ML20248K017

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Change 83 to Procedure OP/1/A/1102/10, Controlling Procedure for Unit Shutdown
ML20248K017
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 02/10/1989
From: Barker E
DUKE POWER CO.
To:
Shared Package
ML15224A107 List:
References
NUDOCS 8904170191
Download: ML20248K017 (57)
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{{#Wiki_filter:___ J - r.,= wa naaei OP/1/A/1102/10 I Duke Power Company (1)lO Na 83 PROCEDURE PROCESS RECORD Crawg3 to inwrporated Oconee Nuclear Station S Controlling Procedure For Unit Shutdown (3) Procedure Title J-(4) Prepared By TJ b& / Date 2 -mf 9 G Date J - /d ' E (5) Reviewed By Cross-Disciplinary Renew By N/R (6) Temporary Approval (if necessary) By (SRO)Date By Date 2-M N bO Date (7) Apprmed By (8) Mis Raneous Remewed/Apprmed By Date Remewed/Apprmed By Date (9) Comments (For procedure reissue indicate whether additional changes, other than pnmously apprmed changes, are in-ciuded. Attach additional pages,if necessary.) AdditionalChanges included lid Yes O No (10) Compared with ControlCopy Date (11) Requires change to FSAR not identified in 10CFR50.59 evaluation? O Yes if "yes', attach detailed explanation. 9 No Completion (12) Date(s) Performed (13) Procedure Completion Verification O Yes O N/A Check lists and/or blanks property rvtialed, sgned, dated or filed in N/A or N/R, as approprisesi- ~~ Oyes ON/A Ustedenclosuresattached? O Yes D N/A Data sheets attached, complet6d, dated and sgnedt O Ye O N/A Chaits, graphs, etc. attached and property dated, identified and martaed? O Yes O N/A Pro dure recuremeds met? Date _. _._ Venfied By Date (14) Procedure Completxx1 Approved (15) Remarks (attach additionalpages. d recessary) 8904170191 890411 PDR ADOCK 05000269 Q PDC

l 4 Checked Control Ccpy OP/1/A/1102/10 Date/ Time DUKE POWER COMPANY OCONEE NUCLEAR STATION CONTROLLING PROCEDURE FOR UNIT SHUTDOWN 1.0 Purpose The purpose of this procedure is to outline the steps necessary to take the Plant from an operating condition of ~15% Reector power to a cold shutdown condition. This proceduro may be used for shutting down from conditions other than the above, but all steps must be verified and signed off to prevent possible omission. 2.0 Limitations and Precautions 2.1 When the body of a controlling procedure refers to another procedure or a section of another procedure, that procedure or section must be completed., reviewed by the Unit Supervisor and signed as complete by the Unit lupervisor prior to proceeding with the controlling procedure. This wil.'. be documented by the Supervisor signing that step in the controlling procedure. 2.2 Cooldown rate of the RC system will not exceed the limits established per Enclosure 4.5 (RCS P/T Limitations). 2.3 Before establishing any new Reactor Coolant pressure or temperature plateau, ensure that at least 1.0". Ak/k shutdown is available for the new Reactor Coolant pressure and temperature with Group 1 at 50% withdrawn per PT/1/A/1103/15 (Reactivity Balance). 2.4 Condenser effluent temperature shall not decrease more than 6*F per hour during the Winter and 10 F per hour during the Spring, Summer, and Fall. I

Page 2 of 4 0P/1/A/1102/10 CONTROLLING PROCEDURE FOR UNIT SHUTDOWN 2.5 When a limiting condition for operation, Section 3.0 of the Technical Specification is not met, the rate of shutdown will be determined by Operations such that the required condition is achieved in a controlled manner within the time specified. If conditions dictate, a faster shutdown rate should be used up to and including a Reactor Trip. (Reference OMP 1-4) 2,6 Maintain RCS Pressure and Pressurizer Level within the restrictions of Enclosure 4.11 (Low Temperature Over Pressure Protection) when RCS Temperature 5 325 F. 2.7 If continuous venting of the Pressurizer or Pressurizer sampling is in progress, RCS low range pressure transmitter may give erroneous indica-tion of true RCS pressure. 2.8 All number steps are critical path steps. All steps that follow a bullet (*) are parallel steps that need to be done along with the critical path step but not in any sequence. Before going to the next critical path step, all parallel steps should be completed unless otherwise stated. 2.9 If either SG 1evel decreases to 5 15 inches, then manually trip the Reactor. 2.10 If both Main Feedwater pumps trip, manually trip the Reactor. 2.11 When a motor-operated valve fails to operate remotely, it will be necessary to operate this valve using a Work Request and I&E procedure. l This process will be used unless an SR0 determines that conditions i exist which require the valve to be operated immediately from the breaker contactor. The malfunctioning valve should be noted in the R0 log. I l L ______________________j

Page 3 of 4 OP/1/A/1102/10 CONTROLLING PROCEDURE FOR UNIT SHUTDOWN 2.12 When the RCS temperature is < 325'F, then the following low temperature over pressure protection shall exist: 2.12.1 Both A and B HPI trains shall be inoperable by: 1) For HPI Train A the following valves, tagged closed and breakers tagged open: 1HP-26 (1A HP Injection) 1HP-409 (IHP-27 Bypass) 1HP-410 (1HP-26 Bypass) SE HPI pumps 1A and 1B breakers tagged open. 2) For HPI Train B: 1HP-27 (1B HP Injection) and 1HP-409 (1HP-27 Bypass) tagged closed and breakers tagged open 03 HPI pump 1C breaker tagged open. 2.13 IF LOW is selected on the PORV and the RCS Low Range Pressure Transmitter becomes inoperable, then the PORV is inoperable. The following are conditions that will make the PORV inoperable: 1) 1RC-4 (Pzr Relief Block) shut 2) PORV Selector Switch to HIGH 3) RCS Low Range Pressure Transmitter inoperable or valved out. 4) Continuous venting of the Pressurizer or Pressurizer sampling is in progress. ) i

I OP/1/A/1102/10 CONTROLLING PROCEDURE FOR UNIT SHUTDOWN 3.0 Procedure 3.1 Perform the following as applicable:.1 (Shutdown tv Hot Shetdawn Conditions) l.2 (Hot Shutdown Conditions to 250*F/350 PSI Conditions).3 (250'F/350 PSI Conditions to Cold Shutdown) 4.0 Enclosures 4.1 Shutdown to Hot Shutdown Conditions .i i 4.2 Hot Shutdown Conditions to 250*F/350 PSI Conditions 4.3 250'F/350 PSI Conditions to Cold Shutdown l 4.4 Steam Trap Bypasses or Steam Drains Valve Checklist 4.5 RCS P/T Limitations 4.6 Procedure for Subcooling the Hot Leg Following Pressurizer Outsurge 4.7 Lowering Pressurizer Level without RCP's Operating 4.8 Pressurizer Cooldown 4.9 Shutdown Equipment Tagging List 4.10 Controlling Procedure for H 0, Addition to the RCS 2 4.10A RCS P/T Limitations 4.11 Low Temperature Over Pressure Protection

Page 1 of 5 Checked Control Copy Date/ Time OP/1/A/1102/10 ENCLOSURE 4.1 SHUTDOWN TO HOT SHUTDOWN CONDITIONS Verify Date Date Init./ Time Init./ Time 1.0 Initial Conditions 1.1 Reactor operating ~ 15*. power (~ 135 MWE), 1.2 If the RC system or the HPI system is to be opened for maintenance, commence degassification per OP/1/A/1102/12 (Degassification of RC System and Pressurizer). 1.3 Anxiliary steam header pressurized, i 1.4 NRC notified per the requirements of OMP 1-10 (Usage j and Testing of the Emergency Notification System (Red Phone)). 1.5 Procedure Limits and Precautions have been reviewed. 2.0 Procedure Date Procedure Started 2.1 At ~ 135 MWE, perform the following: 1. Close the following valves: 1HD-67 ("A" FSRH Drain Tank Control Outlet). 1HD-82 ("B" FSRH Drain Tank Control Outlet). 1HPE-36 ("C" Bleed Supply). ILPE-10 ("D" Heaters Bleed Inlet). 1HPE-6 (IA1 Htr. Bleed Inlet). i 1HPE-10 (1A2 Htr. Bleed Inlet). 1HPE-24 (1B1 Htr. Bleed Inlet). 1HPE-28 (IB2 Mcr. Bleed Inlet).

\\' I Page 2 of 5 OP/1/A/1102/10 ENCLOSURE 4.1 SHUTDOWN TO HOT SHUTDOWN CONDITIONS Verify l Date Date Init./ Time Init./ Time 2. If power decrease is NOT for a Steam Generator tube leak, valve in Auxiliary Steam to "E" Heaters as follows: 1. Verify.desuperheater in service and setpoint @ 280 F. 2. Close the following valves: 1LPE-32 ("E" Bleed Line #1 Isolation). ILPE-34 ("E" Bleed Line #2 Isolation). 3. Open 1AS-34 ("E" FDW Heater Aux. Steam Supply). NOTE: Maximum allowable "E" heater pressure is 50 psig. (4) .4. Throttle open 1AS-35 ("E" FDW Htr. Auxiliary Steam Supply Control) to obtain desired steam flow to "E" Heaters to maintain a minimum of 185'F FDW temperature to OTSGs. 3. Ensure the GENERATOR TURBINE / REACTOR CHANNEL TRIP BYPASS statalarm is on prior to tripping the Turbine. 4. Place the Turbine Header Pressure Control Station in HAND and commence shutting down the Turbine-I Generator per OP/1/A/1106/01 (Turbine-Generator). Unit Supervisor i I l l 1 l l

Page 3 of 5 OP/1/A/1102/10 ENCLOSURE 4.1 SHUTDOWN TO HOT SHUTDOWN CONDITIONS Verify Date Date Init./ Time Init./ Time 2.2 After tripping the Turbino, shutdown the MSRH per OP/1/A/1106/14 (Moisture Separator Reheater). Unit Supervisor After tripping the Turbine, verify that computer point D1626 (EHC Emerg. Trip) prints out and is recorded in the Unit Supervisor's Log. i Record the time the Turbine tripped (per the typer for Computer Point D1626) in the Unit Supervisor's Log. Unit Supervisor 2.3 Place the Reactor Control Station in MANUAL at the Diamond Control Station and reduce reactor power while controlling cooldown to 532*F. Open the following valves to supply minimum flow to the Steam Generators as required to prevent water hammer in the feedwater header: 1FDW-127 (Normal FDW Header "1A" Drain Isolation),__ IFDW-216 (Normal FDw' Header "1B" Drain Isolation). 1FDW-237 (S/G "1B" FDW Header Drain). Complete Enclosure 4.4 (Steam Trap Bypass or Steam Drains Valve Checklist). j

I Page 4 of 5 f OP/1/A/1102/10 ENCLOSURE 4.1 SHUTDOWN TO HOT SHUTDOWN CONDITIONS l Verify ) Date Date Init./ Time Init./ Time [ If Unit Shutdown is for Steam Generator Tube lemk repair,. isolate the FDW valves and the Turbine Bypass j 1 Valves on the affected S/G when T,y, is < 532*F. Refer to OP/0/A/1106/31 (Control of Secondary Contamination) and Emergency Operating Procedure for additional instructions. Transfer Auxiliary Steam supply to CSAE's by: Opening 1AS-40 (AS to CSAE). Closing IMS-47 (MS to CSAE). Place FW Master "A" and "B" Control Stations in MANUAL and decrease control stations to 0%. Place the following control switches in the CLOSED i position: l 1FDW-31 (1A Main FDW Block). 1FDW-40 (1B Main FDW Block). Line up generator hydrogen analyzer for off line operation as follows: l 1. Position 1H-55 (Solenoid Valve) to Vent Open Position by pressing VENT OPEN Pushbutton on f ront of Hydrogen Panel. I I l

l Page 5 of 5 l 1 o J OP/1/A/1102/10 ENCLOSURE 4.1 ) SHUTDOWN TO HOT SHUTDOWN CONDITIONS l Verify j Date Date j Init. / Time Init./ Time 2. Adjust 1H-53 (Purity Analyzer Vent) to give l 1 SCFH flow through Gas Analyzer Flowrator. At approximately lowest power and Reactor critical, record in the R0 Log: Time. i Group 1-8 rod positions. RCS boron concentration. RCS average temperature. Use the Diamond Control Station and insert the CRD's per OP/0/A/1105/09 (Control Rod Drive System). Leave Group 1 withdrawn to 50'. to provide ~ 0.5?. 1 Ak/k for negative insertion. Have ISE reset RPS Channels A, B, C, and D overpower trip setpoints to - 4*.. NOTE: The shutdown may continue. Position Group 8 per PT/1/A/1103/15 (Reactivity s l Balance). Enclosure 13.18 (Required Group 8 l Position). NOTE: CRD Group #8 should be inserted last. CRD trip times may be performed at this time. Verify power supply on and Source Range Channels i l I indication available at ~ 10~ amps on Intermediate l Range. { I W-m-__-__.___..-_,. _ -. _ - - - - - - _ _ _.. - _. _

Page.1 of 11 Checked Control Copy i Date/ Time I OP/1/A/1102/10 ENCLOSURE 4.2 HOT SHUTDOWN CONDITIONS TO 250*F/350 PSI CONDITIONS Verify Date Date Init./ Time Init./ Time 1.0 Initial Conditions 1.1 Enclosure 4.1 (Shutdown to Hot Shutdown Conditions) completed. 1.2 Procedure Limits and Precautions have been reviewed. 2.0 Procedure 2.1 Go to one RC pump per loop operation per OP/1/A/1103/06 (RCP operation). Unit Supervisor If hot blowdown of the Steam Generators is desired during Unit Shutdown, perform the following: 1. OPEN the following valves: 1FDW-144 (SG "1A" Shell Bottom Drain). ) 1FDW-334 (SG "1A" Drain Block). I 1FDW-209 (SG "1B" Shell Bottom Drain). ) 1 1FDW-335 (SG "1B" Drain Block), I l l 1FDW-103 (1A SG Shell Drain Block). j l 1FDW-104 (1A SG Shell Drain Block). i 2. Slowly open 1FDW-242 (SG Drain to Condenser Ctri) to control blowdown flow rate from the SG's to the condenser. l l l _._-_-___________-__-__________A

Page 2 of 11' L l l OP/1/A/1102/10 ENCLOSURE 4.2 HOT SHUTDOWN CONDITIONS TO 250*F/350 PSI CONDITIONS m Verify Date Date Init./ Time Init./ Time 3. Maintain SG at 25 inches on the startup range. NOTE: The shutdown may continue. l (3) 2.2 Plot an RCS Boron versus RCS Temperature for 1% Ak/k SG margin curve per PT/1/A/1103/15 (Reactivity Balance Calculation). 2.3 Borate the RC system per OP/1/A/1103/04 (Soluble Poison 1 Control) to maintain greater than 1% Ak/k shutdown margin with worse case stuck rod fully withdrawn as determined in PT/1/A/1103/15 (Reactivity Balance). Unit Supervisor If the length of the shutdown is not known, run a Xenon profile from time of shutdown to Xenon ~ 0%. 1) Borate the RCS, as necessary, to maintain J 1% Ak/k shutdown margin. j l 2) Calculate the shutdown margin every 12 hours and borate for Xenon decay. Set the Source Range 1NI-1 and 1NI-2 Reactor Building Evacuation Alarm Bistable setpoint 1/2 ( decade above source level. l Enable the REACTOR BUILDING EVACUATION Alarm. l l l l

Page 3 of 11 0P/1/A/1102/10 ENCLOSURE 4.2 HOT SHUTDOWN CONDITIONS TO 250*F/350 PSI CONDITIONS. 1' VerJfy Date Date Init./ Time Init./ Time CAUTION: RC Pressure versus Temperature and cooldown rates must be maintained within the specified limits of ".5-(RCS P/T Limitations). P' lace the Turbine' Bypass valves in MANUAL. Adjust Turbine Bypass valves to give the desired-cooldown rate. De-energize the Pressurizer Heaters and use IRC-1 (Spray Control valve) to depressurize the RC System. When Main Feedwater Pump (s) discharge pressure is 800 psig, perform the following: 1. Close from the manual loader and place the Auto / Manual switches in the MANUAL position: 1FDW-315 (EFWDP Disch. to S/G "1A" Control). 1FDV-316 (EFWDP Disch to S/G "1B" Control). 2. Place the following control switches in the TRIPPED position: "1A" MDEFDWP. I 1 "1B" MDEFDWP. l 3. Place IMS-93 (TDEFDWP Control Switch) in the LOCK 0UT position. l

Page 4 of 11' OP/1/A/1102/10 ENCLOSURE 4.2 HOT SH' FDOWN CONDITIONS TO 250 F/350 PSI CONDITIONS J Verify Date Date Init./ Time Init./ Time 4. Place the following valve switches as indicated: OPEN IFDW-36 (1A SG Norm SU FDW Hdr). OPEN 1FDW-45 (1B SG Norm SU FDW Hdr). CLOSE 1FDW-38 (1A SG EFDW Header). CLOSE 1FDW-47 (1B SG EFDW Header). When feedwater is ~ 180'F go to Feedwater Cleanup as follows: 1. Close 1FDW-71-(FDW Cleanup to Condenser). 2. Close ISD-17 (Turb Byp Line "A" Stm Drn to Trench). 3. Open 1FDW-84 (FDW Cleanup Bypass Block). 4. Close 1FDW-82 (FDW Cleanup Control Valve). 5. Open 1FDW-75 (1A SG FDW Cleanup Bypass). 6. Open 1FDW-77 (1B SG FDW Cleanup Bypass). 7. When 1FDW-75 (1A SG FDW Cleanup Bypass) 1 and 1FDW-77 (IB SG FDW Cleanup Bypass) are 1 )

open, Open 1FDW-200 (1FDW-76 Bypass).

t 8. When 1FDW-200 (1FDW-76 Bypass) is open, Open 1FDW-74 (1A SG FDW Cleanup Bypass). d Open 1FDW-76 (IB SG FDW Cleanup Bypass) i

Page 5 of 11 OP/1/A/1102/10 i ENCLOSURE 4.2 q HOT SHUTDOWN CONDITIONS TO 250*F/350 PSI CONDITIONS Verify Date Date Init./ Time Init./ Time 9. When 1FDW-74 (1A SG FDW Cleanup Bypass). and 1FDW-76 (1B SG FDW Cleanup Bypass) are

open, Throttle open 1FDW-82 (FDW Cleanup Control Valve).

10. Maintain ~ 2300 gpm total feedwater flow as read ou computer point A0156 (CBP Header Flow) or recorder R-304 9.R 1 x 10' LBM/Hr as read on running FWP discharge flow recorder or gauge. When Feedwater temperature is ~ 180 F and only if condensate system is to be taken out of service: Bypass High Pressure Heaters. Place steam or nitrogen blanket on 1A2 Heater per OP/1/A/1106/03 (1A2 HP Heater Blanketing (Steam or Nitrogen)). Unit Supervisor 2.4 When the Reactor Coolant pressure reaches 1850 to 1820 psig insert Safety Rod Group 1. When the Main Steam pressure decreases below 550 psig, stop the second Feedwater Pump per OP/1/A/1106/02 (Condensate and Feedwater System). Unit Supervisor 1

l-Page 6 of 11 OP/1/A/1102/10 ENCLOSURE 4.2 HOT SHUTDOWN CONDITIONS TO 250*F/350 PSI CONDITIONS Verify Date Date Init./ Time Init./ Time. l 2.5 When Reactor Coolant pressure decreases to ~ 1700 psig, l bypass ES Channel 1 and 2: ES Channel 1 bypassed ES Channel 2 bypassed 2.6 When Reactor Coolant pressure is ~ 1700 psig: 1) Verify nuclear overpower trip setpoints are reset te ~ 4% on RPS channels A, B, C, and D. 2) Initiate SHUTDOWN BYPASS for the following: l 'RPS Channel A RPS Channel B RPS Channel C RPS Channel D I 2.7 Reset CRD Breakers and withdraw Control Rod Group 1 to 50% per OP/0/A/1105/09 (Control Rod Drive System),to provide ~ 0.5% Ak/k for negative insertion. l l Throttle 1HP-277 (Seal Return Valve) to maintain l ~ 60 psig backpressure as read on local pressure gauge PG-102. l Open 1HP-275 (RCP Seal #1 Bypass) only if RC Pump l l bearing temperatures or leakoff temperatures approach their alarm levels, and only then if RCS l l pressure is less than 1000 psig and #1 seal leakoff flow on any pump is less than 1 gpm. ( l l l l

1 Page 7 of 11 l OP/1/A/1102/10 ENCLOSURE 4.2 HOT SHUTDOWN CONDITIONS TO 250 F/350 PSI CONDITIONS Verify Date Date l Init./ Time Init./ Time 2.8 When Reactor Coolant pressure decreases below 900 psig, bypass ES Channels 3 and 4 before pressure decreases to j 600 psig: ES Channel 3 bypassed i ES Channel 4 bypassed l NOTE: RC system temperature chall not be reduced below t (2.9) 325'F until CF system pressure is < 350 psig. 2.9 When RC system pressure reaches approximately 700 psig: Remove Core Flood System from ES conditions per OP/1/A/1104/01 (Core Flood System). Unit Supervisor Open 1LPSW-563 (Inside R.B. Hose Rack Isolation). Open ILPSW-564 (Inside R.B. Hose Rack Isolation). When the RC system temperature is < 350 'F but j 325 F, perform the following: 1. Close or verify closed: 1HP-26 (1A HP Injection). 1HP-27 (IB HP Injection). IllP-409 (1HP-27 Bypass). 1HP-410 (1HP-26 Bypass). 4 __ A

Page 8 of 11 OP/1/A/1102/10 ENCLOSURE 4.2 HOT SHUTDOWN CONDITIONS TO 250 F/350 PSI CONDITIONS Verify -[ Date Date Init./ Time Init./ Time 2. White tag the following motor operator breakers in the open position: 1HP-26 BKR Open. White Tag Number i 1HP-27 BKR Open. i White Tag Number 1HP-409 BKR Open. White Tag Number 1HP-410 BKR Open. j White Tag Number 3. White tag the following handwheels closed: 1HP-26 handwheel closed. White Tag Number 1HP-27 handwheel closed. j White Tag Number 1HP 409 handwheel closed. White Tag Number 1HP-410 handwheci closed. White Tag Number l 1

y Page 9 of.11 1 .c iv ?0P/1/A/1102/10 ENCLOSURE'4.2 HOT SHUTDOWN CONDITIONS TO 250 F/350 PSI CONDITIONS Verify Date. Date Init./ Time Init./ Time '4. White tag Unit 1 SSF-RC Makeup Pump Breaker. 600V MCC 1XSF-4C open. .5. Establish a dedicated LTOP 0perator-per.11 (Low Temperature Over Pressure . Protection). r s 2.10 Continue the decrease of RC system pressure to 500 psig. Insert control rod Group #1. If shutdown i for a Refueling Outage, then position' Group 8 at 0% (NOT in11mit). Trip the Control Rod-Drive system. -l NOTE: .The shutdown may continue. (2.11) 2.11 When RC system pressure decreases to < 600 psig (but > 400'psig) _AND RCS Temperature is < 350*F (but > 325 F), have the i Instrument Department valve in the RC system Low Range Pressure ~ indicator. 1) Place the Low Range Pressure indicator in service I by opening: 1RC-6 (Press. Water Sample (Bldg. Isol.) Pen.(1)). l 1RC-7 (Press. Sample (Bldg. Isol.) Pen.(1)). j l' 2) Verify 1RC-4 (Pzr Relief Block) is open. l l q, j j

I Page 10 of 11 ) i OP/1/A/1102/10 ENCLOSURE 4.2 HOT SHUTDOWN CONDITIONS TO 250 F/350 PSI CONDITIONS Verify i Date Date Init./ Time Init./ Time CAUTION: If the RCS Low Range Pressure Transmitter is inoperable, (3) then the PORV is inoperable. 3) When the RCS pressure < 450 psig (but > 400 psig) AND RCS temperature is < 350 F (but > 325'F), select LOW on the IRC-66 Setpoint Selector. 4) Immediately check Quench Tank temperature, pressure,. and Pressurizer Relief Valves Flow Monitor in case 1RC-66 (Press. Power Operated Relief Valve) lifts i unexpectedly. 5) Verify Pressurizer level 5 220 inches. 2.12 Sample the RC system and determine that the required boron concentration to maintain shutdown margin at ambient temperature and Xenon free core is in the t Reactor Coolant system. 2.13 If the length of shutdown is not known to be longer than the time for Xenon decay to ~ 0?., calculate the 1 l shutdown margin every 12 hours and borate for Xenon ) decay to maintain 1*. Ak/k shutdown margin. 2.14 When Reactor Coolant Temperature (Tc) is 325 to 300*F: 1. Secure Steam Generator hot blowdown as follows: Close 1FDW-242 (Hot Blowdown Controller to the l Condenser), i l Close 1FDW-103 (1A SG Shell Drain Block). l I Close 1FDW-104 (IB SG Shell Drain Block). l _a

( l Page 11'of 11 1 l' l OP/1/A/1102/10 i ENCLOSURE 4.2 If0T SHUTDOWN, CONDITIONS TO 250*F/350 PSI CONDITIONS Verify Date Date ] -Init./ Time Init./ Time j 2. If directed by the Unit Operating Engineer, begin hot soak per OP/1/A/1106/08 (Steam Generator Secondary, Fill, Drain and Layup). 2.15 If shutdown is for CRD stator replacement, maintain RCS temperature at ~ 300*F, RCS pressure ~ 350 poig. 2.16 Continue cooldown to 250*F/350 psi. f i I j i i l l l 1 1 l l l J l l l 1

Page 1 of 11 -Checked Control Copy, Date/ Time OP/1/A/1102/10 ENCLOSURE 4.3 250*F/350 PSI CONDITIONS TO COLD SHUTDOWN 2 Verify Date Date Init./ Time Init./ Time 1.0 Initial Conditions 1.1 Completed Enclosure 4.2 (Hot Shutdown Conditions to 250'F/350 PSI Conditions). 1.2 Procedure Limits and Precautions have been reviewed. 2.0 Procedure I 2.1 Slowly start to decrease the Pressurizer level control setpoint to 100 inches. . NOTE: The cooldown may continue. (2.1) CAUTION: Seal #1 AP must be maintained > 275 psi. As the RC system pressure decreases to the point where the 275 psi AP limit is approached on Seal

  1. 1 of the RC pumps, perform the following:

a Open 1GWD-19 (LDST Vent) to reduce the back pressure on the seal return. 9.R Open ILWD-250 (Seal Return Filter Drain). Open 1 LWD-461 (Seal Return Filter Drain Block). Close 1HP-279 (Seal Return Filter Outlet). ? .i

Page 2 of 11 I OP/1/A/1102/10 ENCLOSURE 4.3 250*F/350 PSI CONDITIONS TO COLD SHUTDOWN Verify Date Date Init./ Time Init./ Time When the RC system pressure is < 350 psig and RC temperature < 250*F, ser,ure the Reactor Building Spray system per OP/0/A/1104/05 (Reactor Building j Spray System). 9 Unit Supervisor j When the RC system pressure is reduced < 350 psig ) and < 250*F, refer to OP/1/A/1104/04 (Low Pressure Injection System) and valve in the Low Pressure Injection system in the Switchover mode per RC J System Cooldown Enclosure. Unit Supervisor Have I&E connect trend recorders to sense LPI { cooler outlet temperatures. Verify LPI cooler outlet temperature recorder is ) in operation and agrees with LPI cooler outlet j temperature gauges. q When RCS is < 250 F and < 350 psig place the purge l system in operation per the following: l 1. If going to cold shutdown for refueling, then verify Performance has performed "As Found Leak Rate Test" per PT/1/A/0150/27 (Local Type B Leak Rate of Penetrations 19 and 20). 2. Close in the following breakers: ) l IPR-1 (RB Purge Outlet). q IPR-6 (RB Purge Inlet).

Page 3 of 11 [ x OP/1/A/1102/10 ENCLOSURE 4.3 250*F/350 PSI CONDITIONS TO COLD SHVfDOWN Verify Date Date Init./ Time Init./ Time l 3. Contact I&E to install the links on the following per IP/0/A/310/22 (P.R. velves 2, 3, 4 and 5 Close and Open Links Procedure). IPR-2 (RB Purge Outlet). I I&E 1PR-3 (RB Purge Controller). I&E 1PR-4 (RB Purge Inlet). I&E 1PR-5 (RB Purge Inlet). 1 I&E NOTE: If RCS pressure < 300 psig or RCS temperature < 200'F, (4) the stroke test is not required. 4. If RCS temperature is > 200 F when power is restored to the RB purge valves, contact i Performance to do valve stroke testing of IPR-1 through IPR-6. 5. Start R.B. Purge System per.0P/0/A/1102/14 1 (R.B. Purge System). j i NOTE: The shutdown may continue. 2.2 When RC pressure is 5 314 psig and 5 246'F RC temperature: i Start LPI pump "A" or "C" per RC System Cooldown Enclo-sure in OP/1/A/1104/04 (Low Pressure Injection System). Slowly open ILP-69 (LPI Switchover Flow Controller) j until "B'" header temperature has stabilized. l I I 2.3 Establish 3000 gpm flow in "B" line, using ILP-69 (Switchover Mode Control). l Select ON on Low Flow Alarm Block Switch. l C______._____

?Page"4 of1117 t i t'.. t d,.' '0P/1/A/1102/10f ' ENCLOSURE 4.3 ~ 250*F/350 PSI CONDITIONS TO COLD SHUTDOWN - Verify Date Date Init./ Time Init./ Time _After the LPI system is in service, sample the RCS to ensure required shutdown boron' concentration ~ is being. maintained. Establish LPSW to LPI Coolers by the following: 1. Close ILPSW-251 (1A LPI Clr Outlet Byp V1v). Close ILPSW-252 (1B LPI Clr Outlet Byp V1v). 2. Open 1LPSW-41(1A LPI Cooler Outlet). 1 Open 1LPSW-5.(1B.LPI Cooler' Outlet). ] i CAUTION: Do not exceed 6000 gpm LPSV flow thru cooler. I (3). I L 3. Throttle open 1LPSW-252 (1B LPI Clr Outlet Byp V1v) to cooldown~and depressurize the 4 'RCS p'er limits of' Enclosure 4.5 (RCS P/T I l Limitations). If Steam' Generator Hot Soak is being performed, then maintain the following-i 1. Maintain RCS temp between 225-246*F. 2. RCS pressure should be < 314 psig but > RCP 3 requirements when Steam Generator Hot Soak is complete. NOTE: This temperature / pressure region will allow continued L RCP operation while the LPI System is lined up in the Switchover Cooling Mode. i 3. If necessary, maintain requirements for TCPs i i by energizing Pressurizer Heaters. j

Page 5 of 11.- OP/1/A/1102/10 ENCL 0EURE 4.3 250*F/350. PSI CONDITIONS TO COLD SHUTDOWN Verify. Date Date-Init./ Time Init./ Time l

CAUTION:
1) _ Securing all but one RCP must be'done prit.to (2.4) going below 200*F as per Enclosure 4.5 (RCS P/T Limitations Curve) to minimize stresses created on the Reactor Vessel in the cooldown process.

2) Cooldown rate should be monitored to prevent exceeding cooldown limits when securing RCP's due to removal of pump heat. 2.4 After LPI flow has been established and Steam Generator Hot Soak is complete if performed, stop all RC pumps except the RC pump supplying Pressurizer Spray per CP/1/A/1103/06 (RCP Operation) before cooling RCS below 200*F. Unit Supervisor 2.5 When RC pumps have been otopped for 30 minutes, isolate the LPSW to the idle RC pump motors per OP/1/A/1103/06 (RC Pump Operation). 2.6 Throttle ILPSW-252 (IB LPI Clr Outlet Byp V1v) to establish proper cooldown rates per Enclosure 4.5 (RCS P/T Limitations). 2.7 When RCS Temperature is < 200*F, perform the following: 2.7.1 Secure SG(s) as follows: Close Turbine Bypass Valves. Close the following valves: 1FDW-127 (Normal FDW Header "1A" Drain Isolation). 1FDW-216 (Normal FDW Header "1B" Drain l Isolation). l d 1FDW-237 (S/G "1B" FDW Header Drain).

Page 6 of 11 OP/1/A/1102/10 ENCLOSURE 4.3 250*F/350 PSI CONDITIONS TO COLD SHUTDOWN Verify Date Date Init./ Time Init./ Time 2.7.2 Determine if SG wet or dry layup is desired and implement at this time per OP/1/A/1106/08 (Steam Generator Fill, Drain and Layup). Unit Supervisor 2.7.3 Shutdown secondary systems per OP/1/A/1106/02 (Condensate and Feedwater System). Unit Supervisor 2.7.4 If required, when the RCS reaches ~ 180*F, stop the RCS cooldown and perform Enclosure 4.10 (Controlling Procedure for H 0 Addition 2 f to the RCS), 1 2.8 Cooldown until T is reduced to approximately 150 F. H 1 2.9 Verify pressurizer level has reached 100 inches. l l 2.10 Before securing the last RCP, perform the following: J Line up to use HPI system for Auxiliary Spray as follows: 1. Verify 1HP-355 (Aux. PZR Spray Flow Control) closed. 2. Verify 1HP-473 (Aux Pzr Spray Flow Control l Bypass) closed. l 3. Close 1HP-241 (Loop "Al" and "A2" Nozzle j i l Warming Throttle). l l 4. Open 1HP-472 (Aux. PZR Spray Flow Block). ) 1

y* iPage'7-ofL11 o. OP/1/A/1102/10~ ENCLOSURE 4.3 -250*F/350' PSI CONDITIONS TO COLD SilUTDOWN Verify P Date Date 'Init./ Time'-Init./ Time Close the following Feedwater Startup Blocks: 1FDW-33 (A SU FDW Block). 1FDW-42.'(B SU FDW Block). ' Adjust LPI cool'er_ outlet' temperature to be ~ the same as Tcold' NOTE: The step change'in temperature indication resulting (2.11) ~ from stopping the final RCP'(utilizing T with RCP on, LPI cooler outlet temperature with RCP,off) must be factored in when determining the cooldown rate per ~ Enclosure.4.5~(RCS P/T Limitations). 2.11 Stop the. last RC pump per OP/1/A/1103/06 (RCP Operation). Unit Supervisor Adjust 1LPSW-252 (1B LPI Clr Outlet Byp Viv) to re-initiate RCS'cooldown after all RCPs stopped. NOTE: Use LPI cooler outlet temperature as RCS temperature. Cooldown rates are extremely restrictive <150'F. Maintain limits per Enc. 4.5 (RCS P/T Lin.itations). After RC pumps have been secured and if #1 leakoff was routed to Waste Disposal System: l Open IllP-279 (Seal Return Filter Outlet), j Close ILWD-250 (Seal Return Filter Drain). Close ILWD-461 (Seal Return Filter Drain Block). 'i

) Page 8 of 11 OP/1/A/1102/10 i ENCLOSURE 4.3 250*F/350 PSI CONDITIONS TO COLD SHUTDOWN Verify Date Date Init./ Time Init./ Time Open when RCS Pressure is < 300 PSIG: ILWD-443 (East Penetration Room Floor Drain). ILWD-444 (West Penetration Room Floor Drain). 2.12 Commence cooldown of the pressurizer per Enclosure 4.8 (Pressurizer Cooldown). When the RC system pressure is less than 125 psig, transfer the LPI system from the SWITCH 0VER MODE to the NORMAL MODE of operation per OP/1/A/1104/04 (Low Pressure Injection System). NOTE: Either "1A" or "1C" LPI pump can be operating in conjunction with '1B' LPI pump. Unit Supervisor After all RC pumps have been stopped and the RC system pressure is < 100 psig and temperature < 190'F: 1. Close the following valves: 1HP-20 (RC Pump Seal Return). 1HP-226 (RCP 1A2 RCP Seal Return Stop). 1HP-228 (RCP 1A1 RCP Seal Return Stop). 1HP-230 (RCP 1B2 RCP Seal Return Stop). 1HP-232 (RCP 1B1 RCP Seal Return Stop). 2. Place standby HPI pump in the OFF position.

Page 9 of 11 OP/1/A/1102/10 ENCLOSURE 4.3 250*F/350 PSI CONDITIONS TO COLD SHUTDOWN Verify Date Date Init./ Time Init./ Time 3. Place 1HP-31 (RCP Seal Flow Control) in HAND and close. 4. Open 1HP-42 (Letdown Orifice Manual Bypass) as required to maintain letdown flow. 5. Leave a HPI pump on for Pressurizer auxiliary spray flow and/or purification, degassification operation. Stop the Reactor Vessel Head Cooling Fans by opening the following breakers: Even Reactor Vessel Head Cooling Fans breakers (located on WR2 RB-3). Odd Reactor Vessel Head Cooling Fans breakers (located on ER2 RB-3). 2,13 When Pressurizer temperature is < 200*F, perform the following: 1. Line up letdown flow to 1A BHUT as follows: Verify open ICS-41 (1A RC BHUT Inlet). Open ICS-26 (Letdown to RC BHUT). l Position 1HP-14 (LDST Bypass) to JL ?D position. 2. Adjust letdown flow to lower Pressurizer level to - 115 inches. 3. Maintain Pressurizer nitrogen overpressure at 30 psi per OP/0/A/1103/05 (Pressurizer Operation) while lowering level. L___--.-.---__--

Page 10 of 11 OP/1/A/1102/10 ENCLOSURE 4.3 250 F/350 PSI CONDITIONS TO COLD SHUTLOWN Verify Date Date Init./ Time Init./ Time 4. After Pressurizer level is adjusted to ~ 115 inches, perform the following: 1. Close 1HP-5 (Letdown Isolation). '2. ~When 1HP-5 (Letdown Isolation) is closed, notify Chemistry Department that the normal RCS sample line is isolated. 3. Position 1HP-14 (LDST Bypass) to NORMAL. 4. Close 1CS-26 (Letdown to RC BHUT). 5. Stop the HPI Pump. 5. Secure Pressurizer Auxiliary Spray by performing the following: 1. Close 1HP-355 (Aux. PZR Spray Flow Control). 2. Verify closed 1HP-473 (Aux Pzr Spray Bypass). 3. Close 1HP-472 (Aux. PZR Spray Flow Block). 6. Rack out and white tag the HPI Pump breakers (for Low Temperature Over Pressure Protection): 1A HPI pump bre'mer racked out and white tagged 1B HPI pr.mp breaker racked out and white tagged 1C HPI pump breaker racked out and white tagged _j

Page 11 of 11 OP/1/A/1102/10 ENCLOSURE 4.3 250'F/350 PSI CONDITIONS TO COLD SHUTDOWN Verify Date Date Init./ Time Init./ Time CAUTION: When deprescurizing and draining the RC system, the (2.14) NPSH for the LPI pumps and decay heat flow are affected. Flow must be monitored and regulated to prevent excess flow and pump cavitation. 2.14 When RC temperature is reduced to 160'F as read on LP pump suction and the Pressurizer temperature is 5 200 F, go to one LP pump operation per OP/1/A/1104/04 (Low Pressure Injection System). Reduce total LPI flow to 5 3000 GPM with one LPI Pump. NOTE: To save wear en '1A' or '1B' LPI pumps, the use of '1C' LPI pump is preferred. Place the LPI system in purification per OP/1/A/1104/04 (Low Pressure Injection System) at this time. Adjust the RC System to the desired level for refueling or component repair. Refer to OP/1/A/1103/11 (Draining and Nitrogen Purging the RC System). Unit Supervisor NOTE: This is to ensure equipment is not inadvertently (2.15) operated while shutdown, l 2.15 If directed by the Unit Operation Engineer when the i \\ 'l Unit is being shutdown for Refueling, red tag the f equipment listed on Enclosure 4.9 (Shutdown Equipment Tagging List) to the Unit Supervisor. Unit Operating Engineer Contacted

Checked Control Copy Page 1 of 2 j OP/1/A/1102/10 Date/ Time ENCLOSURE 4.4 STEAM TRAP BYPASSES OR STEAM DRAINS VALVE CHECKLIST VALVE NO. VALVE NAME LOCATION BT POSITION INITIAL l i I .I I I I l 1SD-187 l A Bld to A Htrs Stm Trap Byp l CR l l Open l l 1 I I I I I I l 1SD-199 l A Bld to A Htrs Stm Trap Byp 3 l CR l l Open' l l l l l l l 1 I l 1SD-217 i B Bld to B Htrs Stm Trap Byp 1 l CR l l Open l l 1 1 I I I I I l 1SD-222 l B Bld to B Htrs Stm Trap Byp 2 l CR l l Open l l l 1 I I I I I l 1SD-246 l C Bld to C Htrs Stm Trap Byp 2 CR l l Open l l l l l 1 l I i 1SD-264 i D Bld From A LP Turb Stm Trap Byp 1 l CR l l Open l l l l 1 1 I I I l 1SD-288 i D Bld From A LP Turb Stm Trap Byp 3 l CR l l Open l l l l l 1 I l l l 1SD-294 l D Bld From B LP Turb Stm Trap Byp 2 j CR l l Open l l l l i I I I I l 1SD-276 l D Bld From C LP Turb Stm Trap Byp 1 l CR l l Open l l l l l 1 I I I l 1SD-312 1 D Bld From C LP Turb Stm Trap Byp 3 l CR l l Open l l 1 I I I I i l l 1SD-208 1 D Bld to D Htrs Stm Trap Byp l CR l l Open l l 1 l l I I I I l 1SD-408 l E Bld Lower Line Stm Trap Byp 2 l CR l l Open l l l l l l l l l l 1SD-402 l E Bld Lower Line Stm Trap Byp l CR l l Open l l l 1 I I I I l J ISD-193 l A Bld to A Htrs Stm Trap Byp 2 l CR l l Open l l l l I I I I I l 1SD-182 l A Bld to A Htrs Stm Trap Byp 4 l CR l l Open l l l 1 1 I I I l ISD-228 l B Bld to B htrs Stm Trap dyp 3 l CR l l Open l l l 1 I I I I l 1SD-234 l B Bld to B Htrs Stm Trap Byp 4 l CR l l Open i l i I I I I I I l 1SD-240 l C Bld to C Htrs Stm Trap Byp 1 l CR l l Open l l l .I I I l l I l 1SD-252 l C Bld to C Htrs Stm Trap Byp 3 l CR l l Open l l l l l 1 I I I l 1SD-282 l D Bld / rom A LP Turb Stm Trap Byp 2 l CR l l Open l l 1 I I I I I I l 1SD-270 l D Bld From B LP Turb Stm Trap Byp 1 l CR l l Open l l 1 I I I I I I l 1SD-300 l D Bld From B LP Turb Stm Trap Byp 3 l CR l l Open l l I I I I I I I l 1SD-306 l D Bld From C LP Turb Stm Trap Byp 2 l CR I l Open l l l l l l l l l j_1SD-318 l D Bld Hdr Stm Trap Byp l CR. l l Open l l __m

_-______.________._-.__-_._m.-_______-______m___m_

..y. Page 2 of-2 OP/1/A/1102/10-ENCLOSURE 4.4 -STEAM TRAP BYPASSES OR STEAM DRAINS VALVE CilECKLIST 4 . VALVE NO.- . VALVE'NAME LOCATION BT' POSITION-. INITIAL 1 I I I I i 1SD-390' l E Bld Upper Line'Stm Trap Byp 1 CR l Open l l -l I I I I I . l~1SD-396' l E Bld Lower Line Stm Trap Byp ' l CR l l Open-l l I I I 1. l .I I l 1SD-273 l Comb. Ctrl Viv Before. Seat Drn l'CR l' 'l Open 'l 1 l I I I .I I l-1SD-284 l #2 Ctrl Viv Lead Stm Drn l CR l l Open-1 l' I I I l' I I l 1SD-285 l #1 Ctrl Viv Lead Stm Drn l CR l l Open l J' l' l l f

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- REACTOR C001AllT TEMPERATUR3 ('T) 1 L- + - - - ~ * * ^ = i aC TEW ERATURE (1) ha.IDR98 C0000WE BATE (2) (3) RCS is depressurised when all three of the fol. ~2 h Y > 280'F < 43'r is soy hour period loving conditions miat -< 20'F is any hour period a) RCS temperature 4 2d, j b 150'F e T 4 280'F f i 9,F is any I bour period b) ECS pressure < 50 peig. p T < 150'F c) All RC Pumps off. ? E RCS depressurised(3) o 3 43 F is any 1 hour period The marious cooldoun rete shall be relaxed to 4 45'F $ E in any 1 hour period. E E (1) RC temperature is cold les temperature if one or E E more RC3 pumps are is operation er if on astural lii airealatism osm&deums othenvise it is the LF1 RC TEMPER M M PWF M E m 0E3 i ih

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> 2 70'F any I (2) h=e rete h ames be applied to the change e ~ &s Speture ledicaties from acid leg ter peresiere es LM enstar entlet temperature per 4 200'F. as. more than a.pu_m_p__

l Page.1 of 4 c. L Checked Control Copy Date/ Time OP/1/A/1102/10 ENCLO3URC 4.6 PROCEDURE FOR SUBC00 LING THE HOT LEG FOLLOWING PRESSURIZER OUTSURGE Verify Date Date Init./ Time Init./ Time 1.0 Initial Conditions 1.1 RCS pressure decreased below Hot Leg Saturation Temperature as indicated by rapid increase in pressurizer level. 1.2 RCP's secured. 1.3 LPI system in operation. 1.4 FDW system available. 1.5 Procedure Limits and Precaut. ions have been reviewed. 2.0 Procedure When Pressurizer Temp. > 275'F 2.1 Close 1HP-355 (HPI Auxiliary Spray Flow Control) to secure auxiliary spray. Verify closed 1HP-473 (Aux Pzr Spray Bypass). 2.2 Energize Pressurizer Heaters to increase RCS pressure to minimum RCP NPSH per Enclosure 4.5 (RCS P/T Limitations). 2.3 Start a RC pump per OP/1/A/1103/06. (RCP Operation). Unit Supervisor 2.4 Stabilize or reduce hot leg temperatures at approximately 150*F or less without violating the limits of Enclosure 4.5 (RCS P/T Limitations).

Page 2 of 4 OP/1/A/1102/10 ENCLOSURE 4.6 PROCEDURE FOR SUBC00 LING THE HOT LEG FOLLOWING PRESSURIZER OUTSURGE Verify Date Date Init./ Time Init./ Time 2.5 Reduce Pressurizer level to 100 inches. 2.6 Adjust LPI cooler outlet temperature to be ~ the same as Tcold' 2.7 Stop the RC pump per OP/1/A/1103/06 (RCP Operations). NOTE: The step change in temperature indication resulting from (2.7) stopping the final RCP (utilizing T with RCP on, LPI c cooler outlet temperature with RCP off) must be factored in when determining the cooldown rate per Enclosure 4.5 (RCS P/T Limitations). Unit Supervisor 2.8 Commence cooldown of the Pressurizer per Enclosure 4.8 (Pressurizer Cooldown). 3.0 Procedure When Pressurizer Temp is < 275 F 3.1 Establish nitrogen overpressure on the Pressurizer as follows: 3.1.1 Close the following valves to prevent Quench Tank from pressurizing. 1N-116 (Quench Tank Supply). 1N-121 (High Pressure Supply to Pressurizer). 1GVD-16 (Pressurizer Vent Block). 3.1.2 Open the following valves: 1GWD-18 (Pressurizer Vent and N Isolation). 2 IN-110 (Reactor Bldg. Low Press Header Supply). l I i _________________o

Page 3 of 4 OP/1/A/1102/10 ENCLOSURE 4.6 PROCEDURE FOR SUBC00 LING THE HOT IIG FOLLOWING PRESSURIZER OUTSURGE Verify Date Date Init./ Time Init./ Time Remove White Tag and open: IN-119 (Steam Generator Pressurizer Block). IN-161 (Pressurizer Supply). 3.1.3 Throttle open 1GWD-17 (Pzr Vent) to establish i nitgogen over pressure. CAUTION: Do not exceed 45 psig RCS Pressure. (3.1.4) 3.1.4 Increase pressure until bubble in the hot leg is collapsad as indicated by a decrease in Pressurizer level. 3.2 Line up "1A" SG for feed and bleed as follows: 1. Open the following: 1FDW-141 (SG "1A" Bottom Drain). 1FDW-142 (SG "1A" Bottom Drain). 1FDW-143 (SG "1A" Bottom Drain). 1FDW-144 (SG "1A" Bottom Drain). 1FDW-334 (SG Shell Drain Hdr. Block). 1FDW-103 (IA SG Shell Drain Block). 2. Drain the "1A" SG to ~ 70% full range. 3. Line up feedwater from another Unit to the "1A" SG per OP/1/A/1106/08 (Steam Generator Fill, 1 Drain and Layup). Unit Supervisor

p 3 .Page 4'of.4 ci OP/1/A/1102/10 ENCLOSURE 4.6 PROCEDURE FOR SUBC00 LING THE HOT LEG FOLLOWING PRESSURIZER OUTSURGE Verify .Date Date 'Init./ Time ~ Init./ Time 3.3 Feed and bleed-the "1A" SG between ~ 70% and ~ 90% . full range by performing the following: Throttle open 1FDW-35 (1A Startup FDW Control). Throttle open 1FDW-242 (SG Drain to Condenser' Ctrl). 3.4 Cooldown'the "A" hot leg to < 200* then close: 1FDW-35 (1A Startup FDW Control). 1FDW-242 (SG Drain to Condenser Ctrl)'. 3.5 Stop feed and bleed'of "1A" SG as follows: 1. Close the following valves: 1FDW-141 (SG "1A"' Bottom Drain). 1FDW-142 (SG "1A" Bottom Drain). 1FDW-143 (SG "1A" Bottom Drain). 1FDW-144 (SG "1A" Bottom Drain). 1FDW-334 (SG Shell Drain Hdr. Block). Close 1FDW-103 (1A SG Shell Drain Block). 2. Return to normal the feedwater lineup that supplied FDW from another unit per OP/1/A/1106/08 (Steam Generator Fill, Drain Layup). Unit Supervisor 3.6 Continue with Pressurizer cooldown per Enclosure 4.8 (Pressurizer Cooldown), i

Page 1 of 2 ) Checked Control Copy Date/ Time OP/1/A/1102/10 ENCLOSURE 4.7 LOWERING PRESSURIZER LEVEL WITHOUT RCP'S OPERATING (This procedure aligns RCS letdown from the L'PI to the LDST. This flowpath is to decrease pressurizer level while minimizing RCS hot leg temperature increase). 1 Verify l Date Date Init./ Time Init./ Time 1.0 Initial Conditions 1.1 It is desired to reduce Pressurizer level. 1.2 RCP's OFF. 1.3 LPI system in operation with flow through the 'B' loop. 1.4 HPI available for makeup and auxiliary spray. 1.5 Procedure Limits and Precautions have been reviewed. 2.0 Procedu e j i 2.1 Op-n 1HP-13 (Purification IX Bypass). Plact 1HP-14 (LDST Bypass) in the NORMAL position. 2.2 Close or verify closed the following valves: 1HP-120 (RC Volume Control). 1HP-8 (Purification IX Inlet). q 1HP-9/1HP-11 (Spare Purification IX Isolations). j l

Page 2.of.2 ..t OP/1/A/1102/10 ' ENCLOSURE 4.7 -LOWERING PRESSURIZER LEVEL WITHOUT.RCP'S OPERATING Verify-Date Date Init./ Time Init./ Time -CAUTION:.Do not let. letdown pressure exceed'125 psig in letdown '(2.3) line. i 2.3 Before Pressurizer level reaches 315. inches,- simultaneously: Close-1HP-5'(Letdown Isolation). Throttle open 1LP-96 (LP Supply to Purification I Demineralized Block) until Pressurizer level begins to decrease. NOTE:, .Do not go below 100. inches in Pressurizer. (2.4) 2.4 Slowly decrease Pressurizer level until hot leg temperature reaches 200*F or Pressurizer level approaches 100 inches. 2.5 When Pressurizer reaches desired level, close ILP-96 i (LP Supply to Purification Demineralized Block). 2.6 If Pressurizer. temp is > 200 F, then open 1HP-5 I (Letdown Isolation). 2.7-Re-establish Pressurizer cooldown per Enclosure 4.8 (Pressurizer Cooldown). l 1 1 1 )

Page 1 of 6 Chscked Control Copy Date/ Time OP/1/A/1102/10 ENCLOSURE 4.8 PRESSURIZER C00LDOWN Verify Date Date Init./ Time Init./ Time 1.0 Initial Conditions 1.1 Auxiliary spray is lined up to the Pressurizer per.3 (250 F/350 PSI Condition to Cold Shutdown). 1.2 Verify the following:

  • All'RCP's OFF.
  • RCS pressure approximately 300 psig.
  • PZR level approximately 100 inches.
  • All PZR heaters off.

Htr. Bank #1 Htr. Bank #2 Htr. Bank #3 Htr. Bank #4 1.3 At least 50 inches level in 1A BHUT with Boron concentration > concentration required to maintain 1% AK/K shutdown margin. 1.4 A minimum of one GWD Tank available. 1.5 Procedure Limits and Precautions have been reviewed. 2.0 Procedure 2.1 Refer to Enclosure 4.11 (Low Temperature Over Pressure Protection). J z____ i

i Page^2 off6 OP/1/A/1102/10 ENCLOSURE 4.8 PRESSURIZER C00LDOWN Verify Date-Date ~Init./ Time' Init./ Time 2.2 Open and white tag the following Pressurizer Heater Breakers: Pzr Etr. Group B Bkr. (1XSF-3B) Pzr Htr. Group C Bkr. (1XI-2A) Pzr Htr. Group D Bkr. (1XJ-2A) Pzr Htr. Group E Bkr. (1XH-3A) Pzr Htr. Group'F Bkr (1XI-3A) Pzr Htr. Group G Bkr. (1XJ-3A) Pzr Htr. ' Gr up H Bkr. (1XH-4A) Pzr Htr. Group I Bkr. (1XI-4A) Pzr Htr. Group J Bkr. (1XJ-4A) Pzr Htr. Group A and K Bkr. (1XK-1A) 2.3 After Pzr Htrs breakers are tagged open, reduce Pzr -level to 80 inches. 2.4 Drain Quench Tank to a level of 80 inches and place in' recirculation per OP/1/A/1104/17 (Quench Tank Operation). 2.5 Close IRC-3 (Spray Control Outlet Block). Place 1HP-120 (Makeup Volume Control) in MANUAL and closed. Throttle letdown flow to match RCP seal flow. L_-___-_________

Page 3'of 6 'f I' OP/1/A/1102/10 ENCLOSURE 4.8 PRESSURIZER C00LDOWN Verify Date Date Init./ Time Init./ Time CAUTION: Do not exceed a 90'F/hr. cooldown rate in the Pressu- ~ (2.6) rizer. Enclosure 4.11 (Low Temperature Over Pressure L Protection) is to'be used for Pressurizer level. l restrictions. 2.6 Throttle open 1HP-355 (HPI Aux. Spray Flow Control) to commence Pressurizer Cooldown/Depressurization. 2.6.1 Verify the following restrictions.are main-tained: 1. When RCS Temp. < 220'F and RCS Press. < 1 100 psig: j PZR shall be 5 315 ir.ches 2. When RCS Temp. < 220*F and RCS Press. > 100 psig: ) PZR shall be $ 220 inches RCS Press. shall be 5 350 psig 3. When RCS Temp. > 220*F but < 325'F: PZR shall be $ 260 inches NOTE: Cooldown rate will decrease by itself due to lower AT (2.6.2) between Pressurizer and RCS. 2.6.2 Attempt to achieve ~ 80'F/hr cooldown rate the first hour. 2.6.3 Readjust letdown flow to match RCP-seal flow as RCS pressure decreases. _ __x

Page 4 of 6-. OP/1/A/1102/10 ENCLOSURE 4.8 PRESSURIZER C00LDOWN . Verify Date Date Init./ Time' Init./ Time NOTE: 1HP-120 (RC Volume Control).is to be used only to mini-(2.7). mize the affects of PZR outsurge on RCS hot leg tempera-ture, NOT to increase PZR level. Any increase in PZR level should be due to Auxiliary Spray flow. J2.7 Throttle open 1HP-120 (RC Volume Control) only as-necessary to maintain PZR surge line temperature (Comp. Pt. A1454) subcooled for the existing RCS pressure and hot' leg temperature < 190*F. NOTE: When'RCS pressure is reduced to 30 psig, pressure (2.8)- will be maintained by nitrogen control per OP/0/A/1103/05 (Pressurizer Operation). 2.8 When RCS pressure is approximately 200 psig, commence lineup to maintain RCS pressure control by nitrogen overpressure per OP/0/A/1103/05 (Pressurizer Operation). . Unit Supervisor 2.9 When Pressurizer level reaches 220 inches, check RCS pressure: 1. If RCS pressure is less than 100 psig, continue with the cooldown. 2. If RCS pressure is greater than 100 psig, go to.7. (Lowering Pressurizer Level Without RCP's Operating) to lower pressurizer level. 2.10 If Pressurizer level reaches 315 inches, and Pressurizer temperature is > 300 F, go to Enclosure 4.7 (Lowering Pressurizer Level Without RCP's Oeprating) to lower Pressurizer level.

Page 5 of 6' -. -y OP/1/A/1102/10 ENCLOSURE 4.8 PRESSURIZER C00LDOWN' L Verify Date Date 'Init./ Time-Init./ Time 2.11 When Pressurizer temperature is < 300*F, establish" communication-in the Reactor Building at IRC-17 (Surge- .i Line Drain)-and IRC-18'(Surge Line Drain Block). -i 2.12. Place '1A' BHUT in recirculation. 2.13 Open;1RC-18_(Surge Line Drain Block). NOTE: This' allows a Pressurizer outsurge flowpath to other . ( 2.14). .than the RCS Hot Legs.. Attempt to maintain constant pressurizer level;-however, a very slow increase in level is acceptable. 2.14.0 pen IRC417 (Surge Line Drain) to compensate for . Auxiliary Spray Flow. NOTE: This is'to break up any crud that may be accumulated. (2.14.1) 1 2.14.1 If necessary to achieve flow through the ~ Surge Line Drain, then mechanical agitate l the piping around IRC-17 and IRC-10. 2.15 Maintain Quench Tank Level between 80 and 125 inches per OP/1/A/1104/17 (Quench Tank Operation). CAUTION:,The outsurge of hot Pressurizer water into the hot leg (2.16) has the potential for causing a staam bubble in the hot leg. 2.16 If saturated conditions occur in the hot leg which is indicated by hot leg temperature above the saturation temperature and a rapid increase in Pressurizer level, refer to Enclosure 4.6 (Procedure for Subcooling the Hot Leg Following a Pressurizer Outsurge).

n. ~ Page 6 of.6 Y OP/1/A/1102/10 ENCLOSURE 4.8 PRESSURIZER C00LDOWN Verify 'Date -Date-Init./ Time Init./ Time 2.17 If Pressurizer temperature is not less than 200 when ) Pressurizerflevel reaches 315 inches,' perform the following: 1. 'Close 1HP-355 (HP. Aux. Spray Flow Control). Continue to lower Pressurizer level'.through the i Surge line Drain Valves. Continue to'use 1HP-120 (RC Volume Control) only to mihimize Pressu'izer outsurge, not to increase r pressurizer level. Continue to match letdown flow to seal flow to minimize insurge. 2. When pressurizer level has decreased to ~ 200-inches,' throttle open 1HP-355 (HP Aux. Spray Flow Control) to commence Pressurizer cooldown and depressurization. 3. If pressurizer level reaches 315 inches again before Pressurizer temperature is 5 200*, perform Steps 2.14.1 and 2.14.2. 2.18 When Pressurizer temperature is 5 200*F close: 1RC-17-(Surge Line Drain). 1RC-18 (Surge Line Drain Block). 1HP-355 (HPI Aux. Spray Flow Control). p 1HP-120 (Makeup Volume Control). 1 2.19 Remove '1A' BHUT from recirculation. 2.20 Proceed with cooldown per Enclosure 4.3 (250*7/350 PSI Conditions to Cold Shutdown). f b .______-_-__________ _ Y

Ch:cktd Control Copy OP/1/A/1102/10 Page l'of 4 Ftrm 34873 m343) ENCLOSURE 4.9 SHUTDOWN EQUIPMENT TAGGING LIST Date/ Time E LECTRICAL CHECKLIST TAGGED O COMPONENT NAME LOCATION POSITION INITIAL N MBER TAG Racked Out ITC 1A HPI Pumo Motor Bkr. Racked IB HP.L Pump Motor Bkr. 1TE Out Racked 10 HPI Pumo Motor Bkr. 1TD Out Racked 1A MDEFDWP Motor Bkr. 1TD Out Racked IB MDEFDWP Motor Bkr. ITE Out Racked IE1 Heater Drain Pumo Motor Bkr. 1TE Out Racked IE2 Heater Drain Pumo Motor Bkr. 1TD Out Racked 1D1 Heater Drain Pumo Motor Bkr. ITE Out Racked 1D2 Heater Drain Pumo Motor Bkr. ITD Out Racked 1A CBP Motor Skr. 1TC Out Racked 1B CEP Motor Bkr. 1TD Out Racked 1C CBP riotor Bkr. 1TE Out Racked 1A HWP Motor Bkr. 1TC Out Racked 1B HWP Motor Bkr. ITD Out Racked 1C HWP Motor Bkr. ITE Out 'i Racked 1A1 RCP Motor Bkr. ITA Out Racked 1A2 RCP Motor Bkr. ITB Out Racked IB1 RCP Motor Bkr ITA Out J Racked 1B2 RCP Motor Bkr. 1TB Out Racked 1 Unit 1 Steam Pack Exh. Motor Bkr. IXA Out Racked CSAE Off-Gas Blower Motor Bkr. 1XGA Out Racked 1A EHC Pump Metor Bkr. 1XA Out Racked IB EHC Pump Motor Bkr. 1XGB Out

OP/1/A/1102/10 Page 2 of 4 . Firm 34873 (R343) ENCLOSURE 4.9 SHUTDOWN EQUIPMENT TAGGING LIST ELECTRICAL CHECKLIST TAGGED COMPONENT NAME LOCATION POSITION INITIAL N MBER TAG i Pzr. Htr. Groun B Bkr. 1YSF-1B-Onen Pzr. Htr. Group F. Ekr. 1YH-1A Onen Pze. Htr. Group H Ekr. 1YH-4A Onen Pzr. Htr. Group C Bkr. 1YT-2A Onen Pzr. Htr. Groun F Bkr. 1YT-1A onen Pzr. Htr. Groun I Bkr. 1YT-4A Onen j Pzr. Mtr. Group D Ekr. 1 Y.T-2 A Onen l Pzr. Htr. Group G Ekr. 1YT-1A Onen P'z r. Htr. Groun J Bkr. 1 Y.T-4 A Onen P7R Htr. Group A & Group K Ekr. 1YY-1A Onen PNLBD Gp. A R-2F-Main BKR PZR Htr. Group A Main Bkr. S of Flev. Onen PNLBD Gp. B R-1F-Main BKR P7R Htr. Group B Main Bkr. Emerg. Hatch Onen PNLBD Gp. C R-2F-Main BKR PZR Htr. Group C Main Bkr. S of Elev. Onen PNLBD Gp. D R-2F-Main BKR PZR Hte. Group D Main Bkr. S of Elev. Onen PNIBD Gp. E R-2F-Main BKR PZR Htr. Group E Main Bkr. S of Flev. Onen PNLBD Gp. F R-2F-Main BKR PZR Htr. Group F Main Bkr. S of Elev. Onen j PNLBD Cp. G R-2F-Main BKR PZR Htr. Group G Main Bkt. S of Elev. Onen PNLBD Gp. H R-2F-Main BKR PZR Htr. Group H Main Bkr. S of Elev. Ooen PNLBD Gp. I R-2F-Main BKR PZR Htr. Group I Main Bkr. S of Elev. Open PNLBD Gp. J R-2F-Main BKR PZR Htr. Group J Main Bkr. S of Elev. Onen PNLBD Gp. K R-2F-Main BKR PZR Htr. Group K Main Bkr. S of Elev. Onen 1

OP/1/A/1102/10 Page 3 of 4 Form 34873 (R343) ENCLOSURE 4.9 SHUTDOWN EQUIPMENT TAGGING LIST ELECTRICAL CHECKLIST TAGGED CO PO" " COMPONENT NAME LOCATION POSITION INITIAL N BER TAG i 1AS-40 Bkr. Aux. Steam Supply to CSAE'S 1XC Open 1AS-34 Bkr. Aux. Steam Supply to 'E' Htrs. 1XGA Open 1AS-8 Bkr. Steam Seal Regulator Steam Supolv IXA Open i l I 1AS-102 Bkr. FWPT Aux. Steam Supply Block IXGA Open 1HP-24 Bkr. BWST Supp1v to HPI 1XS1 Ooen 1HP-25 Bkr. BWST Supply to HPI IXS2 Open i 1AS-11 Bkr. AS to MSRH IXA Open l ,I f i

OP/1/A/1102/10 Pags 4 of 4 ENCLOSURE 4.9 i SHUTDOWN EQUIPMENT TAGGING LIST VALVE CHECKLIST TAGGED VALVE NO. VALVE NAME LOCATION BT POSITION INITIAL l l lT-1-C19 l. l l l l 1AS-38 i TDEFDWPT Auxiliary Steam Supply (West l l Closed l l l l lT-1-D19/ l l l l 1 l 1MS-90 l Main Steam to TDEFDWPT l East /D20 I l Closed l l l l lT-3-L18 l l Handwheell J l 1AS-34 l Aux. Steam Supply to 'E' Heaters l l l Closed l l l l lT-3-B25 l l Handwheel l l l 1AS-40 l Aux. Steam Supply to CSAE's l l l Closed l l ) l l lT-3-E15 l l Handwheell l l l 1AS-8 l Steam Seal Regulator Steam Supply l l l Closed l~ l l l lT-3-J21 l l Handwheell l l 1AS-302 l FWPT Aux. Steam Supply Block l l l Closed l l l l lA-1-HPI l l Handwheell l l l 1HP-24 l BWST Supply to HPI l Hatch Area l l Closed l l l j lA-1-HPi l l Handwheell l l l 1HP-25 l BWST Supply to HPI l Hatch Area l l Closed l l l l l lT-3-L15 l l l l l 1MS-127 l MS to AS Supply l l l Closed l l J l lT-3-L15 l l l l I l 1MS-130 l MS to AS Supply l l l Closed l l l j lT-3-L15 l l l l l 1MS-131 i MS to AS Supply l l ' Closed l l-l l lT-1-E14 l l Handwheell l 1AS-11 AS to MSRH I l I Closed l l lT-3-F15 l l l l l 1HPE-34 1 'C' Bleed to Plant Heating l l l Closed l I l l lT-1-D24 l l l l l 1AS-145 i PH to FWPT Pumping Trap l _) l Closed l l l l lT-1-G20 l l l l l 1AS-306 I PH to Bypass Line Pumping Trap l l l Closed l l l lT-1-M19 l l l l 1AS-107 l HP FDW Heater Blanket i l l Closed l l l l l l l 1 l l l l l 1 I I I I I I l l l l l l l 1 l l l 1 l 1 l l 1 1 I I I I l l l l .I I l 1 l l l I I l l l 1 l l l l l 1 l 1 l l l I I i i l l I I l l l l l l l l l l l l l l l l l l I I I I I l i i i I I I I l 1 i l l l l l l l l 1 1 I l I l l 1 I l l l l I d

l Page 1 of 3 l Checked Control Copy Date/ Time j' OP/1/A/1102/10 ENCLOSURE 4.10 CONTROLLING PROCEDURE FOR H 0 ADDITION TO THE RCS 2 Date Init./ Time 1.0 Initial Conditions 1.1 RCS temperature is 195'-140 F. 1.2 Pressurizer level is ~ 220 inches. 1.3 LDST level is ~ 55 inches. 1.4 A RCP is in operation. 1.5' Ensure Unit 1 Purification IX is in service and/or Unit 1&2 Spare Purification IX is in service and boron saturated to RCS boron concentration. 1.6 Limits and Precautions have been reviewed. 2.0 Procedure NOTE: RCS temperature of 195*-140*F shall be maintained (2.0) throughout this enclosure. For this enclosure, the RCS heatup curves, shown on Enclosure 4.10A (RCS P/T Limitations), are to be used. j NOTE: Letdown flow should be maintained at ~ 120 gpm when one (2.1) IX in service or ~ 140 to 150 gpm when both IXs in service. 2.1 Increase letdown flow to ~ 120 gpm or 140 to 150 gpm if both IXs in service. 2.2 If required to maintain letdown flow at ~ 120 gpm, i or 140 to 150 (if both IXs are in service), open 1HP-42 (Letdown Orifice Manual Bypass). 2.3 Notify Chemistry to begin their H 0, additions per 2 CP/0/A/2002/10 (Addition of Hydrogen Peroxide to the l Reactor Coolant System).

Pa,;e 2 of 3 OP/1/A/1102/13 ENCLOSURE 4.10 CONTROLLING PROCEDURE FOR H:02 ADDITION TO THE RCS' Date Init./ Time 2.4 Contact Health Physics to begin their survey program applying to induced crudbursts, listed in H.P. Section Manual 6.2. 2.5 Close iRC-1 (Spray Control). CAUTION RCS temperature 180*-160* shall be maintained during (2.6) the running of two RCPs. Should it not be possible to maintain RCS temperature within this range while running two RCPs, or a RCS temperature decrease of > 10 F has been observed, secure one of the RCPs and refer to RCS cooldown curves. At the Shift Supervisor's discretion the Unit may be returned to one RCP operation at any time during this procedure. NOTE: The RCS may be allowed to heat up to - 180 F, but (2.6) do not cooldown the RCS with two RC pumps running. ~2.6 Perform the following: 1) Cooldown the RCS to ~ 160*F. 2) Start a second RC Pump per OP/1/A/1103/06 (Reactor Coolant Pump Operation). 3) Maintain RCS temperature. 2.7 Start and stop RCPs during this procedure as directed by the Unit Operation Engineer or the Shift Engineer per OP/1/A/1103/06 (Reactor Coolant Pump Operation). 2.8 When notified by Chemistry that the crudburst is complete: Notify Health Phys'ics S and C group that the crudburst evolution is complete. l I J

Page 3 of 3 OP/1/A/1102/10 l ENCLOSURE 4.10 CONTROLLING PROCEDURE FOR H 0 ADDITION TO THE RCS 2 Date Init./ Time Continue with Unit Shutdown per Enclosure 4.3 ' (250*F/350 psi Conditions to Cold Shutdown), of i OP/1/A/1102/10 (Controlling Procedure for Unit Shutdown), i 2.9 Remove one of the Purification IXs from service per l OP/1/A/1104/02 (High Pressure Injection System). 2.10 Position 1HP-42 (Letdown Orifice Manual Bypass) as necessary to maintain letdown flow. i .j

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Page 1 of 2 l l Checked Control Copy l' Date/ Time l l OP/1/A/1102/10 ENCLOSURE 4.11 LOW TEMPERATURE OVERPRESSURE PROTECTION (LTOP) 1.0 Initial Conditions J 1.1 Dedicated LTOP Operator is required whenever RCS Temperature < 325'F and an HPI Pump is operating. 1.2 LTOP Operator is an R0 or SRO. 1.3 Prevention of low temperature overpressurization due to 1HP-120 (RC Volume Control) failing open is the only responsibility and duty of the LTOP Operator. 2.0 Procedure 2.1 Surveillance Requirements: 2.1.1 Continuously monitor the following indications to detect excessive RCS makeup flow due to 1HP-120 (RC Volume Control) failing open: RCS Pressure Pressurizer Lesel l l 2.1.2 Verify the following restrictions are maintained: 1. When RCS Terip. < 220*F and RCS Press. 5 100 psig: PZR shall be 5 315 inches 2. When RCS Temp. < 220*F and RCS Press. > 100 psig: l PZR shall be < 220 inches J RCS Press. shall be < 350 psig 1 3. When RCS Temp. > 220*F but < 325'F: l PZR shall be $ 260 inches l 2.1.5 Prior to turning over LTOP responsibility to another individual, l ensure the new LTOP Operator has reviewed this entire procedure. l

) OP/2/A/1102/10 -( ENCLOSURE 4.11 LOW TEMPERATURE OVERPRESSURE PROTECTI 1 2.2 LTOP Operator Actions For Excessive RCS Hakeup Flow: 2.2.1 If 1HP-120 (RC Volume Control) fails open: 1. Start IB HPI Pump. 2. Stop 1A HPI Pump. 3. Close 1HP-115 (Pump "A" & "B" Discharge Hdr Separation). 4 If 1HP-115 (Pump "A" & "B" Discharge Hdr Separation) fails to close, stop all HPI ' umps to prevent exceedi P ng 1RC-66 (PORV) Setpoint and RCS P/T Limits. I i --}}

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