _____ Initial 4.7.2 Open the outlet valve on the temporary demineralizer. _____ Initial 4.7.3 Start the temporary pump. _____ Initial 4.7.4For each empty CCW drum to receive CCW, perform the following: 4.7.4.1. Process a small amount of CCW through the demineralizer into the empty drum. _____ Initial 4.7.4.2. Stop the temporary pump. _____ Initial 4.7.4.3. Move the effluent around inside the drum long enough to sufficiently rinse the inside of the drum. _____ Initial 4.7.4.4. Pumpthe effluent from the rinsed drum back to the original drum containing the CCW to be processed. _____ Initial 4.7.4.5 Start the pump to process the CCW drum through the demineralizer and into the drum rinsed in step 4.7.4.3. _____ Initial NOTETo monitor demin. effluent, place a white sheet of paper behind the effluent path for comparison to verify water is clear with no yellow tint. 4.8 Monitor effluent frequently for CCW and secure if detected. _____ Initial 4.9WHEN processing is complete, THEN stop the temporary pump. 4.9.1 Close the inlet valve on the temporary demineralizer. _____ Initial 4.9.2 Close the outlet valve on the temporary demineralizer. _____ Initial 4.10 Store the hoses and the temporary pump in the appropriate location. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 99 of 170 APPENDIX 5 PROCESSING CONTAINERS OF WASTE CCW USING TEMPORARY DEMIN LINER Page 4 of 5 4.11 Attach label(s) to any container(s) containing the processed effluent. _____ Initial 4.11.1The labels should include the following: Date / Time stamp from this appendix. Source of CCW processed. Date Chemistry sample requested. 4.12Request Chemistry perform sample analysis of the demin effluent stored in the temporary container(s). _____ Initial 4.13WHEN Chemistry sample analysis has been obtained, THEN perform the following as applicable. 4.13.1IF the sample results are satisfactory for disposal, THEN pump the contents of the containers labeled per step 4.11 into the nearest sump for processing. _____ Initial 4.13.2IF the sample results indicated further processing, THEN perform the following: 4.13.2.1 Contact Operations Supervision for guidance as to how to process the contents of the containers. _____ Initial 4.13.2.2 Remove all labels attached per step 4.11. _____ Initial4.13.2.3 Label the containers to be processed as necessary to prevent inadvertent disposal. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 100 of 170 APPENDIX 5 PROCESSING CONTAINERS OF WASTE CCW USING TEMPORARY DEMIN LINER FIGURE 1 (Page 5 of 5)

TemporaryDemineralizerINOUT66666From CCW Source(a portable pump taking suction from containerized waste CCW)Approx. 8 ft. Section Red Rubber HoseApprox. 4 ft. Section Red Rubber HoseIn Line Johnson ScreenFlow Direction Shown on Sightglass with Arrow(REQUIRED)0000gpmFlow Rate Meter & Flow Totalizer(OPTIONAL)Flow Direction Stamped In Metal on Totalizer(OPTIONAL)Demin Effluent to Suitable ContainerNOTE:The in line Johnson Screen serves as an additional barrier to prevent putting resin into the floor drain system. The temporary demineralizer should not be placed in service without it. The flow indicator and totalizer are optional depending on the need to monitor flowrate and total gallons processed. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 101 of 170 APPENDIX 6 CCW SYSTEM REFILL FROM DRUMS Performed by: Date Verified by: Date Reviewed by: Date This appendix consists of 2 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 102 of 170 APPENDIX 6 CCW SYSTEM REFILL FROM DRUMS (Page 1 of 2) 1.0 PURPOSE This appendix provides guidance to pump CCW back into system from drums. 2.0 PRECAUTIONS AND LIMITATIONS 2.1Continuously monitor CCW Surge Tank level. Maintain below 50". If above 50" then secure adding to surge tank. 2.2All components used for this connection are required to be pressure tested to 150 psig which provides assurance that the system can withstand CCW system pressure. All hoses are to have banded fittings. 2.3Verify adequate capacity exists in the CCW surge tank before transferring any CCW into the CCW Surge Tank. 2.4Ensure that CCW to be added has been sampled by chemistry and meets CCW chemistry specs. 3.0 INITIAL CONDITIONS 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ Initial 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 3.3Perform the following at CCW SRG TK CHEM ADD, Q1P17V114: 3.3.1Remove pipe cap. _____ Initial 3.3.2Connect a hose pressure tested to 150 psi from Discharge of portable pump to CCW SRG TK CHEM ADD, Q1P17V114. _____ Initial 3.4Establish communication between control room and portable pump operator to control CCW Surge Tank level during pumping. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 103 of 170 APPENDIX 6 CCW SYSTEM REFILL FROM DRUMS (Page 2 of 2) 4.0 INSTRUCTIONS 4.1 Notify Chemistry personnel CCW Surge tank will be filled. _____ Initial 4.2 Verify the following chemical mixing valves are CLOSED: 1A CCW PUMP CHEM MIXING ISO, Q1P17V278A. _____ Initial 1B CCW PUMP CHEM MIXING ISO, Q1P17V278B. _____ Initial 1C CCW PUMP CHEM MIXING ISO, Q1P17V278C. _____ Initial 4.3 Ensure portable pump and hoses set up to take suction and pump to CCW surge tank. _____ Initial 4.4 Open CCW SRG TK CHEM ADD, Q1P17V114 and check for leaks. _____ Initial 4.5 Have Control Room monitor CCW Surge Tank Level. _____ Initial 4.6 Start the portable pump and transfer CCW to Surge Tank. _____ Initial 4.7WHEN transfer complete or when directed by the control room, THEN stop portable pump. _____ Initial 4.8 Perform the following at CCW SRG TK CHEM ADD, Q1P17V114: 4.8.1 Close CCW SRG TK CHEM ADD, Q1P17V114. _____ Initial 4.8.2 Remove hose. _____ Initial 4.8.3 Reinstall cap. _____ Initial 4.9 Store portable pump and hoses. _____ Initial 4.10 Return CCW drums to storage _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 104 of 170 APPENDIX 7 PROCESSING WASTE CCW USING TEMPORARY DEMIN LINER DIRECTLY FROM SYSTEM Performed by: Date Reviewed by: Date This appendix consists of 6 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 105 of 170 APPENDIX 7 PROCESSING WASTE CCW USING TEMPORARY DEMIN LINER DIRECTLY FROM SYSTEM (Page 1 of 6) 1.0 PURPOSE The purpose of this procedure Appendix is to allow processing waste CCW using a temporary demin liner discharging to temporary container. 2.0 PRECAUTIONS AND LIMITATIONS 2.1To extend the life of resin, temporary demineralizers should be isolated with water maintained in them when not in use. 2.2When opening low point drain and high point vent do so slowly and carefully to prevent spilling if system has any pressure remaining. 2.3Many CCW vent valves are Kerotest stop-check valves which close when draining a system, preventing the system from venting properly. This could make the section being drained appear to be empty when waste CCW is still in the system. 2.4All components used for this connection are required to be pressure tested to 150 psig, which provides assurance that the system can withstand CCW system pressure. All hoses are to have banded fittings. 2.5Chemistry should sample the non-rad sumps for chromates, oil, and activity prior to pumping to the Turbine Building sump(s). 2.6To preclude the risk of NPDES non-compliance, the discharge from the temporary demineralizer will be contained in drums or other suitable container until completion of Chemistry sample results. Once Chemistry has confirmed that the demin effluent is acceptable for release to the environment, discharge to the environment may take place. 3.0 INITIAL CONDITIONS 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ Initial 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 3.3A suitable temporary pump is available. _____ Initial 3.4A temporary liner with resin is available to process CCW per Figure 1. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 106 of 170 APPENDIX 7 PROCESSING WASTE CCW USING TEMPORARY DEMIN LINER DIRECTLY FROM SYSTEM (Page 2 of 6) 3.5Suitable container(s) available to receive demin effluent. _____ Initial 3.6Verify that the liner is in place in an area that does not interfere with other work activities. Have liner moved as necessary. _____ Initial 3.7Using plant drawings determine location of low point drain and high point vent to be used during waste CCW processing. _____ Initial High point vent: Low point drain: 3.8The section of the CCW system that maintenance is to be performed on is isolated and tagged. _____ Initial 3.9If the liner is placed external to the Auxiliary Building, then a barrier is in place around the temporary lines to contain a CCW spill if one should occur. Contact FAC group, if necessary, to provide a barrier if needed. _____ Initial 3.10If necessary, then direct maintenance to remove one section of grating from the Lower Equipment Room hatch to allow process hoses to be routed (Small section on south east corner). _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 107 of 170 APPENDIX 7 PROCESSING WASTE CCW USING TEMPORARY DEMIN LINER DIRECTLY FROM SYSTEM (Page 3 of 6) 4.0 INSTRUCTIONS 4.1 Ensure that system section to be drained is isolated AND depressurized. _____ Initial 4.2 Attach a hose from the return system on the temporary demin AND route the hose to the LER sump (See Figure 1). _____ Initial 4.3 Connect suction hose to temporary pump from low point drain. _____ Initial Sections drain point: 4.4 Open section drain point AND check for leaks. _____ Initial Valve opened: 4.5 Verify high point vent OPEN. _____ Initial High point vent: CAUTIONAn excessive flow rate will allow high chromium level in the demin effluent. Do not increase the flow rate without obtaining a sample of demin effluent for chromium. 4.6 Commence processing the first pass of resin effluent by performing the following: 4.6.1 Open the outlet valve. _____ Initial 4.6.2 Throttle open the inlet valve. _____ Initial 4.6.3 Start the temporary pump. _____ Initial 4.7 Verify CCW is being processed by the temporary demin AND draining back to the LER sump. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 108 of 170 APPENDIX 7 PROCESSING WASTE CCW USING TEMPORARY DEMIN LINER DIRECTLY FROM SYSTEM (Page 4 of 6) NOTETo monitor demin effluent, place a white sheet of paper behind the effluent path for comparison to verify water is clear with no yellow tint. 4.8 Monitor demin effluent frequently, and secure processing if yellow water is detected. _____ Initial 4.9WHEN the temporary container level is high THEN stop draining by securing temporary pump AND closing inlet valve to demin. _____ Initial 4.10 Close section drain point opened in Step 4.4. _____ Initial Valve closed: 4.11 Remove temporary pump suction hose from CCW section drained. _____ Initial 4.12 Close high point vent valve opened in Step 4.5. _____ Initial Valve closed: 4.13IF desired, THEN have the temporary demin removed. _____ Initial 4.14IF removed, THEN have maintenance replace grating removed on the lower equipment room hatch. _____ MM 4.15 Store the hoses and the temporary pump in the appropriate location. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 109 of 170 APPENDIX 7 PROCESSING WASTE CCW USING TEMPORARY DEMIN LINER DIRECTLY FROM SYSTEM (Page 5 of 6) 4.16 Attach label(s) to any container(s) containing the processed effluent. _____ Initial 4.16.1The labels should include the following: Date / Time stamp from this appendix. Source of CCW processed. Date Chemistry sample requested. 4.17Request Chemistry perform sample analysis of the demin effluent stored in the temporary container(s). _____ Initial 4.18WHEN Chemistry sample analysis has been obtained, THEN perform the following as applicable. 4.18.1IF the sample results are satisfactory for disposal, THEN pump the contents of the containers labeled per step 4.16 into the nearest sump for processing. _____ Initial 4.18.2IF the sample results indicated further processing, THEN perform the following: 4.18.2.1 Contact Operations Supervision for guidance as to how to process the contents of the containers. _____ Initial 4.18.2.2 Remove all labels attached per step 4.16. _____ Initial 4.19 Label the containers to be processed as necessary to prevent inadvertent disposal. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 110 of 170 APPENDIX 7 PROCESSING WASTE CCW USING TEMPORARY DEMIN LINER DIRECTLY FROM SYSTEM (Page 6 of 6) FIGURE 1

UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 111 of 170 APPENDIX 8 ALIGNING B TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH B TRAIN SW OUT OF SERVICE Performed by: Date Reviewed by: Date This appendix consists of 7 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 112 of 170 APPENDIX 8 ALIGNING B TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH B TRAIN SW OUT OF SERVICE (Page 1 of 7) 1.0 PURPOSE Provide guidance to ensure B Train SFP Cooling has the necessary CCW cooling during core offload with B Train SW secured. 2.0 PRECAUTIONS AND LIMITATIONS 2.1To maintain SFP temperature as low as possible during the core off load, consideration should be given to maximizing CCW cooling to the SFP HX(s) early in the fuel transfer to the SFP. Throttle CCW flow to the on service RHR HX(s) as required to maintain appropriate cooling to the on-service train(s) of RHR during core off load. CCW flow rates in excess of 3100 GPM through the SFP HX should be avoided. (1R23 OLL103 CR2010114600) 2.2B Train room coolers will have no service water flow. 3.0 INITIAL CONDITIONS 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ Initial 3.2This procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 3.3The plant is in Mode 5 or 6. _____ Initial 3.4B Train CCW is secured. _____ Initial 3.5A Train is the On Service Train with 1C CCW Pump aligned to 1C CCW HX. _____ Initial 3.6The miscellaneous header has no component operating which requires cooling with the exception of charging pump miniflow lines. _____ Initial 3.7A Train Service Water is in operation per FNP-1-SOP-24.0, SERVICE WATER SYSTEM. _____ Initial 3.8Service Water is isolated to the turbine building. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 113 of 170 APPENDIX 8 ALIGNING B TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH B TRAIN SW OUT OF SERVICE (Page 2 of 7) 3.9A Train Spent Fuel Pool Cooling is on service. _____ Initial 3.10B Train Service Water outage is in progress or planned, and it is desired place B Train SFP Cooling in service per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM, Appendix 1. _____ Initial 3.111B CCW Pump has been verified aligned to A Train power supply per FNP-1-SOP-23.0C, SHIFTING ON SERVICE TRAIN FROM TRAIN B TO TRAIN A, steps 7.1 through 7.12. _____ Initial 3.12Admin LCO is written to ensure power supply breaker Q1R17BKRFVD5, SW TO 1B CCW HX Q1P16MOV3130B is opened prior to Mode 4 entry. _____ _ Initial 3.13The DC control power switch for Q1R15BKRDF05 is open. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 114 of 170 APPENDIX 8 ALIGNING B TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH B TRAIN SW OUT OF SERVICE (Page 3 of 7) 4.0 INSTRUCTIONS 4.1 Align A Train SW supply through 1B and 1C CCW HX simultaneously as follows: 4.1.1 Verify closed 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002B. _____ Initial 4.1.2 Verify closed 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002A. _____ Initial 4.1.3 Verify closed 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008C. _____ Initial 4.1.4 Verify closed 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008B. _____ Initial 4.1.5 Verify open 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002D. _____ Initial 4.1.6 Verify open 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002C. _____ Initial 4.1.7 Verify open 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008E. _____ Initial 4.1.8 Verify open 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008D. _____ Initial 4.1.9 Open SW TO 1B CCW HX Q1P16MOV3130B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 115 of 170 APPENDIX 8 ALIGNING B TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH B TRAIN SW OUT OF SERVICE (Page 4 of 7) 4.2 Align 1B CCW heat exchanger to supply B Train CCW cooling as follows: 4.2.1IF any charging pump running, THEN verify total charging flow 60 gpm. _____ Initial 4.2.2 Close CCW SUPPLY HDR XCONN, Q1P17V009C. _____ Initial 4.2.3 Close CCW SUPPLY HDR XCONN, Q1P17V009D. _____ Initial 4.2.4 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003C. _____ Initial 4.2.5 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003D. _____ Initial 4.2.6 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110D. _____ Initial 4.2.7 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110E. _____ Initial 4.2.8 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110C. _____ Initial 4.2.9 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110B. _____ Initial 4.2.10 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003A. _____ Initial 4.2.11 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003B. _____ Initial 4.2.12 Open CCW SUPPLY HDR XCONN, Q1P17V009A. _____ Initial 4.2.13 Open CCW SUPPLY HDR XCONN, Q1P17V009B. _____ Initial 4.2.14 Open 1B CCW HX CCW OUTLET ISO, Q1P17V008B. _____ Initial 4.2.15 Close 1A CCW HX CCW OUTLET ISO, Q1P17V008A. _____ Initial 4.2.16 Close DC control power switch for Q1R15BKRDF05. _____ Initial 4.2.16.1 Check the breaker closing spring charged. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 116 of 170 APPENDIX 8 ALIGNING B TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH B TRAIN SW OUT OF SERVICE (Page 5 of 7) 4.3 Place 1B CCW heat exchanger on service as follows: 4.3.1 Verify SW FROM 1B CCW HX Q1P16FV3009B in MOD. Throttle 1B CCW HX DISCH FCV HIC 3009B as necessary to control CCW temperature. _____ Initial 4.3.2 Verify CCW TO 1B RHR HX Q1P17MOV3185B is OPEN. _____ Initial 4.3.3 Start 1B CCW PUMP and verify flow increase on FI3043BA for the 1B CCW HX. _____ Initial NOTEThe 1B and 1C CCW HXs are supplied from A Train SW. Adjusting 1B or 1C CCW HX DISCH FCV, HIC 3009B or C affects A Train SW header pressure. 4.3.4 Maintain CCW FROM CCW HX TEMP TI 3042B less than 105°F. _____ Initial NOTEIf the miscellaneous header is in service, it is aligned to the 1B CCW HX which is aligned to B Train CCW. 4.3.5IF desired, THEN after system is stable, close CCW to 1B RHR HX Q1P17MOV3185B. _____ Initial 4.4Restoration to normal alignment after the BTrain of SFP cooling has been secured. 4.4.1 Verify miscellaneous header has no component operating which requires cooling with the exception of charging pump miniflow lines. _____ Initial 4.4.2IF any charging pump running, THEN verify total charging flow 60 gpm. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 117 of 170 APPENDIX 8 ALIGNING B TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH B TRAIN SW OUT OF SERVICE (Page 6 of 7) NOTEThe following step stops all B Train CCW Flow. 4.4.3 Secure the 1B CCW Pump. _____ Initial 4.4.4IF available, THEN verify open CCW to 1B RHR HX Q1P17MOV3185B. _____ Initial 4.4.5 Open the DC control power switch for Q1R15BKRDF05. _____ Initial 4.4.6 Close SW TO 1B CCW HX Q1P16MOV3130B. _____ Initial NOTEThe following sequence aligns the miscellaneous header to A Train CCW. 4.4.7 Close 1B CCW HX CCW OUTLET ISO, Q1P17V008B. _____ Initial 4.4.8 Open 1A CCW HX CCW OUTLET ISO, Q1P17V008A. _____ Initial 4.4.9 Close CCW SUPPLY HDR XCONN, Q1P17V009A. _____ Initial 4.4.10 Close CCW SUPPLY HDR XCONN, Q1P17V009B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 118 of 170 APPENDIX 8 ALIGNING B TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH B TRAIN SW OUT OF SERVICE (Page 7 of 7) 4.4.11 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003B. _____ Initial 4.4.12 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003A. _____ Initial 4.4.13 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110C. _____ Initial 4.4.14 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110B. _____ Initial 4.4.15 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110E. _____ Initial 4.4.16 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110D. _____ Initial 4.4.17 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003C. _____ Initial 4.4.18 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003D. _____ Initial 4.4.19 Open CCW SUPPLY HDR XCONN, Q1P17V009D. _____ Initial 4.4.20 Open CCW SUPPLY HDR XCONN, Q1P17V009C. _____ Initial 4.4.21 Close DC control power switch for Q1R15BKRDF05. _____ Initial 4.4.21.1 Check the breaker closing spring charged. _____ Initial 4.4.22IF desired, THEN verify CCW alignment with A Train on service by performing a walkthrough of FNP-1-SOP-23.0C, SHIFTING ON SERVICE TRAIN FROM TRAIN B TO TRAIN A, Sections 2.0, 3.0 and 4.0. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 119 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE Performed by: Date Reviewed by: Date This appendix consists of 10 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 120 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 1 of 10) 1.0 PURPOSE This appendix provides guidance for aligning the 1B CCW Pump and the 1B CCW Heat Exchanger to the B Train when the 1A CCW Pump and the 1A CCW Heat Exchanger are out of service or unavailable for service. 2.0 PRECAUTIONS AND LIMITATIONS 2.1To maintain SFP temperature as low as possible during the core off load, consideration should be given to maximizing CCW cooling to the SFP HX(s) early in the fuel transfer to the SFP. Throttle CCW flow to the on service RHR HX(s) as required to maintain appropriate cooling to the on-service train(s) of RHR during core off load. CCW flow rates in excess of 3100 GPM through the SFP HX should be avoided. (1R23 OLL103 CR2010114600) 2.2B Train room coolers will have no service water flow. 2.3Any operations involving manipulation of the 4kV disconnect switches associated shall include visual confirmation of the following: 2.3.1The main contacts are in the required state, open or closed. (One contact per phase.) Refer to figure 1 and 2. 2.3.2 The arcing contacts are in the required state, open or closed. (One contact per phase.) Refer to figure 1 and 2. UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 121 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 2 of 10) 3.0 INITIAL CONDITIONS 3.1The version of this appendix has been verified to be the current version. (OR 1-98-498) _____ Initial 3.2The appendix has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 3.31B CCW Pump and 1B CCW Heat Exchanger are currently aligned to A CCW train. _____ Initial 3.4A Train CCW is aligned for service per FNP-1-SOP-23.0A with acceptable line up deviation documented. _____ Initial 3.5The Miscellaneous header is not required to be in service during the performance of this appendix. _____ Initial 3.6The reactor is defueled. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 122 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 3 of 10) 4.0 INSTRUCTIONS 4.1IF required, THEN place the 1C CCW Pump in service on A Train as follows: NOTEStep 4.1.1 is performed to minimize the pressure transient which could otherwise result in CCW to Thermal Barrier HX isolation. CAUTIONThe operation of two pumps through one HX is not allowed. 4.1.1IF not aligned, THEN open CCW TO 1A RHR HX Q1P17MOV3185A. _____ Initial 4.1.2Simultaneously start the Standby 1C CCW Pump AND stop the on service 1B CCW Pump. _____ Initial 4.1.3IF not required for RHR operations, WHEN the system has stabilized, THEN close CCW TO 1A RHR HX, Q1P17MOV3185A. _____ Initial 4.2 Verify the 1A CCW Pump and 1A CCW Heat Exchanger isolated: 4.2.1 Verify that 1A CCW Pump and heat exchanger is out of service and isolated by an appropriate tagging order, _____ Initial OR 4.2.2 Perform the following isolation steps. 4.2.2.1 Verify Q1R15BKRDG04, COMPONENT COOLING WATER PUMP 1A 52-DG04 is racked out. _____ Initial 4.2.3 Verify that 1A CCW HX CCW OUTLET ISO, Q1P17V008A is closed. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 123 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 4 of 10) 4.3 Align 1B CCW Pump and 1B CCW Heat Exchanger to B Train as follows: 4.3.1 Close CCW SUPPLY HDR XCONN, Q1P17V009C. _____ Initial 4.3.2 Close CCW SUPPLY HDR XCONN, Q1P17V009D. _____ Initial 4.3.3 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003C. _____ Initial 4.3.4 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003D. _____ Initial 4.3.5 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110C._____ Initial 4.3.6 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110B. _____ Initial 4.3.7 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110D. _____ Initial 4.3.8 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110E. _____ Initial 4.3.9 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003A. _____ Initial 4.3.10 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003B. _____ Initial 4.3.11 Open CCW SUPPLY HDR XCONN, Q1P17V009A. _____ Initial 4.3.12 Open CCW SUPPLY HDR XCONN, Q1P17V009B. _____ Initial 4.3.13 Open 1B CCW HX CCW OUTLET ISO, Q1P17V008B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 124 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 5 of 10) 4.4 Align SW to the 1B CCW Heat Exchanger as follows: 4.4.1 Close 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002D. _____ Initial 4.4.2 Close 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002C. _____ Initial 4.4.3 Close 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008E. _____ Initial 4.4.4 Close 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008D. _____ Initial 4.4.5 Open 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002B. _____ Initial 4.4.6 Open 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002A. _____ Initial 4.4.7 Open 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008C. _____ Initial 4.4.8 Open 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008B. _____ Initial 4.4.9 Verify SW FROM 1B CCW HX Q1P16FV3009B handswitch is in MOD. _____ Initial 4.4.10 Verify 1B CCW HX DISCH FCV HIC 3009B is demanding the valve to be fully closed (100% demand). _____ Initial 4.4.11Locally verify SW FROM 1B CCW HX Q1P16FV3009B is CLOSED. _____ Initial 4.4.12 Open SW TO 1B CCW HX Q1P16MOV3130B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 125 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 6 of 10) 4.4.13 Throttle open 1B CCW HX DISCH FCV HIC 3009B WHILE throttlingclosed 1A CCW HX DISCH FCV HIC 3009A maintaining existing service water pressure. _____ Initial 4.4.14 Verify 1A CCW HX DISCH FCV HIC 3009A fully CLOSED. _____ Initial 4.4.15 Close SW TO 1A CCW HX Q1P16MOV3130A _____ Initial 4.5 Align B CCW Pump to B Train electrically as follows. 4.5.1 Rackout breaker Q1R15BKRDF05. Turn key # RE-14265 in the mechanical interlock on circuit breaker Q1R15BKRDF05 AND remove it. _____ Initial 4.5.2 Insert key # RE-14265 into the mechanical interlock on 1B CCW Pump 4KV disconnect switch 1A (Q1R18A004A-A) AND turn it. Key # RE-14265 is now held in place. _____ Initial 4.5.3 Perform the following for 1B CCW Pump 4KV disconnect switch 1A (Q1R18A004A-A). 4.5.4 Open disconnect switch Q1R18A004A-A. _____ Initial 4.5.5 Check the position indicator reads SW OPEN. _____ Initial 4.5.6With the aid of a flashlight, perform the following: 4.5.6.1 Check that a visible air gap exists between the main contacts on all three phases. _____ Initial 4.5.6.2 Check that a visible air gap exists between the arcing contacts on all three phases. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 126 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 7 of 10) 4.5.7 Turn key # RE-14224 in its mechanical interlock on disconnect switch 1A AND remove it. 1A disconnect switch is now locked in the open position. _____ Initial 4.5.8 Insert key # RE-14224 into its mechanical interlock on 1B CCW Pump 4KV disconnect switch 1B (Q1R18A004B-B) AND turn it. Key # RE-14224 is now held in place. _____ Initial 4.5.9 Perform the following for 1B CCW Pump 4KV disconnect switch 1B (Q1R18A004B-B). 4.5.10 Close disconnect switch, Q1R18A004B-B. _____ Initial 4.5.11 Check the position indicator reads SW CLOSED. _____ Initial 4.5.12With the aid of a flashlight, perform the following: 4.5.12.1 Check that NO air gap exists for the main contacts on all three phases. (Contacts closed.) _____ Initial 4.5.12.2 Check that NO air gap exists for the arcing contacts on all three phases. (Contacts closed.) _____ Initial 4.5.13 Turn key # RE-14291 in its mechanical interlock. _____ Initial 4.5.14 Remove key # RE-14291. 1B disconnect switch is now locked in the closed position. _____ Initial CAUTIONBreaker Q1R15BKRDG05 has alternate DC control power supplied through fuses in C-HSDP when 1B CCW PUMP LOCAL-REMOTE switch on C-HSDP is in LOCAL. 4.5.15 Verify LOCAL-REMOTE switch on C-HSDP for 1B CCW PUMP in REMOTE ._____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 127 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 8 of 10) 4.5.16 Insert key # RE-14291 into its mechanical interlock on circuit breaker Q1R15BKRDG05. _____ Initial 4.5.17 Turn key # RE-14291. Key # RE-14291 is now held in place. _____ Initial 4.5.18 Rack circuit breaker Q1R15BKRDG05 to the CONNECTED position. _____ Initial 4.5.19 Close DC control power switch for Q1R15BKRDG05 AND verify breaker spring charges. _____ Initial NOTES1B CCW Hx and Pump are now aligned to B Train and can be placed in service if required. At a minimum, the 1B CCW Pump should be "bumped" to cycle the breaker for verifying operability following the racking process. 4.6 Open CCW TO 1B RHR HX Q1P17MOV3185B. _____ Initial 4.7 Start the 1B CCW Pump. _____ Initial 4.8IF not required for RHR operations, WHEN the system has stabilized, THEN close CCW TO 1B RHR HX, Q1P17MOV3185B. _____ Initial 4.9 Throttle 1B CCW HX DISCH FCV HIC 3009B as required to control CCW temperature. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 128 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE Page 9 of 10 FIGURE 1 Typical 4kV Disconnect shown in OPEN condition. Correct Contact Configuration Two Phases shown. Main Contact Arcing Contact Main Contact Arcing Contact UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 129 of 170 APPENDIX 9 ALIGNING B CCW PUMP AND B CCW HX TO B TRAIN WITH A CCW PUMP AND A CCW HX NOT AVAILABLE OR NOT IN SERVICE Page 10 of 10 FIGURE 2 Typical 4kV Disconnect shown in OPEN condition. Incorrect Contact Configuration Two Phases shown. Main contacts open but arcing contact on right is closed (no air gap) Arcing Contact Arcing Contact Main Contact Main Contact UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 130 of 170 APPENDIX 10 RETURNING 1A CCW PUMP TO SERVICE AFTER MAINTENANCE Performed by: Date Reviewed by: Date This appendix consists of 4 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 131 of 170 APPENDIX 10 RETURNING 1A CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 1 of 4)1.0 PURPOSE This appendix provides guidance for filling, venting, and aligning the 1A CCW pump for service after maintenance. 2.0 INITIAL CONDITIONS 2.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ Initial 2.2This procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 2.31A CCW Pump breaker Q1R15BKRDG04 is racked out. _____ Initial 3.0 INSTRUCTIONS 3.1 Verify pump and motor oil levels are 25% to 75%. _____ Initial 3.2 Verify the following vent and drain valves are CLOSED AND CAPPED. 1A CCW PUMP DRN, Q1P17V157A _____ Initial 1A CCW PUMP DRN, Q1P17V157B _____ Initial 1A CCW PUMP VENT, Q1P17V156D _____ Initial 1A CCW PUMP DISCH HDR DRN, Q1P17V281A _____ Initial 3.3 Verify the following vent valves are CLOSED, but NOT capped. These valves will be used for venting. 1A CCW PUMP SUCT LINE VT, Q1P17V279A _____ Initial 1A CCW PUMP VT, Q1P17V156A _____ Initial 3.4 Check 1A CCW PUMP SUCT Q1P17V109A CLOSED. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 132 of 170 APPENDIX 10 RETURNING 1A CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 2 of 4) 3.5 Check 1A CCW PUMP DISCH ISO Q1P17V002A CLOSED. _____ Initial 3.6 Check 1A CCW PUMP MINI-FLOW Q1P17V144A CLOSED. _____ Initial 3.7 Perform the following at 1A CCW PUMP VT Q1P17V156A: _____ Initial 3.7.1 Attach hose to 1A CCW PUMP VT Q1P17V156A. _____ Initial 3.7.2 Route hose to suitable container. _____ Initial 3.7.3 Open 1A CCW PUMP VT Q1P17V156A. _____ Initial 3.8 Perform the following at 1A CCW PUMP SUCT LINE VT, Q1P17V279A: 3.8.1 Attach hose to 1A CCW PUMP SUCT LINE VT, Q1P17V279A. _____ Initial 3.8.2 Route hose to suitable container. _____ Initial 3.8.3 Open 1A CCW PUMP SUCT LINE VT, Q1P17V279A. _____ Initial NOTEThe mini-flow valve should be opened slowly to fill the pump. Opening of the valve too quickly can result in excessive pressure being placed on the mechanical seal. AI 2009201838 3.9 Perform the following to fill 1A CCW PUMP: 3.9.1 Notify Control Room of filling of 1A CCW PUMP: _____ Initial 3.9.2Slowly throttle open 1A CCW PUMP MINI-FLOW Q1P17V144A. _____ Initial 3.9.3 Observe 1A CCW PUMP VT Q1P17V156A, AND 1A CCW PUMP SUCT LINE VT, Q1P17V279A. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 133 of 170 APPENDIX 10 RETURNING 1A CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 3 of 4) 3.9.4WHEN air free water is observed at the valves, THEN close the following valves: 1A CCW PUMP VT Q1P17V156A _____ Initial 1A CCW PUMP SUCT LINE VT, Q1P17V279A _____ Initial 3.10 Remove hose AND cap 1A CCW PUMP SUCT LINE VT, Q1P17V279A. _____ Initial 3.11 Remove hose AND cap 1A CCW PUMP VT Q1P17V156A _____ Initial 3.12 Open 1A CCW PUMP MINI-FLOW Q1P17V144A _____ Initial 3.13 Open 1A CCW PUMP SUCT Q1P17V109A. _____ Initial 3.14 Open 1A CCW PUMP DISCH ISO Q1P17V002A. _____ Initial 3.15 INDEPENDENTLY VERIFY the following are CLOSED AND CAPPED: 1A CCW PUMP SUCT LINE VT, Q1P17V279A _____ Initial 1A CCW PUMP VT Q1P17V156A _____ Initial 3.16 INDEPENDENTLY VERIFY the following are OPEN: 1A CCW PUMP SUCT Q1P17V109A _____ Initial 1A CCW PUMP DISCH ISO Q1P17V002A _____ Initial 1A CCW PUMP MINI-FLOW Q1P17V144A _____ Initial 3.17On C-HSDP, verify 1A CCW Pump Local Remote Handswitch is in REMOTE. _____ Initial 3.18 Rack in 1A CCW Pump supply breaker Q1R15BKRDG04. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 134 of 170 APPENDIX 10 RETURNING 1A CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 4 of 4) 3.19 Turn DC control power ON. _____ Initial 3.20 Verify spring charges on 1A CCW Pump supply breaker Q1R15BKRDG04. _____ Initial 3.21 INDEPENDENTLY VERIFY 1A CCW Pump Local Remote Handswitch is in REMOTE (C-HSDP). _____ Initial 3.22 INDEPENDENTLY VERIFY 1A CCW Pump supply breaker Q1R15BKRDG04 is RACKED IN. _____ Initial 3.23 INDEPENDENTLY VERIFY 1A CCW Pump supply breaker Q1R15BKRDG04 DC control power ON AND spring is CHARGED. _____ Initial 3.24IF required, THEN perform FNP-1-STP-23.1, COMPONENT COOLING WATER PUMP 1A INSERVICE TEST, and record cover page. _____ Initial Time / Date Stamp UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 135 of 170 APPENDIX 11 RETURNING 1B CCW PUMP TO SERVICE AFTER MAINTENANCE Performed by: Date Reviewed by: Date This appendix consists of 5 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 136 of 170 APPENDIX 11 RETURNING 1B CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 1 of 5) 1.0 PURPOSE This appendix provides guidance for filling, venting, and aligning the 1B CCW pump for service after maintenance. 2.0 INITIAL CONDITIONS 2.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ Initial 2.2This procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 2.31B CCW Pump A train supply breaker Q1R15BKRDF05 is racked out. _____ Initial 2.41B CCW Pump B train supply breaker Q1R15BKRDG05 is racked out. _____ Initial 3.0 INSTRUCTIONS 3.1 Verify pump and motor oil levels are 25% to 75%. _____ Initial 3.2 Verify the following vent and drain valves are CLOSED AND CAPPED. 1B CCW PUMP DRN, Q1P17V157C _____ Initial 1B CCW PUMP DRN, Q1P17V157D _____ Initial 1B CCW PUMP VENT, Q1P17V156E _____ Initial 1B CCW PUMP DISCH HDR DRN, Q1P17V281B _____ Initial 3.3 Verify the following vent valves are CLOSED, but NOT capped. These valves will be used for venting. 1B CCW PUMP SUCT LINE VT, Q1P17V279B _____ Initial 1B CCW PUMP VT, Q1P17V156B _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 137 of 170 APPENDIX 11 RETURNING 1B CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 2 of 5) 3.4 Check 1B CCW PUMP SUCT Q1P17V109B closed. _____ Initial 3.5 Check 1B CCW PUMP DISCH ISO Q1P17V002B closed. _____ Initial 3.6 Check 1B CCW PUMP MINI-FLOW Q1P17V144B closed. _____ Initial 3.7 Perform the following at 1B CCW PUMP VT Q1P17V156B: 3.7.1 Attach hose to 1B CCW PUMP VT Q1P17V156B. _____ Initial 3.7.2 Route hose to suitable container. _____ Initial 3.7.3 Open 1B CCW PUMP VT Q1P17V156B. _____ Initial 3.8 Perform the following at 1B CCW PUMP SUCT LINE VT, Q1P17V279B: 3.8.1 Attach hose to 1B CCW PUMP SUCT LINE VT, Q1P17V279B. _____ Initial 3.8.2 Route hose to suitable container. _____ Initial 3.8.3 Open 1B CCW PUMP SUCT LINE VT, Q1P17V279B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 138 of 170 APPENDIX 11 RETURNING 1B CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 3 of 5) NOTEThe mini-flow valve should be opened slowly to fill the pump. Opening of the valve too quickly can result in excessive pressure being placed on the mechanical seal. AI 2009201838 3.9 Perform the following to fill 1B CCW PUMP: 3.9.1 Notify Control Room of filling of 1B CCW PUMP: _____ Initial 3.9.2Slowly throttle open 1B CCW PUMP MINI-FLOW Q1P17V144B. _____ Initial 3.9.3 Observe 1B CCW PUMP VT Q1P17V156B, AND 1B CCW PUMP SUCT LINE VT, Q1P17V279B _____ Initial 3.9.4WHEN air free water is observed at the valves, THEN close the following valves: 1B CCW PUMP VT Q1P17V156B _____ Initial 1B CCW PUMP SUCT LINE VT, Q1P17V279B _____ Initial 3.10 Remove hose AND cap 1B CCW PUMP SUCT LINE VT, Q1P17V279B. _____ Initial 3.11 Remove hose AND cap 1B CCW PUMP VT Q1P17V156B _____ Initial 3.12 Open 1B CCW PUMP MINI-FLOW Q1P17V144B _____ Initial 3.13 Open 1B CCW PUMP SUCT Q1P17V109B. _____ Initial 3.14 Open 1B CCW PUMP DISCH ISO Q1P17V002B. _____ Initial 3.15 INDEPENDENTLY VERIFY the following are CLOSED AND CAPPED: 1B CCW PUMP SUCT LINE VT, Q1P17V279B _____ Initial 1B CCW PUMP VT Q1P17V156B _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 139 of 170 APPENDIX 11 RETURNING 1B CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 4 of 5) 3.16 INDEPENDENTLY VERIFY the following are OPEN: 1B CCW PUMP SUCT Q1P17V109B _____ Initial 1B CCW PUMP DISCH ISO Q1P17V002B _____ Initial 1B CCW PUMP MINI-FLOW Q1P17V144B _____ Initial 3.17On C-HSDP, verify 1B CCW Pump B train Local Remote Handswitch is in REMOTE. _____ Initial 3.18On A-HSDP, verify 1B CCW Pump A train Local Remote Handswitch is in REMOTE. _____ Initial 3.19IF desired to align 1B CCW pump to A Train, THEN perform the following: 3.19.1 Rack in the 1B CCW Pump A train supply breaker Q1R15BKRDF05. _____ Initial 3.19.2 Turn DC control power on. _____ Initial 3.19.3 Verify Q1R15BKRDF05 breaker spring charges. _____ Initial 3.20IF desired to align 1B CCW pump to B Train, THEN perform the following: 3.20.1 Rack in the 1B CCW Pump B train supply breaker Q1R15BKRDG05. _____ Initial 3.20.2 Turn DC control power on. _____ Initial 3.20.3 Verify Q1R15BKRDG05 breaker spring charges. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 140 of 170 APPENDIX 11 RETURNING 1B CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 5 of 5) 3.21 INDEPENDENTLY VERIFY the following: 1B CCW Pump B train Local Remote Handswitch is in REMOTE (C-HSDP). _____ Initial 1B CCW Pump A train Local Remote Handswitch is in REMOTE (A-HSDP). _____ Initial 3.22IF aligned to A train, THEN INDEPENDENTLY VERIFY the 1B CCW Pump A train supply breaker RACKED IN. 3.22.1 Verify 1B CCW Pump A train supply breaker Q1R15BKRDF05 DC control power is ON. _____ Initial 3.22.2 Verify 1B CCW Pump A train supply breaker Q1R15BKRDF05 breaker spring is CHARGED. _____ Initial 3.23IF aligned to B train, THEN INDEPENDENTLY VERIFY the 1B CCW Pump B train supply breaker RACKED IN. 3.23.1 Verify 1B CCW Pump B train supply breaker Q1R15BKRDG05 DC control power is ON. _____ Initial 3.23.2 Verify 1B CCW Pump B train supply breaker Q1R15BKRDG05 breaker spring is CHARGED. _____ Initial 3.24IF required, THEN perform FNP-1-STP-23.2, Component Cooling Water Pump 1B INSERVICE TEST, AND record cover page. _____ Initial Time / Date Stamp UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 141 of 170 APPENDIX 12 RETURNING 1C CCW PUMP TO SERVICE AFTER MAINTENANCE Performed by: Date Reviewed by: Date This appendix consists of 4 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 142 of 170 APPENDIX 12 RETURNING 1C CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 1 of 4) 1.0 PURPOSE This appendix provides guidance for filling, venting, and aligning the 1C CCW pump for service after maintenance. 2.0 INITIAL CONDITIONS 2.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ Initial 2.2This procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 2.31C CCW Pump breaker Q1R15BKRDF04 is racked out. _____ Initial 3.0 INSTRUCTIONS 3.1 Verify pump and motor oil levels are 25% to 75%. _____ Initial 3.2 Verify the following vent and drain valves are CLOSED AND CAPPED. 1C CCW PUMP DRN, Q1P17V157F _____ Initial 1C CCW PUMP DRN, Q1P17V157E _____ Initial 1C CCW PUMP VENT, Q1P17V156F _____ Initial 1C CCW PUMP DISCH HDR DRN, Q1P17V281C _____ Initial 3.3 Verify the following vent valves are CLOSED, but NOT capped. These valves will be used for venting. 1C CCW PUMP SUCT LINE VT, Q1P17V279C _____ Initial 1C CCW PUMP VT, Q1P17V156C _____ Initial 3.4 Check 1C CCW PUMP SUCT ISO Q1P17V109C closed. _____ Initial 3.5 Check 1C CCW PUMP DISCH ISO Q1P17V002C closed. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 143 of 170 APPENDIX 12 RETURNING 1C CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 2 of 4) 3.6 Check 1C CCW PUMP MINI-FLOW Q1P17V144C closed. _____ Initial 3.7 Perform the following at 1C CCW PUMP VT Q1P17V156C: 3.7.1 Attach hose to 1C CCW PUMP VT Q1P17V156C. _____ Initial 3.7.2 Route hose to suitable container. _____ Initial 3.7.3 Open 1C CCW PUMP VT Q1P17V156C. _____ Initial 3.8 Perform the following at 1C CCW PUMP SUCT LINE VT, Q1P17V279C: 3.8.1 Attach hose to 1C CCW PUMP SUCT LINE VT, Q1P17V279C. _____ Initial 3.8.2 Route hose to suitable container. _____ Initial 3.8.3 Open 1C CCW PUMP SUCT LINE VT, Q1P17V279C. _____ Initial NOTEThe mini-flow valve should be opened slowly to fill the pump. Opening of the valve too quickly can result in excessive pressure being placed on the mechanical seal. AI 2009201838 3.9 Perform the following to fill 1C CCW PUMP: 3.9.1 Notify Control Room of filling of 1C CCW PUMP: _____ Initial 3.9.2Slowly throttle open 1C CCW PUMP MINI-FLOW Q1P17V144C. _____ Initial 3.9.3 Observe 1C CCW PUMP VT Q1P17V156C, AND 1C CCW PUMP SUCT LINE VT, Q1P17V279C. _____ Initial 3.9.4WHEN air free water is observed at the valves, THEN close the following valves: 1C CCW PUMP VT Q1P17V156C _____ Initial 1C CCW PUMP SUCT LINE VT, Q1P17V279C _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 144 of 170 APPENDIX 12 RETURNING 1C CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 3 of 4) 3.10 Remove hose AND cap 1C CCW PUMP SUCT LINE VT, Q1P17V279C. _____ Initial 3.11 Remove hose AND cap 1C CCW PUMP VT Q1P17V156C _____ Initial 3.12 Open 1C CCW PUMP MINI-FLOW Q1P17V144C _____ Initial 3.13 Open 1C CCW PUMP SUCT Q1P17V109C. _____ Initial 3.14 Open 1C CCW PUMP DISCH ISO Q1P17V002C. _____ Initial 3.15 INDEPENDENTLY VERIFY the following are CLOSED AND CAPPED: 1C CCW PUMP SUCT LINE VT, Q1P17V279C _____ Initial 1C CCW PUMP VT Q1P17V156C _____ Initial 3.16 INDEPENDENTLY VERIFY the following are OPEN: 1C CCW PUMP SUCT Q1P17V109C _____ Initial 1C CCW PUMP DISCH ISO Q1P17V002C _____ Initial 1C CCW PUMP MINI-FLOW Q1P17V144C _____ Initial 3.17On A-HSDP, verify 1C CCW Pump Local Remote Handswitch is in REMOTE. _____ Initial 3.18 Rack in 1C CCW Pump supply breaker Q1R15BKRDF04. _____ Initial 3.19 Turn DC control power ON. _____ Initial 3.20 Verify spring charges on 1C CCW Pump supply breaker Q1R15BKRDF04. _____ Initial 3.21 INDEPENDENTLY VERIFY 1C CCW Pump Local Remote Handswitch is in REMOTE (A-HSDP). _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 145 of 170 APPENDIX 12 RETURNING 1C CCW PUMP TO SERVICE AFTER MAINTENANCE (Page 4 of 4) 3.22 INDEPENDENTLY VERIFY 1C CCW Pump supply breaker Q1R15BKRDF04 is RACKED IN. _____ Initial 3.23 INDEPENDENTLY VERIFY 1C CCW Pump supply breaker Q1R15BKRDF04 DC control power ON AND spring is CHARGED. _____ Initial 3.24IF required, THEN perform FNP-1-STP-23.3, COMPONENT COOLING WATER PUMP 1C INSERVICE TEST, AND record cover page. _____ Initial Time / Date Stamp UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 146 of 170 APPENDIX 13 ALIGNING A TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH A TRAIN SW OUT OF SERVICE Performed by: Date Reviewed by: Date This appendix consists of 6 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 147 of 170 APPENDIX 13 ALIGNING A TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH A TRAIN SW OUT OF SERVICE (Page 1 of 6) 1.0 PURPOSE Provide guidance to ensure A Train SFP Cooling has the necessary CCW cooling during core offload with A Train SW secured. 2.0 PRECAUTIONS AND LIMITATIONS 2.1A Train room coolers will have no service water flow. 3.0 INITIAL CONDITIONS 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ Initial 3.2This procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 3.3The plant is in Mode 5 or 6. _____ Initial 3.4A Train CCW is secured. _____ Initial 3.5B Train is the On Service Train with 1A CCW Pump aligned to 1A CCW HX. _____ Initial 3.6The miscellaneous header has no component operating which requires cooling with the exception of charging pump miniflow lines. _____ Initial 3.7B Train Service Water is in operation per FNP-1-SOP-24.0, SERVICE WATER SYSTEM. _____ Initial 3.8Service Water is isolated to the turbine building. _____ Initial 3.9B Train Spent Fuel Pool Cooling is on service. _____ Initial 3.10A' Train Service Water outage is in progress or planned, and it is desired place A Train SFP Cooling in service per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM, Appendix 1. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 148 of 170 APPENDIX 13 ALIGNING A TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH A TRAIN SW OUT OF SERVICE (Page 2 of 6) 3.111B CCW Pump has been verified aligned to B Train power supply per FNP-1-SOP-23.0B, SHIFTING ON SERVICE TRAIN FROM TRAIN A TO TRAIN B, steps 7.1 through 7.9. _____ Initial 3.12The DC control power switch for Q1R15BKRDG05 is OPEN. _____ Initial 4.0 INSTRUCTIONS 4.1 Align B Train SW supply through 1B and 1A CCW HX simultaneously as follows: 4.1.1 Verify closed 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002C. _____ Initial 4.1.2 Verify closed 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002D._____ Initial 4.1.3 Verify closed 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008D. _____ Initial 4.1.4 Verify closed 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008E. _____ Initial 4.1.5 Verify open 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002A. _____ Initial 4.1.6 Verify open 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002B. _____ Initial 4.1.7 Verify open 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008B. _____ Initial 4.1.8 Verify open 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008C. _____ Initial 4.1.9 Open SW TO 1B CCW HX Q1P16MOV3130B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 149 of 170 APPENDIX 13 ALIGNING A TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH A TRAIN SW OUT OF SERVICE (Page 3 of 6) 4.2 Align 1B CCW Pump and 1B CCW Heat Exchanger to A Train as follows: 4.2.1 Close CCW SUPPLY HDR XCONN, Q1P17V009A. _____ Initial 4.2.2 Close CCW SUPPLY HDR XCONN, Q1P17V009B. _____ Initial 4.2.3 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003A. _____ Initial 4.2.4 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003B. _____ Initial 4.2.5 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110C. _____ Initial 4.2.6 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110B. _____ Initial 4.2.7 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110D _____ Initial 4.2.8 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110E._____ Initial 4.2.9 Open CCW SUPPLY HDR XCONN, Q1P17V009C. _____ Initial 4.2.10 Open CCW SUPPLY HDR XCONN, Q1P17V009D _____ Initial 4.2.11 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003C. _____ Initial 4.2.12 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003D _____ Initial 4.2.13 Open 1B CCW HX CCW OUTLET ISO, Q1P17V008B _____ Initial 4.2.14 Close 1C CCW HX CCW OUTLET ISO, Q1P17V008C. _____ Initial 4.2.15 Close DC control power switch for Q1R15BKRDG05 and check the breaker closing spring charged. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 150 of 170 APPENDIX 13 ALIGNING A TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH A TRAIN SW OUT OF SERVICE (Page 4 of 6) 4.3 Place 1B CCW heat exchanger on service as follows: 4.3.1 Verify SW FROM 1B CCW HX Q1P16FV3009B in MOD. Throttle 1B CCW HX DISCH FCV HIC 3009B as necessary to control CCW temperature. _____ Initial 4.3.2 Verify open CCW TO 1A RHR HX Q1P17MOV3185A. _____ Initial 4.3.3 Start 1B CCW PUMP AND verify flow increase on FI3043BA for the 1B CCW HX. _____ Initial NOTEThe 1B AND 1A CCW HXs are supplied from B Train SW. Adjusting 1B OR 1A CCW HX DISCH FCV, HIC 3009B or A affects B Train SW header pressure. 4.3.4 Maintain CCW FROM CCW HX TEMP TI 3042B less than 105°F. _____ Initial NOTEIf the miscellaneous header is in service, it is aligned to the 1B CCW HX which is aligned to A Train CCW. 4.3.5IF desired, THEN after system is stable, close CCW to 1A RHR HX Q1P17MOV3185A. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 151 of 170 APPENDIX 13 ALIGNING A TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH A TRAIN SW OUT OF SERVICE (Page 5 of 6) 4.4Restoration to normal alignment after the A Train of SFP cooling has been secured. 4.4.1 Verify miscellaneous header has no component operating which requires cooling with the exception of charging pump miniflow lines. _____ Initial 4.4.2IF any charging pump running, THEN verify total charging flow 60 gpm. _____ Initial NOTEThe following step stops all A Train CCW Flow. 4.4.3 Secure the 1B CCW Pump. _____ Initial 4.4.4IF available, THEN verify open CCW to 1A RHR HX Q1P17MOV3185A. _____ Initial 4.4.5 Open the DC control power switch for Q1R15BKRDG05. _____ Initial 4.4.6 Close SW TO 1B CCW HX Q1P16MOV3130B. _____ Initial NOTEThe following sequence aligns the miscellaneous header to B Train CCW. 4.4.7 Close 1B CCW HX CCW OUTLET ISO, Q1P17V008B. _____ Initial 4.4.8 Open 1C CCW HX CCW OUTLET ISO, Q1P17V008C. _____ Initial 4.4.9 Close CCW SUPPLY HDR XCONN, Q1P17V009C. _____ Initial 4.4.10 Close CCW SUPPLY HDR XCONN, Q1P17V009D. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 152 of 170 APPENDIX 13 ALIGNING A TRAIN CCW TO ALLOW OPERATION OF BOTH SFP COOLING TRAINS DURING CORE OFFLOAD WITH A TRAIN SW OUT OF SERVICE (Page 6 of 6) 4.4.11 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003C. _____ Initial 4.4.12 Close CCW PUMPS DISCH HDR XCONN, Q1P17V003D._____ Initial 4.4.13 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110D. _____ Initial 4.4.14 Close CCW PUMPS SUCT HDR XCONN, Q1P17V110E. _____ Initial 4.4.15 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110C. _____ Initial 4.4.16 Open CCW PUMPS SUCT HDR XCONN, Q1P17V110B. _____ Initial 4.4.17 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003A. _____ Initial 4.4.18 Open CCW PUMPS DISCH HDR XCONN, Q1P17V003B. _____ Initial 4.4.19 Open CCW SUPPLY HDR XCONN, Q1P17V009A. _____ Initial 4.4.20 Open CCW SUPPLY HDR XCONN, Q1P17V009B. _____ Initial 4.4.21 Close DC control power switch for Q1R15BKRDG05. _____ Initial 4.4.21.1 Check the breaker closing spring charged. _____ Initial 4.4.22IF desired, THEN verify CCW alignment with B Train on service by performing a walkthrough of FNP-1-SOP-23.0B, SHIFTING ON SERVICE TRAIN FROM TRAIN A TO TRAIN B, Sections 2.0, 3.0 and 4.0. _____ UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 153 of 170 APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE Performed by: Date Reviewed by: Date This appendix consists of 9 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 154 of 170 APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 1 of 9) 1.0 PURPOSE This appendix provides guidance for aligning the 1B CCW Pump and the 1B CCW Heat Exchanger to the B Train when the 1C CCW Pump and the 1C CCW Heat Exchanger are out of service or unavailable for service. 2.0 PRECAUTIONS AND LIMITATION 2.1Any operations involving manipulation of the 4kV disconnect switches associated shall include visual confirmation of the following: 2.1.1The main contacts are in the required state, open or closed. (One contact per phase.) Refer to figure 1 and 2. 2.1.2The arcing contacts are in the required state, open or closed. (One contact per phase.) Refer to figure 1 and 2. 3.0 INITIAL CONDITIONS 3.1The version of this appendix has been verified to be the current version. (OR 1-98-498) _____ Initial 3.2The appendix has been verified to be the correct unit for the task. (OR 1-98-498) _____ Initial 3.31B CCW Pump and 1B CCW Heat Exchanger are currently aligned to B CCW train. _____ Initial 3.4"B" Train CCW is aligned for service per FNP-1-SOP-23.0A with acceptable line up deviation documented. _____ Initial 3.5The Miscellaneous header is not required to be in service during the performance of this appendix. _____ Initial 3.6The reactor is defueled. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 155 of 170 APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 2 of 9) 4.0 INSTRUCTIONS 4.1IF required, THEN place the 1A CCW Pump in service on B Train as follows: NOTEStep 4.1.1 is performed to minimize the pressure transient which could otherwise result in CCW to Thermal Barrier HX isolation. CAUTIONThe operation of two pumps through one HX is not allowed. 4.1.1IF not previously aligned, THEN open CCW TO 1B RHR HX Q1P17MOV3185B _____ Initial 4.1.2Simultaneously start the Standby 1A CCW Pump AND stop the on service 1B CCW Pump. _____ Initial 4.1.3IF not required for RHR operations, WHEN the system has stabilized, THEN close CCW TO 1B RHR HX, Q1P17MOV3185. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 156 of 170 APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 3 of 9) 4.2 Verify 1C CCW Pump and 1C CCW Heat Exchanger isolated: 4.2.1Verify 1C CCW Pump and heat exchanger is out of service AND isolated by an appropriate tagging order, _____ Initial OR 4.2.2 Perform the following steps: 4.2.2.1 Verify Q1R15BKRDF04, COMPONENT COOLING WATER PUMP 1C 52-DF04 is RACKED OUT. _____ Initial 4.2.2.2 Verify that 1C CCW HX CCW OUTLET ISO, Q1P17V008C is CLOSED. _____ Initial 4.3 Align 1B CCW Pump and 1B CCW Heat Exchanger to A Train as follows: 4.3.1Close CCW SUPPLY HDR XCONN, Q1P17V009A. _____ Initial 4.3.2Close CCW SUPPLY HDR XCONN, Q1P17V009B. _____ Initial 4.3.3Close CCW PUMPS DISCH HDR XCONN, Q1P17V003A. _____ Initial 4.3.4Close CCW PUMPS DISCH HDR XCONN, Q1P17V003B. _____ Initial 4.3.5Open CCW PUMPS SUCT HDR XCONN, Q1P17V110D. _____ Initial 4.3.6Open CCW PUMPS SUCT HDR XCONN, Q1P17V110E. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 157 of 170 APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 4 of 9) 4.3.7Close CCW PUMPS SUCT HDR XCONN, Q1P17V110C. _____ Initial 4.3.8Close CCW PUMPS SUCT HDR XCONN, Q1P17V110B. _____ Initial 4.3.9Open CCW PUMPS DISCH HDR XCONN, Q1P17V003C. _____ Initial 4.3.10Open CCW PUMPS DISCH HDR XCONN, Q1P17V003D. _____ Initial 4.3.11Open CCW SUPPLY HDR XCONN, Q1P17V009C. _____ Initial 4.3.12Open CCW SUPPLY HDR XCONN, Q1P17V009D. _____ Initial 4.3.13Open 1B CCW HX CCW OUTLET ISO, Q1P17V008B _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 158 of 170 APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 5 of 9) 4.4 Align SW to the 1B CCW Heat Exchanger as follows: 4.4.1Close 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002B. _____ Initial 4.4.2Close 1B CCW HX B TRN SW INLET HDR ISO, Q1P16V002A. _____ Initial 4.4.3Close 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008C. _____ Initial 4.4.4Close 1B CCW HX B TRN SW RTN HDR ISO, Q1P16V008B _____ Initial 4.4.5Open 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002C. _____ Initial 4.4.6Open 1B CCW HX A TRN SW INLET HDR ISO, Q1P16V002D. _____ Initial 4.4.7 Open 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008E. _____ Initial 4.4.8Open 1B CCW HX A TRN SW RTN HDR ISO, Q1P16V008D. _____ Initial 4.4.9Verify SW FROM 1B CCW HX Q1P16FV3009B handswitch is in MOD. _____ Initial 4.4.10Verify 1B CCW HX DISCH FCV HIC 3009B is demanding the valve to be fully closed (100% demand). _____ Initial 4.4.11Locally verify SW FROM 1B CCW HX Q1P16FV3009B CLOSED. _____ Initial 4.4.12Open SW TO 1B CCW HX Q1P16MOV3130B. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 159 of 170 APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 6 of9) 4.4.13Throttle open 1B CCW HX DISCH FCV HIC 3009B WHILE throttlingclosed 1C CCW HX DISCH FCV HIC 3009C maintaining existing service water pressure. _____ Initial 4.4.14Verify 1C CCW HX DISCH FCV HIC 3009C fully closed. _____ Initial 4.4.15Close SW TO 1C CCW HX Q1P16MOV3130C. _____ Initial 4.5 Align B CCW Pump to A Train electrically as follows. CAUTIONBreaker Q1R15BKRDG05 has alternate DC control power supplied through fuses in C-HSDP when 1B CCW PUMP LOCAL-REMOTE switch on C-HSDP is in LOCAL. 4.5.1Verify LOCAL-REMOTE switch on C-HSDP for 1B CCW PUMP in REMOTE. _____ Initial 4.5.2Perform the following for breaker Q1R15BKRDG05. 4.5.2.1 Rackout breaker Q1R15BKRDG05. _____ Initial 4.5.2.2 Turn key #RE-14291 in the mechanical interlock on circuit breaker Q1R15BKRDG05. _____ Initial 4.5.2.3 Remove key #RE-14291. _____ Initial 4.5.3Insert key #RE-14291 into the mechanical interlock on 1B CCW pump 4KV disconnect switch 1B (Q1R18A004B-B). _____ Initial 4.5.4Turn Key #RE-14291. Key #RE-14291 is now held in place. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 160 of 170 APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 7 of 9) 4.6 Perform the following for 1B CCW pump 4KV disconnect switch 1B (Q1R18A004B-B). 4.6.1 Open disconnect switch Q1R18A004B-B. _____ Initial 4.6.2 Check the position indicator reads SW OPEN. _____ Initial 4.6.3With the aid of a flashlight, perform the following: 4.6.3.1 Check that a visible air gap exists between the main contacts on all three phases. _____ Initial 4.6.3.2 Check that a visible air gap exists between the arcing contacts on all three phases. _____ Initial 4.6.4Turn key #RE-14224 in its mechanical interlock on 1B disconnect switch. _____ Initial 4.6.5Remove key #RE-14224. 1B disconnect switch is now locked in the open position. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 161 of 170 APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 8 of 9) 4.7 Perform the following for 1B CCW pump 4 KV disconnect switch 1A (Q1R18A004A-A). 4.7.1 Insert key #RE-14224 into its mechanical interlock on 1B CCW pump 4 KV disconnect switch 1A (Q1R18A004A-A). _____ Initial 4.7.2 Turn Key #RE-14224. Key #RE-14224 is now held in place. _____ Initial 4.7.3 Close disconnect switch, Q1R18A004A-A. _____ Initial 4.7.4 Check the position indicator reads SW CLOSED. _____ Initial 4.7.5With the aid of a flashlight, perform the following: 4.7.5.1 Check that NO air gap exists for the main contacts on all three phases. (Contacts closed.) _____ Initial 4.7.5.2 Check that NO air gap exists for the arcing contacts on all three phases. (Contacts closed.) _____ Initial 4.7.6Turn key #RE-14265 in its mechanical interlock AND remove it. 1A disconnect switch is now locked in the closed position. _____ Initial 4.8Insert key #RE-14265 into its mechanical interlock on circuit breaker Q1R15BKRDF05 AND turn key. Key #RE-14265 is now held in place. _____ Initial 4.9Rack circuit breaker Q1R15BKRDF05 to the CONNECTED position. _____ Initial 4.10Close DC control power switch for Q1R15BKRDF05 AND verify breaker spring charges._____ Initial 4.111B CCW Hx and pump are now aligned to A Train, IF desired, THEN place 1B CCW pump and heat exchanger in service. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.2 7/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 162 of 170 APPENDIX 14 ALIGNING B CCW PUMP AND B CCW HX TO A TRAIN WITH C CCW PUMP AND C CCW HX NOT AVAILABLE OR NOT IN SERVICE (Page 9 of 9) NOTES1B CCW Hx and Pump are now aligned to A Train and can be placed in service if required. At a minimum, the 1B CCW Pump should be "bumped" to cycle the breaker for verifying operability following the racking process. 4.12Open CCW TO 1A RHR HX Q1P17MOV3185A. _____ Initial 4.13Start the 1B CCW Pump. _____ Initial 4.14IF not required for RHR operations, THEN close CCW TO 1A RHR HX, Q1P17MOV3185A, WHEN the system has stabilized. _____ Initial 4.15Throttle 1B CCW HX DISCH FCV HIC 3009B as required to control CCW temperature. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 163 of 170

APPENDIX 15

ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1C CCW PUMP

Completed By: Date

SSS Reviewed By: Date This appendix consists of 3 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 164 of 170 APPENDIX 15 ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1C CCW PUMP (Page 1 of 3) 1.0 PURPOSE To enable the 1B CCW Pump to auto start during an ESF actuation, when the 1C CCW Pump is available but not operable. (AI 2009205760) 2.0 PRECAUTIONS AND LIMITATIONS All jumpers must be installed in accordance with NMP-MA-018, Plant Electrical Component Temporary Configuration Control. 3.0 INITIAL CONDITIONS 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498). _____ Initial 3.2This procedure has been verified to be the correct unit for the task (OR 1-98-498). _____ Initial 3.3The 1C CCW Pump has been declared inoperable, but is available for operation. _____ Initial 3.4The electrical distribution system is energized for normal operation per FNP-1-SOP-36.0, PLANT ELECTRICAL DISTRIBUTION LINE-UP, with exceptions noted. _____ Initial 3.5CCW pump room coolers are in service per FNP-1-SOP-58.0, AUXILIARY BUILDING HVAC SYSTEM. _____ Initial 3.6Electrical Maintenance personnel are available to perform the actions required to implement this appendix _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 165 of 170 APPENDIX 15 ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1C CCW PUMP (Page 2 of 3) 4.0 INSTRUCTIONS NOTESPerformance of the following will: Defeat the auto-start functions for 1C CCW Pump from a SI/LOSP signal Defeat the auto-start functions for 1C CCW Pump from an overload trip of the 1B CCW Pump. Cause the 1B CCW Pump to receive an auto-start signal from the A Train SI and LOSP sequencer. Have no effect on the start/stop operation of the 1C or 1B CCW Pumps from the MCB. Have no effect on the load shed circuitry for the 1C or 1B CCW Pumps. Have no effect on HSDP operation for the 1C or 1B CCW Pumps. Have no effect on any CCW Pump room cooler operation. 4.1 Defeat the normal auto-start circuitry and breaker interlock of the 1C CCW Pump by performing the following: 4.1.1In termination cabinet Q1H25L010-A, Panel 1, open link TB2-11. _____ EM _____ CV Initial 4.1.2In termination compartment above 1C CCW PUMP breaker Q1R15BKRDF04, install a jumper between TERMINAL BLOCK SS1-9 and SS1-10 per NMP-MA-018, Plant Electrical Component Temporary Configuration Control. . _____ EM _____ CV Initial 4.1.3Notify the control room of the time the above actions have been completed. _____ EM Time UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 166 of 170 APPENDIX 15 ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1C CCW PUMP (Page 3 of 3) 4.2When requested by the Shift Supervisor to restore the normal auto-start circuitry and breaker interlock for the 1C CCW Pump, perform the following: 4.2.1In termination compartment above 1C CCW PUMP breaker Q1R15BKRDF04, remove the jumper between TERMINAL BLOCK SS1-9 and SS1-10 per NMP-MA-018, Plant Electrical Component Temporary Configuration Control. . _____ EM _____ CV Initial 4.2.2In termination cabinet Q1H25L010-A, Panel 1, close TB2-11. . _____ EM _____ CV Initial 4.2.3Notify the control room of the time the above actions have been completed. _____ EM Time

5.0 REFERENCES

5.1D177183, Sheet 1-ELEMENTARY DIAGRAM COMPONENT COOLING WATER PUMP 1C 5.2D177184, Sheet 1-ELEMENTARY DIAGRAM - COMPONENT COOLING WATER PUMP 1A 5.3D177185, Sheet 1-ELEMENTARY DIAGRAM - COMPONENT COOLING WATER PUMP 1B - TRAIN A 5.4D177187, Sheet 1-ELEMENTARY DIAGRAM - COMPONENT COOLING WATER PUMP 1B - TRAIN "B" 5.5D181509, Sheet 1-CONN DIAG-4160V SWGR BUS 1F COMP DF04 THRU DF06 5.6D181514, Sheet 1-CONN. DIAG.-4160V SWGR. BUS 1G COMPT. DG04, DG05, DG06-Q1R15 A007-B 5.7D181515, Sheet 1-CONNECTION DIAGRAM 4160V SWGR BUS 1G COMPT DG07, DG08, DG09 Q1R15A007-B D181839, Sheet 1-TERMINATION CABINET 31-B FRONT CONNECTION DIAGRAM - Q1H25L031-B UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 167 of 170

APPENDIX 16

ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1A CCW PUMP

Completed By: Date

SSS Reviewed By: Date

This appendix consists of 3 pages UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 168 of 170 APPENDIX 16 ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1A CCW PUMP (Page 1 of 3) 1.0 PURPOSE To enable the 1B CCW Pump to auto start during an ESF actuation, when the 1A CCW Pump is available but not operable. (AI 2009205760) 2.0 PRECAUTIONS AND LIMITATIONS All jumpers must be installed in accordance with NMP-MA-018, Plant Electrical Component Temporary Configuration Control. 3.0 INITIAL CONDITIONS 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498). _____ Initial 3.2This procedure has been verified to be the correct unit for the task. (OR 1-98-498). _____ Initial 3.3The 1A CCW Pump has been declared inoperable, but is available for operation. _____ Initial 3.4The electrical distribution system is energized for normal operation per FNP-1-SOP-36.0, PLANT ELECTRICAL DISTRIBUTION LINE-UP, with exceptions noted. _____ Initial 3.5CCW pump room coolers are in service per FNP-1-SOP-58.0, AUXILIARY BUILDING HVAC SYSTEM. _____ Initial 3.6Electrical Maintenance personnel are available to perform the actions required to implement this appendix. _____ Initial UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 169 of 170 APPENDIX 16 ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1A CCW PUMP (Page 2 of 3) 4.0 INSTRUCTIONS NOTESPerformance of the following will: Defeat the auto-start functions for 1A CCW Pump from a SI/LOSP signal Defeat the auto-start functions for 1A CCW Pump from an overload trip of the 1B CCW Pump. Cause the 1B CCW Pump to receive an auto-start signal from the B Train SI and LOSP sequencer. Have no effect on the start/stop operation of the 1B or 1A CCW Pumps from the MCB. Have no effect on the load shed circuitry for the 1B or 1A CCW Pumps. Have no effect on HSDP operation for the 1B or 1A CCW Pumps. Have no effect on any CCW Pump room cooler operation. 4.1 Defeat the normal auto-start circuitry and breaker interlock of the 1A CCW Pump by performing the following: 4.1.1In termination cabinet Q1H25L031-B, Panel 1, open link TB2-22. _____ EM _____ CV Initial 4.1.2In termination compartment above 1A CCW PUMP breaker Q1R15BKRDG04, install a jumper between TERMINAL BLOCK SS1-9 and SS1-10 per NMP-MA-018, Plant Electrical Component Temporary Configuration Control. _____ EM _____ CV Initial 4.1.3 Notify the control room of the time the above actions have been completed. _____ EM Time UNIT 1 Farley Nuclear Plant Procedure Number VerFNP-1-SOP-23.0 94.27/17/2014 09:52:05 COMPONENT COOLING WATER SYSTEMPage Number 170 of 170 APPENDIX 16 ENABLING THE 1B CCW PUMP TO AUTO-START FOR 1A CCW PUMP (Page 3 of 3) 4.2When requested by the Shift Supervisor to restore the normal auto-start circuitry and breaker interlock for the 1A CCW Pump, perform the following: 4.2.1In termination compartment above 1A CCW PUMP breaker Q1R15BKRDG04, remove the jumper between TERMINAL BLOCK SS1-9 and SS1-10 per NMP-MA-018, Plant Electrical Component Temporary Configuration Control. _____ EM _____ Initial 4.2.2In termination cabinet Q1H25L031-B, Panel 1, close link TB2-22 _____ EM _____ Initial 4.2.3 Notify the control room of the time the above actions have been completed. _____ EM Time

5.0 REFERENCES

5.1D177183, Sheet 1-ELEMENTARY DIAGRAM COMPONENT COOLING WATER PUMP 1C 5.2D177184, Sheet 1-ELEMENTARY DIAGRAM - COMPONENT COOLING WATER PUMP 1A 5.3D177185, Sheet 1-ELEMENTARY DIAGRAM - COMPONENT COOLING WATER PUMP 1B - TRAIN "A" 5.4D177187, Sheet 1-ELEMENTARY DIAGRAM - COMPONENT COOLING WATER PUMP 1B - TRAIN "B" 5.5D181509, Sheet 1-CONN DIAG-4160V SWGR BUS 1F COMP DF04 THRU DF06 5.6D181514, Sheet 1-CONN. DIAG.-4160V SWGR. BUS 1G COMPT. DG04, DG05, DG06-Q1R15 A007-B 5.7D181515, Sheet 1-CONNECTION DIAGRAM 4160V SWGR BUS 1G COMPT DG07, DG08, DG09 Q1R15A007-B 5.8D181839, Sheet 1-TERMINATION CABINET 31-B FRONT CONNECTION DIAGRAM - Q1H25L031-B UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 2 Version 56.0 Version 56.0 FARLEY NUCLEAR PLANT ANNUNCIATOR RESPONSE PROCEDURE FNP-1-ARP-1.1 S A F E T Y MAIN CONTROL BOARD ANNUNCIATOR PANEL A R E L A T E D PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: ALL, Except AF2 & AF3

Reference:

AF2 Information: AF3 Approved: David L Reed Effective Date: 06/24/2015 Operations UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 2 of 2 Version 56.0 TABLE OF CONTENTS Procedure Contains Number of Pages Annunciator Window Panel ......................1 AA1 ...........................................................1 AA2 ...........................................................1 AA3 ...........................................................1 AA4 ...........................................................5 AA5 ...........................................................4 AB1 ...........................................................1 AB2 ...........................................................1 AB3 ...........................................................1 AB4 ...........................................................5 AB5 ...........................................................4 AC4 ...........................................................1 AC5 ...........................................................1 AD1 ...........................................................2 AD2 ...........................................................5 AD3 ...........................................................5 AD4 ...........................................................1 AD5 ...........................................................1 AE1 ...........................................................2 AE2 ...........................................................1 AE3 ...........................................................1 AE4 ...........................................................1 AE5 ...........................................................1 AF1 ...........................................................1 AF2 ...........................................................1 AF3 ...........................................................1 AF4 ...........................................................2 AF5 ...........................................................1 AG1 ...........................................................1 AG2 ...........................................................1 AG3 ...........................................................1 AG4 ...........................................................1 AG5 ...........................................................1 AH1 ...........................................................1 AH2 ...........................................................1 AH3 ...........................................................1 AH4 ...........................................................1 AH5 ...........................................................1 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 3 of 2 Version 56.0 VERSION SUMMARY Version 56.0 DESCRIPTION CR 10047345 - AG3, AH3 added NOTE to OA section CR 10073778 - removed Step 3, this step covered under actions of AOP-7.0 (entry at Step 2) and/or actions of LJ3 Records No records are generated by this procedure UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 MAIN CONTROL BOARD PANEL A A1 B1 D1 E1 F1 G1 H1 1A 1A RW PUMP RM RW PUMP RM SEL SWITCH RIVER LVL RIVER LVL CCW PUMP CCW A TRN B TRN IN A TRN B TRN OVERLOAD RM CLR DELETED FLOODING FLOODING LOCAL CONT HI HI TRIP FAULT A2 B2 D2 E2 F2 G2 H2 1B 1B RW RW RWIS RIVER LVL RIVER LVL CCW PUMP CCW DELETED PRESS PUMP ALARM A TRN B TRN OVERLOAD RM CLR A TRN TRIPPED LO LO TRIP FAULT LO A3 B3 D3 E3 F3 G3 H3 1C CCW RW SWIS SWIS SW SW CCW PUMP PUMP DELETED PRESS FLOODING ALARM POND LVL POND LVL OVERLOAD IN B TRN A TRN B TRN TRIP LOCAL CONT LO LO LO A4 B4 C4 D4 E4 F4 G4 H4 CCW SRG CCW SRG CCW SW SW CTMT CLR SW SW TK LVL TK LVL PUMP RM PRESS PUMP SW FLOW WET PIT LVL WET PIT LVL A TRN B TRN FLOODING A TRN TRIPPED HI-LO A TRN B TRN HI-LO HI-LO LVL 10 IN LO LO LO A5 B5 C5 D5 E5 SW F5 G5 H5 CCW SRG CCW SRG CCW SW TO AUX BLDG SW TO DILUTION MIMS TK LVL TK LVL PUMP RM PRESS HDR PRESS TURB BLDG DISCH ALARM A TRN B TRN FLOODING B TRN A OR B TRN A OR B TRN TEMP LO-LO LO-LO LVL 18 IN LO LO FLOW HI HI UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AA1 SETPOINT: Variable Current/Time A1 1A ORIGIN: 1. 0/1, 0/2, or 0/3 Overcurrent CCW PUMP Relay (50/51 - DG04). OVERLOAD 2. Ground Relay (50G-DG04). TRIP PROBABLE CAUSE 1. 1A CCW Pump overloaded. 2. 1A CCW Pump electrical or mechanical fault. AUTOMATIC ACTION 1. Trips breaker DG04 for 1A CCW Pump. 2. Closes breaker DG05 to start 1B CCW Pump, if 1B CCW Pump is aligned to B Train. OPERATOR ACTION 1. Check 1A CCW Pump has tripped. 2. Verify standby pump running, if aligned to affected train. 3. Perform the actions required by FNP-1-AOP-9.0, LOSS OF COMPONENT COOLING WATER. 4. IF 1B CCW Pump is aligned to B Train, THEN rack out 1A CCW Pump supply breaker Q1R15BKRDG04. 5. Refer to Technical Specification 3.7.7 for LCO requirements with a loss of the on service train of component cooling water.

References:

D-177184; D-177187; A-177048, Sh. 269; A-177100, Sh. 51;B-175810, Sh. 22; Technical Specification 3.7.7 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AA2 SETPOINT: Variable Current/Time A2 1B ORIGIN: 1. 0/1, 0/2, or 0/3 Overcurrent CCW PUMP Relay (50/51 - DF05). OVERLOAD 2. Ground Relay (50G-DF05). TRIP 1. 0/1, 0/2, or 0/3 Overcurrent Relay (50/51 - DG05). 2. Ground Relay (50G-DG05). PROBABLE CAUSE 1. 1B CCW Pump overloaded. 2. 1B CCW Pump electrical or mechanical fault. AUTOMATIC ACTION 1B CCW Pump aligned to A(B) Train.

1. Trips breaker DF05 (DG05) for 1B CCW Pump. 2. Closes breaker DF04 (DG04) to start 1C(1A) CCW Pump. OPERATOR ACTION 1. Check 1B CCW PUMP has tripped. 2. Verify standby pump running, if aligned to affected train. 3. Perform the actions required by FNP-1-AOP-9.0, LOSS OF COMPONENT COOLING WATER. 4. Refer to Technical Specification 3.7.7 for LCO requirements with a loss of the on service train of component cooling water.

References:

D-177183; D-177184; D-177185; D-177187; A-177048, Sh. 256; A-177048, Sh. 270; A-177100, Sh. 52; B-175810, Sh. 23; Technical Specification 3.7.7 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AA3 SETPOINT: Variable Current/Time A3 1C ORIGIN: 1. 0/1, 0/2, or 0/3 Overcurrent CCW PUMP Relay (50/51 - DF04). OVERLOAD 2. Ground Relay (50G-DF04). TRIP PROBABLE CAUSE 1. 1C CCW Pump overloaded. 2. 1C CCW Pump electrical or mechanical fault. AUTOMATIC ACTION 1. Trips breaker DF04 for 1C CCW Pump. 2. Closes breaker DF05 to start 1B CCW Pump, if 1B CCW Pump is aligned to A Train. OPERATOR ACTION 1. Check 1C CCW PUMP has tripped. 2. Verify standby pump running, if aligned to affected train. 3. Perform the actions required by FNP-1-AOP-9.0, LOSS OF COMPONENT COOLING WATER. 4. IF 1B CCW Pump is aligned to A Train, THEN rack out 1C CCW Pump supply breaker Q1R15BKRDF04. 5. Refer to Technical Specification 3.7.7 for LCO requirements with a loss of the on service train of component cooling water.

References:

D-177183; D-177185; A-177048, Sh. 255; B-175810, Sh. 22; A-177100, Sh. 53; Technical Specification 3.7.7 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 5 Version 56.0 LOCATION AA4 SETPOINT: 1. HI: 50 +/- 0.3 inches A4 2. LO: 35 +/- 0.3 inches CCW SRG TK LVL A TRN HI-LO ORIGIN: 1. Level Switch (N1P17LSH3027A-A). 2. Level Switch (N1P17LSL3027A-A). PROBABLE CAUSE

1. HI - In Leakage of Reactor Coolant, Service Water, or through a Makeup Water Valve Letdown heat exchanger (if letdown on service) RCP thermal barriers RHR heat exchanger (if on service) Reactor makeup system (if normally closed, valves leaking by) Demineralized water system (if normally closed, valves leaking by) SW system (if SW discharge pressure higher than CCW discharge pressure) RCDT heat exchanger (if at least one RCDT pump running

2. LO - Rupture or Leakage of A Train CCW components or piping: Spent fuel pool heat exchanger Charging pump oil coolers RHR heat exchanger (if normally closed, MOV 3185 A or B are open) RCP oil coolers Excess letdown heat exchanger (if excess letdown secured) Sample coolers (if sampling not in progress) Seal water heat exchanger Evaporator packages Hydrogen recombiner Waste gas compressors Floor drain tank via CCW relief valves SW system if CCW discharge pressure is higher than SW discharge pressure Primary and secondary sample coolers (if sampling in progress) GFFD sampling assembly UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 2 of 5 Version 56.0 LOCATION AA4 AUTOMATIC ACTION NONE OPERATOR ACTION 1. Check A Train CCW SURGE TANK level indication and determine whether level is HIGH or LOW. 2. Dispatch personnel to locate and isolate the source of leakage.

3. IF CCW Surge Tank level is LOW, THEN perform the following:

3.1 Attempt to fill CCW surge tank using Normal Make-up to maintain level above the lo level alarm point as follows; 3.1.1 Notify Shift Chemist that the CCW surge tank is to be made up to. 3.1.2 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 3.1.3 Monitor CCW surge tank level indications. LI-3027A LI-3027B 3.1.4 Maintain level between 35 inches and 50 inches. 3.1.5 IF desired, THEN open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A to add makeup to A portion of CCW surge tank. 3.1.6 IF desired, THEN open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B to add makeup to B portion of CCW surge tank. 3.1.7 WHEN makeup addition is completed, THEN close appropriate valve(s). MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A. MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 3 of 5 Version 56.0 LOCATION AA4 3.2 IF unable to fill the CCW Surge Tank per the Normal Make-up method, THEN attempt to fill CCW surge tank using Emergency Make-up to maintain level above the lo level alarm point as follows; CAUTION: Reactor makeup water should only be used as an emergency source of makeup water to the CCW surge tank. 3.2.1 Close CCW SRG TK DEMIN INLET ISO, N1P11V045. 3.2.2 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 3.2.3 Monitor CCW surge tank level indications. LI-3027A LI-3027B 3.2.4 Maintain level between 35 inches and 50 inches. 3.2.5 IF desired, THEN open MKUP TO CCW FROM RMW Q1P17MOV3031A to add makeup to the A portion of the CCW surge tank. 3.2.6 IF desired, THEN open MKUP TO CCW FROM RMW Q1P17MOV3031B to add makeup to the B portion of the CCW surge tank. 3.2.7 WHEN makeup addition is completed, THEN close appropriate valve(s). MKUP TO CCW FROM RMW Q1P17MOV3031A MKUP TO CCW FROM RMW Q1P17MOV3031B 3.2.8 Open CCW SRG TK DEMIN INLET ISO, N1P11V045.

UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 4 of 5 Version 56.0 LOCATION AA4 3.3 IF there is a CCW leak affecting the off-service train, perform the following to reduce CCW pressure: 3.3.1 IF the off-service train CHG pump is running, swap running CHG pumps per FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION. 3.3.2 IF the off-service train RHR pump is running, perform the following: 3.3.2.1 IF RHR cooldown operation is required, verify the on-service train RHR pump is running in cooldown operation per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM. 3.3.2.2 Secure the off-service train RHR pump per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM. 3.3.3 Ensure the SFP cooling loop is aligned to the on-service train per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 3.3.4 Secure the off-service CCW train per FNP-1-SOP-23.0, COMPONENT COOLING WATER SYSTEM. 3.4 Control SW pressure to minimize DP across CCW HX tubes: HIC 3009A 1A CCW HX DISCH FCV HIC 3009B 1B CCW HX DISCH FCV HIC 3009C 1C CCW HX DISCH FCV Q1P16V558 A TRN SW DIL BYP ISO Q1P16V557 B TRN SW DIL BYP ISO NOTE: If CCW to SW leakage is suspected, expeditious actions, consistent with safe plant operation, to secure the pump in the leaking CCW train should be taken. This will minimize environmental release of chromated and potentially radioactive water. 3.5 IF CCW HX tube leak suspected, THEN notify the following groups to assess the environmental impacts, notification requirements and corrective actions for potential chromated water and radiological contamination of the service water system: Chemistry Environmental Health Physics UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 5 of 5 Version 56.0 LOCATION AA4 4. IF CCW Surge Tank level is HIGH, THEN perform the following: 4.1 Determine source of in-leakage and isolate if possible. 4.2 Check Radiation Monitors R-17A and R-17B for increasing count rates. 4.3 Verify the following make up valves are closed. MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B MKUP TO CCW FROM RMW Q1P17MOV3031A MKUP TO CCW FROM RMW Q1P17MOV3031B 4.4 IF desired, THEN close CCW SRG TK DEMIN INLET ISO N1P11V045. 4.5 Commence lowering the CCW Surge Tank level per FNP-1-SOP-23.0, COMPONENT COOLING WATER SYSTEM. 4.6 IF CCW Surge Tank level raise is due to RCS leakage, THEN refer to FNP-1-AOP-1.0, RCS LEAKAGE. 4.7 IF CCW Surge Tank level raise is due to Letdown Heat Exchanger leakage, THEN isolate letdown per FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION AND refer to FNP-1-AOP-16.0, LOSS OF LETDOWN. 5. IF a loss of CCW cooling has occurred, THEN refer to FNP-1-AOP-9.0, LOSS OF COMPONENT COOLING WATER. 6. Refer to Technical Specification 3.7.7 for LCO requirements with a loss of the on service train of component cooling water.

References:

A-177100, Sh. 54; B-175810, Sh. 101; B-175968; D-175002, Sh. 1; D-177183; Technical Specification 3.7.7; NEL 98-0327 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 4 Version 56.0 LOCATION AA5 SETPOINT: 20 .15" A5 CCW SRG ORIGIN: Level Switch (Q1P17LSLL3027CA-A) TK LVL A TRN LO-LO PROBABLE CAUSE Rupture or leakage of an A Train CCW component or pipe. AUTOMATIC ACTION 1. Closes CCW Valves (Q1P17HV3096A&B) to isolate CCW to/from Evaporator Packages and H2 Recombiners. (Q1P17LSLL3027CD-A)

2. Trips closed Q1P17HV2229, CCW to Sample Cooler (Q1P17LSLL3027CD-A). OPERATOR ACTION 1. Ensure that the automatic actions have occurred. 2. Dispatch personnel to locate and isolate the source of leakage. 3. Notify chemistry to secure the sample system. (2008108346) 4. Perform the following: 4.1 Attempt to fill CCW surge tank using Normal Make-up to maintain level above the lo level alarm point as follows; 4.1.1 Notify Shift Chemist that the CCW surge tank is to be made up to. 4.1.2 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 4.1.3 Monitor CCW surge tank level indications. LI-3027A LI-3027B UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 2 of 4 Version 56.0 LOCATION AA5 4.1.4 Maintain level between 35 inches and 50 inches. 4.1.5 IF desired, THEN open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A to add makeup to A portion of CCW surge tank. 4.1.6 IF desired, THEN open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B to add makeup to B portion of CCW surge tank. 4.1.7 WHEN makeup addition is completed, THEN close appropriate valve(s). MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A. MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B. 4.2 IF unable to fill the CCW Surge Tank per the Normal Make-up method, THEN attempt to fill CCW surge tank using Emergency Make-up to maintain level above the lo level alarm point as follows; CAUTION: Reactor makeup water should only be used as an emergency source of makeup water to the CCW surge tank. 4.2.1 Close CCW SRG TK DEMIN INLET ISO, N1P11V045. 4.2.2 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 4.2.3 Monitor CCW surge tank level indications. LI-3027A LI-3027B 4.2.4 Maintain level between 35 inches and 50 inches. 4.2.5 IF desired, THEN open MKUP TO CCW FROM RMW Q1P17MOV3031A to add makeup to the A portion of the CCW surge tank.

UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 3 of 4 Version 56.0 LOCATION AA5 4.2.6 IF desired, THEN open MKUP TO CCW FROM RMW Q1P17MOV3031B to add makeup to the B portion of the CCW surge tank. 4.2.7 WHEN makeup addition is completed, THEN close appropriate valve(s). MKUP TO CCW FROM RMW Q1P17MOV3031A MKUP TO CCW FROM RMW Q1P17MOV3031B 4.2.8 Open CCW SRG TK DEMIN INLET ISO, N1P11V045. 4.3 IF there is a CCW leak affecting the off-service train, perform the following to reduce CCW pressure: 4.3.1 IF the off-service train CHG pump is running, swap running CHG pumps per FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION. 4.3.2 IF the off-service train RHR pump is running, perform the following: 4.3.2.1 IF RHR cooldown operation is required, verify the on-service train RHR pump is running in cooldown operation per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM. 4.3.2.2 Secure the off-service train RHR pump per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM. 4.3.3 Ensure the SFP cooling loop is aligned to the on-service train per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 4.3.4 Secure the off-service CCW train per FNP-1-SOP-23.0, COMPONENT COOLING WATER SYSTEM. 4.4 Control SW pressure to minimize DP across CCW HX tubes: HIC 3009A 1A CCW HX DISCH FCV HIC 3009B 1B CCW HX DISCH FCV HIC 3009C 1C CCW HX DISCH FCV Q1P16V558 A TRN SW DIL BYP ISO Q1P16V557 B TRN SW DIL BYP ISO UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 4 of 4 Version 56.0 LOCATION AA5 NOTE: If CCW to SW leakage is suspected, expeditious actions, consistent with safe plant operation, to secure the pump in the leaking CCW train should be taken. This will minimize environmental release of chromated and potentially radioactive water. 4.5 IF CCW HX tube leak suspected, THEN notify the following groups to assess the environmental impacts, notification requirements and corrective actions for potential chromated water and radiological contamination of the service water system: Chemistry Environmental Health Physics 5. IF a loss of CCW cooling has occurred, THEN refer FNP-1-AOP-9.0, LOSS OF COMPONENT COOLING WATER. 6. Refer to Technical Specification 3.7.7 for LCO requirements with a loss of the on service train of component cooling water.

References A-177100, Sh. 55; D-175002, Sh. 1 & 2; B-175968, Sh. 6; D-177183; D-277185; D-177092; D-177670; D-177853; B-175810, Sh. 9, 22, 23 & 101; Technical Specification 3.7.7; PCN B91-1-7431 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AB1 SETPOINT: 1. Diff. Pressure: 1.5 + 0.25" H20 B1 - 0.0 1A 2. Overload: Variable Current/Time CCW RM CLR ORIGIN: 1. Differential pressure switch FAULT (N1E16PDSL3302A-N) 2. Thermal Overload Aux. Relay (49x) PROBABLE CAUSE 1. Low differential pressure across fan 10 sec. after fan started. 2. Fan tripped on overload. AUTOMATIC ACTION NONE

OPERATOR ACTION 1. Start 1B CCW PUMP ROOM COOLER FAN. 2. Notify appropriate personnel to determine and correct the cause of the problem. 3. Refer to FNP-1-SOP-58.0, AUXILIARY BUILDING HVAC SYSTEM, for guidance on removal of room coolers from service, based on the evaluations performed. 4. Refer to Technical Specification 3.7.7 for LCO requirements

References:

A-177100, Sh. 56; B-175968, Sh. 7; D-177243; D-177183; D-177185; B-175810, Sh. 95; Technical Specification 3.7.19 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AB2 SETPOINT: 1. Diff. Pressure: 1.0 + 0.1" H20 B2 - 0.1 1B 2. Overload: Variable Current/Time CCW RM CLR ORIGIN: 1. Differential pressure switch FAULT (N1E16PDSL3302B-N) 2. Thermal Overload Aux. Relay (49x)

PROBABLE CAUSE

1. Low differential pressure across fan 10 sec. after fan started. 2. Fan tripped on overload.

AUTOMATIC ACTION NONE

OPERATOR ACTION

1. Start 1A CCW PUMP ROOM COOLER FAN. 2. Notify appropriate personnel to determine and correct the cause of the problem. 3. Refer to FNP-1-SOP-58.0, AUXILIARY BUILDING HVAC SYSTEM, for guidance on removal of room coolers from service, based on the evaluations performed. 4. Refer to Technical Specification 3.7.7 for LCO requirements.

References:

A-177100, Sh. 57; B-175968, Sh. 7; D-177243; D-177184; D-177187; B-175810, Sh. 95; Technical Specification 3.7.19 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AB3 SETPOINT: Not Applicable B3 CCW ORIGIN: 1. 1C CCW Pump Selector Switch PUMP 2. 1B CCW Pump (A Train) Selector Switch IN 3. 1B CCW Pump (B Train) Selector Switch LOCAL CONT 4. 1A CCW Pump Selector Switch PROBABLE CAUSE Selector Switch at Hot Shutdown Panel for 1A, 1B or 1C CCW Pump in Local position.

AUTOMATIC ACTION NONE

OPERATOR ACTION

1. No action is necessary if alarm is due to preplanned operational or maintenance activities; otherwise send appropriate personnel to determine the cause of the alarm. 2. Return Selector Switch to remote position as soon as possible.

References:

D-177183; D-177184; D-177185; D-177187; A-177100, Sh. 58; B-175810, Sh. 101 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 5 Version 56.0 LOCATION AB4 SETPOINT: 1. HI: 50 +/- 0.3 inches B4 2. LO: 35 +/- 0.3 inches CCW SRG TK LVL B TRN HI-LO ORIGIN: 1. Level Switch (N1P17LSH3027B-B). 2. Level Switch (N1P17LSL3027B-B). PROBABLE CAUSE 1. HI - In Leakage of Reactor Coolant, Service Water, or through a Makeup Water Valve Letdown heat exchanger (if letdown on service) RCP thermal barriers RHR heat exchanger (if on service) Reactor makeup system (if normally closed, valves leaking by) Demineralized water system (if normally closed, valves leaking by) SW system (if SW discharge pressure higher than CCW discharge pressure) RCDT heat exchanger (if at least one RCDT pump running

2. LO - Rupture or Leakage of a B Train CCW components or piping: Spent fuel pool heat exchanger Charging pump oil coolers RHR heat exchanger (if normally closed, MOV 3185 A or B are open) RCP oil coolers Excess letdown heat exchanger (if excess letdown secured) Sample coolers (if sampling not in progress) Seal water heat exchanger Evaporator packages Hydrogen recombiner Waste gas compressors Floor drain tank via CCW relief valves SW system if CCW discharge pressure is higher than SW discharge pressure Primary and secondary sample coolers (if sampling in progress) GFFD sampling assembly UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 2 of 5 Version 56.0 LOCATION AB4 AUTOMATIC ACTION NONE OPERATOR ACTION 1. Check B Train CCW SURGE TANK level indication and determine whether level is HIGH or LOW. 2. Dispatch personnel to locate and isolate the source of leakage.

3. IF CCW Surge Tank level is LOW, THEN perform the following:

3.1 Attempt to fill CCW surge tank using Normal Make-up to maintain level above the lo level alarm point as follows; 3.1.1 Notify Shift Chemist that the CCW surge tank is to be made up to. 3.1.2 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 3.1.3 Monitor CCW surge tank level indications. LI-3027A LI-3027B 3.1.4 Maintain level between 35 inches and 50 inches. 3.1.5 IF desired, THEN open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A to add makeup to A portion of CCW surge tank. 3.1.6 IF desired, THEN open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B to add makeup to B portion of CCW surge tank. 3.1.7 WHEN makeup addition is completed, THEN close appropriate valve(s). MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A. MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 3 of 5 Version 56.0 LOCATION AB4 3.2 IF unable to fill the CCW Surge Tank per the Normal Make-up method, THEN attempt to fill CCW surge tank using Emergency Make-up to maintain level above the lo level alarm point as follows; CAUTION: Reactor makeup water should only be used as an emergency source of makeup water to the CCW surge tank. 3.2.1 Close CCW SRG TK DEMIN INLET ISO, N1P11V045. 3.2.2 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 3.2.3 Monitor CCW surge tank level indications. LI-3027A LI-3027B 3.2.4 Maintain level between 35 inches and 50 inches. 3.2.5 IF desired, THEN open MKUP TO CCW FROM RMW Q1P17MOV3031A to add makeup to the A portion of the CCW surge tank. 3.2.6 IF desired, THEN open MKUP TO CCW FROM RMW Q1P17MOV3031B to add makeup to the B portion of the CCW surge tank. 3.2.7 WHEN makeup addition is completed, THEN close appropriate valve(s). MKUP TO CCW FROM RMW Q1P17MOV3031A MKUP TO CCW FROM RMW Q1P17MOV3031B 3.2.8 Open CCW SRG TK DEMIN INLET ISO, N1P11V045. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 4 of 5 Version 56.0 LOCATION AB4 3.3 IF there is a CCW leak affecting the off-service train, perform the following to reduce CCW pressure: 3.3.1 IF the off-service train CHG pump is running, swap running CHG pumps per FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION. 3.3.2 IF the off-service train RHR pump is running, perform the following: 3.3.2.1 IF RHR cooldown operation is required, verify the on-service train RHR pump is running in cooldown operation per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM. 3.3.2.2 Secure the off-service train RHR pump per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM. 3.3.3 Ensure the SFP cooling loop is aligned to the on-service train per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 3.3.4 Secure the off-service CCW train per FNP-1-SOP-23.0, COMPONENT COOLING WATER SYSTEM. 3.4 Control SW pressure to minimize DP across CCW HX tubes: HIC 3009A 1A CCW HX DISCH FCV HIC 3009B 1B CCW HX DISCH FCV HIC 3009C 1C CCW HX DISCH FCV Q1P16V558 A TRN SW DIL BYP ISO Q1P16V557 B TRN SW DIL BYP ISO NOTE: If CCW to SW leakage is suspected, expeditious actions, consistent with safe plant operation, to secure the pump in the leaking CCW train should be taken. This will minimize environmental release of chromated and potentially radioactive water. 3.5 IF CCW HX tube leak suspected, THEN notify the following groups to assess the environmental impacts, notification requirements and corrective actions for potential chromated water and radiological contamination of the service water system: Chemistry Environmental Health Physics UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 5 of 5 Version 56.0 LOCATION AB4

4. IF CCW Surge Tank level is HIGH, THEN perform the following: 4.1 Determine source of in-leakage and isolate if possible. 4.2 Check Radiation Monitors R-17A and R-17B for increasing count rates.

4.3 Verify the following make up valves are closed. MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B MKUP TO CCW FROM RMW Q1P17MOV3031A MKUP TO CCW FROM RMW Q1P17MOV3031B 4.4 IF desired, THEN close CCW SRG TK DEMIN INLET ISO N1P11V045. 4.5 Commence lowering the CCW Surge Tank level per FNP-1-SOP-23.0, COMPONENT COOLING WATER SYSTEM. 4.6 IF CCW Surge Tank level raise is due to RCS leakage, THEN refer to FNP-1-AOP-1.0, RCS LEAKAGE. 4.7 IF CCW Surge Tank level raise is due to Letdown Heat Exchanger leakage, THEN isolate letdown per FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION AND refer to FNP-1-AOP-16.0, LOSS OF LETDOWN. 5. IF a loss of CCW cooling has occurred, THEN refer to FNP-1-AOP-9.0, LOSS OF COMPONENT COOLING WATER. 6. Refer to Technical Specification 3.7.7 for LCO requirements with a loss of the on service train of component cooling water.

References:

A-177100, Sh. 59; B-175810, Sh. 101; B-175968, Sh. 6; D-175002, Sh. 1; D-177184; Technical Specification 3.7.7; NEL 98-0327 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 4 Version 56.0 LOCATION AB5 SETPOINT: 20 .15" B5 CCW SRG ORIGIN: Level Switch (Q1P17LSLL3027DA-B). TK LVL B TRN LO-LO PROBABLE CAUSE Rupture or leakage of a B Train CCW component or pipe. AUTOMATIC ACTION 1. Closes CCW Valves (Q1P17HV3096A&B) to isolate CCW to/from Evaporator Packages & H2 Recombiners. (Q1P17LSLL3027DD-B) 2. Trips closed Q1P17HV2229, CCW to Sample Cooler (Q1P17LSLL3027DD-B). OPERATOR ACTION 1. Ensure that the automatic actions have occurred. 2. Dispatch personnel to locate and isolate the source of leakage. 3. Notify chemistry to secure the sample system. (2008108346) 4. Perform the following: 4.1 Attempt to fill CCW surge tank using Normal Make-up to maintain level above the lo level alarm point as follows; 4.1.1 Notify Shift Chemist that the CCW surge tank is to be made up to. 4.1.2 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 4.1.3 Monitor CCW surge tank level indications. LI-3027A LI-3027B UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 2 of 4 Version 56.0 LOCATION AB5 4.1.4 Maintain level between 35 inches and 50 inches. 4.1.5 IF desired, THEN open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A to add makeup to A portion of CCW surge tank. 4.1.6 IF desired, THEN open MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B to add makeup to B portion of CCW surge tank. 4.1.7 WHEN makeup addition is completed, THEN close appropriate valve(s). MKUP TO CCW FROM DW STOR TK Q1P17MOV3030A. MKUP TO CCW FROM DW STOR TK Q1P17MOV3030B. 4.2 IF unable to fill the CCW Surge Tank per the Normal Make-up method, THEN attempt to fill CCW surge tank using Emergency Make-up to maintain level above the lo level alarm point as follows; CAUTION: Reactor makeup water should only be used as an emergency source of makeup water to the CCW surge tank. 4.2.1 Close CCW SRG TK DEMIN INLET ISO, N1P11V045. 4.2.2 Verify open CCW SRG TK VT valves: (MCB) Q1P17SV3028A Q1P17SV3028B 4.2.3 Monitor CCW surge tank level indications. LI-3027A LI-3027B 4.2.4 Maintain level between 35 inches and 50 inches. 4.2.5 IF desired, THEN open MKUP TO CCW FROM RMW Q1P17MOV3031A to add makeup to the A portion of the CCW surge tank. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 3 of 4 Version 56.0 LOCATION AB5 4.2.6 IF desired, THEN open MKUP TO CCW FROM RMW Q1P17MOV3031B to add makeup to the B portion of the CCW surge tank. 4.2.7 WHEN makeup addition is completed, THEN close appropriate valve(s). MKUP TO CCW FROM RMW Q1P17MOV3031A MKUP TO CCW FROM RMW Q1P17MOV3031B 4.2.8 Open CCW SRG TK DEMIN INLET ISO, N1P11V045. 4.3 IF there is a CCW leak affecting the off-service train, perform the following to reduce CCW pressure: 4.3.1 IF the off-service train CHG pump is running, swap running CHG pumps per FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION. 4.3.2 IF the off-service train RHR pump is running, perform the following: 4.3.2.1 IF RHR cooldown operation is required, verify the on-service train RHR pump is running in cooldown operation per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM. 4.3.2.2 Secure the off-service train RHR pump per FNP-1-SOP-7.0, RESIDUAL HEAT REMOVAL SYSTEM. 4.3.3 Ensure the SFP cooling loop is aligned to the on-service train per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 4.3.4 Secure the off-service CCW train per FNP-1-SOP-23.0, COMPONENT COOLING WATER SYSTEM. 4.4 Control SW pressure to minimize DP across CCW HX tubes: HIC 3009A 1A CCW HX DISCH FCV HIC 3009B 1B CCW HX DISCH FCV HIC 3009C 1C CCW HX DISCH FCV Q1P16V558 A TRN SW DIL BYP ISO Q1P16V557 B TRN SW DIL BYP ISO UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 4 of 4 Version 56.0 LOCATION AB5 NOTE: If CCW to SW leakage is suspected, expeditious actions, consistent with safe plant operation, to secure the pump in the leaking CCW train should be taken. This will minimize environmental release of chromated and potentially radioactive water. 4.5 IF CCW HX tube leak suspected, THEN notify the following groups to assess the environmental impacts, notification requirements and corrective actions for potential chromated water and radiological contamination of the service water system: Chemistry Environmental Health Physics

5. IF a loss of CCW cooling has occurred, THEN refer FNP-1-AOP-9.0, LOSS OF COMPONENT COOLING WATER. 6. Refer to Technical Specification 3.7.7 for LCO requirements with a loss of the on service train of component cooling water

References:

A-177100, Sh. 60; D-175002, Sh. 1 & 2; B-175968, Sh. 6; D-177183; D-277185; D-177092; D-177670; D-177853; B-175810, Sh. 9, 22, 23 & 101; Technical Specification 3.7.7; PCN B91-1-7431 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AC4 SETPOINT: 10 1 inches C4 CCW ORIGIN: 1. Level Switch (N1P16LSH3084A-N). PUMP RM 2. Level Switch (N1P16LSH3084B-N). FLOODING LVL 10 IN NOTE: Receipt of this alarm in conjunction with other alarms may indicate CCW pump room flooding from a source other than the service water system and should be handled accordingly. PROBABLE CAUSE Rupture of a Service Water pipe in the CCW Heat Exchanger Room. AUTOMATIC ACTION NONE OPERATOR ACTION

1. Notify appropriate personnel to monitor CCW pumproom water level to determine if alarm is valid. 2. Close SW TO AUX. BLDG A HDR ISO Q1P16MOV3084A if deemed necessary. 3. IF level continues to rise (flooding is NOT isolated), THEN open SW TO AUX. BLDG A HDR ISO Q1P16MOV3084A and perform actions of FNP-1-ARP-1.1/AC5 CCW PUMP RM FLOODING LVL 18 IN. 4. IF level stops rising, THEN refer to FNP-1-AOP-10.0, LOSS OF SERVICE WATER. 5. Refer to Technical Specification 3.7.8 for LCO requirements with a loss of train A or B service water.

References:

A-177100, Sh. 64; B-175968, Sh. 5; D-175003, Sh. 1; D-177624; B-175810, Sh. 101; Technical Specification 3.7.8 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AC5 SETPOINT: 18 + 0.25 inches C5 - 1.0 CCW ORIGIN: 1. Level Switch (N1P16LSHH3084A-N). PUMP RM 2. Level Switch (N1P16LSHH3084B-N). FLOODING LVL 18 IN NOTE: Receipt of this alarm in conjunction with other alarms may indicate CCW pump room flooding from a source other than the service water system and should be handled accordingly. PROBABLE CAUSE Rupture of a Service Water pipe in the CCW Heat Exchanger Room. AUTOMATIC ACTION NONE OPERATOR ACTION 1. Ensure That SW TO AUX. BLDG A HDR ISO Q1P16MOV3084A is open. 2. Close SW TO AUX. BLDG B HDR ISO Q1P16MOV3084B if deemed necessary. 3. Monitor CCW Pump Room water level and verify that the flooding has been isolated. 4. Notify appropriate personnel to locate and correct the cause of flooding. 5. Refer to FNP-1-AOP-10.0, LOSS OF SERVICE WATER. 6. Refer to Technical Specification 3.7.8 for LCO requirements with a loss of train A or B Service Water.

References:

A-177100, Sh. 65; B-175968, Sh. 5; D-177623; B-175810, Sh. 101; Technical Specification 3.7.8 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 2 Version 56.0 LOCATION AD1 SETPOINT: 7 3/8" + 1" (Above the Floor) D1 - 0 RW PUMP RM ORIGIN: 1. Level Switch (QSW34LS501-A) A TRN 2. Level Switch (QSW34LS502-A) FLOODING PROBABLE CAUSE 1. River Water (A Train) Header ruptured. 2. Improper valve lineup. AUTOMATIC ACTION NONE OPERATOR ACTION 1. Stop the operating A Train River Water pumps on Unit 1 and Unit 2 MCB. 2. Close valve QSP25V514, RW HDR TO POND ISO A TRAIN. 3. Dispatch personnel to locate and isolate the cause of the flooding. 4. Perform any actions required for annunciator AD2, RW PRESS A TRN LO. 5. Secure power to the A Train portion of the River Water structure as follows: 5.1 Open supply breaker to STATION SERVICE TRANSFORMER 1H breaker DH-02-1. 5.2 Open supply breaker to STATION SERVICE TRANSFORMER 2H breaker DH-02-2. 6. If flooding is due to high river level, then perform any actions required for annunciators AG1 and AH1 RIVER LVL A (B) TRN HI. NOTE: RW HDR TO POND ISO A TRAIN may be in the closed position as a result of step 2 above. 7. IF the cause of the flooding is isolable AND the A Train River Water Header can be returned to operation, THEN refer to FNP-0-SOP-25.0, RIVER WATER SYSTEM and return the header to service. 8. Notify appropriate plant personnel to correct the cause of the flooding. 9. Return the A Train River Water Header to service as soon as possible. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 2 of 2 Version 56.0 LOCATION AD1 10. IF cause of flooding is not isolable, THEN rack out and tag the breakers on TABLE 1 and have EM megger circuit prior to returning to service. TABLE 1 Q1R15BKRDH02 LC-1H Q1R15BKRDH03 #8 RW PUMP Q1R15BKRDH04 #9 RW PUMP Q1R15BKRDH05 #10 RW PUMP Q2R15BKRDH02 LC-2H Q2R15BKRDH03 #6 RW PUMP Q2R15BKRDH04 #7 RW PUMP

References:

A-177100, Sh. 66; A-170750, Sh. 8; D-170119, Sh. 6; D-173497 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 5 Version 56.0 LOCATION AD2 SETPOINT: 20 +/- 1.0 PSIG D2 RW ORIGIN: 1. Pressure Switch QSP25PS512-A PRESS 2. Pressure Switch QSP25PS513-A A TRN LO PROBABLE CAUSE 1. Ruptured A Train River Water Header. 2. Loss of suction to A Train River Water Pumps. 3. A Train River Water Pumps tripped. 4. Improper valve lineup. AUTOMATIC ACTION NONE OPERATOR ACTION 1. Check indications and attempt to identify the cause of A Train River Water low pressure. 2. If the low pressure was caused by loss of a river water pump, then start another river water pump in the A Train. 3. If the cause is other than loss of a river water pump or pressure can not be immediately restored, then trip the operating A Train River Water Pumps. 4. Notify appropriate personnel to determine and correct the cause of the A Train River Water low pressure. 5. Return the A Train River Water System to service as soon as possible. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 2 of 5 Version 56.0 LOCATION AD2 NOTE: The following actions should be taken for Unit 1 as required to ensure proper SW System operation.

6. Verify proper Unit 1 service water system operation as indicated by the following: Service Water pressure above 60 psig Service Water Wet Pit level greater than 184'4", stable or rising. 6.1 Open Service Water Emergency Recirc to the pond. SW A HDR EMERG RECIRC TO POND Q1P16V539 SW B HDR EMERG RECIRC TO POND Q1P16V538 CAUTION: All liquid effluent releases must be suspended prior to the following step due to the loss of SW dilution flow. 6.2 WHEN step 6.1 is complete, THEN open the following breakers to prevent deadheading the SW Pumps on a spurious valve closure. Q1R17BKRFNG2 for Q1P16V539 Q1R17BKRFTN4 for Q1P16V538 6.3 Verify closed LIQUID WASTE RAD. CONT. VLV.

1-LWP-RCV-018 (N1G21V113) (100' LWPP). 6.4 Close UNIT ONE COOLING TOWER BLOWDOWN N1P16V586-N (1B DG Room). 6.5 Secure any TB Sump release in progress per FNP-1-SOP-50.5 6.6 Secure SGBD per FNP-1-SOP-16.1 NOTE: Power is removed from Q1P16V549 due to Appendix R. The breaker for Q1P16V549 is HS-J4. 6.7 Close SW TO DILUTION LINE Q1P16V549. 6.8 IF service water pond level falls to 184'4", THEN refer to FNP-0-AOP-31.0, LOSS OF SERVICE WATER POND. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 3 of 5 Version 56.0 LOCATION AD2 6.9 WHEN the river water system is returned to service, THEN return the service water system to normal as follows: 6.9.1 Open SW TO DILUTION LINE Q1P16V549. 6.9.2 Close the following breakers: Breakers Q1R17BKRFNG2 for Q1P16V539 Breakers Q1R17BKRFTN4 for Q1P16V538. 6.9.3 Close the following valves: SW A HDR EMERG RECIRC TO POND Q1P16V539 SW B HDR EMERG RECIRC TO POND Q1P16V538 6.9.4 Verify open breaker Q1R17BKRHSJ4 for Q1P16V549. 6.9.5 Verify OPEN the following valves: (Unit 2 Main Control Board) SW TO POND EAST HDR ISO QSP16V507. SW TO POND WEST HDR ISO QSP16V508. 6.9.6 Verify CLOSED the following valves: (Unit 2 Main Control Board) SW TO WET PIT EAST HDR ISO QSP16V505. SW TO WET PIT WEST HDR ISO QSP16V506. 6.9.7 IF required, THEN open UNIT ONE COOLING TOWER BLOWDOWN N1P16V586-N (1B DG Room). 6.9.8 IF required, THEN restore SGBD per FNP-1-SOP-16.1 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 4 of 5 Version 56.0 LOCATION AD2 NOTE: The following actions should be taken for Unit 2 as required to ensure proper SW System operation. 7. Notify Unit 2 to verify proper Unit 2 Service Water System operation as indicated by the following: Service Water pressure above 60 psig Service Water Wet Pit level greater than 184'4", stable or rising. 7.1 Open the following valves: SW A HDR EMERG RECIRC TO POND Q2P16V539. SW B HDR EMERG RECIRC TO POND Q2P16V538 CAUTION: All liquid effluent releases must be suspended prior to the following step due to the loss of SW dilution flow. 7.2 WHEN step 7.1 is completed, THEN open the following breakers to prevent deadheading the SW Pumps on a spurious valve closure: Breaker Q2R17BKRFCCB5 for Q2P16V539. Breaker Q2R17BKRFDDB5 for Q2P16V538. 7.3 Verify closed LIQUID WASTE RAD. CONT. VLV. 2-LWP-RCV-018 (N2G21V113) (100' LWPP). 7.4 Close UNIT 2 COOLING TOWER BLOWDOWN N2P16V586-N (155' Rad. side). 7.5 Secure any TB sump release in progress per FNP-2-SOP-50.5 7.6 Secure SGBD per FNP-2-SOP-16.1 NOTE: Power is removed from Q2P16V549 due to Appendix R. The breaker for Q2P16V549 is Q2R17BKRHCCD3. 7.7 Close SW TO DILUTION LINE Q2P16V549. 7.8 IF Service Water Pond level falls to 184'4", THEN refer to FNP-0-AOP-31.0, LOSS OF SERVICE WATER POND. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 5 of 5 Version 56.0 LOCATION AD2 7.9 WHEN the River Water System is returned to service, THEN return the Service Water System to normal as follows: 7.9.1 Open SW TO DILUTION LINE Q2P16V549. 7.9.2 Close the following breakers: Breaker Q2R17BKRFCC5 for Q2P16V539 Breaker Q2R17BKRFDDB5 for Q2P16V538. 7.9.3 Close the following valves: SW HDR A EMERG RECIRC TO POND Q2P16V539. HDR B EMERG RECIRC TO POND Q2P16V538 7.9.4 Verify open breaker Q2R17BKRHCCD3 for Q2P16V549. 7.9.5 Verify open the following valves: SW TO POND EAST HDR ISO QSP16V507. SW TO POND WEST HDR ISO QSP16V508. 7.8.6 Verify closed the following valves: SW TO WET PIT EAST HDR ISO QSP16V505. SW TO WET PIT WEST HDR ISO QSP16V506. 7.9.7 IF required, THEN open UNIT TWO COOLING TOWER BLOWDOWN N2P16V586-N (155' Rad. side). 7.9.8 IF required, THEN restore SGBD per FNP-2-SOP-16.1 8.0 Refer to Technical Specification 3.7.9 for LCO requirements.

References:

A-177100, Sh. 67; A-170750, Sh. 6; D-170119, Sh. 6; D-173497; Technical Specification 3.7.9; {CMT 0008590} UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 5 Version 56.0 LOCATION AD3 SETPOINT: 20 +/- 1.0 PSIG D3 RW ORIGIN: 1. Pressure Switch QSP25PS514-B PRESS 2. Pressure Switch QSP25PS515-B B TRN LO PROBABLE CAUSE 1. Ruptured B train River Water Header. 2. Loss of suction to B train River Water Pumps. 3. B train River Water Pumps tripped. 4. Improper valve lineup. AUTOMATIC ACTION NONE OPERATOR ACTION 1. Check indications and attempt to identify the cause of B Train River Water low pressure. 2. IF the low pressure was caused by loss of a River Water Pump, THEN start another River Water Pump in B Train. 3. IF the cause is other than loss of a River Water Pump or pressure can NOT be immediately restored, THEN trip the operating B Train River Water Pumps. 4. Notify appropriate plant personnel to determine and correct the cause of the B Train River Water low pressure. 5. Return the B Train River Water System to service as soon as possible. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 2 of 5 Version 56.0 LOCATION AD3 NOTE: The following actions should be taken for Unit 1 as required to ensure proper SW System operation. 6. Verify proper Unit 1 Service Water System operation as indicated by The following: Service Water pressure above 60 psig Service Water Wet Pit level greater than 184'4", stable or rising. 6.1 Open the following valves: SW A HDR EMERG RECIRC TO POND Q1P16V539. SW B HDR EMERG RECIRC TO POND Q1P16V538. CAUTION: All liquid effluent releases must be suspended prior to the following step due to the loss of SW dilution flow. 6.2 WHEN step 6.1 is completed, THEN open the following breakers to prevent deadheading the SW Pumps on a spurious valve closure. Q1R17BKRFNG2 for Q1P16V539 Q1R17BKRFTN4 for Q1P16V538 6.3 Verify closed LIQUID WASTE RAD. CONT. VLV 1-LWP-RCV-018 (N1G21V113) (100' LWPP). 6.4 Close UNIT ONE COOLING TOWER BLOWDOWN N1P16V586-N (1B DG Room). 6.5 Secure any TB sump release in progress per FNP-1-SOP-50.5 6.6 Secure SGBD per FNP-1-SOP-16.1 NOTE: Power is removed from Q1P16V549 due to Appendix R. The breaker for Q1P16V549 is HS-J4. 6.7 Close SW TO DILUTION LINE Q1P16V549. 6.8 IF service water pond level falls to 184'4", THEN refer to FNP-0-AOP-31.0, LOSS OF SERVICE WATER POND. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 3 of 5 Version 56.0 LOCATION AD3 6.9 WHEN the river water system is returned to service, THEN return the service water system to normal as follows: 6.9.1 Open SW TO DILUTION LINE Q1P16V549. 6.9.2 Close the following breakers: Q1R17BKRFNG2 for Q1P16V539. Q1R17BKRFTN4 for Q1P16V538. 6.9.3 Close the following valves: SW A HDR EMERG RECIRC TO POND Q1P16V539. SW B HDR EMERG RECIRC TO POND Q1P16V538. 6.9.4 Verify open breaker Q1R17BKRHSJ4 for Q1P16V549. 6.9.5 Verify open the following valves: l(Unit 2 Main Control Board) SW TO POND EAST HDR ISO QSP16V507. SW TO POND WEST HDR ISO QSP16V508. 6.9.6 Verify closed the following valves: (Unit 2 Main Control Board) SW TO WET PIT EAST HDR ISO QSP16V505. SW TO WET PIT WEST HDR ISO QSP16V506. 6.9.7 IF required, THEN open UNIT ONE COOLING TOWER BLOWDOWN N1P16V586-N (1B DG Room). 6.9.8 IF required, THEN restore SGBD per FNP-1-SOP-16.1 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 4 of 5 Version 56.0 LOCATION AD3 NOTE: The following actions should be taken for Unit 2 as required to ensure proper SW system operation. 7. Notify Unit 2 to verify proper Unit 1 Service Water System operation as indicated by the following: Service Water pressure above 60 psig Service Water Wet Pit level greater than 184'4", stable or rising. 7.1 Open the following valves: SW A HDR EMERG RECIRC TO POND Q2P16V539. SW B HDR EMERG RECIRC TO POND Q2P16V538. CAUTION: All liquid effluent releases must be suspended prior to the following step due to the loss of SW dilution flow. 7.2 WHEN step 7.1 is complete, THEN open the following breakers to prevent deadheading the SW Pumps on a spurious valve closure. Q2R17BKRFCCB5 for Q2P16V539. Q2R17BKRFDDB5 for Q2P16V538 7.3 Verify closed LIQUID WASTE RAD. CONT. VLV. 2-LWP-RCV-018 (N2G21V113) (100' LWPP). 7.4 Close UNIT 2 COOLING TOWER BLOWDOWN N2P16V586-N (155' Rad. side). 7.5 Secure any TB sump release in progress per FNP-2-SOP-50.5 7.6 Secure SGBD per FNP-2-SOP-16.1 NOTE: Power is removed from Q2P16V549 due to Appendix R. The breaker for Q2P16V549 is HCC-D3. 7.7 Close SW TO DILUTION LINE Q2P16V549. 7.8 IF service water pond level falls to 184'4", THEN refer to FNP-0-AOP-31.0, LOSS OF SERVICE WATER POND. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 5 of 5 Version 56.0 LOCATION AD3 7.9 WHEN the river water system is returned to service, THEN return the service water system to normal as follows: 7.9.1 Open SW TO DILUTION LINE Q2P16V549. 7.9.2 Close breakers the following breakers: Q2R17BKRFCCB5 for Q2P16V539. Q2R17BKRFDDB5 for Q2P16V538. 7.9.3 Close the following valves: SW HDR A EMERG RECIRC TO POND Q2P16V539. SW HDR B EMERG RECIRC TO POND Q2P16V538. 7.9.4 Verify open breaker Q2R17BKRHCCD3 for Q2P16V549. 7.9.5 Verify open the following valves: SW TO POND EAST HDR ISO QSP16V507. SW TO POND WEST HDR ISO QSP16V508. 7.7.6 Verify closed the following valves: SW TO WET PIT EAST HDR ISO QSP16V505. SW TO WET PIT WEST HDR ISO QSP16V506. 7.9.7 IF required, THEN open UNIT TWO COOLING TOWER BLOWDOWN N2P16V586-N (155' Rad. side). 7.9.8 IF required, THEN restore SGBD per FNP-2-SOP-16.1 7.10 Refer to Technical Specification 3.7.9 for LCO requirements.

References:

A-177100, Sh. 68; A-170750, Sh. 6; D-170119, Sh. 6; D-173497; Technical Specification 3.7.9; {CMT 0008590} UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AD4 SETPOINT: 60 +/- 1 PSIG for Q1P16PS504-N D4 60 +/- 1 PSIG for Q1P16PS505-N SW PRESS ORIGIN: 1. Pressure Switch (Q1P16PS504-A) A TRN 2. Pressure Switch (Q1P16PS505-A) LO PROBABLE CAUSE 1. A Train Service Water Pump tripped. 2. Improper valve lineup on A Train Service Water. 3. A Train Service Water Minimum Flow Bypass Valve (Q1P16V577) has failed open. 4. Rupture of an A Train Service Water pipe. AUTOMATIC ACTION NONE OPERATOR ACTION 1. Check indications and attempt to identify the cause of A Train Service Water low pressure. 2. IF the low pressure was caused by loss of a service water pump, THEN start another Service Water Pump in A Train 3. IF the cause is other than loss of a Service Water Pump OR pressure can NOT be immediately restored, THEN perform the actions required by FNP-1-AOP-10.0. 4. Notify appropriate personnel to determine and correct the cause of the A Train Service Water low pressure. 5. Return the Service Water System to a normal lineup as soon as possible. 6. Refer to Technical Specification 3.7.8 for LCO requirements with a loss of Train A or B Service Water.

References:

A-177100, Sh. 69; D-170119, Sh. 1 & 2; C-170617; A-170750, Sh. 65; B-170033, Sh. 19; B-175968, Sh. 25; B-175803; Technical Specification 3.7.8; {CMT 0004933} UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AD5 SETPOINT: 60 +/- 4 PSIG D5 SW ORIGIN: 1. Pressure Switch (Q1P16PS502-B) PRESS 2. Pressure Switch (Q1P16PS503-B) B TRN LO PROBABLE CAUSE 1. B Train Service Water Pump tripped. 2. Improper valve lineup on B Train Service Water. 3. B Train Service Water Minimum Flow Bypass Valve (Q1P16V579) has failed open. 4. Rupture of a B Train Service Water pipe. AUTOMATIC ACTION NONE OPERATOR ACTION 1. Check indications and attempt to identify the cause of B Train Service Water low pressure. 2. IF the low pressure was caused by loss of a Service Water Pump, THEN start another Service Water Pump in B Train. 3. IF the cause is other than loss of a Service Water Pump OR pressure can NOT be immediately restored, THEN perform the actions required by FNP-1-AOP-10.0, LOSS OF SERVICE WATER. 4. Notify appropriate personnel to determine and correct the cause for the B Train Service Water low pressure. 5. Return the System to a normal lineup as soon as possible. 6. Refer to Technical Specification 3.7.8 for LCO requirements with a loss of train A or B service water.

References:

A-177100, Sh. 70; A-170750, Sh. 20; D-170119, Sh. 1 & 2; C-170617; B-170033, Sh. 19; B-175968; B-175803; Technical Specification 3.7.8; UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 2 Version 56.0 LOCATION AE1 SETPOINT: 7 3/8" + 1" (Above the Floor) E1 - 0 RW PUMP RM ORIGIN: 1. Level Switch QSW34LS503-B B TRN 2. Level Switch QSW34LS504-B FLOODING PROBABLE CAUSE 1. B Train River Water Header ruptured. 2. Improper valve lineup. AUTOMATIC ACTION NONE

OPERATOR ACTION

1. Stop the operating B Train River Water Pumps on Unit 1 and Unit 2 MCB. 2. Close valve QSP25V513 RW HDR TO POND ISO TRAIN B. 3. Dispatch personnel to locate and isolate the cause of the flooding. 4. Perform any actions required for annunciator AD3, RW PRESS B TRN LO. 5. Secure power to the B Train portion of the River Water Structure as follows: 5.1 Open supply breaker to STATION SERVICE TRANSFORMER 1J breaker Q1R15BKRDJ01. 5.2 Open supply breaker to STATION SERVICE TRANSFORMER 2J breaker Q2R16BKRDJ01. 6. IF flooding is due to high river level, THEN perform any actions required for annunciators AG1 and AH1 RIVER LVL A (B) TRN HI.

UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 2 of 2 Version 56.0 LOCATION AE1 NOTE: RW HDR TO POND ISO B Train may be in the closed position as a result of step 2 above. 7. IF the cause of the flooding is isolable AND the B Train River Water header can be returned to operation, THEN refer to FNP-0-SOP-25.0, RIVER WATER SYSTEM, and return the header to service. 8. Notify appropriate plant personnel to correct the cause of the flooding. 9. Return the B Train River Water Header to service as soon as possible. 10. IF cause of flooding is not isolable, THEN rack out and tag the breakers on TABLE 1 and have EM megger circuit prior to returning to service. TABLE 1 Q1R15BKRDJ01 LC-1J Q1R15BKRDJ03 #4 RW PUMP Q1R15BKRDJ04 #5 RW PUMP Q2R15BKRDJ01 LC-2J Q2R15BKRDJ02 #1 RW PUMP Q2R15BKRDJ03 #2 RW PUMP Q2R15BKRDJ04 #3 RW PUMP

References:

A-177100, Sh. 71; A-170750, Sh. 9; D-170119, Sh. 6; D-173497 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AE2 SETPOINT: Not Applicable E2 RW ORIGIN: 52-b Contact on any one of the following breakers PUMP 1. DJ03-#4 RW Pump TRIPPED 2. DJ04-#5 RW Pump 3. DH03-#8 RW Pump 4. DH04-#9 RW Pump 5. DH05-#10 RW Pump PROBABLE CAUSE River Water Pump tripped due to an overload or an electrical fault. AUTOMATIC ACTION NONE OPERATOR ACTION 1. Check indications and determine which River Water Pump has tripped. 2. Start another River Water Pump in the same train as the tripped pump. 3. IF a loss of flow in either train of RW has occurred, THEN perform the actions required for the applicable annunciator: AD2, RW PRESS A TRN LO. OR AD3, RW PRESS B TRN LO. 4. Notify appropriate personnel to determine and correct the cause of the alarm. 5. Return the River Water electrical and component lineup to normal as soon as possible.

References:

A-177100, Sh. 72A, B & C; D-172875; D-172876; D-172877; D-172878; D-172879 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AE3 SETPOINT: 10" + 1" (Above the Floor) E3 SWIS ORIGIN: 1. Level Switch QSW36LS501 FLOODING 2. Level Switch QSW36LS502 PROBABLE CAUSE Rupture of Service Water Header inside the Service Water Structure. AUTOMATIC ACTION NONE OPERATOR ACTION 1. Determine from plant instrumentation which service water train, (A OR B) has the rupture. 2. Stop the operating service water pumps in the affected train. 3. Notify appropriate personnel to locate and isolate the cause of the flooding. 4. Perform any actions required by FNP-1-AOP-10.0, LOSS OF SERVICE WATER. 5. IF the cause of the flooding can NOT be isolated AND the affected Service Water Train returned to service, THEN perform the actions required by FNP-1-AOP-10.0, LOSS OF SERVICE WATER. 6 IF the cause of the flooding is isolable AND the affected Service Water Header returned to service, THEN refer to FNP-1-SOP-24.0, SERVICE WATER SYSTEM, Section 4.2. 7. Notify appropriate plant personnel to correct the cause of the flooding. 8. Return the affected portion of the Service Water System to service as soon as possible. 9. Refer to Technical Specification 3.7.8 for LCO requirements.

References:

A-177100, Sh. 76; A-170750, Sh. 21; D-170119, Sh. 1; D-173497; Technical Specification 3.7.8 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AE4 SETPOINT: Not Applicable E4 SW ORIGIN: 52-b Contact on any one of the following breakers. PUMP 1. DK03-1A SW Pump TRIPPED 2. DK04-1B SW Pump 3. DK05-1C SW Pump A Train 4. DL05-1C SW Pump B Train 5. DL03-1D SW Pump 6. DL04-1E SW Pump PROBABLE CAUSE Service Water Pump tripped due to an overload or an electrical fault. AUTOMATIC ACTION NONE OPERATOR ACTION

1. Check indications and determine which Service Water Pump has tripped. 2. Start another Service Water Pump in the same train as the tripped pump. 3. Refer to FNP-1-AOP-10.0, LOSS OF SERVICE WATER. 4. Refer to FNP-1-SOP-24.0, SERVICE WATER SYSTEM, step 4.5 or step 4.6 as required to align 1C service water pump to A or B train. 5. Notify appropriate personnel to determine and correct the cause of the alarm. 6. Return the Service Water electrical and component lineup to normal as soon as possible. 7. Refer to Technical Specification 3.7.8 for LCO requirements with a loss of train A or B service water.

References:

A-177100, Sh. 74A, B & C; D-172747; D-172748; D-172749; D-172750; D-172751; D-172752; Technical Specification 3.7.8 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AE5 SETPOINT: 50 10 Psig E5 SW TO AUX BLDG ORIGIN: 1. Pressure Switch (N1P16PSL3001A-B) HDR PRESS 2. Pressure Switch (N1P16PSL3001B-A) A OR B TRN LO PROBABLE CAUSE 1. A or B Train Service Water Pump tripped. 2. Improper Service Water valve lineup. 3. Service Water line ruptured. AUTOMATIC ACTION NONE OPERATOR ACTION 1. Check indications and determine which train, A or B has the low pressure. 2. IF the low pressure was caused by loss of a Service Water Pump, THEN start another Service Water Pump in the affected train. 3. IF the cause is other than loss of a Service Water Pump OR pressure can NOT be immediately restored, THEN perform the actions required by FNP-1-AOP-10.0, LOSS OF SERVICE WATER. 4. Notify appropriate personnel to determine and correct the cause of the low pressure. 5. Return the system to a normal lineup as soon as possible. 6. Refer to Technical Specification 3.7.8 for LCO requirements with a loss of train A or B service water.

References:

A-177100, Sh. 75; B-175968, Sh. 5; D-175003, Sh. 1; D-170119, Sh. 2; B-175810, Sh. 107; Technical Specification 3.7.8 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AF1 SETPOINT: Not Applicable F1 SEL SWITCH ORIGIN: Selector Switch for any of the following breakers or IN controls: LOCAL CONT 1. DK03-1A SW Pump 2. DK04-1B SW Pump 3. DK05-1C SW Pump A Train 4. DL05-1C SW Pump B Train 5. DL03-1D SW Pump 6. DL04-1E SW Pump 7. DJ03-#4 RW Pump 8. DJ04-#5 RW Pump 9. DH03-#8 RW Pump 10. DH04-#9 RW Pump 11. DH05-#10 RW Pump 12. Boric Acid to Charging Pump Valve Q1E21MOV8104-B 13. Motor Driven Fire Pump PROBABLE CAUSE One or more of the Selector Switches listed above, in the local position AUTOMATIC ACTION NONE OPERATOR ACTION NOTE: . No action is necessary if the alarm is due to preplanned operational or maintenance activities; otherwise send appropriate personnel to determine the cause of the alarm. 1. Return the Selector Switch to the Remote position as soon as possible. 2. Refer to Technical Specification 3.7.8 for LCO requirements.

References:

A-177100, Sh. 76A, B & C; D-172875; D-172876; D-172877; D-172878; D-172879; D-172747; D-172748; D-172749; D-172750; D-172751; D-172752; D-177601; D-172869; Technical Specification 3.7.8 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AF2 SETPOINT: N/A F2 RWIS ORIGIN: Local and power failure relay alarm contact in River ALARM Water Structure local annunciator panel. PROBABLE CAUSE NOTE: The RW annunciator panel is powered from 1X MCC which in turn is powered from 1-2H 600 V LC. 1X MCC also supplies power to RW pump auxiliaries. 1. Loss of Power to River Water Annunciator Panel. 2. Initiation of any of the alarms on the River Water Structure local annunciator panel. AUTOMATIC ACTION NONE OPERATOR ACTION Dispatch appropriate personnel to check river water structure local annunciator panel for cause of alarm. 1. Refer to FNP-0-ARP-9, RIVER WATER STRUCTURE, for specific actions to be taken in response to any of the alarm initiating conditions. NOTE: 1-2H 600 V LC is normally powered from Unit 2. For a Unit 2 only LOSP that results in deenergizing 1-2H 600 V LC, the Unit 1 A train RW pumps will continue to run without their auxiliaries (Unit 2 RW pumps will load shed). Similarly, for a Unit 1 only LOSP when 1-2H 600 V LC is powered from Unit 1 (alternate), the Unit 2 A train RW pumps will continue to run without their auxiliaries. To prevent damage to the RW pumps, the affected pumps should be stopped, or power to their auxiliaries restored. (DCP 88-1-4773) 2. IF any Unit 1 OR Unit 2 A train RW pump running without it's auxiliaries, THEN stop the affected pump. 3. IF required, THEN restore power to 1-2H 600 V LC per FNP-1-SOP-36.3, 600, 480 AND 208/120 VOLT AC ELECTRICAL DISTRIBUTION SYSTEM.

References:

A-177100, Sh. 77; D-173187; FNP-0-ARP-9, RIVER WATER STRUCTURE UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AF3 SETPOINT: N/A F3 SWIS ORIGIN: Local and power failure relay alarm contact in Service ALARM Water Structure local annunciator panel. PROBABLE CAUSE Initiation of any of the alarms on the Service Water Structure local annunciator panel. AUTOMATIC ACTION NONE OPERATOR ACTION Dispatch appropriate personnel to check Service Water structure local annunciator panel for cause of alarm. Refer to FNP-0-ARP-8, SERVICE WATER STRUCTURE, for specific actions to be taken in response to any of the alarm initiating conditions.

References:

A-177100, Sh. 78; D-173186; FNP-0-ARP-8, SERVICE WATER STRUCTURE UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 2 Version 56.0 LOCATION AF4 SETPOINT: 1. Lo Flow Range (< 1980 GPM): F4 Diff. Flow HI: 300 + 0 GPM CTMT CLR - 75 SW FLOW 2. Hi Flow Range (> 1980 GPM): HI-LO Diff. Flow HI: 750 + 0 GPM - 30 ORIGIN: 1. Flow Switch (Q1P16FDSH3013AA-N 2. Flow Switch (Q1P16FDSH3013AB-N) 3. Flow Switch (Q1P16FDSH3013BA-N) 4. Flow Switch (Q1P16FDSH3013BB-N) NOTE: The appropriate alarm range is selected automatically in response to existing flow conditions; Lo Range for inlet flow < 1980 gpm and Hi Range for inlet > 1980 gpm. The alarm comes in based on high diff flow from inlet to outlet. PROBABLE CAUSE 1. Improper Service Water to Containment Cooler valve lineup. 2. Rupture or leak in Service Water piping.

AUTOMATIC ACTION NONE

OPERATOR ACTION 1. Check indications and determine which Service Water Train, A or B, has the high differential flow across the coolers. 2. Isolate service water to the containment coolers in the affected train. 3. Refer to FNP-1-SOP-12.1, CONTAINMENT AIR COOLING SYSTEM. 4. Have appropriate personnel determine the cause for the containment cooler service water high differential flow. 5. IF high differential flow is due to improper valve lineup, THEN have appropriate personnel correct the valve lineup in the affected train. UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 2 of 2 Version 56.0 LOCATION AF4 6. IF high differential flow is due to rupture in line, THEN perform the following: 6.1 Isolate the affected CTMT cooler service water inlet valves: Q1P16MOV3019A, SW TO 1A CTMT CLR AND CTMT FPS Q1P16MOV3019B, SW TO 1B CTMT CLR Q1P16MOV3019C, SW TO 1C CTMT CLR Q1P16MOV3019D, SW TO 1D CTMT CLR AND CTMT FPS 6.2 Isolate the affected CTMT cooler service water outlet valves: Q1P16MOV3024A, EMERG SW FROM 1A CTMT CLR Q1P16MOV3024B, EMERG SW FROM 1B CTMT CLR Q1P16MOV3024C, EMERG SW FROM 1C CTMT CLR Q1P16MOV3024D, EMERG SW FROM 1D CTMT CLR Q1P16MOV3023A, 1A CTMT CLR SW DISCH Q1P16MOV3023B, 1B CTMT CLR SW DISCH Q1P16MOV3023C, 1C CTMT CLR SW DISCH Q1P16MOV3023D, 1D CTMT CLR SW DISCH. 7. Return system to normal lineup as soon as possible.

References:

A-177100, Sh. 79; B-175968; D-175003, Sh. 1; U-199344; U-199361; {CMT 0004933} UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AF5 SETPOINT: 9.0 + 1.5 PSID (~ 15,000 GPM) F5 SW TO ORIGIN: 1. Diff. Pressure Switch (Q1P16PDS565-A) TURB BLDG 2. Diff. Pressure Switch (Q1P16PDS566-B) A OR B TRN 3. Diff. Pressure Switch (Q1P16PDS568-A) FLOW HI 4. Diff. Pressure Switch (Q1P16PDS569-B) PROBABLE CAUSE Rupture of Service Water piping in Turbine Building. AUTOMATIC ACTION 1. IF Service Water flow in the A Train exceeds 17,600 GPM (11 +/- 1.5 PSID) THEN SW TO TURB BLDG ISO A TRN Q1P16V516 (Q1P16PDS569-B) and SW TO TURB BLDG ISO B TRN Q1P16V514 (Q1P16PDS566-B) will close. 2. IF Service Water flow in the B Train exceeds 17,600 GPM (11 +/- 1.5 PSID) THEN SW TO TURB BLDG ISO A TRN Q1P16V515 (Q1P16PDS565-A) and SW TO TURB BLDG ISO B TRN Q1P16V517 (Q1P16PDS568-A) will close. NOTE: IF SW HDR PRESS is less than 110 psig and SW Dilution Flow normal., crew may consider closing Train A dilution bypass isolation valve Q1P16V558 and/or Train B dilution bypass valve Q1P16V557 (Diesel Bldg.) (Ref. OR 2-99-336) OPERATOR ACTION 1. If Service Water flow lost to Turbine Building, THEN attempt to restore Service Water flow. 2. Refer to FNP-1-AOP-7.0, LOSS OF TURBINE BUILDING SERVICE WATER. 3. IF indication of TB flow switch clogging/malfunction, refer to FNP-1-SOP-24.0, Service Water System, Appendix 9 to troubleshoot DP switches. 4. Direct appropriate personnel to locate and correct the cause of the alarm.

References:

A-177100, Sh. 80; D-172674, Sh. 1 & 2; D-170119, Sh. 2; A-170750, Sh. 19 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AG1 SETPOINT: 124' 0" 0.5" G1 RIVER LVL ORIGIN: Level Switch QSP25LS554A A TRN HI PROBABLE CAUSE 1. Excessive rain and runoff. 2. Instrument failure. AUTOMATIC ACTION NONE OPERATOR ACTION Dispatch appropriate personnel to determine if alarm is due to an actual high level condition or an instrument failure. 1. Monitor building sump levels to insure site facilities are not flooded. 2. IF flooding of the River Water Structure occurs, THEN perform the following actions: 2.1 Stop all river water pumps. 2.2 Perform the actions required for the following annunciators: AD1, RW PUMP RM A TRN FLOODING AE1, RW PUMP ROOM B TRN FLOODING. 3. IF alarm is due to an instrument failure, THEN have appropriate plant personnel investigate and correct the cause of the failure.

References:

A-177100, Sh. 81; A-170750, Sh. 6; B-170270, Sh. 12; D-170119, Sh. 6; D-173497 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AG2 SETPOINT: 74' 0" + 0.5" G2 RIVER LVL ORIGIN: Level Switch QSP25LS555-A A TRN LO PROBABLE CAUSE 1. Excessive drought conditions. 2. Instrument failure. 3. Excessive amount of trash on intake screens. AUTOMATIC ACTION NONE OPERATOR ACTION Dispatch appropriate personnel to determine if alarm is due to an actual low level condition, an instrument failure or clogged intake screens.

1. Monitor river level. 1.1 IF River Water System intake level drops to 67', THEN trip the River Water and Screen Wash Pumps per FNP-0-SOP-25.0, RIVER WATER SYSTEM. 1.1.1 Perform the actions required for the following annunciators: AD2, RW PRESS A TRN LO. AD3, RW PRESS B TRN LO. 2. IF alarm is due to an instrument failure, THEN have appropriate personnel investigate and correct the cause of the failure. 3. IF alarm is due to trash on intake screens, THEN wash screens until clean, per FNP-0-SOP-25.2 RIVER WATER AUXILIARY SYSTEMS.

References:

A-177100, Sh. 82; A-170750, Sh. 6; B-170270, Sh. 12; D-170119, Sh. 6; D-173497 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AG3 SETPOINT: 184' 4" + 1" G3 - 0 SW POND LVL ORIGIN: Level Switch QSP25LS508-A A TRN LO PROBABLE CAUSE 1. Failure of Service Water Pond Level control switches QSP25LS510-A and/or QSP25LS511-B. 2. Rupture of River Water Normal Makeup to pond pipe. 3. River Water System inoperable. AUTOMATIC ACTION NONE OPERATOR ACTION NOTE Securing running RW pumps while this alarm is in requires taking RW Pump hand switch to RESET. 1. Dispatch appropriate personnel to determine cause of alarm. 2. IF RIVER WATER system is determined to be inoperable, THEN perform actions required for the following annunciators: AD2, RW PRESS A TRN LO. AD3, RW PRESS B TRN LO. 3. Monitor pond level. 3.1 IF level continues to decrease, THEN refer to the following: Technical Specifications, Section 3.7.9 for LCO requirements FNP-0-AOP-31.0, Loss Of Service Water Pond. 4. IF River Water Pump operation restores the Service Water Pond level to normal operating level, THEN return system to normal operation at a level of 185' 6". 5. Direct appropriate personnel correct the cause of the alarm. 6. Return system to normal operation as soon as possible.

References:

A-177100, Sh. 83; A-170750, Sh. 7; D-170119, Sh. 6 & 7; D-172780; D-172782; D-172877; D-172878; D-172879; D-202877; D-202878; Technical Specification 3.7.9; PCN S90-0-6413; {CMT's 0005821 & 0008590} UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AG4 SETPOINT: 170' 0" +/- 0.5" G4 SW ORIGIN: Service Water Wet Pit Low Level Switch WET PIT LVL QSP25LS550-A A TRN LO PROBABLE CAUSE 1. Loss of Service Water Pond. 2. Instrument Failure. AUTOMATIC ACTION NONE OPERATOR ACTION

1. Ensure #6, 7, 8, 9 and 10 River Water Pumps are running. 2. Ensure the RW EMERG SUPP TO SW WET PIT QSP25V517 is open. 3. Check MCB indication to determine validity of alarm. 4. Dispatch personnel to determine cause of alarm. 5. Return systems to normal operation as soon as possible. 6. Have appropriate personnel correct the cause for the alarm. 7. Refer to FNP-0-AOP-31.0, LOSS OF SERVICE WATER POND. 8. Refer to Technical Specification, Section 3.7.9 for LCO Requirements with a Loss of the Service Water Pond.

References:

A-177100, Sh. 84; A-170750, Sh. 6; D-170119, Sh. 7; Technical Specification 3.7.9; {CMT 0005821} UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AG5 SETPOINT: 98 +/- 3°F G5 DILUTION ORIGIN: Integrated Plant Computer (IPC) DISCH TE-0561 TEMP HI PROBABLE CAUSE 1. Loss of Service Water to the Dilution Line. 2. High effluent temperature or flow from: a. Cooling Tower Blowdown b. Rad Waste Discharge AUTOMATIC ACTION NONE OPERATOR ACTION

1. Determine validity of alarm using IPC Annunciation application. a. Click on IPC Annunciation button on Applications Menu. b. Click on VIEW POINTS button under WINDOW AG5. c. Determine validity of alarm based on value and quality of TE0561. d. If alarm is invalid, submit CR OR verifying CR exists for problem. e. If alarm is invalid, go to procedure and step in effect. 2. Verify that service water discharge to dilution line valves are open. 3. Start an additional A or B Train Service Water pump as required to lower Service Water discharge temperature by increasing dilution line bypass flow. 4. Notify the Environmental Group of the Dilution Discharge high temperature. 5. Notify appropriate personnel to determine and correct the cause for the Dilution Discharge high temperature alarm.

References:

A-177100, Sh. 85; D-170119, Sh. 2 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AH1 SETPOINT: 124' 0" +/- 0.5" H1 RIVER LVL ORIGIN: Level Switch QSP25LS556-B B TRN HI PROBABLE CAUSE 1. Excessive rain and runoff. 2. Instrument failure. AUTOMATIC ACTION NONE OPERATOR ACTION Dispatch appropriate personnel to determine if alarm is due to an actual high level condition or a instrument failure.

1. Monitor building sump levels to insure site facilities are not flooded. 2. IF flooding of the River Water Structure occurs, THEN perform the following actions: 2.1 Stop all river water pumps. 2.2 Perform the actions required for annunciator AD1, RW PUMP RM A TRN FLOODING, and for AE1, RW PUMP ROOM B TRN FLOODING. 3. IF alarm is due to an instrument failure, THEN have appropriate plant personnel investigate and correct the cause of the failure.

References:

A-177100, Sh. 86; A-170750, Sh. 7; B-170270, Sh. 12; D-170119, Sh. 6; D-173497 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AH2 SETPOINT: 74' 0" +/- 0.5" H2 RIVER LVL ORIGIN: Level Switch QSP25LS557-B B TRN LO PROBABLE CAUSE 1. Extended drought conditions. 2. Instrument failure. 3. Excessive amount of trash on intake screens. AUTOMATIC ACTION NONE OPERATOR ACTION Dispatch appropriate personnel to determine if alarm is due to an actual low level condition, an instrument failure or clogged intake screens.

1. Monitor river level. 1.1 IF River Water System intake level drops to 67', THEN trip the River Water and Screen Wash pumps per FNP-0-SOP-25.0, RIVER WATER SYSTEM. 1.2 Perform the actions required for the following annunciators. AD2, RW PRESS A TRN LO. AD3, RW PRESS B TRN LO. 2. IF alarm is due to an instrument failure, THEN have appropriate personnel investigate and correct the cause of the failure. 3. IF alarm is due to trash on intake screens, THEN wash screens until clean, per FNP-0-SOP-25.2 RIVER WATER AUXILIARY SYSTEMS.

References:

A-177100, Sh. 87; A-170750, Sh. 7; B-170270, Sh. 12; D-170119, Sh. 6; D-173497 UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AH3 SETPOINT: 184' 4" + 1" H3 - 0 SW POND LVL ORIGIN: SW Pond Low Level Switch (QSP25LS509-B) B TRN LO PROBABLE CAUSE 1. Failure of Service Water Pond Level control switches QSP25LS510-A and/or QSP25LS511-B. 2. Rupture of River Water normal makeup to pond pipe. 3. River Water System inoperable. AUTOMATIC ACTION NONE OPERATOR ACTION NOTE Securing running RW pumps while this alarm is in requires taking RW Pump hand switch to RESET. 1. Dispatch appropriate personnel to determine cause of alarm. 2. IF RIVER WATER system is determined to be inoperable, THEN perform actions required for the following annunciators AD2, RW PRESS A TRN LO. AD3, RW PRESS B TRN LO. 3. Monitor pond level. 3.1 IF level continues to decrease, THEN refer to the following: Technical Specifications, Section 3.7.9 for LCO requirements FNP-0-AOP-31.0, Loss Of Service Water Pond. 4. IF River Water Pump operation restores Service Water Pond level to normal operating level, THEN return system to normal operation at a level of 185' 6". 5. Direct appropriate personnel correct the cause of the alarm. 6. Return system to normal operation as soon as possible.

References:

A-177100, Sh. 88; A-170750, Sh. 7; D-170119, Sh. 6 & 7; D-172791; D-172793; D-172875; D-172876; D-202875; D-202876; D-202879; Technical Specification 3.7.9 PCN S90-0-6413; {CMT's 0005821 & 0008590} UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AH4 SETPOINT: 170' 0" +/- 0.5" H4 SW ORIGIN: Service Water Wet Pit Low Level Switch WET PIT LVL QSP25LS551-B B TRN LO PROBABLE CAUSE 1. Loss of Service Water Pond. 2. Instrument failure. AUTOMATIC ACTION NONE OPERATOR ACTION

1. Ensure #1, 2, 3, 4 and 5 River Water Pumps are running. 2. Ensure RW EMERG SUPP TO SW WET PIT, QSP25V518 is open. 3. Check MCB indication to determine validity of alarm. 4. Dispatch appropriate personnel to determine cause of alarm. 5. Return systems to normal operation as soon as possible. 6. Refer to FNP-0-AOP-31.0, LOSS OF SERVICE WATER POND. 7. Refer to Technical Specifications, Section 3.7.9 for LCO Requirements with a loss of the Service Water Pond.

References:

A-177100, Sh. 89; A-170750, Sh. 6; D-170119, Sh. 6; Technical Specification 3.7.9; {CMT 0005821} UNIT 1 08/03/15 08:00:40 FNP-1-ARP-1.1 Page 1 of 1 Version 56.0 LOCATION AH5 SETPOINT: N/A H5 MIMS ORIGIN: Metal Impact Monitoring System Panel ALARM PROBABLE CAUSE 1. Loose parts in reactor vessel. 2. Loose parts in steam generator(s). AUTOMATIC ACTION NONE OPERATOR ACTION

1. Notify Shift Supervisor immediately. 2. Determine alarm source channel. 3. Monitor MIMS source channel for recurring metallic noises. 4. Record alarm receipt in the Control Room Log.

(Include whether alarm due to AMPLITUDE or RATE or BOTH.) 5. Notify Shift Manager of MIMS condition. 6. IF cause for alarm appears to be a momentary 'spike', THEN with Shift Supervisor permission, reset the alarm. 7. IF a selected alarm module channel on MIMS has "static or electrical noise" which is causing alarms to be generated, THEN select the remaining channel to be monitored. 8. IF an interruption of power has occurred, indicated by the illumination of the red light after power is restored, THEN this light must be manually reset by the reset pushbutton.

References:

A-177100, Sh. 90; PCN S-83-1412; U-214743; {CMT 0004714} UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0 January 13, 2014 Version 25.0 FARLEY NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE FNP-1-AOP-9.0SAFE TYLOSS OF COMPONENT COOLING WATER RE LAT EDPROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: ALL

Reference:

NONE Information: NONE Approved:David L Reed (for) Operations Manager Effective Date: 02/01/2014 UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.01 Page of 1 1Table of Contents PROCEDURE CONTAINS NUMBER OF PAGES Body 12 Attachment 1 12 Attachment 2 4 Attachment 3 4 Attachment 4 2 Attachment 5 2 [ ]AA A UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.01 Page of 12 1A. Purpose This procedure provides actions for response to a loss of an operating component cooling water train. This procedure is applicable at all times. B.Symptoms or Entry Conditions I.This procedure is entered when a loss of component cooling water is indicated by any of the following: a.Trip of any operating CCW PUMP b.Loss of SW supply to an operating CCW train UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 2 of 12 ****************************************************************************************** CAUTION: To prevent pump damage the 86 lockout relay for a faulted CCW PUMP must not be reset until the cause of the fault has been determined. Placing the affected CCW PUMP handswitch to STOP will reset this relay. ****************************************************************************************** _________________________________________________________________________________________ NOTE: The standby CCW PUMP will automatically start if the pump in the train it is aligned to trips due to electrical overload. The term "on service train" refers to the train which is aligned to supply the miscellaneous header. _________________________________________________________________________________________ __ 1Verify CCW pump started in affected train.1IF CCW cooling lost to running charging pump, THEN perform the following: 1 1.1Verify CCW pump started in the non affected train. 1.1 1.2IF CCW pump running in non affected train,THEN start charging pump in non affected train.1.2 1.3IF charging pump started in non affected train,THEN stop charging pump in affected train.1.3 S UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 3 of 12 _________________________________________________________________________________________ NOTE: If seal cooling is lost, it will be necessary to trip the RCP(s) within two minutes for a #1 seal leak rate of 5 gpm reducing to 42 seconds for a #1 seal leak rate of 7 gpm, to ensure that the RCP(s) stop rotating prior to actuation of the shutdown seal. (#1 seal leak rate is defined as #1 seal leakoff flow plus #2 seal leakoff flow). IF RCP motor bearing temperatures exceed 195°F, THEN the ON SERVICE train is affected. Adequate CCW flow means sufficient cooling is available to maintain acceptable temperatures. (i.e. charging pumps, RHR cooling, SFP cooling, RCP's etc.) Indications of pump cavitation are: Abnormal CCW flow oscillations or cavitation noise reported at the pump. When transitioning to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION, AND at the Shift Supervisors direction, it is ACCEPTABLE for one team member to complete the Immediate Operator Actions of FNP-1-EEP-0, while the other team member verifies the reactor trip, THEN trips the RCPs before finishing the Immediate Operator Actions of FNP-1-EEP-0. _________________________________________________________________________________________ __ 2[CA] Check cooling adequate for continued plant support. 2Perform the following: 2*Check CCW flow adequate in affected train. *Check RCP motor bearing temperatures less than 195°F. *Check CCW pump not cavitating. Stop any cavitating CCW pump. *CCW Surge tank level being maintained at or above 13 inches.*RCP seal injection to all RCPs greater than 6 gpm. 2.1IF the ON SERVICE train is affected, THEN perform the following: 2.1 2.1.1IF the reactor is critical, THEN trip the reactor and perform, FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION, while continuing with this procedure. 2.1.1 2.1.2Verify all Reactor Coolant pumps stopped. 2.1.2 2.1.3IF in Mode 3 or 4, THEN perform FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW while continuing with procedure. 2.1.3 Step 2 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 4 of 12 __________________________________________________________________________________________ NOTE: Indications of CCW pump cavitation will be abnormal CCW flow oscillations or cavitation noise reported at the pump. __________________________________________________________________________________________ 2.2IF evidence of CCW pump cavitation exists,THEN stop affected CCW pump. 2.2 2.3IF CCW cooling lost to running charging pump, THEN perform the following: 2.3 2.3.1Verify CCW pump started in the non affected train. 2.3.1 2.3.2IF CCW pump running in non affected train,THEN start charging pump in non affected train. 2.3.2 2.3.3IF charging pump started in non affected train, THEN stop charging pump in affected train.2.3.3 2.3.4IF charging pump running in affected train AND not required, THEN stop charging pump in affected train. 2.3.5IF all charging secured, THEN isolate letdown. Step 2 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 5 of 12 ****************************************************************************************** CAUTION: IF seal injection is in service, THEN at least one charging pump must be maintained to support RCP's. ****************************************************************************************** __________________________________________________________________________________________ NOTE: IF necessary to swap train alignment for the 1B charging pump for continued support of plant operations, THEN it is desirable to have separate operators performing the electrical and mechanical alignments simultaneously. __________________________________________________________________________________________ 2.4IF required to establish an operable charging pump in the non affected train, THEN shift the B charging pump to the non affected train per FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM PLANT STARTUP AND OPERATION Appendix A or Appendix B. 2.4 2.5IF CCW is NOT available to support charging operation, THEN align fire water using ATTACHMENT 1, ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP. 2.5 2.6IF CCW cooling to a running RHR pump is inadequate,THEN perform the following. 2.6 2.6.1Stop the affected RHR pump. 2.6.1 2.6.2IF in Mode 5 or 6, THEN perform FNP-1-AOP-12.0, RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION, in conjunction with this procedure. 2.6.2 UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 6 of 12 __________________________________________________________________________________________ NOTE: The ON SERVICE train includes the miscellaneous header and associated train header. __________________________________________________________________________________________ __ 3Verify SW flow supplied to the ON SERVICE train. 3IF Service Water is not available, THEN perform the following in conjunction with FNP-1-AOP-10.0, LOSS OF SERVICE WATER.3CCW HX SW DISCH [ ]Q1P16FI3009AA 1A CCW HX DISC [ ]Q1P16FI3009BA 1B CCW HX DISC [ ]Q1P16FI3009CA 1C CCW HX DISC 3.1Check the following conditions met for swapping ON SERVICE trains. 3.1 [ ]Affected train is the ON SERVICE train. [ ]Unaffected train has adequate SW available.[ ]No CCW leak exists 3.2IF conditions for swapping ON SERVICE trains met, THEN swap ON SERVICE trains per FNP-1-SOP-23.0, COMPONENT COOLING WATER SYSTEM Appendix B or Appendix C. 3.2 __________________________________________________________________________________________ NOTE: IF previous actions have restored the ON SERVICE train, THEN the ON SERVICE train should no longer be considered affected. __________________________________________________________________________________________ __ 4Check ON SERVICE train affected. 4Go to step 9. 4__ 5Check the ON SERVICE train intact. 5Perform the following: 5 5.1IF the miscellaneous header is intact, THEN shift the miscellaneous header to the non-affected train using ATTACHMENT 2, PLACING 1B CCW PUMP ON A TRAIN or ATTACHMENT 3, PLACING 1B CCW PUMP ON B TRAIN depending upon train affected. 5.1 Step 5 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 7 of 12 5.1.1WHEN ATTACHMENT 2, or ATTACHMENT 3, complete, THEN go to step 7. 5.1.1 5.2IF the miscellaneous header is not intact, THEN proceed to step 7. 5.2 __ 6Check 1A AND 1C CCW pumps AVAILABLE. 6Shift the Miscellaneous header to the non-affected train using ATTACHMENT 2, PLACING 1B CCW PUMP ON A TRAIN or ATTACHMENT 3, PLACING 1B CCW PUMP ON B TRAIN AND proceed to step 7. 66.1Shift the Miscellaneous header to the non-affected train using FNP-1-SOP-23.0, COMPONENT COOLING WATER SYSTEM Appendix B or Appendix C. 6.1 __ 7IF both seal injection and CCW are lost to the RCP's, THEN isolate the RCP seal cooling 777.1Verify CCW return from RCP thermal barrier valves CLOSED. 7.1Locally isolate CCW return 7.1 CCW FROM RCP THRM BARR [ ]Q1P17V107 - Closed (121 PPR) [ ]Q1P17HV3045 Closed [ ]Q1P17HV3184 Closed 7.2Isolate RCP seal return valves. 7.2Locally isolate seal water return lines(139 ft. rad side filter room)7.2 RCP SEAL WTR RTN ISO [ ]SEAL WATER RTN FILTER INLET Q1E21V189A Closed [ ]SEAL WATER RTM FILTER BYPASS Q1E21V190 Closed [ ]Q1E21MOV8112 Closed [ ]Q1E21MOV8100 Closed Step 7 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 8 of 12 7.3Isolate seal injection by closing seal water injection filter inlet valves. (139 ft. rad side filter room) 7.37.3 SEAL WATER INJ FILTER A INLET [ ]Q1E21V127A - Closed [ ]Q1E21V127C - Closed SEAL WATER INJ FILTER B INLET [ ]Q1E21V127B - Closed [ ]Q1E21V127D - Closed _________________________________________________________________________________________ NOTE: IF it is believed the miscellaneous header will be restored, THEN step 8 actions may be performed as necessary to reduce loads as needed to isolate affected equipment. This is a continuing action step. _________________________________________________________________________________________ __ 8Perform the following: 888.1Secure letdown 8.18.1 8.1.1Have Chemistry secure the Zinc Addition System per FNP-1-CCP-335. 8.1.18.1.1 __________________________________________________________________________________________ NOTE: In modes 4, 5, & 6 the following actions could affect low pressure letdown and solid plant pressure control. __________________________________________________________________________________________ 8.1.2Manually adjust low pressure letdown controller to 50%. 8.1.28.1.2 LP LTDN PRESS [ ]PK 145 - 50% Step 8 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 9 of 12 8.1.3Close Letdown Orifice isolation valves 8.1.38.1.3 LTDN ORIF ISO 45 GPM [ ]Q1E21HV8149A Closed LTDN ORIF ISO 60 GPM [ ]Q1E21HV8149B Closed [ ]Q1E21HV8149C Closed 8.2Manually secure charging flow. 8.28.2 CHG FLOW [ ]FK-122 Adjusted Closed __________________________________________________________________________________________ NOTE: Aligning charging pump suction to the RWST will result in borating the RCS. __________________________________________________________________________________________ 8.3Align charging pump suction to the RWST.8.38.3 RWSTTO CHG PUMP [ ]Q1E21LCV115B OPEN [ ]Q1E21LCV115D OPEN VCT OUTLET ISO [ ]Q1E21LCV115C CLOSED [ ]Q1E21LCV115E CLOSED Step 8 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 10 of 12 8.4Isolate RCP seal return 8.4Locally isolate seal water return line.(139' filter room) 8.4 RCP SEAL WTR RTN ISO [ ]Q1E21MOV8112 CLOSED [ ]Q1E21MOV8100 CLOSED [ ]SEAL WATER RTN FILTER INLET Q1E21V189A - CLOSED [ ]SEAL WATER RTM FILTER BYPASS Q1E21V190 - CLOSED 8.5Verify excess letdown secured 8.58.5 EXC LTDN ISO [ ]Q1E21HV8153 CLOSED [ ]Q1E21HV8154 CLOSED 8.6Verify RCDT not on recirculation. 8.68.6 8.7Verify waste gas system shutdown 8.78.7 8.8Inform Chemistry to secure any sampling. 8.88.8 __________________________________________________________________________________________ NOTE: Step 2 is a continuing action step and the RNO column has guidance for Charging and RHR pumps which may be applicable. __________________________________________________________________________________________ 8.9IF CCW leak is in the miscellaneous header AND cannot be isolated, , THEN isolate the Miscellaneous header as follows:8.98.9 8.9.1IF the reactor is critical, THEN trip the reactor and perform, FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION, while continuing with this procedure. 8.9.18.9.1 8.9.2Verify all Reactor Coolant pumps stopped. 8.9.28.9.2 Step 8 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 11 of 12 8.9.3IF in Mode 3 or 4, THEN perform FNP-1-AOP-4.0, LOSS OF REACTOR COOLANT FLOW while continuing with procedure.8.9.38.9.3 8.9.4Isolate CCW to secondary heat exchangers.8.9.4Manually isolate the Miscellaneous header by closing the following valves. (100' CCW HX Room) 8.9.4 CCW TO SECONDARY HXS [ ]Q1P17MOV3047 - Closed [ ]1B CCW HX Outlet iso Q1P17V008B. [ ]CCW SUPP HDR XCON Q1P17V009B [ ]CCW SUPP HDR XCON Q1P17V009C __ 9Check both RHR pumps stopped 9IF CCW cooling to a running RHR pump is inadequate,THEN perform the following: 9 9.1Stop the affected RHR pump. 9.1 9.2IF in modes 5 or 6, THEN perform FNP-1-AOP-12.0, RESIDUAL HEAT REMOVAL SYSTEM MALFUNCTION, in conjunction with this procedure.9.2__ 10Evaluate event classification and notification requirements using FNP-0-EIP-8, NON-EMERGENCY NOTIFICATIONS AND NMP-EP-110, EMERGENCY CLASSIFICATION DETERMINATION AND INITIAL ACTIONS. 1010 __ 11Check SFP cooling aligned to an operating CCW train. 11Align SFP cooling to non affected train using FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 11 UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained __Page Completed 11ProcedureStepsMain Page 12 of 12 __ 12Check on service CCW train operating. 12Determine actions required to restore an ON SERVICE Train. 12 __________________________________________________________________________________________ NOTE: Control power should only be removed from components after checking the breaker OPEN. __________________________________________________________________________________________ __ 13IF desired to defeat the Autostart capability of components cooled by CCW, THEN remove control power from the following: A Train 1A RHR Pump, Q1R15BKRDF09 1A Charging Pump, Q1R15BKRDF06 1B Charging Pump (A Trn), Q1R15BKRDF07 B Train 1B RHR Pump, Q1R15BKRDG09 1B Charging Pump, (B Trn) Q1R15BKRDG07 1C Charging Pump, Q1R15BKRDG06 13__ 14WHEN desired to restore the Autostart capability of components cooled by CCW, THEN restore control power to the following: A Train 1A RHR Pump, Q1R15BKRDF09 1A Charging Pump, Q1R15BKRDF06 1B Charging Pump (A Trn), Q1R15BKRDF07 B Train 1B RHR Pump, Q1R15BKRDG09 1B Charging Pump, (B Trn) Q1R15BKRDG07 1C Charging Pump, Q1R15BKRDG06 14__ 15Go to procedure and step in effect. 1513 -END-UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 1 of 12 ****************************************************************************************** CAUTION: RCP seal injection should be maintained, however, only one CHG PUMP can be allowed to suffer damage from operation without cooling water. ****************************************************************************************** _________________________________________________________________________________________ NOTE: The purpose of this attachment is to align the fire protection water system to replace CCW as the cooling water source for a CHG PUMP so that long term RCP seal injection and RCS makeup are available. It is expected that a CHG PUMP may be damaged while operating without cooling water during performance of this attachment. The operating CHG PUMP should be monitored closely for degradation. Until alternate cooling is established, swapping the operating CHG PUMP may lengthen the time that RCP seal injection is maintained. Performance of this attachment will contaminate (chemically) a portion of the CCW system. This contamination should be considered when the system is restored to normal alignment. _________________________________________________________________________________________ __ 1Align charging pump suction to RWST. 11RWSTTO CHG PUMP [ ]Q1E21LCV115B open [ ]Q1E21LCV115D open VCT OUTLET ISO [ ]Q1E21LCV115C closed [ ]Q1E21LCV115E closed S UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 2 of 12 __ 2Isolate seal water return line. 2Locally isolate seal water return line. (139 ft, AUX BLDG rad side filter room) 2RCP SEAL WTR RTN ISO SEAL WATER RTN FLTR INLET [ ]Q1E21MOV8112 - closed [ ]Q1E21MOV8100 - closed [ ]Q1E21V189A closed SEAL WATER RTN FLTR BYP VLV [ ]Q1E21V190 closed ****************************************************************************************** CAUTION: Isolation of CCW flow to the RCP thermal barrier and seal injection flow may result in RCP seal damage. These actions must not be performed prior to reaching the setpoint. ****************************************************************************************** __ 3Monitor RCP seals. 33 __________________________________________________________________________________________ NOTE: RCP number 1 seal outlet temperature can be obtained from computer points TE0132, TE0129 and TE0126. RCP SEAL WTR INJ ISO Q1E21MOV8105 is normally deenergized. The power supply for this valve is FE-G3. __________________________________________________________________________________________ 3.1WHEN any RCP number 1 seal outlet temperature is greater than 235°F, THEN isolate seal injection line. 3.1Locally isolate seal injection line. (139 ft, AUX BLDG rad side filter room) 3.1 RCP SEAL WTER INJ ISO SEAL WATER INJ FILTER A INLET [ ]Q1E21MOV8105 closed [ ]Q1E21V127A closed [ ]Q1E21V127C closed SEAL WATER INJ FILTER B INLET [ ]Q1E21V127B closed [ ]Q1E21V127D closed Step 3 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 3 of 12 3.2WHEN CCW temperature greater than 130°F, THEN isolate CCW return from RCP thermal barrier. 3.2Locally isolate CCW return from RCP thermal barrier. (121 ft, AUX BLDG rad side PPR) 3.2CCW FROM RCP THRM BARR CCW FROM RCP THRM BARR [ ]Q1P17HV3045 closed [ ]Q1P17HV3184 closed [ ]Q1P17V107 closed __ 4Begin cooldown to hot shutdown using FNP-1-ESP-0.2, NATURAL CIRCULATION COOLDOWN TO PREVENT REACTOR VESSEL STEAM HEAD VOIDING for guidance. 44__ 5Establish alternate cooling to one CHG PUMP.55 [ ]1A CHG PUMP go to step 6. [ ]1B CHG PUMP go to step 7 (A Trn). [ ]1B CHG PUMP go to step 8 (B Trn) [ ]1C CHG PUMP go to step 9 S UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 4 of 12 __ 6Establish alternate cooling to 1A CHG PUMP.66.1Isolate CCW to A Train charging pumps.(A train valves are in 100 ft, hallway outside the CHG PUMP area.) 6.1 [ ]Close Q1P17V290, A TRAIN CCW SUPPLY HDR TO CHG PUMPS ISO. [ ]Close Q1P17V292, A TRAIN CCW RETURN HDR FROM CHG PUMPS __________________________________________________________________________________________ NOTE: The intent of the following step is to isolate CCW to the charging pump which will NOT be used (if two pumps are aligned to a single train), to ensure that all firewater cooling established will be directed to the running pump. __________________________________________________________________________________________ 6.2IF 1B CHG Pump aligned to A TRN, THEN isolate CCW to 1B CHG Pump. (100 ft, AUX BLDG CHG PUMP rooms) 6.2 [ ]Close Q1P17V0C1B, CCW to 1B CHG PUMP. [ ]Close Q1P17V0C2B CCW FROM 1B CHG PUMP. __________________________________________________________________________________________ NOTE: All materials needed to make temporary connections in the following steps are stored in Room 160 (Hatch Area) south hall near the scaffold storage area and in fire hose cabinet N1V43D110. __________________________________________________________________________________________ 6.3Install fire hose from hose cabinet N1V43D110 (outside the charging pump hallway) to Q1P17V302, A TRAIN CCW SUPPLY HDR DRN, using a temporary adapter. 6.3 Step 6 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 5 of 12 6.4Install temporary drain hose from Q1P17V304, A TRAIN CCW RETURN HDR DRN to a floor drain. 6.46.5Open supply valve Q1P17V302, A TRAIN CCW SUPPLY HDR DRN. 6.5 6.6Open Q1P17V304, A TRAIN CCW RETURN HDR DRN. 6.6 6.7Adjust hose cabinet isolation valve to establish 20-60 gpm flow to 1A CHG PUMP, FI-3322A. 6.7 6.8Start 1A CHG PUMP. 6.8 6.9Stop any other running CHG PUMP. 6.9 ****************************************************************************************** CAUTION: The CHG PUMP oil cooler may be damaged if cooling flow exceeds 140 gpm. ****************************************************************************************** 6.10Control hose cabinet isolation valve to maintain 1A CHG PUMP oil temperature less than 160°F on TISH-3306AA. 6.10 6.11Proceed to step 10 6.11 S UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 6 of 12 __ 7Establish alternate cooling to 1B CHG PUMP if aligned to A TRN. 77.1Isolate CCW to A train charging pumps. (A train valves are in 100 ft, hallway outside the CHG PUMP area) 7.1 [ ]Close Q1P17V290, A TRAIN CCW SUPPLY HDR TO CHG PUMPS ISO. [ ]Close Q1P17V292, A TRAIN CCW RETURN HDR FROM CHG PUMPS ISO. __________________________________________________________________________________________ NOTE: The intent of the following step is to isolate CCW to the charging pump which will NOT be used (if two pumps are aligned to a single train), to ensure that all firewater cooling established will be directed to the running pump. __________________________________________________________________________________________ 7.2Isolate CCW to 1A CHG Pump. (100 ft, AUX BLDG CHG PUMP rooms) 7.2 [ ]Close Q1P17V0C1A, CCW to 1A CHG PUMP. [ ]Close Q1P17V0C2A CCW FROM 1A CHG PUMP. __________________________________________________________________________________________ NOTE: All materials needed to make temporary connections in the following steps are stored in Room 160 (Hatch Area) south hall near the scaffold storage area and in fire hose cabinet N1V43D110. __________________________________________________________________________________________ 7.3Install fire hose from hose cabinet N1V43D110 (outside the charging pump hallway) to Q1P17V302, A TRAIN CCW SUPPLY HDR DRN, using a temporary adapter. 7.3 Step 7 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 7 of 12 7.4Install temporary drain hose from Q1P17V304, A TRAIN CCW RETURN HDR DRN to floor drain. 7.47.5Open Q1P17V302, A TRAIN CCW SUPPLY HDR DRN. 7.5 7.6Open, Q1P17V304, A TRAIN CCW RETURN HDR DRN. 7.6 7.7Adjust hose cabinet isolation valve to establish 20-60 gpm flow to 1B CHG PUMP, FI-3322B. 7.7 7.8Start 1B CHG PUMP. 7.8 7.9Stop any other running CHG PUMP. 7.9 ****************************************************************************************** CAUTION: The CHG PUMP oil cooler may be damaged if cooling flow exceeds 140 gpm. ****************************************************************************************** 7.10Control hose cabinet isolation valve to maintain 1B CHG PUMP oil temperature less than 160°F on TISH-3306BA. 7.10 7.11Proceed to step 10 7.11 S UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 8 of 12 __ 8Establish alternate cooling to1B CHG PUMP if aligned to B TRN. 88.1Isolate CCW to B Train charging pumps.(B train valves are in the CHG PUMP area.) 8.1 [ ]Close Q1P17V291, B TRAIN CCW SUPPLY HDR ISO. [ ]Close Q1P17V293, B TRAIN CCW RETURN HDR ISO. __________________________________________________________________________________________ NOTE: The intent of the following step is to isolate CCW to the charging pump which will NOT be used (if two pumps are aligned to a single train), to ensure that all firewater cooling established will be directed to the running pump. __________________________________________________________________________________________ 8.2Isolate CCW to 1C CHG Pump. (100 ft, AUX BLDG CHG PUMP rooms) 8.2 [ ]Close Q1P17V0C1C, CCW to 1C CHG PUMP. [ ]Close Q1P17V0C2C CCW FROM 1C CHG PUMP. __________________________________________________________________________________________ NOTE: All materials needed to make temporary connections in the following steps are stored in Room 160 (Hatch Area) south hall near the scaffold storage area and in fire hose cabinet N1V43D110. __________________________________________________________________________________________ 8.3Install fire hose from hose cabinet N1V43D110 (outside the charging pump hallway) to Q1P17V303, B TRAIN CCW SUPPLY HDR DRN using a temporary adapter. 8.3 Step 8 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 9 of 12 8.4Install temporary drain hose from Q1P17V305, B TRAIN CCW RETURN HDR DRN to floor drain 8.48.5Open Q1P17V303, B TRAIN CCW SUPPLY HDR DRN. 8.5 8.6Open Q1P17V305, B TRAIN CCW RETURN HDR DRN. 8.6 8.7Adjust hose cabinet isolation valve to establish 20-60 gpm flow to 1B CHG PUMP on FI-3322B. 8.7 8.8Start 1B CHG PUMP. 8.8 8.9Stop any other running CHG PUMP. 8.9 ****************************************************************************************** CAUTION: The CHG PUMP oil cooler may be damaged if cooling flow exceeds 140 gpm. ****************************************************************************************** 8.10Control hose cabinet isolation valve to maintain 1B CHG PUMP oil temperature less than 160°F on TISH-3306BA 8.10 8.11Proceed to step 10 8.11 S UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 10 of 12 __ 9Establish alternate cooling to 1C CHG PUMP.99.1Isolate CCW to B train. (B train valves are in the CHG PUMP area.) 9.1 [ ]Close Q1P17V291, B TRAIN CCW SUPPLY HDR ISO. [ ]Close Q1P17V293, B TRAIN CCW RETURN HDR ISO. __________________________________________________________________________________________ NOTE: The intent of the following step is to isolate CCW to the charging pump which will NOT be used (if two pumps are aligned to a single train), to ensure that all firewater cooling established will be directed to the running pump. __________________________________________________________________________________________ 9.2IF 1B CHG Pump aligned to B TRN, THEN isolate CCW to 1B CHG Pump. (100 ft, AUX BLDG CHG PUMP rooms) 9.2 [ ]Close Q1P17V0C1B, CCW to 1B CHG PUMP. [ ]Close Q1P17V0C2B CCW FROM1B CHG PUMP __________________________________________________________________________________________ NOTE: All materials needed to make temporary connections in the following steps are stored in Room 160 (Hatch Area) south hall near the scaffold storage area and in fire hose cabinet N1V43D110. __________________________________________________________________________________________ 9.3Install fire hose from hose cabinet N1V43D110 (outside the charging pump hallway) to Q1P17V303, B TRAIN CCW SUPPLY HDR DRN using a temporary adapter. 9.3 Step 9 continued on next page UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 11 of 12 9.4Install temporary drain hose from Q1P17V305, B TRAIN CCW RETURN HDR DRN to floor drain. 9.49.5Open Q1P17V303, B TRAIN CCW SUPPLY HDR DRN. 9.5 9.6Open Q1P17V305, B TRAIN CCW RETURN HDR DRN. 9.6 9.7Adjust hose cabinet isolation valve to establish 20-60 gpm flow to 1C CHG PUMP on FI-3322C. 9.7 9.8Start 1C CHG PUMP. 9.8 9.9Stop any other running CHG PUMP. 9.9 ****************************************************************************************** CAUTION: The CHG PUMP oil cooler may be damaged if cooling flow exceeds 140 gpm. ****************************************************************************************** 9.10Control hose cabinet isolation valve to maintain 1C CHG PUMP oil temperature less than 160°F on TISH-3306CA. 9.10 ****************************************************************************************** CAUTION: To prevent potential seal damage, neither seal injection nor CCW cooling should be restored to RCPs which have lost both seal injection and CCW cooling. ****************************************************************************************** __ 10IF seal injection has been isolated, THEN consult TSC staff to evaluate restoring seal injection. 610 S UNIT 107/15/14 14:02:23FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATERVersion 25.0StepAction/Expected Response Response Not Obtained ATTACHMENT 1 ESTABLISHING FIREWATER COOLING TO A CHARGING PUMP __Page Completed 12ProcedureStepsMain Page 12 of 12 __ 11Consult TSC staff to evaluate long term plant status. 711__ 12Notify control room of RCP seal cooling status.812 -END-UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 2 PLACING 1B CCW PUMP ON A TRAIN __Page Completed 4 Page 1 of 4 __________________________________________________________________________________________ NOTE: This attachment assumes a possible piping break on B train which could jeopardize the A train during the train swap. The 1B CCW pump and HX will be isolated prior to aligning a flow path on the A train. __________________________________________________________________________________________ __ 1Check 1C CCW pump is available. 1Align 1B CCW pump to A train electrically using ATTACHMENT 4, PLACING 1B CCW PUMP ON A TRAIN ELECTRICALLY while continuing with this ATTACHMENT. 1__ 2Verify 1B CCW Pump OFF. 22 __________________________________________________________________________________________ NOTE: The following step is to prevent lifting a CCW relief when the miscellaneous header is isolated. __________________________________________________________________________________________ __ 3IF the 1A CCW pump is running, THEN align CCW to 1B RHR heat exchanger.33CCW TO 1B RHR HX [ ]Q1P17MOV3185B - OPEN __ 4Close CCW pump suction xcon valve. (100' Aux Bldg non-rad, CCW Hx Room) 44 [ ]Q1P17V110C - CLOSED __ 5Close CCW pump discharge header cross connect. (100' Aux Bldg non-rad, CCW Hx Room) 55 [ ]Q1P17V003B - CLOSED S UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 2 PLACING 1B CCW PUMP ON A TRAIN __Page Completed 4 Page 2 of 4 __ 6Verify CLOSED 1B CCW HX outlet valve. (100' Aux Bldg non-rad, CCW Hx Room) 66 [ ]Q1P17V008B - CLOSED __ 7Close CCW supply header xcon. (100' Aux Bldg non-rad, CCW Hx Room) 77 [ ]Q1P17V009B -CLOSED ****************************************************************************************** CAUTION: Monitor CCW surge tank level closely during the following step. Be prepared to add makeup. ****************************************************************************************** __ 8Open the following CCW supply header cross connects: (100' Aux Bldg non-rad, CCW Hx Room) 88 [ ]Q1P17V009C - OPEN [ ]Q1P17V009D - OPEN __ 9Open the following CCW pump discharge header cross connects: (100' Aux Bldg non-rad, CCW Hx Room) 99 [ ]Q1P17V003C - OPEN [ ]Q1P17V003D - OPEN __ 10Open the following CCW suction header cross connects: (100' Aux Bldg non-rad, CCW Hx Room) 1010 [ ]Q1P17V110D - OPEN [ ]Q1P17V110E - OPEN __ 11Verify OPEN 1C CCW HX outlet valve. (100' Aux Bldg non-rad, CCW Hx Room) 1111 [ ]QIP17V008C - OPEN S UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 2 PLACING 1B CCW PUMP ON A TRAIN __Page Completed 4 Page 3 of 4 __ 12Establish Miscellaneous header CCW flow.121212.1Verify A train SW from 1C CCW heat exchanger in MOD 12.112.1 SW FROM 1C CCW HX [ ]Q1P16FV3009C in MOD 12.2Throttle 1C CCW heat exchanger SW discharge flow controller to control CCW temperature. 12.212.2 1C CCW HX DISCH FCV HIC [ ]3009C -ADJUSTED 12.3Verify OPEN CCW to 1A RHR heat exchanger.12.312.3 CCW TO 1A RHR HX [ ]Q1P17MOV3185A - OPEN 12.4Verify 1C CCW Pump started 12.4WHEN 1B CCW Pump electrically aligned to A train per ATTACHMENT 4, PLACING 1B CCW PUMP ON A TRAIN ELECTRICALLY, THEN start 1B CCW Pump. 12.4 __ 13Close CCW suction header cross connect. (100' Aux Bldg non-rad, CCW Hx Room) 1313 [ ]Q1P17V110B - CLOSED S UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 2 PLACING 1B CCW PUMP ON A TRAIN __Page Completed 4 Page 4 of 4 __ 14Close CCW discharge header cross connect. (100' Aux Bldg non-rad, CCW Hx Room) 1414 [ ]Q1P17V003A - CLOSED __ 15Close B TRAIN CCW supply header xcon. (100' Aux Bldg non-rad, CCW Hx Room) 1515 [ ]Q1P17V009A - CLOSED __ 16Close the following 1B CCW HX B TRN SW inlet header isolation valves: (100' Aux Bldg non-rad, CCW Hx Room) 1616 [ ]Q1P16V002A - CLOSED [ ]Q1P16V002B - CLOSED __ 17Close the following 1B CCW HX B TRN SW return header isolation valves: (100' Aux Bldg non-rad, CCW Hx Room) 1717 [ ]Q1P16V008B - CLOSED [ ]Q1P16V008C - CLOSED __ 18Open 1B CCW HX A TRN SW return header isolation valves: (100' Aux Bldg non-rad, CCW Hx Room) 1818 [ ]Q1P16V008D - OPEN [ ]Q1P16V008E - OPEN __ 19Open 1B CCW HX A TRN SW inlet header isolation valves: (100' Aux Bldg non-rad, CCW Hx Room) 1919 [ ]Q1P16V002C - OPEN [ ]Q1P16V002D - OPEN __ 20Return in this procedure to step in effect. 2020 -END-UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 3 PLACING 1B CCW PUMP ON B TRAIN 4 Page 1 of 4 __________________________________________________________________________________________ NOTE: This attachment assumes a possible piping break on A train which could jeopardize the B train during the train swap. The 1B CCW pump and HX will be isolated prior to aligning a flow path on the B train. __________________________________________________________________________________________ __ 1Check 1A CCW pump is available. 1Align 1 B CCW pump to B train electrically using ATTACHMENT 5, PLACING 1B CCW PUMP ON B TRAIN ELECTRICALLY while continuing with this ATTACHMENT. 1__ 2Verify 1B CCW Pump OFF. 22 __________________________________________________________________________________________ NOTE: The following step is to prevent lifting a CCW relief when the miscellaneous header is isolated. __________________________________________________________________________________________ __ 3IF the 1C CCW pump is running, THEN align CCW to 1A RHR heat exchanger.33CCW TO 1A RHR HX [ ]Q1P17MOV3185A - OPEN __ 4Close CCW suction header cross connect (100' Aux Bldg non-rad, CCW Hx Room) 44 [ ]Q1P17V110D - CLOSED __ 5Close CCW pump discharge header cross connects: (100' Aux Bldg non-rad, CCW Hx Room) 55 [ ]Q1P17V003C - CLOSED S UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 3 PLACING 1B CCW PUMP ON B TRAIN 4 Page 2 of 4 __ 6Verify closed 1B CCW HX outlet valve. (100' Aux Bldg non-rad, CCW Hx Room) 66 [ ]Q1P17V008B - CLOSED __ 7Close the CCW supply header cross connect. (100' Aux Bldg non-rad, CCW Hx Room) 77 [ ]Q1P17V009C - CLOSED ****************************************************************************************** CAUTION: Monitor CCW surge tank level closely during the following step. Be prepared to add makeup. ****************************************************************************************** __ 8Open the CCW supply header cross connects. (100' Aux Bldg non-rad, CCW Hx Room) 88 [ ]Q1P17V009A - OPEN [ ]Q1P17V009B - OPEN __ 9Open CCW pump discharge header cross connects: (100' Aux Bldg non-rad, CCW Hx Room) 99 [ ]Q1P17V003A - OPEN [ ]Q1P17V003B - OPEN __ 10Open CCW suction header cross connects: (100' Aux Bldg non-rad, CCW Hx Room) 1010 [ ]Q1P17V110B - OPEN [ ]Q1P17V110C - OPEN __ 11Verify OPEN 1A CCW HX outlet valve (100' Aux Bldg non-rad, CCW Hx Room) 1111 [ ]Q1P17V008A - OPEN S UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 3 PLACING 1B CCW PUMP ON B TRAIN 4 Page 3 of 4 __ 12Establish Miscellaneous header CCW flow.121212.1Verify the B train SW from 1A CCW heat exchanger in MOD. 12.112.1 SW FROM 1A CCW HX [ ]Q1P16FV3009A in MOD 12.2Throttle 1A CCW heat exchanger SW discharge flow controller as necessary to control CCW temperature. 12.212.2 1A CCW HX DISCH FCV HIC [ ]3009A - ADJUSTED 12.3Verify OPEN CCW to 1B RHR heat exchanger.12.312.3 CCW TO 1B RHR HX [ ]Q1P17MOV3185B - OPEN 12.4Verify 1A CCW Pump started 12.4WHEN 1B CCW Pump electrically aligned to B train per ATTACHMENT 5, PLACING 1B CCW PUMP ON B TRAIN ELECTRICALLY, THEN start 1B CCW Pump. 12.4 __ 13Close CCW suction header cross connect valve. (100' Aux Bldg non-rad, CCW Hx Room) 1313 [ ]Q1P17V110E - CLOSED S UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 3 PLACING 1B CCW PUMP ON B TRAIN 4 Page 4 of 4 __ 14Close CCW Pump discharge header cross connects. (100' Aux Bldg non-rad, CCW Hx Room) 1414 [ ]Q1P17V003D - CLOSED __ 15Close CCW supply header cross connect. (100' Aux Bldg non-rad, CCW Hx Room) 1515 [ ]Q1P17V009D - CLOSED __ 16Close the following 1B CCW HX A TRN SW inlet header isolation valves: (100' Aux Bldg non-rad, CCW Hx Room) 1616 [ ]Q1P16V002D - CLOSED [ ]Q1P16V002C - CLOSED __ 17Close the following 1B CCW HX A TRN SW inlet header isolation valves: (100' Aux Bldg non-rad, CCW Hx Room) 1717 [ ]Q1P16V008E - CLOSED [ ]Q1P16V008D - CLOSED __ 18Open the following 1B CCW HX B TRN SW inlet header isolation valves: (100' Aux Bldg non-rad, CCW Hx Room) 1818 [ ]Q1P16V002A - OPEN [ ]Q1P16V002B - OPEN __ 19Open the following 1B CCW HX B TRN SW return header isolation valves. (100' Aux Bldg non-rad, CCW Hx Room) 1919 [ ]Q1P16V008B - OPEN [ ]Q1P16V008C - OPEN __ 20Return in this procedure to step in affect. 2020 -END-UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 4 PLACING 1B CCW PUMP ON A TRAIN ELECTRICALLY 2 Page 1 of 2 __ 1Verify 1B CCW pump OFF. 11****************************************************************************************** CAUTION: Breaker DG-05-1 has alternate DC control power supplied through fuses in HSP-C when 1B CCW PUMP LOCAL-REMOTE switch on HSP-C is in LOCAL. ****************************************************************************************** __ 2Verify LOCAL-REMOTE switch on the HSP-C for 1B CCW PUMP in REMOTE. 22__ 3Rack out Breaker DG05-1. 33__ 4Verify breaker DG05-1 racked out, AND turn key #RE-14291 in the mechanical interlock and remove it. 44__ 5Insert key #RE-14291 into mechanical interlock on 1B CCW pump 4KV disconnect switch 1B (Q1R18A004B-B) and turn it. Key #RE-14291 is now held in place.55__ 6Open 1B disconnect switch, AND verify the position indicator reads SW open. 66__ 7On disconnect 1B turn key #RE-14224 in its mechanical and remove it. 1B disconnect is now locked open. 77__ 8On 1B CCW pump 4KV disconnect switch 1A (Q1R18A004A-A) insert key #RE-14224 into its mechanical interlock and turn it. Key #RE-14224 is now held in place.88__ 9Close 1A disconnect switch, AND verify the position indicator reads SW closed. 99S UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 4 PLACING 1B CCW PUMP ON A TRAIN ELECTRICALLY 2 Page 2 of 2 __ 10On 1A disconnect switch turn key #RE-14625 in the mechanical interlock and remove it. 1A disconnect switch is now locked in the closed position. 1010__ 11Insert key #RE-14625 into the mechanical interlock on breaker DF05-1 and turn it. Key #RE-14625 is now held in place. 1111 __ 12Rack in breaker DF05-1 to the connect position. 1212 __ 13Close DC control power for Breaker DF05-1 AND verify breaker spring charges. 1313 __ 14Verify closed breaker Q1R17BKRFAI4, supply for 1A RM CLR FAN CCW Pump Area. 1414 __ 15Report to the Control Room that the 1B CCW Pump A train electrical line up is complete. 1515 -END-UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 5 PLACING 1B CCW PUMP ON B TRAIN ELECTRICALLY 2 Page 1 of 2 __ 1Verify 1B CCW Pump off 11__ 2Rack out breaker DF05-1 22__ 3Verify breaker DF05-1 is racked out, AND turn key #RE-14265 in the mechanical interlock on breaker DF05-1 and remove it.33__ 4Insert key #RE-14265 into the mechanical interlock on 1B CCW pump 4KV disconnect Switch 1A (Q1R18A004A-A) and turn it. Key #RE-14265 is now held in place.44__ 5Open 1A disconnect switch and verify the position indicator reads SW open. 55__ 6Turn key #RE-14224 in its mechanical interlock on disconnect 1A and remove it.1A disconnect switch is now locked in the open position. 66__ 7Insert key #RE-14224 into its mechanical interlock on 1B CCW pump 4KV disconnect switch 1B (Q1R18A004B-B) and turn it. Key #RE-14224 is now held in place.77__ 8Close 1B disconnect switch. Verify the position indicator reads SW closed. 88__ 9Turn key #RE-14291 in its mechanical interlock and remove it. 1B disconnect switch is now locked in the closed position. 99S UNIT 107/15/14 14:02:23 FNP-1-AOP-9.0LOSS OF COMPONENT COOLING WATER Version 25.0 StepAction/Expected Response Response Not Obtained ATTACHMENT 5 PLACING 1B CCW PUMP ON B TRAIN ELECTRICALLY 2 Page 2 of 2 ****************************************************************************************** CAUTION: Breaker DG05-1 has alternate DC control power supplied through fuses in HSP-C when 1B CCW LOCAL-REMOTE switch on HSP-C is in local ****************************************************************************************** __ 10Verify LOCAL-REMOTE switch on HSP-C for 1B CCW PUMP in REMOTE. 1010 __ 11Insert key #RE-14291 into it mechanical interlock on circuit breaker DG05-1 and turn key. Key #RE-14291 is now held in place.1111 __ 12Rack breaker DG05-1 to the connect position. 1212 __ 13Close DC control power for Breaker DG05-1 AND verify breaker spring charges. 1313 __ 14Verify closed breaker Q1R17BKRFBD4 (1B RM CLR FAN CCW Pump Area) 1414 __ 15Report to the Control Room that the B train Electrical line up for B CCW pump complete. 15 -END-UNIT 1 07/07/15 9:24:45 FNP-1-AOP-4.0 May 31, 2012 Version 20.0 FARLEY NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE FNP-1-AOP-4.0SAFE TYLOSS OF REACTOR COOLANT FLOW RE LAT EDPROCEDURE USAGE REQUIREMENTS PER NMP-AP-003 SECTIONS Continuous Use Remainder of Procedure Reference Use Steps 1 - 2.1 Information Use Approved: David L Reed (for) Operations Manager Effective Date: 09/15/2014 UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.01 Page of 1 1Table of Contents PROCEDURE CONTAINS NUMBER OF PAGES Body 11 Attachment 1 2 UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.01 Page of 11 1A.Purpose This procedure provides actions for response to a loss of forced RCS flow in one or more loops when a reactor trip is not required. In order to prevent a possible reactor power excursion, NO RCP should be restarted while the reactor is critical. This procedure is applicable in Modes 1, 2, 3 and 4. B.Symptoms or Entry Conditions This procedure is entered when forced RCS flow is lost in one or more loops and no reactor trip is required.CAutomatic Actions 1Loss of flow in one loop with reactor power greater than 30% will cause a reactor trip. 2Loss of flow in two loops with reactor or turbine power greater than 10% will cause a reactor trip. DOperational Concerns 1SG level in any affected loop will tend to shrink. 2Thermal shock to the spray nozzle will occur if auxiliary spray is initiated without normal letdown in service. 3The PRT may rupture causing abnormal containment conditions while using PRZR PORVs for pressurizer pressure control. 4To prevent heat exchanger damage, do not attempt restoration of letdown or excess letdown unless the CCW miscellaneous header is aligned to an operating loop. 5In order to prevent a possible reactor power excursion, NO RCP should be restarted while the reactor is critical. 6IF 1B RCP is NOT running, THEN 1A & 1C RCPs are required to provide adequate spray flow through the 1A RCS loop spray valve. UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0StepAction/Expected Response Response Not Obtained __Page Completed 10 Page 2 of 11 __________________________________________________________________________________________ NOTE: Steps 1 through 2.1 are IMMEDIATE OPERATOR actions. __________________________________________________________________________________________ __ 1Check 1A and 1B RCPs - RUNNING. 1Manually close pressurizer spray valve for affected RCP. 1 [ ]1A RCS loop spray valve PK-444C [ ]1B RCS loop spray valve PK-444D __ 2[CA] Maintain SG narrow range level stable at approximately 65% using: 2IF SG level rise cannot be controlled, THEN perform the following: 2 [ ]Main Feedwater Regulating Valves [ ]Main Feedwater Bypass Regulating Valves. [ ]Auxiliary Feedwater Control Valves. 2.1IF main feedwater in service, THEN close the affected SG Main Feedwater Stop Valve(s) 2.1 IF required, THEN momentarily place MDAFW FCV 3227 RESET A TRN or B TRN switches to the RESET position. [ ]1A SG Q1N21MOV3232A [ ]1B SG Q1N21MOV3232B [ ]1C SG Q1N21MOV3232C IF required, THEN momentarily place TDAFWP FCV 3228 RESET switch to the RESET position. 2.2IF Motor Driven auxiliary feedwater in service,THEN close the following for the affected SG.2.2 A Train [ ]MDAFWP TO 1A SG Q1N23MOV3764A [ ]MDAFWP TO 1B SG Q1N23MOV3764D [ ]MDAFWP TO 1C SG Q1N23MOV3764F B Train [ ]MDAFWP TO 1A SG Q1N23MOV3764E [ ]MDAFWP TO 1B SG Q1N23MOV3764B [ ]MDAFWP TO 1C SG Q1N23MOV3764C OR 2.3IF auxiliary feedwater in service, THEN close the affected SG AFW Stop Valve(s) [ ]1A SG Q1N23MOV3350A (FUU4) [ ]1B SG Q1N23MOV3350B (FUU5) [ ]1C SG Q1N23MOV3350C (FUI2) UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0StepAction/Expected Response Response Not Obtained __Page Completed 10 Page 3 of 11 __ 3[CA] Monitor Tavg for all three RCS 3Perform the following. 3 3.1IF the main generator is ON LINE, THEN trip the reactor and go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION 3.1 3.2IF the main generator is OFF LINE, THEN raise Tavg 541°F within 30 minutes3.2 3.2.1Adjust steam dumps to reduce secondary power demand as necessary 3.2.1 3.2.2Verify rod control in MANUAL 3.2.2 3.2.3Stabilize Tavg in the idle loop(s) >541°F while maintaining the running loop(s) <554°F by adjusting rod position and/or boron concentration 3.2.3 3.2.4IF unable to restore Tavg 541°F,THEN trip the reactor and go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION 3.2.4 __ [CA] Maintain PRZR pressure 2200-2300 psig.444.1Control PRZR heaters as required. 4.14.14.2IF 1A and 1B RCPs running, THEN, control pressurizer pressure with both normal spray valves. 4.2Perform the following 4.24.2.1IF 1B RCP running, THEN control pressurizer pressure with PK-444D.4.2.1Step 4 continued on next page UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0StepAction/Expected Response Response Not Obtained __Page Completed 10 Page 4 of 11 __________________________________________________________________________________________ NOTE: Running 1A and 1C RCPs will be required to provide adequate spray flow through the 1A RCS loop spray valve. If possible, the RCP running should accommodate pressurizer spray capability. If available, this will be RCP 1B (preferred) OR both RCP 1A AND 1C.. __________________________________________________________________________________________ 4.2.2IF 1A & 1C RCPs are running, THEN control pressurizer pressure with PK-444C. 4.2.2 4.2.3IF spray flow is adequate, THEN proceed to step 5. 4.2.3 4.2.4IF normal spray NOT available, THEN proceed to step 4.4. 4.2.44.3Proceed to step 5. 4.34.3****************************************************************************************** CAUTION: To prevent PRZR PORV failure, cycling of PRZR PORVs should be minimized. ****************************************************************************************** 4.4IF normal spray not available AND letdown is on service, THEN establish auxiliary spray. 4.4Perform the following: 4.44.4.1Open RCS loop spray valves a)WHEN needed for immediate pressure control, THEN control pressurizer pressure with PRZR PORV.4.4.1 [ ]PK 444C manually open [ ]PK 444D manually open Step 4 continued on next page UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0StepAction/Expected Response Response Not Obtained __Page Completed 10 Page 5 of 11 4.4.2Close RCS NORMAL CHG LINE 1)Open only one PRZR PORV for any RCS pressure reduction. 4.4.2 [ ]Q1E21HV8146 closed 2)Maintain PRT parameters normal using FNP-1-SOP-1.2, REACTOR COOLANT PRESSURE RELIEF SYSTEM 4.4.3Close RCS ALT CHG LINE 4.4.3 [ ]Q1E21HV8147 closed 3)IF any PRZR PORV fails to reclose, THEN close associated PRZR PORV ISO. 4.4.4Open RCS PRZR AUX SPRAY 4.4.4 [ ]Q1E21HV8145 open b)Proceed to step 5 Response Not Obtained Column AND establish normal letdown. __________________________________________________________________________________________ NOTE: Changes in charging flow will cause PRZR pressure fluctuations when auxiliary spray is established. __________________________________________________________________________________________ 4.4.5Operate the following valves as required: 4.4.5 [ ]CHG FLOW FK-122 manually adjusted as required to control pressure [ ]1A LOOP SPRAY VLV PK-444C manually open/closed [ ]1B LOOP SPRAY VLV PK-444D manually open/closed [ ]RCS PRZR AUX SPRAY Q1E21HV8145 open/closed [ ]RCS NORMAL CHG LINE Q1E21HV8146 open/closed [ ]RCS ALT CHG LINE Q1E21HV8147 open/closed 4.4.6Proceed to Step 6. 4.4.6 UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0StepAction/Expected Response Response Not Obtained __Page Completed 10 Page 6 of 11 __ 5Check normal letdown - ESTABLISHED. 5Perform the following: 5****************************************************************************************** CAUTION: CCW to the miscellaneous header is required to prevent damage to the letdown heat exchanger. ****************************************************************************************** 5.1Verify the CCW miscellaneous header is aligned to an operating CCW loop. 5.1 5.2IF letdown has isolated due to a plant transient,THEN establish normal letdown using ATTACHMENT 1, RESTORING LETDOWN. 5.2 5.3IF a letdown isolated due to a system malfunction,THEN perform the following: 5.3 [ ]Attempt to restore any letdown flow using FNP-1-AOP-16.0, CVCS MALFUNCTION. [ ]Continue with applicable steps of this procedure. 5.4WHEN normal letdown restoredAND IF required, THEN return to step 4.4 to establish auxiliary spray. 5.4__ 6[CA] Maintain PRZR level at approximately 22%. 66S UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0StepAction/Expected Response Response Not Obtained __Page Completed 10 Page 7 of 11 __________________________________________________________________________________________ NOTE: In Mode 3 with reactor trip breakers closed AND rod control enabled, loss of two RCP busses requires actions to restart RCP(s) or de-energize all CRDMs within 1 hour per Tech Spec 3.4.5, Condition C. __________________________________________________________________________________________ __ 7Within six hours of the loss of RCS flow complete the following: 777.1IF the unit is in Mode 1 or 2, THEN place unit in Mode 3 using the following procedures: 7.17.1 [ ]FNP-1-UOP-3.1, POWER OPERATION [ ]FNP-1-UOP-2.1, SHUTDOWN OF UNIT FROM MINIMUM LOAD TO HOT STANDBY 7.2WHEN unit in Mode 3 or 4, THEN verify all reactor trip and reactor trip bypass breakers open. 7.2Secure both CRDM MG sets using FNP-1-SOP-41.0, CONTROL ROD DRIVE AND POSITION INDICATION SYSTEM.7.2 [ ]Reactor Trip Breaker A [ ]Reactor Trip Breaker B [ ]Reactor Trip Bypass Breaker A [ ]Reactor Trip Bypass Breaker B __________________________________________________________________________________________ NOTE: Step 7 must be complete before continuing with this procedure. __________________________________________________________________________________________ __ 8Check at least one RCP - RUNNING. 8Perform the following. 8 8.1Secure any dilution in progress. 8.1 8.2Start one RCP using FNP-1-SOP-1.1, REACTOR COOLANT SYSTEM. 8.2Step 8 continued on next page UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0StepAction/Expected Response Response Not Obtained __Page Completed 10 Page 8 of 11 8.3WHEN at least one RCP running, THEN go to FNP-1-UOP-2.1, SHUTDOWN OF UNIT FROM MINIMUM LOAD TO HOT STANDBY. 8.3 8.4IF no RCP can be established running, THEN proceed to step 10. 8.4__ 9Go To UOP-HOT STANDBY 99 _________________________________________________________________________________________ NOTE: During natural circulation, loop transit time will be on the order of 10 minutes. Temperature trends will be of more value than actual temperatures . This will take 20 to 30 minutes Changes in SG feeding or steaming rates must be made slowly to prevent rapid RCS pressure changes. _________________________________________________________________________________________ __ 10Verify adequate natural circulation. 101010.1Check SG pressures stable or falling. 10.110.110.2Check SUB COOLED MARGIN MONITOR indication greater than 16°F subcooled in CETC mode. 10.210.210.3Check RCS hot leg temperatures stable or falling. 10.310.3RCS HOT LEG TEMP [ ]TR 413 10.4Check core exit T/Cs stable or falling. 10.410.410.5IF natural circulation NOT adequate, THEN dump steam at a faster rate. 10.510.5Step 10 continued on next page UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0StepAction/Expected Response Response Not Obtained __Page Completed 10 Page 9 of 11 10.6Begin taking natural circulation logs. 10.610.6****************************************************************************************** CAUTION: During natural circulation with low decay heat loads, overfeeding the SGs will result in excessive cooldown with no apparent rise in SG level. ****************************************************************************************** __ 11[CA] Maintain SG narrow range levels at approximately 65%. 1111Control MDAFWP flow. MDAFWP TO 1A(1B,1C) SG FLOW CONT [ ]HIC 3227AA adjusted [ ]HIC 3227BA adjusted [ ]HIC 3227CA adjusted Control TDAFWP flow. TDAFWP TO 1A(1B,1C) SG FLOW CONT [ ]HIC 3228AA adjusted [ ]HIC 3228BA adjusted [ ]HIC 3228CA adjusted __ 12[CA] Monitor CST level. 121212.1LI-4005 remains in the normal operating band 32-39'. 12.1Contact Chemistry to maximize make up to the CST. 12.112.2LI-4005 indicates >26 ft LI-4132A indicates >11 ft LI-4132B indicates >11 ft 12.2IF adequate make up can NOT be established,THEN notify the Shift Manager and consideration should be given to reducing SGBD flow. 12.212.3LI-4005 indicates >5.3 ft LI-4132A indicates >5.3 ft LI-4132B indicates >5.3 ft 12.3IF CST level less than 5.3 ft, THEN align AFW pump suction to SW using FNP-1-SOP-22.0, AUXILIARY FEEDWATER SYSTEM. 12.3S UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0StepAction/Expected Response Response Not Obtained __Page Completed 10 Page 10 of 11 __ 13Verify reactor makeup system aligned. 13Manually control reactor makeup system using FNP-1-SOP-2.3, CHEMICAL AND VOLUME CONTROL SYSTEM REACTOR MAKEUP CONTROL SYSTEM. 1313.1Verify BORIC ACID MKUP FLOW FK 113 - ADJUSTED TO DELIVER GREATER THAN EXISTING RCS BORON CONCENTRATION. 13.113.2Verify reactor makeup system - IN AUTOMATIC MODE. 13.2MKUP MODE SEL SWITCH [ ]N1E21HS2100Q in AUTO MKUP MODE CONT SWITCH [ ]N1E21HS2100P to START __ [CA] Maintain shutdown margin adequate.141414.1Direct Chemistry to sample RCS for boron concentration using FNP-1-CCP-651, SAMPLING THE REACTOR COOLANT SYSTEM at least once per two hours. 14.114.1Step 14 continued on next page UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0StepAction/Expected Response Response Not Obtained __Page Completed 10 Page 11 of 11 __________________________________________________________________________________________ NOTE: Natural circulation may cause inadequate RCS mixing. Any boration should be at a continuous rate not exceeding 65 gpm. __________________________________________________________________________________________ 14.2Verify shutdown margin using: 14.2Borate RCS using FNP-1-AOP-27.0, EMERGENCY BORATION. 14.2 [ ]FNP-1-STP-29.1, SHUTDOWN MARGIN CALCULATION (TAVG 547F)OR [ ]FNP-1-STP-29.2, SHUTDOWN MARGIN CALCULATION (TAVG < 547 °F OR BEFORE THE INITIAL CRITICALITY FOLLOWING REFUELING).14.3Monitor source range count rate stable or falling. 14.3Borate RCS using FNP-1-AOP-27.0, EMERGENCY BORATION. 14.3__ 15[CA] Maintain hot standby conditions. 1515Maintain steam header pressure less than or equal to 1005 psig. Maintain average core exit T/C temperature less than 600°F. __ 16 RCS cooldown NOT required, THEN return to step 8. 16Go to FNP-1-ESP-0.2, NATURAL CIRCULATION COOLDOWN TO PREVENT REACTOR VESSEL STEAM HEAD VOIDING to initiate RCS cooldown. 16-END-UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0ATTACHMENT 1 RESTORING LETDOWN 2 Page 1 of 2 __________________________________________________________________________________________ NOTE: This attachment assumes that letdown was lost due to a plant transient and that no system malfunction has occurred. __________________________________________________________________________________________ __ 1[CA] WHEN plant conditions permit, THEN restore normal letdown flow as follows: 11.1Verify closed all letdown orifice isolation valves. 1.1 LTDN ORIF ISO 45 GPM [ ]Q1E21HV8149ALTDN ORIF ISO 60 GPM [ ]Q1E21HV8149B[ ]Q1E21HV8149C1.2Verify LP LTDN PRESS PK 145 in MANUAL and adjust the demand signal to 50% or less. 1.2 1.3Verify that LTDN HX OUTLET TEMP TK 144 is in AUTO, and set at 3.3 to maintain temperature at approximately 100 F.1.3 1.4Verify that the VCT HI LVL DIVERT VLV LCV-115A position indicator VCT light is lit and the handswitch is in the AUTO position. 1.4 1.5Verify that LTDN HI TEMP DIVERT VLV Q1E21TCV143, VCT light is lit and the handswitch is in the VCT position. 1.5 1.6IF necessary, , THEN OPEN both LTDN LINE PENE RM ISO's Q1E21HV8175A and B from the Penetration Room Isolation Panel. 1.6 1.7Verify open LTDN LINE CTMT ISO Q1E21HV8152 1.7 1.8Verify open both LTDN LINE ISO Q1E21LCV459 and Q1E21LCV460. 1.8 1.9Verify CHG FLOW FK 122 is in MAN AND establish the required minimum charging flow for the number of orifices to be placed on service. (18 gpm for 1 orifice or 40 gpm for two orifices) 1.9 1.10OPEN LTDN ORIF ISO 60 GPM Q1E21HV8149B or C to establish approximately 60 gpm Letdown flow.1.10Step 1 continued on next page UNIT 1 07/07/15 9:24:45FNP-1-AOP-4.0LOSS OF REACTOR COOLANT FLOWVersion 20.0ATTACHMENT 1 RESTORING LETDOWN 2 Page 2 of 2 1.11Verify that LP LTDN PRESS PK 145 is set between 4.3-7.5 to maintain the desired Letdown Pressure between 260-450 psig. 1.11 1.12IF necessary, THEN adjust LP LTDN PRESS PK 145 in MANUAL to stabilize Letdown Pressure at the desired value. 1.12 1.13Place LP LTDN PRESS PK 145 in AUTO and verify that Letdown pressure is maintained at the desired value.1.13 1.14Verify that LTDN HX OUTLET TEMP TK 144 is maintaining Letdown temperature at approximately 100F.1.14 [ ]TI-116 VCT TEMP [ ]TI-143 DIVERT LTDN HX TEMP [ ]TI-144 CCW LTDN HX TEMP 1.15IF normal letdown flow NOT established, THEN attempt to restore any letdown flow using FNP-1-AOP-16.0, CVCS MALFUNCTION. 1.15 1.16IF normal letdown flow established, THEN initiate actions to establish flow through the demineralizers per FNP-1-SOP-2.1, CHEMICAL AND VOLUME CONTROL SYSTEM, PLANT STARTUP AND OPERATION.. 1.15 -END-FNP ILT-38 JPM Page 1 of 9 Developer S. Jackson Date: 4/8/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 jpm g CRO-033 MOD TITLE: Perform Section 4.9 of STP-5.0, Full Length Control Rod Operability Test ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: X SIMULATOR CONTROL ROOM PLANT PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: IC-217 (Base - 123) ALTERNATE PATH X TIME CRITICAL PRA JPM DIRECTIONS: 1. Examinee will be provided a marked up copy of STP-5.0. All other references of the simulator will be available at the examinee's discretion. a. STP-5.0 will be marked as follows: i. Sections 4.1, step 1 &2, 4.2 through 4.8 marked N/A. 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise. 3. NO Cues are required by the examiner. TASK STANDARD: Upon successful completion of this JPM, the examinee will: Inserted Control Bank D in BANK control > 10 but <15 steps per Section 4.9 of STP-5.0; Initiate an Rx trip due to rods continue to move. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) EXAMINER: FNP ILT-38 JPM Page 2 of 9 Simulator Setup EVENT DESCRIPTION ACTION DETAILS Reset into IC-217 Acknowledge computer alarms Run / Freeze Simulator Clear Ovation Alarms Acknowledge Alarms Turn Horns ON Run / Freeze Simulator FNP ILT-38 JPM Page 3 of 9 CONDITIONS When I tell you to begin, you are to perform step 4.9 of STP-5.0, Full Length Control Rod Operability Test. The conditions under which this task is to be performed are: a. The Plant is at 72.5 % power. b. Previous STP-5.0 performance was UNSAT due to Control Bank D testing. c. Maintenance is complete and a partial performance of STP-5.0 is required for Post Maintenance Acceptance Testing. Your task is to perform Section 4.9 of STP-5.0. INITIATING CUE: "You may begin." EVALUATION CHECKLIST ELEMENTS: STANDARDS: RESULTS: (CIRCLE) START TIME: NOTE: NMP-OS-001 Section 4.3: Step 3 states that the OATC is required to obtain concurrence prior to performing planned reactivity manipulations. ALSO, Step 6 REQUIRES that these manipulations are PEER CHECKED. If requested prior to rod motion CUE: "The SS concurs with your Reactivity manipulation." "A PEER CHECK request is acknowledged" Note: The following steps are from STP-5.0, Full Length Control Rod Operability Test, Section 4.9 1. 1 RECORD the STEP COUNTER reading for Control Bank D Groups 1 and 2. RECORD 190 steps for both Control Bank D: o Group 1 o Group 2 S / U *2. 2 Place the ROD CONTROL BANK SELECTOR SWITCH in the CB D position POSITION the ROD BANK SELECTOR SWITCH CLOCKWISE-to the CBD position S / U 3. 3 Verify indicated control rod speed is approximately 48 steps per min on SI-408. Observes SI-408 approximately 48 steps per min. S / U FNP ILT-38 JPM Page 4 of 9 ELEMENTS: STANDARDS: RESULTS: (CIRCLE) *4. 4 IF at power, perform the following: a Using CONTROL ROD MOTION switch, drive Control Bank D IN 1 to 2 steps. Step Counter change. change. Moves CONTROL ROD MOTION switch UP, and releases when 1 to 2 steps are indicated on Step Counters D1 and D2. S / U NOTE: The actions of the following element will cause FF5, COMP ALARM ROD SEQ/DEV OR PR FLUX TILT, alarm. This is an expected alarm per P&L 2.10 *5. b While observing RODS IN light, using CONTROL ROD MOTION switch, drive Control Bank D IN a total of 10 steps from value recorded in Step 1 Moves CONTROL ROD MOTION switch UP, and releases when 10 steps are indicated on Step Counters D1 and D2. S / U *6. c Using DRPI system indicators, check individual rod movement. Observes rods move in on DRPI. S / U 7. d IF individual rod movement indicated, perform the following: (1) Mark Step 4.e(1) AND Step 4.e(2) N/A. (2) Proceed to Step 4.f. Marks step 4.e(1) and 4.e(2) N/A S / U 8. e IF individual rod movement NOT indicated, perform the following: (1) Review Precaution and Limitation 6. (2) While observing RODS IN light, using CONTROL ROD MOTION switch, drive Control Bank D up to 5 additional steps IN OR until DRPI indication changes. This step is N/A S / U FNP ILT-38 JPM Page 5 of 9 ELEMENTS: STANDARDS: RESULTS: (CIRCLE) Note: When the applicant releases the Rod Control Switch, the rods will continue to move out. This begins the ALTERNATE path *9. f While observing RODS OUT light, using CONTROL ROD MOTION switch, return Shutdown Bank A to original position recorded in Step 1. Moves CONTROL ROD MOTION switch in DOWN and releases when the rods are returned to normal position. S / U Insert malfunction when Applicant places the CONTROL ROD MOTION switch in DOWN (Withdraws rods) Note: The following steps are from AOP-19, Malfunction of Rod Control System. Note: Since the Rod Control Selector Switch is in the CB D position, the applicant may try selecting MANUAL first. This will not stop rod motion. 10. 1.1 IF rod control in AUTO, THEN place rod control in MANUAL. Rods are in CDB. Goes to RNO column. S / U 11. 1.1 (RNO) IF rod control in MANUAL THEN place in AUTO 1.1.1 IF AUTO rod motion due to TAVG/TREF mismatch, THEN verify rod motion stops when TAVG is within 1 degree of TREF. Rod Control Switch placed in AUTO. Observes rods continue to move. This step is N/A S / U 12. 1.2 Check Rod motion stopped Observes rods continue to move S / U *13. 1.2.1 (RNO) Trip the reactor Either Reactor Trip handswitch to taken to TRIP (Counter Clockwise). Observes Rx trip breakers open. S / U FNP ILT-38 JPM Page 6 of 9 ELEMENTS: STANDARDS: RESULTS: (CIRCLE) 14. 1.2.2 (RNO) Go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. S / U Note: The following steps are from FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. It is the intent to allow the applicant to perform the Immediate Operator Actions of EEP-0 then terminate the JPM 15. 1 Check Reactor Trip Observes - Rx trip and Bypass breakers open, nuclear power falling and DRPI rod bottom lights lit. S / U 16. 2 Check turbine trip Observes TSLB2, 14-1, 14-2, 14-3, 14-4 lights are LIT S / U 17. 3 Verify power to 4160V ESF busses 3.1 4160V ESF Busses - AT LEAST ONE ENERGIZED

Observes 1F and 1G power available lights are LIT

S / U 18. 3.2 4160V ESF Busses - BOTH TRAINS ENERGIZED Observes 1F & 1K and 1G & 1L power available lights are LIT S / U 19. 3.3 [CA] Verify operating diesel generator(s) - SUPPLIED FROM AT LEAST ONE SW PUMP This step is N/A S / U 20. 4 Check SI Status 4.1 Check any SI actuated indication. [] BYP & PERM SI ACTUATED status light [] MLB-1 1-1 LIT [] MLB-1 11-1 LIT Observes lights NOT LIT S / U FNP ILT-38 JPM Page 7 of 9 ELEMENTS: STANDARDS: RESULTS: (CIRCLE) 21. 4.1(RNO) Check SI required 4.1.1 IF any setpont and coincidence shown in the Table below has been reached or exceeded THEN Si is required Observes parameters do not exceed setpoint S / U 22. 4.1.2 IF SI is required, THEN actuate SI This step is N/A S / U 23. Informs the Shift Supervisor that their IOA's of EEP-0 are complete. CUE: SS acknowledges the completion of the IOA's of EEP-0 S / U STOP TIME Terminate when the IOAs of EEP-0 are complete CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number. GENERAL

REFERENCES:

FNP ILT-38 JPM Page 8 of 9 1. PROCEDURE: FNP-1-AOP-19.0, V 31.1 2. FNP-1-EEP-0.0, Rev 46.1 3. FNP-1-STP-5.0, ver 31 4. K/As: 001A2.11 - 4.4 / 4.7 001A3.02 - 3.7 / 3.6 001AA1.05 - 4.3 / 4.2 GENERAL TOOLS AND EQUIPMENT: Provide/Acquire: 1. A marked up copy of FNP-1-STP-5.0; mark up as described in INSTRUCTIONS. 2. AOP-19.0, EEP-0.0 will be acquired from Simulator (IOA pages will require cleaning/replacements) Critical ELEMENT justification: 1. Not critical - This is a logging step only. 2. CRITICAL- Required for task completion, movement of PROPER rod bank. 3. Not critical - Check step only 4 - 6 CRITICAL- Required for task completion. 9. CRITICAL- Required for task completion. 10-12 Not critical - No effect on rods 13. CRITICAL - Required due to malfunction of rod control causing loss of Rector control. 14-23 Not critical - No actions required. COMMENTS: FNP ILT-35 JPM HANDOUT Pg 1 of 1 jpm g CONDITIONS When I tell you to begin, you are to perform Section 4.9 of STP-5.0, Full Length Control Rod Operability Test. The conditions under which this task is to be performed are: a. The Plant is at 72.5 % power. b. Previous STP-5.0 performance was UNSAT due to Control Bank D testing. c. Maintenance is complete and a partial performance of STP-5.0 is required for Post Maintenance Acceptance Testing. Your task is to perform Section 4.9 of STP-5.0.

FARLEY Unit 1 SAFETY RELATED FNP-1-STP-5.0 Full Length Control Rod Operability Test PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous Reference Information VERSION SUMMARY Version 31.0 DESCRIPTION TABLE OF CONTENTS 1.0 PURPOSE2.0 PRECAUTIONS AND LIMITATIONS (Ref. Core Analysis procedure NF-CAP-200, Attachment 1 Step 14) (CR 2009100757)

2.0 PRECAUTIONS AND LIMITATIONS (continued) (CR2005105949) (CR 733783, 851994) 3.0 INITIAL CONDITIONS (OR 1-98-498)(OR 1-98-498)(OR 1-98-498)(IR 2-96-025) NOTE 4.0 INSTRUCTIONS NOTE 4.1 SECTION DETERMINATIONgo togo togo to4.2 ROD OPERABILITY TESTING DURING REACTOR STARTUP MarkNOTE completeCheckACCEPTANCE CRITERIA Go to

4.3 ROD OPERABILITY TESTING PER FNP-0-ETP-3643 MarkNOTE completeCheckACCEPTANCE CRITERIA Go to4.4 TESTING SHUTDOWN BANK A Record PlacecheckperformdriveCheckCheckdrivecheckperformMarkProceedto 4.4 TESTING SHUTDOWN BANK A (continued) performReviewdrivereturncheck*CheckACCEPTANCE CRITERIA RecordperformpullCheckCheckpullcheckreturncheck 4.4 TESTING SHUTDOWN BANK A (continued) *CheckACCEPTANCE CRITERIA RecordperformReturnCheckcheckcheck4.5 TESTING SHUTDOWN BANK B Record PlacecheckperformdriveCheckCheck 4.5 TESTING SHUTDOWN BANK B (continued) drivecheckperformMarkProceedtoperformReviewdrivereturncheck*CheckACCEPTANCE CRITERIA RecordperformpullCheckCheckpullpull 4.5 TESTING SHUTDOWN BANK B (continued) checkreturncheck*CheckACCEPTANCE CRITERIA RecordperformReturnCheckcheckcheck4.6 TESTING CONTROL BANK A Record Placecheck 4.6 TESTING CONTROL BANK A (continued) performdriveCheckCheckdrivecheckperformMarkProceedtoperformReviewdrivereturncheck*CheckACCEPTANCE CRITERIA RecordperformpullCheckCheck 4.6 TESTING CONTROL BANK A (continued) pullcheckreturncheck*CheckACCEPTANCE CRITERIA RecordperformReturnCheckcheckcheck4.7 TESTING CONTROL BANK B Record Placecheck 4.7 TESTING CONTROL BANK B (continued) performdriveCheckCheckdrivecheckperformMarkProceedtoperformReviewdrivereturncheck*CheckACCEPTANCE CRITERIA Record 4.7 TESTING CONTROL BANK B (continued) performpullCheckCheckpullcheckreturncheck*CheckACCEPTANCE CRITERIA RecordperformReturnCheckcheckcheck 4.8 TESTING CONTROL BANK C Record PlacecheckperformdriveCheckCheckdrivecheckperformMarkProceedtoperformReviewdrivereturn 4.8 TESTING CONTROL BANK C (continued) check*CheckACCEPTANCE CRITERIA RecordperformpullCheckCheckpullcheckreturncheck*CheckACCEPTANCE CRITERIA Record 4.8 TESTING CONTROL BANK C (continued) performReturnCheckcheckcheck4.9 TESTING CONTROL BANK D Record PlacecheckperformdriveCheckCheckdrivecheckperformMarkProceedto 4.9 TESTING CONTROL BANK D (continued) performReviewdrivereturncheck*CheckACCEPTANCE CRITERIA RecordperformpullCheckCheckpullcheckreturn 4.9 TESTING CONTROL BANK D (continued) check*CheckACCEPTANCE CRITERIA RecordperformReturnCheckcheckcheck4.10 P TO A CONVERTER CHECK NOTE selectrecordControl Bank Bank Position Display ReturnComparenotify NOTE 5.0 ACCEPTANCE CRITERIA 6.0 RECORDS QA Record (X) Non-QA Record (X) Record Generated Retention Time R-Type

7.0 REFERENCES

BANK D ROD MOVEMENT FOR TROUBLESHOOTING NOTE Record PlacecheckdrivereturnreturnCheckcheckcheck ROD OPERABILITY CHECKS NOTE SHUTDOWN BANK A SHUTDOWN BANK B CONTROL BANK A CONTROL BANK B CONTROL BANK C CONTROL BANK D SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SURVEILLANCE TEST REVIEW SHEET Mode(s) Requiring Test:Technical Specification Reference To Be Completed by Test Performer(s) Test Performers (Printed Name) Initial Signature Completed byComponent or Train TestedENTIRE PROCEDURE WAS PERFORMEDPARTIAL PROCEDURE WAS PERFORMEDTest CompletedSatisfactory Unsatisfactory Performing Review Group Reviewed byCommentsEngineering Support Group ScreeningScreened byComments UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 Jun 1, 2015 Version 31.1 FARLEY NUCLEAR PLANT ABNORMAL OPERATING PROCEDURE FNP-1-AOP-19.0 S A F E T Y MALFUNCTION OF ROD CONTROL SYSTEM R E L A T E D PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: Remainder of Procedure

Reference:

Section 1.1 Information: NONE Approved: David L Reed Effective Date: 06/24/2015 Operations UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 1 Page of 1 1 Table of Contents PROCEDURE CONTAINS NUMBER OF PAGES Body 25

UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 1 Page of 1 1 A. Purpose This procedure provides actions for response to a malfunction of the rod control system. This procedure is applicable when the rod control system is capable of rod withdrawal. This procedure is NOT applicable for rod position indication malfunctions. _______________________________________________________________________________________ NOTES: A rod is considered "dropped" if it has fallen completely to the bottom of the core. A rod is considered "deeply misaligned" if its DRPI indication disagrees with the group step counter by greater than 45 steps. A rod is considered "misaligned" if its DRPI indication disagrees with the group step counter by greater than 12 steps but less than or equal to 45 steps. "Dropped" and "Deeply Misaligned" rods will be treated the same. Technical Specifications requires that all individual indicated rod positions be within 12 steps of their group step counter demand position. In general the rod group step counters and the DRPI rod position indications should agree within + four steps. _______________________________________________________________________________________ B. Symptoms or Entry Conditions I. This procedure divided into the following sections. a. Section 1.1 Uncontrolled Continuous Rod Motion In All Modes. b. Section 1.2 Misaligned Rods In Mode 1. c. Section 1.3 Dropped Rods in Mode 1. d. Section 1.4 Dropped Or Misaligned Rods In Modes 2 Through 5. II. A section is entered when a malfunction of the rod control system is indicated by any of the following: a. Significant reactivity insertion due to undesired rod motion. b. Failure of a control bank to move when required. c. One or more dropped rods in Mode 1 OR during reactor startup. d. One or more rods misaligned in Mode 1 OR during reactor startup. RECORDS QA Record (X) Non-QA Record (X) Record Generated Retention Time R-Type X FNP-1-AOP-19.0 LP H06.001 UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.1 Uncontrolled Continuous Rod Motion In All Modes __Page Completed 3 ProcedureStepsMain Page 1 of 3 __________________________________________________________________________________________ NOTE: Step 1 is an IMMEDIATE OPERATOR action. __________________________________________________________________________________________ __ 1 IF undesired rod motion occurring, THEN stop rod motion. 2 1.1 IF rod control in AUTO, THEN place rod control in MANUAL. 1.1 IF rod control in MANUAL, THEN place rod control in AUTO. 2.1 __________________________________________________________________________________________ NOTE: In AUTO rod control, rods will step OUT if TAVG less than TREF by at least 1.5 degrees, and Rods will step IN if TAVG greater than TREF by at least 1.5 degrees. __________________________________________________________________________________________ 1.1.1 IF AUTO rod motion due to TAVG/TREF mismatch, THEN verify rod motion stops when TAVG is within 1 degree of TREF. 2 1.2 Check Rod motion - STOPPED. 1.2 Perform the following: 2.2 1.2.1 Trip the reactor. 2.2.1 1.2.2 Go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. 2.2.2 __ 2 Evaluate undesired rod motion. 2.2 2.1 Check N-44 Operable. 2.1 Go to FNP-1-AOP-100.0, INSTRUMENTATION MALFUNCTION. 2.2.1 2.2 Check selected Pimp channel Operable. 2.2 Go to FNP-1-AOP-100.0, INSTRUMENTATION MALFUNCTION. 2.2.2 S UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.1 Uncontrolled Continuous Rod Motion In All Modes __Page Completed 3 ProcedureStepsMain Page 2 of 3 __ 3 Check the following alarms - CLEAR. 3. IF in Mode 1 or 2, THEN perform the following: Annunciator FE1 - CONT ROD BANK POSITION LO Annunciator FE2 - CONT ROD BANK POSITION LO-LO Borate as necessary to restore Rod height. Initiate the following: TS 3.1.5 TS 3.1.6 __ 4 Restore Tavg to program by adjusting turbine load. 4. Adjust RCS boron concentration to restore Tavg to program. __ 5 Maintain power distribution when greater than or equal to 50% power: 5.1 AFD - WITHIN LIMITS SPECIFIED IN COLR (TS 3.2.3) 5.2 QPTR - LESS THAN OR EQUAL TO 1.02 5.1 Reduce power to less than 50% within 30 minutes. 5.2 Initiate TS 3.2.4. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.1 Uncontrolled Continuous Rod Motion In All Modes __Page Completed 3 ProcedureStepsMain Page 3 of 3 __________________________________________________________________________________________ NOTE: Any transient resulting from undesired rod motion should consider the following limits when evaluating continued plant operation. Pressurizer level greater than 15% Pressurizer Pressure greater than 2100 psig SG narrow range levels between 35% and 75% TAVG between 541°F and 580°F Control Rod Bank position Lo-Lo Annunciator FE2 Clear Delta I within limits specified in the COLR __________________________________________________________________________________________ __ 6 IF rod motion is NOT available in AUTO OR MANUAL, AND rod motion required, THEN perform the following: 3 3.1 6.1 Trip the reactor. 2.2.1 6.2 Go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. 2.2.2 __ 7 Initiate repairs as necessary. __ 8 Go to procedure in effect. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.2 Misaligned Rods In Mode 1 __Page Completed 10 ProcedureStepsMain Page 1 of 10 __ 1 Stop any turbine load change in progress. 3 __ 2 Check only one Rod - Misaligned. 2 Trip the Reactor. 3 2.1 Go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION 3.1 __ 3 Check misaligned Rod - Misaligned By Greater Than 12 Steps. 3 Go to FNP-1-SOP-41.0, CONTROL ROD DRIVE AND POSITION INDICATION SYSTEM, to address restoration of the misaligned rod. 3 __ 4 Check rod misaligned less than or equal to 45 steps from demand. 4 Go to Section 1.3, Dropped Rods in Mode 1. 3.1.1 __ 5 Initiate TS 3.1.4 and TS 3.1.7. 3.1.1 __________________________________________________________________________________________ NOTE: Power reduction as soon as practical after the rod drop occurs minimizes local fuel power distribution variances and the chances of fuel damage. Although TS 3.1.4 requires power to be reduced to less than 75% within 2 hours, a target of achieving reactor power level less than 75% in one hour meets the "as soon as practical" objective. __________________________________________________________________________________________ __ 6 Reduce Thermal Power to less than 75% within 1 hour from the time of discovery of Rod Misalignment using FNP-1-UOP-3.1, POWER OPERATION. 3.1.1 __ 7 Check fuel preconditioned power level greater than or equal to 90% per reactor Engineering. 7 Continue power reduction to the greater of the following, at a rate not to exceed 25% per hour: 25% RTP below the fuel's preconditioned power level. OR 30% RTP 3.1.1 __ 8 [CA]Maintain reduced power level until rod recovery initiated. 3.1.2 UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.2 Misaligned Rods In Mode 1 __Page Completed 10 ProcedureStepsMain Page 2 of 10 __ 9 Notify the Shift Manager of misaligned rod. 13 __ 10 Direct Reactor Engineering to develop a misaligned recovery plan. 3.2 __ 11 [CA]Maintain Tavg at program by performing the following as appropriate: 3.2 Adjust turbine load. Dilute or borate. Use manual Rod control __ 12 [CA]Maintain power distribution when greater than or equal to 50% power. 3.2.1 12.1 AFD - within limits specified in the COLR. 12.1 Adjust power and/or rods until one of the following are met: 3.2.2 AFD within plus or minus 5% of target. OR Reactor power less than 50%. 12.2 QPTR - less than or equal to 1.02. 12.2 Initiate TS 3.2.4. 3.3 S UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.2 Misaligned Rods In Mode 1 __Page Completed 10 ProcedureStepsMain Page 3 of 10 __ 13 Initiate action to determine cause and repair Rod Control malfunction. 3.4 __ 14 Record the following in the Control Room Log. Time of Rod misalignment Misaligned Rod number Misaligned Rod position (DRPI) Affected bank position (Demand and DRPI) Initial power level 14 IF exact time of Rod misalignment is NOT known, THEN use time of previous Rod alignment verification performed in FNP-1-STP-1.0, OPERATION SHIFT AND DAILY SURVEILLANCE REQUIREMENTS. 3.4 __ 15 Check if Rod alignment should be initiated: 4 15.1 Direct cause of misaligned Rod known and corrective actions have been taken. 15.1 Do not proceed with rod realignment until approval to do so is obtained from reactor Engineering and Operations Management. 4.2 15.2 Rod to be recovered is within 120 hours of initial misalignment. 15.2 Notify nuclear fuels to determine impact on Safety Analysis and recovery effort. 4.3 15.2.1 IF Safety Analysis cannot be confirmed within 120 hours, THEN, go to FNP-1-UOP-3.1, POWER OPERATION and initiate a unit shutdown to Mode 3. 15.3 Misaligned rod recovery plan in place. 15.3 WHEN misaligned rod recovery plan in place, continue with step 16. 6 __ 16 [CA]Maintain reduced power level during realignment. 6 __ 17 Maintain power distribution limits: AFD QPTR 7 __ 18 [CA]Maintain Tavg within 3°F of Tref during realignment. 8 UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.2 Misaligned Rods In Mode 1 __Page Completed 10 ProcedureStepsMain Page 4 of 10 __ 19 Record the following in the Control Room Log: Misaligned rod position (DRPI). Affected bank position (Demand and DRPI) __ 20 Position ROD BANK SELECTOR SWITCH to affected bank. __ 21 Determine if it is desirable to position the Misaligned Rod to Affected Bank position. 22 Go to step 31 to position the Affected Bank to the Misaligned Rod. 161 22 IF not already in progress, THEN commence FNP-1-STP-37.0, POWER DISTRIBUTION SURVEILLANCE. __ 23 Disconnect all lift coils in the affected bank except for the misaligned Rod. __________________________________________________________________________________________ NOTE: ROD CONTROL SYS URGENT FAILURE alarm will annunciate when movement of misaligned Rod is initiated. Per NMP-OS 001, REACTIVITY MANAGEMENT PROGRAM, the 3 step rod withdrawal limitation may be suspended during misaligned rod retrieval. Rod withdrawal should be limited to 1 to 4 steps per minute and should not exceed 20 steps over a period of five minutes. __________________________________________________________________________________________ __ 24 Withdraw or insert the misaligned Rod in Bank Select, per the recommended rod withdrawal rate to align with current bank DRPI position. 24 IF the misaligned Rod fails to move, THEN perform the following: 24.1 Connect lift coils opened instep 23. 1Step 24 continued on next page UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.2 Misaligned Rods In Mode 1 __Page Completed 10 ProcedureStepsMain Page 5 of 10 24.2 Reset step counter(s) to value recorded in step 20. 24.3 Notify maintenance to determine cause and repair Rod control malfunction. 24.4 Determine if misaligned rod is trippable: 2 24.4.1 IF rod control system malfunction is preventing rod motion, THEN misaligned rod is considered trippable. 24.4.2 IF rod control system is properly demanding motion and no motion occurs, THEN misaligned rod is considered untrippable. 24.5 IF misaligned Rod determined to be trippable, THEN go to step 25 after repairs are complete. 24.6 IF misaligned Rod determined to be untrippable, THEN: 24.6.1 Be in HOT STANDBY in 6 hours. (TS 3.1.4) 24.6.2 Go To FNP-1-UOP-3.1, POWER OPERATION. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.2 Misaligned Rods In Mode 1 __Page Completed 10 ProcedureStepsMain Page 6 of 10 __ 25 Record the following in the Control Room Log. Recovery completion time. Affected Bank position. __ 26 Connect the lift coil(s) opened in Step 23. __ 27 Reset Rod Control Urgent Failure alarm. 27.1 Depress ROD CONTROL URGENT FAILURE ALARM RESET pushbutton. 27.2 Verify ROD CONT SYS URGENT FAILURE annunciator FF1 - NOT LIT. __ 28 Reset the Master Cycler using FNP-1-SOP-41.0, CONTROL ROD DRIVE AND POSITION INDICATION SYSTEM. __ 29 Reset the Step Counter to value recorded in Step 19. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.2 Misaligned Rods In Mode 1 __Page Completed 10 ProcedureStepsMain Page 7 of 10 __ 30 Check IPC Rod Position should be updated. 203 30.2 Update the IPC BANK POSITION DISPLAY to match the position recorded in step 14. 30.3 Check recovered rod Control Bank Rod. 30.2 Go to step 41 and exercise the affected bank per FNP-1-STP-5.0, FULL LENGTH CONTROL ROD OPERABILITY TEST 30.4 Go to step 41 and exercise the affected bank per FNP-1-STP-5.0, FULL LENGTH CONTROL ROD OPERABILITY TEST __ 31 Reset Rod Control Urgent Failure alarm. 31.1 Depress ROD CONTROL URGENT FAILURE ALARM RESET pushbutton. 31.2 Verify ROD CONT SYS URGENT FAILURE annunciator FF1 - NOT LIT. __ 32 Reset the Master Cycler using FNP-1-SOP-41.0, CONTROL ROD DRIVE AND POSITION INDICATION SYSTEM. 3 UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.2 Misaligned Rods In Mode 1 __Page Completed 10 ProcedureStepsMain Page 8 of 10 __ 33 Disconnect lift coil for misaligned Rod. ***************************************************************************************** CAUTION: Realigning the affected bank to the misaligned rod must be done without violating the bank sequence, overlap and insertion limits. ***************************************************************************************** __ 34 Review the following: TS 3.1.5 TS 3.1.6 __________________________________________________________________________________________ NOTE: Per NMP-OS 001, REACTIVITY MANAGEMENT PROGRAM, the 3 step rod withdrawal limitation may be suspended during misaligned rod retrieval. __________________________________________________________________________________________ __ 35 Position ROD BANK SELECTOR SWITCH in MANUAL. __ 36 Withdraw or insert the affected bank to the misaligned Rod DRPI position recorded in step 20. __ 37 Record the following in the Control Room Log. Recovery completion time. Affected Bank position. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.2 Misaligned Rods In Mode 1 __Page Completed 10 ProcedureStepsMain Page 9 of 10 __ 38 Connect the lift coil for the misaligned Rod. __ 39 Verify affected bank step counter readings are at the misaligned Rod DRPI position recorded in step 20. __ 40 Check if Bank Overlap Unit should be reset: 40.2 Check if affected bank position was less than All Rods Out position during the event. 40.1 Go to step 41. 40.3 Record control bank position in the Control Room Log. 40.4 Reset the Bank Overlap Unit Counter using FNP-1-SOP-41.0, CONTROL ROD DRIVE AND POSITION INDICATION SYSTEM. __ 41 Exercise the affected bank using FNP-1-STP-5.0, FULL LENGTH CONTROL ROD OPERABILITY TEST. 41 IF the Rod misaligns again, THEN return to Step 1. __ 42 Place ROD BANK SELECTOR SWITCH in MAN or AUTO, as desired. __ 43 Perform the following: 43.2 Notify Duty Engineer of misaligned Rod recovery. 43.3 Notify Duty Engineer that plant computer Rod position adjustment may be necessary. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.2 Misaligned Rods In Mode 1 __Page Completed 10 ProcedureStepsMain Page 10 of 10 __ 44 After rod recovery wait 15 hours at reduced power level prior to power ascension. __ 45 Power Ascension shall be in accordance with FNP-1-UOP-3.1, APPENDIX 1, SPECIAL LOAD RATE LIMITATIONS. 4 __ 46 Return to procedure in effect. 4-END-UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.3 Dropped Rods In Mode 1 __Page Completed 9 ProcedureStepsMain Page 1 of 9 __________________________________________________________________________________________ NOTE: A Rod misaligned greater than 45 steps should be considered "dropped" and this section performed. __________________________________________________________________________________________ __ 1 Stop any turbine loading changes. 3.1.1 __ 2 Check the following: 2 Perform the following: DRPI - AVAILABLE. Only one Rod dropped by observing DRPI. 2.1 Trip the Reactor. 2.2 Go to FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION 3 __ 3 Check rod misaligned greater than 45 steps. 3 Go to Section 1.2, Misaligned Rods in Mode 1. 3.4 __ 4 Initiate TS 3.1.4. 3.4 __ 5 Maintain Tavg at program by performing the following as appropriate: 3.4 Adjust Turbine load. 3.4 Dilute or borate. 3.4 Use manual Rod control. 3.4 UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.3 Dropped Rods In Mode 1 __Page Completed 9 ProcedureStepsMain Page 2 of 9 __ 6 Maintain power distribution when greater than or equal to 50% power: 4 6.1 AFD - WITHIN LIMITS SPECIFIED IN THE COLR. 6.1 Reduce power until one of the following are met: 4.2 AFD within plus or minus 5% of target. 4.3 OR Reactor power less than 50%. 6.2 QPTR - LESS THAN OR EQUAL TO 1.02. 6.2 Initiate TS 3.2.4. __ 7 Perform the following: 7.1 Initiate action to determine cause and repair Rod Control malfunction. 7.2 With Maintenance's concurrence disconnect lift coil for the dropped rod. __ 8 Record the following in the Unit Control Log. Record the following in the Unit Control Log. Dropped Rod number. Initial Power Level. Affected group step counter position. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.3 Dropped Rods In Mode 1 __Page Completed 9 ProcedureStepsMain Page 3 of 9 __ 9 Check Annunciator FC3, PR Hi Flux Rate Alert is clear. 9 On the affected PR NI Drawer, reset the Positive Rate Trip as follows: TSLB-2 NI Hi rate bistables not illuminated. 9.1 Turn the RATE MODE Switch momentarily to RESET. 9.2 Verify POSITIVE RATE TRIP Drawer Light is NOT lit. 9.3 Check PR HI RATE bistable not illuminated on TSLB-2 12.1 - PR HI Q RATE NC 41U 12.2 - PR HI Q RATE NC 42U 12.3 - PR HI Q RATE NC 43U 12.4 - PR HI Q RATE NC 44U UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.3 Dropped Rods In Mode 1 __Page Completed 9 ProcedureStepsMain Page 4 of 9 __________________________________________________________________________________________ NOTE: Power reduction as soon as practical after the rod drop occurs minimizes local fuel power distribution variances and the chances of fuel damage. Although TS 3.1.4 requires power be reduced to less that 75% within 2 hours, a target of achieving reactor power level less than 75% in one hour meets the "as soon as practical" objective. __________________________________________________________________________________________ __ 10 Reduce Thermal Power to less than 75% within 1 hour from time of Rod drop using FNP-1-UOP-3.1, POWER OPERATION. 6 __ 11 Check fuel preconditioned power level greater than or equal to 90% per Reactor Engineering. 11 Continue power reduction to the greater of the following: 11.1 Continue power reduction to less than 50% RTP as soon as possible. 40% RTP below the fuel's preconditioned power level. -OR- 30% RTP. __ 12 Check if rod retrieval should be initiated: 1 12.1 Time of dropped rod known. 12.1 Commence a Unit shutdown to Mode 3 per FNP-1-UOP-3.1, POWER OPERATION. 12.2 Direct cause of dropped rod known and corrective action taken. 12.2 Perform the following: 12.2.1 Consult Reactor Engineering and Operations Management. 1Step 12 continued on next page. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.3 Dropped Rods In Mode 1 __Page Completed 9 ProcedureStepsMain Page 5 of 9 12.2.2 Do not continue until one of the following is satisfied: a) IF recovery plan developed to retrieve dropped rod, THEN continue with Step 13. -OR- b) IF decision made to initiate a unit shutdown, THEN go to FNP-1-UOP-3.1, POWER OPERATION. __ 13 [CA]Maintain reduced power level until rod recovery initiated. __ 14 Rod to be recovered within 120 hours of initial misalignment. 14 Notify Nuclear Fuels to determine impact on Safety Analysis and recovery effort. 14.1 IF Safety Analysis cannot be confirmed within 120 hours, THEN go to FNP-1-UOP-3.1, POWER OPERATION and initiate a unit shutdown to Mode 3. __ 15 [CA]Maintain Tavg within 3ºF of Tref during recovery. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.3 Dropped Rods In Mode 1 __Page Completed 9 ProcedureStepsMain Page 6 of 9 __ 16 [CA]Maintain reduced power level during recovery: IF fuel conditioned greater than or equal to 90%, THEN Maintain Reactor Power less than 50%. IF fuel conditioned greater 70% but less than 90%, THEN Maintain Less than or equal to 40% RTP below the fuel's preconditioned power level. IF fuel conditioned less than 70%, THEN Maintain less than or equal to 30% RTP. __ 17 Position the Rod Bank Selector Switch to the affected bank. __ 18 Reset the affected group step counter to zero. __ 19 Connect Lift Coil for dropped rod, if previously disconnected. __ 20 IF not already in progress, THEN commence FNP-1-STP-37.0, POWER DISTRIBUTION SURVEILLANCE. __ 21 Disconnect all lift coils in the affected bank except for the dropped Rod. __________________________________________________________________________________________ NOTE: ROD CONTROL SYS URGENT FAILURE alarm will annunciate when movement of misaligned Rod is initiated. Per NMP-OS 001, REACTIVITY MANAGEMENT PROGRAM, the 3 step rod withdrawal limitation may be suspended during misaligned rod retrieval. __________________________________________________________________________________________ __ 22 Record the affected bank's group step counters positions in the Unit Control Log. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.3 Dropped Rods In Mode 1 __Page Completed 9 ProcedureStepsMain Page 7 of 9 __________________________________________________________________________________________ NOTE: Per NMP-OS 001, REACTIVITY MANAGEMENT PROGRAM, the 3 step rod withdrawal limitation may be suspended during misaligned rod retrieval. __________________________________________________________________________________________ __ 23 Withdraw the Rod in Bank Select to the affected bank's current position. 22 IF the Rod fails to move, THEN: 22.1 Connect Lift Coils opened in Step 20. 22.2 Reset the Step Counter to value recorded in Step 21. 22.3 Continue applicable actions of T.S. 3.1.4. 22.4 Reset Rod Control Urgent Failure alarm. 22.4.1 Depress ROD CONTROL URGENT FAILURE ALARM RESET pushbutton. 22.4.2 Verify ROD CONT SYS URGENT FAILURE annunciator FF1 - NOT LIT. 22.5 Place Rod Bank Selector Switch in MAN. 22.6 Return to Step 12. __ 24 Record the following in the Unit Control Log: 24.1 Recovery completion time. 24.2 Affected Bank Position. __ 25 Connect Lift Coils opened in Step 20. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.3 Dropped Rods In Mode 1 __Page Completed 9 ProcedureStepsMain Page 8 of 9 __ 25 Reset Rod Control Urgent Failure alarm. 25.1 Depress ROD CONTROL URGENT FAILURE ALARM RESET pushbutton. 25.2 Verify ROD CONT SYS URGENT FAILURE annunciator FF1 - NOT LIT. __ 26 Reset the Master Cycler using FNP-1-SOP-41.0, CONTROL ROD DRIVE AND POSITION INDICATION SYSTEM. __ 27 Reset the IPC Rod Bank Positions per FNP-1-SOP-41.0, CONTROL ROD DRIVE AND POSITION INDICATION SYSTEM. __ 28 Check annunciator FF5, COMP ALARM ROD SEQ/DEV OR PR FLUX TILT clear. __ 29 Stop performance of FNP-1-STP-37.0, POWER DISTRIBUTION SURVEILLANCE. __________________________________________________________________________________________ NOTE: If possible, Maintenance should observe Rod exercise to determine required corrective actions. __________________________________________________________________________________________ __ 30 Exercise the affected bank using FNP-1-STP-5.0, FULL LENGTH CONTROL ROD OPERABILITY TEST. __ 31 Place ROD BANK SELECTOR SWITCH in MAN or AUTO position, as desired. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.3 Dropped Rods In Mode 1 __Page Completed 9 ProcedureStepsMain Page 9 of 9 __ 32 After rod recovery wait 15 hours at reduced power level prior to power ascension. __ 33 Power Ascension shall be in accordance with FNP-1-UOP-3.1, APPENDIX 1, SPECIAL LOAD RATE LIMITATIONS. __ 32 Perform the following: 2 32.1 Notify Duty Engineer of Rod drop recovery. __ 33 Return to procedure and step in effect. 2-END-UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.4 Dropped OR Misaligned Rods In Modes 2 through 5 __Page Completed 2 ProcedureStepsMain Page 1 of 2 __ 1 Check if Reactor shutdown is required: 7 1.1 Check one or more rods DROPPED: 1.1.1 IF in Modes 2 or 3, THEN perform one of the following: Go To FNP-1-UOP-2.1, REACTOR SHUTDOWN TO HOT STANDBY, and perform a normal reactor shutdown. OR Trip the reactor and Go To FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. 1.1.2 IF in Modes 4 or 5,THEN perform one of the following: Insert Control Rods OR Open Reactor Trip Breakers 7Step 1 continued on next page. UNIT 1 08/03/15 7:59:44 FNP-1-AOP-19.0 MALFUNCTION OF ROD CONTROL SYSTEM Version 31.1 Step Action/Expected Response Response Not Obtained Section 1.4 Dropped OR Misaligned Rods In Modes 2 through 5 __Page Completed 2 ProcedureStepsMain Page 2 of 2 1.2 Check one or more rods MISALIGNED: 1.2.1 IF in Modes 2 or 3, THEN perform one of the following: i Go To FNP-1-UOP-2.1, REACTOR SHUTDOWN TO HOT STANDBY, and perform a normal reactor shutdown. OR Trip the reactor and Go To FNP-1-EEP-0, REACTOR TRIP OR SAFETY INJECTION. 1.2.2 IF in Modes 4 or 5,THEN perform one of the following: Insert Control Rods OR Open Reactor Trip Breakers __ 2 Initiate repairs of Rod Control System. __ 3 Go to the applicable UOP. i -END-S A F PROCEDURE USAGE REQUIREMENTS-per NMP-AP-003 SECTIONS E T Continuous Use Remainder Y Reference Use R E Information Use L A T E D UNIT 1DavidLReed06/24/20158/5/201510:38

Procedure Contains Number of Pages Body..................................35 Attachment 1...........................1 Attachment 2..........................12 Attachment 3...........................5 Attachment 4...........................3 Attachment 5...........................3 Attachment 6...........................3 Attachment 7...........................7 Attachment 8...........................5 Attachment 9...........................2 Attachment 10..........................2 Foldout Page...........................1 UNIT 1 UNIT 1

UNIT 1

UNIT 1 UNIT 1

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UNIT 1 START STEP CONTINUOUS ACTION 3 3.2[R] [CA] Try to restore power to deenergized 4160 V ESF bus using FNP-1-AOP-5.0, LOSS OF A OR B TRAIN ELECTICAL POWER, as time permits while continuing this with procedure.

3.3 [CA] Verify operating diesel generator(s) - SUPPLIED FROM AT LEAST ONE SW PUMP

6 [CA] Check containment pressure - HAS REMAINED LESS THAN 27 psig. 8 8.4 [CA] WHEN SG narrow range level greater than 31%{48%}, THEN maintain SG narrow range level 31%-65%{48%-65%}.

9 NOTE [CA] Verification that RCS temperature is being Maintained stable at or approaching 547F is a continuing action until directed otherwise.

10 10.1 [CA] WHEN pressurizer pressure less than 2335 psig, THEN verify both PRZR PORVs closed. 10.2 [CA] WHEN pressurizer pressure less than 2260 psig, THEN verify normal pressurizer spray valves closed OR closing.

21 21.2.3 [CA] Control charging flow to maintain pressurizer level 25%-{50%-60%}.

CAUTION [CA] To ensure proper SI flow to the reactor, the RHR pumps must be manually restarted if they are secured and RCS pressure falls below 275 psig.

33 [CA] Check if LHSI Pumps should be stopped. 33.1 [CA] Check RCS pressure - GREATER THAN 275 psig.

33.2 [CA] Check RCS pressure - STABLE OR RISING.

34 [CA] Verify 4160 V busses energized. 35 35.1 [CA] Monitor any loaded diesel generator for proper voltage, frequency and load.

35.2 [CA] Secure any unloaded diesel generators using FNP-0-SOP-38.0, DIESEL GENERATORS. UNIT 1

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UNIT 1 UNIT 1

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UNIT 1 UNIT 1

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UNIT 1 UNIT 1

UNIT 1

UNIT 1 FNP-1-EEP-0.0 FOLDOUT PAGE REACTOR TRIP OR SAFETY INJECTION Revision 46.1 Step Action/Expected Response Response Not Obtained 1 Monitor RCP criteria 1.1 Greater than 16°F {45°F} subcooled in CETC mode. 1.1 IF HHSI flow greater than 0 gpm, THEN stop all RCPs. 2 Monitor switchover criteria 2.1 CST level greater than 5.3 ft 2.1 Align AFW pumps suction to SW using FNP-1-SOP-22.0 3 Monitor charging miniflow criteria (during SI) 3.1 RCS pressure less than 1900 psig 3.1 Verify miniflow valves open 3.2 RCS pressure greater than 1300 psig 3.2 Verify miniflow valves closed 4 Monitor adverse containment criteria 4.1 CTMT pressure less than 4 psig and radiation less than 105 R/hr 4.1 Utilize bracketed adverse CTMT condition numbers 5 Ruptured SG AFW isolation 5.1 Manually stop AFW flow to a S/G if BOTH conditions listed below occur: Level increases in an uncontrolled manner or radiation in that S/G is abnormal AND Narrow range level - GREATER than 31% {48%} 6 Monitor SFP conditions 6 Perform Attachment 10 Check Annunciator EH1, SFP TEMP HI CLEAR Check Annunciator EH2, SFP LEVEL HI-LO CLEAR IF applicable THEN check time to restore power is LESS THAN the time TO REACH 200°F in the SFP using Unit 1 Core Physics Curve Book, PCB-1-VOL1-CRV79 UNIT 1 FNP ILT-38 JPM Page 1 of 6 jpm h CRO-039A TITLE: Adjust Setpoints Of The N-16 Primary To Secondary Leak Detection System ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: X SIMULATOR CONTROL ROOM PLANT PROJECTED TIME: 5 MIN SIMULATOR IC NUMBER: IC-218 (Base - 125) ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS: 1. Examinee will obtain all references from the simulator. 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise. 3. Provide student with HANDOUT. 4. Allow student time to review control board. 5. Instructor will be provided to address alarms not related to evaluated task. TASK STANDARD: Upon successful completion of this JPM, the examinee will: 1. Adjust Setpoints Of The N-16 Primary To Secondary Leak Detection System. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) EXAMINER: _____________________________ Developer S Jackson Date: 4/8/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP ILT-38 JPM Page 2 of 6

EVENT DESCRIPTION ACTION DETAILS Reset into IC-218 Acknowledge computer alarms Freeze Xe Run / Freeze Simulator Acknowledge Alarms Clear Ovation alarms Turn Horns ON Run / Freeze Simulator Unfreeze Xe Run / Freeze Simulator FNP ILT-38 JPM Page 3 of 6 CONDITIONS When I tell you to begin, you are to ADJUST SETPOINTS OF THE N-16 PRIMARY TO SECONDARY LEAK DETECTION SYSTEM. The conditions under which this task is to be performed are: a. The unit is in Mode 1 at 100% power. b. The control room team has entered AOP-2.0 due to an excessive RCS leak rate along with R-19 coming into alarm, indicating a primary to secondary leak. c. R-70B has exceeded the Alert setpoint and is currently indicating ~ 48 gpd. d. You are directed by the Shift Supervisor to raise the R-70B Alert setpoint to 75 gpd per SOP-69.0. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME Note: The below steps are from Section 4.3 Changing Alarm Setpoints. *1. 1 Press the CODE key. Observes display: COD ? S / U *2. 2 Enter 1111. Enters 1111. Observes display: 1111 S / U *3. 3 Press the VAL key. VAL key depressed. Observes display: 48 gpd S / U *4. 4 Press ALRT, H, or H/H key, depending on setpoint to be changed. ALRT key depressed. Observes display: 5.0+0. S / U 5. 5 Check existing setpoint displayed. Observes display: 5.0+0. S / U *6. 6 Press the MOD key. MOD key depressed. Observes display: 5.0+0 with the 5 flashing. S / U FNP ILT-38 JPM Page 4 of 6 NOTE: VALUES ARE CHANGED IN THE FOLLOWING STEP BY MOVING THE CURSOR WITH THE ARROW KEYS AND REPLACING THE CURRENT VALUE WITH A NEW ONE. THE TRAINEE MAY HAVE TO TRY MORE THAN ONCE TO LEARN HOW THE KEYPAD WORKS. *7. 7 Using arrow (, , keys to move cursor, enter desired setpoint (gallons per day) using numeric keys. 7.5+1 entered. Observes display: 7.5+1 (May also enter 75+0) S / U Note: When the VAL key in Element 8 is pressed, FG1 annunciator will clear if the applicant has inserted a setpoint above the current leakrate. *8. 8 WHEN desired setpoint is displayed, press VAL key. VAL key depressed. Observes display: 7.5+1. S / U *9. 9 Press the MEAS key to return to the measurement mode. MEAS key depressed. Observes display: 48 gpd. S / U 10. 10 Check display indicates 'AV' and leak rate. Observes display: AV S / U 11. 11 Press ALRT, H, or H/H key, depending on the setpoint changed. ALRT depressed. Observes display: 7.5+1. S / U 12. 12 Check setpoint was changed to correct, desired value. Observes display: 7.5+1. S / U 13. 13 Press MEAS key to return to measurement mode. MEAS depressed. Observes display: 48 gpd. S / U STOP TIME Terminate JPM when all elements of the task have been completed. CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () before the element number. FNP ILT-38 JPM Page 5 of 6 GENERAL REFERENCES 1. FNP-1-SOP-69.0, ver 6.0 2. KA: 073A4.02 - 3.7 / 3.7 GENERAL TOOLS AND EQUIPMENT

1. FNP-1-SOP-69.0, ver 6.0 Critical ELEMENT justification: 1-4 Critical - Task completion. 5 Not critical - Check step. 6-9 Critical - Task completion. 10-13 Not critical - Check steps. COMMENTS

FNP ILT-38 JPM HANDOUT Page 1 of 1 jpm h CONDITIONS When I tell you to begin, you are to ADJUST SETPOINTS OF THE N-16 PRIMARY TO SECONDARY LEAK DETECTION SYSTEM. The conditions under which this task is to be performed are: a. The unit is in Mode 1 at 100% power. b. The control room team has entered AOP-2.0 due to an excessive RCS leak rate along with R-19 coming into alarm, indicating a primary to secondary leak. c. R-70B has exceeded the Alert setpoint and is currently indicating ~ 48 gpd. d. You are directed by the Shift Supervisor to raise the R-70B Alert setpoint to 75 gpd per SOP-69.0.

Printed November 30, 2013 at 13:35 FARLEYUnit 1SAFETY RELATED FNP-1-SOP-69.0 N-16 Primary To Secondary Leak Detection System VERSION 6.0 Special Considerations: This is an upgraded procedure. Exercise increased awareness during initial use due to potential technical and/or sequential changes. After initial use, provide comments to the procedure upgrade team. PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous ALL Reference NONE Information NONE Approval: David L Reed 11/27/13 Approved By DateEffective Date: OPERATIONS Responsible Department N-16 Primary To Secondary Leak Detection System FNP-1-SOP-69.0FARLEY Version 6.0Unit 1 Page 2 of 10 Printed November 30, 2013 at 13:35 VERSION SUMMARY PVR 6.0 DESCRIPTION Updated to fleet template and latest writer's guide N-16 Primary To Secondary Leak Detection System FNP-1-SOP-69.0FARLEY Version 6.0Unit 1 Page 3 of 10 Printed November 30, 2013 at 13:35 TABLE OF CONTENTS SECTION .......................................................................................................................................... PAGE 1.0 PURPOSE ....................................................................................................................................4 2.0 PRECAUTIONS AND LIMITATIONS ............................................................................................4 3.0 INITIAL CONDITIONS ..................................................................................................................5 4.0 INSTRUCTIONS ...........................................................................................................................5 4.1 System Startup: ............................................................................................................................5 4.2 System Shutdown .........................................................................................................................7 4.3 Changing Alarm Setpoints ............................................................................................................7 4.4 Determining Estimated Leak Based on Assumed Leak Location .................................................8 5.0 RECORDS ....................................................................................................................................9

6.0 REFERENCES

.............................................................................................................................9 TABLE 1 List Of System Abbreviations ......................................................................................................10 N-16 Primary To Secondary Leak Detection System FNP-1-SOP-69.0FARLEY Version 6.0Unit 1 Page 4 of 10 Printed November 30, 2013 at 13:35 1.0 PURPOSE To provide guidance for operation of the Primary to Secondary Leak Detection System. 2.0 PRECAUTIONS AND LIMITATIONS 1. The system receives a reactor power input from power range channel N-43. IF N-43 fails OR is in Test OR is less than 20% power, the system cannot accurately estimate a leak rate in the AV mode, and the indicators will display "PN <20%". IF desired, the Counting Room can configure the N-16 system in the ME counts per second (C/S) mode using FNP-0-CCP-31, Leak Rate Determination. While not able to provide a leak rate determination, this mode can be used to indicate if leakage is increasing based on the indication trending up. The AV mode is the preferred mode of operation above 20%

Reactor Power. The ME mode should only be utilized below 20% Reactor Power. .......................................................................................................................... 2. The N-16 Leak Detection System cannot determine the location of a leak within a specific Steam Generator. The system can however provide a more accurate leak rate determination if the location of the leak is known to be in one of the following locations:

Cold Leg - CB
Hot Leg - HB
U-Bend region - BE WHEN a leak location is selected (CB, HB or BE), the processor displays a leak rate that assumes the leak is at the location you have selected. The AV mode is essentially the average of the three leak rates at the specific locations. ........ 3. The N-16 system is limited to an upward range of 1,000 gallons per day. .................. 4. The MCB annunciator alarms when any channel reaches its ALERT setpoint. To clear the annunciator and provide warning of an increasing leak rate, the alert setpoint may be raised using Section 4.3. .......................................................... 5. The ALERT setpoint cannot be set above the HIGH setpoint. IF an ALERT setpoint greater than the existing HIGH setpoint is needed, the HIGH setpoint must be raised. ............................................................................................................ 6. This procedure may contain previously evaluated Critical Steps that may not be applicable in certain plant conditions. The evaluation of this procedure for Critical Steps is performed during the Pre-Job briefing. The decision concerning how to address error precursors for critical steps should be governed by NMP-GM-005-GL03, Human Performance Tools. .................................

N-16 Primary To Secondary Leak Detection System FNP-1-SOP-69.0FARLEY Version 6.0Unit 1 Page 5 of 10 2.0 PRECAUTIONS AND LIMITATIONS (continued) Printed November 30, 2013 at 13:35 NOTE Any numerical value set in the AV - gallons per day mode will carry over to the ME - counts per second mode. (i.e. an alert setting of 5 gpd in the AV mode will correspond to an alert setting of 5 counts per second in the ME mode). .............................................................................. 7. The normal alarm settings for N1D11RISH0070A, B & C are:

ALERT - 5 gpd
HIGH - 150 gpd
HIGH-HIGH - 300 gpd The existing setpoints may be checked by pressing the ALRT, H, and H/H keys as needed. .......................................................................................................... 8. Minor system faults are indicated by the OPER LED flashing. FNP-1-ARP-1.6, Main Control Board Annunciator Panel F, location FG2, contains corrective actions. ........................................................................................................................ 9. A list of system abbreviations is contained in Table 1. ................................................ 3.0 INITIAL CONDITIONS 1. 120V Regulated Instrumentation Panel 1B is ENERGIZED per FNP-1-SOP-36.4, 120V A.C. Distribution Systems. .................................................... 4.0 INSTRUCTIONS 4.1 System Startup: 1. Close N1R22L001B-N-BKR9, N-16 PRI TO SEC LEAK DETECTION SYS ANAL CAB (R-70) in 120V Regulated A.C. Instrumentation Panel 1B, N1R22L001B-N (121' 1B Battery Charger Room). .................................................... 2. In CONTROL PANEL FOR STEAM GENERATOR N16 LEAK DETECTION SYSTEM, N1H21NFSGL2631-N (121' Rod Control Room) [key C415A], close the three circuit breakers in the following panels: * (A)-CR191 .......................................................................................................... * (B)-CR191 .......................................................................................................... * (C)-CR191 .........................................................................................................

N-16 Primary To Secondary Leak Detection System FNP-1-SOP-69.0FARLEY Version 6.0Unit 1 Page 6 of 10 4.1 System Startup: (continued) Printed November 30, 2013 at 13:35 3. On the following indicating modules, press ON/OFF pushbuttons to energize modules.

N1D11RISH0070A .............................................................................................
N1D11RISH0070B .............................................................................................
N1D11RISH0070C ............................................................................................ NOTES
Changes between the AV and ME modes of operation is performed by the Counting Room technician using the guidance of FNP-0-CCP-31, Leak Rate Determination, Appendix B, N-16 System. ...........................................................................................................
AV / gallons per day mode is the preferred mode of operation above 20% Reactor Power. ME / counts per second (C/S) mode does not indicate a leak rate, but is useful for trending changes in leak rate below 20% power. It is possible to indicate ME gallons per day (GPD), however this is misleading. While GPD units may be indicated, the value is actually representing counts per second. IF indicating 'ME ---- GPD', the Counting Room technician should be requested to change the display to C/S. .......................... 4. Check that all three indicating modules initialize and provide a display as follows: a. IF Reactor Power is greater than or equal to 20%, check each display indicates 'AV ---- GPD':
N1D11RISH0070A ..................................................................................
N1D11RISH0070B ..................................................................................
N1D11RISH0070C .................................................................................. b. IF Reactor Power is less than 20%, check each display indicates 'AV PN <20% ' OR , 'ME ---- C/S '
N1D11RISH0070A ..................................................................................
N1D11RISH0070B ..................................................................................
N1D11RISH0070C ..................................................................................

N-16 Primary To Secondary Leak Detection System FNP-1-SOP-69.0FARLEY Version 6.0Unit 1 Page 7 of 10 Printed November 30, 2013 at 13:35 4.2 System Shutdown 1. On the following indicating modules, press ON/OFF pushbuttons to de-energize the modules.

N1D11RISH0070A .............................................................................................
N1D11RISH0070B .............................................................................................
N1D11RISH0070C ............................................................................................ 2. In CONTROL PANEL FOR STEAM GENERATOR N16 LEAK DETECTION SYSTEM, N1H21NFSGL2631-N (121' Rod Control Room) [key C415A], open the three circuit breakers in the following panels: * (A)-CR191 .......................................................................................................... * (B)-CR191 .......................................................................................................... * (C)-CR191 ......................................................................................................... 3. Open N1R22L001B-N-BKR9, N-16 PRI TO SEC LEAK DETECTION SYS ANAL CAB (R-70) in 120V Regulated A.C. Instrumentation Panel 1B, N1R22L001B-N (121' 1B Battery Charger Room). .................................................... 4.3 Changing Alarm Setpoints 1. Press CODE key. ....................................................................................................... NOTE IF the wrong value is entered in Step 2, pressing the VAL key and returning to Step 1 will allow the correct value to be entered. ............................................................................................... 2. Enter 1111. ................................................................................................................. 3. Press VAL key. ........................................................................................................... NOTE The alarm setpoints are displayed in scientific notation in gallons per day (gpd). For example: 1.5 + 2 displayed = 1.5 x 102 = 150 gpd. .................................................................... 4. Press ALRT, H, or H/H key, depending on setpoint to be changed. ........................... 5. Check existing setpoint displayed. ............................................................................. 6. Press MOD key. ......................................................................................................... 7. Using arrow (, , , ) keys to move cursor, enter desired setpoint (gallons per day) using numeric keys. .........................................................................

N-16 Primary To Secondary Leak Detection System FNP-1-SOP-69.0FARLEY Version 6.0Unit 1 Page 8 of 10 4.3 Changing Alarm Setpoints (continued) Printed November 30, 2013 at 13:35 8. WHEN desired setpoint is displayed, press VAL key. ................................................ 9. Press MEAS key to return to measurement mode. .................................................... 10. Check display indicates 'AV' and leak rate. ................................................................ 11. Press ALRT, H, or H/H key, depending on the setpoint changed. .............................. 12. Check setpoint was changed to correct, desired value. ............................................. 13. Press MEAS key to return to measurement mode. .................................................... 14. IF a setpoint has been changed from NORMAL value listed in Section 2.0 Precaution and Limitation 7, place a Status tag stating new setpoint on channel modified. ..................................................................................... NOTE The N-16 Leak Detection System cannot determine the location of a leak within a specific Steam Generator. The system can however, provide a more accurate leak rate determination if the location of the leak is known to be in one of the following locations: Cold Leg - CB, Hot Leg - HB or U-Bend region - BE WHEN a leak location is selected (CB, HB or BE), the processor displays a leak rate that assumes the leak is at the location you have selected. ..................................................................... 4.4 Determining Estimated Leak Based on Assumed Leak Location 1. Press CODE key. ........................................................................................................ 2. Enter 1111. .................................................................................................................. 3. Press VAL key. ............................................................................................................ 4. Press MEAS key. ......................................................................................................... 5. Press VAL key. ............................................................................................................ 6. Press MOD key. .......................................................................................................... 7. Using arrow (, , , ) keys, scroll to desired leak location (CB, AV, BE, or HB ). ................................................................................................... 8. Press VAL key. ............................................................................................................ 9. IF desired to check another leak location, repeat Step 1 to Step 8. ........................... 10. To return to the NORMAL operating mode (AV - gallons per day mode), repeat Step 1 to Step 8, selecting AV in Step 7. ................................................................... N-16 Primary To Secondary Leak Detection System FNP-1-SOP-69.0FARLEY Version 6.0Unit 1 Page 9 of 10 Printed November 30, 2013 at 13:35 5.0 RECORDS Documents created using this procedure will become QA Records when completed unless otherwise stated. The procedures and documents are considered complete when issued in DMS. QA Record (X) Non-QA Record (X)Record Generated Retention Time R-Type X FNP-1-SOP-69.0 LP HH6.051

6.0 REFERENCES

PCN B88-1-5212, N-16 Primary to Secondary Leak Detection System.
U-265894, N-16 USER MANUAL.
D-175033, Sht. 1, P&ID Main Steam System.
D-181594, Connection Diagram Analyzer Cabinet N1H21NFSGL2631-N.
D-181706, Connection Diagram BOP Rack N1H11NGBOP2506Q-N.

N-16 Primary To Secondary Leak Detection System FNP-1-SOP-69.0FARLEY Version 6.0Unit 1 Page 10 of 10 TABLE 1Page 1 of 1List Of System Abbreviations A, ALRT -Alert ACC -Accumulation ALG -Algorithm AV -Averaging Mode (in gallons per day) BE -U-Bend Break C -Cancel CB -Cold Leg Break (bottom) COD,CODE -Code C/S -Counts per Second FLT -Fault H -High HB -Hot Leg Break (bottom) H/H -High-High IMP -Impulse (Pulse Count) INIT -Initialize ME -Counts per Second Mode (C/S) MEAS -Measurement MOD -Modify OPER -Operate PARAM -Parameters PN -Reactor Power SEL -Select STA,STAT -Status TEST -Test UNI -Units VAL -Validate + -Change Exponent Sign -Scroll Up -Scroll Down -Scroll Right -Scroll Left FNP ILT-38 JPM Page 1 of 6 jpm i. SO-607A TITLE: Perform the Required Actions to Minimize DC Loads ACCEPTABLE EVALUATION METHOD: PERFORM X SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X PLANT PROJECTED TIME: 12 MIN. SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS: 1. All actions will be SIMULATED. 2. This JPM to be performed on UNIT 1 ONLY. 3. Provide student HANDOUT and procedure. 4. Allow student time to review conditions and procedure. TASK STANDARD: 1. Perform the actions to minimize DC loads. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) EXAMINER: Developer S. Jackson Date: 4/6/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP ILT-38 JPM Page 2 of 6 CONDITIONS When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS TO MINIMIZE DC LOADS. The conditions under which this task is to be performed are:

a. A loss of all AC power has occurred on UNIT 1. b. ECP-0.0 is in progress. c. You are the Rover and are directed by the control room to de-energize non-essential DC loads in the non-rad side of the auxiliary building using Attachment 4 of ECP-0.0. d. A pre-job brief is not required. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME *1. 1 De-energize non-essential DC loads in the NON-RAD AUX BLDG. 1.1 Open breaker for non-essential load on 1A 125V DC distr panel (155 ft AUX BLDG main control room)

Load Control Remote Unit Control Power To Fuse Block NSH11NGLCR2507I-N [] BKR 25 Breaker 25 taken to the OFF position. (CUE: For each breaker operated the breaker indicates as you described.) S / U *2. 1.2 Open breakers for non-essential load on 1B 125V DC distr panel (139 ft. AUX BLDG A train SWGR room). CRDM MG "1A" Control Cab Power to Starter Bkr., Field Flash & output CT [] BKR 9 Rx Trip SWGR Control Power to Unit 1 "A" Bypass Bkr & "A" Rx Trip Bkr [] BKR 16 Breakers 9 and 16 taken to the OFF position. (CUE: For each breaker operated the breaker indicates as you described.) S / U FNP ILT-38 JPM Page 3 of 6 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *3. 1.3 Open breakers for non-essential load on 1H 125V DC distr panel (139 ft. AUX BLDG CDRM MG set room). Solenoid Valve 600 Volt Load Center Dampers LCS [] BKR 7 Radioactive Lab Exh Fan SV/JB NSV46V3860-N/JB [] BKR 10 Waste Evaporator Control Panel N1G21NDWE2609-N [] BKR 13 Recycle Evaporator Control Panel N1G21NDRE2608-N [] BKR 16 Steam Generator Blowdown Processing Panel N1G24NDSGB2611-N [] BKR 20 Breakers 7, 10, 13, 16, and 20. taken to the OFF position. (CUE: For each breaker operated the breaker indicates as you described.) S / U *4. 1.4 Open breakers for non-essential load on 1G 125V DC distr panel (139 ft. AUX BLDG CDRM SWGR room). Waste Encap. Panel N1G24NGWBP2614-N [] BKR 15 Containment Cooler Vibration Switches [] BKR 16 Lower Equip Room HVAC Local Control Station N1V47L003-N [] BKR 17 Breakers 15, 16, and 17 taken to the OFF position. (CUE: For each breaker operated the breaker indicates as you described.) S / U FNP ILT-38 JPM Page 4 of 6 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *5. 1.5 Open breakers for non-essential load on 1E 125V DC distr panel (121 ft. AUX BLDG B train SWGR room). CRDM MG Set 1B control cabinet [] BKR 9 Rx Trip SWGR Cabinet Unit 1 Q1C11E004A-AB [] BKR 16 Breakers 9 and 16 taken to the OFF position. (CUE: For each breaker operated the breaker indicates as you described.) S / U UNIT 1 STOP TIME Terminate when DC breakers at distribution panel 1E are opened.

CRITICAL ELEMENTS: Critical Elements are denoted with as Asterisk (*) preceding the element number.

FNP ILT-38 JPM Page 5 of 6 GENERAL

REFERENCES:

1. FNP-1-ECP-0.0, Attachment 4, ver 27 2. K/As: 055EA1.04 - 3.5 / 3.9 GENERAL TOOLS AND EQUIPMENT:

Provide either: FNP-1-ECP-0.0, Attachment 4, Rev. 26 FNP-2-ECP-0.0, Attachment 4, Rev. 26 Critical ELEMENT justification: 1-5 Critical - Task completion. DC loads must be reduced to extend battery life to permit monitoring and control of the plant until AC is restored. COMMENTS: FNP ILT-38 JPM HANDOUT Page 1 of 1 jpm i CONDITIONS When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS TO MINIMIZE DC LOADS. The conditions under which this task is to be performed are:

a. A loss of all AC power has occurred on UNIT 1. b. ECP-0.0 is in progress. c. You are the Rover and are directed by the control room to de-energize non-essential DC loads in the non-rad side of the auxiliary building using Attachment 4 of ECP-0.0. d. A pre-job brief is not required.

S AF PROCEDURE USAGE REQUIREMENTS per NMP-AP-003 SECTIONSETContinuous Use Remainder ofYProcedureReference UseSteps 1-2 REInformation UseLA T E DUNIT 1DavidLReed(for)03/30/20156/2/201511:41 Procedure Contains Number of Pages Body..................................44 Attachment 1...........................1 Attachment 2...........................3 Attachment 3...........................2 Attachment 4...........................5 Attachment 5...........................4 Attachment 6...........................1 UNIT 1

UNIT 1

UNIT 1 START STEP CONTINUOUS ACTION CA Rere per eere CA EN per rere eere TEN pree ep CA EN SI pree TEN ree SI 3 3 CA EN rr re SG ee reer 3 TEN SG rr re ee 3-- CA EN CST ee e 3 TEN A pp ere re CA EN CST ee e 3 TEN TDAP r S Mr RCS er R Pree Sep Ce e epe e RCP e - ESS TAN OURS R C TSC eere e p e e R EN p e e TEN pree Sep 3R Pree Sep 3 Pree Sep 3 CA e r pe e p AU DG pe e r CA M SG prere e rre e UNIT 1

UNIT 1

FNP UNIT 1 LOAD LIST A-5062501sectf.doc Page F - 4 Rev. 2DF03ED04 LA08 1A 125V DC DIST PNL AB-155' D177082 BKR TPNS DESCRIPTIONSEEPAGEQ1R41L0001A-A1A 125V DC DISTRIBUTION PANEL <<< LA08 1A-01 Q1R45G0002A-A NO. 1 EMERGENCY LIGHTING RELAY BOX FEEDER (CONTROL ROOM) 1A-02 Q1R45G0002A-A NO. 2 EMERGENCY LIGHTING RELAY BOX FEEDER (CONTROL ROOM) 1A-03 Q1R45G0002A-A NO. 3 EMERGENCY LIGHTING RELAY BOX FEEDER (CONTROL ROOM) 1A-04 ------------ SPARE 1A-05 ------------ SPARE 1A-06Q1H25L0009-A9A TERMINATION CABINET PANEL 1 FRONT >>> F-6 1A-07N1H11NGAR2506F-N#1 AUXILIARY RELAY RACK TRAIN "A" >>> F-7 1A-08QSH11NGEPB2508-ABEMERGENCY POWER BOARD (VIA EPB ANNUN UNIT 1/UNIT 2 PWR TRANS SW QSH11S0001A-A) >>> F-8Q1H25L036-A36A TERMINATION CABINET PANEL 3 REAR (VIA EPB ANNUN UNIT 1/UNIT 2 PWR TRANS SW QSH11S0001A-A) >>> F-91A-09Q1H25L0004-A4A TERMINATION CABINET PANEL 1 FRONT >>> F-10 1A-10Q1H25L0004-A4A TERMINATION CABINET PANEL 2 FRONT >>> F-11 1A-11Q1H25L0005-A5A TERMINATION CABINET PANEL 3 REAR >>> F-12 Q1H25L0005-A5A TERMINATION CABINET PANEL 4 REAR >>> F-13 1A-12Q1H25L0008-A8A TERMINATION CABINET PANEL 1 FRONT >>> F-14 1A-13Q1H25L0008-A8A TERMINATION CABINET PANEL 3 REAR >>> F-15 1A-14Q1H25L0008-A8A TERMINATION CABINET PANEL 4 REAR >>> F-16 FNP UNIT 1 LOAD LIST A-5062501sectf.doc Page F - 5 Rev. 2DF03ED04 LA08 1A 125V DC DIST PNL AB-155' D177082 (CONT'D)BKR TPNS DESCRIPTIONSEEPAGE1A-15Q1H25L0010-A10A TERMINATION CABINET PANEL 1 FRONT >>>F-17 1A-16Q1H25L0010-A10A TERMINATION CABINET PANEL 2 FRONT >>>F-18 Q1H25L0010-A10A TERMINATION CABINET PANEL 4 REAR >>> F-19 1A-17Q1H25L0006-A6A TERMINATION CABINET PANEL 2 FRONT >>> F-20 1A-18Q1H25L0006-A6A TERMINATION CABINET PANEL 3 REAR >>> F-21 1A-19Q1H11NGB2504L-A"L" BALANCE OF PLANT PANEL >>> F-22 Q1H11NGB2504M-A"M" BALANCE OF PLANT PANEL >>> F-24 1A-20Q1H25L0006-A6A TERMINATION CABINET PANEL 4 REAR >>> F-25 1A-21 Q1H11NGSSP2506N-A"A" TRAIN SSPS TEST CABINET (TURB - TRN A TRIPS & GEN TIME DELAY TRIP AFTER TURB TRIP CKTS) 1A-22Q1H22L0001B-A1B MULTIPLYING RELAY CABINET >>> F-26 Q1P15L0001A-A1A SAMPLE CONTROL PNL AUX RELAY CAB >>> F-27 1A-23Q1H11NGASC2506D-A"D" AUXILIARY SAFEGUARD CABINET >>> F-28 1A-24Q1H22L0001E-A1E MULTIPLYING RELAY CABINET >>> F-29 1A-25 NSH11NGLCR2507I-NLOAD CONTROL REMOTE UNIT CONTROL POWER FUSEBLOCK (10A) 1A-26 ------------ SPARE 1A-27Q1H25L0004-A4A TERMINATION CABINET PANEL 3 REAR >>> F-30 1A-28 ------------ SPARE 1A-29Q1H25L0004-A4A TERMINATION CABINET PANEL 3 REAR >>> F-31 1A-30 ------------ SPARE FNP UNIT 1 LOAD LIST A-5062501sectf.doc Page F - 57 Ver. 68.0DF03ED04 LA13 1B 125V DC DIST PNL AB-139' D177082 BKR TPNS DESCRIPTIONSEEPAGEQ1R41L0001B-A1B 125V DC DISTRIBUTION PANEL <<< LA13 1B-01 Q1R15A0006-A 1F 4160V BUS DC CONTROL POWER FOR INCOMING BREAKERS DF01, DF08 & DF15 1B-02 Q1R16B0002-A 1A 600V LOAD CENTER DC CONTROL POWER FOR INCOMING BREAKERS EA02, EA07, EA08 & EA09 1B-03 Q1R15A0006-A 1F 4160V BUS DC CONTROL PWR FOR FEEDER BREAKERS DF02, DF03, DF04, DF05, DF06, DF07, DF09, DF10, DF11, DF12, DF13 1F 4160V BUS U/F TRIP AUX RELAYS (TRIP DG BKR DF08)1B-04 Q1R16B0002-A 1A 600V LOAD CNTR DC CONT PWR FOR FDR BKRS EA03, EA04, EA05, EA06, EA10, EA11, EA12, EA13, EA14, EA15 & EB05 (PWR FROM EA12) 1B-05Q1H21NBL2702A-A"A" TRAIN PENETRATION ROOM ISOLATION PANEL >>> F-591B-06 Q1R16B0006-A 1D 600V LOAD CENTER DC CONTROL POWER FOR INCOMING BREAKERS ED02, ED08 & ED12 1B-07 Q1R15A0503-A 1H 4160V BUS DC CONTROL POWER FOR BREAKERS DH01, DH02, DH03, DH04, DH05, DH07 & DH08 1H 4160V BUS U/F TRIP AUX RELAYS (TRIP DG BKR DH07) N1R15A0508-N 1H 4160V BUS BKR TEST CABINET 1B-08 Q1R16B0006-A 1D 600V LOAD CENTER DC CONT POWER FOR FEEDER BREAKERS ED03, ED04, ED05, ED06, ED09, ED10, ED11, ED13, ED14, ED15 & ED16 1B-09 N1C11L0005A-N 1A CRDM M-G SET CONTROL CABINET POWER TO STARTER BKR 52-2, FIELD FLASH & OUTPUT CT 1B-10 Q1R16B0508-A 1R 600V LOAD CENTER DC CONTROL POWER FOR INCOMING BREAKER ER02 FNP UNIT 1 LOAD LIST A-5062501sectf.doc Page F - 58 Ver. 68.0DF03ED04 LA13 1B 125V DC DIST PNL AB-139' D177082 (CONT'D)BKR TPNS DESCRIPTIONSEEPAGE1B-11 N1R15G0001C-N 1F 4160V BUS BREAKER TEST CABINET 1B-12Q1N21L0001A-A1A HOT SHUTDOWN PANEL AUX RELAY CABINET >>>F-601B-13 Q1H21E0004-A 1F 4160V BUS LOCAL CONTROL PANEL DIFFERENTIAL LOCKOUT RELAY CONTROL CIRCUIT 1B-14 Q1R43E0001A-A 1F BUS LOADING SEQUENCER CONTROL POWER TO: LOSP SEQ, LOAD SHEDDING, BKR CLOSE FAILURE & SEQ LOCAL ANNUN 1B-15 Q1H21E0504-A 1H 4160V BUS LOCAL CONTROL PANEL DIFFERENTIAL PROTECTION CONTROL CIRCUIT 1B-16 Q1C11E0004B-AB "A" REACTOR TRIP SWITCHGEAR CONTROL POWER TO BYPASS BREAKER & REACTOR TRIP BREAKER 1B-17Q1H21NBAFP2605A-A1A LOCAL HOT SHUTDOWN PANEL >>> F-61 Q1H21NBAFP2605G-A1G LOCAL HOT SHUTDOWN PANEL >>> F-62 1B-18 Q1R43E0501A-A 1H BUS LOADING SEQUENCER CONTROL POWER TO LOAD SHEDDING CONTROL CIRCUIT 1B-19Q1H25L0004-A4A TERMINATION CABINET PANEL 4 REAR >>> F-63 1B-20 N1R15A0003-N 1C 4160V BUS UNDERVOLTAGE AND UNDERFREQUENCY PROTECTIVE RELAYING & RCP AUX PT CAB. N1R15A003X, DCX3 TIMING & ALARM RELAYS 2-3, 2-4, AND 74-1 1C 4160V BUS DC CONTROL POWER FOR RCP BUS U/V TRIP LOGIC AUX RELAYS 2-1 & 2-2 1C 4160V BUS DC CONTROL POWER FOR RCP BUS U/F TRIP LOGIC RELAYS 81-1 & 81-2 1C 4160V BUS DC CONTROL POWER FOR BUS U/V AUX RELAYS 27-2X & 27-4X (SYNCHRONIZING CHECK PERMISSIVE, LOAD SHED, ALARM) 1B-21Q1H25L0006-A6A TERMINATION CABINET PANEL 1 FRONT >>> F-64 1B-22 ------------ SPARE FNP UNIT 1 LOAD LIST A-506250 1sectg.doc Page G - 53 Ver. 68.0 DG03EE05 LB07 1E 125V DC DIST PNL AB-121' D177083 BKR TPNS DESCRIPTIONSEEPAGEQ1R41L0001E-B1E 125V DC DISTRIBUTION PANEL <<< LB07 1E-01 Q1R15A0007-B 1G 4160V BUS DC CONTROL POWER FOR INC BREAKERS DG01, DG08 & DG15 1E-02 Q1R16B0005-B 1C 600V LOAD CENTER DC CONTROL POWER FOR INC BREAKERS EC02, EC07, EC08 & EC10 1E-03 Q1R15A0007-B 1G 4160V BUS DC CONTROL POWER FOR FEEDER BREAKERS DG02, DG03, DG04, DG05, DG06, DG07, DG09, DG10, DG11, DG12 & DG13 1G 4160V BUS U/F TRIP AUX RELAYS (TRIP DG BKR DG08)1E-04 Q1R16B0005-B 1C 600V LOAD CENTER DC CONTROL POWER FOR FDR BREAKERS EC03, EC04, EC05, EC06, EC09, EC11, EC12, EC13 & EC14 1E-05Q1H21NBL2702B-B"B" TRAIN PENETRATION ROOM ISOLATION PANEL >>> G-551E-06 Q1R16B0007-B 1E 600V LOAD CENTER DC CONTROL POWER FOR INC BREAKERS EE02, EE07 & EE12 1E-07 Q1R15A0504-B 1J 4160V BUS DC CONTROL POWER FOR BREAKERS DJ01, DJ02, DJ03, DJ04, DJ06 & DJ07 1J 4160V BUS U/F TRIP AUX RELAYS (TRIP DG BKR DJ06) N1R15A0509-N 1J 4160V BUS BREAKER TEST CABINET 1E-08 Q1R16B0007-B 1E 600V LOAD CENTER DC CONTROL POWER FOR FEEDER BREAKERS EE03, EE05, EE06, EE08, EE09, EE10, EE11, EE13, EE14, EE15 FNP UNIT 1 LOAD LIST A-506250 1sectg.doc Page G - 54 Ver. 68.0 DG03EE05 LB07 1E 125V DC DIST PNL AB-121' D177083 (CONT'D)BKR TPNS DESCRIPTION1E-09 N1C11L0005B-N 1B CRDM M-G SET CONTROL CABINET POWER TO STARTER BKR 52-2, FIELD FLASH & OUTPUT CT 1E-10 Q1R16B0509-B 1S 600V LOAD CENTER CONTROL POWER FOR INC BREAKER ES02 1E-11 N1R15G0001D-N 1G 4160V BUS BREAKER TEST CABINET 1E-12 ----------- SPARE 1E-13 Q1H21E0005-B 1G 4160V BUS LOCAL CONTROL PANEL DIFFERENTIAL LOCKOUT RELAY CONTROL CIRCUIT 1E-14 Q1R43E0001B-B 1G BUS LOADING SEQUENCER CONTROL POWER TO: LOSP SEQ, LOAD SHEDDING, BKR CLOSE FAILURE & SEQ LOCAL ANNUN 1E-15 Q1H21E0505-B 1J 4160V BUS LOCAL CONTROL PANEL DIFFERENTIAL PROTECTION CONTROL CIRCUIT 1E-16 Q1C11E0004A-AB "B" REACTOR TRIP SWITCHGEAR CONTROL POWER TO BYPASS BREAKER & REACTOR TRIP BREAKER 1E-17 ----------- SPARE 1E-18 Q1R43E0501B-B 1J BUS LOADING SEQUENCER CONTROL POWER TO LOAD SHEDDING CIRCUIT 1E-19 ----------- SPARE 1E-20 ----------- SPARE 1E-22 ----------- SPARE FNP UNIT 1 LOAD LIST A-506250 1secth.doc Page H - 11 Rev. 66 DH01EG05 FHA4 1K-36 1G 125V DC DIST PNL AB - 139' D177082 D181743BKR TPNS DESCRIPTIONN1R41L0001G-N1G 125V DC DISTRIBUTION PANEL <<< 1K-36 1G-01N1R15A0001-N 1A 4160V BUS DC CONTROL POWER FOR INCOMING BKRS DA01 & DAO71G-02 N1R16B0003-N 1B 600V LOAD CENTER DC CONTROL PWR FOR INCOMING BKR EB02 & EB07 1B 600V LOAD CENTER LOSS OF DC PWR & U/V RELAY 27 SIGNAL TO AUX RLY 27X-1 1G-03 N1R15A0001-N 1A 4160V BUS DC CONTROL POWER FOR RCP BUS U/V TRIP LOGIC AUX RLYS 2-1 & 2-2, AND RCP AUX PT CAB. N1R15A001X, DAX4 TIMING & ALARM RLYS 2-3, 2-4, 75-1 1A 4160V BUS DC CONTROL POWER FOR RCP BUS U/F TRIP LOGIC RLYS 81-1 & 81-2 1A 4160V BUS DC CONTROL POWER FOR BUS U/V AUX RELAYS 27-2X & 27-4X (SYNC CHECK PERMISSIVE LOAD SHED, ALARM) 1A 4160V BUS DC CONTROL POWER FOR FDR BKRS DA03, DA04, DA05, DA06 & LOSS OF DC (VOLTAGE ALARM RELAY 74) 1G-04 N1R16B0003-N 1B 600V LOAD CENTER CONTROL PWR FOR FEEDER BKRS EB03,EB04,EB08,EB09,EB10 & EB11 1G-05 N1R15A0003-N 1C 4160V BUS DC CONTROL POWER FOR INCOMING BRKRS DC01 & DC041G-06 N1R16B0014-N 1M 600V LOAD CENTER DC CONTROL PWR FOR INCOMING BKRS EM02 & EM07 FNP UNIT 1 LOAD LIST A-506250 1secth.doc Page H - 12 Ver. 62.0 DH01EG05 FHA4 1K-36 1G 125V DC DIST PNL AB - 139' D177082 (CONT'D) D181743FUSE TPNS DESCRIPTIONSEEPAGE1G-07 N1R15A0003-N 1C 4160V BUS DC CONTROL POWER FOR FDR BRKRS DC03 AND DC05 AND LOSS OF DC (VOLTAGE ALARM RLY 74)1G-08 N1R16B0014-N 1M 600V LOAD CENTER CONTROL PWR FOR FEEDER BKRS EM03,EM04,EM05,EM061G-09 N1R15G0001A-N BKR TEST CABINET FOR 4KV BUS 1A 1G-10 N1Y43S0010A-N & B-N125VDC FIRE PROTECTION SAFETY SWITCHES >>> DIESEL GENERATOR BLDG C02 SYSTEM CONTROL POWER (SYSTEMS 1D-78, ID-79, 1D-80, 1D-81) 1G-11 N1V43G0086-N LORAIN INVERTER >>> FP SMOKE DETECTION SYSTEM CABINETS N1V43G0082, 83, 84, 85, 130, 131, 132, 133, & 134-N (POWER TO FIRE IND UNIT, ZONE IND UNITS, & SUPPLEMENTARY RELAY PANELS) 1G-12Q1H11NGB2504P-NPLANT BALANCE OF PLANT PNL "P" H-16 Q1H11NGB2504Q-NPLANT BALANCE OF PLANT PNL "Q" H-18 1G-13 --------------- SPARE 1G-14 --------------- SPARE 1G-15N1G24GWEP2614-NWASTE ENCAPSULATION PANEL >>> H-19 FNP UNIT 1 LOAD LIST A-506250 1secth.doc Page H - 13 Rev. 2 DH01EG05 FHA4 1K-36 1G 125V DC DIST PNL AB - 139' D177082 (CONT'D) D181743FUSE TPNS DESCRIPTION1G-16 N1E12YSH3186A-N CTMT COOLER 1A VIBRATION SWITCH RESET COIL N1E12YSH3186B-N CTMT COOLER 1B VIBRATION SWITCH RESET COIL N1E12YSH3186C-N CTMT COOLER 1C VIBRATION SWITCH RESET COIL N1E12YSH3186D-N CTMT COOLER 1D VIBRATION SWITCH RESET COIL 1G-17 N1V47L0003-N LOWER EQUIP RM INTAKE & EXHAUST DAMPERS LOCAL CONTROL STATION - SV'S & POS IND LTS FOR DAMPERS N1V47HV2774,HV2778,HV2777,HV27801G-18 N1T50TAH2790A-N CTMT PRE-ACCESS FILTER UNIT 1A FIRE DET PNL N1T50TAH2790B-N CTMT PRE-ACCESS FILTER UNIT 1B FIRE DET PNL 1G-19 N1V43G0096-N SPRINKLER SYSTEM 1A-52A (DOSIMETRY LAB RM 461) TROUBLE HORN N1V43G0097-N SPRINKLER SYSTEM 1A-52A ALARM BELL N1V43G0771A-N SPRINKLER SYSTEM 1A-52B (HP OFFICE/LAB, CLEAN REST ROOMS) TROUBLE HORN N1V43G0772A-N SPRINKLER SYSTEM 1A-52B FIRE BELL 1G-20 N1V43G0102-N SPRINKLER SYSTEM 1A-21 (STORAGE RM 167 - ELEV. 100') FIRE BELL N1V43G0101-N SPRINKLER SYSTEM 1A-21 TROUBLE HORN ------------- SPRINKLER SYSTEM 1A-21 AUX ANNUN RELAY N1V43G0135-N SPRINKLER SYS SUPPRESSION ZONE 1A-132 (COMBUST STOR RM 107 & AUX BLDG WEST ELEV. 83') FIRE BELL N1V43G0136-N SPRINKLER SYS SUPPRESSION ZONE 1A-132 TROUBLE HORN N1V43G0137-N SPRINKLER SYS SUPPRESSION ZONE 1A-132 ACTUATION IND LIGHT FNP UNIT 1 LOAD LIST A-506250 1secth.doc Page H - 14 Rev. 2 DH01EG05 FHA4 1K-36 1G 125V DC DIST PNL AB - 139' D177082 (CONT'D) D181743FUSE TPNS DESCRIPTION1G-21 --------------- SPARE 1G-22 --------------- SPARE 1G-23 N1V43G0012N-N SPRINKLER SYS SUPPRESSION ZONE 1A-48 (AUX BLDG NORTH CORRIDOR ELEV. 139') ACTUATION IND LIGHT N1V43G0002Y-N SPRINKLER SYS SUPPRESSION ZONE 1A-48 TROUBLE HORN N1V43G0003Y-N SPRINKLER SYS SUPPRESSION ZONE 1A-48 FIRE BELL N1V43G0012P-N SPRINKLER SYS SUPPRESSION ZONE 1A-53 (TRAIN A,N,V VERT CABLE CHASE ELEV. 83-144') ACTUATION IND LIGHT N1V43G0012Q-N SPRINKLER SYS SUPPRESSION ZONE 1A-55 (TRAIN B,S,W VERT CABLE CHASE ELEV. 83-155') ACTUATION IND LIGHT N1V43G0012T-N SPRINKLER SYS SUPPRESSION ZONE 1A-45 (PIPE PENE RM 223 ELEV. 139') ACTUATION IND LIGHT N1V43G0004A-N SPRINKLER SYS SUPPRESSION ZONES 1A-53, 1A-55, 1A-45 TROUBLE HORN N1V43G0005A-N SPRINKLER SYS SUPPRESSION ZONES 1A-53, 1A-55, 1A-45 FIRE BELL 1G-24 --------------- SPARE FNP UNIT 1 LOAD LIST A-506250 1secth.doc Page H - 15 Rev. 2 DH01EG05 FHA4 1K-36 1G 125V DC DIST PNL AB - 139' D177082 (CONT'D) D181743FUSE TPNS DESCRIPTION1G-25 N1V43G0012L-N SPRINKLER SYS SUPPRESSION ZONE 1A-61 (TRAIN "B" CABLE CHASE FROM DG BLDG) ACTUATION IND LIGHT N1V43G0012F-N SPRINKLER SYS SUPPRESSION ZONE 1A-62 (AFW PUMPS CABLE AREA ELEV. 100') ACTUATION IND LIGHT N1V43G0012K-N SPRINKLER SYS SUPPRESSION ZONE 1A-119 (NORTHWEST CORNER RM 185 & CCW PUMP AREA ELEV. 100') ACTUATION IND LIGHT N1V43G0012U-N SPRINKLER SYS SUPPRESSION ZONE 1A-27 (CCW PUMP 1B 5KV SW 1A & 1B AND CABLE TRAY AREA, RM 185 ELEV. 100') ACTUATION IND LIGHT N1V43G0012E-N SPRINKLER SYS SUPPRESSION ZONE 1A-60 (TRAIN "A" CABLE CHASE FROM DG BLDG) ACTUATION IND LIGHT N1V43G0003R-N SPRINKLER SYS SUPPRESSION ZONES 1A-61,1A-62,1A-119,1A-27,1A-60 FIRE BELL N1V43G0002R-N SPRINKLER SYS SUPPRESSION ZONES 1A-61,1A-62,1A-119,1A-27,1A-60 TROUBLE HORN FNP UNIT 1 LOAD LIST A-506250 1secth.doc Page H - 32 Rev. 66 DHO1EG07 FJB4 1J-27 1H 125V DC DIST PNL AB - 139' D177083 BKR TPNS DESCRIPTIONN1R41L0001H-N1H 125V DC DISTRIBUTION PANEL <<< 1J-27 1H-01 N1R15A0002-N 1B 4160V BUS DC CONTROL POWER FOR INCOMING BKRS DB01&DB051H-02 N1R16B0009-N 1I 600V LOAD CENTER DC CONTROL PWR FOR INCOMING BKRS EI02 & EI05 1H-03 N1R15A0002-N 1B 4160V BUS DC CONTROL POWER FOR RCP BUS U/V TRIP LOGIC AUX TIMING RELAYS 2-1 & 2-2, AND RCP AUX PT CABINET N1R15A002X, DBX3 TIMING & ALARM RLYS 2-3, 2-4, 74-1 1B 4160V BUS DC CONTROL PWR FOR RCP BUS U/F TRIP LOGIC RELAYS 81-1 & 81-2 1B 4160V BUS DC CONTROL POWER FOR BUS U/V AUX RELAYS 27-2X & 27-4X (SYNC CHECK PERMISSIVE, LOAD SHED ALARM) 1B 4160V BUS DC CONTROL POWER FOR FDR BKRS DB03 & DB04 AND LOSS OF DC VOLTAGE ALARM RELAY 74 1H-04 N1R16B0009-N 1I 600V LOAD CENTER DC CONTROL PWR FOR FEEDER BKRS EI03 & EI04 1H-05 N1R15G0001B-N BKR TEST CABINET FOR 4KV BUS 1B & 1C 1H-06 N1R16B0015-N 1N 600V LOAD CENTER DC CONTROL PWR FOR INCOMING BKRS EN02 & EN04 1H-07 N1V47HS3633-N 600V AUX BLDG LOAD CENTER RM DAMPER SV'S LOCAL CONTROL STATION - DAMPER SVS N1V47SV3633A - H & POS IND LIGHTS 1H-08 N1R16B0015-N 1N 600V LOAD CENTER DC CONTROL PWR FOR FEEDER BKRS EN03,EN05,EN06,EN07 AND EN08 1N 600V LOAD CENTER DC CONTROL PWR FOR STATION SERVICE XFMR 1N DIFFERENTIAL PROTECTION FNP UNIT 1 LOAD LIST A-506250 1secth.doc Page H - 33 Rev. 7 DHO1EG07 FJB4 1J-27 1H 125V DC DIST PNL AB - 139' D177083 (CONT'D)BKR TPNS DESCRIPTION1H-09 --------------- SPARE 1H-10 NSV46SV3860-N RADIOACTIVE LAB EXH DAMPER "A" SV NSV46SV3861-N RADIOACTIVE LAB EXH DAMPER "A" SV NSV46SV3862-N RADIOACTIVE LAB EXH DAMPER "B" SV NSV46SV3863-N RADIOACTIVE LAB EXH DAMPER "B" SV NSV46SV3864-N GAS ANALYSIS RM EXH DAMPER SV NSV46SV3865-N GAS ANALYSIS RM EXH DAMPER SV 1H-11 --------------- SPARE 1H-12 --------------- SPARE 1H-13 N1G21NDWE2609-N WASTE EVAPORATOR CONTROL PNL ANNUN & VALVE POS IND LIGHTS 1H-14 --------------- SPARE 1H-15 N1G21G0019-N CTMT SUMP PUMP ALTERNATOR --------------- MAIN TURBINE AC BEARING OIL PUMP (NIN33M0501-N) DISCH PRESS SWITCH AUX RELAY 63X: AUTO CLOSE PERMISSIVES FOR ALT BRG OIL PUMP BKR EG04 & AUX SEAL OIL BACKUP PUMP (N1N33M0503-N) 1H-16 N1G21NDRE2608-N RE-CYCLE EVAPORATOR CONTROL PANEL ANNUN & VALVE POS IND LIGHTS 1H-17 N1V46TAH2792-N RADWASTE FILTRATION UNIT FIRE DETECTION PANEL CONTROL POWER N1P13TAN2791-N CTMT PURGE FILTER UNIT FIRE DETECTION PANEL CONTROL POWER N1V48TAH2800-N SPENT FUEL POOL FILTRATION UNIT FIRE DETECTION PANEL CONTROL POWER FNP UNIT 1 LOAD LIST A-506250 1secth.doc Page H - 34 Rev. 7 DHO1EG07 FJB4 1J-27 1H 125V DC DIST PNL AB - 139' D177083 (CONT'D)BKR TPNS DESCRIPTION1H-18 --------------- SPARE 1H-19 N1P16V0588-N CIRCULATING WATER BLOWDOWN VALVE SOLENOID 20-12 1H-20 N1G24NDSGB2611-NSTEAM GEN BLOWDOWN PROCESSING PANEL CONTROL CKT (VALVES 1TCV-1150 & 1152,1RCV-023B,1-7604 & 7607 AND FAILURE RELAY XY\1180B FOR ANNUN) 1H-21 N1V43G0091-N CASK WASH AREA (EL. 155') SPRINKLER SYSTEM (ZONE 1A-58) TROUBLE HORN N1V43G0092-N CASK WASH AREA (EL. 155') SPRINKLER SYSTEM (ZONE 1A-58) ALARM BELL 1H-22 --------------- SPARE 1H-23 N1V43G0012B-N AUX BLDG WEST CORRIDOR (ELEV. 139') SPRINKLER SYSTEM (ZONE 1A-59) ACTUATION IND LIGHT N1V43G0012C-N AUX BLDG WEST VERTICLE CABLE CHASE SPRINKLER SYSTEM (ZONE 1A-23) ACTUATION IND LIGHT N1V43G0012G-N CABLE SPREADING RM (ELEV. 139') SPRINKLER SYSTEM (ZONE 1A-43) ACTUATION IND LIGHT N1V43G0002S-N SPRINKLER SYSTEM SUPPRESSION ZONES 1A-59, 1A-23, & 1A-43 TROUBLE HORN FNP UNIT 1 LOAD LIST A-506250 1secth.doc Page H - 35 Rev. 2 DHO1EG07 FJB4 1J-27 1H 125V DC DIST PNL AB - 139' D177083 (CONT'D)BKR TPNS DESCRIPTION1H-23 N1V43G0003S-N SPRINKLER SYSTEM SUPPRESSION ZONES 1A-59, 1A-23, & 1A-43 ALARM BELL 1H-24 --------------- SPARE 1H-25 N1V43G0012H-N AUX BLDG FILT HATCH ACCESS RM (ELEV. 155') SPRINKLER SYSTEM (ZONE 1A-112) ACTUATION IND LIGHT N1V43G0012J-N AUX BLDG WEST CORRIDOR (ELEV. 155') SPRINKLER SYSTEM (ZONE 1A-114) ACTUATION IND LIGHT N1V43G0003T-N SPRINKLER SYSTEM SUPPRESSION ZONES 1A-112 & 1A-114 ALARM BELL N1V43G0002T-N SPRINKLER SYSTEM SUPPRESSION ZONES 1A-112 & 1A-114 TROUBLE HORN N1V43G0012A-N DOSIMETRY LAB & NON-RAD VENT EQUIP ROOMS 461, 462, 463, 464 (ELEV. 155') SPRINKLER SYSTEM (ZONE 1A-51) ACTIVATION IND LIGHT N1V43G0002N-N SPRINKLER SYSTEM SUPPRESSION ZONE 1A-51 HORN N1V43G0003N-N SPRINKLER SYSTEM SUPPRESSION ZONE 1A-51 BELL 1H-26 --------------- SPARE FNP ILT-38 JPM Page 1 of 4 jpm j. SO-444 TITLE: Restore Compressed Air Systems After An Auto Isolation ACCEPTABLE EVALUATION METHOD: PERFORM X SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X PLANT PROJECTED TIME: 8 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS: 1. All actions will be SIMULATED. 2. This JPM to be performed on UNIT 1 ONLY. 3. Provide student HANDOUT and procedure. 4. Allow student time to review conditions and procedure. TASK STANDARD: 1. Restore Compressed Air Systems After An Auto Isolation on Unit 1. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) EXAMINER:___________________________ Developer S. Jackson Date: 4/6/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP ILT-38 JPM Page 2 of 4 CONDITIONS When I tell you to begin, you are to RESTORE COMPRESSED AIR SYSTEMS AFTER AN AUTO ISOLATION. The conditions under which this task is to be performed are:

a. An auto isolation of the compressed air system has occurred. b. Cause of auto isolation has been found and corrected. c. Sufficient air compressors have been returned to continuous service. d. Directed by control room operator to perform FNP SOP-31.0, Section 4.1 step 2 and continue with the procedure. e. A pre-job brief is not required. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME NOTE: All steps come from Section 4.1 of SOP-31.0 *1. 2 Reset, close Air Dryer AUTO BYP VLV N1P19V902. Reset button for N1P19V902 depressed. (CUE: Valve position indicating light not illuminated, if valve position checked, valve is as you see it.) S / U 2. 3 Reset, open Non-Essential IA AUTO ISO VLV N1P19V904. Reset button for N1P19V904 depressed. (CUE: Valve position indicating light not illuminated, if valve position checked, valve is as you see it.) S / U *3. 4 Crack open Essential IA HDR ISO BYP VLV N1P19V942C, allow DP to equalize. N1P19V942C turned counter-clockwise to crack open. (CUE: Handle is as you describe and flow noise is heard then stops.) S / U *4. 5 Reset, open Essential IA HDR AUTO ISO VLV N1P19V903. Reset button N1P19V903 depressed. (CUE: Valve position indicating light not illuminated, if valve position checked valve is as you see it.) S / U NOTE: THIS JPM WILL BE PERFORMED ON UNIT 1 ONLY.

FNP ILT-38 JPM Page 3 of 4 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *5. 6 Close Essential IA HDR BYP VLV N1P19V942C. N1P19V942C turned clockwise to close. (CUE: Valve handle is as you see it.) S / U STOP TIME Terminate after V942C is closed. CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) preceding the element number. GENERAL

REFERENCES:

1. FNP-1-SOP-31.0, Version 80.0 2. K/A 065AA1.03 - 2.9 / 3.1 GENERAL TOOLS AND EQUIPMENT:

None Critical ELEMENT justification: 1 Critical- If the air dryers are left bypassed for a significant period of time, moisture in the air line would negatively affect component operation. 2 Not Critcal - No critical equipment in the Service building. 3 Critical - Without equalizing pressure, opening V903 may cause air pressure to drop to the point of another auto isolation 4 Critical - Task completion. Allows for regaining control of AOVs. 5 Critical - Task completion. Would prevent the system from automatically isolating future leaks. COMMENTS: FNPP ILT-38 JPM HANDOUT Page 1 of 1 jpm j CONDITIONS When I tell you to begin, you are to RESTORE COMPRESSED AIR SYSTEMS AFTER AN AUTO ISOLATION. The conditions under which this task is to be performed are:

a. An auto isolation of the compressed air system has occurred. b. Cause of auto isolation has been found and corrected. c. Sufficient air compressors have been returned to continuous service. d. Directed by control room operator to perform FNP SOP-31.0, Section 4.1 step 2 and continue with the procedure. e. A pre-job brief is not required.

Printed 06/03/2015 at 12:48:00 FARLEY Unit 1 SAFETY RELATEDFNP-1-SOP-31.0COMPRESSED AIR SYSTEM VERSION 80.0 PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous ALLReference NONE InformationNONE Approval: David L Reed 05/21/2015 Approved By Date Effective Date: OPERATIONS Responsible Department COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 2 of 81 Printed 06/03/2015 at 12:48:00 VERSION SUMMARY Version 78.0 Description Reformatted to new Fleet Template per NMP AP 002 GL02, SNC Fleet Procedure Template Guidelines.Updated procedure to requirements of NMP-AP-002, SNC Fleet Procedures Writers Guide. Updated SEQ OPS & incorporated SAC Appendixes into main body of procedure. Version 79.0 Description Added Sections 4.2.2, 4.2.3, 4.3.2, 4.3.3, 4.4.2, 4.4.3 for starting/stopping A/C from MCB Version 80.0 Description Split Sections into individual Sections for each SAC. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 3 of 81 Printed 06/03/2015 at 12:48:00 TABLE OF CONTENTS SECTION ..........................................................................................................................................PAGE1.0 PURPOSE ....................................................................................................................................62.0 INITIAL CONDITIONS ..................................................................................................................63.0 PRECAUTIONS AND LIMITATIONS ............................................................................................64.0 INSTRUCTIONS ...........................................................................................................................94.1 COMPRESSED AIR SYS STARTUP, NORMAL OPERATION ....................................................94.2 1A SAC OPERATION .................................................................................................................114.2.1 Starting 1A SAC in Local or Remote Following Extended S/D or MAINT .....................114.2.2 MCB Shutdown of 1A SAC ............................................................................................144.2.3 MCB Startup of 1A SAC ................................................................................................144.3 1B SAC OPERATION .................................................................................................................154.3.1 Starting 1B SAC in Local or Remote Following Extended S/D or MAINT .....................154.3.2 MCB Shutdown of 1B SAC ............................................................................................184.3.3 MCB Startup of 1B SAC ................................................................................................184.4 1C SAC OPERATION .................................................................................................................194.4.1 Starting 1C SAC in Local or Remote Following Extended S/D or MAINT .....................19 4.4.2 MCB Shutdown of 1C SAC ...........................................................................................224.4.3 MCB Startup of 1C SAC ................................................................................................224.5 SEQUENCER SETUP, OPERATION .........................................................................................234.5.1 Activating Sequencer on 1A SAC Primary Regulator ....................................................234.5.2 Verifying Number of SACs Selected in LAN ..................................................................244.5.3 Verifying Pressure Control Band 1 on SEQ ..................................................................254.5.4 Zeroing SAC Run Hours on SEQ ..................................................................................264.6 INTEGRATION OF 1A OR 1B OR 1C SAC TO SEQUENCER ..................................................274.6.1 Integrating 1A SAC to SEQ ...........................................................................................274.6.2 Integrating 1B SAC to SEQ ...........................................................................................284.6.3 Integrating 1C SAC to SEQ ...........................................................................................294.7 DURING OPERATION ...............................................................................................................304.8 ISOLATING 1A OR 1B OR 1C SAC FROM SEQ .......................................................................314.8.1 Isolating 1A SAC From SEQ .........................................................................................314.8.2 Isolating 1B SAC From SEQ .........................................................................................324.8.3 Isolating 1C SAC From SEQ .........................................................................................334.9 RE-INTEGRATION OF 1A OR 1B OR 1C SAC TO SEQ ...........................................................344.9.1 Re-Integrating 1A SAC to SEQ .....................................................................................344.9.2 Re-Integrating 1B SAC to SEQ .....................................................................................354.9.3 Re-Integrating 1C SAC to SEQ .....................................................................................364.10 MANUAL BLOWDOWN OF TURBINE BLDG SAC AIR RECEIVERS .......................................37 COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 4 of 81 Printed 06/03/2015 at 12:48:00 TABLE OF CONTENTS (continued)SECTION ..........................................................................................................................................PAGE4.10.1 Manual BLDN of 1A SAC Air RCVR ..............................................................................374.10.2 Manual BLDN of 1B SAC Air Receivers ........................................................................374.10.3 Manual BLDN of 1C SAC Air RCVR .............................................................................384.11 SUPPLYING SW FROM UNIT 2 ................................................................................................394.12 RETURNING SW SUPPLY FROM UNIT 2 TO UNIT 1 ..............................................................394.13 BYPASSING SAC SW SUPPLY SOLENOID VALVES ..............................................................394.13.1 Bypassing 1A SAC SW Supply Solenoid VLV N1P19G0507A .....................................394.13.2 Bypassing 1B SAC SW Supply Solenoid VLV N1P19G0507B .....................................39 4.13.3 Bypassing 1C SAC SW Supply Solenoid VLV N1P19G0507C .....................................394.14 RETURN TO SERVICE: SAC SW SUPPLY SOLENOID VALVES ............................................404.14.1 RTS 1A SAC SW Supply Solenoid VLV N1P19G0507A ...............................................404.14.2 RTS 1B SAC SW Supply Solenoid VLV N1P19G0507B ...............................................404.14.3 RTS 1C SAC SW Supply Solenoid VLV N1P19G0507C ..............................................404.15 PURGE FLOW SETUP FOR TURB BLDG IA DRYER DEWPOINT MONITOR ........................404.16 RESETTING SAC SERVICE PLAN WARNING ALARMS .........................................................414.16.1 Resetting 1A SAC Service Plan Warning Alarms ..........................................................414.16.2 Resetting 1B SAC Service Plan Warning Alarms ..........................................................424.16.3 Resetting 1C SAC Service Plan Warning Alarms .........................................................4

35.0 REFERENCES

...........................................................................................................................446.0 RECORDS ..................................................................................................................................45FIGURE1 MK-IV REG CONT PNL ..............................................................................................................462 MK-IV REG FUNCTIONS ...........................................................................................................473 MK-IV REG CONT PROGRAMS ................................................................................................48 4 MK-IV PRI REG: SAC STATUS .................................................................................................495 MK-IV REG: CALLING UP MENUS ............................................................................................506 MK-IV REG: STATUS DATA MENU ...........................................................................................517 MK-IV REG: MEASURE DATA, PROG CONT MODES, SAVED DATA MENUS ......................52ATTACHMENT 1 ALIGNING ALTERNATE AIR SUPPLY TO CTMT (Retain for QA Record) ...............................532 2C SAC OPERATION ON UNIT ONE ........................................................................................573 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) ............................................60 4 LEAKAGE ASSESSMENT ON IA HEADER IN CTMT (Retain for QA Record) .........................71TABLE1 COMPONENTS DOWNSTREAM OF N1P19V094, IA TO 105 FT NE AREA ISO ....................732 COMPONENTS DOWNSTREAM OF N1P19V010, IA TO 105 FT NW AREA ISO ...................77 COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 5 of 81 Printed 06/03/2015 at 12:48:00 TABLE OF CONTENTS (continued)SECTION ..........................................................................................................................................PAGETABLE (continued) 3 COMPONENTS DOWNSTREAM OF N1P19V011, IA TO 129 FT ISO .....................................784 COMPONENTS DOWNSTREAM OF N1P19V012, IA TO 155 FT ISO .....................................81 COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 6 of 81 Printed 06/03/2015 at 12:48:00 1.0 PURPOSEThis procedure provides Initial Conditions, Precautions, Limitations, Instructions for operation of Compressed Air SYS. ......................................................................................... 2.0 INITIAL CONDITIONS 1. Electrical DIST SYS energized for normal operation per FNP-1-SOP-36.0, Plant Electrical DIST Line-Up, FNP-1-SOP-36.4, 120V A.C. DIST SYS, with exceptions noted. 2. Compressed Air SYS valves, Electrical DIST SYS, aligned per SYS Check Lists FNP-1-SOP-31.0A, B, C, D with exceptions noted. 3. SW available to supply cooling water to SACs. 4. Figures show helpful information. 3.0 PRECAUTIONS AND LIMITATIONS 1.Openair valves slowly to allow PRESS to equalize gradually. .................................... 2.Do Not operate SACs without cooling water................................................................3. Configure SACs at their LCPs to Remote [MCB] or Local to unload prior to stopping. ....................................................................................................................... 4. 1B AND 1C SACs must be isolated from SEQ per Section 4.8.2 ANDSection 4.8.3, placed in Remote CONT (MCB) IF removing power from 1A SAC. [BKR open] ......................................................................................................... 5. In order to prevent excessive condensation, DO NOT circulate cooling water through SAC removed from service. [via SW Supply BYP VLV] .................................. 6.Maintaincooling water outlet temperature < 122F. ["Cooling Water Element Out" on SAC LCP display screen] ................................................................................ 7. SACs have MAX permissible number of motor starts of 5 per hour. Recommended by manufacturer to observe interval of 20 minutes between each manual start. ........................................................................................................ 8. Stop times. [NOT associated with power loss] a.Whenin Local or Remote CONT, Programmed Stop Time (SAC): After pressing stop button, SAC runs unloaded for 3 seconds, then stops.

Start command during this period ignored. ........................................................ b.Whenin Local or Remote CONT, MIN Stop Time (SAC Motor): After stopping, module prevents motor from restarting for 20 seconds. Start command during this time will be memorized, executed after 20 second time period. ........................................................................................................ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 7 of 81 3.0 PRECAUTIONS AND LIMITATIONS (continued) Printed 06/03/2015 at 12:48:00 9.WhenSAC configured for Remote CONT, SAC will (1) stop if MCB hand switch selected to OFF or (2) start, load if MCB hand switch taken to AUTO position, based on Internal Mode PRESS settings on SAC, Automatic Operation LED on SAC LCP will be lit. When SAC configured for LAN or Local, MCB hand switch disabled. .......................................................................................... 10.Do Not use EMERGENCY STOP button for normal shutdown of SAC (normal stop unloads SAC first, maintains cooling water flow to SAC for several seconds after stopping. EMERGENCY STOP does neither). ...................................... 11. Automatic Restart After Voltage Failure Function activated for SACs. For any SAC, if aligned for operation prior to loss of power, it will resume operation after its power supply restored dependent upon its internal PRESS switch demand. Following A-TRN LOSP, power supply to 1C SAC automatically re-energized following B1F Sequencer operation. 1A SAC must be manually aligned to re-start following LOSP. ............................................................................... 12.Whenon SEQ (MCC function) SAC's internal PRESS settings disabled. SAC will load, unload by SEQ based on 1A SAC outlet PRESS (PRI REG). IF SEQ fails or loses power, SACs controlled by their internal PRESS switches. When in Local or Remote CONT, SAC start-load/unload-stop operation controlled by its internal PRESS settings, timers, as long as Automatic Operation LED (green) LIT. IF operation by Internal Mode PRESS settings desired, refer to Section 4.2, Section 4.3 or Section 4.4 for guidance on operating SAC in Local or Remote. .......... 13. Pressing F2 from Main Screen on 1A SAC PRI REG will activate MCC (SEQ) Screen showing 1A, 1B, 1C SAC status. If one of SACs not reacting on command from PRI REG, press F2 ("Reset" Key) to reset communication between PRI REG SEQ, other two Secondary Regulators. [Figure 4] ......................... 14. SAC Protection: a. Number of times based AUTO start/stop commands programmed on SACs. ... b.Takeinto account start command will be executed (if programmed, activated), even after manually stopping SAC. .................................................. c. Several sensors provided on SAC. If one of these measurements exceeds programmed S/D level, SAC will stop. This will be indicated on display, General Alarm LED will blink. Refer to Figure 6 for guidance on various shut-down messages, S/D warning messages. .................................... d. IFmeasurements exceeds programmed S/D warning levels, message will appear on SAC LCP Display Screen, General Alarm LED will light up to warn operator S/D warning level exceeded. message disappears when warning condition clears. .......................................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 8 of 81 3.0 PRECAUTIONS AND LIMITATIONS (continued) Printed 06/03/2015 at 12:48:00 15. Service warning: A number of service operations are grouped (called Level A, B, C, ...). Each level has programmed time interval. If time interval exceeded, a message will appear on display (1) to warn operator to carry out service actions belonging to that level. ..................................................................................... 16. Warning functions prior to S/D: a. LO PRESS Outlet Air TEMP (ELE 1), 410°F. .................................................... b. HI PRESS Inlet Air TEMP (ELE 2), 149°F. ........................................................ c. HI PRESS Outlet Air TEMP (ELE 2), 410°F. ..................................................... d. Oil TEMP, 149°F. ............................................................................................... e. Oil PRESS LO, 18.9 PSIG. ................................................................................ 17. S/D functions: a. LO PRESS Outlet Air TEMP HI (ELE 1), 428°F. ............................................... b. HI PRESS Inlet Air TEMP HI (ELE 2), 158°F. ................................................... c. HI PRESS Outlet Air TEMP HI (ELE 2), 428°F. ................................................. d. Oil TEMP HI, 158°F. .......................................................................................... e. Oil PRESS LO, < 17.4 PSIG. ............................................................................. f. SW DISCH TEMP HI, 122°F..............................................................................g. Drive Motor Overload. ........................................................................................ h. Vent Fan Motor Overload. ................................................................................. i. Emergency Stop Button on SAC Local Panel. ................................................... j. Loss of Control Power to SAC Local Panel. ...................................................... k. Loss of 600 V Power to SAC. ............................................................................ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 9 of 81 Printed 06/03/2015 at 12:48:00 4.0 INSTRUCTIONS 4.1 COMPRESSED AIR SYS STARTUP, NORMAL OPERATION NOTES SECT 4.1 Step 2 through SECT 4.1 Step 11 only required if Compressed Air SYS been completely S/D, SYS being placed in-SERV with initial SAC. ..................................................... These steps should have been completed if Compressed Air SYS in-SERV; however, IF desired, steps can be verified when SAC placed in-SERV. ..................................... 1.Place 1A, 1B AND/OR 1C SAC in service per Section 4.2 1A ,Section 4.3 1B or Section 4.4 1C. ............................................................................................................. 2.Reset,close Air Dryer AUTO BYP VLV N1P19V902. ................................................. 3.Reset,open Non-Essential IA AUTO ISO VLV N1P19V904. ...................................... CAUTION In the following step, open air VLV slowly to allow PRESS to equalize gradually. ............................. 4.Crackopen Essential IA HDR ISO BYP VLV N1P19V942C, allow DP to equalize. ... 5.Reset,open Essential IA HDR AUTO ISO VLV N1P19V903. ..................................... 6.Close Essential IA HDR BYP VLV N1P19V942C. ....................................................... 7.Open the following valves to supply IA to PPR, CTMT: IA to PENE RM N1P19HV3885. ........................................................................ IA to PENE RM N1P19HV3825. ........................................................................ IA to CTMT Q1P19HV3611. .............................................................................. 8.Verify IA PRESS 90 - 100 PSIG. .............................................................................. NOTES Purge PRESS can only be read, adjusted when off-stream desiccant chamber depressurized for regeneration. When off-stream chamber pressurized, Purge PRESS Indicator reads SYS PRESS. (Ref. U418762) ............................................................................. I&C assistance needed for the following step, IF adjustments to be made. ................................ 9.Monitor each air dryer during regeneration cycle to ensure purge air PRESS 21 to 31 PSIG. IF required, adjust purge air PRESS using associated FCV on 1A and/or 1B Air Dryer by performing the following: a.Slowlyrotate 1A Dryer, N1P19F001A Purge Throttle VLV, N1P19V1088E until purge PRESS reads 21 to 31 PSIG on Purge Flow Indicator, N1P19FI565. Throttle VLV, located 5 inches behind Purge PRESS Indicator, between 2 chambers. Requires screwdriver or similar device to make adjustment. ............................................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 10 of 81 4.1 COMPRESSED AIR SYS STARTUP, NORMAL OPERATION (continued) 9. (continued) Printed 06/03/2015 at 12:48:00 b.Slowlyrotate 1B Dryer, N1P19F001B Purge Throttle VLV, N1P19V1089E until purge PRESS reads 21 to 31 PSIG on Purge Flow Indicator, N1P19FI566. Throttle VLV located 5 inches behind Purge PRESS Indicator, between 2 chambers. Requires screwdriver or similar device to make adjustment. ............................................................................... 10.Monitor each air dryer during operation cycle; verify proper operation by BLUE color on moisture indicator. ................................................................................ 11.Monitor SA, IA PRESS', IF necessary to maintain air PRESS' > 88 PSIG, place additional SAC(s) in service. .............................................................................. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 11 of 81 Printed 06/03/2015 at 12:48:00 4.2 1A SAC OPERATION4.2.1 Starting 1A SAC in Local or Remote Following Extended S/D or MAINT NOTE This section may also be used for pre-operational checks for 1A SAC. ............................................ 1.Start-up 1A SAC by performing the following: a.Obtain SS permission prior to S/U of 1A SAC in Local or Remote CONT. ....... b.Notify CRO 1A SAC to be started up. ............................................................... c.Verify 1A SAC Emergency Stop Button UNLOCKED by turning to left. .......... NOTE In the following step, IF Emergency Stop required to be reset to clear General Alarm LED, refer to Figure 6 for guidance. ............................................................................................................ d.Verify 1A SAC General Alarm LED NOT 'ON' .................................................. e.Check proper oil level in 1A SAC crankcase. .................................................... f. IF returning SA SYS to service, verify SW to Air Compressors Combined HDR ISO VLV N1P16V108 OPEN. .................................................. g.Open 1A SAC After Cooler Moisture Separator Manual DRN N1P19V1065A to DRN any CNDS. ................................................................... h.Close 1A SAC After Cooler Moisture Separator MAN DRN N1P19V1065A. .... i.Open 1A SAC Intercooler Moisture Separator Manual DRN N1P19V1061A to DRN any CNDS. ................................................................... j.Close 1A SAC Intercooler Moisture Separator MAN DRN N1P19V1061A. ...... k.Verify 1A SAC 'Voltage On' LED LIT. ............................................................... NOTE SAC skid valves throttled as necessary to maintain SW, air outlet temperatures. If these valves still in position to which they were throttled previous time SAC in operation, valves do not have to be fully opened. .......................................................................................................... 2. IF 1A SAC being started for first time after maintenance, check 1A SAC skid valves in their proper position: ..................................................................................... N1P16V623A 1A SAC SW REG OpenN1P16V645A 1A SAC After Cooler SW REG Open COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 12 of 81 4.2.1 Starting 1A SAC in Local or Remote Following Extended S/D or MAINT (continued)Printed 06/03/2015 at 12:48:00 3.Verify Internal Mode Loading AND Unloading PRESS settings on 1A SAC LCP, as follows: a.Verify 1A SAC MCB Hand Switch in OFF. ........................................................ b.Press F1 until Main Screen appears. ................................................................ c.Press F1 ('Menu') from Main Screen. ................................................................ d.Press Scroll Down Key until "Modify Parameters" followed by horizontal arrow. [Tabulator Key] ....................................................................................... e.Press Tabulator Key to activate Menu. ............................................................. f.Check first item, "Parameters", followed by horizontal arrow. ........................... g.Press Tabulator Key..........................................................................................h.Verify Loading PRESS 88 PSIG, Unloading PRESS 96 PSIG for 1A SAC. ..... i. IF pressures correct, proceed to Step 4 below. ................................................ j. IF pressures need adjusting, perform the following: (1)Press F2 ("Modify") to change Loading PRESS setting. ........................ NOTE F2 ("Limits") can be used to find limitations for parameter. ................................................................ (2)Use Scroll Keys to change 1A Loading PRESS to 88 PSIG. ................. (3)Press F1 ("Program") to program new value OR F3 ("Cancel"). ............. (4)Press F2 ("Modify") to change Unloading PRESS setting. .................... (5)Use Scroll Keys to change 1A Unloading PRESS to 96 PSIG. .............. (6)Press F1 ("Program") to program new value OR F3 ("Cancel"). ............. 4.Press F1 until Main Screen appears. .......................................................................... 5.Press andhold Scroll Up Key to activate "Configurations Menu". .............................. 6.Scroll to option 'C.C.M', perform the following: a.Press F2 ('Mod') to modify. ............................................................................... b.Use Scroll Keys to select LOCAL. ..................................................................... c.Press "PROG" Key. ........................................................................................... d.Check 1A SAC number blinks on MCC Screen of 1A SAC PRI REG. ........ 7.Press F1 until Main Screen appears. .......................................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 13 of 81 4.2.1 Starting 1A SAC in Local or Remote Following Extended S/D or MAINT (continued)Printed 06/03/2015 at 12:48:00 NOTE It may be necessary to manually BLDN 1A Air RCVR < 85 PSIG per Section 4.10 to watch SAC ....... CAUTION Procedure verifies SAC operability on Internal Mode PRESS settings; therefore, plant conditions must allow establishment of 1A RCVR PRESS < 85 PSIG...............................................8.Press 1A SAC start button. .......................................................................................... 9.Verify 1A SAC starts, loads, unloads as programmed on its Internal Mode PRESS settings. ........................................................................................................... 10. IF pre-operational check, press 1A SAC stop button. ................................................. 11.Press andhold Scroll Up Key to activate "Configurations Menu". .............................. 12.Scroll to option 'C.C.M', perform the following: .......................................................... a.Press F2 ('Mod') to modify. ............................................................................... b.Use Scroll Keys to select REMOTE. [MCB] ...................................................... c.Press "PROG" Key. ........................................................................................... d.Check 1A SAC number blinks on MCC Screen of 1A SAC PRI REG. ........ 13.Press F1 until Main Screen appears. .......................................................................... 14.Notify CONT RM 1A SAC in REMOTE CONTROL. .................................................... 15.Place MCB H/S for 1A Air Compressor to AUTO. ....................................................... 16.Verify 1A SAC starts, loads, unloads as programmed on its Internal Mode PRESS settings. ........................................................................................................... 17. Leave 1A SAC in Remote on MCB OR proceed to Section 4.6.1 to integrate 1A SAC onto SEQ. ....................................................................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 14 of 81 Printed 06/03/2015 at 12:48:00 4.2.2 MCB Shutdown of 1A SACNOTE 1B AND 1C SACs must be isolated from SEQ per Section 4.8.2 AND Section 4.8.3, placed in Remote CONT (MCB) IF removing power from 1A SAC. [BKR open] ........................................... 1. IF 1A SAC previously selected to MCB control, go to Step 3. ..................................... 2.Isolate 1A SAC from sequencer as follows: a.Obtain SS permission to isolate 1A SAC from sequencer. ............................... b.Notify Control Room of intent to isolate 1A SAC from sequencer. ................... c.Perform the following at 1A SAC: (1)Press F1 until Main Screen appears.......................................................(2)Press and hold Scroll Up Key to activate "Configurations Menu". ......... (3)Scroll to option 'C.C.M'. .......................................................................... (4) To modify, press F2 ('Mod'). ................................................................... (5)Use Scroll Keys to select Remote. [MCB] .............................................. (6)Press "PROG" Key. ................................................................................ (7)Check 1A SAC number blinks on MCC Screen of 1A SAC PRI REG.........................................................................................................d.Notify Control Room 1A SAC in REMOTE CONTROL. .................................... 3. On MCB, place 1A Air Compressor H/S to OFF. ......................................................... 4.2.3 MCB Startup of 1A SAC 1. IF 1A SAC shutdown for long duration such as maintenance or tagging go toSection 4.2.1. ............................................................................................................... 2. IF 1A SAC shutdown for short duration AND no configuration changes made, place 1A Air Compressor H/S to AUTO. ...................................................................... 3. IF desired, perform one of the following: IF 1A SAC shutdown for short duration AND no configuration changes made, go to Section 4.9.1, Re-Integration of 1A SAC to SEQ. .......................... Integrate 1A SAC on sequencer per Section 4.6.1. .......................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 15 of 81 Printed 06/03/2015 at 12:48:00 4.3 1B SAC OPERATION4.3.1 Starting 1B SAC in Local or Remote Following Extended S/D or MAINT NOTE This section may also be used for pre-operational checks for 1B SAC. ............................................ 1.Start-up 1B SAC by performing the following: a.Obtain SS permission prior to S/U of 1B SAC in Local or Remote CONT. ....... b.Notify CRO 1B SAC to be started up. ............................................................... c.Verify 1B SAC Emergency Stop Button UNLOCKED by turning to left. .......... NOTE In the following step, IF Emergency Stop required to be reset to clear General Alarm LED, refer to Figure 6 for guidance. ............................................................................................................. d.Verify 1B SAC General Alarm LED NOT 'ON' .................................................. e.Check proper oil level in 1B SAC crankcase. .................................................... f. IF returning SA SYS to service, verify SW to Air Compressors Combined HDR ISO VLV N1P16V108 OPEN. .................................................. g.Open 1B SAC After Cooler Moisture Separator Manual DRN N1P19V1065B to DRN any CNDS. ................................................................... h.Close 1B SAC After Cooler Moisture Separator MAN DRN N1P19V1065B. .... i.Open 1B SAC Intercooler Moisture Separator Manual DRN N1P19V1061B to DRN any CNDS. ................................................................... j.Close 1B SAC Intercooler Moisture Separator MAN DRN N1P19V1061B. ...... k.Verify 1B SAC 'Voltage On' LED LIT. ............................................................... NOTE SAC skid valves throttled as necessary to maintain SW, air outlet temperatures. If these valves still in position to which they were throttled previous time SAC in operation, valves do not have to be fully opened. .......................................................................................................... 2. IF 1B SAC being started for first time after maintenance, check 1B SAC skid valves in their proper position: ..................................................................................... N1P16V623B 1B SAC SW REG OpenN1P16V645B 1B SAC After Cooler SW REG Open COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 16 of 81 4.3.1 Starting 1B SAC in Local or Remote Following Extended S/D or MAINT (continued)Printed 06/03/2015 at 12:48:00 3.Verify Internal Mode Loading AND Unloading PRESS settings on 1B SAC LCP, as follows: a.Verify 1B SAC MCB Hand Switch in OFF. ........................................................ b.Press F1 until Main Screen appears. ................................................................ c.Press F1 ('Menu') from Main Screen. ................................................................ d.Press Scroll Down Key until "Modify Parameters" followed by horizontal arrow. [Tabulator Key] ....................................................................................... e.Press Tabulator Key to activate Menu. ............................................................. f.Check first item, "Parameters", followed by horizontal arrow. ........................... g.Press Tabulator Key..........................................................................................h.Verify Loading PRESS 92 PSIG, Unloading PRESS 100 PSIG for 1B SAC. ... i. IF pressures correct, proceed to Step 4 below. ................................................ j. IF pressures need adjusting, perform the following: (1)Press F2 ("Modify") to change Loading PRESS setting. ........................ NOTE F2 ("Limits) can be used to find limitations for parameter. ................................................................. (2)Use Scroll Keys to change 1B Loading PRESS to 92 PSIG. ................. (3)Press F1 ("Program") to program new value OR F3 ("Cancel"). ............. (4)Press F2 ("Modify") to change Unloading PRESS setting. .................... (5)Use Scroll Keys to change 1B Unloading PRESS to 100 PSIG. ............ (6)Press F1 ("Program") to program new value OR F3 ("Cancel"). ............. 4.Press F1 until Main Screen appears. .......................................................................... 5.Press andhold Scroll Up Key to activate "Configurations Menu". .............................. 6.Scroll to option 'C.C.M', perform the following: .......................................................... a.Press F2 ('Mod') to modify. ............................................................................... b.Use Scroll Keys to select LOCAL. ..................................................................... c.Press "PROG" Key. ........................................................................................... d.Check 1B SAC number blinks on MCC Screen of 1A SAC PRI REG. ........ 7.Press F1 until Main Screen appears. .......................................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 17 of 81 4.3.1 Starting 1B SAC in Local or Remote Following Extended S/D or MAINT (continued)Printed 06/03/2015 at 12:48:00 NOTE It may be necessary to manually BLDN 1B1 AND 1B2 Air RCVRs < 90 PSIG per Section 4.10 15 minutes if no load on SAC. ............................................................................................................ CAUTION Procedure verifies SAC operability on Internal Mode PRESS settings; therefore, plant conditions must allow establishment of 1B1 AND 1B2 RCVR PRESS < 90 PSIG............................. 8.Press 1B SAC start button. .......................................................................................... 9.Verify 1B SAC starts, loads, unloads as programmed on its Internal Mode PRESS settings. ........................................................................................................... 10. IF pre-operational check, press 1B SAC stop button. ................................................. 11.Press andhold Scroll Up Key to activate "Configurations Menu". .............................. 12.Scroll to option 'C.C.M', perform the following: .......................................................... a.Press F2 ('Mod') to modify. ............................................................................... b.Use Scroll Keys to select REMOTE. [MCB] ...................................................... c.Press "PROG" Key. ........................................................................................... d.Check 1B SAC number blinks on MCC Screen of 1A SAC PRI REG. ........ 13.Press F1 until Main Screen appears. .......................................................................... 14.Notify CONT RM 1B SAC in REMOTE CONTROL. .................................................... 15.Place MCB H/S for 1B Air Compressor to AUTO. ....................................................... 16.Verify 1B SAC starts, loads, unloads as programmed on its Internal Mode PRESS settings. ........................................................................................................... 17. Leave 1B SAC in Remote on MCB OR proceed to Section 4.6.2 to integrate 1B SAC on SEQ. .......................................................................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 18 of 81 Printed 06/03/2015 at 12:48:00 4.3.2 MCB Shutdown of 1B SAC1. IF 1B SAC previously selected to MCB control, go to Step 3. ..................................... 2.Isolate 1B SAC from sequencer as follows: a.Obtain SS permission to isolate 1B SAC from sequencer. ............................... b.Notify Control Room of intent to isolate 1B SAC from sequencer. ................... c. At 1B SAC, perform the following: (1)Press F1 until Main Screen appears.......................................................(2)Press andhold Scroll Up Key to activate "Configurations Menu". ......... (3)Scroll to option 'C.C.M'. .......................................................................... (4) To modify, press F2 ('Mod'). ................................................................... (5)Use Scroll Keys to select Remote. [MCB] .............................................. (6)Press "PROG" Key. ................................................................................ (7)Check 1B SAC number blinks on MCC Screen of 1A SAC PRI REG.........................................................................................................d.Notify Control Room 1B SAC in REMOTE CONTROL. .................................... 3. On MCB, place 1B Air Compressor H/S to OFF. ......................................................... 4.3.3 MCB Startup of 1B SAC 1. IF 1B SAC shutdown for long duration such as maintenance or tagging go toSection 4.3.1. ............................................................................................................... 2. IF 1B SAC shutdown for short duration AND no configuration changes made, place 1B Air Compressor H/S to AUTO. ...................................................................... 3. IF desired, perform one of the following: IF 1B SAC shutdown for short duration AND no configuration changes made, go to Section 4.9.2, Re-Integration of 1B SAC to SEQ. .......................... Integrate 1B SAC on sequencer per Section 4.6.2. .......................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 19 of 81 Printed 06/03/2015 at 12:48:00 4.4 1C SAC OPERATION 4.4.1 Starting 1C SAC in Local or Remote Following Extended S/D or MAINT NOTE This section may also be used for pre-operational checks for 1C SAC. ............................................. 1.Start-up 1C SAC by performing the following: a.Obtain SS permission prior to S/U of 1C SAC in Local or Remote CONT. ....... b.Notify CRO 1C SAC to be started up. ............................................................... c.Verify 1C SAC Emergency Stop Button UNLOCKED by turning to left. .......... NOTE In the following step, IF Emergency Stop required to be reset to clear General Alarm LED, refer to Figure 6 for guidance. ............................................................................................................. d.Verify 1C SAC General Alarm LED NOT 'ON' .................................................. e.Check proper oil level in 1C SAC crankcase. ................................................... f. IF returning SA SYS to service, verify SW To Air Compressors Combined HDR ISO VLV N1P16V108 OPEN. .................................................. g.Open 1C SAC After Cooler Moisture Separator Manual DRN N1P19V1065C to DRN any CNDS. ................................................................... h.Close 1C SAC After Cooler Moisture Separator MAN DRN N1P19V1065C.....i.Open 1C SAC Intercooler Moisture Separator Manual DRN N1P19V1061C to DRN any CNDS. ................................................................... j.Close 1C SAC Intercooler Moisture Separator MAN DRN N1P19V1061C. ...... k.Verify 1C SAC 'Voltage On' LED LIT. ............................................................... NOTE SAC skid valves throttled as necessary to maintain SW, air outlet temperatures. If these valves still in position to which they were throttled previous time SAC in operation, valves do not have to be fully opened. .......................................................................................................... 2. IF 1C SAC being started for first time after maintenance, check 1C SAC skid valves in their proper position: ..................................................................................... N1P16V623C 1C SAC SW REG OpenN1P16V645C 1C SAC AFTER COOLER SW REG Open COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 20 of 81 4.4.1 Starting 1C SAC in Local or Remote Following Extended S/D or MAINT (continued)Printed 06/03/2015 at 12:48:00 3.Verify Internal Mode Loading AND Unloading PRESS settings on 1C SAC LCP, as follows: a.Verify 1C SAC MCB Hand Switch in OFF. ........................................................ b.Press F1 until Main Screen appears. ................................................................ c.Press F1 ('Menu') from Main Screen. ................................................................ d.Press Scroll Down Key until "Modify Parameters" followed by horizontal arrow. (Tabulator Key) ....................................................................................... e.Press Tabulator Key to activate Menu. ............................................................. f.Check first item, "Parameters", followed by horizontal arrow. ........................... g.Press Tabulator Key..........................................................................................h.Verify Loading PRESS 90 PSIG, Unloading PRESS 98 PSIG for 1C SAC ...... i. IF pressures correct, proceed to Step 4 below. ................................................ j. IF pressures need adjusting, perform the following: (1)Press F2 ("Modify") to change Loading PRESS setting. ........................ NOTE F2 ("Limits") can be used to find limitations for parameter. ................................................................ (2)Use Scroll Keys to change 1C Loading PRESS to 90 PSIG. ................. (3)Press F1 ("Program") to program new value or F3 ("Cancel"). ............... (4)Press F2 ("Modify") to change Unloading PRESS setting. .................... (5)Use Scroll Keys to change 1C Unloading PRESS to 98 PSIG. .............. (6)Press F1 ("Program") to program new value or F3 ("Cancel"). ............... 4.Press F1 until Main Screen appears. .......................................................................... 5.Press andhold Scroll Up Key to activate "Configurations Menu". .............................. 6.Scroll to option 'C.C.M', perform the following: .......................................................... a.Press F2 ('Mod') to modify. ............................................................................... b.Use Scroll Keys to select LOCAL. ..................................................................... c.Press "PROG" Key. ........................................................................................... d.Check 1C SAC number blinks on MCC Screen of 1A SAC PRI REG. ........ 7.Press F1 until Main Screen appears. .......................................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 21 of 81 4.4.1 Starting 1C SAC in Local or Remote Following Extended S/D or MAINT (continued)Printed 06/03/2015 at 12:48:00 NOTE It may be necessary to manually BLDN 1C Air RCVR < 87 PSIG per Section 4.10 to watch SAC ....... CAUTION Procedure verifies SAC operability on Internal Mode PRESS settings; therefore, plant conditions must allow establishment of 1C RCVR PRESS < 87 PSIG. ............................................. 8.Press 1C SAC start button. ......................................................................................... 9.Verify 1C SAC starts, loads, unloads as programmed on its Internal Mode PRESS settings. ........................................................................................................... 10. IF pre-operational check, press 1C SAC stop button. ................................................. 11.Press andhold Scroll Up Key to activate "Configurations Menu". .............................. 12.Scroll to option 'C.C.M', perform the following: .......................................................... a.Press F2 ('Mod') to modify. ............................................................................... b.Use Scroll Keys to select REMOTE. [MCB] ...................................................... c.Press "PROG" Key. ........................................................................................... d.Check 1C SAC number blinks on MCC Screen of 1A SAC PRI REG. ........ 13.Press F1 until Main Screen appears. .......................................................................... 14.Notify CONT RM 1C SAC in REMOTE. ...................................................................... 15.Place MCB H/S for 1C Air Compressor to AUTO. ....................................................... 16.Verify 1C SAC starts, loads, unloads as programmed on its Internal Mode PRESS settings. ........................................................................................................... 17. Leave 1C SAC in Remote CONT on MCB OR proceed to Section 4.6.3 to integrate 1C SAC onto SEQ. ........................................................................................ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 22 of 81 Printed 06/03/2015 at 12:48:00 4.4.2 MCB Shutdown of 1C SAC1. IF 1C SAC previously selected to MCB control, go to Step 3......................................2.Isolate 1C SAC from sequencer as follows: a.Obtain SS permission to isolate 1C SAC from sequencer. ............................... b.Notify Control Room of intent to isolate 1C SAC from sequencer. ................... c. At 1C SAC, perform the following: (1)Press F1 until Main Screen appears.......................................................(2)Press and hold Scroll Up Key to activate "Configurations Menu". ......... (3)Scroll to option 'C.C.M'. .......................................................................... (4) To modify, press F2 ('Mod'). ................................................................... (5)Use Scroll Keys to select Remote. [MCB] .............................................. (6)Press "PROG" Key. ................................................................................ (7)Check 1C SAC number blinks on MCC Screen of 1A SAC PRI REG.........................................................................................................d.Notify Control Room 1C SAC in REMOTE CONTROL. .................................... 3. On MCB, place 1C Air Compressor H/S to OFF..........................................................4.4.3 MCB Startup of 1C SAC 1. IF 1C SAC shutdown for long duration such as maintenance or tagging go to Section 4.4.1. ..................................................................................................... 2. IF 1C SAC shutdown for short duration AND no configuration changes made, place 1C Air Compressor H/S to AUTO.......................................................................3. IF desired, perform one of the following: IF 1C SAC shutdown for short duration AND no configuration changes made, go to Section 4.9.3, Re-Integration of 1C SAC to SEQ. ......................... Integrate 1C SAC on sequencer per Section 4.6.3. .......................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 23 of 81 Printed 06/03/2015 at 12:48:00 NOTES 1A SAC controller (PRI REG) acts as sequencer for SACs. ES4i functionality (also referred to as MCC, Multi COMPR CONT) an integrated feature of MKIV REG, on 1A SAC display PNL, shown as "MCC". ........................................................................................... SACs controlled are connected with each other in Local Area Network (LAN). After activating ES4i, all local start, stop functions on LCPs of SACs are disabled (except for EMERG Stop Buttons which remain active). ............................................................................... After pressing start button on 1A SAC, PRI REG will start, load, unload, stop selected SACs based on run time, PRI REG outlet PRESS input, PRESS range programmed into PRI REG. .............................................................................................................................. SACs "isolated" from MCC network, have their COMPR CONT Mode (C.C.M.) set to Local or Remote CONT (MCB) will run, load, unload,, stop based on their own internal PRESS switch (PRESS XMTR PT600A, B or C), MIN/MAX setpoints programmed into their respected LCP. .................................................................................................................... Three function Keys (F1, F2, F3) under display screen on SAC LCP used to select various functions when programming SAC. Actual function of each function Key indicated on bottom line of display screen just above relevant Function Key. Three Scroll Keys -Key called "Tabulator". ..................................................... 4.5 SEQUENCER SETUP, OPERATION4.5.1 Activating Sequencer on 1A SAC Primary Regulator1.Activate SEQ on 1A SAC PRI REG, perform the following: a.Inform SS, CRO, SEQ to be setup for operation. ............................................. b.Verify 1A SAC 'Voltage On' LED LIT. ............................................................... c.Press F1 until Main Screen appears. ................................................................ d.Press and hold Scroll Up Key to activate "Configurations Menu". ................... e.Scroll to option 'M.C.C.' .................................................................................... NOTE By default, text 'Not Activated', blinking. ............................................................................................. f.Verify text shows "Active", IF not, perform the following: ................................. g.Press F2 ('Mod') to change setting. .................................................................. h.Use Scroll Keys to change setting to "ACTIVATED". ........................................ i.Press F1 ('PROG') to save modification or F3 ("Cancel"). ................................ j.Press 1A SAC start button if needed to have PRI REG take CONT of SACs in LAN or to be placed in LAN. ................................................................ k.Press F1 until Main Screen appears. ................................................................ l.Notify CONT RM SEQ ACTIVATED. ................................................................ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 24 of 81 Printed 06/03/2015 at 12:48:00 4.5.2 Verifying Number of SACs Selected in LAN1.Verify SACs selected in LAN by performing the following: a.Notify SS, CRO, number of SACs to be selected in LAN. ................................ b.Press F1 until Main Screen appears on 1A SAC PRI REG. ............................. c.Press F1 ('Menu') from Main Screen. ................................................................ d.Use Scroll Keys, Scroll to option 'Modify Params'. ........................................... e.Press horizontal arrow key to select. [Tabulator] .............................................. f.Scroll to option 'Parameters MCC'. ................................................................... g.Press Tabulator Key to select. .......................................................................... h.Verify number 3 (or number requested by SS), shown on screen. ................... i. IF number not shown, perform the following: (1)Press F2 ('Mod') to change setting. ........................................................ (2)Use Scroll Keys to change number of SACs in LAN to 3 (or to number requested by SS). ...................................................................... (3)Press F1 ('PROG') to save selected value or F3 ("Cancel"). .................. j.Press F1 until Main Screen appears. ................................................................ k.NotifyCONT RM, number of SACs selected in LAN. ....................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 25 of 81 Printed 06/03/2015 at 12:48:00 4.5.3 Verifying Pressure Control Band 1 on SEQ 1. Verify PRESS CONT Band 1 by performing the following: a.Notify SS, CRO, PRESS CONT Band 1 on SEQ to be CHECKED. ................. b.Press F1 until Main Screen appears on 1A SAC PRI REG. ............................. c.Press F1 ('Menu') from Main Screen. ................................................................ d.Use Scroll Keys, Scroll to option 'Modify Params'. ........................................... e.Press horizontal arrow key to select. [Tabulator] .............................................. f.Scroll to option 'Parameters MCC'. ................................................................... g.Press Tabulator Key to select. .......................................................................... h.Verify 'MIN PRESS Band 1' indicates 92 PSIG. .............................................. i. IF MIN PRESS Band 1' does not indicates 92 PSIG, perform the following:(1)Verify right side SEL mark at 'MIN PRESS Band 1'. .............................. (2)Press F2 ('Mod') to change setting. ........................................................ (3)Use Scroll Keys to change PRESS to 92 PSIG. ..................................... (4)Press F1 ('PROG') to save selected value or F3 ("Cancel"). .................. j.Scroll,verify 'MAX PRESS Band 1' indicates 100 PSIG. ............................... k. IF MAX PRESS Band 1' does not indicates 100 PSIG, perform the following with SS' permission: (1)Verify right side SEL mark at 'MAX PRESS Band 1'. ............................. (2)Press F2 ('Mod') to modify. ..................................................................... (3)Use Scroll Keys to change PRESS to 100 PSIG. ................................... (4)Press F1 ('PROG') to save selected value or F3 ("Cancel"). .................. l.Press F1 until Main Screen appears. ................................................................ m. NotifyCONT RM, PRESS CONT Band 1 on SEQ verified or changed. ........... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 26 of 81 Printed 06/03/2015 at 12:48:00 NOTES SACs run hours should be zeroed on SEQ (1A SAC PRI REG) prior to integration if SAC has been S/D for long time. ................................................................................................. SEQ balances run hours when in control. ................................................................................... 4.5.4 Zeroing SAC Run Hours on SEQ1.Zero run hours on SEQ (1A SAC PRI REG),by performing the following: a.Notify SS, CRO, which SAC(s) run hours to be zeroed. .................................. b.Press F1 until Main Screen appears on 1A SAC. ............................................. c.Press F1 ('Menu') from Main Screen. ................................................................ d.Use Scroll Keys, Scroll to option 'Modify Params'. ........................................... e.Press horizontal arrow key to select. [Tabulator] .............................................. f.Scroll to option 'Parameters MCC'. ................................................................... g.Press Tabulator Key to select. .......................................................................... h.Scrollto 1A OR 1B OR 1C SAC Run Hours. .................................................... (1) For 1A SAC, perform the following: (a)Verify right side SEL mark at 1A SAC Run Hours........................(b)Press F2 ('Mod') to modify. .......................................................... (c)Scroll Run Hours to 0. [keep pushed, hours will reach 0 fast] ..... (d)Press F1 ('PROG') to save value or F3 ("Cancel"). ...................... (2) For 1B SAC, perform the following: (a)Verify right side SEL mark at 1B SAC Run Hours........................(b)Press F2 ('Mod') to modify. .......................................................... (c)Scroll Run Hours to 0. [keep pushed, hours will reach 0 fast] ..... (d)Press F1 ('PROG') to save value or F3 ("Cancel"). ...................... (3) For 1C SAC, perform the following: (a)Verify right side SEL mark at 1C SAC Run Hours. ...................... (b)Press F2 ('Mod') to modify. .......................................................... (c)Scroll Run Hours to 0. [keep pushed, hours will reach 0 fast] ..... (d)Press F1 ('PROG') to save value or F3 ("Cancel"). ...................... i.Press F1 until Main Screen appears. ................................................................ j.Notify CONT RM SACs run hours zeroed. ....................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 27 of 81 Printed 06/03/2015 at 12:48:00 4.6 INTEGRATION OF 1A OR 1B OR 1C SAC TO SEQUENCERNOTE IF 1A SAC shutdown for short duration AND no configuration changes made, go to Section 4.9.1, Re-Integration of 1A SAC to SEQ. .............................................................................. 4.6.1 Integrating 1A SAC to SEQ 1.Integrate 1A SAC to SEQ (1A SAC PRI REG), by performing the following: a.Obtain SS permission prior to integrating 1A SAC to SEQ. .............................. b.Notify CRO 1A SAC to be integrated to SEQ. ................................................. c.Verify 1A SAC setup COMPLETE. [Section 4.2.1] ........................................... d.Verify SEQ setup COMPLETE. [Section 4.5] .................................................... e.Verify 1A SAC Automatic Operation LED LIT. .................................................. f.Press F1 until Main Screen appears. ................................................................ g.Press and hold Scroll Up Key to activate "Configurations Menu". ................... h.Scroll to option 'C.C.M'. .................................................................................... i.Press Key F2 ('Mod') to change setting. ........................................................... j.Use Scroll Keys to select 'LAN Control' or F3 ('Cancel'). ................................. k.Press "PROG" Key to save or F3 ('Cancel'). ..................................................... NOTE Recommended to set 1A SAC REG Node to number 1 in configuration. .......................................... l.Verify Node ID for 1A SAC set to 1 in its "Configurations Menu" ...................... m. IF Node ID not set, perform the following: (1)Scroll to option 'Node ID'. ....................................................................... (2)Press F2 ('Mod'), use Scroll Keys to select number 1 for 1A SAC. ........ (3)Press ('PROG') Key to confirm modification. .......................................... n.Press F1 until Main Screen appears. ................................................................ o.Press F2 on 1A SAC to activate MCC Screen. ................................................. NOTE 1A SAC PRI REG will take CONT of 1A SAC. ........................................................................ p.Press "Reset" Key on MCC Screen of 1A SAC PRI REG. ......................... q.NotifyCONT RM 1A SAC integrated to SEQ. .................................................. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 28 of 81 Printed 06/03/2015 at 12:48:00 NOTE IF 1B SAC shutdown for short duration AND no configuration changes made, go to Section 4.9.2, Re-Integration of 1B SAC to SEQ. .............................................................................. 4.6.2 Integrating 1B SAC to SEQ 1.Integrate 1B SAC to SEQ (1A SAC PRI REG), by performing the following: a.Obtain SS permission prior to integrating 1B SAC to SEQ. .............................. b.Notify CRO 1B SAC to be integrated to SEQ. ................................................. c.Verify 1B SAC setup COMPLETE. [Section 4.3.1] ........................................... d.Verify SEQ setup COMPLETE. [Section 4.5] .................................................... e.Verify 1B SAC Automatic Operation LED LIT. .................................................. f.Press F1 until Main Screen appears. ................................................................ g.Press and hold Scroll Up Key to activate "Configurations Menu". ................... h.Scroll to option 'C.C.M'. .................................................................................... i.Press Key F2 ('Mod') to change setting. ........................................................... j.Use Scroll Keys to select 'LAN Control or F3 ('Cancel'). .................................. k.Press "PROG" Key to save or F3 ('Cancel'). ..................................................... NOTE Recommended to set 1B SAC REG Node to number 2 in configuration. .......................................... l.Verify Node ID for 1B SAC set to 2 in its "Configurations Menu" ...................... m. IF Node ID not set, perform the following: (1)Scroll to option 'Node ID'. ....................................................................... (2)Press F2 ('Mod'), use Scroll Keys to select number 2 for 1B SAC. ........ (3)Press ('PROG') Key to confirm modification. .......................................... n.Press F1 until Main Screen appears. ................................................................ o.Press F2 on 1A SAC to activate MCC Screen. ................................................. NOTE 1A SAC PRI REG will take CONT of 1B SAC. ........................................................................ p.Press "Reset" Key on MCC Screen of 1A SAC PRI REG. ......................... q.NotifyCONT RM 1B SAC integrated to SEQ. .................................................. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 29 of 81 Printed 06/03/2015 at 12:48:00 NOTE IF 1C SAC shutdown for short duration AND no configuration changes made, go to Section 4.9.3, Re-Integration of 1C SAC to SEQ. .............................................................................. 4.6.3 Integrating 1C SAC to SEQ 1.Integrate 1C SAC to SEQ (1A SAC PRI REG), by performing the following: a.Obtain SS permission prior to integrating 1C SAC to SEQ. .............................. b.Notify CRO 1C SAC to be integrated to SEQ. ................................................. c.Verify 1C SAC setup COMPLETE. [Section 4.4.1] ........................................... d.Verify SEQ setup COMPLETE. [Section 4.5] .................................................... e.Verify 1C SAC Automatic Operation LED LIT. .................................................. f.Press F1 until Main Screen appears. ................................................................ g.Press and hold Scroll Up Key to activate "Configurations Menu". ................... h.Scroll to option 'C.C.M'. .................................................................................... i.Press Key F2 ('Mod') to change setting. ........................................................... j.Use Scroll Keys to select 'LAN Control' or F3 ('Cancel'). ................................. k.Press "PROG" Key to save or F3 ('Cancel'). ..................................................... NOTE Recommended to set 1C SAC REG Node to number 3 in configuration. .......................................... l.Verify Node ID for 1C SAC set to 3 in its "Configurations Menu" ...................... m. IF Node ID not set, perform the following: (1)Scroll to option 'Node ID'. ....................................................................... (2)Press F2 ('Mod'), use Scroll Keys to select number 3 for 1C SAC. ........ (3)Press ('PROG') Key to confirm modification. .......................................... n.Press F1 until Main Screen appears. ................................................................ o.Press F2 on 1A SAC to activate MCC Screen. ................................................. NOTE 1A SAC PRI REG will take CONT of 1C SAC. ....................................................................... p.Press "Reset" Key on MCC Screen of 1A SAC PRI REG. ......................... q.NotifyCONT RM 1C SAC integrated to SEQ. .................................................. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 30 of 81 Printed 06/03/2015 at 12:48:00 4.7 DURING OPERATION This section for checking SAC status if warranted. NOTE PRI REG screen shows PRESS AND each SAC status. ................................................................... 1.Press F2 ('MCC') from Main Screen on 1A SAC PRI REG to activate "MCC Menu"(SEQ). ................................................................................................................ 2.Press F2 ('Reset'), if needed, to allow SEQ to re-establish communications with "LAN" connected SACs. ........................................................................................ 3.Press Scroll Down Key to show net PRESS, PRI REG regulating SACs connected to LAN. ........................................................................................................ 4.Press Scroll Up Key to return to previous screen. ....................................................... 5.Press F1 to return to Main Screen or Main Menu. Main Screen shows 1A SAC outlet PRESS AND its current status. .......................................................................... 6.Press F1 ('Main Screen') on each SACs to allow Scrolling through Menus to call up SAC Data. ......................................................................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 31 of 81 Printed 06/03/2015 at 12:48:00 CAUTION 1B AND 1C SACs must be isolated from SEQ per Section 4.8.2 AND Section 4.8.3, placed in Remote CONT (MCB) IF removing power from 1A SAC. [BKR open] ........................................... 4.8 ISOLATING 1A OR 1B OR 1C SAC FROM SEQ4.8.1 Isolating 1A SAC From SEQ1.Isolate 1A SAC from SEQ (1A SAC PRI REG) byperforming the following: a.Obtain SS permission prior to isolating 1A SAC from SEQ. ............................. b.Notify CRO 1A SAC to be isolated from SEQ. .................................................. c. IF power to be removed from 1A SAC, place 1B AND 1C SACs in Remote per Section 4.8.2 AND Section 4.8.3 FIRST. ....................................... d.Press F1 until Main Screen appears. ................................................................ e.Press and hold Scroll Up Key to activate "Configurations Menu". ................... f.Scroll to option 'C.C.M'. .................................................................................... g.Press F2 ('Mod') to modify. ............................................................................... h.Use Scroll Keys to select Remote. [MCB] ........................................................ i.Press "PROG" Key. ........................................................................................... j.Check 1A SAC number blinks on MCC screen of 1A SAC PRI REG. ......... k.Notify CONT RM 1A SAC isolated, in REMOTE. ............................................. NOTE It may be necessary to manually BLDN 1A Air RCVR per Section 4.10 to < 85 PSIG in order to watch SAC load on Internal Mode PRESS settings. SAC will S/D in 10-15 minutes if no load on SAC. ......................................................................................................................................CAUTION Procedure verifies SAC operability on Internal Mode PRESS settings; therefore, plant conditions must allow establishment of 1A RCVR PRESS < 85 PSIG...............................................l. Have CRO take 1A SAC H/S to AUTO to verify proper operation. ................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 32 of 81 Printed 06/03/2015 at 12:48:00 4.8.2 Isolating 1B SAC From SEQ1.Isolate 1B SAC from SEQ (1A SAC PRI REG) byperforming the following: a.Obtain SS permission prior to isolating 1B SAC from SEQ. ............................. b.Notify CRO 1B SAC to be isolated from SEQ. .................................................. c.Press F1 until Main Screen appears. ................................................................ d.Press and hold Scroll Up Key to activate "Configurations Menu". ................... e.Scroll to option 'C.C.M'. .................................................................................... f.Press F2 ('Mod') to modify. ............................................................................... g.Use Scroll Keys to select Remote. [MCB] ........................................................ h.Press "PROG" Key. ........................................................................................... i.Check 1B SAC number blinks on MCC screen of 1A SAC PRI REG. ......... j.Notify CONT RM 1B SAC isolated, in REMOTE. ............................................. NOTE It may be necessary to manually BLDN 1B1 AND 1B2 Air RCVRs < 90 PSIG per Section 4.10load on SAC. ......................................................................................................................................CAUTION Procedure verifies SAC operability on Internal Mode PRESS settings; therefore, plant conditions must allow establishment of 1B1 AND 1B2 Air RCVRs < 90 PSIG...................................k. Have CRO take 1B SAC H/S to AUTO to verify proper operation. ................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 33 of 81 Printed 06/03/2015 at 12:48:00 4.8.3 Isolating 1C SAC From SEQ1.Isolate 1C SAC from SEQ (1A SAC PRI REG) byperforming the following: a.Obtain SS permission prior to isolating 1C SAC from SEQ. ............................. b.Notify CRO 1C SAC to be isolated from SEQ. ................................................. c.Press F1 until Main Screen appears. ................................................................ d.Press and hold Scroll Up Key to activate "Configurations Menu". ................... e.Scroll to option 'C.C.M'. .................................................................................... f.Press F2 ('Mod') to modify. ............................................................................... g.Use Scroll Keys to select Remote. [MCB] ........................................................ h.Press "PROG" Key. ........................................................................................... i.Check 1C SAC number blinks on MCC screen of 1A SAC PRI REG. ......... j.Notify CONT RM 1C SAC isolated, in REMOTE. ............................................. NOTE It may be necessary to manually BLDN 1C Air RCVR < 87 PSIG per Section 4.10 to watch SAC ....... CAUTION Procedure verifies SAC operability on Internal Mode PRESS settings; therefore, plant conditions must allow establishment of 1C Air RCVR < 87 PSIG. ..................................................... k. Have CRO take 1C SAC H/S to AUTO to verify proper operation. ................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 34 of 81 Printed 06/03/2015 at 12:48:00 4.9 RE-INTEGRATION OF 1A OR 1B OR 1C SAC TO SEQ4.9.1 Re-Integrating 1A SAC to SEQ1.Re-integrate 1A SAC to SEQ (1A SAC PRI REG) by performing the following: a.Obtain SS permission prior to re-integrating 1A SAC to SEQ. ......................... b.Notify CRO 1A SAC to be re-integrated to SEQ. .............................................. c.Verify 1A SAC Automatic Operation LED LIT. .................................................. d.Press F1 until Main Screen appears. ................................................................ e.Press and hold Scroll Up Key to activate "Configurations Menu". ................... f.Scroll to option 'C.C.M'. .................................................................................... g.Press F2 ('Mod') to modify. ............................................................................... h.Use Scroll Keys to select 'LAN Control'. ............................................................ i.Press "PROG" Key. ........................................................................................... j.Press F1 until Main Screen appears. ................................................................ k.Press F2 ('MCC') on 1A SAC. ........................................................................... NOTE 1A SAC PRI REG will take CONT of 1A SAC. ........................................................................ l.Press "Reset" Key on MCC Screen of 1A SAC PRI REG to allow SEQ to re-establish communications with 1A SAC. .......................................... m. NotifyCONT RM 1A SAC re-integrated to SEQ. .............................................. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 35 of 81 Printed 06/03/2015 at 12:48:00 4.9.2 Re-Integrating 1B SAC to SEQ1.Re-integrate 1B SAC to SEQ (1A SAC PRI REG) by performing the following: a.Obtain SS permission prior to re-integrating 1B SAC to SEQ. ......................... b.Notify CRO 1B SAC to be re-integrated to SEQ. .............................................. c.Verify 1B SAC Automatic Operation LED LIT. .................................................. d.Press F1 until Main Screen appears. ................................................................ e.Press and hold Scroll Up Key to activate "Configurations Menu". ................... f.Scroll to option 'C.C.M'. .................................................................................... g.Press F2 ('Mod') to modify. ............................................................................... h.Use Scroll Keys to select 'LAN Control'. ............................................................ i.Press "PROG" Key. ........................................................................................... j.Press F1 until Main Screen appears. ................................................................ k.Press F2 ('MCC') on 1A SAC. ........................................................................... NOTE 1A SAC PRI REG will take CONT of 1B SAC. ........................................................................ l.Press "Reset" Key on MCC Screen of 1A SAC PRI REG to allow SEQ to re-establish communications with 1B SAC. .......................................... m. NotifyCONT RM 1B SAC re-integrated to SEQ. .............................................. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 36 of 81 Printed 06/03/2015 at 12:48:00 4.9.3 Re-Integrating 1C SAC to SEQ1.Re-integrate 1C SAC to SEQ (1A SAC PRI REG) by performing the following: a.Obtain SS permission prior to re-integrating 1C SAC to SEQ. ......................... b.Notify CRO 1C SAC to be re-integrated to SEQ. .............................................. c.Verify 1C SAC Automatic Operation LED LIT. .................................................. d.Press F1 until Main Screen appears. ................................................................ e.Press and hold Scroll Up Key to activate "Configurations Menu". ................... f.Scroll to option 'C.C.M'. .................................................................................... g.Press F2 ('Mod') to modify. ............................................................................... h.Use Scroll Keys to select 'LAN Control'. ............................................................ i.Press "PROG" Key. ........................................................................................... j.Press F1 until Main Screen appears. ................................................................ k.Press F2 ('MCC') on 1A SAC. ........................................................................... NOTE 1A SAC PRI REG will take CONT of 1C SAC. ....................................................................... l.Press "Reset" Key on MCC Screen of 1A SAC PRI REG to allow SEQ to re-establish communications with 1C SAC. .......................................... m. NotifyCONT RM 1C SAC re-integrated to SEQ. .............................................. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 37 of 81 Printed 06/03/2015 at 12:48:00 4.10 MANUAL BLOWDOWN OF TURBINE BLDG SAC AIR RECEIVERS4.10.1 Manual BLDN of 1A SAC Air RCVR 1.Perform the following for manual BLDN of 1A Air RCVR: a.Open RCVR Strainer Drain VLV N1P19V867A AND/OR RCVR AUTO Drain BYP VLV N1P19V509A. .......................................................................... b.Perform the following only IF DP needs establishing across CK VLV: (1)Close (temporarily if needed) Air RCVR Outlet VLV N1P19V501A while blowing down RCVR. ..................................................................... (2)Open Air RCVR Outlet VLV N1P19V501A when DP established across CK VLV. ....................................................................................... c. WHEN draining complete, perform the following: Close RCVR Strainer Drain VLV N1P19V867A, IF opened. .................. Close RCVR AUTO Drain BYP VLV N1P19V509A, IF opened. ............. 4.10.2 Manual BLDN of 1B SAC Air Receivers 1.Perform the following for manual BLDN of 1B1 Air RCVR: a.Open RCVR Strainer Drain VLV N1P19V867B1 AND/OR RCVR AUTO Drain BYP VLV N1P19V509B1. ........................................................................ b.Perform following only IF DP needs establishing across CK VLV: (1)Close (temporarily if needed) Air RCVR Outlet VLV N1P19V501B1 while blowing down RCVR. ............................................ (2)Open Air RCVR Outlet VLV N1P19V501B1 when DP established across CK VLV. ....................................................................................... c. WHEN draining complete, perform the following: Close RCVR Strainer Drain VLV N1P19V867B1, IF opened. ................ Close RCVR AUTO Drain BYP VLV N1P19V509B1, IF opened. ........... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 38 of 81 4.10.2 Manual BLDN of 1B SAC Air Receivers (continued) Printed 06/03/2015 at 12:48:00 2.Perform the following for manual BLDN of 1B2 Air RCVR: a.Open RCVR Strainer Drain VLV N1P19V867B2 AND/OR RCVR AUTO Drain BYP VLV N1P19V509B2. ........................................................................ b.Perform the following only IF DP needs establishing across CK VLV: (1)Close (temporarily if needed) Air RCVR Outlet VLV N1P19V501B2 while blowing down RCVR. ............................................ (2)Open Air RCVR Outlet VLV N1P19V501B2 when DP established across CK VLV. ....................................................................................... c. WHEN draining complete, perform the following: Close RCVR Strainer Drain VLV N1P19V867B2, IF opened. ................ Close RCVR AUTO Drain BYP VLV N1P19V509B2, IF opened. ........... 4.10.3 Manual BLDN of 1C SAC Air RCVR 1.Perform the following for manual BLDN of 1C Air RCVR: a.Open RCVR Strainer Drain VLV N1P19V867C AND/OR RCVR AUTO Drain BYP VLV N1P19V509C. .......................................................................... b.Perform following only IF DP needs establishing across CK VLV: (1)Close (temporarily if needed) Air RCVR Outlet VLV N1P19V501C while blowing down RCVR. .............................................. (2)Open Air RCVR Outlet VLV N1P19V501C when DP established across CK VLV. ....................................................................................... c. WHEN draining complete, perform the following: Close RCVR Strainer Drain VLV N1P19V867C, IF opened. .................. Close RCVR AUTO Drain BYP VLV N1P19V509C, IF opened. ............. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 39 of 81 Printed 06/03/2015 at 12:48:00 4.11 SUPPLYING SW FROM UNIT 2 1.Open SW Supply to Air COMPR HDR XCONN U2 To U1 N2P16V783. ..................... 2.Close SW Emergency Supply HDR ISO N1P16V932. ................................................ 3.Close SW Inlet ISO to SACs N1P16V108. .................................................................. 4.Verify proper SAC operation. ...................................................................................... 4.12 RETURNING SW SUPPLY FROM UNIT 2 TO UNIT 1 1.Open SW Inlet ISO to SACs N1P16V108. ................................................................... 2.Open SW Emergency Supply HDR ISO N1P16V932. ................................................. 3.Close SW Supply to Air COMPR HDR XCONN U2 To U1 N2P16V783. .................... 4.Verify proper SAC operation. ...................................................................................... 4.13 BYPASSING SAC SW SUPPLY SOLENOID VALVES4.13.1 Bypassing 1A SAC SW Supply Solenoid VLV N1P19G0507A 1. BYP 1A SAC SW SUPP Solenoid VLV N1P19G0507A by performing the following: a.Open 1A SAC SW Supply Solenoid BYP VLV N1P16V635A. .......................... b.Close 1A SAC SW Supply Solenoid Inlet Isolation VLV N1P16V627A. ............ c.Close 1A SAC SW Supply Solenoid Outlet Isolation VLV N1P16V639A. ......... 4.13.2 Bypassing 1B SAC SW Supply Solenoid VLV N1P19G0507B 1. BYP 1B SAC SW SUPP Solenoid VLV N1P19G0507B by performing the following: a.Open 1B SAC SW Supply Solenoid BYP VLV N1P16V635B. .......................... b.Close 1B SAC SW Supply Solenoid Inlet Isolation VLV N1P16V627B. ............ c.Close 1B SAC SW Supply Solenoid Outlet Isolation VLV N1P16V639B. ......... 4.13.3 Bypassing 1C SAC SW Supply Solenoid VLV N1P19G0507C 1. BYP 1C SAC SW SUPP Solenoid VLV N1P19G0507C by performing the following: a.Open 1C SAC SW Supply Solenoid BYP VLV N1P16V635C. .......................... b.Close 1C SAC SW Supply Solenoid Inlet Isolation VLV N1P16V627C. ........... c.Close 1C SAC SW Supply Solenoid Outlet Isolation VLV N1P16V639C. ........ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 40 of 81 Printed 06/03/2015 at 12:48:00 4.14 RETURN TO SERVICE: SAC SW SUPPLY SOLENOID VALVES4.14.1 RTS 1A SAC SW Supply Solenoid VLV N1P19G0507A 1. RTS 1A SAC SW SUPP Solenoid VLV N1P19G0507A by performing the following: a.Open 1A SAC SW Supply Solenoid Outlet Isolation VLV N1P16V639A. ......... b.Open 1A SAC SW Supply Solenoid Inlet Isolation VLV N1P16V627A. ............ c.Close 1A SAC SW Supply Solenoid BYP VLV N1P16V635A. .......................... 4.14.2 RTS 1B SAC SW Supply Solenoid VLV N1P19G0507B 1. RTS 1B SAC SW SUPP Solenoid VLV N1P19G0507B by performing the following: a.Open 1B SAC SW Supply Solenoid Outlet Isolation VLV N1P16V639B. ......... b.Open 1B SAC SW Supply Solenoid Inlet Isolation VLV N1P16V627B. ............ c.Close 1B SAC SW Supply Solenoid BYP VLV N1P16V635B. .......................... 4.14.3 RTS 1C SAC SW Supply Solenoid VLV N1P19G0507C 1. RTS 1C SAC SW SUPP Solenoid VLV N1P19G0507C by performing the following: a.Open 1C SAC SW Supply Solenoid Outlet Isolation VLV N1P16V639C. ......... b.Open 1C SAC SW Supply Solenoid Inlet Isolation VLV N1P16V627C. ............ c.Close 1C SAC SW Supply Solenoid BYP VLV N1P16V635C. ......................... 4.15 PURGE FLOW SETUP FOR TURB BLDG IA DRYER DEWPOINT MONITOR 1.Open IA To Dewpoint Sensor ME-569 ROOT N1P19V564. ........................................ 2.Open IA To Dewpoint Sensor ISO N1P19V1076.........................................................3.Adjust Flow IND/CONT FOR Dewpoint Sensor ME-569 N1P19FIC0569 to obtain 4-7 SCFH. (> 5 SCFH recommended flow). ...................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 41 of 81 Printed 06/03/2015 at 12:48:00 4.16 RESETTING SAC SERVICE PLAN WARNING ALARMSNOTE If service message shown, inform SSS, record message in CR, reset service message............ When service plan interval reached, a message will appear on the screen. After MAINT carries out service actions related to the indicated levels, MAINT resets timers associated with Service Plan. [U418371] .................................................................................... 4.16.1 Resetting 1A SAC Service Plan Warning Alarms1. On 1A SAC CONT PNL, perform the following: a.Press F1 until Main Screen appears. ................................................................ b.Press F1 to bring up Main Menu Screen. .......................................................... NOTE "Service will be blinking in "Status Data Menu". ................................................................................. c.Press Scroll Down Key until "Status Data" followed by horizontal arrow. [Tabulator Key] .................................................................................................. d.Press Tabulator Key to activate Menu. ............................................................. e.Press Scroll Down Key until "Service" followed by horizontal arrow. ................ f.Press Tabulator Key to activate Menu. ............................................................. g.Scroll to blinking option. .................................................................................... h.Press Tabulator Key to activate. ....................................................................... i.Press "Reset" Key. ........................................................................... j.Press "Yes" Key. ............................................................................................... k.Verify "Service Message" clears. ...................................................................... l.Press F1 until Main Screen appears. ................................................................ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 42 of 81 Printed 06/03/2015 at 12:48:00 NOTE If service message shown, inform SSS, record message in CR, reset service message............ When service plan interval reached, a message will appear on the screen. After MAINT carries out service actions related to the indicated levels, MAINT resets timers associated with Service Plan. [U418371] .................................................................................... 4.16.2 Resetting 1B SAC Service Plan Warning Alarms1. On 1B SAC CONT PNL, perform the following: a.Press F1 until Main Screen appears. ................................................................ b.Press F1 to bring up Main Menu Screen. .......................................................... NOTE "Service will be blinking in "Status Data Menu". ................................................................................. c.Press Scroll Down Key until "Status Data" followed by horizontal arrow. [Tabulator Key] .................................................................................................. d.Press Tabulator Key to activate Menu. ............................................................. e.Press Scroll Down Key until "Service" followed by horizontal arrow. ................ f.Press Tabulator Key to activate Menu. ............................................................. g.Scroll to blinking option. .................................................................................... h.Press Tabulator Key to activate. ....................................................................... i.Press "Reset" Key. ........................................................................... j.Press "Yes" Key. ............................................................................................... k.Verify "Service Message" clears. ...................................................................... l.Press F1 until Main Screen appears. ................................................................ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 43 of 81 Printed 06/03/2015 at 12:48:00 NOTE If service message shown, inform SSS, record message in CR, reset service message............ When service plan interval reached, a message will appear on the screen. After MAINT carries out service actions related to the indicated levels, MAINT resets timers associated with Service Plan. [U418371] .................................................................................... 4.16.3 Resetting 1C SAC Service Plan Warning Alarms1. On 1C SAC CONT PNL, perform the following: a.Press F1 until Main Screen appears. ................................................................ b.Press F1 to bring up Main Menu Screen. .......................................................... NOTE "Service will be blinking in "Status Data Menu". ................................................................................. c.Press Scroll Down Key until "Status Data" followed by horizontal arrow. [Tabulator Key] .................................................................................................. d.Press Tabulator Key to activate Menu. ............................................................. e.Press Scroll Down Key until "Service" followed by horizontal arrow. ................ f.Press Tabulator Key to activate Menu. ............................................................. g.Scroll to blinking option. .................................................................................... h.Press Tabulator Key to activate. ....................................................................... i.Press "Reset" Key. ........................................................................... j.Press "Yes" Key. ............................................................................................... k.Verify "Service Message" clears. ...................................................................... l.Press F1 until Main Screen appears. ................................................................ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 44 of 81 Printed 06/03/2015 at 12:48:00

5.0 REFERENCES

1. P&IDs, Elementary a. A-170059 - (sh. 5, 6, 171-174 & 179), Controlled Air Diagrams b. D-170061 - Air to ES & MSR DRN SYS' Check VLVs (PCCVs) c. D-170119 - (sh. 5), SW in TURB BLDG (SUPP to A/C's) d. D-170131 - Compressed Air SYS e. D-170133 - SA SYS f. D-170473 - (sh. 1); Essential IA to CONT VLVs (IA in TURB BLDG) g. D-170473 - (sh. 2 - 4); Essential CONT Air (IA in TURB BLDG) h. D-170473 - (sh. 5); CONT Air SYS (IA outside TURB BLDG) i. D-170950 - SW DISCH from Unit 1 & 2 A/C's to plant yard DRN j. D-172746 - Station Service Air Compressors k. D-175034 - (sh. 1-3), IA SYS (AUX BLDG) l. D-175035 - (sh. 1), SA SYS (AUX BLDG, CTMT) 2. Manuals a. FSAR - Chapter 9, Section 3.1 b. FSD - A-181012, IA SYS c. U-418371, SAC Instruction Book 1/2P19C0001A,B(C Unit 1) d. U-418762, Air Dryer - Installation Operation Maintenance Manual e. U-423686, SAC Motor Tech Manual f. U-423687, Hankison Automatic Condensate Drain Trap Instruction Manual COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 45 of 81

5.0 REFERENCES

(continued) Printed 06/03/2015 at 12:48:00 3. Design Changes a. PCN 841-2989 b. PCN S78-1-273 c. PCN S84-1-2914 d. PCN S89-1-5950 e. DCP B88-1-4773 f. DCP S91-2-7267, SAC replacement g. DCP S95-1-8887 h. DCP S00-1-9570, Atlas Copco SAC Modifications to Eliminate Nuisance Alarms/Trips6.0 RECORDS NOTE Performance of this procedure shall be captured in eSOMS narrative logs. NO documents created by this procedure required for retention, unless otherwise stated or determined for business needs (ex: Human Performance Review Board (HURB), flawed release, or other equipment malfunctions). ................................................................................................................... QA Record (X) Non-QA Record (X) Record Generated Retention Time R-Type NA X NA NA H06.051 COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 46 of 81 Printed 06/03/2015 at 12:48:00 FIGURE 1 Page 1 of 1 MK-IV REG CONT PNL Reference Designation Function 1 Start Button Button to start SAC. LED (# 8) lights up indicating Elektronikon regulator operative. 2 Display Shows messages about SAC operating condition, service need, or fault. 3 Scroll Keys Keys to Scroll upwards or downwards through display.4 Tabulator Key Key to select parameter indicated by horizontal arrow. Only parameters followed by an arrow pointing to right can be modified. 5 Function Keys Keys to control, program SAC. 6 Voltage on LED Indicates voltage switched on. 7 General Alarm LED Lit if S/D warning condition exists. 7 General Alarm LED Flashes if S/D condition exists, if important sensor out of order, or after emergency stop. 8 Automatic Operation LED Indicates REG automatically controlling SAC. 9 Stop Button Button to stop SAC. LED (# 8) goes out. S2 Emergency Stop Button Push button to stop SAC immediately in event of emergency. After remedying trouble, unlock button by turning to left.

COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 47 of 81 Printed 06/03/2015 at 12:48:00 FIGURE 2 Page 1 of 1 MK-IV REG FUNCTIONS 1. Manually load/unload SAC. 2. Call up or go to program settings. 3. Reset a motor overload, S/D or SERV message or EMERG stop.

4. Access data collected by REG.

5. Functions of Keys vary depending on display Menu. Actual function indicated just above relevant Key. Most common functions listed below: DESIGNATION FUNCTION "Add" To add SAC start/stop commands (day/hour). "Back" To return to previously shown option or Menu. "Cancel" To cancel programmed setting when programming parameters. "Delete" To delete SAC start/stop commands. "Help" To find Atlas Copco internet address. "Limits" To show limits for programmable setting. "Load" To load SAC manually. "Main screen" To return from a Menu to Main Screen. "Menu" Starting from Main Screen, to have access to submenus. "Menu" Starting from submenu, to return to previous Menu. "Modify" To modify programmable settings. "Program" To program modified settings. "Reset" To reset timer or message. "Return" To return to previously shown option or Menu. "Unload" To unload SAC manually. "Extra" To find module configuration of REG.

COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 48 of 81 Printed 06/03/2015 at 12:48:00 FIGURE 3 Page 1 of 1 MK-IV REG CONT PROGRAMS MAIN MENU PROGRAM FUNCTION Main Screen Shows in short, operation status of SAC. Gateway to all functions. Automatically shown when voltage switched on. "Status Data" Calls up status of SAC protection functions (S/D, S/D warning, service warning, warning). Resets S/D, motor overload, service condition. "Measured Data" Calls up data currently measured, status of number of inputs. "Counters" Calls up run hours, REG (module) hours, number of motor starts. "Test" Display test. "Modify Parameters" Modifies settings for: parameters (e.g. loading, unloading pressures), protections (e.g. temperature S/D level), service plans (timers for service plans), clock functions (automatic SAC start/stop/pressure band commands), configuration (time, date, display, language). "Service"Calls up service plans, resets timers after carrying out service actions belonging to plan. "Saved Data" Calls up saved data: last S/D, last emergency stop. See U-418371, SAC Instruction Book page 52 for flow chart. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 49 of 81 Printed 06/03/2015 at 12:48:00 FIGURE 4 Page 1 of 1 MK-IV PRI REG: SAC STATUS 1. When switching on voltage (or if no Key pressed during 4 minutes), Main Screen will be shown on 1A SAC PRI REG.2.Press F2 to show MCC Screen.3.If one of SACs not reacting on command from PRI REG, "Reset" will be shown on MCC Screen.4."Reset" used to reset communication between PRI REG, other two Secondary Regulators.Related SAC runs loaded.Related SAC runs unloaded.Related SAC stopped.Related SAC S/D.!!Related SAC not reacting on command from PRI REG.??No communication between PRI REG, related Secondary REG.XXRelated SAC not recognized. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 50 of 81 Printed 06/03/2015 at 12:48:00 FIGURE 5 Page 1 of 1 MK-IV REG: CALLING UP MENUS 1. Main Screen shown automatically when voltage switched on. 2.Press F1 ("Menu") to show Sub-Menus. 3.Using up or down Scroll Keys, Scroll until desired Sub-Menu (Status Data, Measured Data, Counters, Test, Modify Parameters , Service or Saved Data) followed by horizontal arrow (Tabulator).4.Press Tabulator Key to select desired Sub-Menu. 5.Scroll Down Key used for quick look at SAC status. 6.Scroll to any option shown in Sub-Menu selected to view contents, press Tabulator Key. 7.Press appropriate Function Key (F2 or F3) if changes to be made. 8.Press F1 when finished to return to Main Screen or Main Menu. 9.Press Scroll Up Key for 3 seconds to go directly to "Configuration Menu" if desired. 10. IF function or arrow Keys not used for around 3 minutes, REG will automatically return to Main Screen. ................................................................................................................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 51 of 81 Printed 06/03/2015 at 12:48:00 FIGURE 6 Page 1 of 1 MK-IV REG: STATUS DATA MENU 1. Starting from Main Screen. 2.Press F1 ("Menu"): option "Status Data" followed by horizontal arrow (Tabulator). 3.Press Tabulator Key. 4. IF no abnormal message exists, General Alarm LED not lit; message on display will indicate "all conditions normal". 5. IF S/D message exists (in case SAC S/D), General Alarm LED will blink. Indicators (***) blinking. Screen shows actual reading, S/D setting. Remains possible to Scroll through other menus, to check values of other parameters. When returning to "Status Data" Menu, option "Shutdowns" will blink. This option selected by pressing Tabulator Key to return to selected S/D screen. 6. For S/D reset: Switch off SAC voltage (open BKR with LCC LCP switch), remedy trouble. After remedying, when S/D condition has disappeared, switch on voltage, press "Reset" (F3) Key. Press "Menu", "Main Screen" Keys to return to Main Screen, restart SAC by pressing start button if in Local or MCB H/S if in Remote CONT. If in LAN CONT, pressReset Key on 1A SAC REG. 7. For S/D warning message: S/D warning level, programmable level below S/D level. IF S/D warning exists, General Alarm LED lit. Main Screen will change into screen showing "Shutdown Warning" (F2). Press "Menu" (F1) Key, Tabulator Key to select "Status Data" Menu. Option "Protection" blinking. Scroll to this option, select it by pressing Tabulator Key. Screen indicates parameter exceeds programmed S/D warning level. Warning message will disappear automatically as warning condition disappears. IF necessary, place SAC in Local, stop it by means of stop button, wait until it has stopped. Switch offvoltage (open BKR with LCC LCP switch), inspect, remedy. After remediation completed, switch on voltage, if needed, press "Menu", "Main Screen" Keys to return to Main Screen. Restart SAC by pressing start button or place SAC in LAN CONT, Press Reset Key on 1A SAC REG. ..................................................................................................................................8. If service message shown, record service message in CR, then reset service message. ............... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 52 of 81 Printed 06/03/2015 at 12:48:00 FIGURE 7 Page 1 of 1 MK-IV REG: MEASURE DATA, PROG CONT MODES, SAVED DATA MENUS MK-IV REG: MEASURE DATA MENU 1.Press F1 ('Menu') starting from Main Screen. 2.Press Scroll Down Key until "Measured Data" followed by horizontal arrow (Tabulator). 3.Press Tabulator Key to activate Menu. 4. By pressing Scroll Keys, a number of actually measured data can be found. 5. IF one of sensors linked to S/D, service or warning function, THEN both actually measured value as well as corresponding S/D, warning or service level can be called up by pressingTabulator Key. 6.Press F1 to return to Main Menu or Main Screen. MK-IV REG: PROGRAMMING SAC CONT MODES 1.Press F1 ("Menu") starting from Main Screen. 2.Press Scroll Down Key until "Modify Parameters" followed by arrow pointing to right (Tabulator). 3.Press Tabulator Key to activate Menu. 4.Scroll until "Configuration" followed by horizontal arrow. 5.Press Tabulator Key to activate Menu. 6.Scroll through display until option "C.C.M." indicated. 7. Press "Mod" Key. 8. "Local Control" blinking, use Scroll Keys to select desired control mode. 9.Press "Program" Key (F1) to program new control mode or "Cancel" Key (F3) to quit without reprogramming.10.Press F1 to return to Main Menu or Main Screen. MK-IV REG: SAVED DATA MENU 1.Press F1 ("Menu") starting from Main Screen. 2.Press Scroll Down Key until "Saved Data" followed by horizontal arrow.(Tabulator). 3.Press Tabulator Key to activate Menu. 4.Scroll through items, press Tabulator Key on item chosen to find out data reflecting status of SAC. 5.Scroll, If desired, through other items. 6.PressF1 to return to Main Menu or Main Screen............................................................................ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 53 of 81 Printed 06/03/2015 at 12:48:00 ATTACHMENT 1 Page 1 of 4 ALIGNING ALTERNATE AIR SUPPLY TO CTMT(Retain for QA Record) Completed by: Signature Print Name Initials Date Reviewed by: Signature Print Name Initials Date COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 54 of 81 UATTACHMENT 1 Page 2 of 4 ALIGNING ALTERNATE AIR SUPPLY TO CTMT (Retain for QA Record) Printed 06/03/2015 at 12:48:00 1.0 PURPOSEProvide instructions for aligning BKUP IA to PORVs, to Supply IA to CTMT Purge Dampers, Breathing Air Isolation & Containment Sump Discharge VLVs in Mode 5 or 6. ..... 2.0 INITIAL CONDITIONS Version of procedure verified current. .......................................................................... Procedure verified correct unit for task......................................................................... Administrative LCO for Mode 4 written for completion of Attachment. ......................... 3.0 PRECAUTIONS, LIMITATIONS1. Valves manipulated during course of Attachment will be included on applicable Operations tag out or approved checklist. This will ensure proper valve positioning when test completed. ................................................................................. 2. Notify HP if conditions warrant it. ................................................................................. 3. Exercise caution if climbing. ......................................................................................... 4. Exercise caution when venting pressure off air hose when disconnecting. ................. 5. Ensure air hose secured to connections before opening valves. ................................. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 55 of 81 UATTACHMENT 1 Page 3 of 4 ALIGNING ALTERNATE AIR SUPPLY TO CTMT (Retain for QA Record) Printed 06/03/2015 at 12:48:00 4.0 INSTRUCTIONS4.1 ALIGNING ALTERNATE AIR SUPPLY TO CTMT 1.Route hose, connect with tee from IA to PORVs HDR Test Connection, N1P19V130 (121' CTMT PENE 97B), connect to IA Drain, N1P19V975B (105' CTMT under 1A ACCUM) & IA Drain, N1P19V975C (105' CTMT NW quadrant). ... ______ ..................................................................................................................................InitialCAUTION Notify HP temporary loss of breathing air, CTMTPurge, may occur while air supplies shifted..........2.Open BKUP IA to PORV`s HDR Test CONN, N1P19V130, verify no air leaks on hoses, fittings. .............................................................................................................................................______3.Open IA Drain, N1P19V975B. ................................................................................. ______4.Open IA DRN, N1P19V975C. .................................................................................. ______5.Align BKUP Air to CTMT. [FNP-1-SOP-62.1, BKUP Air or N2 SUPP to PORVs] ... ______6.Close IA HDR ISO VLV N1P19V011. [129' CTMT near 1A ACCUM] ..................... ______7.Close IA HDR ISO N1P19V094. [105' CTMT near sump SUCT behind elevator] ... ______8.Verify CTMTPurge Dampers HV3196, HV3197 OPEN. ......................................... ______9.Verify Breathing Air VLV HV2935C OPEN. ............................................................. ______NOTE Section 4.2 to be performed when normal IA to CTMT returned to service. ...................................... 4.2 RESTORING NORMAL IA TO CTMT PURGE DAMPERS, BREATHING AIR, CTMT SUMP DISCH VALVES1.Verify IA To CTMT, Q1P19HV3611 OPEN. [BOP] .................................................. ______2.Verify IA TO CTMT HDR ISO, N1P19V009 OPEN. [105' CTMT PENE 48] ............ ______3.Open IA HDR Isolation, N1P19V094. ...................................................................... ______4.Open IA HDR Isolation, VLV N1P19V011. .............................................................. ______5.Close IA Drain, N1P19V975B. ................................................................................. ______6.Close IA Drain VLV N1P19V975C. .......................................................................... ______7.Verify CTMTPurge Dampers HV3196, HV3197 OPEN. .......................................................... ______8.Close BKUP IA to PORV Test Connection, N1P19V130.........................................______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 56 of 81 UATTACHMENT 1 Page 4 of 4 ALIGNING ALTERNATE AIR SUPPLY TO CTMT (Retain for QA Record) 4.2 RESTORING NORMAL IA TO CTMT PURGE DAMPERS, BREATHING AIR, CTMT SUMP DISCH VALVES (continued) Printed 06/03/2015 at 12:48:00 9.Remove hoses attached in Step 1 above, cap lines. .............................................. ______10.Secure BKUP Air to CTMT. [FNP-1-SOP-62.1, BKUP Air or N2 SUPP to PORVs] .................................................................................................................... ______11. Independently Verify the following OPEN: IA To CTMT, Q1P19HV3611. [BOP] ............................................................. ______ CTMTPurge Dampers HV3196, HV3197. IA TO CTMT HDR ISO, N1P19V009. [105' CTMT PENE 48]........................______ IA HDR Isolation, N1P19V094. ...................................................................... ______ IA HDR Isolation, VLV N1P19V011. .............................................................. ______12. Independently Verify the following valves CLOSED: IA Drain VLV N1P19V975B. .......................................................................... ______ IA Drain VLV N1P19V975C. .......................................................................... ______ BKUP IA to PORV Test Connection N1P19V130. ......................................... ______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 57 of 81 Printed 06/03/2015 at 12:48:00 ATTACHMENT 2 Page 1 of 3 2C SAC OPERATION ON UNIT ONE Completed by: Signature Print Name Initials Date Reviewed by: Signature Print Name Initials Date COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 58 of 81 UATTACHMENT 2 Page 2 of 3 2C SAC OPERATION ON UNIT ONE Printed 06/03/2015 at 12:48:00 1.0 PURPOSE Placing 2C SAC on service to supply Unit SA, IA. ....................................................... 2.0 INITIAL CONDITIONS Version of procedure verified current. .......................................................................... Procedure verified correct unit for task.........................................................................3.0 PRECAUTIONS, LIMITATIONS2C SAC must be in Local or Remote Control prior to XCONN with Unit 1. ............................ 4.0 INSTRUCTIONS4.1 ALIGNING 2C SAC TO UNIT 1 NOTE The following step only required if 2C SAC controlled by SEQ. ......................................................... 1.Isolate 2C SAC from the sequencer, place in Remote by performing FNP-2-SOP-31, Compressed Air SYS, Sect 4.8. ................................................................ ______2.HaveUnit 2 CRO verify 2C SAC not running. .......................................................... ______3.HaveUnit 2 CRO verify Unit 2 SACs loading properly, maintaining Unit 2 IA - 100 PSIG. ......................................................................................... ______CAUTION To prevent jeopardizing Unit 2 operation, DO NOT proceed unless sufficient SACs in service to supply Unit 2 demand without relying on 2C SAC to maintain air PRESS. ....................... 4.Close 2C SAC to Unit 2 Air HDR Isolation, N2P19V561. ........................................ ______5.Open Unit 1 to 2 Compressed Air XCONN, N1P19V560.........................................______6.Have Unit 2 CRO start 2C SAC. .............................................................................. ______7.Verify 2C SAC Local PNL Automatic Operation LED LIT. [green]...........................______8.Direct Unit 1 CRO to monitor Unit 1 Air HDR PRESS while 2C SAC aligned to Unit 1. ....................................................................................................................... ______9. Locally monitor 2C SAC operation. ......................................................................... ______10.Place Caution Tag on 2C SAC MCB H/S stating 2C SAC aligned to Unit 1. ........... ______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 59 of 81 UATTACHMENT 2 Page 3 of 3 2C SAC OPERATION ON UNIT ONE Printed 06/03/2015 at 12:48:00 4.2 RETURNING 2C SAC TO NORMAL (UNIT 2) OPERATION: 1.Verify 1A, 1B or 1C SAC running. ........................................................................... ______2. IF sufficient SACs running, have Unit 2 CRO stop 2C SAC....................................______3. IF remaining SACs cannot maintain Unit 1 IA PRESS, haveUnit 2 CRO start2C SAC. ................................................................................................................... ______4.Verify Unit 2 SACs loading properly, maintaining Unit 2 IA PRESS 90 - 100 PSIG. ........................................................................................................................ ______CAUTION To prevent jeopardizing Unit 1 operation, DO NOT proceed unless sufficient SACs in service to supply Unit 1 demand without relying on 2C SAC to maintain air PRESS. ....................... 5.Close Unit 1 to 2 Compressed Air XCONN, N1P19V560. ....................................... ______6.Open 2C SAC to Unit 2 Air HDR Isolation, N2P19V561. ......................................... ______7.Notify Unit 2 CRO 2C SAC returned to Unit 2. ........................................................ ______8.Re-integrate 2C SAC to sequencer (if warranted) by performing FNP-2-SOP-31, Compressed Air SYS, Sect 4.9. ..................................................... ______9.Remove caution tag previously placed on 2C SAC MCB H/S. ................................ ______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 60 of 81 Printed 06/03/2015 at 12:48:00 ATTACHMENT 3 Page 1 of 11 INSTRUMENT AIR DRYER OPERATION(Retain for QA Record) Completed by: Group Signature Print Name Initials Date Reviewed by (OPS): Signature Print Name Initials Date COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 61 of 81 UATTACHMENT 3 Page 2 of 11 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) Printed 06/03/2015 at 12:48:00 1.0 PURPOSE Guidance for placing, removing, bypassing Unit 1 IA Dryers. ...................................... 2.0 INITIAL CONDITIONS Version of procedure verified current. .......................................................................... Procedure verified correct unit for task.........................................................................3.0 PRECAUTIONS, LIMITATIONS1. Flow through on-service chamber never halted for any warning or alarm condition. ... 2. IF warning light or alarm light lit on ADC Controller, write CR identifying which light lit. .......................................................................................................................... 3. Loss of IA at power may result in Turbine or Reactor Trip. .......................................... COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 62 of 81 UATTACHMENT 3 Page 3 of 11 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) Printed 06/03/2015 at 12:48:00 NOTE Purge frequency of IA dryers dependent on regeneration demands, not on cyclic timer. .................. 4.0 INSTRUCTIONS4.1 PLACING 1A AIR DRYER IN SERVICE1.Verify breaker N1R19L504-N-BKR13, Air Dryer 1A Regeneration Controller, N1P19G506A-N OPEN. [120/208V DIST PNL 1J, TURB BLDG 155', West of 1B SGFP] ................................................................................................................. ______2.Verify the following valves CLOSED: N1P19V505A, 1A Air Dryer Inlet ISO. ........................................................... ______ N1P19V506A, 1A Air Dryer Outlet ISO. ......................................................... ______ N1P19V1080P, 1A IA Dryer Solenoid Air Supply ISO. .................................. ______ N1P19V1080R, 1A IA Dryer Pilot Gas Filter Bleed ISO. ............................... ______ N1P19V1080Q, 1A IA Dryer Moisture Indicator ISO. .................................... ______3.Close N1P19V1081H, 1A IA Dryer Inlet Filter Drain Bleed ISO. ............................. ______4.Close N1P19V1082G, 1A IA Dryer Outlet Filter Drain ISO. .................................... ______5.Open N1P19V1081C, 1A IA Dryer Inlet FLTR ISO..................................................______6.Open N1P19V1082C, 1A IA Dryer Outlet FLTR ISO. .............................................. ______7.Open N1P19V1080P, 1A IA Dryer Solenoid Air Supply ISO. .................................. ______8.Slowly open 1A Air Dryer Inlet ISO, N1P19V505A to supply PRESS. ................... ______9.Open N1P19V1080Q, 1A IA Dryer Moisture Indicator ISO......................................______NOTE Step 10 easier to perform with two people, one manipulating N1P19V506A, one observing N1P19PI558. ......................................................................................................................................CAUTION Verify 1A IA Dryer (F001A) Outlet PRESS IND N1P19PI558, does not exceed 15 PSIG drop in PRESS while pressurizing downstream piping. ..................................................................... 10.Slowlyopen N1P19V506A, 1A Air Dryer Outlet ISO, while monitoring N1P19PI558 to ensure air dryer outlet PRESS does not exceed 15 PSIG drop in PRESS while pressurizing downstream piping.....................................................______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 63 of 81 UATTACHMENT 3 Page 4 of 11 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) 4.1 PLACING 1A AIR DRYER IN SERVICE (continued) Printed 06/03/2015 at 12:48:00 NOTE Step 11 initialed after checking PRESS in Step 12 because 21 31 PSIG requirement in Step 12 will only be displayed for three (3) minutes (during Regeneration Mode) on N1P19FI565, then SYS PRESS will be displayed. ............................................................................. 11.Close breaker N1R19L504-N-BKR13, Air Dryer 1A Regeneration Controller, N1P19G506A-N. [120/208V DIST PNL 1J, TURB BLDG 155', West of 1B SGFP] ...................................................................................................................... ______NOTES Purge PRESS can only be read, adjusted, when off-stream chamber depressurized for regeneration. When off-stream chamber pressurized, Purge PRESS Indicator reads SYS PRESS. (Ref. U418762) ...................................................................................................... I&C assistance will be needed for the following step IF adjustments to be made. ...................... 12. IF PRESS on N1P19FI565, Purge Flow Indicator for IA Dryer N1P19F001A, not 21 31 PSIG during Regeneration Mode, perform the following: a.Slowly rotate Dryer Purge Throttle VLV, N1P19V1088E, until purge PRESS reads 21 - 31 PSIG. Throttle VLV located 5 inches behind Purge PRESS Indicator, N1P19FI565 between 2 chambers. Requires screwdriver or similar device to make adjustment. ....................................... ______ .................................................................................................................... I&C Initial 13.Notify CONT RM 1A Air Dryer in service.................................................................______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 64 of 81 UATTACHMENT 3 Page 5 of 11 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) Printed 06/03/2015 at 12:48:00 4.2 REMOVING 1A AIR DRYER FROM SERVICENOTES Dryer S/D after Step 4, may be left pressurized during periods of non-use if desired; however, leaving air dryer pressurized NOT DESIRED if maintenance or servicing to be performed. ................................................................................................................................... IF maintenance or servicing to be performed, complete all steps in this section to depressurize air dryer before beginning work. ............................................................................. CAUTION Verify 1B Air Dryer in service prior to removing 1A Air Dryer from service. ...................................... 1.Open breaker N1R19L504-N-BKR13, Air Dryer 1A Regeneration Controller, N1P19G506A-N. [120/208V DIST PNL 1J, TURB BLDG 155', West of 1B SGFP] ...................................................................................................................... ______CAUTION Inlet, outlet isolation valves must be closed to prevent moisture overloading of desiccant beds due to continuous flow without regeneration. ............................................................................ 2.Close N1P19V506A, 1A Air Dryer Outlet ISO. ........................................................ ______3.Close N1P19V505A, 1A Air Dryer Inlet ISO. ........................................................... ______4.Close N1P19V1080Q, 1A IA Dryer Moisture Indicator ISO. .................................... ______NOTES Continue with Steps 5 through 10 to depressurize air dryer through Purge Exhaust Muffler. ..... IF maintenance or servicing to be performed on air dryer, verify air dryer depressurized. .......... 5.Close N1P19V1080P, 1A IA Dryer Solenoid Air Supply ISO...................................______6.Open N1P19V1080R, 1A IA Dryer Pilot Gas Filter Bleed ISO.................................______7.Verify PRESS indicates zero (0) PSIG on the following indicators after reasonable amount of time: N1P19PI557, 1A IA Dryer, (F001A) Inlet Air PI. ............................................ ______ N1P19PI561, 1A IA Dryer (F001A) Left Chamber PI. .................................... ______ N1P19PI562, 1A IA Dryer (F001A) Right Chamber PI. ................................. ______ N1P19PI558, 1A IA Dryer (F001A) Outlet PI. ................................................ ______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 65 of 81 UATTACHMENT 3 Page 6 of 11 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) 4.2 REMOVING 1A AIR DRYER FROM SERVICE (continued) Printed 06/03/2015 at 12:48:00 8. IF PRESS on Step 7 listed PIs does NOT indicate zero (0) PSIG after reasonable amount of time, open N1P19V1080Q, 1A IA Dryer Moisture Indicator ISO. ........................................................................................................... ______9. WHEN PRESS indicates zero (0) on PIs listed in Step 7, perform the following: a.Close N1P19V1081C, 1A IA Dryer Inlet FLTR ISO. ..................................... ______b.Close N1P19V1082C, 1A IA Dryer Outlet FLTR ISO. ................................... ______c.Open N1P19V1081H, 1A IA Dryer Inlet Filter Drain Bleed ISO. ................... ______d.Open N1P19V1082G, 1A IA Dryer Outlet Filter Drain ISO............................______10. WHEN PRESS indicates zero (0) on PIs listed in Step 7, notify CONT RM, 1A Air Dryer removed from service, depressurized. ...................................................... ______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 66 of 81 UATTACHMENT 3 Page 7 of 11 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) Printed 06/03/2015 at 12:48:00 4.3 PLACING 1B AIR DRYER IN SERVICE 1.Verify breaker N1R19L504-N-BKR10, Air Dryer 1B Regeneration Controller, N1P19G506B-N OPEN. [120/208V DIST PNL 1J, TURB BLDG 155', West of 1B SGFP] ................................................................................................................. ______2.Verify the following valves CLOSED: N1P19V505B, 1B Air Dryer Inlet ISO. ........................................................... ______ N1P19V506B, 1B Air Dryer Outlet ISO. ......................................................... ______ N1P19V1083P, 1B IA Dryer Solenoid Air Supply ISO. .................................. ______ N1P19V1083R, 1B IA Dryer Pilot Gas Filter Bleed ISO. ............................... ______ N1P19V1083Q, 1B IA Dryer Moisture Indicator ISO. .................................... ______3.Close N1P19V1084H, 1B IA Dryer Inlet Filter Drain Bleed ISO. ............................. ______4.Close N1P19V1085G, 1B IA Dryer Outlet Filter Drain ISO. .................................... ______5.Open N1P19V1084C, 1B IA Dryer Inlet FLTR ISO..................................................______6.Open N1P19V1085C, 1B IA Dryer Outlet FLTR ISO. .............................................. ______7.Open N1P19V1083P, 1B IA Dryer Solenoid Air Supply ISO VLV. .......................... ______8.Slowly open 1B Air Dryer Inlet ISO N1P19V505B to supply PRESS. .................... ______9.Open N1P19V1083Q, 1B IA Air Dryer Moisture Indicator ISO. ............................... ______NOTE Step 10 easier to perform with two people, one manipulating N1P19V506B, one observing N1P19PI560. ......................................................................................................................................CAUTION Ensure 1B Instrument Air Dryer (F001B) Outlet PRESS IND N1P19PI560 does not exceed a 15 PSIG drop in PRESS while pressurizing downstream piping. .................................................... 10.Slowlyopen N1P19V506B, 1B Air Dryer Outlet ISO, while monitoring N1P19PI560 to ensure Air Dryer outlet PRESS does not exceed 15 PSIG drop in PRESS while pressurizing downstream piping.....................................................______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 67 of 81 UATTACHMENT 3 Page 8 of 11 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) 4.3 PLACING 1B AIR DRYER IN SERVICE (continued) Printed 06/03/2015 at 12:48:00 NOTE Step 11 initialed after checking PRESS in Step 12 because 21 31 PSIG requirement in Step 12 will only be displayed for three (3) minutes (during regeneration mode) on N1P19FI566, then SYS PRESS will be displayed. ............................................................................. 11.Close breaker N1R19L504-N-BKR10, Air Dryer 1B Regeneration Controller, N1P19G506B-N. [120/208V DIST PNL 1J, TURB BLDG 155', West of 1B SGFP] ...................................................................................................................... ______NOTES Purge PRESS can only be read, adjusted, when off-stream chamber depressurized for regeneration. When off-stream chamber pressurized, Purge PRESS Indicator reads SYS PRESS. (Ref. U418762) ...................................................................................................... I&C assistance will be needed for the following step IF adjustments to be made. ...................... 12. IF PRESS on N1P19FI566, Purge Flow Indicator for IB Dryer N1P19F001B, not 21 31 PSIG during Regeneration Mode, perform the following : a.Slowly rotate Dryer Purge Throttle VLV N1P19V1089E until purge PRESS reads 21 - 31 PSIG. Throttle VLV located 5 inches behind Purge PRESS Indicator, N1P19FI566, between 2 chambers. Requires screwdriver or similar device to make adjustment. ................................... ______ .................................................................................................................... I&C Initial 13.Notify CONT RM 1B Air Dryer in service.................................................................______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 68 of 81 UATTACHMENT 3 Page 9 of 11 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) Printed 06/03/2015 at 12:48:00 4.4 REMOVING 1B AIR DRYER FROM SERVICENOTES Dryer S/D after Step 4, may be left pressurized during periods of non-use if desired; however, leaving air dryer pressurized NOT DESIRED if maintenance or servicing to be performed. ................................................................................................................................... IF maintenance or servicing to be performed, complete all steps in this section to depressurize air dryer before beginning work. ............................................................................. CAUTION Verify 1A Air Dryer in service prior to removing 1B Air Dryer from service. ...................................... 1.Open breaker N1R19L504-N-BKR10, Air Dryer 1B Regeneration Controller, N1P19G506B-N. [120/208V DIST PNL 1J, TURB BLDG 155', West of 1B SGFP] ...................................................................................................................... ______CAUTION Inlet, outlet isolation valves must be closed to prevent moisture overloading of desiccant beds due to continuous flow without regeneration. ............................................................................ 2.Close N1P19V506B, 1B Air Dryer Outlet ISO. ........................................................ ______3.Close N1P19V505B, 1B Air Dryer Inlet ISO. ........................................................... ______4.Close N1P19V1083Q, 1B IA Dryer Moisture Indicator ISO. .................................... ______NOTES Continue with Steps 5 through 10 to depressurize air dryer through Purge Exhaust Muffler. ..... IF maintenance or servicing to be performed on air dryer, verify air dryer depressurized. .......... 5.Close N1P19V1083P, 1B IA Dryer Solenoid Air Supply ISO...................................______6.Open N1P19V1083R, 1B IA Dryer Pilot Gas Filter Bleed ISO.................................______7.Verify PRESS indicates zero (0) PSIG on the following indicators after reasonable amount of time: N1P19PI559, 1B IA Dryer, (F001B) Inlet Air PI. ............................................ ______ N1P19PI563, 1B IA Dryer (F001B) Left Chamber PI. .................................... ______ N1P19PI564, 1B IA Dryer (F001B) Right Chamber PI. ................................. ______ N1P19PI560, 1B IA Dryer (F001B) Outlet PI. ................................................ ______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 69 of 81 UATTACHMENT 3 Page 10 of 11 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) 4.4 REMOVING 1B AIR DRYER FROM SERVICE (continued) Printed 06/03/2015 at 12:48:00 8. IF PRESS on Step 7 listed PIs does NOT indicate zero (0) PSIG after reasonable amount of time, open N1P19V1083Q, 1B IA Dryer Moisture Indicator ISO. ........................................................................................................... ______9. WHEN PRESS indicates zero (0) on PIs listed in Step 7, perform the following: a.Close N1P19V1084C, 1B IA Dryer Inlet FLTR ISO. ..................................... ______b.Close N1P19V1085C, 1B IA Dryer Outlet FLTR ISO. ................................... ______c.Open N1P19V1084H, 1B IA Dryer Inlet Filter Drain Bleed ISO. ................... ______d.Open N1P19V1085G, 1B IA Dryer Outlet Filter Drain ISO............................______10. WHEN PRESS indicates zero (0) on PIs listed in Step 7, notify CONT RM, 1B Air Dryer removed from service, depressurized. ...................................................... ______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 70 of 81 UATTACHMENT 3 Page 11 of 11 INSTRUMENT AIR DRYER OPERATION (Retain for QA Record) Printed 06/03/2015 at 12:48:00 4.5 BYPASSING BOTH AIR DRYERS1.Unseal,close N1P19V888, IA ISO to Air Dryer AUTO BYP ISO. ........................... ______2.Verify N1P19V902, Air Dryer AUTO BYP OPEN. ................................................... ______3.Close N1P19V506A, 1A Air Dryer Outlet ISO. ........................................................ ______4.Close N1P19V506B, 1B Air Dryer Outlet ISO. ........................................................ ______5.Close N1P19V505A, 1A Air Dryer Inlet ISO. ........................................................... ______6.Close N1P19V505B, 1B Air Dryer Inlet ISO. ........................................................... ______7.Notify CONT RM Air Dryers bypassed. ................................................................... ______4.6 REMOVING BOTH AIR DRYERS FROM BYP 1.Open N1P19V505B, 1B Air Dryer Inlet ISO. ............................................................ ______2.Open N1P19V505A, 1A Air Dryer Inlet ISO. ............................................................ ______3.Open N1P19V506A, 1A Air Dryer Outlet ISO. ......................................................... ______4.Open N1P19V506B, 1B Air Dryer Outlet ISO. ......................................................... ______5.Verify N1P19V902, Air Dryer AUTO BYP OPEN. ................................................... ______6.Close,sealN1P19V888, IA ISO to Air Dryer AUTO BYP ISO. ............................... ______7.Notify CONT RM Air Dryers removed from BYP. .................................................... ______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 71 of 81 Printed 06/03/2015 at 12:48:00 ATTACHMENT 4 Page 1 of 2 LEAKAGE ASSESSMENT ON IA HEADER IN CTMT(Retain for QA Record) Completed by: Signature Print Name Initials Date Reviewed by: Signature Print Name Initials Date COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 72 of 81 UATTACHMENT 4 Page 2 of 2 LEAKAGE ASSESSMENT ON IA HEADER IN CTMT (Retain for QA Record) Printed 06/03/2015 at 12:48:00 1.0 PURPOSE Attachment written to perform leak assessment of IA HDR inside CTMT to determine possible sources of CTMT air in leakage. ................................................... 2.0 INITIAL CONDITIONS Version of procedure verified current. .......................................................................... Procedure verified correct unit for task.........................................................................3.0 PRECAUTIONS, LIMITATIONS1. "Positioners" (I/Ps) on PRZR Spray valves (Fisher 846 I/Ps) vent air continuously. Blocking small single port underneath in center of cover plate can cause VLV to reposition. ....................................................................................... 2. Tables 1 through 4 may be performed in any order. .................................................... 4.0 INSTRUCTIONS1.Verify IA SYS aligned to CTMT with Q1P19HV3611 OPEN. .................................. ______2.Locate,identify air leak(s) on IA secondary HDRs utilizing the following tables: Table 1: Components Downstream of N1P19V094, IA To 105 FT ELEV Northeast Area ISO ........................................................................................... Table 2: Components Downstream of N1P19V010, IA To 105 FT ELEV Northwest Area ISO ........................................................................................... Table 3: Components Downstream of N1P19V011, IA To 129 FT ELEV ISO..................................................................................................................... Table 4: Components Downstream of N1P19V012, IA To 155 FT ELEV ISO.....................................................................................................................3. Generate Condition Report(s) as necessary to have air leaks/components repaired or replaced. ................................................................................................ ______ COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 73 of 81 Printed 06/03/2015 at 12:48:00 TABLE 1 Page 1 of 4 COMPONENTS DOWNSTREAM OF N1P19V094, IA TO 105 FT NE AREA ISO TPNSDescriptionLocationFail POS REF Drawing VLV POS* Deficiencies** Date/TimeQ1E21HCV936ACCUM Vent CTMT, 129' F.C. D175038/2 Q1E21HV8878B ACCUM Fill Line CTMT, 131'F.C.D175038/2Q1E21HV8875B ACCUM to Vent CTMT, 134' F.C. D175038/2 N1G21HV3395C1C CTMT CLR CNDS Drain CTMT, 134' F.C.D175004/1N1G21HV3395D1D CTMT CLR CNDS Drain CTMT, 134' F.C. D175004/1 N1G21HV3395B1B CTMT CLR CNDS Drain CTMT, 134 F.C.D175004/1Q1E21HV8141B RCP 1B #1 Seal LKOF CTMT, 130' F.O. D175039/1 N1E21HV8168B RMW to RCP 1B Seal CTMT, 130' F.C.D175039/1Q1E21HV8878C 1C ACCUM Fill Line ISO CTMT, 129' F.C. D175038/2 Q1P13HV2866D CTMT Mini Purge Supply DMPR CTMT, 129' F.C.D175010/1Q1P13HV3197 CTMT Purge SUPP CTMT, 129' F.C. D175010/1 N1G21HV3395A1A CTMT CLR CNDS DRN ISOCTMT, 129' F.C.D175004/1Q1E21HV8141C 1C RCP Seal LKOF CTMT, 129' By 1C RCP F.O. D175039/1 *Remote indication acceptable method, when available, for determining VLV POS, confirmation at VLV will serve as peer check. **If VLV in failed position, there may be no air between positioner, diaphragm to determine diaphragm leakage. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 74 of 81 UTABLE 1 Page 2 of 4 COMPONENTS DOWNSTREAM OF N1P19V094, IA TO 105 FT NE AREA ISO Printed 06/03/2015 at 12:48:00 TPNSDescriptionLocationFail POS REF Drawing VLV POS* Deficiencies** Date/TimeN1E21HV8168C 1C RCP Standpipe Fill ISO CTMT, 155' F.C. D175039/1 Q1B31PCV444CPRZR Spray VLV CTMT, 174' F.C.D175037/2Q1B31PCV444DPRZR Spray VLV CTMT, 174' F.C. D175037/2 N1G21HV7144RCDT RECIRC ISO CTMT, 105' F.O.D175042/1Q1E21HV8154 EXC LTDN ISO (Under RF Canal)CTMT, 106' F.C. D175039/1 Q1E21HV8153 EXC LTDN ISO (Under RF Canal)CTMT, 106' F.C.D175039/1Q1B13HV8032 RX Vessel LKOF ISO CTMT, 105' F.O. D175037/1 Q1E21HV8879C 1C ACCUM INJ Line Test ISO CTMT, 105' Below 1C ACCUM F.C.D175038/2Q1E21HV8877C 1C ACCUM Test Line ISO CTMT, 105' Below 1C ACCUM F.C. D175038/2 Q1E21HV8145 RCS PRZR AUX Spray CTMT, 106'F.C.D175039/1Q1E21HV8146 RCS Normal CHG Line CTMT, 107' F.C. D175039/1 Q1B13HV8047 PRT N2 Supply ISO (Q1B13V0037) CTMT, 105' F.C.D175037/2*Remote indication acceptable method, when available, for determining VLV POS, confirmation at VLV will serve as peer check. **If VLV in failed position, there may be no air between positioner, diaphragm to determine diaphragm leakage. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 75 of 81 UTABLE 1 Page 3 of 4 COMPONENTS DOWNSTREAM OF N1P19V094, IA TO 105 FT NE AREA ISO Printed 06/03/2015 at 12:48:00 TPNSDescriptionLocationFail POS REF Drawing VLV POS* Deficiencies** Date/TimeQ1G21HV3376 CTMT Sump DISCH CTMT, 105' OMB F.C. D175004/1 N1B13HV8031 PRT DRN to RCDT ISO (N1B13V002) CTMT, 105' RCDT Area F.C.D175037/2N1B13HV8030 RMW to PRT ISO (N1B13V005) CTMT, 105' - IMBF.C. D175037/2 N1G21HV7127RCDT DISC CTMT, 107' F.O.D175042/1N1G21HV7141 RCDT to PRT CTMT, 107' F.C. D175042/1 Q1E21HV8175A LTDN Line PENE RM ISO CTMT, 108' @ PENE 23 F.C.D175039/1Q1E21HV8175B LTDN Line PENE RM ISO CTMT, 108' @ PENE 23 F.C. D175039/1 Q1G21LCV1003RCDT LCV CTMT, 105' By Elevator F.C.D175042/1Q1E21HV8879B 1B ACCUM INJ Line Test VLV CTMT, 105' Below 1B ACCUM F.C. D175038/2 Q1E21HV8877B 1B ACCUM Test Line ISO CTMT, 105' Below 1B ACCUM F.C.D175038/2*Remote indication acceptable method, when available, for determining VLV POS, confirmation at VLV will serve as peer check. **If VLV in failed position, there may be no air between positioner, diaphragm to determine diaphragm leakage. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 76 of 81 UTABLE 1 Page 4 of 4 COMPONENTS DOWNSTREAM OF N1P19V094, IA TO 105 FT NE AREA ISO Printed 06/03/2015 at 12:48:00 TPNSDescriptionLocationFail POS REF Drawing VLV POS* Deficiencies** Date/TimeQ1E12HV3999A RX CAV CLG DMPR CTMT, 79' F.C. D175010/2 Q1E12HV3999B RX CAV CLG DMPR CTMT, 79' F.C.D175010/2N1G21HV7143RCDT Pump RECIRC Orifice BYPCTMT, 105' F.C. D175042/1 N1P18HV2935C Service Air to CTMT AUTO ISOBehind Elevator CTMT, 105' 12' In OVHD F.C.D175035/1*Remote indication acceptable method, when available, for determining VLV POS, confirmation at VLV will serve as peer check. **If VLV in failed position, there may be no air between positioner, diaphragm to determine diaphragm leakage. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 77 of 81 Printed 06/03/2015 at 12:48:00 TABLE 2 Page 1 of 1 COMPONENTS DOWNSTREAM OF N1P19V010, IA TO 105 FT NW AREA ISO TPNSDescriptionLocationFail POS REF Drawing VLV POS* Deficiencies** Date/TimeQ1P17HV3184 CCW From RCP Thermal BarrierCTMT, 122' F.C. D175002/2 Q1E21LCV460LTDN Line ISO CTMT, 106' F.C.D175039/1Q1E21LCV459 LTDN Line ISO CTMT, 106' F.C. D175039/1 Q1E21HV8147 RCS ALT CHG Line CTMT, 106' F.O.D175039/1Q1E21HV8879A 1A ACCUM INJ Line Test CTMT, 105' Below 1A ACCUM F.C. D175038/2 Q1E21HV8877A 1A ACCUM Test Line ISO CTMT, 105' Below 1A ACCUM F.C.D175038/2*Remote indication acceptable method, when available, for determining VLV POS, confirmation at VLV will serve as peer check. **If VLV in failed position, there may be no air between positioner, diaphragm to determine diaphragm leakage. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 78 of 81 Printed 06/03/2015 at 12:48:00 TABLE 3 Page 1 of 3 COMPONENTS DOWNSTREAM OF N1P19V011, IA TO 129 FT ISO TPNSDescriptionLocationFail POS REF Drawing VLV POS* Deficiencies** Date/TimeQ1E21HV8878A 1A ACCUM Fill Line CTMT, 131' @ 1A ACCUM F.C. D-175038/2 Q1E21HV8875A 1A ACCUM N2 SUPP/Vent ISOCTMT, 129' 1A ACCUM F.C.D-175038/2Q1P13HV2867D CTMT Mini Purge EXH CTMT, 134' F.C. D-175010/1 Q1P13HV3196 CTMT Purge EXH CTMT, 130' F.C.D-175010/1Q1P17HV3443 CCW From EXC LTDN/RCDT HXs CTMT, 129' PENE 45 & 46 F.C. D-175002/2 Q1E21HV8871 ACCUM Test Line to RWST ISOCTMT, 134' F.C.D-175038/2Q1G24HV7699A 1C SG BLDN ISO CTMT, 134' F.C. D-175071/1 Q1G24HV7699B 1C SG BLDN ISO CTMT, 134' F.C.D-175071/1Q1G24HV7698A 1B SG BLDN ISO CTMT, 134' F.C. D-175071/1 Q1G24HV7698B 1B SG BLDN ISO CTMT, 134' F.C.D-175071/1Q1G24HV7697A 1A SG BLDN ISO CTMT, 134' F.C. D-175071/1 Q1G24HV7697B 1A SG BLDN ISO CTMT, 134' F.C.D-175071/1Q1E21HV8142 RCP BYP CTMT, 125' F.C. D-175039/1 Q1P15HV3179C 1A SG BLDN CTMT, 134' F.C.D-175009/2*Remote indication acceptable method, when available, for determining VLV POS, confirmation at VLV will serve as peer check. **If VLV in failed position, there may be no air between positioner, diaphragm to determine diaphragm leakage. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 79 of 81 UTABLE 3 Page 2 of 3 COMPONENTS DOWNSTREAM OF N1P19V011, IA TO 129 FT ISO Printed 06/03/2015 at 12:48:00 TPNSDescriptionLocationFail POS REF Drawing VLV POS* Deficiencies** Date/TimeQ1P15HV3180C 1B SG BLDN CTMT, 134' F.C.D-175009/2Q1P15HV3181C 1C SG BLDN CTMT, 130' F.C.D-175009/2Q1P15HV3766 ACCUM Tanks CTMT, 130' F.C.D-175009/1Q1P15HV3164 1C ACCUM CTMT, 130' F.C.D-175009/1Q1P15HV3163 1B ACCUM CTMT, 130' F.C.D-175009/1Q1P15HV3162 1A ACCUM CTMT, 130' F.C.D-175009/1Q1P15HV3181A 1C SG Lower B/D CTMT, 130' F.C.D-175009/2Q1E21HV8143 EXC LTDN Divert VLV CTMT, 109' Fails to VCT D-175039/1Q1P15HV3180A 1B SG Lower BLDN CTMT, 134' F.C.D-175009/2Q1P15HV3179A 1A SG Lower BLDN CTMT, 134' F.C.D-175009/2Q1P15HV3181B SG 1C Upper BLDN CTMT, 129' F.C.D175071/1Q1P15HV3180B SG 1B Upper BLDN CTMT, 129' F.C.D175071/1N1B13HV8031 PRT DRN to RCDT ISO (N1B13V002) CTMT, 105' RCDT Area F.C.D175037/2Q1P15HV3179B SG 1A Upper BLDN CTMT, 129' F.C.D175071/1*Remote indication acceptable method, when available, for determining VLV POS, confirmation at VLV will serve as peer check. **If VLV in failed position, there may be no air between positioner, diaphragm to determine diaphragm leakage. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 80 of 81 UTABLE 3 Page 3 of 3 COMPONENTS DOWNSTREAM OF N1P19V011, IA TO 129 FT ISO Printed 06/03/2015 at 12:48:00 TPNSDescriptionLocationFail POS REF Drawing VLV POS* Deficiencies** Date/TimeQ1E21HV8141A 1A RCP Seal LKOF CTMT, 129' 1A RCP (OMB) F.O.D-175039/1Q1E21HV8149A Orifice Isolation CTMT, 106' F.C.D-175039/1Q1E21HV8149B Orifice Isolation CTMT, 106' F.C.D-175039/1Q1E21HV8149C Orifice Isolation CTMT, 106' F.C.D-175039/1Q1E21HCV137Excess LTDN HX DISCH CTMT, 106' F.C.D-175039/1Q1G21HV7126 RCDT DISCH CTMT, 108' F.C.D-175042/1*Remote indication acceptable method, when available, for determining VLV POS, confirmation at VLV will serve as peer check. **If VLV in failed position, there may be no air between positioner, diaphragm to determine diaphragm leakage. COMPRESSED AIR SYSTEM FNP-1-SOP-31.0 FARLEY Version 80.0 Unit 1 Page 81 of 81 Printed 06/03/2015 at 12:48:00 TABLE 4 Page 1 of 1 COMPONENTS DOWNSTREAM OF N1P19V012, IA TO 155 FT ISO TPNSDescriptionLocationFail POS REF Drawing VLV POS* Deficiencies** Date/TimeN1E21HV8168A 1A RCP Standpipe Fill ISO CTMT, 155' F.C.D175039/1*Remote indication acceptable method, when available, for determining VLV POS, confirmation at VLV will serve as peer check. **If VLV in failed position, there may be no air between positioner, diaphragm to determine diaphragm leakage. FNP ILT-38 JPM. Page 1 of 7 jpm k. SO-368A TITLE: Align RCDT Discharge To WHT ACCEPTABLE EVALUATION METHOD: PERFORM X SIMULATE DISCUSS EVALUATION LOCATION: SIMULATOR CONTROL ROOM X PLANT PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: N/A ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS: 1. All actions will be SIMULATED. 2. This JPM may be performed on either unit. 3. Provide student HANDOUT and procedure. 4. Allow student time to review conditions and procedure. 5. Unit 2 numbers are in (parentheses) TASK STANDARD: 1. Pump the RCDT to the WHT per FNP-1(2)-SOP-50.0, step 4.1.4, to decrease RCDT level to approximately 10%. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) EXAMINER:

Developer S. Jackson Date: 4/6/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP ILT-38 JPM. Page 2 of 7 CONDITIONS When I tell you to begin, you are to ALIGN THE RCDT DISCHARGE TO THE WHT on UNIT 1(2) PER SOP-50.0. The conditions under which this task is to be performed are: a. The RCDT is aligned per SOP-50.0A. b. #1 RHT is on service per SOP-2.4. c. The liquid waste system is aligned per SOP-50.0. d. Both RCDT pumps are off and aligned for normal operation per SOP-50.0. e. RCDT level / pressure, and WHT level has been checked. RCDT level is 50% RCDT pressure is 5psig WHT level is 20% f. You have been instructed by the control room to pump the RCDT to the WHT per FNP-1(2)-SOP-50.0, step 4.1.4, to decrease RCDT level to approximately 10%. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME *1. 4.1.4.1 Open RCDT DISCH TO WHT, Q1(2)G21V009 (1(2)-LWP-V-7137). Q1(2)G21V009 is turned counter-clockwise. (CUE: V009 is as you described) S / U *2. 4.1.4.2 Close RCDT PUMP DISCH TO RHT ISO, Q1(2)E21V315 (1(2)-CVC-V-8551). Q1(2)E21V315 is turned clockwise. (CUE: V315 is as you described.) S / U NOTE FOR CUE IF ASKED: RCDT ANNUNCIATORS initial conditions: Window 11 REACTOR COOLANT DRAIN TANK HI-LO LEVEL NOT LIT (75%, 5% stpts) Window 12 REACTOR COOLANT DRAIN TANK HI TEMP NOT LIT (170 degrees stpt) Window 13 REACTOR COOLANT DRAIN TANK HI PRESS NOT LIT (8 psig stpt) Window 37 REACTOR COOLANT DRAIN TK RECIRC LO FLOW LIT (85 gpm stpt) 3. 4.1.4.3 Verify open the following valves: RCDT RECIRC ISO N1(2)G21HV7144 (LWPP) RCDT OUTLET ISO N1(2)G21HV7127 (LWPP) N1(2)G21HV7144 and N1(2)G21HV7127 position lights checked on LWPP. (CUE: Red lights are lit for both valves.) S / U FNP ILT-38 JPM. Page 3 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 4. 4.1.4.4 IF required to maintain RCDT pressure by addition of hydrogen, THEN perform the following: 1. Verify pressure controller WASTE PROCESSING SYSTEM HYDROGEN BOTTLE DIS, Q1(2)G21HV7155 (Q1(2)G21V063) set to maintain 5 psi. (155' Plant Grounds) 2. Open H2 bottle isolation. 3. Open H2 BOTTLE TO RCDT ISO, N1(2)G21V340. 4. Verify open H2 SUPP TO RCDT, N1(2)G21V285(2) (at H2 Bottle) with regulator set for approximately 20 psi. (TIME COMPRESSION - CUE: This step has been completed by another operator.) S / U 5. 4.1.4.5 Verify that RCDT LCV Q1(2)G21LCV1003 (Q1(2)G21V064) is in manual and closed (LWPP) Q1(2)G21LCV1003 M/A station on LWPP checked to ensure in manual and closed. (CUE: LCV1003 M/A station display indications are as follows: "M" is lit on display the far right bargraph is at minimum A blue dot is lit above the far right bargraph the display above the 3 bargraphs displays "0.0".) S / U *6. 4.1.4.6 Take RCDT LCV Q1(2)G21LCV1003 (Q1(2)G21V064) selector switch on MCB to OPEN and then spring return to AUTO. Control Room contacted to take Q1(2)G21LCV1003 switch to OPEN and returned to AUTO. (CUE: Control Room acknowledges, and LCV1003 switch has been taken to OPEN and has been returned to AUTO.) S / U FNP ILT-38 JPM. Page 4 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *7. 4.1.4.7 Open RCDT PUMPS DISCH LINE ISO Q1(2)G21HV7136. Control Room contacted to open Q1(2)G21HV7136. (CUE: Control Room acknowledges instruction, and HV7136 has been opened.) S / U *8. 4.1.4.8 Place RCDT LCV, Q1(2)G21LCV1003 (Q1(2)G21V064) in MANUAL and open 20-50%. (LWPP) Q1(2)G21LCV1003 M/A station demand raised to 20-50% by pressing up arrow until desired demand is reached. (CUE: the far right bargraph is at approximately 40% "39.1" is displayed above the 3 bargraphs) S / U *9. 4.1.4.9 Start 1(2)A(B) RCDT pump, and verify flow through FI 1008 (LWPP). Either RCDT pump handswitch taken to start. N1(2)G21FI1008 checked to verify flow. (CUE: RCDT pump red "running" light lit for pump started. N1(2)G21FI1008 indicates ~100 gpm Alarm clears: WINDOW 37 REACTOR COOLANT DRAIN TK RECIRC LO FLOW. S / U 10. Monitor tank transfer. RCDT level, pressure and flow are monitored. WHT level is monitored. (CUE: RCDT level is falling. RCDT press stable at 5 psig. RCDT flow is stable at ~ 100 gpm. WHT level is rising slightly. S / U TIME COMPRESSION - CUE: RCDT LEVEL IS 10% AND PRESSURE IS 5 PSIG. FNP ILT-38 JPM. Page 5 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *11. 4.1.4.10 WHEN desired level is reached, THEN perform the following: a. Stop 1(2)A(B) RCDT pump. RCDT pump handswitch is taken to off. (CUE: Green "stopped" light is lit. Alarm comes in: WINDOW 37 REACTOR COOLANT DRAIN TK RECIRC LO FLOW. S / U b. Close RCDT LCV, Q1(2)G21LCV1003 (Q1(2)G21V064) (LWPP). Q1(2)G21LCV1003 M/A station demand lowered to 0% by depressing the down arrow. (CUE: the far right bargraph is at minimum and the display above the bargraphs indicates 0.0) S / U *12. 4.1.4.11 Realign valves as follows: Open RCDT PUMP DISCH TO RHT ISO, Q1(2)E21V315 (1(2)-CVC-V-8551). Q1(2)E21V315 is turned counter-clockwise. (CUE: V315 is as you described.) S / U Close RCDT DISCH TO WHT Q1(2)G21V009 (1(2)-LWP-V-7137). Q1(2)G21V009 is turned clockwise. (CUE: V009 is as you described) S / U 13. 4.1.4.12 Verify RCDT pressure PI 1004 (LWPP) between 3 and 8 psig. PI 1004 checked. (CUE: PI 1004 indicates 5 psig) S / U 14. 4.1.4.13 IF opened in step 4.1.4.4, THEN perform the following: 1. Close H2 bottle isolation. 2. Close H2 BOTTLE TO RCDT ISO, N1(2)G21V340. (CUE: This step will be performed by another operator) S / U 15. 4.1.4.14 Restore the RCDT to normal per section 4.1.2. (CUE: Another operator will complete this step) S / U STOP TIME Terminate when Pump Down is complete. FNP ILT-38 JPM. Page 6 of 7 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk (*) preceding the element number. GENERAL

REFERENCES:

1. FNP-1(2)-SOP-50.0, Version 75(70) 2. K/As: 068K1.07 - 2.7 / 2.9 GENERAL TOOLS AND EQUIPMENT:

Provide: 1. FNP-1(2)-SOP-50.0, section 4.1.4

Critical ELEMENT justification: STEP Evaluation 1, 2, Critical - Task completion. Proper line up to move water from RCDT to WHT. 3 - 5 Not Critical - NO actions required by operator. 6 - 9 Critical - Task completion. Proper line up to move water from RCDT to WHT. 10 Not Critical - NO actions required. 11-12 Critical - Task completion. Required to not pump the RCDT dry and restore system line up 13-15 Not Critical - NO actions required. COMMENTS: FNP ILT-38 JPM. Page 7 of 7 jpm k. CONDITIONS When I tell you to begin, you are to ALIGN THE RCDT DISCHARGE TO THE WHT on UNIT 1(2) PER SOP-50.0. The conditions under which this task is to be performed are: a. The RCDT is aligned per SOP-50.0A. b. #1 RHT is on service per SOP-2.4. c. The liquid waste system is aligned per SOP-50.0. d. Both RCDT pumps are off and aligned for normal operation per SOP-50.0. e. RCDT level / pressure, and WHT level has been checked. RCDT level is 50% RCDT pressure is 5psig WHT level is 20% f. You have been instructed by the control room to pump the RCDT to the WHT per FNP-1(2)-SOP-50.0, step 4.1.4, to decrease RCDT level to approximately 10%. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 FARLEY NUCLEAR PLANT SYSTEM OPERATING PROCEDURE FNP-1-SOP-50.0SAFE TYLIQUID WASTE PROCESSING SYSTEM RE LAT EDPROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORYSECTIONSContinuous: ALL

Reference:

NONE Information: NONE Approved: David L Reed Effective Date: 04/16/2015 Operations UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Page 1 of 1 Version 75.0 TABLE OF CONTENTS Procedure Contains Number of Pages Body ........................................................61 Appendix 1.------------5 Appendix 2 ................................................3 Appendix 3 ................................................2 Appendix 4 ................................................2 Appendix 5 ................................................6 Appendix 6 ................................................1 Appendix 7..-----------...2 Appendix 8.------------3 UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 FARLEY NUCLEAR PLANT UNIT 1 SYSTEM OPERATING PROCEDURE SOP-50.0 LIQUID WASTE PROCESSING SYSTEM 1.0PURPOSEThis procedure provides the Initial Conditions, Precautions and Limitations, and Instructions for Operation of the Liquid Waste Processing System. Included are the following instructions. 4.1 Reactor Coolant Drain Tank (RCDT) Operation 4.1.1 RCDT system startup and recirculation 4.1.2 RCDT normal operation 4.1.3 Manual Pump Down of RCDT to RHT 4.1.4 RCDT Discharge to WHT 4.1.5 Draining refueling canal with the RCDT System to the RWST. 4.1.6 Filling the RCDT from the PRT 4.1.7 Draining Refueling Cavity Using the RCDT System and Pumping to the RHT or WHT 4.1.8 Processing Nozzle Dam Leakage to RHT. 4.1.9 Draining the RCS Loops for Maintenance Via the Reactor Coolant Drain System. 4.1.10 Establishing a Hydrogen Atmosphere in the RCDT. 4.1.11 Establishing a Nitrogen Atmosphere in the RCDT 4.2 Waste Holdup Tank (WHT) Operation 4.3 Waste Evap Condensate Tank (WECT) Operation 4.4 Chemical Drain Tank (CDT) Operation - Draining the CDT to the WHT 4.5 Floor Drain Tank (FDT) System Operation 4.6 #1(2) Waste Monitor Tank (WMT) Operation 4.7 #1(2) Waste Monitor Tank (WMT) Recirculation 4.8 Educting Diaphragm on WECT 4.9 Laundry and Hot Shower Tank (LHST) Operation 4.10 Manually Draining Refueling Cavity to CTMT Sump 4.11 Alternate Processing of the FDT to the WHT 4.12 Draining the Cask Wash area to the FDT UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 Appendix 1 Measurement of Floor Drain Tank Pump Recirc Line Flow. Appendix 2 Floor Drain Tank Filter Isolation for Filter Replacement. Appendix 3 Floor Drain Tank Strainer Isolation for Basket Cleaning or Replacement. Appendix 4 LHST Strainer Isolation for Basket Cleaning or Replacement. Appendix 5 Processing FDT Using Temporary Demin Liner Appendix 6 Use of the RCDT LCV-1003 Controller Appendix 7 Installation of Temporary Level Indication for the Floor Drain Tank Appendix 8 Waste Evaporator Feed Filter Isolation for filter replacement 2.0INITIAL CONDITIONS 2.1The electrical distribution system is energized and aligned for normal operation per system checklist FNP-1-SOP-36.0, PLANT ELECTRICAL DISTRIBUTION LINE-UP, with exceptions noted. 2.2The compressed air system is in service and aligned for normal operation per FNP-1-SOP-31.0, COMPRESSED AIR SYSTEM, with exceptions noted. 2.3The liquid waste processing system valves are aligned per system checklist FNP-1-SOP-50.0A-E, LIQUID WASTE PROCESSING SYSTEM, with exceptions noted. 2.4Component cooling water system is aligned per FNP-1-SOP-23.0, COMPONENT COOLING WATER SYSTEM, to supply water to the waste evaporator condenser, distillate cooler, vent condenser, and RCDT heat exchanger. This initial condition may be waived by the Shift Supervisor if not required to support the activity being performed. 2.5A hydrogen blanket has been established in the RCDT and is being maintained at a pressure between three and eight psig per Section 4.1.10. This initial condition may be waived by the Shift Supervisor if not required to support the activity being performed. 2.6Solid Waste Processing System aligned per FNP-1-SOP-49.0A, SOLID WASTE PROCESSING SYSTEM, and FNP-1-SOP-49.0B, STEAM GENERATOR BLOWDOWN SPENT RESIN STORAGE SYSTEM. 2.7The WHT to Recycle Evap. Spoolpiece and the R.E.C. Filter to WECT Spoolpiece are both removed and blind flanges are installed. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 3.0PRECAUTIONS AND LIMITATIONS 3.1Due to the presence of radioactive or potentially radioactive materials within the confines of the liquid waste processing system, constant vigilance must be exercised over system piping, valves, tanks, and other components whether in operation or shutdown. Pre-operational checks and normal routine operations and surveillance should include visual checks for system deterioration, component leakage, and correct system line-up which if not detected and corrected could subsequently result in the release of radioactive liquid to the immediate area, the environment, or other parts of this system. 3.2Radiation monitor R-18 must be operable and in service during liquid waste discharge to the river except as permitted by technical specifications. 3.3IF R-18 becomes inoperable while discharging liquid waste to the river, THEN the discharge must be stopped immediately. 3.4The Shift Supervisor or Shift Support Supervisor shall be notified any time R-18 is taken out of service or becomes inoperable. 3.5A Radioactive Liquid Release Permit must be completed and approved prior to discharging radioactive liquid to the river. 3.6Verify that tanks aligned to receive liquid waste discharge have sufficient capacity to receive the liquid. 3.7ALL tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste, including non-source and non-destination tank levels.For processing or transfers, the levels of the source tank and thedestination tankshould be determined. The approximate flow rate should be considered and used to determine an approximate completion time. Tank levels shall be checked prior to the estimated completion of the processing or transfer such that sufficient margin exists to prevent tank overflow. At no time should the High Level Alarm be relied upon for securing the processing or transfer of a tank. To preclude overflow, waste tanks should not be filled to greater than 95%. 3.8A deficiency report should be written to replace liquid waste system filters when theP increases to greater than 20 psid. 3.9Caution should be exercised when pumping liquids to ascertain that affected pumps do not lose suction. 3.10Once a WMT has been placed on recirculation for sampling purposes, prior to discharging to the environment, the tank shall remain in an isolated condition to prevent the introduction of any liquids which could alter the concentrations of the tanks contained volume. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 3.11WECT should not be drained less than 5% to prevent admission of air under the diaphragm. 3.12Sample source tank for activity prior to transfer from Unit 1 to Unit 2. This sample may be waived by Chemistry based on source of water. 3.13When filling the WMT's, estimate the time that the WMT tank will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%. WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) 3.14Contact Health Physics prior to opening N1G21V021 Refueling Cavity Drain.Opening this valve has the potential for increased dose rates in the RCDT pump area and 100' PPR in Aux Building. (AI2008207409) 4.0INSTRUCTIONS4.1REACTOR COOLANT DRAIN TANK (RCDT) OPERATION. 4.1.1RCDT system startup and recirculation 4.1.1.1RCDT system is aligned per system checklist FNP-1-SOP-50.0A.4.1.1.2RCDT level is greater than 20%. 4.1.1.3Verify open the following valves: RCDT RECIRC ISO N1G21HV7144 (LWPP) RCDT OUTLET ISO N1G21HV7127 (LWPP) 4.1.1.4Verify that RCDT LCV Q1G21LCV1003 (Q1G21V064) is in MANUAL and closed (LWPP)4.1.1.5Start an RCDT pump. 4.1.1.6IFnecessary to establish adequate recirc flow to keep an RCDT pump running, THEN openRCDT RECIRC VALVE N1G21HV7143. 4.1.1.7IF desired to adjust tank level while on recirc, THENadjust RCDT LCV Q1G21LCV1003 (Q1G21V064) as required in manual or automatic to control RCDT level. NOTE: The following condition should be tracked using a caution tag or administrative tracking item to ensure that it is restored when recirc is no longer required. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.2RCDT normal operation NOTES: Venting of the RCDT should be performed as needed in accordance with FNP-1-SOP-51.0, WASTE GAS SYSTEM. The RCDT should be pumped down periodically per sections 4.1.3 or 4.1.4 to maintain parameters within the following bands: MIN MAX RCDT Level 5% 75% RCDT Pressure 3 PSIG 8 PSIG RCDT Temp N/A 170° F RCDT pumps should automatically trip at 10% RCDT level. 4.1.2.1Place both RCDT pumps in PULL TO LOCK. 4.1.2.2IFopened in step 4.1.1.6, THEN close RCDT RECIRC VALVE N1G21HV7143. 4.1.2.3Verify that RCDT LCV Q1G21LCV1003 (Q1G21V064) is in MANUAL and closed (LWPP) 4.1.2.4Take RCDT LCV Q1G21LCV1003 (Q1G21V064) selector switch on MCB to OPEN and then spring returnto AUTO. 4.1.2.5Take RCDT PUMPS DISCH LINE ISO Q1G21HV7136 (Q1G21V006) handswitch on MCB, to OPEN and in AUTO.4.1.2.6WHEN necessary to lower tank level or pressure, THENperform Section 4.1.3 to pump to the RHT OR 4.1.4 to pump to the WHT. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: The following section may be utilized to lower RCDT pressure by lowering RCDT level. 4.1.3Manual Pump Down of RCDT to RHT: 4.1.3.1Verify open the following valves: RCDT RECIRC ISO N1G21HV7144 (LWPP) RCDT OUTLET ISO N1G21HV7127 (LWPP) 4.1.3.2IF required to maintain RCDT pressure by addition of hydrogen, THEN perform the following: a.Verify pressure controller H2 SUPP TO RCDT Q1G21HV7155 (Q1G21V063) set to maintain 3 psi. (155' Plant Grounds) b.Open H2bottle isolation. c.Open H2 BOTTLE TO RCDT ISO, N1G21V340. d.Verify open H2 SUPP TO RCDT, N1G21V285 (at H2Bottle) with the bottle regulator set for approximately 20 psi. 4.1.3.3Verify that RCDT LCV Q1G21LCV1003 (Q1G21V064) is in MANUAL and closed (LWPP) 4.1.3.4Take RCDT LCV Q1G21LCV1003 (Q1G21V064) selector switch on MCB to OPEN and then spring returnto AUTO. 4.1.3.5Take RCDT PUMPS DISCH LINE ISO Q1G21HV7136 (Q1G21V006) handswitch on MCB, to OPEN and then place in AUTO. 4.1.3.6Place RCDT LCV, Q1G21LCV1003 (Q1G21V064) in MANUAL and open 20-50%. (LWPP) 4.1.3.7Start 1A(B) RCDT pump, and verify flow through FI 1008 (LWPP). 4.1.3.8WHEN desired level is reached, THEN perform the following:a.Stop 1A(B) RCDT pump. b.Close RCDT LCV, Q1G21LCV1003 (Q1G21V064) (LWPP). 4.1.3.9Verify RCDT pressure PI 1004 (LWPP) between 3 and 8 psi. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.3.10IF opened in Step 4.1.3.2, THEN perform the following: a.Close H2bottle isolation. b.Close H2 BOTTLE TO RCDT ISO, N1G21V340. 4.1.3.11Restore the RCDT to normal operation per Section 4.1.2. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: The following section may be utilized to lower RCDT pressure by lowering RCDT level. IF no RCDT pumps are operable, THEN it is permissible to gravity drain to WHT. 4.1.4RCDT Discharge to WHT: 4.1.4.1Open RCDT DISCH TO WHT, Q1G21V009 (1-LWP-V-7137). 4.1.4.2Close RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551).4.1.4.3Verify open the following valves: RCDT RECIRC ISO N1G21HV7144 (LWPP) RCDT OUTLET ISO N1G21HV7127 (LWPP) 4.1.4.4IF required to maintain RCDT pressure by addition of hydrogen, THEN perform the following: a.Verify pressure controller H2 SUPP TO RCDT Q1G21HV7155 (Q1G21V063) set to maintain 5 psi. (155' Plant Grounds) b.Open H2bottle isolation. c.Open H2 BOTTLE TO RCDT ISO, N1G21V340. d.Verify open H2 SUPP TO RCDT, N1G21V285 (at H2Bottle) with regulator set for approximately 20 psi. 4.1.4.5Verify that RCDT LCV Q1G21LCV1003 (Q1G21V064) is in MANUAl and closed (LWPP)4.1.4.6Take RCDT LCV Q1G21LCV1003 (Q1G21V064) selector switch on MCB to OPEN and then spring returnto AUTO. 4.1.4.7Take RCDT PUMPS DISCH LINE ISO Q1G21HV7136 (Q1G21V006) handswitch on MCB, to OPEN and then springreturn to AUTO. 4.1.4.8Place RCDT LCV, Q1G21LCV1003 (Q1G21V064) in MANUAL and open 20-50%. (LWPP) 4.1.4.9Start 1A(B) RCDT pump, and verify flow through FI 1008 (LWPP). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.4.10WHEN desired level is reached, THEN perform the following:a.Stop 1A(B) RCDT pump. b.Close RCDT LCV, Q1G21LCV1003 (Q1G21V064) (LWPP). 4.1.4.11Realign valves as follows: Open RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551).Close RCDT DISCH TO WHT Q1G21V009(1-LWP-V-7137). 4.1.4.12Verify RCDT pressure PI 1004 (LWPP) between 3 and 8 psi. 4.1.4.13IF opened in Step 4.1.4.4, THEN perform the following: a.Close H2bottle isolation. b.Close H2 BOTTLE TO RCDT ISO, N1G21V340. 4.1.4.14Restore the RCDT to normal operation per section 4.1.2. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.5Draining refueling canal with the RCDT System to the RWST: 4.1.5.1Stop all operating RCDT pumps. 4.1.5.2Close RCDT OUTLET ISO N1G21HV7127 (N1G21V006).4.1.5.3Close RCDT RECIRC ISO N1G21HV7144 (N1G21V106).4.1.5.4Verify closed RCDT DISCH TO WHT Q1G21V009 (1-LWP-V-7137). 4.1.5.5Verify closed RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). 4.1.5.6Verify closed PRESSURIZER RELIEF TANK DRN N1B13V002 (N1B13HV8031). 4.1.5.7Verify SFP purification loop is not in operation per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 4.1.5.8IF RWST purification is in operation, THEN performthe following: a.Stop the RWP pump. b.CloseQ1G31HV033A, RWST TO RWPP AUTO ISO (MCB)c.Close Q1G31HV033B, RWST TO RWPP AUTO ISO (MCB)NOTES: IF jumper installed in the following step, a tracking item must be initiated to ensure jumper removed prior to Mode 4 entry. Jumper to be installed in the following step is necessary to bypass HV033A/B OPEN / RWPP start interlock if HV033A OR HV033B cannot be operated (no power, FNP-1-SOP-54.0 - Attachment 9 not in use with EG4 ILLUMINATED, etc). IF jumper is to be installed in the following step, performer may continue in this procedure while awaiting jumper installation. Jumper installation must be completed prior to performing Step 4.1.5.17 4.1.5.9IF desired to use RWP pump to assist pumping down cavity at Step 4.1.5.17 AND Q1G31HV033A OR Q1G31HV033B cannot be operated, in N1G31HS2764, install jumper between TB1-3 and TB1-4. (Reference D177244/1, SNC540544E006, B181606/100 & 101). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.5.10Verify the following open: a.RWP PUMP DISCH ISO, N1G31V008 (1-SFP-V-8792)b.SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B).4.1.5.11Bypass the SFP demineralizer by performing the following:Close SFP PURIF INLET ISO, N1G31V009 (1-SFP-V-8773).Open SFP DEMIN BYPASS, N1G31V012 (1-SFP-V-8774).Close SFP DEMIN INLET ISO, N1G31V003 (1-SFP-V-8776).4.1.5.12Verify RCDT PUMPS DISCH LINE ISO Q1G21HV7136 (Q1G21V006) is open and the handswitch is in the AUTO position. NOTES: The RWP pump is not required; however, experience has shown it greatly increases flow and it is normally desired to have running. Throttle SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B) as necessary to limit flow through SFP demineralizer to < 100 GPM on FI-654. N1G21V021 should not be opened until Rx Cavity draining is in progress (AI2008207409) 4.1.5.13Open REFUELING CANAL DRN, N1G21V021 (1-LWP-V-7129). 4.1.5.14Open RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.1.5.15Open RCDT LCV Q1G21LCV1003 (Q1G21V064). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTES: In the following step, it will be necessary to hold the handswitch in start for the RCDT pump until flow is established to permit the pump to remain running. An operator stationed at the refueling water purification pump should monitor discharge pressure of the pump. When RWST pump discharge pressure increases due to the start of the RCDT pump, the RWST purification pump may be started per step 4.1.5.16. 4.1.5.16Start an RCDT pump. CAUTION: The RWP pump does not have a low flow trip. 4.1.5.17IF desired, perform one of the following to start RWP pump: a.IF Q1G31HV033A OR Q1G31HV033B cannot be operated,perform the following: (1)Verify jumper installed per Step 4.1.5.9. (2)Start RWP pump ORb.IF Q1G31HV033A AND Q1G31HV033B can be operated,perform the following: (1) IF MCB annunciator EG4, RWST MIN TECH SPEC LVL A TRN ILLUMINATED, verifyjumpers installed per FNP-1-SOP-54.0, . (2)Verify Q1G31V010, RWP PUMP SUCTION FROM RWST ISO CLOSED. (3)Open the following: Q1G31V033A, RWST TO RWPP AUTO ISOLATIONQ1G31V033B, RWST TO RWPP AUTO ISOLATION(4)Start RWP pump UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 CAUTION: RCDT pump discharge piping is protected from over pressurization by a relief valve at penetration 31 outside containment which discharges to the equipment drains. This relief valve can sustain seat leakage at pressures above 150 psig. NOTE: Two RCDT pumps may be required to prevent the RWP pump from cavitating. IF a second RCDT pump is started THEN monitor RCDT pump discharge pressure to ensure the relief valve is not challenged (<150 psig). 4.1.5.18IF necessary to prevent RWP pump cavitation THEN start the second RCDT pump. 4.1.5.19WHEN the desired RWST level is reached, perform the following a.IF running, stop RWP pump. (1)Verify Q1G31V033A, RWST TO RWPP AUTO ISOLATION CLOSED.(2)Verify Q1G31V033B, RWST TO RWPP AUTO ISOLATION CLOSED.(3)Open Q1G31V010, RWP PUMP SUCTION FROM RWST ISO. NOTE: Procedure should be continued while awaiting jumper removal. (4) IF installed per Step 4.1.5.9, in N1G31HS2764, remove jumper between TB1-3 and TB1-4.(Reference D177244/1, SNC540544E006, B181606/100 & 101) b.Shift RCDT discharge to RHT by performing the following:(1)Open RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551) (2)Close RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138) UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.5.20WHEN draining is completed, THEN stop the RWP pump if running, and stop the RCDT pump. Realignvalves as follows: Close REFUELING CANAL DRN, N1G21V021 (1-LWP-V-7129). Verify closed RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). Close RWP PUMP DISCH ISO, N1G31V008 (1-SFP-V-8792).Close SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B).Verify open RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). Open RCDT OUTLET ISO Q1G21HV7127 (Q1G21V006).Open RCDT RECIRC ISO Q1G21HV7144 (N1G21V106).Close RCDT LCV Q1G21LCV1003 (Q1G21V064) and return control to MANUAL. 4.1.5.21Restore SFP demineralizer alignment by performing the following:Open SFP PURIF INLET ISO, N1G31V009 (1-SFP-V-8773).Open SFP DEMIN INLET ISO, N1G31V003 (1-SFP-V-8776).Close SFP DEMIN BYPASS, N1G31V012 (1-SFP-V-8774).4.1.5.22Restore the RCDT to normal operation per Section 4.1.2. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: Leave vent path in operation for pressure increases due to level increases. 4.1.6Filling the RCDT from the PRT: 4.1.6.1Verify RCDT aligned in recirculation per Section 4.1. 4.1.6.2Verify sufficient water available in PRT. 4.1.6.3Open PRT DRN ISO, N1B13HV8031 (N1B13V002) [MCB].NOTE: Closing RCDT outlet iso N1G21HV7127 (N1G21V006) RCDT OUTLET ISO will cause rapid rise in RCDT Level. 4.1.6.4IF required, THEN close RCDT OUTLET ISO, N1G21HV7127 (N1G21V006) [LWPP]. 4.1.6.5WHEN desired level reached in RCDT, THEN verifyRCDT OUTLET ISO, N1G21HV7127 (N1G21V006) open.4.1.6.6Close PRT DRN ISO, N1B13HV8031 (N1B13V002) [MCB].4.1.6.7IF required, THEN vent the RCDT per FNP-1-SOP-51.0, WASTE GAS SYSTEM, Section 4.9 or 4.17. 4.1.6.8Restore alignment of RCDT for normal operation per step 4.1.2 of this procedure. 4.1.7Draining Refueling Cavity Using the RCDT System and Pumping to the RHT or WHT: 4.1.7.1Verify an RHT in service per FNP-1-SOP-2.4, CVCS BORON RECYCLE SYSTEM. 4.1.7.2Stop all operating RCDT pumps. 4.1.7.3Close RCDT OUTLET ISO, N1G21HV7127 (N1G21V006) on LWPP. 4.1.7.4Close RCDT RECIRC ISO, N1G21HV7144 (N1G21V106) on LWPP. 4.1.7.5Verify RCDT PUMPS DISCH LINE ISO, Q1G21HV7136 is open and handswitch is in the auto position (MCB). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: N1G21V021 should not be opened until Rx Cavity draining is to commence. (AI2008207409) 4.1.7.6Open REFUELING CANAL DRAIN, N1G21V021 (1-LWP-V-7129). 4.1.7.7Verify closed RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.1.7.8IF discharge of the RCDT to the WHT is desired: a.Close RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551).b.Open RCDT DISCH TO WHT Q1G21V009 (1-LWP-V-7137). 4.1.7.9IF discharge of the RCDT to the RHT is desired: a.Verify closed RCDT DISCH TO WHT Q1G21V009 (1-LWP-V-7137). b.Verify open RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). c.Monitor RHT level and WHEN necessary, THEN stopRCDT pumps and shift RHT's per FNP-1-SOP-2.4. 4.1.7.10Open RCDT LCV Q1G21LCV1003 (Q1G21V064). CAUTIONS: Continuous monitoring of refueling cavity level is necessary to prevent cavitation of the RCDT pump(s). If a second RCDT pump is started, ensure that the flow rate remains at least 15 gpm higher than the flow obtained from a single pump to ensure miniflow protection is maintained. The flow rate will change as the cavity is lowered so the single pump reference will need to be obtained repeatedly. 4.1.7.11Start a RCDT pump. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.7.12IF desired to start the second RCDT pump, THEN perform the following: a.Note the discharge flow rate with a single pump in operation.b.Start the second RCDT pump and verify that the discharge flow rate increases by at least 15 gpm. c.Monitor discharge flow rate, and secure one RCDT pump prior to flow decreasing to within 15 gpm of the single pump flow rate. Return to Step 4.1.7.12.a and repeat as necessary. 4.1.7.13WHEN draining is complete, THEN stop the RCDT pump. 4.1.7.14Close REFUELING CANAL DRN, N1G21V021 (1-LWP-V-7129). 4.1.7.15Close RCDT LCV Q1G21LCV1003 and place in MANUAL.4.1.7.16Open RCDT OUTLET ISO N1G21HV7127 (N1G21V006) on LWPP. 4.1.7.17Open RCDT RECIRC ISO N1G21HV7144 (N1G21V106) on LWPP. 4.1.7.18IF the RCDT was aligned to the WHT, THEN performthe following: a.Close RCDT DISCH TO WHT Q1G21V009 (1-LWP-V-7137). b.Open RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551).4.1.7.19Restore the RCDT to normal operation per Section 4.1.2. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.8Processing Nozzle Dam Leakage to RHT. 4.1.8.1Verify closed RCDT VENT, Q1G21V192 (1-LWP-V-7163). 4.1.8.2Connect drain hose(s) from the nozzle dam leakage to the RCDT VENT, Q1G21V192 (1-LWP-V-7163). 4.1.8.3Stop 1A and 1B RCDT pumps. 4.1.8.4Open RCDT VENT, Q1G21V192 (1-LWP-V-7163). 4.1.8.5Control RCDT level and discharge to RHT per Step 4.1.2. 4.1.8.6WHEN nozzle dam leakage processing to RHT is no longer required, THEN perform the following: a.Stop 1A and 1B RCDT pumps. b.Close RCDT VENT, Q1G21V192 (1-LWP-V-7163). c.Remove nozzle dam drain hose from RCDT vent. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.9Draining the RCS Loops for Maintenance Via the Reactor Coolant Drain System. 4.1.9.1Verify core unload is completed. 4.1.9.2Verify both trains of RHR are secured. 4.1.9.3Verify nozzle dam leakage processing is secured per Step 4.1.8.6. 4.1.9.4IF the SFP purification loop is in service, THEN removefrom service per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 4.1.9.5IF RWST purification is in operation, THEN removefrom service per FNP-1-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 4.1.9.6Open the SFP PURIF OUTLET THE RWST, N1G31V021B (1-SFP-V-8793B). 4.1.9.7Open the RWP PUMP DISCH ISO, N1G31V008 (1-SFP-V-8792).4.1.9.8Close the RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). 4.1.9.9Open the RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.1.9.10Close the RCDT RECIRC ISO 1-LWP-HV-7144 (N1G21V106)4.1.9.11Close the RCDT OUTLET ISO N1G21HV7127 (N1G21V006).4.1.9.12Open the desired RCS LOOP TO RCDT PUMP ISO: Q1B13V002A, (1-RC-V-8057A) AND Q1B13V001A, (1-RC-V-8058A) for Loop 1A Q1B13V002B, (1-RC-V-8057B) AND Q1B13V001B, (1-RC-V-8058B) for Loop 1B Q1B13V002C, (1-RC-V-8057C) AND Q1B13V001C, (1-RC-V-8058C) for Loop 1C 4.1.9.13Open the RCDT PUMPS DISCH LINE ISO 1-LWP-HV-7136 (Q1G21V006). 4.1.9.14Start 1A (B) RCDT pump. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.9.15Adjust the RCDT LCV Q1G21LCV1003 (Q1G21V064) in manual to control the draining rate and maintainRCDT pump flow to < 100 gpm. 4.1.9.16IF unable to maintain RCDT discharge flow greater than minimum to maintain pump in operation, THEN performthe following: a.Open RCDT OUTLET ISO N1G21HV7127 (N1G21V006)b.Open RCDT RECIRC ISO N1G21HV7144 (N1G21V106)c.Place RCDT LCV Q1G21LCV1003 (Q1G21V064) in automatic and adjust to maintain RCDT level as desired.4.1.9.17WHEN RWST level reaches 39 feet, THEN shift RCDT discharge to RHT by performing the following: a.Open RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551).b.Close RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.1.9.18WHEN the desired RCS level is reached, THEN stop the 1A (1B) RCDT pump. 4.1.9.19Close the RCS loop to RCDT pump isolation valve(s) opened in Step 4.1.9.12. 4.1.9.20Verify closed RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.1.9.21Verify open RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). 4.1.9.22Close SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B).4.1.9.23Close the RWP PUMP DISCH ISO, N1G31V008 (1-SFP-V-8792).4.1.9.24Verify open RCDT OUTLET ISO N1G21HV7127 (N1G21V006).4.1.9.25Verify open RCDT RECIRC ISO, N1G21HV7144 (N1G21V106).4.1.9.26Place the RCDT in service per Section 4.1.2. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.10Establishing a Hydrogen Blanket in the RCDT. 4.1.10.1Verify that the oxygen concentration in the RCDT gas space is less than 5% by volume. 4.1.10.2RCDT system is aligned per system checklist FNP-1-SOP-50.0A.4.1.10.3An RHT is aligned for service per FNP-1-SOP-2.4, CVCS BORON RECYCLE SYSTEM. 4.1.10.4Close the following RCDT vent line iso valves: RCDT VENT LINE ISO, Q1G21HV7126 (MCB)RCDT VENT LINE ISO, Q1G21HV7150 (MCB)NOTE: Reference FNP-0-ACP-36.0, COMPRESSED GAS SAFETY, as required, before performing steps involving a gas cylinder. (AI 2002202992) 4.1.10.5Verify the hydrogen bottle is attached to the supply line AND bottle isolation valves are open, THEN open H2bottle to RCDT ISO, N1G21V340. 4.1.10.6Close H2 SUPP TO RCDT, Q1G21V211 (1-LWP-V-7125). 4.1.10.7Open RCDT VENT, Q1G21V192 (1-LWP-V-7163). 4.1.10.8Establish excess letdown to RCDT per FNP-1-SOP-2.7, CVCS EXCESS LETDOWN. 4.1.10.9Start an RCDT pump and recirculate tank while tank is filling to ensure air is not entrapped in lines. 4.1.10.10WHEN water comes out of the vent, THEN stop the RCDT pump and close RCDT VENT, Q1G21V192 (1-LWP-V-7163). 4.1.10.11Remove excess letdown from service per FNP-1-SOP-2.7, CVCS EXCESS LETDOWN. 4.1.10.12Open H2 SUPP TO RCDT, Q1G21V211 (1-LWP-V-7125). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.10.13Verify open the following valves: RCDT VENT LINE ISO Q1G21HV7126 (MCB). RCDT VENT LINE ISO Q1G21HV7150 (MCB). 4.1.10.14Verify the following: H2 SUPP TO RCDT, Q1G21PCV7155 (Q1G21V063) is set to maintain 3.0 psig. GAS DISCH FROM RCDT, Q1G21PCV7152 (Q1G21V002) is set to maintain 6.0 psig. 4.1.10.15Start a RCDT pump. 4.1.10.16Regulate RCDT LCV, Q1G21LCV1003 (Q1G21V064) in manual to pump tank level down to 20%. 4.1.10.17IF needed, THEN place RCDT in normal operation per Section 4.1.IF NOT, stop the pump and close RCDT LCV, Q1G21LCV1003 (Q1G21V064). 4.1.10.18IF H2 supply to the RCDT is NOT to be maintained, THENclose the bottle isolation valves AND closeH2 BOTTLE TO RCDT ISO, N1G21V340. 4.1.11Establishing a Nitrogen Atmosphere in the RCDT (Burp Method): 4.1.11.1RCDT system is aligned per system checklist FNP-1-SOP-50.0A, REACTOR COOLANT DRAIN COLLECTION AND DISCHARGE, and is aligned for normal operation per FNP-1-SOP-50.0, LIQUID WASTE PROCESSING SYSTEM. 4.1.11.2The waste gas system is in service and capable of receiving gas from the RCDT. 4.1.11.3Close the following valves: RCDT VENT LINE ISO Q1G21HV7126 (MCB) RCDT VENT LINE ISO Q1G21HV7150 (MCB) 4.1.11.4Verify nitrogen bottle is attached to the supply line and bottle isolations are open (155' outside MSVR). 4.1.11.5Open nitrogen bottle to RCDT iso. N1G21V339 (155' outside MSVR) and close H2 bottle to RCDT iso. N1G21V340. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.11.6Ensure H2 supply to RCDT 1-LWP-PCV-7155 (Q1G21V063) and gas discharge from RCDT 1-LWP-PCV-7152 (Q1G21V002) are set to maintain 3.0 psig and 6.0 psig respectively. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: When filling the RCDT, the gas discharge valve from the RCDT should be set to maintain 3 psig Q1G21V003 (1-LWP-PCV-7152) RCDT DISCH TO WPS GAS SYSTEM and Q1G21V0063 (1-LWP-PCV-7155) H2 SUPP TO RCDT should be closed if RCDT pressure is 3 psig. This will allow H2 to be purged to the Waste Gas System. 4.1.11.7Verify open the following valves (outside MSVR). H2 supply to RCDT N1G21V285. RCDT PCV Root Iso. 1-LWP-V-7165 (Q1G21V062). H2 Supply to RCDT PCV Iso. 1-LWP-V-7154 (Q1G21V061).4.1.11.8Verify air cut in to H2 Supply to RCDT 1-LWP-PCV-7155 (Q1G21V063). 4.1.11.9Open RCDT Vent Line Iso. Q1G21HV7126. 4.1.11.10Open RCDT Vent Line Iso. Q1G21HV7150. 4.1.11.11Establish RCDT pressure of 8 psig by adjusting H2 supply to RCDT 1-LWP-V-7155 (Q1G21V063) as needed. IF pressure is raised, THEN verify N2 flow to the RCDT as evidenced by an increase in RCDT pressure and/or a decrease in N2 bottle pressure. WHEN RCDT pressure is at 8 psig, THEN adjust H2 supply to RCDT 1-LWP-V-7155 (Q1G21V063) to 0 psig. NOTES: Sampling of the RCDT is done in the 121' Piping Penetration Room. Sampling will not necessarily be done on the first burp, but should be performed on all subsequent burps. The sample should be obtained near the end of the burp to ensure that the sample obtained is representative of the RCDT atmosphere instead of being representative of the bulk N2 supply to the RCDT. An actual transfer of gas from the RCDT to the GDT must be in progress in order for Chemistry to take their sample. This evolution must be closely coordinated with Chemistry personnel. 4.1.11.12Notify Chemistry to be ready to sample the RCDT during the burp, if desired. 4.1.11.13Set the gas discharge from RCDT 1-LWP-PCV-7152 to maintain 3 psig (Q1G21V002). 4.1.11.14Verify RCDT LCV Q1G21LCV1003 is in MANUAL and closed. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: A level hose may be used to monitor level changes in the RCDT if the installed level transmitter is not functioning properly AND containment is accessible.4.1.11.15Perform the following to raise RCDT level to approximately 90% to purge gas from the RCDT to the Waste Gas System: a.Stop all operating RCDT pumps. b.Close RCDT Outlet Iso N1G21HV7127. c.Verify open RCDT Recirc Iso N1G21HV7144. d.Open RCDT to Waste Gas Compressor suction Q1G22V010 (100'El Aux Building). e.Open PRT Drain Iso. N1B31HV8031 (MCB). CAUTION: Monitor PRT pressure during drain to RCDT to ensure a positive pressure is maintained on the PRT. NOTE: IF it is necessary to use the RCDT pump to fill the RCDT per the following step, THEN the pump should be started and stopped as necessary to allow the gas from the RCDT atmosphere to bleed off to the waste gas system without overwhelming the waste gas compressor. f.IF gravity drain is NOT sufficient to transfer water from the PRT, THEN run a RCDT pump as needed per the above note. g.Monitor RCDT level, pressure, and waste gas decay tank pressure as the water transfer proceeds to ensure proper system response. h.Coordinate with Chemistry personnel to obtain sample, if required, per the note preceding Step 4.1.11.12. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: It may be necessary to fill the PRT to the normal level using FNP-1-SOP-1.2, Section 4.3 4.1.11.16WHEN RCDT level has been raised to approximately 90% and the RCDT GAS PRESS is approximately 3 psig, THENperform the following: a.Stop all operating RCDT pumps. b.Close PRT DRAIN ISO. N1B31V8031. (MCB) c.Close RCDT to WASTE GAS COMPRESSOR SUCTION Q1G22V010 (100' Aux Building). NOTE: Step 4.1.11.16.d and 4.1.11.16.e may be N/A'd if the RCDT can NOT be recirculated due to valve/pump problems, etc. d.Open RCDT OUTLET ISO. N1G21HV7127. NOTE: N2 PRESS may have to be added to the RCDT to operate the RCDT Pumps. e.Start a RCDT pump to recirc RCDT contents. f.WHEN burp is completed as indicated by RCDT pressure falling to 3 psig, THEN open H2 supply to RCDT 1-LWP-PCV-7155 (Q1G21V063) to maintain approximately 8 psig. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.1.11.17Begin lowering RCDT level to approximately 30%. NOTES: RCDT drain down rate should be slow enough that H2 SUPPLY TO RCDT 1-LWP-PCV-7155 (Q1G21V063) can maintain a positive RCDT pressure of 3 PSIG. Closely monitor RCDT pressure during drain down. Change out the N2 cylinder outside the MSVR as required. IF the RCDT can NOT be pumped down due to some problem, THEN drain the RCDT using Q1G21V207 RCDT DRN. a.Using the controller on the LWPP throttle open Q1G21LCV1003 to slowly lower RCDT level to 30%. b.WHEN RCDT level is approximately 30%, THEN closeQ1G21LCV1003 and stop the running RCDT pump. 4.1.11.18Repeat Step 4.1.11.11 through 4.1.11.17 until the hydrogen concentration is acceptable for chemical degas per Chemistry group requirements. 4.1.11.19WHEN N2 purge no longer required, THEN close N2 bottle to RCDT iso N1G21V339 (outside MSVR). 4.1.11.20Return setting of H2 supply to RCDT 1-LWP-PCV-7155 (Q1G21V063) and gas discharge from RCDT 1-LWP-PCV-7152 (Q1G21V002) to maintain 3.0 psig and 6 psig, respectively. 4.1.11.21Place MCB handswitch for RCDT LCV Q1G21LCV1003 to OPEN and allow to spring return to AUTO. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.2WHT OPERATION4.2.1WHT recirculation and sampling: 4.2.1.1WHT system is aligned per FNP-1-SOP-50.0B. 4.2.1.2Start waste evaporator feed pump. NOTE: Prior to discharge, the WHT must be sampled and the sample checked for chromates. 4.2.1.3Perform the following: a.Obtain a WHT sample from the test valve downstream of Q1G21V025, WEFP DISCH PI-1016 ROOT. b.Visuallycheck sample for chromates by placing a white sheet of paper behind the sample for comparison to verify water is clear with no yellow tint. 4.2.2WHT discharge to disposable demineralizer system: 4.2.2.1Proceed per FNP-0-SOP-50.7, LIQUID WASTE PROCESSING USING THE DISPOSABLE DEMINERALIZER SYSTEM. 4.2.3WHT discharge to the FDT: 4.2.3.1In the 139' filter room close WASTE EVAP FEED FILTER OUTLET, Q1G21V019 (1-LWP-V-7244). 4.2.3.2At the liquid waste panel start the waste evaporator feed pump. 4.2.3.3In the waste evaporator feed pump room open WEFP DISCH TO FDT ISO, Q1G21V027 (1-LWP-V-7240). 4.2.3.4In the waste evaporator feed pump room open WEFF INLET, Q1G21V020 (1-LWP-V-7239). 4.2.3.5WHEN WHT to FDT discharge is complete, THEN perform the following: a.Stop the waste evaporator feed pump. b.Close the WEFF INLET, Q1G21V020 (1-LWP-V-7239). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.2.3.6Close WEFP DISCH TO FDT ISO, Q1G21V027 (1-LWP-V-7240). 4.2.3.7Open WASTE EVAP FEED FILTER OUTLET, Q1G21V019 (1-LWP-V-7244). 4.2.4Draining the WHT to the FDT: NOTES: Health Physics coverage is required for the performance of this procedure due to the potential for contamination. Draining should be done at a controlled rate to reduce splashing and the spread of contamination. 4.2.4.1Verify that the waste evaporator feed pump is not running.4.2.4.2Verify that WEFF INLET, Q1G21V020 (1-LWP-V-7239) is closed. 4.2.4.3Verify closed WASTE GAS PROCESSING RM SUMP PUMPS DISCH TO WHT, N1G21V159A. 4.2.4.4Verify open WASTE GAS PROCESSING RM SUMP PUMPS DISCH TO FDT, N1G21V159B (located in the recombiner hallway). NOTE: Removing the drain grating will reduce splashing. Remove grating if possible. 4.2.4.5Slowlythrottle open the WHT DRN, Q1G21V029 (1-LWP-V-7234). 4.2.4.6Verify the waste gas processing room sump pump starts and is pumping down the sump as the WHT is being drained to it. IF the pumps are not keeping up with drain rate OR the drains back up, THEN secure draining immediately and contact HP and notify the control room. 4.2.4.7WHEN draining is complete, THEN close the WHT DRN, Q1G21V029 (1-LWP-V-7234) and have HP survey the area around the floor drain. 4.2.5Waste Evaporator Feed Filter Isolation for Filter Element Replacement: 4.2.5.1ProceedTo Appendix 8. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.3WECT OPERATIONS. 4.3.1WECT recirculation and sampling: 4.3.1.1WECT system is aligned per system checklist FNP-1-SOP-50.0B.4.3.1.2Close WECT INLET ISO, Q1G21V217 (1-LWP-V-7221). 4.3.1.3Start waste evaporator condensate tank pump. 4.3.1.4Notify the Shift Radio Chemist to obtain a sample. 4.3.1.5IF desired, THEN remove the tank from recirc by performing the following a.Stop the WASTE EVAPORATOR CONDENSATE TANK PUMP b.Open Q1G21V217 (1-LWP-V-7221), WECT INLET ISO4.3.2WECT discharge to RHT's: 4.3.2.1Waste evap condensate pump is on and in recirculation mode per 4.3.1. 4.3.2.2An RHT is aligned to receive tank contents per system checklist FNP-1-SOP-2.4A, CVCS BORON RECYCLE SYSTEM.4.3.2.3Open WECT PUMP DISCH TO RHT ISO, Q1G21V031 (1-LWP-V-7229). 4.3.2.4Open WASTE EVAP CNDS PUMP DISCH, Q1G21V230 (1-LWP-V-7225). 4.3.2.5WHEN discharge of WECT contents to RHT has been completed, THEN stop pump and perform the following:a.Close WECT PUMP DISCH TO RHT ISO, Q1G21V031 (1-LWP-V-7229). b.Close WASTE EVAP CNDS PUMP DISCH, Q1G21V230 (1-LWP-V-7225). 4.3.2.6Open WECT INLET ISO, Q1G21V217 (1-LWP-V-7221). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.3.3WECT discharge to WHT. 4.3.3.1WECT pump is on and in recirculation mode per 4.3.1. In the Filter Room: 4.3.3.2Open WASTE EVAP CNDS PUMP DISCH TO WHT, Q1G21V085 (1-LWP-V-7218). 4.3.3.3Open WASTE EVAP CNDS FILTER OUTLET, Q1G21V084 (1-LWP-V-7217). 4.3.3.4IF tank contents are to be routed through the waste evap condensate demineralizer, THEN perform the following.IF NOT, THEN ProceedTo Step 4.3.3.5. a.Open WASTE EVAP CNDS DEMIN INLET, Q1G21V086 (1-LWP-V-7203). b.Open WASTE EVAP CNDS DEMIN OUTLET, Q1G21V225 (1-LWP-V-7212). c.Close WASTE EVAP CNDS DEMIN BYPASS, Q1G21V216 (1-LWP-V-7213). In the WECT Room: 4.3.3.5Close WECT INLET ISO, Q1G21V217 (1-LWP-V-7221). 4.3.3.6Open the following valves: a.WASTE EVAP CNDS PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q1G21V087 (1-LWP-V-7232). b.WASTE EVAP CNDS PUMP DISCH, Q1G21V230 (1-LWP-V-7225). (Step 4.3.3 cont'd on next page) UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.3.3.7WHEN discharge of WECT is completed, THEN stop the pump and perform the following: In the Filter Room: a.IF tank contents were routed through the waste evap condensate demineralizer, THEN perform the following.IF NOT, THEN ProceedTo Step 4.3.3.7.b. Close WASTE EVAP CNDS DEMIN INLET, Q1G21V086 (1-LWP-V-7203). Close WASTE EVAP CNDS DEMIN OUTLET, Q1G21V225 (1-LWP-V-7212). Open WASTE EVAP CNDS DEMIN BYPASS, Q1G21V216 (1-LWP-V-7213). b.Close WASTE EVAP CNDS FILTER OUTLET, Q1G21V084 (1-LWP-V-7217). Close WASTE EVAP CNDS PUMP DISCH TO WHT, Q1G21V085 (1-LWP-V-7218). In the WECT Room: Open WECT INLET ISO, Q1G21V217 (1-LWP-V-7221). Close WASTE EVAP CNDS PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q1G21V087 (1-LWP-V-7232). Close WASTE EVAP CNDS PUMP DISCH, Q1G21V230 (1-LWP-V-7225). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.3.4WECT discharge to #2 WMT: 4.3.4.1WECT pump is on and in recirculation mode per 4.3.1. 4.3.4.2IF tank contents are to be routed through the WMT demineralizer, THEN perform the following.IF NOT, THEN ProceedTo Step 4.3.4.3. Open WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434) [demin valve area]. In the Filter Room: Close #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428). Open WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). Open FDT TO WMT DEMIN, Q1G21V091B (1-LWP-V-7452B). 4.3.4.3IF tank contents are to be routed through the waste evaporator condensate demineralizer, THEN perform the following.IF NOT, THEN proceed to Step 4.3.4.4. Open WASTE EVAP CNDS DEMIN INLET, Q1G21V086 (1-LWP-V-7203). Open WASTE EVAP CNDS DEMIN OUTLET, Q1G21V225 (1-LWP-V-7212). Close WASTE EVAP CNDS DEMIN BYP, Q1G21V216 (1-LWP-V-7213). 4.3.4.4Open WASTE EVAP CNDS FILTER OUTLET, Q1G21V084 (1-LWP-V-7217). 4.3.4.5Open WASTE EVAP CNDS TANK DISCH TO WMT, Q1G21V220 (1-LWP-V-7219). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 In the WECT Room: 4.3.4.6Verify closed WECT INLET ISO, Q1G21V217 (1-LWP-V-7221). 4.3.4.7Open the following valves: WASTE EVAP CNDS PUMP DISCH, Q1G21V230 (1-LWP-V-7225). WASTE EVAP CNDS PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q1G21V087 (1-LWP-V-7232). 4.3.4.8Estimate the time that the WMT tank will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%. (IR 2-96-167)4.3.4.9WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) CAUTION: The WECT is subject to siphoning when pumping to a WMT. Closing WASTE EVAP CNDS TANK DISCH TO WMT, Q1G21V220, after stopping the waste condensate pump will prevent possible overflowing of the WMT. 4.3.4.10WHEN discharge of WECT is completed, THEN stop the pump and perform the following: In the Filter Room:a.Close WASTE EVAP CNDS TANK DISCH TO WMT, Q1G21V220 (1-LWP-V-7219). (Filter Room)b.Close WASTE EVAP CNDS FILTER OUTLET, Q1G21V084 (1-LWP-V-7217). (Filter Room) c.IF tank contents were routed through the waste evap condensate demineralizer, THEN perform the following: IF NOT, proceed to Step 4.3.4.10.d. Close WASTE EVAP CNDS DEMIN INLET, Q1G21V086 (1-LWP-V-7203). Close WASTE EVAP CNDS DEMIN OUTLET, Q1G21V225 (1-LWP-V-7212). Open WASTE EVAP CNDS DEMIN BYP, Q1G21V216 (1-LWP-V-7213). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 d.IF WECT was routed through the WMT demineralizer, THENperform the following:IF NOT, THEN ProceedTo Step 4.3.4.10.f. Open #2 WMT DEMIN BYPASS, Q1G21V125 (1-LWP-V-7428). Close WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). Close FDT TO WMT DEMIN, Q1G21V091B (1-LWP-V-7452B). At the WMT Demin Valve area:e.IF the WECT contents were routed through the WMT demineralizer, THEN close WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434) [located at WMT demin valve area]. In the WECT Room: f.Close WASTE EVAP CNDS PUMP DISCH, Q1G21V230 (1-LWP-V-7225). g.Close WASTE EVAP CNDS PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q1G21V087 (1-LWP-V-7232). h.Open WECT INLET ISO, Q1G21V217 (1-LWP-V-7221). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.3.5WECT discharge to #1 WMT: 4.3.5.1WECT pump is on and in recirculation mode per 4.3.1. 4.3.5.2In the WMT pump room, close #2 WMT INLET ISO, Q1G21V135 (1-LWP-V-7429). 4.3.5.3IF tank contents are to be routed through the WMT demin, THEN perform the following.IF NOT, THEN ProceedTo Step 4.3.5.4. Open WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434) [WMT demineralizer valve area]. In the Filter Rooms: a. Close #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428) b. Close LHST DISCH TO #1 WMT ISO, Q1G21V089 (1-LWP-V-7412). c. Open WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). d. Open FDT TO WMT DEMIN, Q1G21V091B (1-LWP-V-7452B). e. ProceedTo Step 4.3.5.5. 4.3.5.4WHEN bypassing the WMT demineralizer, THEN perform the following: Open WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). Open WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). Close LHST DISCH TO #1 WMT ISO, Q1G21V089 (1-LWP-V-7412). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.3.5.5IF tank contents are to be routed through the waste evap condensate demineralizer, THEN perform the following.IF NOT, THEN proceedTo Step 4.3.5.6. Open WASTE EVAP CNDS DEMIN INLET, Q1G21V086 (1-LWP-V-7203). Open WASTE EVAP CNDS DEMIN OUTLET, Q1G21V225 (1-LWP-V-7212). Close WASTE EVAP CNDS DEMIN BYPASS, Q1G21V216 (1-LWP-V-7213). 4.3.5.6Open WASTE EVAP CNDS FILTER OUTLET, Q1G21V084 (1-LWP-V-7217). 4.3.5.7Open WASTE EVAP CNDS TANK DISCH TO WMT, Q1G21V220 (1-LWP-V-7219). In the Waste Evaporator Condensate Tank Room: 4.3.5.8Check closed WECT INLET ISO, Q1G21V217 (1-LWP-V-7221). 4.3.5.9Open the following valves: WASTE EVAP CNDS PUMP DISCH, Q1G21V230 (1-LWP-V-7225). WASTE EVAP CNDS PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q1G21V087 (1-LWP-V-7232). 4.3.5.10Estimate the time that the WMT tank will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%. (IR 2-96-167) 4.3.5.11WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) CAUTION: The WECT is subject to siphoning when pumping to a WMT. Therefore, upon stopping the waste evap condensate pump, steps 4.3.5.12 through 4.3.5.16 should be completed expeditiously. 4.3.5.12WHEN discharge of WECT is completed, THEN stop the pump and perform the following: In the Filter Room: UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 a.IF tank contents were routed through the waste evap condensate demin, THEN perform the following.IF NOT, THEN ProceedTo Step 4.3.5.12.b. Close WASTE EVAP CNDS DEMIN INLET, Q1G21V086 (1-LWP-V-7203). Close WASTE EVAP CNDS DEMIN OUTLET, Q1G21V225 (1-LWP-V-7212). Open WASTE EVAP CNDS DEMIN BYPASS, Q1G21V216 (1-LWP-V-7213). b.IF tank contents bypassed the waste evap condensate demin, THEN perform the following: Close WASTE EVAP CNDS FILTER OUTLET, Q1G21V084 (1-LWP-V-7217). Close WASTE EVAP CNDS TANK DISCH TO WMT, Q1G21V220 (1-LWP-V-7219). c.IF WECT was routed through the WMT demin, THEN perform the following.IF NOT, THEN ProceedTo Step 4.3.5.12.d. 1. Open #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428). 2. Close WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). 3. Close FDT TO WMT DEMIN, Q1G21V091B (1-LWP-V-7452B). 4. Open LHST DISCH TO #1 WMT ISO, Q1G21V089 (1-LWP-V-7412). 5.ProceedTo step 4.3.5.13. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 d.IF WECT contents bypassed WMT demineralizer, THENperform the following: Close WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). Open LHST DISCH TO #1 WMT ISO, Q1G21V089 (1-LWP-V-7412). Close WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). 4.3.5.13Close or verify closed WASTE EVAP CNDS FILTER OUTLET, Q1G21V084 (1-LWP-V-7217). 4.3.5.14Close or verify closed WASTE EVAP CNDS TANK DISCH TO WMT, Q1G21V220 (1-LWP-V-7219). 4.3.5.15IF tank contents were routed through the WMT demineralizer, THEN close WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434) (WMT demin valve area.) 4.3.5.16Close WASTE EVAP CNDS PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q1G21V087 (1-LWP-V-7232) (WECT room) 4.3.5.17Close WASTE EVAP CNDS PUMP DISCH, Q1G21V230 (1-LWP-V-7225) (WECT room). 4.3.5.18Open WECT INLET ISO, Q1G21V217 (1-LWP-V-7221) (WECT room). 4.3.5.19IF NOT on recirc per FNP-1-SOP-50.1 LIQUID WASTE PROCESSING SYSTEM LIQUID WASTE RELEASE FROM WASTE MONITOR TANK, THEN open #2 WMT INLET ISO, Q1G21V135 (1-LWP-V-7429) (WMT room). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.3.6WECT discharge to disposable demineralizer system: 4.3.6.1Proceed per FNP-0-SOP-50.7, LIQUID WASTE PROCESSING USING THE DISPOSABLE DEMINERALIZER SYSTEM. NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.3.7Draining the contents of a contaminated WECT: CAUTION: The WECT should not be drained to less than 5% to prevent admission of air under the diaphragm. 4.3.7.1Ensure sufficient capacity exists in the WHT to receive the contents to be drained from the WECT. 4.3.7.2IF the WECT is on recirc, THEN Go To step 4.3.1.5 and remove from recirc. 4.3.7.3Open the WECT DRN, Q1G21V235 (1-LWP-V-7223) to drain contents of WECT to the WHT. 4.3.7.4When WECT draining is completed, then close WECT DRN Q1G21V235 (1-LWP-V-7223). 4.3.7.5ProceedTo Section 4.2 for processing the WHT. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.4CDT OPERATION 4.4.1Draining the CDT to the WHT: 4.4.1.1Verify WHT level 30% and < 90%. 4.4.1.2Attach hose to CDT DRN, Q1G21V238 (1-LWP-V-7327) and route to equipment drain. 4.4.1.3Slowlyopen CDT DRN, Q1G21V238 (1-LWP-V-7327). 4.4.1.4Drain CDT to approximately 5-15% level. 4.4.1.5Close CDT DRN, Q1G21V238 (1-LWP-V-7327). 4.4.1.6Remove hose. NOTE: Two OPS personnel will be required for this task and a catch bag should be installed below the vent line to prevent the potential spread of contamination in case of overflow while applying air to the CDT. 4.4.2Unclogging the CDT Drain: 4.4.2.1Coordinate with HP for coverage. 4.4.2.2Verify closed CDT DRN, Q1G21V238. NOTE: In the following step, the purpose of the vent valve in line with the air hose is to allow pressure to be vented from the hose before disconnecting from the SA connection and the CDT drain. 4.4.2.3Obtain air hose with a flow restrictor and vent valve. 4.4.2.4Verify air hose vent valve closed. 4.4.2.5Connect air hose to the nearest SA connection. 4.4.2.6Connect air hose to the CDT DRN, Q1G21V238. 4.4.2.7Slowlythrottle open the SA ISO valve. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 CAUTION: Opening CDT DRN, Q1G21V238 too quickly or too far may result in blowing contaminated water out of the tank vent. Listen and feel for air flow through the drain line while throttling the valve open to prevent overflow of the tank. 4.4.2.8 Initiate air flow to dislodge the clog per the following: 4.4.2.8.1 Slowly throttle open Q1G21V238 to dislodge debris.4.4.2.8.2Monitor tank overflow and close Q1G21V238 if overflowing.4.4.2.8.3 WHEN air flow is heard through the drain line, THENclose Q1G21V238. 4.4.2.9 Close the SA ISO valve. 4.4.2.10 Perform the following: 4.4.2.10.1 Carefully vent the air hose using the air hose vent valve. 4.4.2.10.1Disconnect air hose from SA connection. 4.4.2.10.2Coordinate with HP for removal of air hose from drain line to check for proper draining. 4.4.2.11 Perform section 4.4.1 and check for proper draining. 4.4.2.12 IF no drain flow, THEN repeat steps 4.4.2.2 through 4.4.2.10 as necessary to clear line. 4.4.2.13 IF drain flow is adequate, THEN coordinate with HP for removal and storage of air hose and connections used. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.5FDT SYSTEM DISCHARGE CAUTION: IF it is known OR suspected that chromates are present in the FDT, THEN notify the Shift Chemist prior to transferring or processing the tank.4.5.1FDT Recirculation and Sampling: 4.5.1.1FDT system is aligned per system checklist FNP-1-SOP-50.0C.NOTES: Sampling is required prior to transferring waste between units, prior to direct transfer to a WMT, or if chromates or other chemicals are suspected of being in the source tank. Sampling may be waived with Chemistry concurrence if repetitive draining of a system is being performed and previous samples have been within limits. 4.5.1.2Start FDT pump and IF required, notify the Shift Radio Chemist to obtain sample. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 CAUTION: The contents of the FDT must be sampled and the sample analyzed prior to discharge to a WMT, unless waived per previous note. NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.5.2FDT discharge to #2 waste monitor tank (WMT): 4.5.2.1FDT pump is on and in recirculation mode as per 4.5.1. 4.5.2.2IF FDT contents are to be processed through the WMT demineralizer, THEN perform the following.IF NOT, THEN Proceed To Step 4.5.2.3. Open WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434) [WMT demineralizer valve area]. In the Filter Room: Close #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428). Open FDT TO WMT DEMIN, Q1G21V091B (1-LWP-V-7452B). Open WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). 4.5.2.3Close FDT DISCH TO WASTE EVAP, Q1G21V267 (1-LWP-V-7427). 4.5.2.4 Open FDT FILTER OUTLET, Q1G21V189 (1-LWP-V-7456). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 In the FDT Pump Room: 4.5.2.5Open FDT STRAINER DISCH, N1G21V118 (1-LWP-V-7421). 4.5.2.6Estimate the time that the WMT tank will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%. (IR 2-96-167)4.5.2.7WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) 4.5.2.8WHEN discharge of FDT is completed, THEN stop the pump and perform the following alignments: a.IF tank contents were routed through the WMT demineralizer, THEN perform the following.IF NOT, THEN ProceedTo Step 4.5.2.8.b. Close WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434) (At WMT demineralizer valve area).In the Filter Room: Open #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428). Close FDT TO WMT DEMIN, Q1G21V091B (1-LWP-V-7452B). Close WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). b.Close FDT FILTER OUTLET, Q1G21V189 (1-LWP-V-7456). c.Open FDT DISCH TO WASTE EVAP, Q1G21V267 (1-LWP-V-7427). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 In the FDT Pump Room: Close FDT STRAINER DISCH, N1G21V118 (1-LWP-V-7421). CAUTION: The contents of the FDT must be sampled and the sample analyzed prior to discharge to a WMT, unless waived per previous note. NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.5.3FDT discharge to #1 WMT: 4.5.3.1FDT pump is on and in recirculation mode per 4.5.1. 4.5.3.2IF FDT contents are to be processed through the WMT demineralizer, THEN perform the following.IF NOT, THEN Proceed To Step 4.5.3.3. Open WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434) (at WMT demin valve area). In the Filter Rooms: Close #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428). Open FDT TO WMT DEMIN, Q1G21V091B (1-LWP-V-7452B). Open WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). a.ProceedTo Step 4.5.3.5. 4.5.3.3Open WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). 4.5.3.4Open WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). 4.5.3.5Close FDT DISCH TO WASTE EVAP, Q1G21V267 (1-LWP-V-7427). 4.5.3.6Open FDT FILTER OUTLET, Q1G21V189 (1-LWP-V-7456). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 In the WMT Pump Room: 4.5.3.7Close #2 WMT INLET ISO, Q1G21V135 (1-LWP-V-7429). In the FDT Pump Room: 4.5.3.8Open FDT STRAINER DISCH, N1G21V118 (1-LWP-V-7421). 4.5.3.9Estimate the time that the WMT tank will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%.

(IR 2-96-167) 4.5.3.10WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%.  (IR 2-96-167) 4.5.3.11WHEN discharge of FDT is completed, THEN stop the pump and perform the following alignments: a.IF tank contents were routed through the WMT demineralizer, THEN perform the following.IF NOT, THEN ProceedTo Step 4.5.3.12. Close WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434) (at WMT demineralizer valve area).In the Filter Rooms: Open #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428). Close FDT TO WMT DEMIN, Q1G21V091B (1-LWP-V-7452B). Close WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). b.ProceedTo Section 4.5.3.14. 4.5.3.12Close WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). 4.5.3.13Close WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A).

UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.5.3.14Perform the following: Close FDT FILTER OUTLET, Q1G21V189 (1-LWP-V-7456). Open FDT DISCH TO WASTE EVAP, Q1G21V267 (1-LWP-V-7427) In the WMT Pump Room: 4.5.3.15IF NOT on recirc per FNP-1-SOP-50.1 LIQUID WASTE PROCESSING SYSTEM LIQUID WASTE RELEASE FROM WASTE MONITOR TANK, THEN open #2 WMT INLET ISO, Q1G21V135 (1-LWP-V-7429). In the FDT Pump Room: 4.5.3.16Close FDT STRAINER DISCH, N1G21V118 (1-LWP-V-7421). 4.5.4FDT discharge to WHT: 4.5.4.1FDT pump is on and in recirculation mode per 4.5.1. In the Filter Room: 4.5.4.2Close FDT DISCH TO WASTE EVAP, Q1G21V267 (1-LWP-V-7427). 4.5.4.3Open FDT DISCHARGE TO WHT, Q1G21V123 (1-LWP-V-7426). In FDT Pump Room: 4.5.4.4Open FDT STRAINER DISCH, N1G21V118 (1-LWP-V-7421). 4.5.4.5WHEN discharge of the FDT is completed, THEN stop the pump and perform the following alignment: In the Filter Room: Close FDT discharge to WHT 1-LWP-V-7426 (Q1G21V123).Open FDT disch to waste evap 1-LWP-V-7427 (Q1G21V267)In the FDT Pump Room: Close FDT STRAINER DISCH, N1G21V118 (1-LWP-V-7421). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.5.5FDT discharge to disposable demineralizer: 4.5.5.1ProceedTo FNP-0-SOP-50.7, LIQUID WASTE PROCESSING USING THE DISPOSABLE DEMINERALIZER SYSTEM. 4.5.6Floor Drain Tank Filter Isolation for Filter Element Replacement: 4.5.6.1ProceedTo Appendix 2. 4.5.7Floor Drain Tank Strainer Isolation for Basket Cleaning or Replacement: 4.5.7.1ProceedTo Appendix 3 4.6#1(2) WASTE MONITOR TANK OPERATION. 4.6.1#1(2) Waste Monitor Tank recirculation and sampling for discharge to the environment: 4.6.1.1Perform FNP-1-SOP-50.1 APPENDIX 1(2) WASTE MONITOR TANK 1(2) RELEASE TO THE ENVIRONMENT.NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.6.2#1(2) WMT discharge to WHT: 4.6.2.1Close #1(2) WMT INLET ISO, Q1G21V090 (Q1G21V135).4.6.2.2Verify closed, #1(2) WMT PUMP DISCH, N1G21V108B (N1G21V108A). 4.6.2.3Start #1(2) WMT Pump. In the Filter Rooms: 4.6.2.4Close FDT DISCH TO WASTE EVAP, Q1G21V267 (1-LWP-V-7427). 4.6.2.5Open FDT DISCHARGE TO WHT, Q1G21V123 (1-LWP-V-7426). In the WMT Pump Room: 4.6.2.6Open #1(2) WMT DISCH TO FDT, Q1G21V115 (Q1G21V266).4.6.2.7Open #1(2) WMT PUMP DISCH, N1G21V108B (N1G21V108A).4.6.2.8WHEN discharge of tank contents is completed, THEN stop the #1(2) waste monitor tank pump and perform the following: UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 In the Filter Room: Close FDT DISCHARGE TO WHT, Q1G21V123 (1-LWP-V-7426). Open FDT DISCH TO WASTE EVAP, Q1G21V267 (1-LWP-V-7427). In the WMT Pump Room: Close #1(2) WMT DISCH TO FDT, Q1G21V115 (Q1G21V266).Close #1(2) WMT PUMP DISCH, N1G21V108B (N1G21V108A).Open #1(2) WMT INLET ISO, Q1G21V090 (Q1G21V135). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.6.3#1(2) WMT discharge to Unit 2 #1(2) WMT: 4.6.3.1Close #1(2) WMT INLET ISO, Q1G21V090 (Q1G21V135).4.6.3.2Verify closed, #1(2) WMT PUMP DISCH, N1G21V108B (N1G21V108A). 4.6.3.3Start #1(2) WMT Pump. 4.6.3.4Close DISPOSABLE DEMIN SYS INLET FROM WHT & FDT, N2G21V345. NOTE: The following Step will flush contaminated water out of Disposable Demineralizer system inlet piping to Unit 2 WHT. 4.6.3.5Open Unit 2 FLOOR DRN TANK DISCH TO WHT, Q2G21V123 (2-LWP-V-7426). 4.6.3.6Open #1(2) WMT DISCH TO FDT, Q1G21V115 (Q1G21V266).4.6.3.7Open #1(2) WMT PUMP DISCH, N1G21V108B (N1G21V108A).a.Flush approximately 100-200 gallons (2-4% level) from the Unit 1 WMT to the Unit 2 WHT then close Unit 2 FLOOR DRN TANK DISCH TO WHT, Q2G21V123 (2-LWP-V-7426). b.Close the inlet to the WMT that is NOT to be filled, Unit 2 #1(2) WMT INLET ISO, Q2G21V090 (Q2G21V135).c.Open Unit 2 FLOOR DRAIN TANK FILTER OUTLET Q2G21V189 (2-LWP-V-7456) to start discharge to Unit 2 #1(2) WMT. 4.6.3.8Estimate the time that the WMT tank will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%.

(IR 2-96-167) 4.6.3.9WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%.  (IR 2-96-167)

UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.6.3.10WHEN discharge of tank contents is complete, THEN stop #1(2) Waste Monitor Pump and perform following: Close #1(2) WMT DISCH TO FDT, Q1G21V115 (Q1G21V266).Close #1(2) WMT PUMP DISCH, N1G21V108B (N1G21V108A).Close Unit 2 FLOOR DRAIN TANK FILTER OUTLET Q2G21V189 (2-LWP-V-7456). Open DISPOSABLE DEMIN SYS INLET FROM WHT & FDT, N2G21V345. Open the inlet to the WMT that was closed in Step 4.6.3.7.b, Unit 2 #1(2) WMT INLET ISO, Q2G21V090 (Q2G21V135). Open #1(2) WMT INLET ISO, Q1G21V090 (Q1G21V135).4.6.4#1(#2)WMT discharge to disposable demineralizer system: 4.6.4.1Proceed per FNP-0-SOP-50.7, LIQUID WASTE PROCESSING USING THE DISPOSABLE DEMINERALIZER SYSTEM. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.7#1(2) WMT RECIRCULATION THROUGH THE WMT DEMINERALIZER. 4.7.1ReferTo FNP-1-SOP-50.1, LIQUID WASTE PROCESSING SYSTEM LIQUID WASTE RELEASE FROM WASTE MONITOR TANK.4.8EDUCTING DIAPHRAGM ON WECT. 4.8.1Verify Waste Evaporator Condensate Tank aligned to receive water per FNP-0-SOP-50.7, LIQUID WASTE PROCESSING USING THE DISPOSABLE DEMINERALIZER SYSTEM. 4.8.2Attach Tygon hose from WASTE EVAP CNDS TANK VENT, Q1G21V354.4.8.2.1Verify routed to polybottle or to WHT via drain header. 4.8.2.2WHEN hose has been routed, THEN open WASTE EVAP CNDS TANK VENT, Q1G21V354. 4.8.3Proceed with water transfer per FNP-0-SOP-50.7, LIQUID WASTE PROCESSING USING THE DISPOSABLE DEMINERALIZER SYSTEM, until air-free water emitted from vent valve. 4.8.4Immediately close WASTE EVAP CNDS TANK VENT, Q1G21V354 andsecure input to Waste Evaporator Condensate tank per FNP-0-SOP-50.7, LIQUID WASTE PROCESSING USING THE DISPOSABLE DEMINERALIZER SYSTEM. 4.8.5Disconnect vent rig from WASTE EVAP CNDS TANK VENT, Q1G21V354. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.9LHST OPERATION 4.9.1LHST recirculation: 4.9.1.1LHST system is aligned per system checklist FNP-1-SOP-50.0E.4.9.1.2Start the LHST pump and recirculate tank contents. NOTES: #1 WMT is the normal path for the LHST and sampling is not routinely performed. Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non-source and non-destination tanks. CR# 20101023584.9.2LHST discharge to #1 WMT: 4.9.2.1LHST pump is on and in recirculation mode per 4.9.1. 4.9.2.2IF LHST contents are to be routed through the WMT demineralizer, THEN perform the following.IF NOT, THEN proceedTo Step 4.9.2.3. a.Close LHST DISCH TO #1 WMT ISO, Q1G21V089 (1-LWP-V-7412). b.Open LAUNDRY & HOT SHOWER TANK TO WMT DEMIN, Q1G21V091A (1-LWP-V-7452A). c.Open WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). d.Open WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434). 4.9.2.3Open LHST PUMP DISCH STRAINER OUTLET ISO, N1G21V084 (1-LWP-V-7407). 4.9.2.4Estimate the time that the WMT tank will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%.

(IR 2-96-167)

UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.9.2.5WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) 4.9.2.6WHEN discharge of LHST is completed, THEN stop the pump and perform the following alignments: a.IF tank contents were routed through the waste monitor tank demineralizer, THEN perform the following.IF NOT, THEN ProceedTo Step 4.9.2.7. Open LHST DISCH TO #1 WMT ISO, Q1G21V089 (1-LWP-V-7412). Close WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434). Close LAUNDRY & HOT SHOWER TANK TO WMT DEMIN, Q1G21V091A (1-LWP-V-7452A). Close WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). 4.9.2.7Close LHST PUMP DISCH STRAINER OUTLET ISO, N1G21V084 (1-LWP-V-7407). UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.9.3LHST discharge to #2 WMT: NOTES: Transferring the LHST to the #2 WMT is not a normal operation, and should be used only in an emergency, with SS permission. Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non-source and non-destination tanks. CR# 20101023584.9.3.1LHST pump is on and in recirculation mode as per 4.9.1. 4.9.3.2IF LHST contents are to be routed through the WMT demineralizer, THEN perform the following:IF NOT, THEN ProceedTo Step 4.9.3.3. a.Open LAUNDRY & HOT SHOWER TANK TO WMT DEMIN, Q1G21V091A (1-LWP-V-7452A). b.Open WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B) c.Open WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434) d.ProceedTo Step 4.9.3.5. 4.9.3.3Open WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). 4.9.3.4Open WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). 4.9.3.5Close #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428). 4.9.3.6Close #1 WMT INLET ISO, Q1G21V090 (1-LWP-V-7413). 4.9.3.7Open LHST PUMP DISCH STRAINER OUTLET ISO, N1G21V084 (1-LWP-V-7407). 4.9.3.8Estimate the time that the WMT tank will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%.

(IR 2-96-167) 4.9.3.9WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%.  (IR 2-96-167)

UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.9.3.10WHEN discharge of LHST is completed, THEN stop the pump and perform the following alignments: a.IF tank contents were routed through the WMT demineralizer, THEN perform the following:IF NOT, THEN ProceedTo Step 4.9.3.11. Close LAUNDRY & HOT SHOWER TANK TO WMT DEMIN, Q1G21V091A (1-LWP-V-7452A). Close WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). Close WMT DEMIN OUTLET, Q1G21V094 (1-LWP-V-7434). b.ProceedTo Step 4.9.3.13. 4.9.3.11Close WMT DEMIN DISCH TO #1 WMT, Q1G21V093A (1-LWP-V-7438A). 4.9.3.12Close WMT DEMIN DISCH TO #2 WMT, Q1G21V093B (1-LWP-V-7438B). 4.9.3.13Open #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428). 4.9.3.14Open #1 WMT INLET ISO, Q1G21V090 (1-LWP-V-7413). 4.9.3.15Close LHST PUMP DISCH STRAINER OUTLET ISO, N1G21V084 (1-LWP-V-7407). 4.9.4LHST Strainer Isolation for Basket Cleaning or Replacement: 4.9.4.1ProceedTo Appendix 4.0. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 4.10MANUALLY DRAINING REFUELING CAVITY TO CTMT SUMP: 4.10.1Verify the following valves CLOSED: FUEL TRANSFER CANAL DRN, N1G21V172 REFUELING CANAL DRAIN, N1G21V021 (1-LWP-V-7129). 4.10.2Provide for leakage collection and HP coverage, then remove blind flange on cavity drain valve. 4.10.3Attach flange with nipple to drain line using existing gasket. 4.10.4Attach drain hose to nipple and route to strainer/filter container or sock filter supplied by Health Physics Support. NOTE: The hose needs to be placed in the drain trough close to the drain pipe to the CTMT sump to prevent potential contamination problems. The drain pipe is located at the area by "C" S/G. 4.10.5Attach drain hose to strainer/filter container and route to drain (CTMT sump). 4.10.6With Health Physics Support coverage, throttle open FUEL TRANSFER CANAL DRN, N1G21V172 to prevent strainer/filter container from overflowing. NOTE: Ensure all loose particles are being removed by ensuring only clean water is flowing from strainer/filter to CTMT sump. 4.10.7WHEN draining is completed, THEN close FUEL TRANSFER CANAL DRN, N1G21V172. 4.10.8With HP coverage provided, remove drain flange and reinstall blind flange on drain line. 4.10.9Have Health Physics Support store drain flange with strainer/ filter container. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.11ALTERNATE PROCESSING OF THE FDT TO THE WHT. 4.11.1Procure a 6" S/S flange with a 6" long x 2" nipple 4.11.2Attach a 10' x 2" drain hose to the nipple flange. 4.11.3Remove the existing blind flange and install the above described drain flange downstream of the FDT DRAIN, Q1G21V130 (1-LWP-V-7414). 4.11.4Route hose to floor drain. 4.11.5Align the Waste Gas Processing Room pumps discharge to the alternate tank (WHT) per FNP-1-SOP-50.2, LIQUID WASTE PROCESSING SYSTEM SUMP PUMP SYSTEM OPERATION. 4.11.6Notify HP of the intent to drain the FDT to the floor drain system. NOTE: Monitor the WHT level and sump operation to ensure satisfactory results. 4.11.7Open or throttle open FDT DRAIN, Q1G21V130 (1-LWP-V-7414) anddrain the FDT as desired. 4.11.8WHEN the desired level in the FDT OR WHT is reached, THEN closeFDT DRAIN, Q1G21V130 (1-LWP-V-7414). 4.11.9WHEN the normal method of processing the FDT is available, THEN realign the Waste Gas Processing Room sump pump discharge to the normal tank (FDT) per FNP-1-SOP-50.2, LIQUID WASTE PROCESSING SYSTEM SUMP PUMP SYSTEM OPERATION. 4.11.10Remove temporary drain flange and replace blind flange.4.11.11Bluetag and return the drain flange and hose to the SFP Storage Room. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.12DRAINING THE CASK WASH AREA TO THE FDT. 4.12.1Verify sufficient capacity in the FDT and the System Operator is aware of the evolution. (CASK wash area, 31,000 gallon capacity) 4.12.2Verify any additional draining evolutions planned concurrently with draining the Cask Wash area have been evaluated to ensure the floor drain system will not be overloaded. NOTES: The CASK WASH ROOM DRAIN TO FDT ISO N1G21V927 is a 6 inch valve. Depending on circumstances significant opening of this valve can overload the floor drains and cause them to back up onto the floor potentially spreading contamination. The CASK WASH ROOM DRAIN TO FDT ISO N1G21V927 is located in the 121' batching area approximately 15 feet above floor level and will require a ladder or scaffolding for access. It is desirable to have an additional individual monitor the 100' elevation floor drains adjacent to the boric acid pumps while establishing the draining rate. 4.12.3Slowlyopen CASK WASH ROOM DRAIN TO FDT ISO N1G21V927 in approximately 1/4 turn increments. 4.12.4Allow sufficient time to ensure drain rate equilibrium is obtained while monitoring the 121' elevation floor drain at the batching funnel and the 100' elevation floor drains adjacent to the boric acid transfer pumps and in the hallway adjacent to the charging pump suction valves. 4.12.5Continue slowly opening CASK WASH ROOM DRAIN TO FDT ISO N1G21V927 in approximately 1/4 turn increments until an acceptable drain rate is obtained without backup through the floor drains.4.12.6WHEN the cask wash area draining is complete, THEN close CASK WASH ROOM DRAIN TO FDT ISO N1G21V927. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 Version 75.0 5.0RECORDSQARecord(X)Non-QARecord (X) Record Generated Retention Time R-Type X FNP-1-SOP-50.0 Life of plant HH6.051

6.0REFERENCES

6.1Drawings P&ID-l75042 sheets l Waste Processing System 6.2Westinghouse System Description SD-ALA-407 6.3Westinghouse Technical Manual U-258243. 6.4PCN B85-1-3124 Educting Diaphragm on WECT 6.5Drawings B-175787 Liquid Waste Instrument Loop Diagrams. 6.6PCN S90-1-6414 PORV N2 and RCDT H2/N2 drawing revisions. 6.7RER Number 03 306 (AI 2003203123) UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 1 Version 74.0 APPENDIX 1 MEASUREMENT OF FLOOR DRAIN TANKPUMP RECIRC LINE FLOW Performed by: DateReviewed by: DateThis appendix consists of 5 pages UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 1 Page 1 of 5 Version 75.0 APPENDIX 1 MEASUREMENT OF FLOOR DRAIN TANK PUMP RECIRC LINE FLOW 1.0 Verify the following (OR 1-98-498): The version of this procedure has been verified to be the current version. (OR 1-98-498) This procedure has been verified to be the correct procedure and unit for the task. (OR 1-98-498) 2.0INITIAL CONDITIONS 2.1 The FDT has been sampled and meets the requirements to be transferred to either WMT or the WHT. 2.2 The floor drain tank has sufficient volume to permit transferring water to the #1 WMT, the #2 WMT and the WHT as required for the purpose of calculating recirculation flow rates. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 1 Page 2 of 5 Version 75.0 NOTES: The optimum differential pressure for the FDT pump on recirculation is < 111 PSID. The optimum differential pressure for the FDT pump in a discharge alignment is > 88 PSID and < 108 PSID. 3.0INSTRUCTIONS 3.1 VerifyFDT pump is secured. 3.2 Unlock and close FDT PUMP RECIRC N1G21V128 (Master Key). 3.3 Open FDT PUMP RECIRC N1G21V128 to approximately half open (this should be equal to ~5/16" rise in the valve stem. 3.4 Record FDT level 3.5 Calculate FDT pump suction pressure as follows: pressureSuctiong2.31ft/psift85.11100level tank % ft/psig2.31ft85.11100 3.6 Verify the FDT pump started and record the following: FDT pump discharge pressure(PI-1090) 3.7 Using the discharge pressure recorded above and the suction pressure calculated in Step 3.5, determine FDT pump differential pressure. pressure)aldifferenti(Pumppressure)(Suctionpressure)(Discharge 3.8 Adjust FDT PUMP RECIRC N1G21V128 as necessary to obtain a pump differential pressure < 111 PSID. 3.9 Using the guidance contained in Section 4.5.2, align the FDT to discharge to the #2 WMT for the purpose of collecting pump differential pressure. 3.10 Record FDT level UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 1 Page 3 of 5 Version 75.0 3.11 Calculate FDT pump suction pressure as follows: pressureSuctiong2.31ft/psift85.11100level tank % ft/psig2.31ft85.11100 3.12 Verify the FDT pump started and record the following: FDT pump discharge pressure(PI-1090) 3.13 Using the discharge pressure recorded above and the suction pressure calculated in Step 3.11, determine FDT pump differential pressure. pressure)aldifferenti(Pumppressure)(Suctionpressure)(Discharge 3.14 IF necessary, THEN adjust FDT PUMP RECIRC N1G21V128 to obtain a pump differential pressure > 88 PSID but < 108 PSID. 3.15 After the data has been collected, secure per Section 4.5.2.8. 3.16 Using the guidance contained in Section 4.5.3, align the FDT to discharge to the #1 WMT for the purpose of collecting pump differential pressure. 3.17 Record FDT level 3.18 Calculate FDT pump suction pressure as follows: pressureSuctiong2.31ft/psift85.11100level tank % ft/psig2.31ft85.11100 3.19 Verify the FDT pump started and record the following: FDT pump discharge pressure(PI-1090) UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 1 Page 4 of 5 Version 75.0 3.20 Using the discharge pressure recorded above and the suction pressure calculated in Step 3.18, determine FDT pump differential pressure. pressure)aldifferenti(Pumppressure)(Suctionpressure)(Discharge 3.21 IF necessary, THEN adjust FDT PUMP RECIRC N1G21V128 to obtain a pump differential pressure > 88 PSID but < 108 PSID. 3.22 After the data has been collected, secure per Section 4.5.3.11 through 4.5.3.16. 3.23 Using the guidance contained in Section 4.5.4, align the FDT to discharge to the WHT for the purpose of collecting pump differential pressure. 3.24 Record FDT level 3.25 Calculate FDT pump suction pressure as follows: pressureSuctiong2.31ft/psift85.11100level tank % ft/psig2.31ft85.11100 3.26 Verify the FDT pump started and record the following: FDT pump discharge pressure(PI-1090) 3.27 Using the discharge pressure recorded above and the suction pressure calculated in Step 3.25, determine FDT pump differential pressure. pressure)aldifferenti(Pumppressure)(Suctionpressure)(Discharge 3.28 IF necessary, THEN adjust FDT PUMP RECIRC N1G21V128 to obtain a pump differential pressure > 88 PSID but < 108 PSID. 3.29 After the data has been collected, secure per Section 4.5.4.5. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 1 Page 5 of 5 Version 75.0 3.30 IF FDT PUMP RECIRC N1G21V128 was adjusted in steps 3.14, 3.21 OR 3.28, THENperform the following, otherwise ProceedTo Step 3.31: 3.30.1 Record FDT level 3.30.2 Calculate FDT pump suction pressure as follows: pressureSuctiong2.31ft/psift85.11100level tank % ft/psig2.31ft85.11100 3.30.3 Verify the FDT pump started and record the following: FDT pump discharge pressure(PI-1090) 3.30.4 Using the discharge pressure recorded above and the suction pressure calculated in Step 3.30.2, determine FDT pump differential pressure. pressure)aldifferenti(Pumppressure)(Suctionpressure)(Discharge 3.30.5 Verify pump differential pressure < 111 PSID. 3.31 Install locking device on FDT PUMP RECIRC N1G21V128. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 2 Version 75.0 APPENDIX 2 FLOOR DRAIN TANK FILTER ISOLATION Performed by: DateReviewed by: DateThis appendix consists of 3 pages UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 2 Page 1 of 3 Version 75.0 APPENDIX 2 FLOOR DRAIN TANK FILTER ISOLATION NOTES: This Appendix is only good for filter replacement on the shift it was performed. Each Step must be signed off immediately after completion of that step. 1.0PURPOSE: 1.1 To provide guidance for isolating the Floor Drain Tank Filter for filter element replacement. 2.0 Verify the following (OR 1-98-498): 2.1 The version of this procedure has been verified to be the current version. (OR 1-98-498) 2.2 This procedure has been verified to be the correct procedure and unit for the task. (OR 1-98-498) 3.0INITIAL CONDITIONS: 3.1 Perform this appendix when notified that Maintenance is ready to change the filter. This will prevent the filter from drying out. 4.0PRECAUTION AND LIMITATIONS: 4.1 This Appendix is only good for filter replacement on the shift it was performed. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 2 Page 2 of 3 Version 75.0 5.0INSTRUCTIONS: 5.1 Record the work order number associated with the current filter replacement. WO #_________________ 5.2 Isolate Floor Drain Tank Filter as follows: 5.2.1 Verify closed FDT FILTER OUTLET, Q1G21V189. (139' Floor Drain Tank Filter room) 5.2.2 Close FDT FILTER INLET, Q1G21V120.(139' Floor Drain Tank Filter room) 5.2.3 Verify closed FDT DISCH TO WHT, Q1G21V123. (139' Floor Drain Tank Filter room) 5.2.4 Close FDT DISCH TO WASTE EVAP, Q1G21V267. (139' Floor Drain Tank Filter room) 5.2.5 Open FDT FILTER DRN, Q1G21V121A.(139' Floor Drain Tank Filter room) 5.2.6 Open FDT FILTER DRN, Q1G21V121B.(139' Floor Drain Tank Filter room) 5.2.7 Open FDT FILTER VENT, Q1G21V122.(139' Floor Drain Tank Filter room) 5.2.8 IF maintenance is (will be) delayed and work has not (will not be) started on the current shift, THEN restore the lineup to an in service configuration starting at Step 5.3.1, OR have the system configuration documented with a Tagout. 5.2.9 Notify SS that FDT filter has been replaced with new o-ring and lid MAINT torqued to 100 in lb. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 2 Page 3 of 3 Version 75.0 NOTE: IF the FDT filter was tagged in Step 5.2.8 THEN the rest of this appendix is N/A. 5.3 WHEN maintenance has completed the filter replacement, THEN return the Floor Drain Tank Filter to service as follows: 5.3.1 Close FDT FILTER VENT, Q1G21V122.(139' Floor Drain Tank Filter room) 5.3.2 Close FDT FILTER DRN, Q1G21V121B.(139' Floor Drain Tank Filter room) 5.3.3 Close FDT FILTER DRN, Q1G21V121A.(139' Floor Drain Tank Filter room) 5.3.4 Open FDT DISCH TO WASTE EVAP, Q1G21V267. (139' Floor Drain Tank Filter room) 5.3.5 Verify closed FDT DISCH TO WHT, Q1G21V123. (139' Floor Drain Tank Filter room) 5.3.6Open FDT FILTER INLET, Q1G21V120.(139' Floor Drain Tank Filter room) 5.3.7 Verify closed FDT FILTER OUTLET, Q1G21V189.(139' Floor Drain Tank Filter room) UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 3 Version 75.0 APPENDIX 3 FLOOR DRAIN TANK STRAINER ISOLATION Performed by: DateReviewed by: DateThis appendix consists of 2 pages UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 3 Page 1 of 2 Version 75.0 APPENDIX 3 FLOOR DRAIN TANK STRAINER ISOLATION 1.0PURPOSE: 1.1 To provide guidance for Floor Drain Tank Strainer basket cleaning or replacement. 2.0Verify the following (OR 1-98-498): 2.1 The version of this procedure is the current version. 2.2 This procedure is the correct unit for the task. 3.0INITIAL CONDITIONS: 3.1 Floor Drain Tank Pump is tagged out. 4.0INSTRUCTIONS: 4.1 Verify Floor Drain Tank Pump has been tagged out with the following minimum electrical isolation:Pump hand switch N1G21P007-N LWPP H/S tagged in the pull-to-lock position.Motor 600V supply breaker FE-C5 open and tagged. 4.2 Verify closed FDT STRAINER DISCH, N1G21V118. (83' FDT pump room) 4.3 Close FDT PUMP SUCT, Q1G21V131. (83' FDT pump room) 4.4 Open FDT STRAINER DRN, Q1G21V268. (83' FDT pump room) 4.5 Open FDT STRAINER VENT, Q1G21V132. (83' FDT pump room) UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 3 Page 2 of 2 Version 75.0 4.6 WHEN the strainer has been drained, THEN perform the following: 4.6.1 Slowly loosen and remove the four, 1/2" nuts holding the strainer cover in place. 4.6.2 Remove strainer cover. 4.6.3 Remove and clean the strainer basket. 4.6.4 Re-install the strainer basket. 4.6.5 Inspect strainer gasket for damage. NOTE: For a new strainer gasket use Red Rubber Gasket Material 1/8" Stock # 0000000014426. 4.6.6 IF required, THEN have maintenance cut a new strainer gasket. 4.6.7 Re-install strainer gasket and cover. 4.6.8 Replace the four 1/2" nuts and tighten. 4.7 Close FDT STRAINER VENT, Q1G21V132. 4.8 Close FDT STRAINER DRN, Q1G21V268. 4.9 Verify closed FDT STRAINER DISCH, N1G21V118. 4.10 Open FDT PUMP SUCT, Q1G21V131. 4.11 Notify SSS that strainer cleaning is complete, in order to have the removal Section of the FDT pump tagout prepared.

5.0REFERENCES

5.1 Drawing D175042/4 5.2 Drawing U-183750 5.3 List of Materials U-183751 UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 4 Version 75.0 APPENDIX 4 LAUNDRY AND HOT SHOWER DRAIN TANK STRAINER ISOLATION Performed by: DateReviewed by: DateThis appendix consists of 2 pages UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 4 Page 1 of 2 Version 75.0 APPENDIX 4 LAUNDRY AND HOT SHOWER DRAIN TANK STRAINER ISOLATION 1.0PURPOSE: 1.1 To provide guidance for Laundry and Hot Shower Tank, Strainer basket cleaning or replacement. 2.0Verify the following (OR 1-98-498): 2.1 The version of this procedure is the current version. 2.2 This procedure is the correct unit for the task. 3.0INITIAL CONDITIONS: 3.1 Laundry and Hot Shower Tank Pump is tagged out. 4.0INSTRUCTIONS: 4.1 Verify Laundry and Hot Shower Tank Pump has been tagged out with the following minimum isolation: Pump hand switch N1G21P004-LWPP H/S tagged in the pull-to-lock position. Motor 600V supply breaker FE-D2 open and tagged. LHST PUMP SUCT ISO, Q1G21V247 closed and tagged. 4.2 Verify closed LHST PUMP DISCH STRAINER OUTLET ISO, N1G21V084. (100' Chem Drain Tank room) 4.3 Open LHST PUMP DISCH STRAINER DRAIN, Q1G21V265.(100' Chem Drain Tank room) 4.4 Open LHST PUMP DISCH STRAINER VENT, Q1G21V250.(100' Chem Drain Tank room)

UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 4 Page 2 of 2 Version 75.0 4.5 WHEN the strainer has been drained, THEN perform the following: 4.5.1 Slowly loosen and remove the four, 1/2" nuts holding the strainer cover in place. 4.5.2 Remove strainer cover. 4.5.3 Remove and clean the strainer basket. 4.5.4 Re-install the strainer basket. 4.5.5 Inspect strainer gasket for damage. NOTE: For a new strainer gasket use Red Rubber Gasket Material 1/8" Stock # 014426. 4.5.6 IF required, THEN have maintenance cut a new strainer gasket. 4.5.7 Re-install strainer gasket and cover. 4.5.8 Replace the four 1/2" nuts and tighten. 4.6 Close LHST PUMP DISCH STRAINER VENT, Q1G21V250. 4.7 Close LHST PUMP DISCH STRAINER DRAIN, Q1G21V265 4.8 Verify closed LHST PUMP DISCH STRAINER OUTLET ISO, N1G21V084. 4.9 Notify SSS that strainer cleaning is complete, in order to have the removal Section of the FDT pump tagout prepared.

5.0REFERENCES

5.1 Drawing D175042/4 5.2 Drawing D-175354 5.3 Drawing U-183748 5.4 List of Materials U-183749 UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 5 Version 75.0 FARLEY NUCLEAR PLANT UNIT 1 APPENDIX 5 PROCESSING FDT USING TEMPORARY DEMIN LINER Completed By Date Reviewed By Date This appendix consists of 6 pages.

UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 5 Page 1 of 6 Version 75.0 PROCESSING FDT USING TEMPORARY DEMIN LINER 1.0PURPOSE The purpose of this procedure Appendix is to allow processing of the FDT using a temporary demin liner discharging to the FDT or WHT. 2.0Verify the following (OR 1-98-498): 2.1 The version of this procedure is the current version. 2.2 This procedure is the correct unit for the task. 3.0PRECAUTIONS AND LIMITATIONS 3.1 WHEN processed fluid is being routed to the FDT or WHT, THEN the appropriate tank level(s) should be monitored closely. 3.2 To extend the life of resin, temporary demineralizers should be isolated with water maintained in them when not in use. 3.3 IF any fire doors will be propped open due to hoses, THEN contact the Fire Protection Administrator to implement the appropriate compensatory measures. 4.0INITIAL CONDITIONS 4.1 A temporary liner with resin is available to process the FDT per Figure 1. 4.2 Arrange with ENV to sample first pass of resin effluent, and sample the FDT to determine its ultimate destination (either FDT or WHT). 4.3 Verify that the liner is in place in an area that does not interfere with other work activities;have liner moved as necessary. 4.4 IF effluent is processed to the WHT, THEN adequate space is available to receive the volume of water processed. 4.5 Set up an empty, clean container to contain the first pass of resin effluent. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 5 Page 2 of 6 Version 75.0 5.0INSTRUCTIONS 5.1 Notify the Radside SO that a large amount of water will be transferred and additional level monitoring of the FDT or WHT will be necessary. 5.2 Close FDT FILTER INLET PI-1078 ROOT, Q1G21V119A (1-LWP-V-7422A). 5.3 Have I&C remove flange to FDT FLTR INLET PI, N1G21PI1078. I&C 5.4 Have I&C install flange with elbowed Chicago Fitting to flange in Step 5.3. I&C 5.5 Commence processing the first pass of resin effluent by performing the following: 5.5.1 Verify closed FDT FILTER INLET, Q1G21V120 (1-LWP-V-7423). 5.5.2 Verify closed #1 WMT DISCH TO FDT, Q1G21V115 (1-LWP-V-7454) 5.5.3 Verify closed #2 WMT DISCH TO FDT, Q1G21V266 (1-LWP-V-7455) 5.5.4 Verify closed FDT STRAINER DISCH, N1G21V118 (1-LWP-V-7421). 5.5.5 Attach 200' of red rubber hose tested to 150 # with banded Chicago fittings to the flange installed in Step 5.4. 5.5.6 Route and attach hose to portable demineralizer. 5.5.7 Route discharge of portable demineralizer to empty clean container. 5.5.8 Verify open FDT FILTER INLET PI-1078 ROOT, Q1G21V119A (1-LWP-V-7422A). 5.5.9 Verify open portable demineralizer inlet valve. 5.5.10 Verify open portable demineralizer outlet valve. 5.5.11 Start FDT PUMP, N1G21P007. 5.5.12 Throttle open FDT STRAINER DISCH, N1G21V118 (1-LWP-V-7421) to obtain desired flow rate through the portable demineralizer. 5.6 Sample the first pass of resin effluent. ENV UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 5 Page 3 of 6 Version 75.0 5.7 Secure the effluent flow by performing the following: 5.7.1 Stop FDT PUMP, N1G21P007. 5.7.2 Close the portable demineralizer inlet valve. 5.7.3 Close the portable demineralizer outlet valve. 5.8 Determine discharge path for processed effluent as follows: 5.8.1 Check sample for visible chromates. IF visible chromates are present, ENV THEN recommend replacement of the portable demineralizer resin, and repeat of steps 5.5 through 5.7. Visible chromates present (circle one) YES / NO 5.8.2 Based on sample activity level and chromate concentration results ENV above, circle below the tank to receive the processed effluent. Signing for this Step grants ENV permission to discharge portable demineralizer effluent to the tank designated below. FDT / WHT 5.9 Processing to the WHT or FDT. CAUTION: Ensure the hose is adequately secured to prevent hose from becoming dislodged from the appropriate drain. 5.9.1 Route outlet hose from temporary demineralizer to the drain system for the tank designated in Step 5.8.2. (i.e. floor drain for FDT or equipment drain for WHT) 5.9.2 Open portable demineralizer inlet valve. 5.9.3 Open portable demineralizer outlet valve. 5.9.4 Start FDT PUMP, N1G21P007 to initiate continuous processing of the FDT. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 5 Page 4 of 6 Version 75.0 NOTE: To monitor demineralizer effluent, place a white sheet of paper behind the effluent path for comparison to verify water is clear with no yellow tint. 5.9.5 Monitor effluent frequently for CCW and secure if yellow tint detected. 5.9.6 WHEN processing is complete, THEN stop FDT PUMP, N1G21P007. 5.9.7 Close the portable demineralizer inlet valve. 5.9.8 Close the portable demineralizer outlet valve. 5.10 Restoration of process flowpath. 5.10.1 Close FDT FILTER INLET PI-1078 ROOT. Q1G21V119A (1-LWP-V-7422A). CAUTION: When disconnecting the 200' hose it could contain 8 - 10 gallons of water. Have a suitable container available to drain the contents of the hose. Have the drained water tested to ensure it contains no chromates prior to disposal. 5.10.2 Disconnect the 200' hose from the installed flange and the portable demineralizer. 5.10.3 Have I&C remove flange with elbowed Chicago Fitting installed in I&C Step 5.4. 5.10.4 Have I&C reinstall flange to FDT FLTR INLET PI, N1G21PI1078. I&C / 5.10.5 Open FDT FILTER INLET PI-1078 ROOT. Q1G21V119A (1-LWP-V-7422A). CV / 5.10.6 Open FDT FILTER INLET, Q1G21V120 (1-LWP-V-7423). CV / 5.10.7 Close FDT STRAINER DISCH, N1G21V118 (1-LWP-V-7421). CV UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 5 Page 5 of 6 Version 75.0 5.10.8 Independently verify the following: 5.10.8.1 FDT FILTER INLET PI-1078 ROOT, Q1G21V119A open. 5.10.8.2 FDT FILTER INLET, Q1G21V120 open. 5.10.8.3 FDT STRAINER DISCH, N1G21V118 closed. 5.11 Store the hoses and elbowed flange in the appropriate location. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 5 Page 6 of 6 Version 75.0 FIGURE 1 TemporaryDemineralizerINOUT66666From FDTSourceApprox. 8 ft.Section RedRubber HoseApprox. 4 ft.Section RedRubber HoseIn Line Johnson ScreenFlow Direction Shown onSightglass with Arrow(REQUIRED)0000gpmFlow Rate Meter &Flow Totalizer(OPTIONAL)Flow DirectionStamped In Metal onTotalizer(OPTIONAL)Demin. Effluent to Floor orEquipment Drain as directedNOTE:The in line Johnson Screen serves as an additional barrier to prevent putting resininto the floor drain system. The temporary demineralizer should not be placed inservice without it. The flow indicator and totalizer are optional depending on theneed to monitor flowrate and total gallons processed. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 6 Page 1 of 1 Version 75.0 APPENDIX 6 Use of the RCDT LCV-1003 Controller (Q1G21LCV1003)1. To select Automatic (AUTO) or Manual (MAN) mode of operation, press the A/Mbutton on the keypad. The graphics display will have either A or M highlighted to show the selected mode. 2. In Manual, depressing or controls the valve position. Valve position is monitored on the right hand bargraph display. 3. In Automatic, depressing or controls the setpoint. The setpoint can be monitored on the left hand bargraph display. 4. To change the setpoint of LCV-1003 with the valve controller in Manual: a.Select the left-hand bargraph display by depressing SEL and observing the blue dot above the bargraph displays. b.Depress or to control the setpoint. The bar graph will move up or down and the digital display will show the setpoint. General Notes:1. The new controller is a FOXBORO 760 series, microprocessor based, multi display system. 2. It has three "bargraph" LCD displays. From left they are: a.Setpoint-this shows the AUTO setpoint for RCDT level. b. Variable - this shows the actual RCDT level. c.Demand - this shows the demanded position of LCV-1003. 3. The digital display above the bar graphs gives a readout for whichever bar graph is currently selected. 4. The keypad on the lower Section of the controller has eight buttons: - to increase the selected variable. - to decrease the selected variable. W/P - not used R/L - not used A/M - selects Auto or Manual SEL - selects the function for the up/down buttons and the bargraph display which will have the digital display. Also used by I&C. TAG - used by I&C.41 UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 7 Page 1 of 1 Version 75.0 FARLEY NUCLEAR PLANT UNIT 1 APPENDIX 7 INSTALLATION OF TEMPORARY LEVEL INDICATION FOR THE FLOOR DRAIN TANK Completed By Date __________________ Reviewed By Date __________________ This appendix consists of 2 pages. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 7 Page 1 of 2 Version 75.0 1.0PURPOSE Provide guidance for the installation of a level hose to provide temporary level indication when the installed level transmitter is inoperable or for any other operational necessity. 2.0INITIAL CONDITIONS 2.1 Check the appendix of this procedure for the following: 2.1.1 The version of this procedure appendix has been verified to be the current version. (OR 1-98-498) 2.1.2 This procedure appendix has been verified to be the correct unit for the task. (OR 1-98-498) 3.0PRECAUTIONS AND LIMITATIONS 3.1 Do NOT leave FDT DRN, Q1G21V130 open unattended. Intent is to valve in level hose temporarily to check level, and then isolate hose before leaving area. 4.0INSTRUCTIONS:NOTE: Only the appropriate section of this appendix needs to be completed. The other section may be signed off as N/A if not required to be performed. 4.1 LEVEL HOSE INSTALLATION: 4.1.1 Verify closed FDT DRN, Q1G21V130. 4.1.2 Remove the blind flange from the floor drain tank drain line. 4.1.3 Connect a 2" reducer sized for the diameter tubing/tygon to be used for the level hose. 4.1.4 Connectand route level hose. NOTE: Do NOT leave FDT DRN, Q1G21V130 open unattended. 4.1.5 OpenFDT DRN, Q1G21V130 as required to check level, THEN closeQ1G21V130. 4.1.6 Repeatstep 4.1.5 as needed to monitor FDT level. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 7 Page 2 of 2 Version 75.0 4.2 LEVEL HOSE REMOVAL: 4.2.1 Verify closed FDT DRN, Q1G21V130. NOTE:Take appropriate measures to contain any leakage from the level hose and drain line when performing the following steps. 4.2.2 Carefully disconnect level hose and drain to an appropriate container. 4.2.3 Remove the 2" reducer from the floor drain tank drain line. 4.2.4 Reinstall the blind flange to floor drain tank drain line. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 8 Page 1 OF 1 Version 75.0 APPENDIX 8 WASTE EVAPORATOR FEED FILTER ISOLATION Performed by: DateReviewed by: DateThis appendix consists of 3 pages UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 8 Page 1 of 3 Version 75.0 APPENDIX 2 WASTE EVAPORATOR FEED FILTER ISOLATION NOTES: This Appendix is only good for filter replacement on the shift it was performed. Each Step must be signed off immediately after completion of that step. 1.0PURPOSE: 1.1 To provide guidance for isolating the Waste Evaporator Feed Filter for filter element replacement. 2.0 Verify the following (OR 1-98-498): 2.1 The version of this procedure has been verified to be the current version. (OR 1-98-498) 2.2 This procedure has been verified to be the correct procedure and unit for the task. (OR 1-98-498) 3.0INITIAL CONDITIONS: 3.1 Perform this appendix when notified that Maintenance is ready to change the filter. This will prevent the filter from drying out. 4.0PRECAUTION AND LIMITATIONS: 4.1 This Appendix is only good for filter replacement on the shift it was performed. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 8 Page 2 of 3 Version 75.0 5.0INSTRUCTIONS: 5.1 Record the work order number associated with the current filter replacement. WO #_________________ 5.2 Isolate Waste Evaporator Feed Filter as follows: 5.2.1 Verifyclosed WEFF INLET, Q1G21V020. (83' WEF Pump room) 5.2.2 Verify closed WEFP DISCH TO FDT ISO, Q1G21V027. (83' WEF Pump room) 5.2.3 Close WASTE EVAP FEED FILTER OUTLET, Q1G21V019. (139' Waste Evap Feed Filter room) 5.2.4 Open WASTE EVAP FEED FILTER DRN Q1G21V023A. (139' Waste Evap Feed Filter room) 5.2.6 Open WASTE EVAP FEED FILTER DRN Q1G21V023B. (139' Waste Evap Feed Filter room) 5.2.7 Open WASTE EVAP FEED FILTER vent Q1G21V022. (139' Waste Evap Feed Filter room) 5.2.8 IF maintenance is (will be) delayed and work has not (will not be) started on the current shift, THEN restore the lineup to an in service configuration starting at Step 5.3.1, OR have the system configuration documented with a Tagout. 5.2.9 Notify SS that WEF filter has been replaced with new o-ring and lid MAINT torqued to 100 in lb. UNIT 1 06/02/15 14:51:09 FNP-1-SOP-50.0 APPENDIX 8 Page 3 of 3 Version 75.0 NOTE: IF the WEF filter was tagged in Step 5.2.8 THEN the rest of this appendix is N/A. 5.3 WHEN maintenance has completed the filter replacement, THEN return the Waste Evaporator Feed Filter to service as follows: 5.3.1 Close WASTE EVAP FEED FILTER vent Q1G21V022. (139' Waste Evap Feed Filter room) 5.3.2 Close WASTE EVAP FEED FILTER DRN Q1G21V023B. (139' Waste Evap Feed Filter room) 5.3.3 Close WASTE EVAP FEED FILTER DRN Q1G21V023A. (139' Waste Evap Feed Filter room) 5.3.4 Open WASTE EVAP FEED FILTER OUTLET, Q1G21V019. (139' Waste Evap Feed Filter room) 5.3.5 Verify closed WEFP DISCH TO FDT ISO, Q1G21V027. (83' WEF Pump room) 5.3.6Verifyclosed WEF FILTER INLET, Q1G21V020. (83' WEF Pump room) 08/14/14 12:25:04 FNP-2-SOP-50.0 October 31, 2011 UNIT 2 Version 70.0 FARLEY NUCLEAR PLANT SYSTEM OPERATING PROCEDURE FNP-2-SOP-50.0 S A F E T Y LIQUID WASTE PROCESSING SYSTEM R E L A T E D

PROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORY SECTIONS Continuous: ALL

Reference:

NONE Information: NONE

Approved:

David L. Reed (for) 07/07/2014 Operations Manager Effective Date

UNIT 2 08/14/14 12:25:04 FNP-2-SOP-50.0 Page 1 of 1 Version 70.0 TABLE OF CONTENTS Procedure Contains Number of Pages Body ........................................................54 Appendix 1 ................................................1 Appendix 2 ................................................3 Appendix 3 ................................................2 Appendix 4 ...............................................6 Appendix 5 ................................................2 Appendix 6 ................................................3

08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 FARLEY NUCLEAR PLANT UNIT 2 SYSTEM OPERATING PROCEDURE SOP-50.0 LIQUID WASTE PROCESSING SYSTEM 1.0 PURPOSE This procedure provides the Initial Conditions, Precautions and Limitations, and Instructions for Operation of the Liquid Waste Processing System. Included are the following instructions. 4.1 Reactor Coolant Drain Tank (RCDT) Operation 4.1.1 RCDT system startup and recirculation 4.1.2 RCDT normal operation 4.1.3 Manual Pump Down of RCDT to RHT 4.1.4 RCDT Discharge to WHT 4.1.5 Draining refueling canal with the RCDT System to the RWST. 4.1.6 Filling the RCDT from the PRT 4.1.7 Draining Refueling Cavity Using the RCDT System and Pumping to the RHT or WHT 4.1.8 Processing Nozzle Dam Leakage to RHT. 4.1.9 Draining the RCS Loops for Maintenance Via the Reactor Coolant Drain System. 4.1.10 Establishing a Hydrogen Atmosphere in the RCDT. 4.1.11 Establishing a Nitrogen Atmosphere in the RCDT 4.2 Waste Holdup Tank (WHT) Operation 4.3 Waste Evaporator Condensate Tank (WECT) Operation 4.4 Chemical Drain Tank (CDT) Operation 4.5 Floor Drain Tank (FDT) System Operation 4.6 Waste Monitor Tank (WMT) #1 (2) Operation 4.7 Waste Monitor Tank (WMT) #1 (2) Recirculation through the Waste Monitor Tank Demineralizer. 4.8 Manually Draining Refueling Cavity to CTMT Sump 4.9 Alternate Processing of the FDT to the WHT 4.10 Draining the Cask Wash Area to the FDT 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 Appendix 1 Use of the RCDT LCV-1003 Controller

Appendix 2 Floor Drain Tank Filter Isolation for Filter Replacement.

Appendix 3 Floor Drain Tank Strainer Isolation for Basket Cleaning or Replacement.

Appendix 4 Processing FDT using Temporary Demin Line Appendix 5 Installation of Temporary Level Indication For the Floor Drain Tank Appendix 6 Waste Evaporator Feed Filter Isolation for Filter Replacement. 2.0 INITIAL CONDITIONS 2.1 The electrical distribution system is energized and aligned for normal operation per system check list FNP-2-SOP-36.0, PLANT ELECTRICAL DISTRIBUTION LINE-UP, with exceptions noted. 2.2 The compressed air system is in service and aligned for normal operation per FNP-2-SOP-31.0, COMPRESSED AIR SYSTEM. 2.3 The liquid waste processing system valves are aligned per system check list FNP-2-SOP-50.0A-D with exceptions noted. 2.4 Component cooling water system is aligned per FNP-2-SOP-23.0, COMPONENT COOLING WATER SYSTEM, to supply water to the waste evaporator condenser, distillate cooler, vent condenser and RCDT heat exchanger. This initial condition may be waived by the Shift Supervisor if not required to support the activity being performed. 2.5 A hydrogen blanket has been established in the RCDT and is being maintained at a pressure between 3 and 8 psig per section 4.1.10. This initial condition may be waived by the Shift Supervisor if not required to support the activity being performed. 2.6 Solid Waste Processing System aligned per FNP-2-SOP-49.1A and B, WASTE TRANSFER TO BULK SOLIDIFICATION & DEWATERING FACILITY. 2.7 The WHT to Recycle Evap. Spoolpiece and the R.E.C. Filter to Waste Evap. Condensate Tank Spoolpiece are both removed and blind flanges are installed. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 3.0 PRECAUTIONS AND LIMITATIONS 3.1 Due to the presence of radioactive or potentially radioactive materials within the confines of the liquid waste processing system, constant vigilance must be exercised over system piping, valves, tanks, and other components whether in operation or shutdown. Pre-operational checks and normal routine operations and surveillance should include visual checks for system deterioration, component leakage, and correct system line-up which if not detected and corrected could subsequently result in the release of radioactive liquid to the immediate area, the environment, or other parts of this system. 3.2 Radiation monitor RE-18 must be operable and in service during liquid waste discharge to the river except as permitted by technical specifications. 3.3 IF RE-18 becomes inoperable while discharging liquid waste to the river, THEN the discharge must be stopped immediately. 3.4 The Shift Supervisor or Shift Support Supervisor shall be notified any time RE-18 is taken out of service or becomes inoperable. 3.5 A Radioactive Liquid Release Permit must be completed and approved prior to discharging radioactive liquid to the river. 3.6 Verify that tanks aligned to receive liquid waste discharge have sufficient capacity to receive the liquid. 3.7 ALL tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste, including non-source and non-destination tank levels. For processing or transfers, the levels of the source tank and the destination tank should be determined. The approximate flow rate should be considered and used to determine an approximate completion time. Tank levels shall be checked prior to the estimated completion of the processing or transfer such that sufficient margin exists to prevent tank overflow. At no time should the High Level Alarm be relied upon for securing the processing or transfer of a tank. To preclude overflow, waste tanks should not be filled to greater than 85%. 3.8 A deficiency report should be written to replace liquid waste system filters when the P increases to greater than 20 psid. 3.9 Caution should be exercised when pumping liquids to ascertain that affected pumps do not lose suction. 3.10 Once a WMT has been placed on recirculation for sampling purposes, prior to discharging to the environment, the tank shall remain in an isolated condition to prevent the introduction of any liquids which could alter the concentrations of the tank's contained volume. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 3.11 Sample source tank for activity prior to transfer from Unit 2 to Unit 1. This sample may be waived by Chemistry based on source of water. 3.12 When filling the WMTs, estimate the time that the WMT tank will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%. WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) 3.13 If a level hose has been installed on the floor drain tank it may be valved in for periodic monitoring whenever needed. However it must be valved out when the observation or monitoring is complete. 3.14 Contact Health Physics prior to opening N2G21V021 Refueling Canal Drain. Opening this valve has the potential for increased dose rates in the RCDT pump area and 100' PPR in Aux Building. (AI2008207409) 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.0 INSTRUCTIONS 4.1 REACTOR COOLANT DRAIN TANK (RCDT) OPERATION NOTE: Refer to Appendix 1 for operation of the RCDT level controller (LCV-1003) located on the Liquid Waste Processing Panel. 4.1.1 RCDT System Startup and Recirculation NOTE: IF necessary to establish adequate recirc flow to keep an RCDT pump running, THEN RCDT RECIRC ORIFICE BYP VALVE N2G21HV7143 may be opened. This condition should be tracked using a caution tag or administrative tracking item to ensure that it is restored when recirc is no longer required. 4.1.1.1 RCDT system is aligned per system checklist FNP-2-SOP-50.0A. 4.1.1.2 Verify open the following valves: RCDT RECIRC ISO N2G21HV7144 (LWPP) RCDT OUTLET ISO N2G21HV7127 (LWPP) 4.1.1.3 Verify that RCDT LCV Q2G21LCV1003 (Q2G21V064) is in MANUAL and closed (LWPP)

4.1.1.4 RCDT level is greater than 20%. 4.1.1.5 Start an RCDT pump. 4.1.1.6 IF desired to adjust tank level while on recirc, THEN adjust RCDT LCV Q2G21LCV1003 (Q2G21V064) as required in manual or automatic to control RCDT level. NOTE: IF RCDT is being aligned for recirculation to fill the RCDT then steps 4.1.1.4 thru 4.1.1.6 may be NA'ed to allow gravity filling of the RCDT 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.2 RCDT Normal Operation NOTES: Venting of the RCDT should be performed as needed in accordance with FNP-2-SOP-51.0, WASTE GAS SYSTEM. RCDT pumps should automatically trip at 10% RCDT level. The RCDT should be pumped down periodically per sections 4.1.3 or 4.1.4 to maintain parameters within the following bands: RCDT Level RCDT Pressure RCDT Temp MIN 5% 3 psig N/A MAX 75% 8 psig 170° F 4.1.2.1 Place both RCDT pumps in PULL-TO-LOCK. 4.1.2.2 Verify that RCDT LCV Q2G21LCV1003 (Q2G21V064) is in MANUAL and closed (LWPP) 4.1.2.3 Take RCDT LCV Q2G21LCV1003 selector switch on MCB to OPEN and then spring return to AUTO. 4.1.2.4 Verify RCDT PUMPS DISCH LINE ISO Q2G21HV7136 (Q2G21V0006) handswitch on MCB, OPEN and in AUTO. 4.1.2.5 WHEN necessary to lower tank level or pressure, THEN perform section 4.1.3 to pump to the RHT OR 4.1.4 to pump to the WHT. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: The following section may be utilized to lower RCDT pressure by lowering RCDT level. 4.1.3 Manual Pump Down of RCDT to RHT 4.1.3.1 Verify open the following valves: RCDT RECIRC ISO N2G21HV7144 (LWPP) RCDT OUTLET ISO N2G21HV7127 (LWPP) 4.1.3.2 IF required to maintain RCDT pressure by addition of hydrogen, THEN perform the following: 1. Verify pressure controller WASTE PROCESSING SYSTEM HYDROGEN BOTTLE DIS, Q2G21HV7155 (Q2G21V063) set to maintain 3 psi. (155' Plant Grounds) 2. Open H2 bottle isolation. 3. Open H2 BOTTLE TO RCDT ISO, N2G21V340. 4. Verify open H2 SUPP TO RCDT, N2G21V284 (at H2 Bottle) with the bottle regulator set for approximately 20 psi. 4.1.3.3 Verify that RCDT LCV Q2G21LCV1003 (Q2G21V064) is in MANUAL and closed (LWPP) 4.1.3.4 Take RCDT LCV Q2G21LCV1003 selector switch on MCB to OPEN and then spring return to AUTO. 4.1.3.5 Open RCDT PUMPS DISCH LINE ISO Q2G21HV7136. 4.1.3.6 Place RCDT LCV, Q2G21LCV1003 (Q2G21V064) in MANUAL and open 20-50%. (LWPP) 4.1.3.7 Start 2A(B) RCDT pump, and verify flow through FI 1008 (LWPP). 4.1.3.8 WHEN desired level is reached, THEN perform the following: a. Stop 2A(B) RCDT pump. b. Close RCDT LCV, Q2G21LCV1003 (Q2G21V064) (LWPP). 4.1.3.9 Verify RCDT pressure PI 1004 (LWPP) between 3 and 8 psi. 4.1.3.10 IF opened in step 4.1.3.2, THEN perform the following: 1. Close H2 bottle isolation. 2. Close H2 BOTTLE TO RCDT ISO, N2G21V340. 4.1.3.11 Restore the RCDT to normal operation per section 4.1.2. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: The following section may be utilized to lower RCDT pressure by lowering RCDT level. IF no RCDT pumps are operable, THEN it is permissible to gravity drain to WHT. 4.1.4 RCDT Discharge to WHT 4.1.4.1 Open RCDT DISCH TO WHT, Q2G21V009 (2-LWP-V-7137). 4.1.4.2 Close RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551). 4.1.4.3 Verify open the following valves: RCDT RECIRC ISO N2G21HV7144 (LWPP) RCDT OUTLET ISO N2G21HV7127 (LWPP) 4.1.4.4 IF required to maintain RCDT pressure by addition of hydrogen, THEN perform the following: 1. Verify pressure controller WASTE PROCESSING SYSTEM HYDROGEN BOTTLE DIS, Q2G21HV7155 (Q2G21V063) set to maintain 5 psi. (155' Plant Grounds) 2. Open H2 bottle isolation. 3. Open H2 BOTTLE TO RCDT ISO, N2G21V340. 4. Verify open H2 SUPP TO RCDT, N2G21V284 (at H2 Bottle) with regulator set for approximately 20 psi. 4.1.4.5 Verify that RCDT LCV Q2G21LCV1003 (Q2G21V064) is in manual and closed (LWPP) 4.1.4.6 Take RCDT LCV Q2G21LCV1003 (Q2G21V064) selector switch on MCB to OPEN and then spring return to AUTO. 4.1.4.7 Open RCDT PUMPS DISCH LINE ISO Q2G21HV7136. 4.1.4.8 Place RCDT LCV, Q2G21LCV1003 (Q2G21V064) in MANUAL and open 20-50%. (LWPP) 4.1.4.9 Start 2A(B) RCDT pump, and verify flow through FI 1008 (LWPP). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.4.10 WHEN desired level is reached, THEN perform the following: a. Stop 2A(B) RCDT pump. b. Close RCDT LCV, Q2G21LCV1003 (Q2G21V064) (LWPP). 4.1.4.11 Realign valves as follows: Open RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551). Close RCDT DISCH TO WHT Q2G21V009 (2-LWP-V-7137). 4.1.4.12 Verify RCDT pressure PI 1004 (LWPP) between 3 and 8 psi. 4.1.4.13 IF opened in step 4.1.4.4, THEN perform the following: 1. Close H2 bottle isolation. 2. Close H2 BOTTLE TO RCDT ISO, N2G21V340. 4.1.4.14 Restore the RCDT to normal operation per section 4.1.2. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.5 Draining refueling canal with the RCDT System to the RWST. 4.1.5.1 Stop all operating RCDT pumps. 4.1.5.2 Close RCDT OUTLET ISO N2G21HV7127 (N2G21V006). 4.1.5.3 Close RCDT RECIRC ISO N2G21HV7144 (N2G21V106). 4.1.5.4 Verify closed RCDT DISCH TO WHT Q2G21V009 (2-LWP-V-7137). 4.1.5.5 Verify closed RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551). 4.1.5.6 Verify closed PRESSURIZER RELIEF TANK DRN N2B13HV8031. 4.1.5.7 Verify SFP purification loop is not in operation per FNP-2-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 4.1.5.8 IF RWST purification is in operation, THEN perform the following: a. Stop the RWP pump. b. Close RWP PUMP SUCTION FROM RWST ISO, Q2G31V010. 4.1.5.9 Verify the following open: 1. RWP PUMP DISCH ISO, N2G31V008 (2-SFP-V-8792) 2. SFP PURIF OUTLET TO RWST, N2G31V021B (2-SFP-V-8793B). 4.1.5.10 Bypass the SFP demineralizer by performing the following: Close SFP PURIF INLET ISO, N2G31V009 (2-SFP-V-8773). Open SFP DEMIN BYPASS, N2G31V012 (2-SFP-V-8774). Close SFP DEMIN INLET ISO, N2G31V003 (2-SFP-V-8776). 4.1.5.11 Verify RCDT PUMPS DISCH LINE ISO Q2G21HV7136 is open and the handswitch is in the AUTO position. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTES: The RWP pump is not required; however, experience has shown it greatly increases flow and it is normally desired to have running. Throttle SFP PURIF OUTLET TO RWST, N2G31V021B (2-SFP-V-8793B) as necessary to limit flow through SFP demineralizer to < 100 GPM on FI-654. N2G21V021 should not be opened until Rx Cavity draining is in progress (AI2008207409) 4.1.5.12 Open REFUELING CANAL DRN, N2G21V021 (2-LWP-V-7129). 4.1.5.13 Open RCDT DISCH TO SFPCS RWPP SUCT, Q2G21V008 (2-LWP-V-7138). 4.1.5.14 Open RCDT LCV Q2G21LCV1003 (Q2G21V064). NOTES: In the following step, it will be necessary to hold the handswitch in start for the RCDT pump until flow is established to permit the pump to remain running. An operator stationed at the refueling water purification pump should monitor discharge pressure of the pump. When RWST pump discharge pressure increases due to the start of the RCDT pump, the RWST purification pump may be started per step 4.1.5.16. 4.1.5.15 Start an RCDT pump. CAUTION: The RWP pump does not have a low flow trip. 4.1.5.16 IF desired, THEN start the RWP pump. CAUTION: RCDT pump discharge piping is protected from over pressurization by a relief valve at penetration 31 outside containment which discharges to the equipment drains. This relief valve can sustain seat leakage at pressures above 150 psig. NOTE: Two RCDT pumps may be required to prevent the RWP pump from cavitating. IF a second RCDT pump is started THEN monitor RCDT pump discharge pressure to ensure the relief valve is not challenged (<150 psig). 4.1.5.17 IF necessary to prevent RWP pump cavitation THEN start the second RCDT pump. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.5.18 WHEN the desired RWST level is reached, THEN stop the RWP pump, if running, and shift the RCDT discharge to one of the following: 4.1.5.18.1 Aligning discharge to the RHT by performing the following: 1. Open RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551) 2. Close RCDT DISCH TO SFPCS RWPP SUCT, Q2G21V008 (2-LWP-V-7138) 4.1.5.18.2 Aligning discharge to the WHT by performing the following: 1. Open RCDT DISCH TO WHT Q2G21V009 (2-LWP-V-7137) 2. Close RCDT DISCH TO SFPCS RWPP SUCT, Q2G21V008 (2-LWP-V-7138) 4.1.5.19 WHEN draining is completed, THEN stop the RWP pump if running, and stop the RCDT pump. Realign valves as follows: Close REFUELING CANAL DRN, N2G21V021 (2-LWP-V-7129). Verify closed RCDT DISCH TO SFPCS RWPP SUCT, Q2G21V008 (2-LWP-V-7138). Close RWP PUMP DISCH ISO, N2G31V008 (2-SFP-V-8792). Close SFP PURIF OUTLET TO RWST, N2G31V021B (2-SFP-V-8793B). Close RCDT DISCH TO WHT Q2G21V009 (2-LWP-V-7137) Verify open RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551). Open RCDT OUTLET ISO Q2G21HV7127 (Q2G21V006). Open RCDT RECIRC ISO Q2G21HV7144 (N2G21V106). Close RCDT LCV Q2G21LCV1003 (Q2G21V064) and return control to MANUAL. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.5.20 Restore SFP demineralizer alignment by performing the following: Open SFP PURIF INLET ISO, N2G31V009 (2-SFP-V-8773). Open SFP DEMIN INLET ISO, N2G31V003 (2-SFP-V-8776). Close SFP DEMIN BYPASS, N2G31V012 (2-SFP-V-8774). 4.1.5.21 Restore the RCDT to normal operation per section 4.1.2. NOTE: Leave vent path in operation for pressure increases due to level increases. 4.1.6 Filling the RCDT from the PRT 4.1.6.1 Verify RCDT aligned in recirculation per Section 4.1. 4.1.6.2 Verify sufficient water available in PRT. 4.1.6.3 Open PRT DRN ISO, N2B13HV8031 [MCB]. NOTE: Closing RCDT outlet iso N2G21HV7127 (N2G21V006) RCDT OUTLET ISO will cause rapid rise in RCDT Level. 4.1.6.4 IF required, THEN close RCDT OUTLET ISO, N2G21HV7127 (N2G21V006) [LWPP]. 4.1.6.5 WHEN desired level reached in RCDT, THEN verify RCDT OUTLET ISO, N2G21HV7127 (N2G21V006) open. 4.1.6.6 Close PRT DRN ISO, N2B13HV8031 [MCB]. 4.1.6.7 IF required, THEN vent the RCDT per FNP-1-SOP-51.0, WASTE GAS SYSTEM, section 4.9 or 4.17. 4.1.6.8 Restore alignment of RCDT for normal operation per step 4.1.2 of this procedure. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.7 Draining Refueling Cavity Using the RCDT System and Pumping to the RHT or WHT 4.1.7.1 Verify an RHT in service per FNP-2-SOP-2.4, CVCS BORON RECYCLE SYSTEM. 4.1.7.2 Stop all operating RCDT pumps. 4.1.7.3 Close RCDT OUTLET ISO, N2G21HV7127 (N2G21V006) on LWPP. 4.1.7.4 Close RCDT RECIRC ISO, N2G21HV7144 (N2G21V106) on LWPP. 4.1.7.5 Verify RCDT PUMPS DISCH LINE ISO, Q2G21HV7136 is open and handswitch is in the AUTO position (MCB). NOTE: N2G21V021 should not be opened until Rx Cavity draining is to commence. (AI2008207409) 4.1.7.6 Open REFUELING CANAL DRAIN, N2G21V021 (2-LWP-V-7129). 4.1.7.7 Verify closed RCDT DISCH TO SFPCS RWPP SUCT, Q2G21V008 (2-LWP-V-7138). 4.1.7.8 If discharge of the RCDT to the WHT is desired: 4.1.7.8.1 Close RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551). 4.1.7.8.2 Open RCDT DISCH TO WHT Q2G21V009 (2-LWP-V-7137). 4.1.7.9 If discharge of the RCDT to the RHT is desired: 4.1.7.9.1 Verify closed RCDT DISCH TO WHT Q2G21V009 (2-LWP-V-7137). 4.1.7.9.2 Verify open RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551). 4.1.7.9.3 Monitor RHT level and WHEN necessary, THEN stop RCDT pumps and shift RHT's per FNP-2-SOP-2.4. 4.1.7.10 Open RCDT LCV Q2G21LCV1003 (Q2G21V064). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 CAUTIONS: Continuous monitoring of refueling cavity level is necessary to prevent cavitation of the RCDT pump(s). If a second RCDT pump is started, ensure that the flow rate remains at least 15 gpm higher than the flow obtained from a single pump to ensure miniflow protection is maintained. The flow rate will change as the cavity is lowered so the single pump reference will need to be obtained repeatedly. 4.1.7.11 Start a RCDT pump. 4.1.7.12 IF desired to start the second RCDT pump, THEN perform the following: 4.1.7.12.1 Note the discharge flow rate with a single pump in operation. 4.1.7.12.2 Start the second RCDT pump and verify that the discharge flow rate increases by at least 15 gpm. 4.1.7.12.3 Monitor discharge flow rate, and secure one RCDT pump prior to flow decreasing to within 15 gpm of the single pump flow rate. Return to step 4.1.7.12.1 and repeat as necessary. 4.1.7.13 WHEN draining is complete, THEN stop the RCDT pump. 4.1.7.14 Close REFUELING CANAL DRN, N2G21V021 (2-LWP-V-7129). 4.1.7.15 Close RCDT LCV Q2G21LCV1003 and place in manual. 4.1.7.16 Open RCDT OUTLET ISO N2G21HV7127 (N2G21V006) on LWPP. 4.1.7.17 Open RCDT RECIRC ISO N2G21HV7144 (N2G21V106) on LWPP. 4.1.7.18 IF the RCDT was aligned to the WHT, THEN perform the following: 4.1.7.18.1 Close RCDT DISCH TO WHT Q2G21V009 (2-LWP-V-7137). 4.1.7.18.2 Open RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551). 4.1.7.19 Restore the RCDT to normal operation per section 4.1.2. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.8 Processing Nozzle Dam Leakage to RHT. 4.1.8.1 Verify closed RCDT VENT, Q2G21V192 (2-LWP-V-7163). 4.1.8.2 Connect drain hose(s) from the nozzle dam leakage to the RCDT VENT, Q2G21V192 (2-LWP-V-7163). 4.1.8.3 Stop 2A and 2B RCDT pumps. 4.1.8.4 Open RCDT VENT, Q2G21V192 (2-LWP-V-7163). 4.1.8.5 Control RCDT level and discharge to RHT per step 4.1.2. 4.1.8.6 WHEN nozzle dam leakage processing to RHT is no longer required, THEN perform the following: 4.1.8.6.1 Stop 2A and 2B RCDT pumps. 4.1.8.6.2 Close RCDT VENT, Q2G21V192 (2-LWP-V-7163). 4.1.8.6.3 Remove nozzle dam drain hose from RCDT vent. 4.1.9 Draining the RCS Loops for Maintenance Via the Reactor Coolant Drain System. 4.1.9.1 Verify core unload is completed. 4.1.9.2 Verify both trains of RHR are secured. 4.1.9.3 Verify nozzle dam leakage processing is secured per step 4.1.8.6. 4.1.9.4 IF the SFP purification loop is in service, THEN remove from service per FNP-2-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.9.5 IF RWST purification is in operation, THEN remove from service per FNP-2-SOP-54.0, SPENT FUEL PIT COOLING AND PURIFICATION SYSTEM. 4.1.9.6 Open the SFP PURIF OUTLET TO RWST, N2G31V021B (2-SFP-V-8793B). 4.1.9.7 Open the RWP PUMP DISCH ISO, N2G31V008 (2-SFP-V-8792). 4.1.9.8 Close the RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551). 4.1.9.9 Open the RCDT DISCH TO SFPCS RWPP SUCT, Q2G21V008 (2-LWP-V-7138). 4.1.9.10 Close the RCDT RECIRC ISO 2-LWP-HV-7144 (N2G21V106) 4.1.9.11 Close the RCDT OUTLET ISO N2G21HV7127 (N2G21V006). 4.1.9.12 Verify open DRAIN HEADER ISO DOWNSTREAM OF SPECTACLE FLANGES, N2G21V0364. (CTMT 107' between RCDT and RCDT Pumps) 4.1.9.13 Open the desired RCS LOOP TO RCDT PUMP ISO: Q2B13V002A, (2-RC-V-8057A) and Q2B13V001A, (2-RC-V-8058A) for Loop 2A Q2B13V002B, (2-RC-V-8057B) and Q2B13V001B, (2-RC-V-8058B) for Loop 2B Q2B13V002C, (2-RC-V-8057C) and Q2B13V001C, (2-RC-V-8058C) for Loop 1C 4.1.9.14 Open the RCDT PUMPS DISCH LINE ISO 2-LWP-HV-7136 (Q2G21V006). 4.1.9.15 Start 2A (B) RCDT pump. 4.1.9.16 Adjust the RCDT LCV Q2G21LCV1003 (Q2G21V064) in manual to control the draining rate and maintain RCDT pump flow to < 100 gpm. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.9.17 IF unable to maintain RCDT discharge flow greater than minimum to maintain pump in operation, THEN perform the following: 4.1.9.17.1 Open RCDT OUTLET ISO N2G21HV7127 (N2G21V006) 4.1.9.17.2 Open RCDT RECIRC ISO N2G21HV7144 (N2G21V106) 4.1.9.17.3 Place RCDT LCV Q2G21LCV1003 (Q2G21V064) in automatic and adjust to maintain RCDT level as desired. 4.1.9.18 WHEN RWST level reaches 39 feet, THEN perform the following: 4.1.9.18.1 Shift RCDT discharge to RHT by performing the following: 1. Opening RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551) AND 2. Closing RCDT DISCH TO SFPCS RWPP SUCT, Q2G21V008 (2-LWP-V-7138). 4.1.9.19 WHEN the desired RCS level is reached, THEN stop the 2A (2B) RCDT pump. 4.1.9.20 Close the RCS loop to RCDT pump isolation valve(s) opened in step 4.1.9.13. 4.1.9.21 Verify closed RCDT DISCH TO SFPCS RWPP SUCT, Q2G21V008 (2-LWP-V-7138). 4.1.9.22 Verify open RCDT PUMP DISCH TO RHT ISO, Q2E21V315 (2-CVC-V-8551). 4.1.9.23 Close SFP PURIF OUTLET TO RWST, N2G31V021B (2-SFP-V-8793B). 4.1.9.24 Close the RWP PUMP DISCH ISO, N2G31V008 (2-SFP-V-8792). 4.1.9.25 Verify open RCDT OUTLET ISO N2G21HV7127 (N2G21V006). 4.1.9.26 Verify open RCDT RECIRC ISO, N2G21HV7144 (N2G21V106). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.9.27 Place the RCDT in service per section 4.1.2. 4.1.10 Establishing a Hydrogen Blanket in the RCDT. 4.1.10.1 Verify that the oxygen concentration in the RCDT gas space is less than 5% by volume. 4.1.10.2 RCDT system is aligned per system checklist FNP-1-SOP-50.0A. 4.1.10.3 An RHT is aligned for service per FNP-2-SOP-2.4, CVCS BORON RECYCLE SYSTEM. 4.1.10.4 Close the following RCDT vent line iso valves: RCDT VENT LINE ISO, Q2G21HV7126 (MCB) RCDT VENT LINE ISO, Q2G21HV7150 (MCB) NOTE: Reference FNP-0-ACP-36.0, COMPRESSED GAS SAFETY, as required, before performing steps involving a gas cylinder. (AI 2002202992) 4.1.10.5 Verify the hydrogen bottle is attached to the supply line AND bottle isolation valves are open, THEN open H2 bottle to RCDT ISO, N2G21V340. 4.1.10.6 Close H2 SUPP TO RCDT, Q2G21V211 (2-LWP-V-7125). 4.1.10.7 Open RCDT VENT, Q2G21V192 (2-LWP-V-7163). 4.1.10.8 Establish excess letdown to RCDT per FNP-2-SOP-2.7, CVCS EXCESS LETDOWN. 4.1.10.9 Start an RCDT pump and recirculate tank while tank is filling to ensure air is not entrapped in lines. 4.1.10.10 WHEN water comes out of the vent, THEN stop the RCDT pump and close RCDT VENT, Q2G21V192 (2-LWP-V-7163). 4.1.10.11 Remove excess letdown from service per FNP-2-SOP-2.7, CVCS EXCESS LETDOWN. 4.1.10.12 Open H2 SUPP TO RCDT, Q2G21V211 (2-LWP-V-7125). 4.1.10.13 Verify open the following valves: RCDT VENT LINE ISO Q2G21HV7126 (MCB). RCDT VENT LINE ISO Q2G21HV7150 (MCB). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.10.14 Verify the following: H2 SUPP TO RCDT, Q2G21PCV7155 (Q2G21V063) is set to maintain 3.0 psig. GAS DISCH FROM RCDT, Q2G21PCV7152 (Q2G21V002) is set to maintain 6.0 psig. 4.1.10.15 Start a RCDT pump. 4.1.10.16 Regulate RCDT LCV, Q2G21LCV1003 (Q2G21V064) in manual to pump tank level down to 20%. 4.1.10.17 IF needed, THEN place RCDT in normal operation per section 4.1, IF NOT, stop the pump and close RCDT LCV, Q2G21LCV1003 (Q2G21V064). 4.1.10.18 IF H2 supply to the RCDT is NOT to be maintained, THEN close the bottle isolation valves AND close H2 BOTTLE TO RCDT ISO, N2G21V340. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.11 Establishing a Nitrogen Atmosphere in the RCDT

4.1.11.1 RCDT system is aligned per system checklist FNP-2-SOP-50.0A, REACTOR COOLANT DRAIN COLLECTION AND DISCHARGE, and is aligned for normal operation per FNP-2-SOP-50.0, LIQUID WASTE PROCESSING SYSTEM. 4.1.11.2 The waste gas system is in service and capable of receiving gas from the RCDT. 4.1.11.3 Close the following valves: RCDT VENT LINE ISO Q2G21HV7126 (MCB) RCDT VENT LINE ISO Q2G21HV7150 (MCB) 4.1.11.4 Verify nitrogen bottle is attached to the supply line and bottle isolations are open (155' outside MSVR). 4.1.11.5 Open N2 BOTTLE TO RCDT ISO, N2G21V339 (155' outside MSVR) and close H2 BOTTLE TO RCDT ISO, N2G21V340. 4.1.11.6 Ensure the following pressure regulators are set as follows: H2 SUPP TO RCDT 2-LWP-PCV-7155 (Q2G21V063) set to maintain 3.0 psig. GAS DISCH FROM RCDT, 2-LWP-PCV-7152 (Q2G21V002) set to maintain 6.0 psig. NOTE: When filling the RCDT, the gas discharge valve from the RCDT should be set to maintain 3 psig Q2G21V0002 (2-LWP-PCV-7152) GAS DISCH FROM RCDT and the Q2G21V0063 (2-LWP-PCV-7155) H2 SUPP TO RCDT should be closed if RCDT pressure is 3 psig. This will allow H2 to be purged to the Waste Gas System. 4.1.11.7 Verify open the following valves (outside MSVR). H2 BOTTLES SUPP TO RCDT ISO, N2G21V284. H2 SUPP TO RCDT PCV OUTLET ISO, Q2G21V062 (2-LWP-V-7165). H2 SUPP TO RCDT PCV OUTLET ISO, Q2G21V061 (2-LWP-V-7154). 4.1.11.8 Verify air cut in to H2 SUPP TO RCDT Q2G21V063 (2-LWP-PCV-7155). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.11.9 Open RCDT VENT LINE ISO, Q2G21HV7126. 4.1.11.10 Open RCDT VENT LINE ISO. Q2G21HV7150. 4.1.11.11 Establish RCDT pressure of 8 psig by adjusting H2 SUPP TO RCDT Q2G21V063 (2-LWP-V-7155) as needed. IF pressure is raised, THEN verify N2 flow to the RCDT as evidenced by an increase in RCDT pressure and/or a decrease in N2 bottle pressure. WHEN RCDT pressure is at 8 psig, THEN adjust H2 SUPP TO RCDT Q2G21V063 (2-LWP-V-7155) to 0 psig. NOTES: Sampling of the RCDT is done in the 121' Piping Penetration Room. Sampling will not necessarily be done on the first burp, but should be performed on all subsequent burps. The sample should be obtained near the end of the burp to ensure that the sample obtained is representative of the RCDT atmosphere instead of being representative of the bulk N2 supply to the RCDT. An actual transfer of gas from the RCDT to the GDT must be in progress in order for Chemistry to take their sample. This evolution must be closely coordinated with Chemistry personnel. 4.1.11.12 Notify Chemistry to be ready to sample the RCDT during the burp, if desired. 4.1.11.13 Set the GAS DISCH FROM RCDT, 2-LWP-PCV-7152 to maintain 3 psig (Q2G21V002). 4.1.11.14 Verify RCDT LCV Q2G21LCV1003 in MANUAL and close. NOTE: A level hose may be used to monitor level changes in the RCDT if the installed level transmitter is not functioning properly AND containment is accessible. 4.1.11.15 Perform the following to raise RCDT level to approximately 90% to purge gas from the RCDT to the Waste Gas System. A. Stop all operating RCDT pumps. B. Close RCDT OUTLET ISO N2G21HV7127. C. Verify open RCDT RECIRC ISO N2G21HV7144. D. Open RCDT VENT TO WGC SUCT ISO, Q2G22V010 (100'El Aux Building). E. Open PRT DRAIN TO RCDT ISO. N2B13HV8031 (MCB). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 CAUTION: Monitor PRT pressure during drain to RCDT to ensure a positive pressure is maintained on the PRT. NOTE: IF it is necessary to use the RCDT pump to fill the RCDT per the following step, THEN the pump should be started and stopped as necessary to allow the gas from the RCDT atmosphere to bleed off to the waste gas system without overwhelming the waste gas compressor. F. If gravity drain is NOT sufficient to transfer water from the PRT, THEN run a RCDT pump as needed per the above note. G. Monitor RCDT level, pressure, and waste gas decay tank pressure as the water transfer proceeds to ensure proper system response. H. Coordinate with Chemistry personnel to obtain sample, if required, per the note preceding step 4.1.11.12. NOTE: It may be necessary to fill the PRT to the normal level using FNP-2-SOP-1.2, section 4.3. 4.1.11.16 WHEN RCDT level has been raised to approximately 90% and the RCDT GAS PRESS is approximately 3 psig, THEN perform the following: A. Stop all operating RCDT pumps. B. Close PRT DRAIN ISO. N2B31V8031. (MCB) C. Close RCDT VENT TO WGC SUCT ISO, Q2G22V010 (100' Aux Building). NOTE: Step 4.1.11.16D and 4.1.11.16E may be marked N/A if the RCDT can not be recirculated due to valve/pump problems, etc. D. Open RCDT OUTLET ISO. N2G21HV7127. NOTE: N2 PRESS may have to be added to the RCDT to operate the RCDT Pumps. E. Start a RCDT pump to recirc RCDT contents. F. WHEN burp is completed as indicated by RCDT pressure falling to 3 psig, THEN open H2 supp to RCDT, Q2G21V063 (2-LWP-PCV-7155) to maintain approximately 8 psig. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.1.11.17 Begin lowering RCDT level to approximately 30%. NOTES: RCDT drain down rate should be slow enough that H2 SUPPLY TO RCDT 2-LWP-PCV-7155 (Q2G21V063) can maintain a positive RCDT pressure of 3 psig. Closely monitor RCDT pressure during drain down. Change out the N2 cylinder outside the MSVR as required. IF the RCDT can NOT be pumped down due to some problem, THEN drain the RCDT using RCDT drain Q2G21V207. A. Using the controller on the LWPP throttle open REACTOR COOLANT DRN TANK LCV, Q2G21LCV1003 to slowly lower RCDT level to 30%. B. WHEN RCDT level is approximately 30%, THEN close REACTOR COOLANT DRN TANK LCV, Q2G21LCV1003 and stop the running RCDT pump. 4.1.11.18 Repeat step 4.1.11.11 through 4.1.11.17 until the hydrogen concentration is acceptable for chemical degas per Chemistry group requirements. 4.1.11.19 WHEN N2 purge no longer required, THEN close N2 BOTTLE TO RCDT ISO, N2G21V339 (outside MSVR). 4.1.11.20 Return setting of H2 SUPP TO RCDT 2-LWP-PCV-7155 (Q2G21V063) and GAS DISCH FROM RCDT, 2-LWP-PCV-7152 (Q2G21V002) to maintain 3.0 psig and 6 psig, respectively. 4.1.11.21 Place MCB handswitch for REACTOR COOLANT DRN TANK LCV Q2G21LCV1003 to OPEN and allow to spring return to AUTO.

08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.2 WASTE HOLD-UP TANK OPERATION 4.2.1 Waste Hold-Up Tank Recirculation and Sampling 4.2.1.1 Waste hold-up tank system is aligned per FNP-2-SOP-50.0B, LIQUID WASTE PROCESSING SYSTEM. 4.2.1.2 Start waste evaporator feed pump. NOTE: Prior to discharge, the WHT must be sampled and the sample checked for chromates. 4.2.1.3 Perform the following: a. Obtain a WHT sample. b. Visually check sample for chromates by placing a white sheet of paper behind the sample for comparison to verify water is clear with no yellow tint. 4.2.2 WHT discharge to disposable demineralizer system 4.2.2.1 Proceed per FNP-0-SOP-50.7, LIQUID WASTE PROCESSING USING THE DISPOSABLE DEMINERALIZER SYSTEM. 4.2.3 Waste Holdup Tank Discharge to the Floor Drain Tank 4.2.3.1 IF required to monitor floor drain tank level with a level hose and the hose has not been previously installed, THEN perform Appendix 5. 4.2.3.2 IF it is necessary to monitor and or determine the level of the floor drain tank with a level hose attached, THEN follow the guidance in step 4.5.1.3. 4.2.3.3 In the 139' filter room close WASTE EVAP FEED FILTER OUTLET, Q2G21V019 (2-LWP-V-7244). 4.2.3.4 At the liquid waste panel, start the waste evaporator feed pump. 4.2.3.5 In the waste evaporator feed pump room, open WEFP DISCH TO FDT ISO, Q2G21V027 (2-LWP-V-7240). 4.2.3.6 In the waste evaporator feed pump room, open WEFF INLET, Q2G21V020 (2-LWP-V-7239). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.2.3.7 WHEN WHT to FDT discharge is complete, THEN perform the following: 1. Stop the waste evaporator feed pump. 2. Close WEFF INLET, Q2G21V020 (2-LWP-V-7239). 4.2.3.8 Close WEFP DISCH TO FDT ISO, Q2G21V027 (2-LWP-V-7240). 4.2.3.9 Open WASTE EVAP FEED FILTER OUTLET, Q2G21V019 (2-LWP-V-7244). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.2.4 Draining the WHT to the FDT NOTES: Health Physics coverage is required for the performance of this procedure due to the potential for contamination. Draining should be done at a controlled rate to reduce splashing and the spread of contamination. 4.2.4.1 IF required to monitor floor drain tank level with a level hose and the hose has not been previously installed, THEN perform Appendix 5. 4.2.4.2 IF it is necessary to monitor and or determine the level of the floor drain tank with a level hose attached, THEN follow the guidance in step 4.5.1.3. 4.2.4.3 Verify that the waste evaporator feed pump is not running. 4.2.4.4 Verify that the WEFF INLET, Q2G21V020 (2-LWP-V-7239) is closed. 4.2.4.5 Verify closed WASTE GAS PROCESSING RM SUMP PUMPS DISCH TO WHT, N2G21V159A. 4.2.4.6 Verify open WASTE GAS PROCESSING RM SUMP PUMPS DISCH TO FDT, N2G21V159B (located in the recombiner hallway). NOTE: Removing the drain grating will reduce splashing. Remove grating if possible. 4.2.4.7 Slowly throttle open WHT DRN, Q2G21V029 (2-LWP-V-7234). 4.2.4.8 Verify the waste gas processing room sump pump starts and is pumping down the sump as the WHT is being drained to it. IF the pumps are not keeping up with drain rate OR the drains back up, THEN secure draining immediately and contact HP and notify the control room. 4.2.4.9 WHEN draining is complete, THEN close WHT DRN, Q2G21V029 (2-LWP-V-7234) and have HP survey the area around the floor drain. 4.2.5 Waste Evaporator Feed Filter Isolation for Filter Element Replacement 4.2.5.1 Proceed to Appendix 6. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.3 WECT OPERATIONS NOTE: WHEN starting waste evaporator condensate pump, THEN the handswitch for pump must be held in ON position until indication for N2G21V331, WECT PUMP DISCHARGE AOV, shows full open. 4.3.1 WECT Recirculation and Sampling 4.3.1.1 WECT system is aligned per system check list FNP-2-SOP-50.0B, LIQUID WASTE PROCESSING SYSTEM. 4.3.1.2 Close WECT INLET ISO, Q2G21V217 (2-LWP-V-7221) 4.3.1.3 Start waste evaporator condensate tank pump. 4.3.1.4 Notify the Shift Radio Chemist to obtain a sample. 4.3.1.5 IF desired, THEN remove the tank from recirc by performing the following: A. Stop the WASTE EVAPORATOR CONDENSATE TANK PUMP B. Open Q2G21V217 (2-LWP-V-7221), WECT INLET ISO 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.3.2 WECT discharge to WHT. 4.3.2.1 WECT pump is on and in recirculation mode per 4.3.1. In the Filter Room: 4.3.2.2 Open WASTE EVAP CNDS PUMP DISCH TO WHT, Q2G21V085 (2-LWP-V-7218). 4.3.2.3 Open WASTE EVAP CNDS FILTER OUTLET, Q2G21V084 (2-LWP-V-7217). 4.3.2.4 IF tank contents are to be routed through the waste evap condensate demineralizer, THEN perform the following. IF NOT, THEN proceed to step 4.3.2.5. A. Open WASTE EVAP CNDS DEMIN INLET, Q2G21V086 (2-LWP-V-7203). B. Open WASTE EVAP CNDS DEMIN OUTLET, Q2G21V225 (2-LWP-V-7212). C. Close WASTE EVAP CNDS DEMIN BYPASS, Q2G21V216 (2-LWP-V-7213). In the WECT Room: 4.3.2.5 Verify closed WECT INLET ISO, Q2G21V217 (2-LWP-V-7221). 4.3.2.6 Open the following valves: A. WASTE EVAP CNDS PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q2G21V087 (2-LWP-V-7232). B. WASTE EVAP CNDS PUMP DISCH, Q2G21V230 (2-LWP-V-7225). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.3.2.7 WHEN discharge of WECT is completed, THEN stop the pump and perform the following: In the Filter Room: A. IF tank contents were routed through the waste evap condensate demineralizer, THEN perform the following. IF NOT, THEN proceed to step 4.3.2.7.b. Close WASTE EVAP CNDS DEMIN INLET, Q2G21V086 (2-LWP-V-7203). Close WASTE EVAP CNDS DEMIN OUTLET, Q2G21V225 (2-LWP-V-7212). Open WASTE EVAP CNDS DEMIN BYPASS, Q2G21V216 (2-LWP-V-7213). B. Close WASTE EVAP CNDS FILTER OUTLET, Q2G21V084 (2-LWP-V-7217). Close WASTE EVAP CNDS PUMP DISCH TO WHT, Q2G21V085 (2-LWP-V-7218). In the WECT Room: Open WECT INLET ISO, Q2G21V217 (2-LWP-V-7221). Close WASTE EVAP CNDS PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q2G21V087 (2-LWP-V-7232). Close WASTE EVAP CNDS PUMP DISCH, Q2G21V230 (2-LWP-V-7225). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.3.3 WECT Discharge to WMT #2 4.3.3.1 WECT pump is on and in recirculation mode per 4.3.1. 4.3.3.2 IF tank contents are to be routed through the waste monitor tank demineralizer, THEN perform the following, IF NOT, proceed to step 4.3.3.3. Open WMT DEMIN OUTLET, Q2G21V094 (2-LWP-V-7434) (demineralizer valve area). In the Filter Rooms: Close WASTE MONITOR TANK DEMIN BYP, Q2G21V125 (2-LWP-V-7428). Close FLOOR DRN TANK DISCH TO #1 WMT ISO, Q2G21V089 (2-LWP-V-7412). Close WMT DISCH TO DEMIN, N2G21V355. Open WMT DISCH TO FLOOR DRN TANK LINE, Q2G21V093B (2-LWP-V-7438B) Open FLOOR DRN TANK TO WMT DEMIN, Q2G21V091 (2-LWP-V-7452) Proceed to step 4.3.3.4. 4.3.3.3 Close FLOOR DRN TANK DISCH TO #1 WMT ISO, Q2G21V089 (2-LWP-V-7412). 4.3.3.4 IF tank contents are to be routed thru the waste evaporator condensate demineralizer, THEN perform the following, IF NOT, proceed to 4.3.3.5. Open WASTE EVAP CNDS DEMIN INLET, Q2G21V086 (2-LWP-V-7203) (demin. valve access area on 139' elevation). Open WASTE CNDS DEMIN OUTLET, Q2G21V225 (2-LWP-V-7212) (filter room). Close WASTE EVAP CNDS DEMIN BYPASS, Q2G21V216 (2-LWP-V-7213) (filter room). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.3.3.5 Open WASTE EVAP CNDS FILTER OUTLET VALVE, Q2G21V084 (2-LWP-V-7217). 4.3.3.6 Open WASTE CNDS DISCH TO WASTE MONITOR TANK, Q2G21V220 (2-LWP-V-7219). In the Waste Evaporator Condensate Tank Room: 4.3.3.7 Verify closed WASTE EVAP CNDS TANK INLET ISO, Q2G21V217 (2-LWP-V-7221). 4.3.3.8 Open the following valves: WASTE EVAP CNDS PUMP DISCH ISO, Q2G21V230 (2-LWP-V-7225) WASTE EVAP CNDS TANK PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q2G21V087 (2-LWP-V-7232). 4.3.3.9 Estimate the time that the WMT will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%. (IR 2-96-167) 4.3.3.10 WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) CAUTION: The WECT is subject to siphoning when pumping to a WMT. Closing WASTE CNDS DISCH TO WASTE MONITOR TANK, Q2G21V220, after stopping the waste condensate pump will prevent possible overflowing of the WMT. 4.3.3.11 WHEN discharge of WECT is completed, THEN perform the following: a. Stop the Waste Evaporator Condensate Tank Pump. b. Close WASTE CNDS DISCH TO WASTE MONITOR TANK, Q2G21V220 (2-LWP-V-7219). c. IF the WECT contents were routed through the WMT demineralizer, THEN close WMT DEMIN OUTLET, Q2G21V094 (2-LWP-V-7434) (WMT demin valve area). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 In the Filter Rooms: d. IF tank contents were routed thru the waste evaporator condensate demineralizer, THEN perform the following, IF NOT, proceed to 4.3.3.11.e. Close WASTE EVAP CNDS DEMIN INLET, Q2G21V086 (2-LWP-V-7203). Close WASTE CNDS DEMIN OUTLET, Q2G21V225 (2-LWP-V-7212). Open WASTE EVAP CNDS DEMIN BYPASS, Q2G21V216 (2-LWP-V-7213). e. Close WASTE EVAP CNDS FILTER OUTLET VALVE, Q2G21V084 (2-LWP-V-7217). f. IF Waste Evaporator Condensate tank was routed thru the waste monitor tank demineralizer, THEN perform the following, IF NOT, proceed to 4.3.3.12. Open WASTE MONITOR TANK DEMIN BYP, Q2G21V125 (2-LWP-V-7428). Open FLOOR DRN TANK DISCH TO #1 WMT ISO, Q2G21V089 (2-LWP-V-7412). Close WMT DISCH TO FLOOR DRN TANK LINE, Q2G21V093B (2-LWP-V-7438B) Close FLOOR DRN TANK TO WMT DEMIN, Q2G21V091 (2-LWP-V-7452) Open WMT DISCH TO DEMIN N2G21V355. 4.3.3.12 Open FLOOR DRN TANK DISCH TO #1 WMT ISO, Q2G21V089 (2-LWP-V-7412). 4.3.3.13 In the Waste Evaporator Cond. Tank Room, perform the following: Close WASTE EVAP CNDS TANK PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q2G21V087 (2-LWP-V-7232). Close WASTE EVAP CNDS PUMP DISCH ISO, Q2G21V230 (2-LWP-V-7225) Open WASTE EVAP CNDS TANK INLET ISO, Q2G21V217 (2-LWP-V-7221). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.3.4 WECT Discharge to WMT #1 4.3.4.1 WECT pump is on and in recirculation mode per 4.3.1. 4.3.4.2 IF tank contents are to be routed thru the waste monitor tank demineralizer, THEN perform the following, IF NOT, proceed to step 4.3.4.4. Open WMT DEMIN OUTLET, Q2G21V094 (2-LWP-V-7434) (WMT demin vlv area) In the Filter Rooms: Close WASTE MONITOR TANK DEMIN BYP, Q2G21V125 (2-LWP-V-7428). Close WMT DISCH TO DEMIN, N2G21V355. Close FLOOR DRN TANK DISCH TO WMT #1 ISO, Q2G21V089 (2-LWP-V-7412). Open WMT DEMIN DISCH TO #1 WMT, Q2G21V093A (2-LWP-V-7438A). Open FLOOR DRN TANK TO WMT DEMIN, Q2G21V091 (2-LWP-V-7452). 4.3.4.3 Proceed to 4.3.4.5. 4.3.4.4 Close WASTE MONITOR TANK DEMIN BYP, Q2G21V125 (2-LWP-V-7428). 4.3.4.5 Open WASTE EVAP CNDS FILTER OUTLET, Q2G21V084 (2-LWP-V-7217). 4.3.4.6 Open WASTE CNDS DISCH TO WASTE MONITOR TANK, Q2G21V220 (2-LWP-V-7219). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.3.4.7 IF tank contents are to be routed thru the waste evaporator condensate demineralizer, THEN perform the following. IF NOT, proceed to 4.3.4.8. Open WASTE EVAP CNDS DEMIN INLET, Q2G21V086 (2-LWP-V-7203). (Demin. valve access area 139' elevation). Open WASTE CNDS DEMIN OUTLET, Q2G21V225 (2-LWP-V-7212). (Filter room). Close WASTE EVAP CNDS DEMIN BYPASS, Q2G21V216 (2-LWP-V-7213). (Filter room). 4.3.4.8 Verify closed WASTE EVAP CNDS TANK INLET ISO, Q2G21V217 (2-LWP-V-7221). 4.3.4.9 Open WASTE EVAP CNDS TANK PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q2G21V087 (2-LWP-V-7232). 4.3.4.10 Open WASTE EVAP CNDS PUMP DISCH ISO, Q2G21V230 (2-LWP-V-7225) 4.3.4.11 Estimate the time that the WMT will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%. (IR 2-96-167) 4.3.4.12 WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.3.4.13 WHEN discharge of liquid waste condensate tank is completed, THEN stop the pump. 4.3.4.14. IF tank contents were routed thru the waste evaporator condensate demineralizer, THEN perform the following, IF NOT, proceed to 4.3.4.15. Close WASTE EVAP CNDS DEMIN INLET, Q2G21V086 (2-LWP-V-7203). (Demin valve access area 139' elevation). Close WASTE CNDS DEMIN OUTLET, Q2G21V225 (2-LWP-V-7212). (Filter room). Open WASTE EVAP CNDS DEMIN BYPASS, Q2G21V216 (2-LWP-V-7213). (Filter room). 4.3.4.15. Close the following valves: WASTE EVAP CNDS FILTER OUTLET, Q2G21V084 (2-LWP-V-7217). WASTE CNDS DISCH TO WASTE MONITOR TANK, Q2G21V220 (2-LWP-V-7219). 4.3.4.16 IF waste evaporator condensate tank was routed thru the waste monitor tank demineralizer, THEN perform the following, IF NOT, proceed to 4.3.4.17. Close WMT DEMIN DISCH TO #1 WMT, Q2G21V093A (2-LWP-V-7438A). Close FLOOR DRN TANK TO WMT DEMIN, Q2G21V091 (2-LWP-V-7452). Open WASTE MONITOR TANK DEMIN BYP, Q2G21V125 (2-LWP-V-7428). Open WMT DISCH TO DEMIN, N2G21V355. Open FLOOR DRN TANK DISCH TO WMT #1 ISO, Q2G21V089 (2-LWP-V-7412). Close WMT DEMIN OUTLET, Q2G21V094 (2-LWP-V-7434) (WMT demin valve area, 139' elevation). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.3.4.17 Open or verify open WASTE MONITOR TANK DEMIN BYP, Q2G21V125 (2-LWP-V-7428). 4.3.4.18 Close WASTE EVAP CNDS TANK PUMP DISCH TO WASTE EVAP CNDS DEMIN, Q2G21V087 (2-LWP-V-7232). 4.3.4.19 Close WASTE EVAP CNDS PUMP DISCH ISO, Q2G21V230 (2-LWP-V-7225) 4.3.4.20 Open WASTE EVAP CNDS TANK INLET ISO, Q2G21V217 (2-LWP-V-7221). 4.3.5 Draining the Contents of a Contaminated WECT 4.3.5.1 IF the WECT is on recirc, THEN go to step 4.3.1.5 and remove from recirc. 4.3.5.2 Ensure sufficient capacity exists in the WHT to receive the contents to be drained from the WECT. 4.3.5.3 Open WASTE EVAP CNDS TK DRN, Q2G21V235 (2-LWP-V-7223) to drain contents of WECT to the WHT. 4.3.5.4 WHEN WECT draining is completed, THEN close WASTE EVAP CNDS TK DRN, Q2G21V235 (2-LWP-V-7223) 4.3.5.5 Proceed to section 4.2 for processing the WHT. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.4 CDT OPERATION 4.4.1 Draining the CDT to the WHT 4.4.1.1 Verify WHT level > 30% and < 90%. 4.4.1.2 Attach hose to CDT DRN Q2G21V238 and route to equipment drain. 4.4.1.3 Open CDT DRN Q2G21V238. 4.4.1.4 Drain CDT to approximately 5-15% level. 4.4.1.5 Close CDT DRN Q2G21V238. 4.4.1.6 Remove hose. NOTE: Two OPS personnel will be required for this task and a catch bag should be installed below the vent line to prevent the potential spread of contamination in case of overflow while applying air to the CDT. 4.4.2 Unclogging the CDT Drain 4.4.2.1 Coordinate with HP for coverage. 4.4.2.2 Verify closed CDT DRN, Q2G21V238. NOTE: In the following step, the purpose of the vent valve in line with the air hose is to allow pressure to be vented from the hose before disconnecting from the SA connection and the CDT drain. 4.4.2.3 Obtain air hose with a flow restrictor and vent valve. 4.4.2.4 Verify air hose vent valve closed. 4.4.2.5 Connect air hose to the nearest SA connection. 4.4.2.6 Connect air hose to the CDT DRN, Q2G21V238. 4.4.2.7 Slowly throttle open the SA ISO valve. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 CAUTION: Opening CDT DRN, Q2G21V238 too quickly or too far may result in blowing contaminated water out of the tank vent. Listen and feel for air flow through the drain line while throttling the valve open to prevent overflow of the tank. 4.4.2.8 Initiate air flow to dislodge the clog per the following: A. Slowly throttle open Q2G21V238 to dislodge debris. B. Monitor tank overflow and close Q2G21V238 if overflowing. C. WHEN air flow is heard through the drain line, THEN close Q2G21V238. 4.4.2.9 Close the SA ISO valve. 4.4.2.10 Perform the following: A. Carefully vent the air hose using the air hose vent valve. B. Disconnect air hose from SA connection. C. Coordinate with HP for removal of air hose from drain line to check for proper draining. 4.4.2.11 Perform section 4.4.1 and check for proper draining. 4.4.2.12 IF no drain flow, THEN repeat steps 4.4.2.2 through 4.4.2.10 as necessary to clear line. 4.4.2.13 IF drain flow is adequate, THEN coordinate with HP for removal and storage of air hose and connections used. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.5 FLOOR DRAIN TANK (FDT) SYSTEM OPERATION NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 CAUTION: IF it is known or suspected that chromates are present in the FDT, THEN notify the Shift Chemist prior to transferring or processing the tank. 4.5.1 FDT Recirculation and Sampling 4.5.1.1 Floor drain tank system is aligned per system check list FNP-2-SOP-50.0C, LIQUID WASTE PROCESSING SYSTEM 4.5.1.2 IF required to monitor floor drain tank level with a level hose and the hose has not been previously installed, THEN perform Appendix 5. 4.5.1.3 IF level hose is installed and it is required to monitor floor drain tank level with the hose, THEN open FLOOR DRAIN TANK DRN, Q2G21V130 and perform the following: Calculate the amount of waste water to be transferred. Ensure FDT level will be > 15% AFTER the transfer is completed. Monitor waste water transfer via the level increase in the tank receiving the water. Close the floor drain tank drain. Q2G21V130 NOTE: Sampling is required prior to transferring waste between units, prior to direct transfer to a WMT, or if chromates or other chemicals are suspected of being in the source tank. Sampling may be waived with Chemistry concurrence if repetitive draining of a system is being performed and previous samples have been within limits. 4.5.1.4 Start FDT pump and notify the Shift Radio Chemist to obtain sample, IF required. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 CAUTION: The contents of the FDT must be sampled and the sample analyzed prior to discharge to a WMT. NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.5.2 FDT Discharge to Waste Monitor Tank #2 (WMT) 4.5.2.1 Floor drain tank pump is on and in recirculation mode as per 4.5.1. 4.5.2.2 Close FLOOR DRAIN TANK DISCH TO #1 WMT, Q2G21V089 (2-LWP-V-7412) (In FDT filter room). 4.5.2.3 IF floor drain tank contents are NOT to be processed through the WMT demineralizer, THEN proceed to 4.5.2.4; IF it is, THEN perform the following: Open WMT DEMIN OUTLET, Q2G21V094 (2-LWP-V-7434) (WMT demin valve area). In the Filter Rooms: Close WMT DEMIN BYP, Q2G21V125 (2-LWP-V-7428). Close WMT DISCH TO DEMIN, N2G21V355. Open FLOOR DRN TANK TO WMT DEMIN, Q2G21V091 (2-LWP-V-7452). Open WMT DEMIN DISCH TO FLOOR DRN TANK LINE, Q2G21V093B (2-LWP-V-7438B). 4.5.2.4 Perform the following: Close FLOOR DRN TANK DISCH TO WASTE EVAP, Q2G21V267 (2-LWP-V-7427). Open FLOOR DRN TANK FILTER OUTLET, Q2G21V189 (2-LWP-V-7456). Open FLOOR DRAIN TANK STRAINER DISCH, N2G21V118 (2-LWP-V-7421) (FDT Pump Room). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.5.2.5 Estimate the time that the WMT will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%. (IR 2-96-167) 4.5.2.6 WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) 4.5.2.7 WHEN discharge of floor drain tank is completed, THEN stop the pump and perform the following alignments: A. IF tank contents were routed thru the WMT demineralizer, THEN perform the following, IF NOT, proceed to 4.5.2.7.B. Close WMT DEMIN OUTLET, Q2G21V094 (2-LWP-V-7434) (at WMT demin valve area). In the Filter Rooms: Open WMT DEMIN BYP, Q2G21V125 (2-LWP-V-7428). Open WMT DISCH TO DEMIN, N2G21V355. Close FLOOR DRN TANK TO WMT DEMIN, Q2G21V091 (2-LWP-V-7452). Close WMT DEMIN DISCH TO FLOOR DRN TANK LINE, Q2G21V093B (2-LWP-V-7438B). B. Perform the following: Close FLOOR DRN TANK FILTER OUTLET, Q2G21V189 (2-LWP-V-7456). Open FLOOR DRAIN TANK DISCH TO #1 WMT, Q2G21V089 (2-LWP-V-7412) Open FLOOR DRN TANK DISCH TO WASTE EVAP, Q2G21V267 (2-LWP-V-7427). In the FDT Pump Room: Close FLOOR DRAIN TANK STRAINER DISCH, N2G21V118 (2-LWP-V-7421) 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 CAUTION: The contents of the FDT must be sampled and the sample analyzed prior to discharge to a WMT. NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.5.3 FDT discharge to #1 WMT 4.5.3.1 Floor drain tank pump is on and in recirculation mode per 4.5.1. 4.5.3.2 IF FDT contents are NOT to be processed through the WMT demineralizer, THEN proceed to 4.5.3.3; IF it is, THEN perform the following: Open WMT DEMIN OUTLET, Q2G21V094 (2-LWP-V-7434) (WMT demin valve area).

In the Filter Rooms: Open FLOOR DRN TO WMT DEMIN, Q2G21V091 (2-LWP-V-7452). Open WMT DEMIN TO #1 WMT, Q2G21V093A (2-LWP-V-7438A). Close WMT DISCH TO DEMIN, N2G21V355. Close WASTE MONITOR TANK DEMIN BYP, Q2G21V125 (2-LWP-V-7428). Close FLOOR DRN TANK DISCH TO #1WMT ISO, Q2G21V089 (2-LWP-V-7412). Proceed to 4.5.3.4. 4.5.3.3 Close WASTE MONITOR TANK DEMIN BYP, Q2G21V125 (2-LWP-V-7428). 4.5.3.4 Close FLOOR DRN TANK DISCH TO WASTE EVAP, Q2G21V267 (2-LWP-V-7427). 4.5.3.5 Open FLOOR DRN TANK FILTER OUTLET, Q2G21V189 (2-LWP-V-7456). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 In the FDT Pump Room: 4.5.3.6 Open FLOOR DRAIN TANK STRAINER DISCH, N2G21V118 (2-LWP-V-7421) 4.5.3.7 Estimate the time that the WMT will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%. (IR 2-96-167) 4.5.3.8 WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) 4.5.3.9 WHEN discharge of floor drain tank is completed, THEN stop the pump and perform the following alignments: A. IF tank contents were routed thru the WMT demineralizer, THEN perform the following. IF NOT, proceed to 4.5.3.10. Close WMT DEMIN OUTLET, Q2G21V094 (2-LWP-V-7434) (WMT demin valve area). In the Filter Rooms: Open FLOOR DRN TANK DISCH TO #1WMT ISO, Q2G21V089 (2-LWP-V-7412). Open WMT DISCH TO DEMIN, N2G21V355. Close FLOOR DRN TO WMT DEMIN, Q2G21V091 (2-LWP-V-7452). Close WMT DEMIN TO #1 WMT, Q2G21V093A (2-LWP-V-7438A). 4.5.3.10 Close FLOOR DRN TANK FILTER OUTLET, Q2G21V189 (2-LWP-V-7456). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.5.3.11 Open FLOOR DRN TANK DISCH TO WASTE EVAP, Q2G21V267 (2-LWP-V-7427). 4.5.3.12 Open WASTE MONITOR TANK DEMIN BYP, Q2G21V125 (2-LWP-V-7428). In the FDT Pump Room: 4.5.3.13 Close FLOOR DRAIN TANK STRAINER DISCH, N2G21V118 (2-LWP-V-7421) NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.5.4 FDT Discharge to WHT 4.5.4.1 FDT pump is on and in recirculation mode per 4.5.1.

In the Filter Rooms: 4.5.4.2 Close FDT DISCH TO WASTE EVAP, Q2G21V267 (2-LWP-V-7427). 4.5.4.3 Open FDT DISCH TO WHT, Q2G21V123 (2-LWP-V-7426). In FDT Pump Room: 4.5.4.4 Open FDT STRAINER DISCH, N2G21V118 (2-LWP-V-7421). 4.5.4.5 WHEN discharge of the FDT is completed, THEN stop the pump and perform the following alignment:

a. In the Filter Rooms: Open FDT DISCH TO WASTE EVAP, Q2G21V267 (2-LWP-V-7427). Close FDT DISCH TO WHT, Q2G21V123 (2-LWP-V-7426). In FDT Pump Room: 4.5.4.6 Close FDT STRAINER DISCH, N2G21V118 (2-LWP-V-7421).

08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.5.5 FDT Discharge to Disposable Demineralizer System 4.5.5.1 Proceed to FNP-0-SOP-50.7, LIQUID WASTE PROCESSING USING THE DISPOSABLE DEMINERALIZER. 4.5.6 Floor Drain Tank Filter Isolation for Filter Element Replacement 4.5.6.1 Proceed to Appendix 2. 4.5.7 Floor Drain Tank Strainer Isolation for Basket Cleaning or Replacement 4.5.7.1 Proceed to Appendix 3 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.6 WASTE MONITOR TANK #1 (2) OPERATION 4.6.1 Waste Monitor Tank #1 (2) Recirculation and Sampling for Discharge to the Environment 4.6.1.1 Perform FNP-2-SOP-50.1 APPENDIX 1(2) WASTE MONITOR TANK 1(2) RELEASE TO THE ENVIRONMENT. NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.6.2 #1(2) WMT Discharge to WHT 4.6.2.1 Close #1(2) WMT INLET ISO, Q2G21V090 (Q2G21V135). 4.6.2.2 Verify closed, #1(2) WMT PUMP DISCH, N2G21V108B (N2G21V108A). 4.6.2.3 Start #1(2) WMT Pump. In The Filter Rooms: 4.6.2.4 Close FDT DISCH TO WASTE EVAP, Q2G21V267 (2-LWP-V-7427). 4.6.2.5 Open FDT DISCHARGE TO WHT, Q1G21V123 (1-LWP-V-7426). 4.6.2.6 Close WMT DISCH TO DEMIN, N2G21V355. In FDT Pump Room: 4.6.2.7 Open WMT PUMP DISCH TO FDT FILT N2G21V356. In WMT Pump Room: 4.6.2.8 Open #1(2) WMT DISCH TO FDT, Q2G21V115 (Q2G21V266). 4.6.2.9 Open #1(2) WMT PUMP DISCH, N2G21V108B (N2G21V108A). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.6.2.10 WHEN discharge of tank contents is completed, THEN stop the waste monitor tank pump 1 (2) AND perform the following: In the Filter Rooms: Close FDT DISCHARGE TO WHT, Q1G21V123 (1-LWP-V-7426). Open FDT DISCH TO WASTE EVAP, Q2G21V267 (2-LWP-V-7427). Open WMT DISCH TO DEMIN, N2G21V355. In FDT Pump Room: Close WMT PUMP DISCH TO FDT FILT N2G21V356. In WMT Pump Room: Close #1(2) WMT DISCH TO FDT, Q2G21V115 (Q2G21V266). Close #1(2) WMT PUMP DISCH, N2G21V108B (N2G21V108A). Open #1(2) WMT INLET ISO, Q2G21V090 (Q2G21V135). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.6.3 Waste Monitor Tank #1 (2) Transfer to Unit 1 Waste Monitor Tank: 4.6.3.1 Close #1(2) WMT INLET ISO, Q2G21V090 (Q2G21V135). 4.6.3.2 Verify closed, #1(2) WMT PUMP DISCH, N2G21V108B (N2G21V108A). 4.6.3.3 Start #1(2) WMT Pump. 4.6.3.4 Close DISPOSABLE DEMIN SYS INLET FROM WHT & FDT, N2G21V345. 4.6.3.5 IF Unit 1 WMT #1 is to receive contents, THEN perform the following, IF NOT, proceed to 4.6.3.6: Close #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428) Open LAUNDRY & HOT SHOWER TANK TO WMT DEMIN, Q1G21V091A (1-LWP-V-7452A) Open FDT TO WMT DEMIN, Q1G21V091B (1-LWP-V-7452B) 4.6.3.6 Open #1(2) WMT DISCH TO FDT, Q2G21V115 (Q2G21V266). 4.6.3.7 Open #1(2) WMT PUMP DISCH, N2G21V108B (N2G21V108A). 4.6.3.8 Open WMT PUMP DISCH TO FDT FILT N2G21V356. A. Open FDT DISCHARGE TO WHT, Q1G21V123 (1-LWP-V-7426) to flush approximately 100-200 gallons (2-4% level) from the Unit 2 WMT to the Unit 1 WHT, then close FDT DISCHARGE TO WHT, Q1G21V123 (1-LWP-V-7426). B. Open FDT FILTER OUTLET, Q1G21V189 (1-LWP-V-7456) to start discharge to Unit 1 WMT 1(2). 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.6.3.9 Estimate the time that the WMT will reach 80% level. The estimated time to reach 80% may be determined by timing the WMT level increase for at least 5% and extrapolating the time to reach 80%. (IR 2-96-167) 4.6.3.10 WHEN the WMT reaches 80%, THEN continuously monitor the WMT level indication to ensure the WMT filling is secured prior to exceeding 85%. (IR 2-96-167) 4.6.3.11 WHEN discharge of tank contents is complete, THEN stop Waste Monitor pump 1(2) AND perform the following: Close #1(2) WMT DISCH TO FDT, Q2G21V115 (Q2G21V266). Close #1(2) WMT PUMP DISCH, N2G21V108B (N2G21V108A). Open #1(2) WMT INLET ISO, Q2G21V090 (Q2G21V135). Close WMT PUMP DISCH TO FDT FILT N2G21V356. Close Unit 1 FDT FILTER OUTLET, Q1G21V189 (1-LWP-V-7456) Open DISPOSABLE DEMIN SYS INLET FROM WHT & FDT, N2G21V345. 4.6.3.12 IF Unit 1 WMT #1 received tank contents, THEN perform the following: Close LAUNDRY & HOT SHOWER TANK TO WMT DEMIN, Q1G21V091A (1-LWP-V-7452A) Close FDT TO WMT DEMIN, Q1G21V091B (1-LWP-V-7452B) Open #2 WMT DEMIN BYP, Q1G21V125 (1-LWP-V-7428) 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 4.7 WASTE MONITOR TANKS #1 (2) RECIRCULATION THROUGH THE WASTE MONITOR TANK DEMINERALIZER 4.7.1 Refer to FNP-2-SOP-50.1, LIQUID WASTE PROCESSING SYSTEM LIQUID WASTE RELEASE FROM WASTE MONITOR TANK. 4.8 MANUALLY DRAINING REFUELING CAVITY TO CTMT SUMP 4.8.1 Verify the following valves CLOSED; FUEL TRANSFER CANAL DRN, N2G21V172 REFUELING CANAL DRAIN, N2G21V021 (2-LWP-V-7129). 4.8.2 Provide for leakage collection and HP coverage, then remove blind flange on cavity drain valve. 4.8.3 Attach flange with nipple to drain line using existing gasket. 4.8.4 Attach drain hose to nipple and route to strainer/filter container supplied by HPS. 4.8.5 Attach drain hose to strainer/filter container and route to drain (CTMT sump). 4.8.6 With HPS coverage, throttle open FUEL TRANSFER CANAL DRN, N2G21V172 to prevent strainer/filter container from overflowing. NOTE: Ensure all loose particles are being removed by ensuring only clean water is flowing from strainer/filter to CTMT sump. 4.8.7 WHEN draining is completed, THEN close FUEL TRANSFER CANAL DRN, N2G21V172. 4.8.8 With HP coverage provided, remove drain flange and reinstall blind flange on drain line. 4.8.9 Have HPS store drain flange with strainer/filter container. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: Tank levels shall be monitored periodically during processing, discharge or transfer of liquid waste. ALL tank levels should be monitored, including non- source and non- destination tanks. CR# 2010102358 4.9 ALTERNATE PROCESSING OF THE FDT TO THE WHT 4.9.1 IF required to monitor floor drain tank level with a level hose and the hose has not been installed, THEN perform Appendix 5. 4.9.2 IF it is necessary to monitor and or determine the level of the floor drain tank with a level hose attached, THEN follow the guidance in step 4.5.1.3. 4.9.3 Procure a 6" S/S flange with a 6" long x 2" nipple. 4.9.4 Attach a 10' x 2" drain hose to the nipple flange. 4.9.5 Remove the existing blind flange and install the above described drain flange downstream of the FDT DRAIN, Q2G21V130 (2-LWP-V-7414). NOTE: The Floor Drain Tank room floor drain, drains to the RHR heat exchanger room sump. (AI2006204965) 4.9.6 Route hose to floor drain. 4.9.7 Notify HP of the intent to drain the FDT to the floor drain system. 4.9.8 Monitor the following: Waste Hold Up Tank level Proper operation of the RHR Heat Exchanger room sump pump (AI2006204965) 4.9.9 Open or throttle open FDT DRAIN, Q2G21V130 (2-LWP-V-7414) and drain the FDT as desired. 4.9.10 WHEN the desired level in the FDT OR WHT is reached, THEN close FDT DRAIN, Q2G21V130 (2-LWP-V-7414). 4.9.11 WHEN the normal method of processing the FDT is available, THEN realign the Waste Gas Processing Room sump pump discharge to the normal tank (FDT) per FNP-2-SOP-50.2, LIQUID WASTE PROCESSING SYSTEM SUMP PUMP SYSTEM OPERATION. 4.9.12 Remove temporary drain flange and replace blind flange. 4.9.13 Blue tag and return the drain flange and hose to the SFP Storage Room. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 NOTE: The CASK WASH Area should be pumped to the SFP as much as possible IAW FNP-2-SOP-54.0 before draining to the FDT. 4.10 DRAINING THE CASK WASH AREA TO THE FDT 4.10.1 IF required to monitor floor drain tank level with a level hose and the hose has not been previously installed, THEN perform Appendix 5. 4.10.2 IF it is necessary to monitor and or determine the level of the floor drain tank with a level hose attached, THEN follow the guidance in step 4.5.1.3. 4.10.3 Verify sufficient capacity in the FDT and the system operator is aware of the evolution. (CASK wash area, approx. 31,000 gallon capacity) 4.10.4 Verify any additional draining evolutions planned concurrently with draining the Cask Wash area have been evaluated to ensure the floor drain system will not be overloaded. NOTES: The CASK WASH ROOM DRAIN TO FDT ISO, N2G21V927 is a 6 inch valve. Depending on circumstances significant opening of this valve can overload the floor drains and cause them to back up onto the floor potentially spreading contamination. The CASK WASH ROOM DRAIN TO FDT ISO, N2G21V927 is located in the 121' batching area approximately 15 feet above floor level and will require a ladder or scaffolding for access. It is desirable to have an additional individual monitor the 100' elevation floor drains adjacent to the boric acid pumps while establishing the draining rate. 4.10.5 Slowly open CASK WASH ROOM DRAIN TO FDT ISO, N2G21V927 in approximately 1/4 turn increments. 4.10.6 Allow sufficient time to ensure drain rate equilibrium is obtained while monitoring the 121' elevation floor drain at the batching funnel and the 100' elevation floor drains adjacent to the boric acid transfer pumps and in the hallway adjacent to the charging pump suction valves. 4.10.7 Continue slowly opening CASK WASH ROOM DRAIN TO FDT ISO, N2G21V927 in approximately 1/4 turn increments until an acceptable drain rate is obtained without backup through the floor drains. 4.10.8 WHEN the cask wash area draining is complete, THEN close CASK WASH ROOM DRAIN TO FDT ISO, N2G21V927. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2

5.0 REFERENCES

5.1 Drawings P & ID - 205042, sheets 1-4, Waste Processing System.

5.2 Westinghouse System Description, SD-ALA-407.

5.3 Test Procedure, ALA/APR-SU-5.5.1 and 5.5.2. 5.4 Westinghouse Technical Manual, U-258243.

5.5 Drawing P & ID - 205008, Closed Loop Aux. Stm. and Cnds. Recovery System.

5.6 B-205787, Liquid Waste Instrument Loop Diagrams

08/14/14 12:25:04 FNP-2-SOP-50.0 Page 1 of 1 Version 70.0 UNIT 2 APPENDIX 1 Use of the RCDT LCV-1003 Controller (Q2G21LCV1003) 1. To select Automatic (AUTO) or Manual (MAN) mode of operation, press the A/M button on the keypad. The graphics display will have either A or M highlighted to show the selected mode. 2. In Manual, depressing or controls the valve position. Valve position is monitored on the right hand bargraph display. 3. In Automatic, depressing or controls the setpoint. The setpoint can be monitored on the left hand bargraph display. 4. To change the setpoint of LCV-1003 with the valve controller in Manual: a. Select the left-hand bargraph display by depressing SEL and observing the blue dot above the bargraph displays. b. Depress or to control the setpoint. The bargraph will move up or down and the digital display will show the setpoint. General Notes: 1. The new controller is a FOXBORO 760 series, microprocessor based, multi display system. 2. It has three "bargraph" LCD displays. From left they are: a. Setpoint - this shows the AUTO setpoint for RCDT level. b. Variable - this shows the actual RCDT level. c. Demand - this shows the demanded position of LCV-1003. 3. The digital display above the bargraphs gives a readout for whichever bargraph is currently selected. 4. The keypad on the lower section of the controller has eight buttons: - to increase the selected variable. - to decrease the selected variable. W/P - not used R/L - not used A/M - selects Auto or Manual SEL - selects the function for the up/down buttons and the bargraph display which will have the digital display. Also used by I&C. TAG - used by I&C. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 FARLEY NUCLEAR PLANT UNIT 2 APPENDIX 2

FLOOR DRAIN TANK FILTER ISOLATION

Completed By Date _________________ Reviewed By Date _________________

This Appendix consists of 3 pages. 08/14/14 12:25:04 FNP-2-SOP-50.0 Appendix 2 Page 1 of 3 Version 70.0 UNIT 2 APPENDIX 2 FLOOR DRAIN TANK FILTER ISOLATION NOTES: 1. This Appendix is only good for filter replacement on the shift it was performed. 2. Each step must be signed off immediately after completion of that step. 1.0 PURPOSE 1.1 To provide guidance for isolating the Floor Drain Tank Filter for filter element replacement. 2.0 VERIFY THE FOLLOWING (OR 1-98-498) 2.1 The version of this procedure has been verified to be the current version. (OR 1-98-498) 2.2 This procedure has been verified to be the correct procedure and unit for the task. (OR 1-98-498) 3.0 INITIAL CONDITIONS 3.1 Perform this appendix when notified that Maintenance is ready to change the filter. This will prevent the filter from drying out. 4.0 PRECAUTION AND LIMITATIONS 4.1 This Appendix is only good for filter replacement on the shift it was performed.

08/14/14 12:25:04 FNP-2-SOP-50.0 Appendix 2 Page 2 of 3 Version 70.0 UNIT 2 5.0 INSTRUCTIONS 5.1 Record the work order number associated with the current filter replacement. WO #_________________ 5.2 Isolate Floor Drain Tank Filter as follows: 5.2.1 Verify closed FLOOR DRN TANK FILTER OUTLET, Q2G21V189 (139' Floor Drain Tank Filter room) 5.2.2 Close FLOOR DRN TANK FILTER INLET, Q2G21V120. (139' Floor Drain Tank Filter room) 5.2.3 Close FLOOR DRN TANK DISCH TO WHT, Q2G21V123. (139' Floor Drain Tank Filter room) 5.2.4 Close FLOOR DRN TANK DISCH TO WASTE EVAP, Q2G21V267. (139' Floor Drain Tank Filter room) 5.2.5 Open FLOOR DRN TANK FILTER DRN, Q2G21V121A. (139' Floor Drain Tank Filter room) 5.2.6 Open FLOOR DRN TANK FILTER DRN, Q2G21V121B. (139' Floor Drain Tank Filter room) 5.2.7 Open FLOOR DRN TANK FILTER VENT, Q2G21V122. (139' Floor Drain Tank Filter room) 5.2.8 IF maintenance is (will be) delayed and work has not (will not be) started on the current shift, THEN restore the lineup to an inservice configuration starting at step 4.3.1, OR have the system configuration documented with a Tagout. 5.2.9 Notify SS that FDT filter has been replaced with the new o-ring and lid MAINT torqued to 100 in-lb.

08/14/14 12:25:04 FNP-2-SOP-50.0 Appendix 2 Page 3 of 3 Version 70.0 UNIT 2 NOTE: IF the FDT filter was tagged in step 5.2.8 THEN the rest of this appendix is N/A. 5.3 WHEN maintenance has completed the filter replacement, THEN return the Floor Drain Tank Filter to service as follows: 5.3.1 Close FLOOR DRN TANK FILTER VENT, Q2G21V122. (139' Floor Drain Tank Filter room) 5.3.2 Close FLOOR DRN TANK FILTER DRN, Q2G21V121B. (139' Floor Drain Tank Filter room) 5.3.3 Close FLOOR DRN TANK FILTER DRN, Q2G21V121A. (139' Floor Drain Tank Filter room) 5.3.4 Open FLOOR DRN TANK DISCH TO WASTE EVAP, Q2G21V267. (139' Floor Drain Tank Filter room) 5.3.5 Verify closed FLOOR DRN TANK DISCH TO WHT, Q2G21V123. (139' Floor Drain Tank Filter room) 5.3.6 Open FLOOR DRN TANK FILTER INLET, Q2G21V120. (139' Floor Drain Tank Filter room) 5.3.7 Open FLOOR DRN TANK FILTER OUTLET, Q2G21V189. (139' Floor Drain Tank Filter room) 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 3 Version 70.0 UNIT 2 FARLEY NUCLEAR PLANT UNIT 2 APPENDIX 3

FLOOR DRAIN TANK STRAINER ISOLATION

Completed By Date __________________ Reviewed By Date __________________

This Appendix consists of 2 pages 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 3 Page 1 of 2 Version 70.0 UNIT 2 1.0 PURPOSE 1.1 To provide guidance for Floor Drain Tank Strainer basket cleaning or replacement. 2.0 VERIFY THE FOLLOWING (OR 1-98-498): 2.1 The version of this procedure is the current version. 2.2 This procedure is the correct unit for the task. 3.0 INITIAL CONDITIONS 3.1 Floor Drain Tank Pump is tagged out. 4.0 PROCEDURE STEPS 4.1 Verify Floor Drain Tank Pump has been tagged out with the following minimum electrical isolation: Pump hand switch N2G21P007-N LWPP H/S tagged in the pull-to-lock position. Motor 600V supply breaker FE-C5 open and tagged. 4.2 Verify closed FLOOR DRN TANK STRAINER DISCH, N2G21V118. (83' FDT pump room) 4.3 Close FLOOR DRN TANK PUMP SUCT, Q2G21V131. (83' FDT pump room) 4.4 Open FLOOR DRN TANK STRAINER DRN, Q2G21V268. (83' FDT pump room) 4.5 Open FLOOR DRN TANK STRAINER VENT, Q2G21V132. (83' FDT pump room) 4.6 WHEN the strainer has been drained, THEN perform the following: 46.1 Slowly loosen and remove the four, 1/2" nuts holding the strainer cover in place. 4.6.2 Remove strainer cover. 4.6.3 Remove and clean the strainer basket. 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 3 Page 2 of 2 Version 70.0 UNIT 2 4.6.4 Re-install the strainer basket. 4.6.5 Inspect strainer gasket for damage. NOTE: For a new strainer gasket use Red Rubber Gasket Material 1/8" Stock # 0000000014426. 4.6.6 IF required, THEN have maintenance cut a new strainer gasket. 4.6.7 Re-install strainer gasket and cover. 4.6.8 Replace the four 1/2" nuts and tighten. 4.7 Close FLOOR DRN TANK STRAINER VENT, Q2G21V132. 4.8 Close FLOOR DRN TANK STRAINER DRN, Q2G21V268. 4.9 Verify closed FLOOR DRN TANK STRAINER DISCH, N2G21V118. 4.10 Open FLOOR DRN TANK PUMP SUCT, Q2G21V131. 4.11 Notify SSS that strainer cleaning is complete, in order to have the removal section of the FDT pump tagout prepared. 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 4 Version 70.0 UNIT 2

FARLEY NUCLEAR PLANT UNIT 2 APPENDIX 4

PROCESSING FDT USING TEMPORARY DEMIN LINER

Completed By Date __________________

Reviewed By Date __________________ This appendix consists of 6 pages. 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 4 Page 1 of 6 Version 70.0 UNIT 2 PROCESSING FDT USING TEMPORARY DEMIN LINER 1.0 PURPOSE The purpose of this procedure Appendix is to allow processing of the FDT using a temporary demin liner discharging to the FDT or WHT. 2.0 VERIFY THE FOLLOWING (OR 1-98-498): 2.1 The version of this procedure is the current version. 2.2 This procedure is the correct unit for the task. 3.0 PRECAUTIONS AND LIMITATIONS 3.1 WHEN processed fluid is being routed to the FDT or WHT, THEN the appropriate tank level(s) should be monitored closely. 3.2 To extend the life of resin, temporary demineralizers should be isolated with water maintained in them when not in use. 3.3 IF any fire doors will be propped open due to hoses, THEN contact the Fire Protection Administrator to implement the appropriate compensatory measures. 4.0 INITIAL CONDITIONS 4.1 IF required to monitor floor drain tank level with a level hose and the hose has not been previously installed, THEN perform Appendix 5. 4.2 IF it is necessary to monitor and or determine the level of the floor drain tank with a level hose attached, THEN follow the guidance in step 4.5.1.3. 4.3 A temporary liner with resin is available to process the FDT per Figure 1. 4.4 Arrange with ENV to sample first pass of resin effluent, and sample the FDT to determine its ultimate destination (either FDT or WHT). 4.5 Verify that the liner is in place in an area that does not interfere with other work activities; have liner moved as necessary. 4.6 IF effluent is processed to the WHT, THEN adequate space is available to receive the volume of water processed. 4.7 Set up an empty, clean container to contain the first pass of resin effluent. 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 4 Page 2 of 6 Version 70.0 UNIT 2 5.0 INSTRUCTIONS 5.1 Notify the Radside SO that a large amount of water will be transferred and additional level monitoring of the FDT or WHT will be necessary. 5.2 Close FLOOR DRN TANK FILTER INLET PI-1078 ISO, Q2G21V119A (2-LWP-V-7422A). 5.3 Have I&C remove flange to FDT FLTR INLET PI, N2G21PI1078. I&C 5.4 Have I&C install flange with elbowed Chicago Fitting to flange in Step 4.3. I&C 5.5 Commence processing the first pass of resin effluent by performing the following: 5.5.1 Verify closed FLOOR DRN TANK FILTER INLET, Q2G21V120 (2-LWP-V-7423). 5.5.2 Verify closed WMT PUMP DISCH TO FDT FILT, N2G21V356. 5.5.2 Verify closed FLOOR DRN TANK STRAINER DISCH, N2G21V118 (2-LWP-V-7421). 5.5.4 Attach 200' of red rubber hose tested to 150# with banded Chicago fittings to the flange installed in step 4.4. 5.5.5 Route and attach hose to portable demineralizer. 5.5.6 Route discharge of portable demineralizer to empty clean container. 5.5.7 Verify open FLOOR DRN TANK FILTER INLET PI-1078 ISO, Q2G21V119A (2-LWP-V-7422A). 5.5.8 Verify open portable demineralizer inlet valve. 5.5.9 Verify open portable demineralizer outlet valve. 5.5.10 Start FLOOR DRAIN TANK PUMP, N2G21P007. 5.5.11 Throttle open FLOOR DRN TANK STRAINER DISCH, N2G21V118 (2-LWP-V-7421) to obtain desired flow rate through the portable demineralizer. 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 4 Page 3 of 6 Version 70.0 UNIT 2 5.6 Sample the first pass of resin effluent. ENV 5.7 Secure the effluent flow by performing the following: 5.7.1 Stop FLOOR DRAIN TANK PUMP, N2G21P007. 5.7.2 Close the portable demineralizer inlet valve. 5.7.3 Close the portable demineralizer outlet valve. 5.8 Determine discharge path for processed effluent as follows: 5.8.1 Check sample for visible chromates. IF visible chromates are present, ENV THEN recommend replacement of the portable demineralizer resin, and repeat of steps 4.5 through 4.7. Visible chromates present (circle one) YES / NO

5.8.2 Based on sample activity level and chromate concentration results ENV above, circle below the tank to receive the processed effluent. Signing for this step grants ENV permission to discharge portable demineralizer effluent to the tank designated below. FDT / WHT 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 4 Page 4 of 6 Version 70.0 UNIT 2 5.9 Processing to the WHT or FDT. CAUTION: Ensure the hose is adequately secured to prevent hose from becoming dislodged from the appropriate drain. 5.9.1 Route outlet hose from temporary demineralizer to the drain system for the tank designated in step 4.8.2. (i.e. floor drain for FDT or equipment drain for WHT) 5.9.2 Open portable demineralizer inlet valve. 5.9.3 Open portable demineralizer outlet valve. 5.9.2 Start FLOOR DRAIN TANK PUMP, N2G21P007 to initiate continuous processing of the FDT. NOTE: To monitor demin. effluent, place a white sheet of paper behind the effluent path for comparison to verify water is clear with no yellow tint. 5.9.3 Monitor effluent frequently for CCW and secure if detected. 5.9.4 WHEN processing is complete, THEN stop FLOOR DRAIN TANK PUMP, N2G21P007. 5.9.5 Close the portable demineralizer inlet valve. 5.9.6 Close the portable demineralizer outlet valve. 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 4 Page 5 of 6 Version 70.0 UNIT 2 5.10 Restoration of process flowpath. 5.10.1 Close FLOOR DRN TANK FILTER INLET PI-1078 ISO, Q2G21V119A (2-LWP-V-7422A). CAUTION: When disconnecting the 200' hose it could contain 8 - 10 gallons of water. Have a suitable container available to drain the contents of the hose. Have the drained water tested to ensure it contains no chromates prior to disposal. 5.10.2 Disconnect the 200' hose from the installed flange and the portable demineralizer. 5.10.3 Have I&C remove flange with elbowed Chicago Fitting I&C installed in Step 4.4. 5.10.4 Have I&C reinstall flange to N2G21PI1078, FLOOR DRAN I&C TK FILTR INL. / 5.10.5 Open FLOOR DRN TANK FILTER INLET PI-1078 ISO, CV Q2G21V119A (2-LWP-V-7422A). / 5.10.6 Open, FLOOR DRN TANK FILTER INLET, Q2G21V120 CV (2-LWP-V-7423). 5.11 Independently verify the following: 5.11.1 Verify closed FLOOR DRN TANK STRAINER DISCH, N2G21V118 (2-LWP-V-7421). 5.11.2 Verify open FLOOR DRN TANK FILTER INLET PI-1078 ISO, Q2G21V119A (2-LWP-V-7422A). 5.11.3 Verify open FLOOR DRN TANK FILTER INLET, Q2G21V120 (2-LWP-V-7423). 5.12 Store the hoses and elbowed flange in the appropriate location. 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 4 Page 6 of 6 Version 70.0 UNIT 2 FIGURE 1 TemporaryDemineralizerINOUT66666From FDTSourceApprox. 8 ft.Section RedRubber HoseApprox. 4 ft.Section RedRubber HoseIn Line Johnson ScreenFlow Direction Shown onSightglass with Arrow(REQUIRED)0000gpmFlow Rate Meter &Flow Totalizer(OPTIONAL)Flow DirectionStamped In Metal onTotalizer(OPTIONAL)Demin. Effluent to Floor orEquipment Drain as directedNOTE:The in line Johnson Screen serves as an additional barrier to prevent putting resininto the floor drain system. The temporary demineralizer should not be placed inservice without it. The flow indicator and totalizer are optional depending on theneed to monitor flowrate and total gallons processed. 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 5 Version 70.0 UNIT 2

FARLEY NUCLEAR PLANT UNIT 2 APPENDIX 5

INSTALLATION OF TEMPORARY LEVEL INDICATION FOR THE FLOOR DRAIN TANK

Completed By Date __________________

Reviewed By Date __________________ This appendix consists of 2 pages 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 5 Page 1 of 2 Version 70.0 UNIT 2 1.0 PURPOSE Provide guidance for the installation of a level hose to provide temporary level indication when the installed level transmitter is inoperable or for any other operational necessity. 2.0 INITIAL CONDITIONS 2.1 Check this appendix of this procedure for the following: 2.1.1 The version of this appendix has been verified to be the current version. (OR 1-98-498) 2.1.2 This appendix has been verified to be the correct unit for the task. (OR 1-98-498) 3.0 PRECAUTIONS AND LIMITATIONS 3.1 If a level hose has been installed on the floor drain tank it may be valved in for periodic monitoring whenever needed. However it must be valved out when the observation or monitoring is complete. Do NOT leave FDT DRN, Q2G21V130 open unattended. 4.0 INSTRUCTIONS NOTE: Only the appropriate section of this appendix needs to be completed. The other section may be signed off as N/A if not required to be performed. 4.1 LEVEL HOSE INSTALLATION: 4.1.1 Verify closed FLOOR DRN TANK DRN, Q2G21V130. 4.1.2 Remove the blind flange from the floor drain tank drain line. 4.1.3 Connect a 2" reducer sized for the diameter tubing/tygon to be used for the level hose. 4.1.4 Connect and route level hose. NOTE: Do NOT leave FDT DRN, Q2G21V130 open unattended. 4.1.5 Open FLOOR DRN TANK DRN, Q2G21V130 as required to check level, THEN close Q2G21V130. 4.1.6 Repeat step 4.1.5 as needed to monitor FDT level. 08/14/14 12:25:04 FNP-2-SOP-50.0 APPENDIX 5 Page 1 of 1 Version 70.0 UNIT 2 4.2 LEVEL HOSE REMOVAL: 4.2.1 Verify closed FLOOR DRN TANK DRN, Q2G21V130. NOTE: Take appropriate measures to contain any leakage from the level hose and drain line when performing the following steps. 4.2.2 Carefully disconnect level hose and drain to an appropriate container. 4.2.3 Remove the 2" reducer from the floor drain tank drain line. 4.2.4 Reinstall the blind flange to floor drain tank drain line. 08/14/14 12:25:04 FNP-2-SOP-50.0 Version 70.0 UNIT 2 FARLEY NUCLEAR PLANT UNIT 2 APPENDIX 6

WASTE EVAPORATOR FEED FILTER ISOLATION

Completed By Date _________________ Reviewed By Date _________________

This Appendix consists of 3 pages. 08/14/14 12:25:04 FNP-2-SOP-50.0 Page 1 of 3 Version 70.0 UNIT 2 APPENDIX 6 WASTE EVAPORATOR FEED FILTER ISOLATION NOTES: 1. This Appendix is only good for filter replacement on the shift it was performed. 2. Each step must be signed off immediately after completion of that step. 1.0 PURPOSE 1.1 To provide guidance for isolating the Waste Evaporator Feed Filter for filter element replacement. 2.0 VERIFY THE FOLLOWING (OR 1-98-498) 2.1 The version of this procedure has been verified to be the current version. (OR 1-98-498) 2.2 This procedure has been verified to be the correct procedure and unit for the task. (OR 1-98-498) 3.0 INITIAL CONDITIONS 3.1 Perform this appendix when notified that Maintenance is ready to change the filter. This will prevent the filter from drying out. 4.0 PRECAUTION AND LIMITATIONS 4.1 This Appendix is only good for filter replacement on the shift it was performed. 08/14/14 12:25:04 FNP-2-SOP-50.0 Page 2 of 3 Version 70.0 UNIT 2 5.0 INSTRUCTIONS 5.1 Record the work order number associated with the current filter replacement. WO #_________________ 5.2 Isolate Waste Evaporator Feed Filter as follows: 5.2.1 Verify closed WEFF INLET, Q2G21V020. (83' WEF Pump room) 5.2.2 Verify closed WEFP DISCH TO FDT ISO, Q2G21V027. (83' WEF Pump room) 5.2.3 Close WASTE EVAP FEED FILTER OUTLET, Q2G21V019. (139' Waste Evap Feed Filter room) 5.2.4 Open WASTE EVAP FEED FILTER DRN Q2G21V023A. (139' Waste Evap Feed Filter room) 5.2.6 Open WASTE EVAP FEED FILTER DRN Q2G21V023B. (139' Waste Evap Feed Filter room) 5.2.7 Open WASTE EVAP FEED FILTER vent Q2G21V022. (139' Waste Evap Feed Filter room) 5.2.8 IF maintenance is (will be) delayed and work has not (will not be) started on the current shift, THEN restore the lineup to an in service configuration starting at Step 5.3.1, OR have the system configuration documented with a Tagout. 5.2.9 Notify SS that WEF filter has been replaced with new o-ring and lid MAINT torqued to 100 in lb. 08/14/14 12:25:04 FNP-2-SOP-50.0 Page 3 of 3 Version 70.0 UNIT 2 NOTE: IF the WEF filter was tagged in step 5.2.8 THEN the rest of this appendix is N/A. 5.3 WHEN maintenance has completed the filter replacement, THEN return the Waste Evaporator Feed Filter to service as follows: 5.3.1 Close WASTE EVAP FEED FILTER vent Q2G21V022. (139' Waste Evap Feed Filter room) 5.3.2 Close WASTE EVAP FEED FILTER DRN Q2G21V023B. (139' Waste Evap Feed Filter room) 5.3.3 Close WASTE EVAP FEED FILTER DRN Q2G21V023A. (139' Waste Evap Feed Filter room) 5.3.4 Open WASTE EVAP FEED FILTER OUTLET, Q2G21V019. (139' Waste Evap Feed Filter room) 5.3.5 Verify closed WEFP DISCH TO FDT ISO, Q2G21V027. (83' WEF Pump room) 5.3.6 Verify closed WEF FILTER INLET, Q2G21V020. (83' WEF Pump room)

FNP ILT-38 JPM Page 1 of 8 jpm a CRO-074 TITLE: Fill The SIS Accumulators ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: X SIMULATOR CONTROL ROOM PLANT PROJECTED TIME: 20 MIN SIMULATOR IC NUMBER: IC-211 (Base -188) ALTERNATE PATH TIME CRITICAL PRA JPM DIRECTIONS: 1. Examinee will obtain all references from the simulator. 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise. 3. Provide student with HANDOUT. 4. Allow student time to review control board. 5. Instructor will be provided to address alarms not related to evaluated task. TASK STANDARD: Upon successful completion of this JPM, the examinee will: 1. Fill the 1A SIS Accumulator. Examinee: Trainee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) Developer S Jackson Date: 4/9/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP ILT-38 JPM Page 2 of 8 EVENT DESCRIPTION ACTION DETAILS Reset into IC-211 Freeze Xe Run / Freeze Simulator Update Rods FF5 CLEAR Clear Ovation Alarms OVATION Acknowledge computer alarms SIPC Acknowledge Alarms Turn Horns ON Run / Freeze Simulator Un freeze Xe Run / Freeze Simulator FNP ILT-38 JPM Page 3 of 8 CONDITIONS When I tell you to begin, you are to FILL THE SIS ACCUMULATORS. The conditions under which this task is to be performed are: a. The Unit is at 100% power. b. The 1A accumulator level is 40% and pressure is 585 psig due to normal sampling. c. Chemistry has verified RWST boron concentration is suitable for makeup to the accumulator. d. You are directed to fill only the 1A accumulator to 45% using FNP-1-SOP-8.0. e. Continuous communications have been established. f. The Rad Side SO is standing by with a copy of the procedure and the required locked valve key. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME NOTE: Step 4.1.1.1, Verify RWST boron concentration is suitable for makeup to the accumulator, is satisfied by the initial conditions provided. If requested then provide the cue: Chemistry has verified RWST boron concentration is suitable for makeup to the accumulator. 1. 4.1.1.2 Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V- 8979) OPEN. SO directed to verify valve open. (CUE: SO reports V083 is open.) S / U *2. 4.1.1.3 Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). SO directed to open V028. (CUE: SO reports V028 open.) S / U 3. 4.1.1.4 Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. Observes HIK-947 Potentiometer fully clockwise, arrow at full right - 100%. S / U 4. 4.1.1.5 Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. Position of HV-8880 is checked. Observes green light lit, red light out. S / U *5. 4.1.1.6 Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC- V-8967). SO directed to unlock and open the hydro test pump discharge to accumulator valve V085. (CUE: SO reports V085 is open.) S / U FNP ILT-38 JPM Page 4 of 8 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *6. 4.1.1.7 Start the hydro test pump using local handswitch N1E21HS2100F. SO directed to start the hydro test pump. (CUE: SO reports the hydro test pump is started.) S / U *7. 4.1.1.8.1 Open ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091). HS for HV-8860 taken to open position. Observes red light lit, green light out. S / U *8 4.1.1.8.2 Open 1A ACCUM FILL LINE ISO Q1E21HV8878A (Q1E21V034A). HS for HV-8878A taken to open position. Observes red light lit, green light out. S / U *9. 4.1.1.9 Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947. HIK-947 is turned counterclockwise until SO reports that pressure is greater than Accumulator pressure. S / U 10. 4.1.1.10 Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, AND verify that only the desired accumulator shows an increase while filling. Accumulator levels are monitored. Observes 1A Accumulator level rising. S / U 11. 4.1.1.11 Monitor accumulator pressure indicators PI-921, 923,925, 927, 929, and 931 AND verify that only the desired accumulator shows a pressure increase while filling. Monitor accumulator pressures. Pressure should remain < 640 psig. Observes pressure rising. S / U

FNP ILT-38 JPM Page 5 of 8 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) When Accumulator level reaches 45% then: *12. 4.1.1.12.1 Adjust HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. HIK-947 taken fully clockwise. Observes HIK-947 Potentiometer fully clockwise, arrow at full right - 100%. S / U *13. 4.1.1.12.2 Close 1A ACCUM FILL LINE ISO Q1E21HV8878A (Q1E21V034A). Handswitch for HV-8878A taken to close position. Observes green light lit, red light out. S / U NOTE: Step 4.1.1.13 is N/A *14. 4.1.1.14.1 Close ACCUM FILL LINE ISO Q1E21HV8860 Q1E21V091). Handswitch for HV-8860 taken to close position. Observes green light lit, red light out. S / U *15. 4.1.1.14.2 Stop the hydro test pump. SO directed to stop the hydro test pump. (CUE: SO reports hydro test pump is stopped.) S / U 16. 4.1.1.15 Close ACCUM N2 VENT HIK 936 (Q1G21V092). ACCUM N2 VT HIK 936 (QV092) checked closed. Observes potentiometer fully counterclockwise - arrow at 0%. S / U 17. 4.1.1.16 Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. Observes HIK-947 Potentiometer fully clockwise, arrow at full right - 100. S / U *18. 4.1.1.17 Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC- V-8967). SO directed to close and lock V085. (CUE: SO reports that V085 is locked closed.) S / U FNP ILT-38 JPM Page 6 of 8 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *19. 4.1.1.18 Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). SO directed to close V028. (CUE: SO reports that V028 is closed.) S / U STOP TIME Terminate when Q1E21V028 is closed CRITICAL ELEMENTS: Critical Elements are denoted with an asterisk () preceding the element number. GENERAL REFERENCES 1. FNP-1-SOP-8.0, Version 43.0 2. K/A: 006A1.13 - 3.5 / 3.7 006A4.02 - 4.0 / 3.8 GENERAL TOOLS AND EQUIPMENT None FNP ILT-38 JPM Page 7 of 8 Critical ELEMENT justification: 1 Not Critical - Does not prevent filling the Accumulator. 2 Critical - Task completion. Required for system line up. 3-4 Not Critical - No actions taken by applicant. Check steps 5 Critical - Task completion. Required for system line up. 6 Critical - Task completion. Provides motive force for water to fill the accumulator 7, 8 Critical - Task completion. Required for system line up. 9 Critical - Task completion. Required for adequate pressure. 10, 11 Not Critical - No actions taken by applicant. 12 Critical - Task completion. Prevents overfilling Accumulator 13-15 Critical - Task completion. Proper system restoration. 16 Not Critical - No action taken by applicant. 18, 19 Critical - Task completion. Proper system restoration. COMMENTS FNP ILT-38 JPM HANDOUT Page 1 of 1 jpm a CONDITIONS When I tell you to begin, you are to FILL THE SIS ACCUMULATORS. The conditions under which this task is to be performed are: a. The Unit is at 100% power. b. The 1A accumulator level is 40% and pressure is 585 psig due to normal sampling. c. Chemistry has verified RWST boron concentration is suitable for makeup to the accumulator. d. You are directed to fill only the "1A" accumulator to 45% using FNP-1-SOP-8.0. e. Continuous communications have been established. f. The Rad Side SO is standing by with a copy of the procedure and the required locked valve key. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 1 of 72SAFETYSAFETY INJECTION SYSTEM - ACCUMULATORS RELATEDPROCEDURE LEVEL OF USE CLASSIFICATION PER NMP-AP-003 CATEGORYSECTIONSContinuous: ALL

Reference:

NONE Information: NONE Approved:David L Reed 04/10/2015 Operations Effective Date UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 2 of 72Procedure Version Description Version Number Version Description 41.0Updated procedure to requirements of NMP-OS-008-001, Operations Procedure Writing Instructions. Also revised mythology to fill and pressurize accumulators. 42.0Corrected sequence of applied cautions before steps 4.1.1.9 and 4.1.1.11. CR 353194 43.0DCP SNC540544 - Revised per mark-up provided. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 3 of 72Table of ContentsPage1.0Purpose .........................................................................................................................................42.0Initial Conditions ............................................................................................................................43.0Precautions and Limitations ..........................................................................................................44.0Instructions ....................................................................................................................................54.1Filling Accumulators at power ...........................................................................................54.2Draining Accumulators ....................................................................................................12 4.3Draining Accumulators with RCS Pressure Less Than 1000 psig...................................14 4.4Establishing a Nitrogen Atmosphere in the Accumulators ..............................................21 4.5Increasing Accumulator Nitrogen Pressure .....................................................................30 4.6Venting Accumulators .....................................................................................................334.7Pumping Accumulators to RWST With RCS Pressure Less Than 1000 psig .................354.8Complete Depressurization of All Accumulators to Support Outage Activities ................47 4.9Increasing Accumulator Nitrogen Pressure Using temporary Bottles ..............................495.0References ..................................................................................................................................536.0Records .......................................................................................................................................53APPENDIX 1 ...........................................................................................................................................54APPENDIX 2 ...........................................................................................................................................59APPENDIX 3 ...........................................................................................................................................64APPENDIX 4 ...........................................................................................................................................69 UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 4 of 721.0 Purpose This procedure provides the Initial Conditions, Precautions, Limitations, and Instructions for the operation of the Safety Injection System-Accumulators.2.0 Initial Conditions 2.1The Electrical Distribution System is energized and aligned for normal operation per FNP-1-SOP-36.0, Plant Electrical Distribution Line-Up, with exceptions noted. 2.2The accumulator valves and electrical distribution system are aligned per System Check List FNP-1-SOP-8.0A, Safety Injection System - Accumulators, with exceptions noted. 2.3The refueling water storage tank contains primary grade water borated to greater than 2300 ppm. 2.4The Nitrogen System is in service and aligned for normal operation per FNP-0-SOP-33.0, Nitrogen System. 3.0 Precautions and Limitations 3.1Accumulator pressure should be maintained between 605 and 645 psig inModes 1, 2, and 3. Do not exceed the accumulator design pressure of 700 psig. 3.2Do not allow accumulator level to exceed a high level of 55% or a low level of 35% in Modes 1, 2, and 3. 3.3Alert personnel in containment prior to venting accumulators. 3.41A, B, and C ACCUM DISCH ISO Q1E21MOV8808A, B, and C (Q1E21V038A, B, and C) should be closed when RCS pressure is less than 1000 psig and open when RCS pressure is greater than 1000 psig. 3.5The temperature of the accumulators must be kept above 70°F (the minimum temperature for pressurization) whenever the accumulators are pressurized. 3.6If any accumulator level rises significantly (approx. 5%) due to in-leakage from RCS, then sample the accumulator to verify boron concentration > 2300 ppm. 3.7Cross-connection of accumulators via N2 or Fill lines is prohibited in Modes 1, 2, or 3 (with RCS pressure greater than 1000 psig). This is because in the event of a LOCA, all cross-connected accumulators would depressurize through the faulted RCS loop. 3.8If increasing accumulator nitrogen pressure per Section 4.5 after establishing nitrogen atmosphere per section 4.4, then ensure the high pressure nitrogen banks are greater than 1000 psig prior to performing Section 4.5. 3.9Guidance in this procedure has the potential to impact reactivity. Close coordination with the control room operators is required to ensure proper reactivity management per NMP-OS-001, Reactivity Management Program. (AI 2008203128) UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 5 of 72NOTES Accumulator levels must be maintained between 35% and 55% while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). The accumulator boron concentration must be maintained between 2200 and 2500 ppm while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). The hydro test pump is a positive displacement pump, therefore a flowpath must be maintained at all times with pump running; so HIK-947 must remain open while pump is running to prevent lifting the relief valve. (CR 2008108980) CAUTIONCross-connection of accumulators via N2 or Fill lines is Prohibited in Modes 1, 2, or 3 (with RCS pressure greater than 1000 psig).4.0 Instructions 4.1Filling Accumulators at power 4.1.1Filling Accumulator 1A: 4.1.1.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.1.1.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.1.1.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.1.1.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.1.1.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. 4.1.1.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.1.7Start the hydro test pump using local handswitch N1E21HS2100F. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 6 of 724.1.1.8Perform the following: 4.1.1.8.1Open ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.1.8.2Open 1A ACCUM FILL LINE ISO Q1E21HV8878A (Q1E21V034A). CAUTIONAdjust pressure in the following step gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980) 4.1.1.9Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947.4.1.1.10Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, ANDverify that only the desired accumulator shows an increase while filling.NOTEIF accumulator pressure increases to greater than 640 psig, THEN the hydro test pump must be stopped AND the accumulator vented. CAUTIONEnsure accumulator pressure does not exceed 645 psig during filling, which is the setpoint for accumulator high pressure alarm. 4.1.1.11Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify that only the desired accumulator shows a pressure increase while filling. 4.1.1.12 WHEN the accumulator is filled to desired level, THEN perform the following: 4.1.1.12.1Adjust HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. 4.1.1.12.2Close 1A ACCUM FILL LINE ISO Q1E21HV8878A (Q1E21V034A). 4.1.1.13 IF additional accumulators are required to be filled, THEN proceed to Sections 4.1.2 OR 4.1.3. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 7 of 724.1.1.14 IF no additional accumulators require filling, THEN perform the following: 4.1.1.14.1Close ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.1.14.2Stop the hydro test pump. 4.1.1.15Close ACCUM N2 VENT HIK 936 (Q1G21V092). 4.1.1.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. 4.1.1.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.1.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).NOTEIn the following step, sampling is not required if the make up source was the RWST. 4.1.1.19 IF any accumulator level was increased more than 12% on the level indicator, THEN verify the boron concentration within 6 hours. 4.1.2Filling Accumulator 1B: 4.1.2.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.1.2.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.1.2.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.1.2.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.1.2.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. 4.1.2.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.2.7Start the hydro test pump using local handswitch N1E21HS2100F. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 8 of 724.1.2.8Perform the following: 4.1.2.8.1Open ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.2.8.2Open 1B ACCUM FILL LINE ISO Q1E21HV8878B (Q1E21V034B). 4.1.2.9Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947.CAUTIONAdjust pressure in the following step gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980) 4.1.2.10Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, to verify that only the desired accumulator shows an increase while filling.NOTEIf accumulator pressure increases to greater than 640 psig, then the hydro test pump must be stopped and the accumulator vented. 4.1.2.11Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify that only the desired accumulator shows a pressure increase while filling. CAUTIONEnsure accumulator pressure does not exceed 645 psig during filling, which is the setpoint for accumulator high pressure alarm. 4.1.2.12 WHEN the accumulator is filled to desired level, THEN perform the following: 4.1.2.12.1Adjust HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. 4.1.2.12.2Close 1B ACCUM FILL LINE ISO Q1E21HV8878B (Q1E21V034B). 4.1.2.13 IF additional accumulators are required to be filled, THEN proceed to Sections 4.1.1 or 4.1.3. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 9 of 724.1.2.14 IF no additional accumulators require filling, THEN perform the following: 4.1.2.14.1Close ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.2.14.2Stop the hydro test pump. 4.1.2.15Close ACCUM N2 VENT HIK 936 (Q1G21V092). 4.1.2.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. 4.1.2.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.2.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).NOTEIn the following step, sampling is not required if the make-up source was the RWST. 4.1.2.19 IF any accumulator level was increased more than 12% on the level indicator, THEN verify the boron concentration within 6 hours.4.1.3Filling Accumulator 1C: 4.1.3.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.1.3.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.1.3.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.1.3.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.1.3.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. 4.1.3.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.3.7Start the hydro test pump using local handswitch N1E21HS2100F. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 10 of 724.1.3.8Perform the following: 4.1.3.8.1Open ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.3.8.2Open 1C ACCUM FILL LINE ISO Q1E21HV8878C (Q1E21V034C). 4.1.3.9Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on local pressure indicator N1E21PI0947.CAUTIONAdjust pressure in the following step gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980) 4.1.3.10Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, ANDverify that only the desired accumulator shows an increase while filling.NOTEIf accumulator pressure increases to greater than 640 psig, the hydro test pump must be stopped and the accumulator vented. 4.1.3.11Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify that only the desired accumulator shows a pressure increase while filling. CAUTIONEnsure accumulator pressure does not exceed 645 psig during filling, which is the setpoint for accumulator high pressure alarm. 4.1.3.12 WHEN the accumulator is filled to desired level, THEN perform the following: 4.1.3.12.1Adjust HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. 4.1.3.12.2Close 1C ACCUM FILL LINE ISO Q1E21HV8878C (Q1E21V034C). 4.1.3.13 IF additional accumulators are required to be filled, THEN return to Sections 4.1.1 or 4.1.2. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 11 of 724.1.3.14 IF no additional accumulators require filling, THEN perform the following: 4.1.3.14.1Close ACCUM FILL LINE ISO Q1E21HV8860 (Q1E21V091).4.1.3.14.2Stop the hydro test pump. 4.1.3.15Close ACCUM N2 VENT HIK 936(Q1G21V092). 4.1.3.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. 4.1.3.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.1.3.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).NOTEIn the following step, sampling is not required if the make up source was the RWST. 4.1.3.19 IF any accumulator level was increased more than 12% on the level indicator, THEN verify the boron concentration within 6 hours. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 12 of 72CAUTIONSAccumulator levels must be maintained between 35% and 55% while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). Cross-connection of accumulators via N2 or Fill lines is Prohibited in Modes 1, 2 or 3 (with RCS pressure greater than 1000 psig).4.2Draining Accumulators:4.2.1Draining 1A Accumulator with RCS Pressure Greater Than 1000 psig: 4.2.1.1Open the following valves: ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. 4.2.1.2Open 1A ACCUM TEST LINE ISO, Q1E21HV8877A to commence draining accumulator. 4.2.1.3Monitor accumulator level indicators AND verify the water level in accumulator 1A is the only accumulator which shows a decrease in level. 4.2.1.4Monitor accumulator pressure while draining. NOTEIf pressure decreases to less than 610 psig, then draining must be secured AND accumulator pressurized. 4.2.1.5 WHEN the accumulator is drained to the desired level, THENclose the following valves: 1A ACCUM TEST LINE ISO, Q1E21HV8877A. ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. 4.2.2Draining 1B Accumulator with RCS Pressure Greater Than 1000 psig: 4.2.2.1Open the following valves: ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. 4.2.2.2Open 1B ACCUM TEST LINE ISO, Q1E21HV8877B to commence draining accumulator. 4.2.2.3Monitor accumulator level indicators AND verify the water level in accumulator 1B is the only accumulator which shows a decrease in level. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 13 of 724.2.2.4Monitor accumulator pressure while draining. NOTEIf pressure decreases to less than 610 psig, then draining must be secured and accumulator pressurized.4.2.2.5 WHEN the accumulator is drained to the desired level, THEN close the following valves: 1B ACCUM TEST LINE ISO, Q1E21HV8877B. ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. 4.2.3Draining 1C Accumulator with RCS Pressure Greater Than 1000 psig 4.2.3.1Open the following valves: ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. 4.2.3.2Open 1C ACCUM TEST LINE ISO, Q1E21HV8877C to commence draining accumulator. 4.2.3.3Monitor accumulator level indicators AND verify the water level in accumulator 1C is the only accumulator which shows a decrease in level. 4.2.3.4Monitor accumulator pressure while draining. NOTEIf pressure decreases to less than 610 psig, then draining must be secured and accumulator pressurized.4.2.3.5 WHEN the accumulator is drained to the desired level, THEN close the following valves: 1C ACCUM TEST LINE ISO, Q1E21HV8877C. ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 14 of 72NOTEDraining may be done using section 4.7, Pumping accumulators to RWST with RCS Pressure Less Than 1000 psig. If only a small level decrease is required, the accumulator may be drained via the sample system by Chemistry personnel per FNP-1-CCP-660 Sampling The Accumulators. 4.3Draining Accumulators with RCS Pressure Less Than 1000 psig 4.3.1Draining 1A Accumulator.4.3.1.1Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to start venting 1B ACCUM. 4.3.1.2Verify the RCDT system is aligned for normal operation (not cavity drain) per FNP-1-SOP-50.0, Liquid Waste Processing System. (AI 2003201775) 4.3.1.3Verify 1A ACCUM DISCH ISO, Q1E21MOV8808A is CLOSED.4.3.1.4Open 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 4.3.1.5Alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere.4.3.1.6 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092).4.3.1.7Monitor accumulator pressure during venting operation. 4.3.1.8 WHEN accumulator pressure has decreased to approximately 15 psig, THEN close the following valves: ACCUM N2 VENT HIK 936 (Q1G21V092). ACCUM N2 SUPP/VT ISO Q1E21HV8875A. 4.3.1.9Verify the following valves CLOSED: 1A ACCUM DRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). SIS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A).4.3.1.10Notify Maintenance to install spool piece in accumulator 1A drain line to RCDT pump suction. 4.3.1.11 WHENspool piece is installedTHEN, Open 1A ACCUMDRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 15 of 724.3.1.12Stop or verify stopped the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. 4.3.1.13Close the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. NOTEWhen the following lineup is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.3.1.14Open the following valves: SIS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A). RCDT LCV, Q1G21LCV1003. RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). (Located in 121' PPR) 4.3.1.15Start one of the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, then the operating RCDT pump will automatically stop. 4.3.1.16 WHEN desired accumulator level is reached, THEN perform the following: 4.3.1.16.1Stop the RCDT pump started in Step 4.3.1.15. 4.3.1.16.2Close RCDT LCV Q1G21LCV1003 (Q1G21V064).4.3.1.17Close the following valves: SIS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A). 1A ACCUM DRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 16 of 724.3.1.18Open the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. 4.3.1.19Restore the RCDT system to normal operation per FNP-1-SOP-50.0, Liquid Waste Processing System. 4.3.1.20Notify Maintenance to remove spool piece from accumulator 1A drain line to RCDT pump suction. 4.3.2Draining 1B Accumulator. 4.3.2.1Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to start venting 1C ACCUM. 4.3.2.2Verify the RCDT system is aligned for normal operation (not cavity drain) per FNP-1-SOP-50.0, Liquid Waste Processing System. (AI 2003201775) 4.3.2.3Verify 1B ACCUM DISCH ISO, Q1E21MOV8808B is CLOSED.4.3.2.4Open1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. 4.3.2.5Alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere.4.3.2.6 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092). 4.3.2.7Monitor accumulator pressure during venting operation.4.3.2.8 WHEN accumulator pressure has decreased to approximately15psig, THEN close the following valves: ACCUM N2 VENT HIK 936(Q1G21V092). 1B ACCUM N2 SUPP/VT ISO Q1E21HV8875B. 4.3.2.9Verify the following valves CLOSED: 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). SIS 1B ACCUM DRN, Q1G21V255B (1-LWP-V-7130B).4.3.2.10Notify Maintenance to install spool piece in accumulator 1B drain line to RCDT pump suction. 4.3.2.11 WHENspool piece is installed,THEN Open 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 17 of 724.3.2.12 Stop or verify stopped the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. 4.3.2.13Close the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. NOTEWhen the following line up is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.3.2.14Open the following valves: SIS 1B ACCUM DRN, Q1G21V255B (1-LWP-V-7130B). RCDT LCV, Q1G21LCV1003. RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). (Located in 121' PPR) 4.3.2.15Start one of the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, the operating RCDT pump will automatically stop. 4.3.2.16 WHEN desired accumulator level is reached, THEN perform the following: 4.3.2.16.1Stop the RCDT pump started in Step 4.3.2.15. 4.3.2.16.2Close RCDT LCV Q1G21LCV1003 (Q1G21V064).4.3.2.17Close the following valves: SIS 1B ACCUM DRN, Q1G21V255B (1-LWP-V-7130B). 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 18 of 724.3.2.18Open the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. 4.3.2.19Restore the RCDT system to normal operation per FNP-1-SOP-50.0, Liquid Waste Processing System. 4.3.2.20Notify Maintenance to remove spool piece from accumulator 1B drain line to RCDT pump suction. 4.3.3Draining 1C Accumulator: 4.3.3.1Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to start venting 1A ACCUM. 4.3.3.2 Verify that the RCDT system is aligned for normal operation (not cavity drain) per FNP-1-SOP-50.0, Liquid Waste Processing System. (AI 2003201775) 4.3.3.3Verify 1C ACCUM DISCH ISO, Q1E21MOV8808C is CLOSED. 4.3.3.4Open 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.3.3.5 Prior to venting, alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.3.3.6 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092). 4.3.3.7Monitor accumulator pressure during venting operation.4.3.3.8 WHEN accumulator pressure has decreased to approximately 15 psig, THEN close the following valves: ACCUM N2 VENT HIK 936(Q1G21V092). 1C ACCUM N2 SUPP/VT ISO Q1E21HV8875C. 4.3.3.9Verify the following valves CLOSED: 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). SIS 1C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C). 4.3.3.10Notify Maintenance to install spool piece in accumulator 1C drain line to RCDT pump suction. 4.3.3.11 WHENspool piece is installed,THEN Open 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 19 of 724.3.3.12Stop or verifystopped the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. 4.3.3.13Close the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. NOTEWHEN the following line-up is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.3.3.14Open the following valves: SIS 1C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C). RCDT LCV, Q1G21LCV1003. RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551). (Located in 121' PPR) 4.3.3.15Start one of the following RCDT pumps: RCDT pump 1A. RCDT pump 1B. NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, the operating RCDT pump will automatically stop. 4.3.3.16 WHEN desired accumulator level is reached, THEN perform the following: 4.3.3.16.1Stop the RCDT pump started in Step 4.3.3.15. 4.3.3.16.2Close RCDT LCV Q1G21LCV1003 (Q1G21V064).4.3.3.17Close the following valves: SIS C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C). 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 20 of 724.3.3.18Open the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. 4.3.3.19Restore the RCDT system to normal operation per FNP-1-SOP-50.0, Liquid Waste Processing System. 4.3.3.20Notify Maintenance to remove spool piece from accumulator 1C drain line to RCDT pump suction. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 21 of 724.4Establishing a Nitrogen Atmosphere in the Accumulators: 4.4.1Establishing a Nitrogen Atmosphere in Accumulator 1A4.4.1.1 IF required, THEN vent accumulator 1A to zero psig per Section 4.8. 4.4.1.2Open the following valves: 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. ACCUM N2 VENT HIK-936. 4.4.1.3Fill accumulator 1A per the following steps: 4.4.1.3.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.4.1.3.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.4.1.3.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.4.1.3.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.4.1.3.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED.4.4.1.3.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.1.3.7Start the hydro test pump using local handswitch N1E21HS2100F.4.4.1.3.8Open ACCUM FILL LINE ISO, Q1E21HV8860. 4.4.1.3.9Open 1A ACCUM FILL LINE ISO, Q1E21HV8878A.CAUTIONPressure should be adjusted gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980) 4.4.1.3.10Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 22 of 724.4.1.3.11Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, ANDverifyonly the desired accumulator shows an increase while filling.NOTEIf accumulator pressure increases to greater than 640 psig, the hydro test pump must be stopped and the accumulator vented. 4.4.1.3.12Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify only the desired accumulator shows a pressure increase while filling. 4.4.1.3.13 WHEN accumulator level reaches the indicating range, THEN verify level indicators show approximately same level. 4.4.1.3.14 IF level indicators are not approximately equal, THENcontact maintenance. NOTEEnsure accumulator pressure does not exceed 645 psig during filling, which is the setpoint for accumulator high pressure alarm. 4.4.1.3.15 WHEN the accumulator is filled to approximately mid scale on the MCB level indicators ( LI 920, LI922),THENperform the following: 4.4.1.3.15.1Adjust HYDRO TEST PMP DISCH CONT VLV full open using HIK 947. 4.4.1.3.15.2Close 1A ACCUM FILL LINE ISO, Q1E21HV8878A.4.4.1.3.15.3Close 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A.4.4.1.3.15.4Close ACCUM FILL LINE ISO, Q1E21HV8860.4.4.1.3.15.5Stop the hydro test pump. 4.4.1.3.15.6Close ACCUM N2 VENT HIK 936 (Q1G21V092).4.4.1.3.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 23 of 724.4.1.3.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.1.3.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.4.1.3.19Verify ACCUM N2 VENT HIK-936 CLOSED. 4.4.1.3.20Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 25 psig. (Located in 121' PPR) 4.4.1.3.21Open the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B.4.4.1.3.22Open 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A.4.4.1.3.23Open ACCUM N2 SUPPLY ISO, Q1E21HV8880. NOTEThe intent of the following is to pressurize the accumulator to approximately 25 psig. Stop at this point and wait for I&C to complete venting the lower level taps on the accumulator instruments. After venting is complete then continue with accumulator pressurization to the normal pressure band. 4.4.1.3.24 WHEN accumulator pressure reaches approximately 25 psig, THEN perform the following:4.4.1.3.24.1Close 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 4.4.1.3.24.2Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B.4.4.1.3.24.3Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 625 PSIG. (Located in 121' PPR). 4.4.1.3.24.4Close ACCUM N2 SUPP ISO, Q1E21HV8880. 4.4.1.3.24.5HaveI&C vent the lower level taps on the accumulator instruments. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 24 of 724.4.1.3.25 IF required, THEN increase accumulator pressure to the desired value per Section 4.5. 4.4.2Establishing a Nitrogen Atmosphere in Accumulator 1B4.4.2.1 IF required, THEN vent accumulator 1B to zero psig per Section 4.8. 4.4.2.2Open the following valves: 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. ACCUM N2 VENT HIK-936. 4.4.2.3Fill accumulator 1B per the following steps: 4.4.2.3.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.4.2.3.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.4.2.3.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.4.2.3.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.4.2.3.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED.4.4.2.3.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.2.3.7Start the hydro test pump using local handswitch N1E21HS2100F.4.4.2.3.8Open ACCUM FILL LINE ISO, Q1E21HV8860. 4.4.2.3.9Open 1B ACCUM FILL LINE ISO, Q1E21HV8878B.CAUTIONPressure should be adjusted gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980) 4.4.2.3.10Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 25 of 724.4.2.3.11Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, ANDverifyonly the desired accumulator shows an increase while filling.NOTEIf accumulator pressure increases to greater than 640 psig, then the hydro test pump must be stopped and the accumulator vented. 4.4.2.3.12Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify only the desired accumulator shows a pressure increase while filling. 4.4.2.3.13 WHEN accumulator level reaches the indicating range, THEN verify level indicators show approximately same level. 4.4.2.3.14 IF level indicators are not approximately equal, THENcontact Maintenance. 4.4.2.3.15 WHEN the accumulator is filled to approximately mid scale on the MCB level indicators ( LI- 924, LI- 926), THENperform the following: 4.4.2.3.15.1Adjust HYDRO TEST PMP DISCH CONT VLV full open using HIK 947. 4.4.2.3.15.2Close 1B ACCUM FILL LINE ISO, Q1E21HV8878B.4.4.2.3.15.3Close 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B.4.4.2.3.15.4Close ACCUM FILL LINE ISO, Q1E21HV8860.4.4.2.3.15.5Stop the hydro test pump. 4.4.2.3.15.6Close ACCUM N2 VENT HIK 936 (Q1G21V092).4.4.2.3.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. 4.4.2.3.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.2.3.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 26 of 724.4.2.3.19Verify ACCUM N2 VENT HIK-936 CLOSED. 4.4.2.3.20Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 25 psig. (Located in 121' PPR) 4.4.2.3.21Open the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B.4.4.2.3.22Open 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B.4.4.2.3.23Open ACCUM N2 SUPPLY ISO, Q1E21HV8880. NOTEThe intent of the following is to pressurize the accumulator to approximately 25 psig. Stop at this point and wait for I&C to complete venting the lower level taps on the accumulator instruments. After venting is complete then continue with accumulator pressurization to the normal pressure band. 4.4.2.3.24 WHEN accumulator pressure reaches approximately 25 psig, THEN perform the following:4.4.2.3.24.1Close 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B.4.4.2.3.24.2Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B.4.4.2.3.24.3Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 625 PSIG. (Located in 121' PPR) 4.4.2.3.24.4Close ACCUM N2 SUPP ISO, Q1E21HV8880.4.4.2.3.24.5HaveI&C vent the lower level taps on the accumulator instruments. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 27 of 724.4.2.3.25 IF required, THEN increase accumulator pressure to the desired value per Section 4.5. 4.4.3Establishing a Nitrogen Atmosphere in Accumulator 1C4.4.3.1 IF required, THEN vent accumulator 1C to zero psig per Section 4.8. 4.4.3.2Open the following valves: 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. ACCUM N2 VENT HIK-936. 4.4.3.3Fill accumulator 1C per the following steps: 4.4.3.3.1Verify RWST boron concentration is suitable for makeup to the accumulator. 4.4.3.3.2Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. 4.4.3.3.3Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.4.3.3.4Verify HYDRO TEST PUMP DISCH CONT VLV HIK N1E21V313, HIK-947 set to 100% open on the MCB. 4.4.3.3.5Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED.4.4.3.3.6Unlock AND open HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.3.3.7Start the hydro test pump using local handswitch N1E21HS2100F.4.4.3.3.8Open ACCUM FILL LINE ISO, Q1E21HV8860. 4.4.3.3.9Open 1C ACCUM FILL LINE ISO, Q1E21HV8878C.CAUTIONPressure should be adjusted gradually, reading pressure locally at hydro test pump on N1E21PI0947, while in contact with the Control Room (two people may be required locally to maintain communication). (CR 2008108980)4.4.3.3.10Adjust HYDRO TEST PUMP DISCH CONT VLV HIK 947 to maintain 665 psig on the local pressure indicator N1E21PI0947. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 28 of 724.4.3.3.11Monitor accumulator water level indicators LI-920, 922, 924, 926, 928, and 930, ANDverifyonly the desired accumulator shows an increase while filling.NOTEIf accumulator pressure increases to greater than 640 psig, then the hydro test pump must be stopped and the accumulator vented. 4.4.3.3.12Monitor accumulator pressure indicators PI-921, 923, 925, 927, 929, and 931 ANDverify only the desired accumulator shows a pressure increase while filling. 4.4.3.3.13 WHEN accumulator level reaches the indicating range, THEN verify level indicators show approximately same level. 4.4.3.3.14 IF level indicators are not approximately equal, THENcontact maintenance. NOTEEnsure accumulator pressure does not exceed 645 psig during filling, which is the setpoint for accumulator high pressure alarm. 4.4.3.3.15 WHEN the accumulator is filled to approximately mid scale on the MCB level indicators ( LI- 928, LI- 930), THENperform the following: 4.4.3.3.15.1Adjust HYDRO TEST PMP DISCH CONT VLV full open using HIK 947. 4.4.3.3.15.2Close 1C ACCUM FILL LINE ISO, Q1E21HV8878C.4.4.3.3.15.3Close 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C.4.4.3.3.15.4Close ACCUM FILL LINE ISO, Q1E21HV8860.4.4.3.3.15.5Stop the hydro test pump. 4.4.3.3.15.6Close ACCUM N2 VENT HIK 936 (Q1G21V092).4.4.3.3.16Verify HYDRO TEST PMP DISCH CONT VLV N1E21V313 fully open by adjusting HIK 947 on MCB to 100% demand. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 29 of 724.4.3.3.17Close AND lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). 4.4.3.3.18Close HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932).4.4.3.3.19Verify ACCUM N2 VENT HIK-936CLOSED.4.4.3.3.20Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 25 psig. (Located in 121' PPR) 4.4.3.3.21Open the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.4.3.3.22Open 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C.4.4.3.3.23Open ACCUM N2 SUPPLY ISO, Q1E21HV8880. NOTEThe intent of the following is to pressurize the accumulator to approximately 25 psig. Stop at this point and wait for I&C to complete venting the lower level taps on the accumulator instruments. After venting is complete then continue with accumulator pressurization to the normal pressure band. 4.4.3.3.24 WHEN accumulator pressure reaches approximately 25 psig, THEN perform the following: 4.4.3.3.24.1Close 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.4.3.3.24.2Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.4.3.3.24.3Adjust N2 SUPP TO ACCUM REGULATOR, N1E21V013 (1-CVC-PCV-8893) to approximately 625 PSIG. (Located in 121' PPR) 4.4.3.3.24.4Close ACCUM N2 SUPP ISO, Q1E21HV8880. 4.4.3.3.24.5HaveI&C vent the lower level taps on the accumulator instruments.4.4.3.3.25 IF required, THEN increase accumulator pressure to the desired value per Section 4.5. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 30 of 72CAUTIONS The nitrogen cover pressure should be maintained between 605 and 645 psig while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). Cross-connection of accumulators via N2 or Fill lines is Prohibited in Modes 1, 2, or 3 (with RCS pressure greater than 1000 psig). 4.5Increasing Accumulator Nitrogen Pressure 4.5.1IF increasing accumulator nitrogen pressure after establishing nitrogen atmosphere per Section 4.4, THEN ensure the high pressure nitrogen banks are greater than 1000 psig.4.5.2Increasing 1A Accumulator Nitrogen Pressure: 4.5.2.1Ensure nitrogen atmosphere has been established in 1A accumulator.4.5.2.2Verify ACCUM N2 VENT HIK 936(Q1E21V092) closed. 4.5.2.3Open OR check open the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.2.4Open OR checkopen ACCUM N2 SUPP ISO Q1E21HV8880, (Q1E21V059). 4.5.2.5Open 1A ACCUM N2 SUPP/VT ISO Q1E21HV8875A. 4.5.2.6Monitor accumulator pressure AND verify the pressure in accumulator 1A is the only accumulator which shows an increase in pressure. 4.5.2.7 WHEN pressure increases to approximately 625 psig, THENclose 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A.(Q1E21V047A).4.5.2.8 IF pressure is to be increased in another accumulator immediately, THEN proceed to Section 4.5.3 or 4.5.4. 4.5.2.9Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.2.10Close ACCUM N2 SUPP ISO Q1E21HV8880 (Q1E21V059). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 31 of 724.5.3Increasing 1B Accumulator Nitrogen Pressure: 4.5.3.1Ensure nitrogen atmosphere has been established in 1B accumulator.4.5.3.2Verify ACCUM N2 VENT HIK 936(Q1E21V092) CLOSED.4.5.3.3Open OR checkopen the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.3.4Open OR checkopen ACCUM N2 SUPP ISO Q1E21HV8880 (Q1E21V059). 4.5.3.5Open 1B ACCUM N2 SUPP/VT ISO Q1E21HV8875B. (Q1E21V047B).4.5.3.6Monitor accumulator pressure AND verify the pressure in accumulator 1B is the only accumulator which shows an increase in pressure. 4.5.3.7 WHEN pressure increases to approximately 625 psig, THENclose 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B.4.5.3.8 IF pressure is to be increased in another accumulator immediately, THEN proceed to Section 4.5.2 or 4.5.4. 4.5.3.9Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.3.10Close ACCUM N2 SUPP ISO, Q1E21HV8880. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 32 of 724.5.4Increasing 1C Accumulator Nitrogen Pressure: 4.5.4.1Ensure that a nitrogen atmosphere has been established in 1C accumulator. 4.5.4.2Verify ACCUM N2 VENT HIK 936(Q1E21V092) CLOSED.4.5.4.3Open OR check open the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.4.4Open OR checkopen ACCUM N2 SUPP ISO Q1E21HV8880 (Q1E21V059). 4.5.4.5Open 1C ACCUM N2 SUPP/VT ISO Q1E21HV8875C (Q1E21V047C).4.5.4.6Monitor accumulator pressure AND verify the pressure in accumulator 1C is the only accumulator which shows an increase in pressure. 4.5.4.7 WHEN pressure increases to approximately 625 psig, THENclose 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C.4.5.4.8 IF pressure is to be increased in another accumulator immediately, THEN proceed to Section 4.5.2 or 4.5.3. 4.5.4.9Close the following valves on the PRIP: ACCUM N2 SUPPLY ISOLATION, N1E21HV3938A. ACCUM N2 SUPPLY ISOLATION, N1E21HV3938B. 4.5.4.10Close ACCUM N2 SUPP ISO, Q1E21HV8880. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 33 of 72CAUTIONS The nitrogen cover pressure should be maintained between 605 and 645 psig while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). Cross-connection of accumulators via N2 or Fill lines is Prohibited in Modes 1, 2, or 3 (with RCS pressure greater than 1000 psig).4.6Venting Accumulators 4.6.1 Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to start venting accumulators. 4.6.2Prior to venting, alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.6.3Venting 1A Accumulator: 4.6.3.1Open 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 4.6.3.2Slowly open ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.3.3Monitor accumulator pressure AND verify the pressure in accumulator 1A is the only accumulator which shows a decrease in pressure. 4.6.3.4 WHEN pressure decreases to the desired value, THEN close ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.3.5Close 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A.4.6.4Venting 1B Accumulator: 4.6.4.1Open 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. 4.6.4.2 Slowly open ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.4.3Monitor accumulator pressure AND verify the pressure in accumulator 1B is the only accumulator which shows a decrease in pressure. 4.6.4.4 WHEN pressure decreases to the desired value, THEN close ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.4.5Close 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B.4.6.5Venting 1C Accumulator: 4.6.5.1Open 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.6.5.2 Slowly open ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.5.3Monitor accumulator pressure AND verify the pressure in accumulator 1C is the only accumulator which shows a decrease in pressure. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 34 of 724.6.5.4 WHEN pressure decreases to the desired value, THEN close ACCUM N2 VENT, HIK 936(Q1G21V092). 4.6.5.5Close 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 35 of 72NOTEThe accumulators may be pump to the RWST in any order. 4.7Pumping Accumulators to RWST With RCS Pressure Less Than 1000 psig 4.7.1 Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to vent accumulators. 4.7.2 Verify that the RCDT system is aligned for normal operation per Liquid Waste Processing System FNP-1-SOP-50.0A (with exceptions noted). 4.7.3Pumping 1A Accumulator to the RWST: 4.7.3.1 Prior to venting, alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.7.3.2 Verify 1A ACCUM DISCH ISO, Q1E21MOV8808AisCLOSED.4.7.3.3Verify 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A OPEN.4.7.3.4 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092).4.7.3.5Decrease accumulator pressure to 0 psig. 4.7.3.6Verify the following valves CLOSED: 1A ACCUM DRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). SIS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A).4.7.3.7Notify Maintenance to install spool piece in Accumulator 1A drain line to RCDT pump suction. 4.7.3.8 WHENspool piece is installedTHEN, Open 1A ACCUM DRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). 4.7.3.9Stop OR verify stopped the following RCDT pumps: 4.7.3.9.1 RCDT pump 1A. 4.7.3.9.2 RCDT pump 1B. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 36 of 724.7.3.10Close the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. NOTEWhen the following lineup is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.7.3.11Open the following valves: SIS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A). RCDT LCV, Q1G21LCV1003. 4.7.3.12Verify closed OR close the following valves: RCDT DISCH TO WHT, Q1G21V009 (1-LWP-V-7137). RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551).4.7.3.13Verify SFP purification loop is NOT in operation per FNP-1-SOP-54.0, Spent Fuel Pit Cooling And Purification System.4.7.3.14 IF RWST purification is in operation, THEN perform the following:4.7.3.14.1Stop the refueling water purification pump. 4.7.3.14.2CloseQ1G31HV033A, RWST TO RWPP AUTO ISO (MCB) 4.7.3.14.3Close Q1G31HV033B, RWST TO RWPP AUTO ISO (MCB) 4.7.3.15Open OR verifyopen the following valves: RWP PUMP DISCH LINE ISO, N1G31V008 (1-SFP-V-8792). SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B).4.7.3.16Verify RCDT PUMPS DISCH LINE ISO, Q1G21HV7136 OPEN. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 37 of 724.7.3.17Place the handswitch for RCDT PUMPS DISCH LINE ISO, Q1G21HV7136 in the AUTO position. NOTEThe operation of the refueling water purification pump is not required. SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B) should be throttled as necessary to limit flow through SFP demineralizer to < 100 GPM on FI-654. 4.7.3.18Open RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.7.3.19Open RCDT LCV, Q1G21LCV1003. 4.7.3.20Start one of the following RCDT pumps: RCDT pump 1A. OR RCDT pump 1B. NOTEThe RWP pump is not required; however, experience has shown it greatly increases flow and it is normally desired to have running. CAUTIONThe RWP pump does not have a low flow trip. 4.7.3.21 IF desired when pumping to the RWST, THEN start the RWP pump as follows:4.7.3.21.1Notify an operator at the refueling water purification pump to monitor discharge pressure of the pump. 4.7.3.21.2 IF the RWP pump discharge pressure indicator PI-3924 indicates a positive pressure due to a running RCDT pump, THEN the RWP pump may bestarted. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 38 of 72NOTETwo RCDT pumps may be required to prevent the RWP pump from cavitating. If a second RCDT pump is started, RCDT pump discharge pressure should be monitored to ensure the relief valve is not challenged (< 150 psig). CAUTIONRCDT pump discharge piping is protected from over pressurization by a relief valve at penetration 31 outside containment which discharges to the equipment drains. This relief valve can sustain seat leakage at pressures above 150 psig 4.7.3.22 IF necessary to prevent RWP pump cavitation, THEN start the second RCDT pump.NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, the operating RCDT pump will automatically stop. 4.7.3.23 WHEN draining is complete on 1A accumulator, THEN perform the following for the affected accumulator: 4.7.3.24 IF draining on all accumulators complete, THEN stop the REFUEL WATER PURIFICATION PUMP IF running. 4.7.3.24.1 IF draining on all accumulators complete, THEN secure the RCDT pump(s). 4.7.3.24.2Close SI SYS 1A ACCUM DRN, Q1G21V255A (1-LWP-V-7130A).4.7.3.24.3Close 1A ACCUM DRAIN TO RCDT, Q1E21V041A (1-CVC-V-8955A). 4.7.3.25GoTo Section 4.7.4, 4.7.5 or 4.7.6 as required. 4.7.4Pumping 1B Accumulator to the RWST: 4.7.4.1 Prior to venting, alert personnel in Containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.7.4.2Verify 1B ACCUM DISCH ISO, Q1E21MOV8808B is CLOSED.4.7.4.3Verify 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B is OPEN.4.7.4.4 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092).4.7.4.5Decrease accumulator pressure to 0 psig. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 39 of 724.7.4.6Verify the following valves CLOSED: 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). SIS 1B ACCUM DRN, Q1G21V255B (1-LWP-V-7130B).4.7.4.7Notify Maintenance to install spool piece in accumulator 1B drain line to RCDT pump suction. 4.7.4.8 WHENspool piece is installedTHEN, Open 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). 4.7.4.9Verify RCDT pumps 1A and 1B STOPPED. 4.7.4.10Close the following valves: RCDT OUTLET ISO, N1G21HV7127. RCDT RECIRC ISO, N1G21HV7144. NOTEWhen the following lineup is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.7.4.11Open the following valves: SIS 1B ACCUM DRN, Q1G21V255A (1-LWP-V-7130B). RCDT LCV, Q1G21LCV1003. 4.7.4.12Verifyclosed OR close the following valves. CDT DISCH TO WHT, Q1G21V009 (1-LWP-V-7137). RCDT PUMP DISCH TO RHT ISO, Q1E21V315 (1-CVC-V-8551).4.7.4.13Verify SFP purification loop is NOT in operation per FNP-1-SOP-54.0, Spent Fuel Pit Cooling And Purification System. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 40 of 724.7.4.14 IF RWST purification is in operation, THEN perform the following:4.7.4.14.1Stop the refueling water purification pump. 4.7.4.14.2CloseQ1G31HV033A, RWST TO RWPP AUTO ISO (MCB) 4.7.4.14.3Close Q1G31HV033B, RWST TO RWPP AUTO ISO (MCB) 4.7.4.15Open OR verifyopen the following valves: RWP PUMP DISCH LINE ISO, N1G31V008 (1-SFP-V-8792). SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B).4.7.4.16Verify RCDT PUMPS DISCH LINE ISO, Q1G21HV7136 OPEN.4.7.4.17Place the handswitch for RCDT PUMPS DISCH LINE ISO, Q1G21HV7136 in the AUTO position. NOTEThe operation of the refueling water purification pump is not required. SFP PURIF OUTLET TO RWST, N1G31V021B (1-SFP-V-8793B) should be throttled as necessary to limit flow through SFP demineralizer to < 100 GPM on FI-654. 4.7.4.18Open RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.7.4.19Open RCDT LCV, Q1G21LCV1003. 4.7.4.20Start one of the following RCDT pumps: RCDT pump 1A. OR RCDT pump 1B. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 41 of 72NOTEThe RWP pump is not required; however, experience has shown it greatly increases flow and it is normally desired to have running. CAUTIONThe RWP pump does not have a low flow trip. 4.7.4.21 IF desired when pumping to the RWST, THEN start the RWP pump as follows: 4.7.4.21.1Notify an operator at the refueling water purification pump to monitor discharge pressure of the pump. 4.7.4.21.2 IF the RWP pump discharge pressure indicator PI-3924 indicates a positive pressure due to a running RCDT pump, THEN the RWP pump may bestarted.NOTETwo RCDT pumps may be required to prevent the RWP pump from cavitating. If a second RCDT pump is started, RCDT pump discharge pressure should be monitored to ensure the relief valve is not challenged (< 150 psig). CAUTIONRCDT pump discharge piping is protected from over pressurization by a relief valve at penetration 31 outside containment which discharges to the equipment drains. This relief valve can sustain seat leakage at pressures above 150 psig. 4.7.4.22 IF necessary to prevent RWP pump cavitation, THEN start the second RCDT pump. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 42 of 72NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, the operating RCDT pump will automatically stop. 4.7.4.23 WHEN draining is complete on 1B accumulator, THEN perform the following for the affected accumulator: 4.7.4.23.1 IF draining on all accumulators complete, THEN stop the REFUEL WATER PURIFICATION PUMP,IF running. 4.7.4.23.2 IF draining on all accumulators complete, THEN secure the RCDT pump(s). 4.7.4.23.3Close SI SYS 1B ACCUM DRN, Q1G21V255B(1-LWP-V-7130B).4.7.4.23.4Close 1B ACCUM DRAIN TO RCDT, Q1E21V041B (1-CVC-V-8955B). 4.7.4.24Go to Section 4.7.3, 4.7.5 or 4.7.6 as required. 4.7.5Pumping 1C Accumulator to the RWST: 4.7.5.1 Prior to venting, alert personnel in Containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.7.5.2Verify 1C ACCUM DISCH ISO, Q1E21MOV8808C is CLOSED.4.7.5.3Verify 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C is OPEN.4.7.5.4 SLOWLY open ACCUM N2 VENT HIK 936 (Q1G21V092).4.7.5.5Decrease accumulator pressure to 0 psig. 4.7.5.6Verify the following valves CLOSED: 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). SI SYS 1C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C).4.7.5.7 Notify Maintenance to install spool piece in accumulator 1C drain line to RCDT pump suction. 4.7.5.8 WHENspool piece is installedTHEN,Open 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 43 of 724.7.5.9Verify RCDT pumps 1A and 1B STOPPED. 4.7.5.10Close the following valves: RCDT OUTLET ISO, N1G21HV7127 (N1G21V006). RCDT RECIRC ISO, N1G21HV7144 (N1G21V106). NOTEWhen the following lineup is complete, the source and receipt tanks should be frequently monitored for level changes. Due to the different elevations and system pressures, fluid may transfer with or without RCDT Pump operation. (CR2010106296) 4.7.5.11Open the following valves: SI SYS 1C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C). RCDT LCV Q1G21LCV1003 (Q1G21V064). 4.7.5.12Verifyclosed OR close the following valves: RCDT DISCH TO WHT Q1G21V009 (1-LWP-V-7137). RCDT PUMP DISCH TO RHT ISO Q1E21V315 (1-CVC-V-8551).4.7.5.13Verify SFP purification loop is NOT in operation per FNP-1-SOP-54.0, Spent Fuel Pit Cooling and Purification System.4.7.5.14 IF RWST purification is in operation, THEN perform the following: 4.7.5.14.1Stop the refueling water purification pump. 4.7.5.14.2CloseQ1G31HV033A, RWST TO RWPP AUTO ISO (MCB) 4.7.5.14.3Close Q1G31HV033B, RWST TO RWPP AUTO ISO (MCB) 4.7.5.15Open or verifyopen the following valves: RWP PUMP DISCH LINE ISO, N1G31V008 (1-SFP-V-8792). SFP PURIF OUTLET TO RWST N1G31V021B (1-SFP-V-8793B).4.7.5.16Verify RCDT PUMPS DISCH LINE ISO Q1G21HV7136 (Q1G21V006) OPEN. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 44 of 724.7.5.17Place the handswitch for RCDT PUMPS DISCH LINE ISO Q1G21HV7136 (Q1G21V006) is in the AUTO position. NOTEThe operation of the refueling water purification pump is not required. 1-SFP-V-8793B (N1G31V021B) should be throttled as necessary to limit flow through SFP demineralizer to 100 GPM on FI-654. 4.7.5.18Open RCDT DISCH TO SFPCS RWPP SUCT Q1G21V008 (1-LWP-V-7138). 4.7.5.19Open RCDT LCV Q1G21LCV1003 (Q1G21V064).4.7.5.20Start one of the following RCDT pumps: RCDT pump 1A. OR RCDT pump 1B. NOTEThe RWP pump is not required; however, experience has shown it greatly increases flow and it is normally desired to have running. CAUTIONThe RWP pump does not have a low flow trip. 4.7.5.21 IF desired when pumping to the RWST, THEN start the RWP pump as follows: 4.7.5.21.1Notify an operator at the refueling water purification pump to monitor discharge pressure of the pump. 4.7.5.21.2 IF the RWP pump discharge pressure indicator PI-3924 indicates a positive pressure due to a running RCDT pump, THEN the RWP pump may bestarted. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 45 of 72NOTETwo RCDT pumps may be required to prevent the RWP pump from cavitating. If a second RCDT pump is started,RCDT pump discharge pressure should be monitored to ensure the relief valve is not challenged (< 150 psig). CAUTIONRCDT pump discharge piping is protected from over pressurization by a relief valve at penetration 31 outside containment which discharges to the equipment drains. This relief valve can sustain seat leakage at pressures above 150 psig. 4.7.5.22 IF necessary to prevent RWP pump cavitation, THEN start the second RCDT pump.NOTEIf the RCDT pump discharge flow decreases to less than 85 gpm, the operating RCDT pump will automatically stop. 4.7.5.23 WHEN draining is complete on 1C accumulator, THEN perform the following for the affected accumulator: 4.7.5.23.1 IF draining on all accumulators complete, THEN stop the REFUEL WATER PURIFICATION PUMP,IF running. 4.7.5.23.2 IF draining on all accumulators complete, THEN secure the RCDT pump(s). 4.7.5.23.3Close SI SYS 1C ACCUM DRN, Q1G21V255C (1-LWP-V-7130C).4.7.5.23.4Close 1C ACCUM DRAIN TO RCDT, Q1E21V041C (1-CVC-V-8955C). 4.7.5.24GoTo sections 4.7.3, 4.7.4 or 4.7.6 as required. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 46 of 72NOTEThe remainder of this procedure section is meant to be performed after all accumulator draining is completed. 4.7.6Realignment After Pumping to the RWST: 4.7.6.1 IF running, THEN stop the REFUEL WATER PURIFICATION PUMP. 4.7.6.2 IF running, THEN shutdown the RCDT pump(s). 4.7.6.3Realign valves as follows: 4.7.6.3.1Close RCDT DISCH TO SFPCS RWPP SUCT, Q1G21V008 (1-LWP-V-7138). 4.7.6.3.2Close RWP PUMP DISCH LINE ISO, N1G31V008 (1-SFP-V-8792). 4.7.6.3.3Close SFP PURIF OUTLET TO RWST N1G31V021B (1-SFP-V-8793B). 4.7.6.3.4Close RCDT LCV Q1G21LCV1003 (Q1G21V064).4.7.6.3.5OpenRCDT to RHT Q1E21V315 (1-CVC-V8551) 4.7.6.4Open the following valves: RCDT OUTLET ISO N1G21HV7127 (N1G21V006). RCDT RECIRC ISO N1G21HV7144 (N1G21V106). 4.7.6.5Restore the RCDT to normal operation per FNP-1-SOP-50.0, Liquid Waste Processing System. 4.7.6.6Close the following valves: ACCUM N2 VT HIK-936 (Q1E21V092). 1C ACCUM N2 SUPP/VT ISO Q1E21HV8875C (Q1E21V047C).4.7.6.7Notify Maintenance to remove spool piece from accumulator drain lines to RCDT pump suction. 4.7.6.8Realign RWST OR SFP purification as required. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 47 of 72NOTEThis section should only be used in Modes 4, 5 or 6 and is intended to maintain the accumulators in a depressurized state. Steps 4.8.3, 4.8.4 and 4.8.5 may be performed in any order.4.8Complete Depressurization of All Accumulators to Support Outage Activities 4.8.1 Coordinate with OCC or CTMT Coordinator to determine the most appropriate time to start venting accumulators. 4.8.2Prior to venting, alert personnel in containment that nitrogen will be vented from the accumulators into the containment atmosphere. 4.8.3Depressurizing 1A Accumulator: 4.8.3.1Open 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 4.8.3.2 SLOWLY open ACCUM N2 VENT, HIK 936 (Q1G21V092). 4.8.3.3Monitor accumulator pressure AND verify the pressure in accumulator 1A is the only accumulator which shows a decrease in pressure. 4.8.3.4 WHEN pressure decreases to zero, THEN close ACCUM N2 VENT, HIK 936 (Q1G21V092). 4.8.3.5Close 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 4.8.4Depressurizing 1B Accumulator: 4.8.4.1Open 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. 4.8.4.2 SLOWLY open ACCUM N2 VENT, HIK 936 (Q1G21V092). 4.8.4.3Monitor accumulator pressure AND verify the pressure in accumulator 1B is the only accumulator which shows a decrease in pressure. 4.8.4.4 WHEN pressure decreases to zero, THEN close ACCUM N2 VENT, HIK 936 (Q1G21V092). 4.8.4.5Close 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 48 of 724.8.5Depressurizing 1C Accumulator: 4.8.5.1Open 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.8.5.2 SLOWLY open ACCUM N2 VENT, HIK 936 (Q1G21V092). 4.8.5.3Monitor accumulator pressure AND verify the pressure in accumulator 1C is the only accumulator which shows a decrease in pressure. 4.8.5.4 WHEN pressure decreases to zero, THEN close ACCUM N2 VENT, HIK 936(Q1G21V092). 4.8.5.5Close 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.8.6WHEN all accumulators have been depressurized,THENperform the following: 4.8.6.1Open the following valves: 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.8.6.2 Slowly open ACCUM N2 VENT, HIK 936(Q1G21V092). 4.8.7WHEN activities are complete that required complete depressurization of the accumulators, THEN perform the following:4.8.7.1Close the following valves: 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. 4.8.7.2Close ACCUM N2 VENT, HIK 936(Q1G21V092). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 49 of 72CAUTIONSThe nitrogen cover pressure should be maintained between 605 and 645 psig while in operational modes 1, 2, and 3 (with RCS pressure greater than 1000 psig). Cross-connection of accumulators via N2 or Fill lines is Prohibited in Modes 1, 2, or 3 (with RCS pressure greater than 1000 psig).4.9Increasing Accumulator Nitrogen Pressure Using temporary Bottles 4.9.1 Ensure a nitrogen atmosphere has been established in the accumulator(s) to be pressurized. 4.9.2 Verify ACCUM N2 VT HIK 936 (Q1E21V092) CLOSED. 4.9.3 Close the following valves: ACCUM N2 SUPPLY ROOT (Active Bank) N1E21V002A.(Aux. BLDG 155' Nitrogen Storage Rm.) ACCUM N2 SUPPLY ROOT (Reserve Bank) N1E21V002B. (Aux. BLDG 155' Nitrogen Storage Rm.) 4.9.4 Verify the following valves CLOSED: PRIP NITROGEN SUPPLY ISOLATION VALVE N1E21HV3938A. PRIP NITROGEN SUPPLY ISOLATION VALVE N1E21HV3938B.NOTEIt will take approximately 3 Nitrogen bottles to raise accumulator pressure from 610 psig to 625 psig. 4.9.5 Secure the required Nitrogen bottles near penetration 63. (121' Piping Pen Rm.)4.9.6 Install a regulator capable of supplying 650 psig pressure on one of the N2 bottles ANDconnect discharge to piping downstream of ACCUM N2 SUPP TEST DRAIN, N1E21V303B.4.9.7 Open the isolation valve on the Nitrogen bottle AND adjustthe output of the regulator to approximately 625 psig. 4.9.8 Open the following valves: ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B. ACCUM N2 SUPPLY TEST DRAIN ROOT N1E21V303A. 4.9.9 Open ACCUM N2 SUPP ISO Q1E21HV8880 (Q1E21V059). UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 50 of 724.9.10IF pressurizing 1A Accumulator, THEN perform the following: 4.9.10.1Open 1A ACCUM N2 SUPP/VT ISO Q1E21HV8875A (Q1E21V047A).4.9.10.2Monitor accumulator pressure AND verify the pressure in accumulator 1A is the only accumulator which shows an increase in pressure. 4.9.10.3 IF necessary to change out bottles while increasing pressure, THEN: 4.9.10.3.1Close ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B.4.9.10.3.2Close the isolation valve on the in use Nitrogen bottle.4.9.10.3.3Remove the regulator from the in use Nitrogen bottle.4.9.10.3.4Install the regulator on a full Nitrogen bottle.4.9.10.3.5Open the Nitrogen bottle isolation valve.4.9.10.3.6Ensure that the regulator is still set for approximately 625 psig. 4.9.10.3.7Open ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B.4.9.10.4 WHEN pressure increases to approximately 625 psig, THENclose 1A ACCUM N2 SUPP/VT ISO Q1E21HV8875A (Q1E21V047A). 4.9.11IF pressurizing 1B Accumulator, THEN perform the following: 4.9.11.1Open 1B ACCUM. N2 SUPP/VT ISO Q1E21HV8875B (Q1E21V047B).4.9.11.2Monitor accumulator pressure AND verify the pressure in accumulator 1B is the only accumulator which shows an increase in pressure. 4.9.11.3 IF necessary to change out bottles while increasing pressure, THEN: UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 51 of 724.9.11.3.1Close ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B.4.9.11.3.2Close the isolation valve on the in use Nitrogen bottle.4.9.11.3.3Remove the regulator from the in use Nitrogen bottle.4.9.11.3.4Install the regulator on a full Nitrogen bottle.4.9.11.3.5Open the Nitrogen bottle isolation valve.4.9.11.3.6Ensure that the regulator is still set for approximately 625 psig. 4.9.11.3.7Open ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B.4.9.11.4 WHEN pressure increases to approximately 625 psig, THENclose 1B ACCUM N2 SUPP/VT ISO Q1E21HV8875B (Q1E21V047B). 4.9.12IF pressurizing 1C Accumulator, THEN perform the following: 4.9.12.1Open 1C ACCUM. N2 SUPP/VT ISO Q1E21HV8875C (Q1E21V047C).4.9.12.2Monitor accumulator pressure AND verify the pressure in accumulator 1C is the only accumulator which shows an increase in pressure. 4.9.12.3 IF necessary to change out bottles while increasing pressure, THEN:4.9.12.3.1Close ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B.4.9.12.3.2Close the isolation valve on the in use Nitrogen bottle.4.9.12.3.3Remove the regulator from the in use Nitrogen bottle.4.9.12.3.4Install the regulator on a full Nitrogen bottle.4.9.12.3.5Open the Nitrogen bottle isolation valve.4.9.12.3.6Ensure that the regulator is still set for approximately 625 psig. 4.9.12.3.7Open ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 52 of 724.9.12.4 WHEN pressure increases to approximately 625 psig, THENclose 1C ACCUM N2 SUPP/VT ISO Q1E21HV8875C (Q1E21V047C). 4.9.13 Close the following valves: ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B. ACCUM N2 SUPPLY TEST DRAIN ROOT N1E21V303A. 4.9.14 Close ACCUM N2 SUPP ISO Q1E21HV8880 (Q1E21V059). 4.9.15 Open ACCUM N2 SUPPLY ROOT (Active Bank) N1E21V002A. (Aux. BLDG 155' Nitrogen Storage Rm.)4.9.16WHEN nitrogen bottles are no longer required, THEN performthe following: 4.9.16.1Ensure isolation valve on the nitrogen bottle connected for use is closed. 4.9.16.2Disconnect the regulator from ACCUM N2 SUPPLY TEST DRAIN ISOL N1E21V303B. 4.9.16.3Disconnect regulator from the nitrogen bottle. 4.9.16.4Remove all nitrogen bottles and the regulator from the 121 piping penetration room. 4.9.16.5Place the nitrogen bottles and regulator in the appropriate storage locations. UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 53 of 725.0 References 5.1D-175038 (Sh 1-2), Safety Injection System 5.2D-175039 (Sh 1-4), CVCS 5.3D-175042 (Sh 1), Waste Processing System 5.4D-175043, Spent Fuel Pool Cooling System 6.0 Records QARecord(X)Non-QARecord(X)Record Generated Retention Time R-Type X FNP-1-SOP-8.0 Life of plant HH6.051 UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 54 of 72APPENDIX 1 FEED AND BLEED OF ACCUMULATOR 1A TO RAISE BORON CONCENTRATION > 2300 PPM Performed by: DateReviewed by: DateThis appendix consists of 4 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 55 of 72APPENDIX 1 FEED AND BLEED OF ACCUMULATOR 1ATO RAISE BORON CONCENTRATION > 2300 PPM (Page 1 of 4) 1.0 Purpose This appendix is written to address in-leakage into 1A accumulator from the RCS and the associated concern for a reduction in boron concentration. 2.0 Precautions and Limitations 2.1Utilizing this method of Feed and Bleed, reactor coolant will backfill the accumulator discharge line up to the accumulator test line connection. 2.2A 1% increase in accumulator level = 8.3 gallons. 2.3Sample flushes should be minimized to only that required to obtain sample when sampling an accumulator that has in-leakage to prevent accumulator from filling with RCS water. 2.4Do not use extended sampling as method to drain accumulators as this would allow the accumulator to slowly fill with RCS water and dilute accumulator boron concentration.2.5Tech Specs require the accumulator be sampled within 6 hours after each solution volume increase of 1% of tank volume (approximately 12% increase in level). 3.0 Initial Conditions 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 56 of 72APPENDIX 1 FEED AND BLEED OF ACCUMULATOR 1ATO RAISE BORON CONCENTRATION > 2300 PPM (Page 2 of 4) 4.0 Instructions 4.1 Record initial Accumulator 1A boron concentration. _____ Boron concentration ppm CAUTIONSAccumulator level must be maintained between 35% and 55%; the intent of this appendix is to finish the feed and bleed at approximately 40%. Accumulator boron concentration must be maintained between 2200 and 2500 ppm; the intent of this appendix is to raise accumulator boron concentration > 2300 ppm. 4.2Aligning Accumulator 1A for Filling 4.2.1 Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. _____ 4.2.2 Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). _____ 4.2.3 Set HYDRO TEST PUMP DISCH CONT VLV, HIK 947, to OPEN._____4.2.4 Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. _____ 4.2.5 Start the hydro test pump. _____ 4.2.6 Unlock ANDopen HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). _____ 4.2.7 Open the following valves: ACCUM FILL LINE ISO, Q1E21HV8860. _____ 1A ACCUM FILL LINE ISO, Q1E21HV8878A _____ 4.3IF desired for trending purposes, THENnotify Chemistry to sample accumulator test line at start of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B) _____ 4.3.1 Record the boron concentration ppm UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 57 of 72APPENDIX 1 FEED AND BLEED OF ACCUMULATOR 1ATO RAISE BORON CONCENTRATION > 2300 PPM (Page 3 of 4) 4.4Aligning Accumulator 1A for Draining 4.4.1 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ 4.4.2 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.4.3 Open 1A ACCUM TEST LINE ISO, Q1E21HV8877A to commence draining accumulator. _____ 4.5 Adjust HYDRO TEST PUMP DISCH CONT VLV, using HIK 947 to control fill rate to match drain rate. _____ CAUTIONIf accumulator 1A level exceeds 55% or decreases below 35%, then stop feed and bleed and restore level. 4.6 Monitor Accumulator 1A, level. 4.6.1 Verify that only 1A accumulator level is changing. _____ 4.6.2 Verify all other accumulator levels remain constant. _____ CAUTIONIf accumulator 1A pressure exceeds 640 psig or decreases below 610 psig, stop feed and bleed and restore pressure. 4.7 Monitor Accumulator 1A pressures.4.7.1 Verify that 1A accumulator pressure is changing. _____ 4.7.2 Verify all other accumulator pressures remain constant. _____ 4.8 Continue Accumulator 1A feed and bleed for approximately 1 hour OR as specified by Shift Supervisor. _____ 4.9IF desired for trending purposes, THEN notify Chemistry to sample accumulator test line prior to completion of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B)_____4.9.1 Record boron concentration ppm. 4.10WHEN Accumulator 1A feed AND bleed is complete, THEN adjustHYDRO TEST PUMP DISCH CONT VLV, HIK 947 to open. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 58 of 72APPENDIX 1 FEED AND BLEED OF ACCUMULATOR 1ATO RAISE BORON CONCENTRATION > 2300 PPM (Page 4 of 4) 4.11 Secure Accumulator 1A draining as follows: 4.11.1 Close the following valves: 1A ACCUM TEST LINE ISO, Q1E21HV8877A. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.12 Secure Accumulator 1A filling as follows: 4.12.1 Stop the hydro test pump. _____ 4.12.2 Close the following valves: 1A ACCUM FILL LINE ISO, Q1E21HV8878A. _____ ACCUM FILL LINE ISO, Q1E21HV8860. _____ HYDRO TEST PUMP SUCT, Q1E21V028(1-CVC-V-8932) _____ 4.12.3 Lockclosed HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). _____ 4.12.4 Verify the following valves CLOSED: 1A ACCUM N2 SUPP/VT ISO, Q1E21HV8875A. _____ ACCUM N2 VENT, HIK 936(Q1G21V092). _____ 4.12.5 Verify HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. _____ 4.13 Notify Chemistry to sample Accumulator 1A for boron concentration ANDrecord boron concentration. _____ Boron concentration ppm. 4.14IF boron concentration < 2300 ppm, THEN perform additional feed AND bleeds. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 59 of 72APPENDIX 2 FEED AND BLEED OF ACCUMULATOR 1B TO RAISE BORON CONCENTRATION > 2300 PPM Performed by: DateReviewed by: DateThis appendix consists of 4 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 60 of 72APPENDIX 2 FEED AND BLEED OF ACCUMULATOR 1BTO RAISE BORON CONCENTRATION > 2300 PPM (Page 1 of 4) 1.0 Purpose This appendix is written to address in-leakage into 1B accumulator from the RCS and the associated concern for a reduction in boron concentration. 2.0 Precautions and Limitations 2.1Utilizing this method of Feed and Bleed, reactor coolant will backfill the accumulator discharge line up to the accumulator test line connection. 2.2A 1% increase in accumulator level = 8.3 gallons. 2.3Sample flushes should be minimized to only that required to obtain sample when sampling an accumulator that has in-leakage to prevent accumulator from filling with RCS water. 2.4Do not use extended sampling as method to drain accumulators as this would allow the accumulator to slowly fill with RCS water and dilute accumulator boron concentration.2.5Tech Specs require the accumulator be sampled within 6 hours after each solution volume increase of 1% of tank volume (approximately 12% increase in level). 3.0 Initial Conditions 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 61 of 72APPENDIX 2 FEED AND BLEED OF ACCUMULATOR 1BTO RAISE BORON CONCENTRATION > 2300 PPM (Page 2 of 4) 4.0 Instructions 4.1 Record initial Accumulator 1B boron concentration. _____ Boron Concentration ppm CAUTIONSAccumulator level must be maintained between 35% and 55%; the intent of this appendix is to finish the feed and bleed at approximately 40%. Accumulator boron concentration must be maintained between 2200 and 2500 ppm; the intent of this appendix is to raise accumulator boron concentration > 2300 ppm. 4.2Aligning Accumulator 1B for Filling 4.2.1 Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. _____ 4.2.2 Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). _____ 4.2.3 Set HYDRO TEST PUMP DISCH CONT VLV, HIK 947, to OPEN._____4.2.4 Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. _____ 4.2.5 Start the hydro test pump. _____ 4.2.6 Unlock ANDopen HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). _____ 4.2.7 Open the following valves: _____ ACCUM FILL LINE ISO, Q1E21HV8860. _____ 1B ACCUM FILL LINE ISO, Q1E21HV8878B _____ 4.3IF desired for trending purposes, THEN have Chemistry sampleaccumulator test line at start of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B) _____ 4.3.1 Record the boron concentration ppm UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 62 of 72APPENDIX 2 FEED AND BLEED OF ACCUMULATOR 1BTO RAISE BORON CONCENTRATION > 2300 PPM (Page 3 of 4) 4.4Aligning Accumulator 1B for Draining 4.4.1 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ 4.4.2 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.4.3 Open 1B ACCUM TEST LINE ISO, Q1E21HV8877B to commence draining accumulator. _____ 4.5 Adjust HYDRO TEST PUMP DISCH CONT VLV, using HIK 947 to control fill rate to match drain rate. _____ CAUTIONIf accumulator 1B level exceeds 55% or decreases below 35%, stop feed and bleed and restore level. 4.6 Monitor Accumulator 1B level. 4.6.1 Verify that only 1B accumulator level is changing. _____ 4.6.2 Verify all other accumulator levels remain constant. _____ CAUTIONIf accumulator 1B pressure exceeds 640 psig or decreases below 610 psig, stop feed and bleed and restore pressure. 4.7 Monitor Accumulator 1B pressures. 4.7.1 Verify that 1B accumulator pressure is changing. _____ 4.7.2 Verify all other accumulator pressures remain constant. _____ 4.8 Continue Accumulator 1B feed and bleed for approximately 1 hour or as specified by Shift Supervisor. _____ 4.9IF desired for trending purposes, THENnotify Chemistry to sample accumulator test line prior to completion of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B)_____4.9.1 Record boron concentration ppm. 4.10WHEN Accumulator 1B feed and bleed is complete, THEN adjustHYDRO TEST PUMP DISCH CONT VLV, HIK 947 to open. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 63 of 72APPENDIX 2 FEED AND BLEED OF ACCUMULATOR 1BTO RAISE BORON CONCENTRATION > 2300 PPM (Page 4 of 4) 4.11 Secure Accumulator 1B draining as follows: 4.11.1 Close the following valves: 1B ACCUM TEST LINE ISO, Q1E21HV8877B. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.12 Secure Accumulator 1B filling as follows: 4.12.1 Stop the hydro test pump. _____ 4.12.2 Close the following valves: 1B ACCUM FILL LINE ISO, Q1E21HV8878B. _____ ACCUM FILL LINE ISO, Q1E21HV8860. _____ HYDRO TEST PUMP SUCT Q1E21V028 (1-CVC-V-8932) _____ 4.12.3 Lock closed HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). _____ 4.12.4 Verify the following valves CLOSED: 1B ACCUM N2 SUPP/VT ISO, Q1E21HV8875B. _____ ACCUM N2 VENT, HIK 936(Q1G21V092). _____ 4.12.5 Verify HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. _____ 4.13 Notify Chemistry to sample Accumulator 1B for boron concentration ANDrecord boron concentration. _____ Boron concentration ppm. 4.14IF boron concentration < 2300 ppm, THEN perform additional feed and bleeds._____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 64 of 72APPENDIX 3 FEED AND BLEED OF ACCUMULATOR 1C TO RAISE BORON CONCENTRATION > 2300 PPM Performed by: DateReviewed by: DateThis appendix consists of 4 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 65 of 72APPENDIX 3 FEED AND BLEED OF ACCUMULATOR 1CTO RAISE BORON CONCENTRATION > 2300 PPM (Page 1 of 4) 1.0 Purpose This appendix is written to address in-leakage into 1C accumulator from the RCS and the associated concern for a reduction in boron concentration. 2.0 Precautions and Limitations 2.1Utilizing this method of Feed and Bleed, reactor coolant will backfill the accumulator discharge line up to the accumulator test line connection. 2.2A 1% increase in accumulator level = 8.3 gallons. 2.3Sample flushes should be minimized to only that required to obtain sample when sampling an accumulator that has in-leakage to prevent accumulator from filling with RCS water. 2.4Do not use extended sampling as method to drain accumulators as this would allow the accumulator to slowly fill with RCS water and dilute accumulator boron concentration.2.5Tech Specs require the accumulator be sampled within 6 hours after each solution volume increase of 1% of tank volume (approximately 12% increase in level). 3.0 Initial Conditions 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 66 of 72APPENDIX 3 FEED AND BLEED OF ACCUMULATOR 1CTO RAISE BORON CONCENTRATION > 2300 PPM (Page 2 of 4) 4.0 Instructions 4.1 Record initial Accumulator 1C boron concentration. _____ Boron concentration ppm CAUTIONSAccumulator level must be maintained between 35% and 55%; the intent of this appendix is to finish the feed and bleed at approximately 40%. Accumulator boron concentration must be maintained between 2200 and 2500 ppm; the intent of this appendix is to raise accumulator boron concentration > 2300 ppm. 4.2Aligning Accumulator 1C for Filling 4.2.1 Verify HYDRO TEST PUMP SEAL OVERFLOW ISO, Q1E21V083 (1-CVC-V-8979) OPEN. _____ 4.2.2 Open HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932). _____ 4.2.3 Set HYDRO TEST PUMP DISCH CONT VLV, HIK 947, to OPEN._____4.2.4 Verify ACCUM N2 SUPP ISO, Q1E21HV8880 CLOSED. _____ 4.2.5 Start the hydro test pump. _____ 4.2.6 Unlock ANDopen HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967). _____ 4.2.7 Open the following valves: ACCUM FILL LINE ISO, Q1E21HV8860. _____ 1C ACCUM FILL LINE ISO, Q1E21HV8878C _____ 4.3IF desired for trending purposes, THENnotify Chemistry to sample accumulator test line at start of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B) _____ 4.3.1 Record the boron concentration ppm UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 67 of 72APPENDIX 3 FEED AND BLEED OF ACCUMULATOR 1CTO RAISE BORON CONCENTRATION > 2300 PPM (Page 3 of 4) 4.4Aligning Accumulator 1C for Draining 4.4.1 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ 4.4.2 Open ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.4.3 Open 1C ACCUM TEST LINE ISO, Q1E21HV8877C to commence draining accumulator. _____ 4.5 Adjust HYDRO TEST PUMP DISCH CONT VLV, using HIK 947 to control fill rate to match drain rate. _____ CAUTIONIf accumulator 1C level exceeds 55% or decreases below 35%, then stop feed and bleed and restore level. 4.6 Monitor Accumulator 1C level. 4.6.1 Verify that only 1C accumulator level is changing. _____ 4.6.2 Verify all other accumulator levels remain constant. _____ CAUTIONIf accumulator 1C pressure exceeds 640 psig or decreases below 610 psig, then stop feed and bleed and restore pressure. 4.7 Monitor Accumulator 1C pressures.4.7.1 Verify that 1C accumulator pressure is changing. _____ 4.7.2 Verify all other accumulator pressures remain constant. _____ 4.8 Continue Accumulator 1C feed and bleed for approximately 1 hour OR as specified by Shift Supervisor. _____ 4.9IF desired for trending purposes, THEN notify Chemistry to sample accumulator test line prior to completion of feed and bleed at ACCUM TEST LINE TO RWST LOCAL SAMPLE, N1E21V008B (1-CVC-V-8962B)_____4.9.1 Record boron concentration ppm. 4.10WHEN Accumulator 1C feed and bleed is complete, THEN adjustHYDRO TEST PUMP DISCH CONT VLV, HIK 947 to OPEN. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 68 of 72APPENDIX 3 FEED AND BLEED OF ACCUMULATOR 1CTO RAISE BORON CONCENTRATION > 2300 PPM (Page 4 of 4) 4.11 Secure Accumulator 1C draining as follows: 4.11.1 Close the following valves: 1C ACCUM TEST LINE ISO, Q1E21HV8877C. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8961. _____ ACCUM TEST LINE TO RWST ISO, Q1E21HV8871. _____ 4.12 Secure Accumulator 1C filling as follows: 4.12.1 Stop the hydro test pump. _____ 4.12.2 Close the following valves: 1C ACCUM FILL LINE ISO, Q1E21HV8878C. _____ ACCUM FILL LINE ISO, Q1E21HV8860. _____ HYDRO TEST PUMP SUCT, Q1E21V028 (1-CVC-V-8932) _____ 4.12.3 Lock HYDRO TEST PUMP DISCH TO ACCUM, N1E21V085 (1-CVC-V-8967) closed. _____ 4.12.4 Verify the following valves CLOSED: 1C ACCUM N2 SUPP/VT ISO, Q1E21HV8875C. _____ ACCUM N2 VENT, HIK 936(Q1G21V092). _____ 4.12.5 Verify HYDRO TEST PUMP DISCH CONT VLV full open using HIK 947. _____ 4.13 Notify Chemistry to sample Accumulator 1C for boron concentration. ANDrecord boron concentration. _____ Boron concentration ppm. 4.14IF boron concentration < 2300 ppm, THEN perform additional feed and bleeds. _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 69 of 72APPENDIX 4 LEAKAGE ASSESSMENT OF NITROGEN HEADER IN CTMT DURING MODES 5, 6 OR DEFUELED Performed by: DateReviewed by: DateThis appendix consists of 3 pages UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 70 of 72APPENDIX 4 LEAKAGE ASSESSMENT OF NITROGEN HEADER IN CTMT DURING MODES 5, 6 OR DEFUELED (Page 1 of 3) 1.0 Purpose This appendix is written to perform leak assessment of nitrogen header inside CTMT to determine possible sources of CTMT air in leakage. 2.0 Precaution and Limitations None.3.0 Initial Conditions 3.1The version of this procedure has been verified to be the current version. (OR 1-98-498) _____ 3.2The procedure has been verified to be the correct unit for the task. (OR 1-98-498) _____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 71 of 72APPENDIX 4 LEAKAGE ASSESSMENT OF NITROGEN HEADER IN CTMT DURING MODES 5, 6 OR DEFUELED (Page 2 of 3) 4.0 Instructions 4.1 Verify the following valves CLOSED: 4.1.1Accumulator Nitrogen Vent Q1E21HCV936-(HIK 936) (MCB). _____ 4.1.21A ACCUM N2 SUPP/VT ISO Q1E21HV8875A (MCB). _____ 4.1.31B ACCUM N2 SUPP/VT ISO Q1E21HV8875B (MCB). _____ 4.1.41C ACCUM N2 SUPP/VT ISO Q1E21HV8875C (MCB). _____ 4.2 Verify ACCUM N2 SUPPLY ROOT (ACTIVE BANK) N1E21V002A OPEN._____4.3 Open the following valves located on the PRIP: 4.3.1ACCUM N2 SUPPLY ISOLATION N1E21HV3938A _____ 4.3.2ACCUM N2 SUPPLY ISOLATION N1E21HV3938B _____ 4.4 Open Accumulator N2 Supply ISO Q1E21HV8880 (MCB) _____ 4.5Slowlyadjust N2 Supply to Accumulator Regulator N1E21V013 to approximately 650 psig. _____ 4.6 Perform leak checks on the following components: Accum Nitrogen Vent Q1E21HCV936 (CTMT 129') _____ N2Supply HDR to Accum Relief Valve Q1E21V060 (CTMT 129') _____ N2Supply HDR to Accum. Test Conn. Q1E21V420A (CTMT 126') _____ N2Supply HDR to Accum Test Conn. ISO Q1E21V420B (CTMT 126') _____ N2Supply HDR to Accum Test Conn. N1E21V304A (CTMT 129') _____ N2Supply HDR to Accum. Test Conn. ISO N1E21V304B (CTMT 129') _____4.7 Generate work orders to have air leaks/components repaired ORreplaced._____ UNIT 1Farley Nuclear Plant Procedure Number Ver FNP-1-SOP-8.0 43.0 6/2/2015 13:45:16 SAFETY INJECTION SYSTEM - ACCUMULATORSPage Number 72 of 72APPENDIX 4 LEAKAGE ASSESSMENT OF NITROGEN HEADER IN CTMT DURING MODES 5, 6 OR DEFUELED (Page 3 of 3) 4.8 Close the following valves located on the PRIP: 4.8.1ACCUM N2 SUPPLY ISOLATION N1E21HV3938A _____ 4.8.2ACCUM N2 SUPPLY ISOLATION N1E21HV3938B _____ 4.9 Close accumulator N2 supply ISO Q1E21HV8880 (MCB) _____ 4.10Slowlyadjust N2 Supply to Accumulator Regulator N1E21V013 to approximately 15 psig. _____ 4.11 Vent N2 Hdr in CTMT by opening Accumulator Nitrogen Vent Q1E21HCV936-(HIK 936) (MCB) _____ 4.12 Verify Accumulator Nitrogen Vent Q1E21HCV936-(HIK 936) CLOSED (MCB) _____ FNP ILT-38 JPM Page 1 of 9 jpm b TITLE: Perform The Required Actions For Cold Leg Recirculation ACCEPTABLE EVALUATION METHOD: X PERFORM SIMULATE DISCUSS EVALUATION LOCATION: X SIMULATOR CONTROL ROOM PLANT PROJECTED TIME: 15 MIN SIMULATOR IC NUMBER: IC-212 (Base -151) ALTERNATE PATH X TIME CRITICAL PRA JPM DIRECTIONS: 1. Examinee will obtain all references from the simulator. 2. The actions of this task are intended to be performed on an Active Simulator in which the examinee may diagnose the correctness of system response to his/her actions and respond to any abnormal conditions which may arise. 3. Provide student with HANDOUT. 4. Allow student time to review control board. 5. Instructor will be provided to address alarms not related to evaluated task. TASK STANDARD: Upon successful completion of this JPM, the examinee will: 1. Perform the Required Actions For Cold Leg Recirculation. Examinee: Overall JPM Performance: Satisfactory Unsatisfactory Evaluator Comments (attach additional sheets if necessary) EXAMINER:

Developer S Jackson Date: 4/7/15 NRC Approval SEE NUREG 1021 FORM ES-301-3 FNP ILT-38 JPM Page 2 of 9 EVENT DESCRIPTION ACTION DETAILS Reset into IC-212 Acknowledge computer alarms Run / Freeze Simulator Acknowledge Alarms Turn Horns ON Run / Freeze Simulator FNP ILT-38 JPM Page 3 of 9 CONDITIONS When I tell you to begin, you are to PERFORM THE REQUIRED ACTIONS FOR COLD LEG RECIRCULATION. The conditions under which this task is to be performed are: a. A LBLOCA has occurred. b. ESP-1.3, Transfer to Cold Leg Recirc, has been entered and all steps through Step 6 have been completed. c. Recirculation Disconnects are Closed. d. You are directed by the Shift Supervisor to transfer to cold leg recirculation starting at Step 7 of ESP-1.3. e. A pre-job brief is not required. EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) START TIME 1. 7.1 Check large break LOCA has occurred as indicated by accumulators discharged. Observes LI-920 & 922, 924 & 926, 928 & 930, TK1, TK2, TK3 ACCUMULATOR LVL indicates 0 percent. S / U 2. 7.2 Check containment sump level - GREATER THAN 3.4 ft {3.8 ft}. LI-3594A or LR-3594B checked. Observes sump level ~ 4 ft. S / U 3. 7.3 Proceed to step 7.5 Proceeds to step 7.5 S / U 4. 7.5 Verify recirculation valve disconnects - CLOSED USING ATTACHMENT 1. This is part of the initial conditions. May refer to . Observes all white lights lit. S / U *5. 7.6 Stop both RHR PUMPs. 1A and 1B RHR pump handswitches taken to stop. Observes 1A & 1B RHR pump Amps indicate '0', Both pumps green lights lit and red lights NOT lit. S / U NOTE: THE FOLLOWING ELEMENT IS THE START OF THE ALTERNATE PATH IN THE RNO COLUMN. FNP ILT-38 JPM Page 4 of 9 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 6. 7.7 Close RWST TO 1A RHR PUMP Q1E11MOV8809A. MOV-8809A handswitch taken to closed. Observes BOTH lights are out. S / U 7. 7.7 (RNO) Perform the following: 7.7.1 Stop the running A train CHG PUMP. Note: Step 7.7.2 is not critical. 7.7.2 Proceed to step 7.12 Takes 1A Charging pump HS to stop. Observes 1A CHG pump Amps indicate '0', pump green light lit and red light NOT lit.

Proceeds to step 7.12 S / U

S / U *8. 7.12 Close RWST TO 1B RHR PUMP Q1E11MOV8809B. HS for MOV-8809B taken to closed. Observes green light lit, red light out. S / U *9. 7.13 Align CTMT sump to 1B RHR PUMP. CTMT SUMP TO 1B RHR PUMP [] Q1E11MOV8811B open [] Q1E11MOV8812B open HS for MOV-8811B and MOV-8812B, taken to open. Observes red lights lit, green lights out. S / U *10. 7.14 Close RHR to RCS HOT LEGS XCON Q1E11MOV8887B. HS for MOV-8887B taken to closed. Observes green light lit, red light out. S / U *11. 7.15 Start 1B RHR PUMP. [] 1B amps > 0 HS for 1B RHR PMP taken to start. Observes pump Amp meter indicates amps, pump breaker red light lit, green light out. S / U 12. 7.16 Verify B Train LHSI flow - STABLE. 1B RHR HDR FLOW [] FI 605B FI-605B checked. Observes FI-605B stable. S / U FNP ILT-38 JPM Page 5 of 9 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) 13. 7.17 Verify at least one train of RHR in operation providing recirculation flow. Checks that B train RHR is providing recirculation flow. Observes 1B RHR pump running and providing flow. S / U 14. 7.18 Verify charging pump miniflow valves - CLOSED. 1A(1B,1C) CHG PUMP MINIFLOW ISO [] Q1E21MOV8109A [] Q1E21MOV8109B [] Q1E21MOV8109C CHG PUMP MINIFLOW ISO [] Q1E21MOV8106 Indications for MOVs 8109A/B/C and 8106 checked. Observes green lights are lit and red lights are out. S / U 15. 7.19 Verify seal return flow valves - CLOSED. RCP SEAL WTR RTN ISO [] Q1E21MOV8100 closed [] Q1E21MOV8112 closed Indications for seal return flow valves MOV 8100 and 8112 checked. Observes MOV 8100 and 8112 indications green lights lit, red lights NOT lit. S / U 16. 7.20 IF 1A RHR PUMP started, THEN align charging pump suction header isolation valves based on 1B charging pump status. Observes 1A Charging pump breaker position indicators green lights lit, red lights out. Proceeds to step 7.25 S / U Note: Closing MOV-8131A & B is the critical portion of this step. *17. 7.25 IF 1B RHR PUMP started, THEN align charging pump suction header isolation valves based on 1B charging pump status. Checks position indication for CHG PMP SUCT HDR ISO VLV MOV-8130A and B. Observes valve position indicators red lights lit, green lights NOT lit. S / U . HS for MOV-8131A and B taken to close. Observes green lights lit red lights out. S / U FNP ILT-38 JPM Page 6 of 9 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) *18. 7.26 Open RHR supply to B train charging pump suction. 1B RHR HX CHG PUMP. TO CHG PUMP SUCT [] Q1E11MOV8706B HS for MOV-8706B taken to open. Observes red light lit, green light out. S / U 19. 7.27 Verify B train CHG PUMP - started. Observes 1B Charging pump red light lit and Amps > 0. S / U 20. 7.28 Verify VCT level is > 5%. Observes LI-115/112 indicates > 5% level. S / U *21. 7.29 Close B train RWST to charging pump header valve. RWST TO CHG PUMP [] Q1E21LCV115D HS for LCV-115D taken to close. Observes green light lit, red light out. S / U 22. 7.30 Check one CHG PUMP in each train - STARTED.

[] A train (1A or 1B) amps > 0   [] B train (1C or 1B) amps > 0 Observes 1C pump Amps > 0, red light is lit, green light NOT lit. Observes 1A Charging pump green light lit, red light out. S  /  U    *23. 7.30.1 (RNO)  Open charging pump recirculation to RCS  cold legs valve. CHG PUMP RECIRC  TO RCS COLD LEGS  [] Q1E21MOV8885 HS for MOV-8885 handswitch taken to open. Observes valve position indicator red light lit, green light NOT lit, FI-940 HAS flow and FI-943 does NOT have flow. S  /  U    *24. 7.30.2 (RNO)  Close HHSI isolation valves.

HHSI TO RCS CL ISO [] Q1E21MOV8803A [] Q1E21MOV8803B HS for MOV-8803A and MOV-8803B taken to close. Observes green lights lit, red lights out. Proceeds to step 7.32 S / U FNP ILT-38 JPM Page 7 of 9 EVALUATION CHECKLIST RESULTS: ELEMENTS: STANDARDS: (CIRCLE) Note: Closing MOV-8133A & B is the critical portion of this step. *25. 7.32 Align charging pump discharge header isolation valves based on 1B charging pump status. Checks open MOV-8132A and B. Observes valve position indicators red lights lit, green lights NOT lit. S / U HS for MOV-8133A and B taken to close. Observes valve position indicators green lights lit, red light out. S / U 26. 7.33 Verify SI flow - STABLE Flow is checked. Observes flow indicated on FI-940, 'B' TRAIN RECIRC FLOW and FI-605B 'B' train RHR HDR flow. NO flow indicated on FI-943, A TRAIN RECIRC FLOW and FI-605A, 'A' train RHR HDR flow. S / U STOP TIME Terminate when STEP 7 is complete: SI flow is determined to be stable.

CRITICAL ELEMENTS: Critical Elements are denoted with an Asterisk (*) preceding the element number.