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=Text=
=Text=
{{#Wiki_filter:OT-3701-E12_506_RO Rev 0
{{#Wiki_filter:OT-3701-E12_506_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:
 
E12, Residual Heat Removal Time Critical:
JOB PERFORMANCE MEASURE SETUP SHEET
No Alternate Path:
 
Yes Applicability:
System: E12, Residual Heat Removal Time Critical: No Alternate Path: Yes Applicability: RO Safety Function: 4 - Heat Removal From The Core Setting: Simulator Validated: 36 minutes
RO Safety Function:
4 - Heat Removal From The Core Setting:
Simulator Validated:
36 minutes  


==References:==
==References:==
SOI-E12 Rev. 71 & ONI -E12-2Rev. 38 Required Material SOI-E12 - Residual Heat Removal System Tasks: 205-535-01-01 Warmup and Initiate Shutdown Cooling from Standby Readiness Task Standard: Initiate SDC in Alternate Return Path mode prior to exceeding 200° F in vessel.
SOI-E12 Rev. 71 & ONI-E12-2 Rev. 38 Required Material SOI-E12 - Residual Heat Removal System Tasks:
K/A Data: 205000 Ability to (a) predict the impacts of the following on the Shutdown Cooling System (RHR Shutdown Cooling Mode); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.06 SDC/RHR pump trips.
205-535-01-01 Warmup and Initiate Shutdown Cooling from Standby Readiness Task Standard:
Importance RO 3.4 / SRO 3. 5. A2.10 R Valve operation. Importance: RO 2.9 SRO 2.9 Ability to manually operate and/or monitor in the control room: A4.01 SDC/RHR pumps Importance RO 3.7 / SRO 3.7. A4.03 SDC/RHR discharge valves Importance RO 3.6 / SRO 3.5. A4.09 System flow. Importance RO 3.1 / SRO 3.1
Initiate SDC in Alternate Return Path mode prior to exceeding 200° F in vessel.
 
K/A Data:
OT-3701-E12_506_RO Rev 0
205000 Ability to (a) predict the impacts of the following on the Shutdown Cooling System (RHR Shutdown Cooling Mode); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.06 SDC/RHR pump trips.
Importance RO 3.4 / SRO 3.5. A2.10 R Valve operation. Importance: RO 2.9 SRO 2.9 Ability to manually operate and/or monitor in the control room: A4.01 SDC/RHR pumps Importance RO 3.7 / SRO 3.7. A4.03 SDC/RHR discharge valves Importance RO 3.6 / SRO 3.5. A4.09 System flow. Importance RO 3.1 / SRO 3.1  


JOB PERFORMANCE MEASURE SETUP SHEET contd.
OT-3701-E12_506_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET contd.
: 1. Simulator Setup Instructions: Reset simulator to a shutdown IC with RPV temperature about 160°. Insert malfunctions mv06_1e12f0053a & cb01_1e12C0002b for F053A failure and RHR B pump breaker trip. Set decay heat level to obtain a H/U rate of ~
: 1.
40°/hr (~8.83E6 watts). Maintain reactor v essel level between 260 and 270 inches using G33 blowdown. Simulator driver to control vessel level. Complete necessary portions of SOI-E12 Sect 4.7 through Step 4.7.18. Provide marked-up copy of SOI-E12. For 2017 ILO: R eset simulator to IC 68. Load schedule E12-506. Place simulator in freeze.
Simulator Setup Instructions: Reset simulator to a shutdown IC with RPV temperature about 160°. Insert malfunctions mv06_1e12f0053a & cb01_1e12C0002b for F053A failure and RHR B pump breaker trip. Set decay heat level to obtain a H/U rate of ~
Place simulator in run after reading Initial Conditions to Operator. Remove Attachment 42 from SOI and give to Evaluator.
40°/hr (~8.83E6 watts). Maintain reactor vessel level between 260 and 270 inches using G33 blowdown. Simulator driver to control vessel level. Complete necessary portions of SOI-E12 Sect 4.7 through Step 4.7.18. Provide marked-up copy of SOI-E12. For 2017 ILO: Reset simulator to IC 68. Load schedule E12-506. Place simulator in freeze.
: 2. Location / Method: Simulator / performance
Place simulator in run after reading Initial Conditions to Operator. Remove 2 from SOI and give to Evaluator.
: 3. Initial Condition: The p lant shutdown due to scram yesterday. Currently in Mode 4 and the Unit Supervisor is operating in IOI-12, Maintaining Cold Shutdown. RHR B was operating in Shutdown Cooling when the pump tripped 20 minutes ago. The Unit Supervisor has entered ONI -E12-2 Loss of Decay Heat Removal. Reactor Recirculation pumps are in operation. Reactor temperature band is 135 to 145° F. RPV temperature was 140° F prior to trip. Current RPV temperature is ~160° F. The RO shifting SDC loops became ill.
: 2.
: 4. Initiating Cue: The Unit Supervisor directs you the Reactor Operator to continue shifting Shutdown Cooling loops from B to A using RHR A through the Normal Return Path.
Location / Method: Simulator / performance
: 3.
Initial Condition: The plant shutdown due to scram yesterday. Currently in Mode 4 and the Unit Supervisor is operating in IOI-12, Maintaining Cold Shutdown. RHR B was operating in Shutdown Cooling when the pump tripped 20 minutes ago. The Unit Supervisor has entered ONI-E12-2 Loss of Decay Heat Removal. Reactor Recirculation pumps are in operation. Reactor temperature band is 135 to 145° F. RPV temperature was 140° F prior to trip. Current RPV temperature is ~160° F. The RO shifting SDC loops became ill.
: 4.
Initiating Cue: The Unit Supervisor directs you the Reactor Operator to continue shifting Shutdown Cooling loops from B to A using RHR A through the Normal Return Path.
Section 4.7 Shutdown Cooling Startup for RHR A is complete through Step 4.7.18.
Section 4.7 Shutdown Cooling Startup for RHR A is complete through Step 4.7.18.
Monitor Reactor Temperature per IOI-12.
Monitor Reactor Temperature per IOI-12.
Start Time:
End Time:
Operator:


Start Time: End Time:
OT-3701-E12_506_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
 
Operator:
 
OT-3701-E12_506_RO Rev 0
 
JPM BODY SHEET
 
Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
 
Standard: Performer follows management expectations with regards to safety and communication standards.
Standard: Performer follows management expectations with regards to safety and communication standards.
 
Step 1 SOI-E12, RESIDUAL HEAT REMOVAL SYSTEM 2.0 Precautions And Limitations 2.2 Observe the following limitations during the operation of the RHR pumps:
Step 1
 
SOI-E12, RESIDUAL HEAT REMOVAL SYSTEM
 
2.0 Precautions And Limitations
 
2.2 Observe the following limitations during the operation of the RHR pumps:
* Do not operate the RHR pump against a shutoff head for greater than 8 seconds.
* Do not operate the RHR pump against a shutoff head for greater than 8 seconds.
2.6 Operation of the LPCI mode of RHR with injection flow to the vessel shall only be done in an accident condition, a plant emergency condition, or an approved test condition of short duration. ONI-E12-2, Loss of Decay Heat Removal, and IOI-11, Shutdown From Outside Control Room, direct the use of the LPCI injection lines as Alternate Shutdown Cooling flow paths. Use of this flow path is still subject to reportability (as described in PAP-1604) when used for Alternate Shutdown Cooling.
2.6 Operation of the LPCI mode of RHR with injection flow to the vessel shall only be done in an accident condition, a plant emergency condition, or an approved test condition of short duration. ONI-E12-2, Loss of Decay Heat Removal, and IOI-11, Shutdown From Outside Control Room, direct the use of the LPCI injection lines as Alternate Shutdown Cooling flow paths. Use of this flow path is still subject to reportability (as described in PAP-1604) when used for Alternate Shutdown Cooling.
4.7 Shutdown Cooling Startup for RHR A(B)
4.7 Shutdown Cooling Startup for RHR A(B)
Operator reviews place-kept copy of SOI-E12 including Precautions and Limitations and panel H13-P601.
Operator reviews place-kept copy of SOI-E12 including Precautions and Limitations and panel H13-P601.
Standard:
The Operator reviews place-kept copy of SOI-E12 Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Standard: The Operator reviews place-kept copy of SOI-E12
OT-3701-E12_506_RO Rev 0 Step 2 4.7.19 Hold the Oncoming RJR HXS BYPASS VALVE in CLOSE for 59-62 seconds.
 
1E12-F048A Critical Step:
Instructor Cue: None
The Operator closes 1E12-F048A for 59-62 seconds.
 
Instructor Cue:
Notes: None SAT ___ UNSAT ___
None Notes:
 
If the Operator fails to close the valve inside this time band, this Critical Step can be recovered in JPM Step 9.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Step 3 4.7.20 Hold the Oncoming RHR HXS OUTLET VALVE in CLOSE until closed.
1E12-F003A Critical Step:
The Operator closes 1E12-F003A.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


OT-3701-E12_506_RO Rev 0
OT-3701-E12_506_RO Rev 0 Step 4 4.7.21 It is desired to establish the Normal Return Path 1E12-F053A 1E12-F053B RHR Upper Pool Cooling Isol is closed 1E12-F037A 1E12-F037B LPCI Injection Valve is closed 1E12-F042A 1E12-F042B THEN PERFORM the following:
 
Step 2
 
4.7.19 Hold the Oncoming RJR HXS BYPASS VALVE in CLOSE for 59 -62 seconds.
1E12-F048A
 
Critical Step: The Operator closes 1E12 -F048A for 59 -62 seconds.
 
Instructor Cue: None
 
Notes: If the Operator fails to close thevalve inside this time band, this Critical Step can be recovered in JPM Step 9.
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
Step 3
 
4.7.20 Hold the Oncoming RHR HXS OUTLET VALVE in CLOSE until clo sed.
1E12-F003A
 
Critical Step: The Operator closes 1E12 -F003A.
 
Instructor Cue: None
 
Notes: None SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701-E12_506_RO Rev 0
 
Step 4
 
4.7.21 It is desired to establish the Normal 1E12-1E12-Return Path F053A F053B RHR Upper Pool Cooling Isol is closed 1E12-1E12-F037A F037B LPCI Injection Valve is closed 1E12-1E12-F042A F042B THEN PERFORM the following:
 
4.7.21.a IF the Feedwater System is shutdown, THEN VERIFY the Oncoming RHR loop FDW HDR SHUTOFF is closed, to prevent flow to the feedwater system.
4.7.21.a IF the Feedwater System is shutdown, THEN VERIFY the Oncoming RHR loop FDW HDR SHUTOFF is closed, to prevent flow to the feedwater system.
1B21-F065A 1B21-F065B
1B21-F065A 1B21-F065B Standard:
The Operator observes that feedwater is shutdown and the B21-F065s are closed.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Standard: The Operator observes that feedwater is shutdown and the B21-F065s are closed.
OT-3701-E12_506_RO Rev 0 Step 5 CAUTIONS
 
* The RHR PUMP MIN FLOW VALVE is downpowered in the closed position. Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
Instructor Cue: None
 
Notes: None SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701-E12_506_RO Rev 0
 
Step 5
 
CAUTIONS
* The RHR PUMP MIN FLOW VALVE is downpowered in the closed position. Throttling open the RHR HXS BYPASS VALVE, 1E12 -F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
* Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
* Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
 
4.7.21.b INITIATE flow through the SHUTDOWN COOLING TO FDW SHUTOFF as follows:
4.7.21.b INITIATE flow through the SHUTDOWN COOLING TO FDW SHUTOFF as follows: 1E12-F053A
1E12-F053A 4.7.21.b.1 PERFORM the following simultaneously:
 
* HOLD the SHUTDOWN COOLING TO FDW SHUTOFF in OPEN, UNTIL open.
4.7.21.b.1 PERFORM the following simultaneously :
1E12-F053A
* HOLD the SHUTDOWN COOLING TO FDW SHUTOFF in OPEN, UNTIL open. 1E12-F053A
* TAKE the RHR PUMP to START.
* TAKE the RHR PUMP to START. 1E12-C002A 4.7.21.b.2 WITHIN 8 seconds, THROTTLERHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.
1E12-C002A 4.7.21.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.
 
Standard The Operator starts to open 1E12-F053A and starts RHR A pump.
Standard The Operator starts to open 1E12-F053A and starts RHR A pump.
 
Critical Step:
Critical Step: If the operator starts the RHR pump, he must shut it down.
If the operator starts the RHR pump, he must shut it down.
 
Instructor Cue:
Instructor Cue: If necessary, after report of valve failure, if pump was started, question operator on a course of action.
If necessary, after report of valve failure, if pump was started, question operator on a course of action.
Direct Operator to establish shutdown cooling.
Direct Operator to establish shutdown cooling.
 
Notes:
Notes: Operator may or may not start pump if he notices failure of 1E12-F053A.
Operator may or may not start pump if he notices failure of 1E12-F053A.
1E12-F053A is failed closed and will lose indication simulating blown fuse. If Operator started pump, the Minimum Flow Valve was down-powered per step 4.7.10.c and the pump will not have minimum flow protection.
1E12-F053A is failed closed and will lose indication simulating blown fuse. If Operator started pump, the Minimum Flow Valve was down-powered per step 4.7.10.c and the pump will not have minimum flow protection.
SAT ___ UNSAT ___
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Comment(s): ________________________________________________________________
OT-3701-E12_506_RO Rev 0 Step 6 4.7.22 It is desired to establish the Refuel Return Path 1E12-F037A 1E12-F037B Operator determines that this step is N/A.
 
Standard:
OT-3701-E12_506_RO Rev 0
This Step is N/A. The Operator cannot use Refuel Mode Path.
 
Instructor Cue:
Step 6
None Notes:
 
Plant not in Mode 5, Vessel Head installed.
4.7.22 It is desired to establish the Refuel 1E12-1E12-Return Path F037A F037B
SAT ___
 
UNSAT ___
Operator determines that this step is N/A.
Comment(s): ________________________________________________________________  
 
Standard: This Step is N/A. The Operator cannot use Refuel Mode Path.
 
Instructor Cue: None
 
Notes: Plant not in Mode 5, Vessel Head insta lled.
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________


OT-3701-E12_506_RO Rev 0
OT-3701-E12_506_RO Rev 0 Step 7 CAUTION Operation of the RHR Loop with Vessel Injection via the LPCI Injection Line has the potential to result in fatigue failure of incore instrument tubes and burnishing of fuel channels.
 
The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.
Step 7
 
CAUTION
* Operation of the RHR Loop with Vessel Injection via the LPCI Injection Line has the potential to result in fatigue failure of incore instrument tubes and burnishing of fuel channels.
* The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.
Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
* Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
 
4.7.23 It is desired to establish the Alternate Return Path 1E12-F042A 1E12-F042B Normal Shutdown Cooling return path is unavailable 1E12-F053A 1E12-F053B Refuel Shutdown Cooling return path is unavailable 1E12-F037A 1E12-F037B THEN PERFORM the following:
4.7.23 It is desired to establish the Alternate 1E12-1E12-Return Path F042A F042B Normal Shutdown Cooling return path 1E12-1E12-is unavailable F053A F053B Refuel Shutdown Cooling return path is 1E12-1E12-unavailable F037A F037B THEN PERFORM the following:
 
4.7.23.a REFER TO Alternate Shutdown Cooling Data (Attachment 42) and TAKE Pre-Start Data.
4.7.23.a REFER TO Alternate Shutdown Cooling Data (Attachment 42) and TAKE Pre-Start Data.
Standard:
The Operator requests/obtains/completes Attachment 42.
Instructor Cue:
None Notes:
When Operator goes to green book to obtain Att-42, provide him with a Yellow copy of Attachment 42.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Standard: The Operator re quests/obtains/completes Attachment 42.
OT-3701-E12_506_RO Rev 0 Step 8 CAUTIONS
 
Instructor Cue: None
 
Notes: When Operator goes to green book to obtain Att-42, provide him with a Yellow copy of Attachment 42.
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701-E12_506_RO Rev 0
 
Step 8
 
CAUTIONS
* The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.
* The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.
Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
* Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
* Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
4.7.23.b INITIATE flow through the LPCI INJECTION VALVE as follows:
4.7.23.b INITIATE flow through the LPCI INJECTION VALVE as follows:
1E12-F042A 4.7.23.b.1 PERFORM the following simultaneously:
1E12-F042A 4.7.23.b.1 PERFORM the following simultaneously:
* TAKE the LPCI INJECTION VALVE to OPEN. 1E12-F042A
* TAKE the LPCI INJECTION VALVE to OPEN.
* TAKE the RHR PUMP to START. 1E12-C002A
1E12-F042A
 
* TAKE the RHR PUMP to START.
Critical Step: The Operator takes 1E12-F042A to OPEN and starts RHR A pump.
1E12-C002A Critical Step:
 
The Operator takes 1E12-F042A to OPEN and starts RHR A pump.
Instructor Cue: None
Instructor Cue:
 
None Notes:
Notes: None SAT ___ UNSAT ___
None SAT ___
 
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________  
 
OT-3701-E12_506_RO Rev 0
 
Step 9
 
4.7.23.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.
1E12-F048A 1E12-R603A 4.7.23.c JOG OPEN the RHR HXS BYPASS VALVE in 1000 -2000 gpm increments, UNTIL RHR PUMP FLOW is 2575-7100 gpm.
1E12-F048A 1E12-R603A
 
Critical Step: Within 8 seconds the Operator open s 1E12-F048A until flow is > 2575 gpm then controls flow within directed band.
 
Instructor Cue: Reactor coolant temperature band is 135 to 145 deg F
 
Notes: If JPM Step 2 was performed correctly, this Step is not Critical.


OT-3701-E12_506_RO Rev 0 Step 9 4.7.23.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.
1E12-F048A 1E12-R603A 4.7.23.c JOG OPEN the RHR HXS BYPASS VALVE in 1000-2000 gpm increments, UNTIL RHR PUMP FLOW is 2575-7100 gpm.
1E12-F048A 1E12-R603A Critical Step:
Within 8 seconds the Operator opens 1E12-F048A until flow is > 2575 gpm then controls flow within directed band.
Instructor Cue:
Reactor coolant temperature band is 135 to 145 deg F Notes:
If JPM Step 2 was performed correctly, this Step is not Critical.
Reactor coolant temperature should be between 165 and 180 degrees if Operator establishes flow with some urgency. If Operator delays and spends time reviewing the procedure, Reactor temperature could be as high as 190 degrees. Initial flow will be 3500 gpm. Temperature indication will be RHR Out on SPDS or Point 5 on recorder with E12-F003A closed.
Reactor coolant temperature should be between 165 and 180 degrees if Operator establishes flow with some urgency. If Operator delays and spends time reviewing the procedure, Reactor temperature could be as high as 190 degrees. Initial flow will be 3500 gpm. Temperature indication will be RHR Out on SPDS or Point 5 on recorder with E12-F003A closed.
SAT ___ UNSAT ___
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Comment(s): ________________________________________________________________
OT-3701-E12_506_RO Rev 0 Step 10 4.7.23.d NOTIFY the following of the use of the Shutdown Cooling return flow to the Vessel via LPCI INJECTION VALVE so the required fuel inspection may be scheduled:
 
OT-3701-E12_506_RO Rev 0
 
Step 10
 
4.7.23.d NOTIFY the following of the use of the Shutdown Cooling return flow to the Vessel via LPCI INJECTION VALVE so the required fuel inspection may be scheduled:
* Reactor Engineering.
* Reactor Engineering.
* Outage Planning.
* Outage Planning.
 
4.7.23.e INITIATE a special report to the NRC in accordance with NOP-OP-1015, Event Notifications.
4.7.23.e INITIATE a special report to the NRC in accordance with NOP -OP-1015, Event Notifications.
4.7.23.f GO TO RHR Shutdown Cooling Operations for RHR A(B).
4.7.23.f GO TO RHR Shutdown Cooling Operations for RHR A(B).
 
Standard:
Standard: The Operator will proceed to Section 7.6, RHR Shutdown Cooling Operations for RHR A(B).
The Operator will proceed to Section 7.6, RHR Shutdown Cooling Operations for RHR A(B).
 
Instructor Cue:
Instructor Cue: Steps 4.7.23.d & e are being performed by the Shift Manager.
Steps 4.7.23.d & e are being performed by the Shift Manager.
 
Notes:
Notes: None SAT ___ UNSAT ___
None SAT ___
 
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Step 11 7.6 RHR Shutdown Cooling Operations for RHR A(B)
NOTES Normal Design parameters for Shutdown Cooling/Test Mode operation:
RHR Pump Flow 7000-7100 gpm.
RHR Pump Amps 95-110 Amps.
RHR A Head Spray Flow 0 - 500 gpm.
RHR Suction Pressure Less than 135 psig.
RHR HX ESW Outlet Temps Less than 108oF.
RHR Pump Suct Temp Less than 100oF (Refuel Mode).
RHR HXS RHR Outlet Temp Less than 86oF (Refuel Mode).
The following actions can be performed in any logical order or repeated to support current plant conditions.
Step 11 - Continued next page


Step 11
OT-3701-E12_506_RO Rev 0 Step 11 - Continued 7.6.1 OBSERVE the following limitations when in Shutdown Cooling:
 
7.6 RHR Shutdown Cooling Operations for RHR A(B)
NOTES
* Normal Design parameters for Shutdown Cooling/Test Mode operation:
- RHR Pump Flow 7000-7100 gpm.
- RHR Pump Amps 95-110 Amps.
- RHR A Head Spray Flow 0 - 500 gpm.
- RHR Suction Pressure Less than 135 psig.
- RHR HX ESW Outlet Temps Less than 108 oF.
- RHR Pump Suct Temp Less than 100oF (Refuel Mode).
- RHR HXS RHR Outlet Temp Less than 86 oF (Refuel Mode).
* The following actions can be performed in any logical order or repeated to support current plant conditions.
 
Step 11 - Continued next page
 
OT-3701-E12_506_RO Rev 0
 
Step 11 - Continued
 
7.6.1 OBSERVE the following limitations when in Shutdown Cooling:
* MAINTAIN cooldown rate less than 100oF in any 1 hour period.
* MAINTAIN cooldown rate less than 100oF in any 1 hour period.
* DO NOT allow any RHR piping which has been inadvertently drained to be refilled with water from the Reactor Vessel.
* DO NOT allow any RHR piping which has been inadvertently drained to be refilled with water from the Reactor Vessel.
Line 277: Line 203:
* MAINTAIN RHR flow in the band 2575-7100 gpm. 1E12-F042A
* MAINTAIN RHR flow in the band 2575-7100 gpm. 1E12-F042A
* MAINTAIN RHR H2O DISCH temperature greater than 65°F. 1E12-R601 Pt 5
* MAINTAIN RHR H2O DISCH temperature greater than 65°F. 1E12-R601 Pt 5
Standard:
The Operator establishes flow of 2575-7100 gpm.
Instructor Cue:
None Notes:
Reactor temperature will increase steadily if cooling is not established.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Standard: The Operator establishes flow of 2575-7100 gpm.
OT-3701-E12_506_RO Rev 0 Step 12 7.6.2 PERFORM the following as needed to maintain desired cooldown rate AND RHR Pump flow 7000-7100 (alternate return path 2575-7100):
 
Instructor Cue: None
 
Notes: Reactor temperature will increase steadily if cooling is not established.
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701-E12_506_RO Rev 0
 
Step 12
 
7.6.2 PERFORM the following as needed to maintain desired cooldown rate AND RHR Pump flow 7000-7100 (alternate return path 2575-7100):
1E12-R603A 1E12-R603B:
1E12-R603A 1E12-R603B:
* THROTTLE RHR HXS OUTLETVALVE. 1E12-F003A
* THROTTLE RHR HXS OUTLET VALVE.
* THROTTLE RHR HXS BYPASS VALVE. 1E12-F048A
1E12-F003A
 
* THROTTLE RHR HXS BYPASS VALVE.
Critical Step: The Operator thrott les open s 1E12-F003A and 1E12-F048A is throttled close to establish a cooldown.
1E12-F048A Critical Step:
 
The Operator throttles opens 1E12-F003A and 1E12-F048A is throttled close to establish a cooldown.
Instructor Cue: Establish a cooldown to restore temperature within band of 135 to 145 degrees.
Instructor Cue:
 
Establish a cooldown to restore temperature within band of 135 to 145 degrees.
Notes: Exceeding 200 degrees Reactor Water temperature would be a failure.
Notes:
Exceeding 200 degrees Reactor Water temperature would be a failure.
200 degrees is a MODE change.
200 degrees is a MODE change.
Operator can establish full cooling and not have a problem with 100 degrees per hour.
Operator can establish full cooling and not have a problem with 100 degrees per hour.
Terminate JPM once satisfied with cooldown rate.
Terminate JPM once satisfied with cooldown rate.
SAT ___ UNSAT ___
SAT ___
 
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Terminating Cue: Shutdown Cooling Flow established through Alternate Return path, a cooldown rate has been established and Reactor Water Temperature is maintained less than 200 degrees.
Terminating Cue: Shutdown Cooling Flow established through Alternate Return path, a cooldown rate has been established and Reactor Water Temperature is maintained less than 200 degrees.
Evaluation Results:
SAT_____
UNSAT_____
End Time


Evaluation Results: SAT_____ UNSAT_____
OT-3701-E12_506_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:
 
End Time
 
OT-3701-E12_506_RO Rev 0
 
JPM CUE SHEET
 
IN IT IA L
* The plant shutdown due to scram yesterday.
* The plant shutdown due to scram yesterday.
CONDITIONS:
* Currently in Mode 4 and the Unit Supervisor is operating in IOI-12 Maintaining Cold Shutdown.
* Currently in Mode 4 and the Unit Supervisor is operating in IOI-12 Maintaining Cold Shutdown.
* RHR B was operating in Shutdown Cooling when the pump tripped 20 minutes ago.
* RHR B was operating in Shutdown Cooling when the pump tripped 20 minutes ago.
Line 331: Line 245:
* Current RPV temperature is 160° F.
* Current RPV temperature is 160° F.
* The RO shifting SDC loops became ill.
* The RO shifting SDC loops became ill.
 
INITIATING CUE:
IN IT IA T ING CUE:
* The Unit Supervisor directs you the Reactor operator to continue shifting Shutdown Cooling loops from B to A using RHR A through the Normal Return Path. Section 4.7
* The Unit Supervisor directs you the Reactor operator to continue shifting Shutdown Cooling loops from B to A using RHR A through the Normal Return Path. Section 4.7
* Shutdown Cooling Startup for RHR A is complete through Step 4.7.18.
* Shutdown Cooling Startup for RHR A is complete through Step 4.7.18.
* Monitor Reactor Temperature per IOI-12.
* Monitor Reactor Temperature per IOI-12.  


Instruction Number:
PERRY NUCLEAR POWER PLANT Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12
SOI-E12


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 1 of 346
71 Page:
1 of 346 RESIDUAL HEAT REMOVAL SYSTEM Effective Date:
5-2-17 Preparer:
Michael Garnett
/ 4-4-17 Date Approver:
Ed Condo
/ 4-6-17 Date Working Copy - Verified Today


RESIDUAL HEAT REMOVAL SYSTEM
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12
Effective Date: 5-2-17
 
Preparer: Michael Garnett / 4-4-17 Date
 
Approver: Ed Condo / 4-6-17 Date
 
Working Copy - Verified Today Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 2 of 346
71 Page:
2 of 346 TABLE OF CONTENTS PAGE 1.0
SCOPE 7
2.0
PRECAUTIONS AND LIMITATIONS 7
3.0
PREREQUISITES 14
4.0
STARTUP 15
4.1
Startup to Standby 15
4.2
LPCI Automatic Initiation 22
4.3
LPCI Manual Pushbutton Initiation 25
4.4
LPCI Manual Startup 26
4.5
Containment Spray Automatic Initiation 28
4.6
Startup for RHR A(B) for Suppression Pool Cooling/Test Mode Operation or Suppression Pool Pumpdown to Radwaste 30
4.7
Shutdown Cooling Startup for RHR A(B) 33
4.8
RHR Loop C Flush/Test Mode Startup 50
4.9
Alternate Keep Fill Startup 53
4.10
Fuel Pool Cooling Assist Startup 55
4.11
Water Leg Pump Startup 59
4.12
Placing RHR Conductivity Alarm In Service 64
5.0
NORMAL OPERATIONS/DATA 65
6.0
SHUTDOWN 66
6.1
LPCI Shutdown to Standby Readiness 66
6.2
Suppression Pool Cooling/Test Mode Shutdown to Standby Readiness for RHR A(B) 68
6.3
Shutdown Cooling Shutdown to Standby Readiness for RHR A(B) 70
6.4
Shutdown from Standby Readiness to Secured Status 77
6.5
RHR Loop C Test Mode Shutdown to Standby Readiness 80
6.6
Fuel Pool Cooling Assist Shutdown 81
6.7
Alternate Keep Fill Shutdown 84
6.8
Removing RHR Conductivity Alarm From Service 87
7.0
SYSTEM OPERATIONS 88
7.1
LPCI Operations 88
7.2
Suppression Pool Cooling/Test Mode Operations for RHR A(B) 91
7.3
Suppression Pool Pumpdown to Radwaste 96
7.4
Raising Suppression Pool Level Using Condensate Transfer and Storage Water with RHR in Suppression Pool Cooling 99
7.5
Shifting Shutdown Cooling From Loop A(B) to Loop B(A) 100
7.6
RHR Shutdown Cooling Operations for RHR A(B) 101
7.7
Fill and Vent of RHR A(B,C) 117
7.8
Fill and Vent of RHR Prerequisites 120


TABLE OF CONTENTS PAGE
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 1.0
1.0SCOPE 7
2.0 PRECAUTIONS AND LIMITATIONS 7
3.0PREREQUISITES 14
4.0STARTUP 15
4.1 Startup to Standby 15
4.2 LPCI Automatic Initiation 22
4.3 LPCI Manual Pushbutton Initiation 25
4.4 LPCI Manual Startup 26
4.5 Containment Spray Automatic Initiation 28
4.6 Startup for RHR A(B) for Suppression Pool Cooling/Test Mode Operation or Suppression Pool Pumpdown to Radwaste 30
4.7 Shutdown Cooling Startup for RHR A(B) 33
4.8 RHR Loop C Flush/Test Mode Startup 50
4.9 Alternate Keep Fill Startup 53
4.10 Fuel Pool Cooling Assist Startup 55
4.11 Water Leg Pump Startup 59
4.12 Placing RHR Conductivity Alarm In Service 64
5.0 NORMAL OPERATIONS/DATA 65
6.0SHUTDOWN 66
6.1 LPCI Shutdown to Standby Readiness 66
6.2 Suppression Pool Cooling/Test Mode Shutdown to Standby Readiness for RHR A(B) 68
6.3 Shutdown Cooling Shutdown to Standby Readiness for RHR A(B) 70
6.4 Shutdown from Standby Readiness to Secured Status 77
6.5 RHR Loop C Test Mode Shutdown to Standby Readiness 80
6.6 Fuel Pool Cooling Assist Shutdown 81
6.7 Alternate Keep Fill Shutdown 84
6.8 Removing RHR Conductivity Alarm From Service 87
7.0 SYSTEM OPERATIONS 88
7.1 LPCI Operations 88
7.2 Suppression Pool Cooling/Test Mode Operations for RHR A(B) 91
7.3 Suppression Pool Pumpdown to Radwaste 96
7.4 Raising Suppression Pool Level Using Condensate Transfer and Storage Water with RHR in Suppression Pool Cooling 99
7.5 Shifting Shutdown Cooling From Loop A(B) to Loop B(A) 100
7.6 RHR Shutdown Cooling Operations for RHR A(B) 101
7.7 Fill and Vent of RHR A(B,C) 117
7.8 Fill and Vent of RHR Prerequisites 120
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 1.0


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 7 of 346
71 Page:
 
7 of 346 1.0 SCOPE This instruction provides the detailed operating instructions for the Residual Heat Removal (RHR) System.
1.0 SCOPE
2.0 PRECAUTIONS AND LIMITATIONS 2.1 Portions of this system are covered by Technical Specifications; these include the equipment and controls necessary to support RHR system operation in the following modes:
 
x Low Pressure Coolant Injection (LPCI) x Containment Spray x
This instruction provides the detailed operating instructions for the Residual Heat Removal (RHR) System.
Suppression Pool Cooling x
 
Shutdown Cooling Also, this system has controls which are related to T.S. 3.3.3.2, Remote Shutdown System.
2.0 PRECAUTIONS AND LIMITATIONS
 
2.1 Portions of this system are covered by Technical Specifications; these include the equipment and controls necessary to support RHR system operation in the following modes:
 
x Low Pressure Coolant Injection (LPCI)
 
x Containment Spray
 
x Suppression Pool Cooling
 
x Shutdown Cooling
 
Also, this system has controls which are related to T.S. 3.3.3.2, Remote Shutdown System.
 
2.2 Observe the following limitations during the operation of the RHR pumps:
2.2 Observe the following limitations during the operation of the RHR pumps:
x Do NOT operate the RHR pump against a shutoff head for greater than 8 seconds.
x Do NOT operate the RHR pump against a shutoff head for greater than 8 seconds.
x All pump trips shall be investigated prior to restarting the pump, except during emergency conditions in which operation of the pump is required to provide protection of the plant or public.
x All pump trips shall be investigated prior to restarting the pump, except during emergency conditions in which operation of the pump is required to provide protection of the plant or public.
x Observe the following pump restart limitations:
x Observe the following pump restart limitations:
x The motor may be started twice successively from ambient temperature or once from rated motor temperature.
x The motor may be started twice successively from ambient temperature or once from rated motor temperature.
x Repetitive starts are governed by motor operating temperature. In absence of thermal devices to determine machine temperature, the following can be used as a guide: the motor can be assumed to have returned to rated temperature after 80 minutes idle time or 30 minutes running time, after which time another start is permissible.


x Repetitive starts are governed by motor operating temperature. In absence of thermal devices to determine machine temperature, the following can be used as a guide: the motor can be assumed to have returned to rated temperature after 80 minutes idle time or 30 minutes running time, after which time another start is permissible.
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 2.0
PERRY NUCLEAR POWER PLANT SOI-E12 Section 2.0


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 8 of 346
71 Page:
 
8 of 346 x
x Limit RHR pump flow as follows:
Limit RHR pump flow as follows:
 
x 8520 gpm with flow bypassing the RHR heat exchangers. This limit is based on RHR Pump runout flow.
x 8520 gpm with flow bypassing the RHR heat exchangers. This limit is based on RHR Pump runout flow.
x 7800 gpm with flow through the RHR heat exchangers. This limit is based on RHR heat exchanger maximum flow.
x 7800 gpm with flow through the RHR heat exchangers. This limit is based on RHR heat exchanger maximum flow.
2.3 Any time it is suspected that the RHR Loops are NOT filled or the system has been breached, fill and vent the RHR Loop as applicable.
2.3 Any time it is suspected that the RHR Loops are NOT filled or the system has been breached, fill and vent the RHR Loop as applicable.
2.4 The reactor shall be placed and maintained in a Cold Shutdown condition whenever a loop of RHR is used in the Fuel Pool Cooling Assist mode.
2.4 The reactor shall be placed and maintained in a Cold Shutdown condition whenever a loop of RHR is used in the Fuel Pool Cooling Assist mode.
2.5 The disconnect, MCC EF1B07-H, for SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, shall be closed only to perform Shutdown Cooling or related shutdown operations. It shall be open during all other conditions to satisfy 10CFR50 Appendix R considerations.
2.5 The disconnect, MCC EF1B07-H, for SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, shall be closed only to perform Shutdown Cooling or related shutdown operations. It shall be open during all other conditions to satisfy 10CFR50 Appendix R considerations.
2.6 Operation of the LPCI mode of RHR with injection flow to the vessel shall only be done in an accident condition, a plant emergency condition, or an approved test condition of short duration. ONI-E12-2, Loss of Decay Heat Removal, and IOI-11, Shutdown From Outside Control Room, direct the use of the LPCI injection lines as Alternate Shutdown Cooling flow paths. Use of this flow path is still subject to reportability (as described in NOP-OP-1015, Event Notifications) when used for Alternate Shutdown Cooling.
2.6 Operation of the LPCI mode of RHR with injection flow to the vessel shall only be done in an accident condition, a plant emergency condition, or an approved test condition of short duration. ONI-E12-2, Loss of Decay Heat Removal, and IOI-11, Shutdown From Outside Control Room, direct the use of the LPCI injection lines as Alternate Shutdown Cooling flow paths. Use of this flow path is still subject to reportability (as described in NOP-OP-1015, Event Notifications) when used for Alternate Shutdown Cooling.
2.7 Water Hammer:
2.7 Water Hammer:
Do NOT start a pump in the effected loop prior to ensuring the loop is filled. This could result in water hammer in a loop that is severe enough to cause component damage or pressure boundary failure. Potential causes of voiding include:
Do NOT start a pump in the effected loop prior to ensuring the loop is filled. This could result in water hammer in a loop that is severe enough to cause component damage or pressure boundary failure. Potential causes of voiding include:
x A loss of pumping power with RHR A(B) TEST VALVE TO SUPR POOL, 1E12-F024A(B), open.
x A loss of pumping power with RHR A(B) TEST VALVE TO SUPR POOL, 1E12-F024A(B), open.
x A Division 1(2) RHR Isolation during Shutdown Cooling Operation may allow steam voids to form.
x A Division 1(2) RHR Isolation during Shutdown Cooling Operation may allow steam voids to form.
x Opening RHR A(B) SUPR POOL SUCTION VALVE, 1E12-F004A(B), when the RHR Pump A(B) suction piping is filled with water that is at greater than 200qF.


x Opening RHR A(B) SUPR POOL SUCTION VALVE, 1E12-F004A(B), when the RHR Pump A(B) suction piping is filled with water that is at greater than 200qF.
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 2.0
PERRY NUCLEAR POWER PLANT SOI-E12 Section 2.0


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 9 of 346
71 Page:
 
9 of 346 x
x Deviation from written instructions when operating the system.
Deviation from written instructions when operating the system.
 
x Maintenance or testing on portions of the system that require realigning valves.
x Maintenance or testing on portions of the system that require realigning valves.
2.8 If it becomes necessary to close RHR A(B) TO CNTMT SHUTOFF, 1E12-F027A(B), then to prevent back leakage or thermal changes from over pressurizing the isolated piping refer to RHR A(B) To Cntmt Shutoff 1E12-F027A(B) Operation and perform the actions.
2.8 If it becomes necessary to close RHR A(B) TO CNTMT SHUTOFF, 1E12-F027A(B), then to prevent back leakage or thermal changes from over pressurizing the isolated piping refer to RHR A(B) To Cntmt Shutoff 1E12-F027A(B) Operation and perform the actions.
2.9 If the RHR PUMP A(B,C), MIN FLOW VALVE, 1E12-F064A(B,C), is NOT capable of opening to provide minimum flow (except as allowed in 3.5.2 for Shutdown Cooling),
2.9 If the RHR PUMP A(B,C), MIN FLOW VALVE, 1E12-F064A(B,C), is NOT capable of opening to provide minimum flow (except as allowed in 3.5.2 for Shutdown Cooling),
Then declare RHR Pump A(B,C) INOPERABLE and take one of the following actions:
Then declare RHR Pump A(B,C) INOPERABLE and take one of the following actions:
x Ensure RHR Pump A(B,C), 1E12-C002A(B,C) breaker open with its control power fuses removed.
x Ensure RHR Pump A(B,C), 1E12-C002A(B,C) breaker open with its control power fuses removed.
x Provide increased monitoring whenever RHR Pump A(B,C) is in operation to ensure RHR A(B,C) does NOT operate at less than 1650 gpm for greater than 8 seconds.
x Provide increased monitoring whenever RHR Pump A(B,C) is in operation to ensure RHR A(B,C) does NOT operate at less than 1650 gpm for greater than 8 seconds.
x If RHR A(B) Pump is operated at less than 1650 gpm for greater than 8 seconds, an Engineering analysis of RHR Pump A(B,C) shall be performed prior to declaring RHR Pump A(B,C) OPERABLE.
x If RHR A(B) Pump is operated at less than 1650 gpm for greater than 8 seconds, an Engineering analysis of RHR Pump A(B,C) shall be performed prior to declaring RHR Pump A(B,C) OPERABLE.
2.10 Operation of RHR Loop A in the Test Mode or Suppression Pool Cooling when SPCU is in operation through the Suppression Pool Return Line Bypassing RHR A could result in loss of flow to the SPCU pump.
2.10 Operation of RHR Loop A in the Test Mode or Suppression Pool Cooling when SPCU is in operation through the Suppression Pool Return Line Bypassing RHR A could result in loss of flow to the SPCU pump.
2.11 If LPCS & RHR A WATER LEG PUMP, 1E21-C002, or RHR B & C WATER LEG PUMP, 1E12-C003, are shutdown, Then the respective Feedwater Leakage Control System (N27A or N27B), will become inoperable.
2.11 If LPCS & RHR A WATER LEG PUMP, 1E21-C002, or RHR B & C WATER LEG PUMP, 1E12-C003, are shutdown, Then the respective Feedwater Leakage Control System (N27A or N27B), will become inoperable.
2.12 If RHR A, B, or C are placed on alternate keep fill or the respective Waterleg pump is shutdown the affected RHR loop will be inoperable.
2.12 If RHR A, B, or C are placed on alternate keep fill or the respective Waterleg pump is shutdown the affected RHR loop will be inoperable.
2.13 To provide a suction to the LPCS & RHR A WATER LEG PUMP, 1E21-C002, the LPCS SUPR POOL SUCTION VALVE, 1E21-F001, must be open.


2.13 To provide a suction to the LPCS & RHR A WATER LEG PUMP, 1E21-C002, the LPCS SUPR POOL SUCTION VALVE, 1E21-F001, must be open.
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 2.0
PERRY NUCLEAR POWER PLANT SOI-E12 Section 2.0


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 10 of 346
71 Page:
 
10 of 346 2.14 To provide suction to the RHR B & C WATER LEG PUMP, 1E12-C003, the RHR C SUPR POOL SUCTION VALVE, 1E12-F105, must be open.
2.14 To provide suction to the RHR B & C WATER LEG PUMP, 1E12-C003, the RHR C SUPR POOL SUCTION VALVE, 1E12-F105, must be open.
 
2.15 Prior to placing RHR in Shutdown Cooling mode, RPV pressure shall be less than 135 psig.
2.15 Prior to placing RHR in Shutdown Cooling mode, RPV pressure shall be less than 135 psig.
2.16 RP should be notified prior to conducting Suppression Pool evolutions, so the survey frequency may be increased as necessary.
2.16 RP should be notified prior to conducting Suppression Pool evolutions, so the survey frequency may be increased as necessary.
2.17 Opening of RHR PUMP A(B) MIN FLOW VALVE, 1E12-F064A(B) or RHR A(B)
2.17 Opening of RHR PUMP A(B) MIN FLOW VALVE, 1E12-F064A(B) or RHR A(B)
UPPER POOL COOLING ISOL, 1E12-F037A(B), while in shutdown cooling could result in the draining of the vessel. Do NOT allow any RHR piping, which has been inadvertently drained down, to refill with Reactor Vessel Water.
UPPER POOL COOLING ISOL, 1E12-F037A(B), while in shutdown cooling could result in the draining of the vessel. Do NOT allow any RHR piping, which has been inadvertently drained down, to refill with Reactor Vessel Water.
2.18 Valve alignments and system manipulations on the RHR system when SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, and SHUTDOWN COOLING INBD SUCT ISOL, 1E12-F009, are open shall be supervised by the Shift Manager or Unit Supervisor when required by OAI-0201 Section 4.4.2.
2.18 Valve alignments and system manipulations on the RHR system when SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, and SHUTDOWN COOLING INBD SUCT ISOL, 1E12-F009, are open shall be supervised by the Shift Manager or Unit Supervisor when required by OAI-0201 Section 4.4.2.
2.19 LPCI operability requires flow both through the RHR Heat Exchangers and the RHR Heat Exchanger Bypass line; therefore, anytime RHR A(B) HXS INLET VALVE, 1E12-F047A(B), is NOT open or either RHR A(B) HXS OUTLET VALVE, 1E12-F003A(B), or RHR A(B) HXS BYPASS VALVE, 1E12-F048A(B), is NOT capable of automatically opening LPCI shall be declared INOPERABLE.
2.19 LPCI operability requires flow both through the RHR Heat Exchangers and the RHR Heat Exchanger Bypass line; therefore, anytime RHR A(B) HXS INLET VALVE, 1E12-F047A(B), is NOT open or either RHR A(B) HXS OUTLET VALVE, 1E12-F003A(B), or RHR A(B) HXS BYPASS VALVE, 1E12-F048A(B), is NOT capable of automatically opening LPCI shall be declared INOPERABLE.
2.20 When 1E12-F024A(B) is open, system flow through 1E12-F024A(B) shall be maintained greater than 6000 gpm. 6000 gpm is the minimum flow allowable to prevent voiding at the high point in the RHR system piping. The normal Suppression Pool Cooling/Test Mode flow is 7100-7300 gpm.
2.20 When 1E12-F024A(B) is open, system flow through 1E12-F024A(B) shall be maintained greater than 6000 gpm. 6000 gpm is the minimum flow allowable to prevent voiding at the high point in the RHR system piping. The normal Suppression Pool Cooling/Test Mode flow is 7100-7300 gpm.
2.21 The pump rotation during fill and vent operations shall be minimized.


2.21 The pump rotation during fill and vent operations shall be minimized.
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 2.0
PERRY NUCLEAR POWER PLANT SOI-E12 Section 2.0


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 11 of 346
71 Page:
 
11 of 346 2.22 Operating the RHR System in a Secondary Mode of operation, except Shutdown Cooling, will *INOP the LPCI mode of RHR due to the system being unable to realign within the Technical Specification response time requirements.
2.22 Operating the RHR System in a Secondary Mode of operation, except Shutdown Cooling, will *INOP the LPCI mode of RHR due to the system being unable to realign within the Technical Specification response time requirements.
 
With temperature is less than 200qF the LPCI does NOT need to be declared inoperable when the RHR loop is in Shutdown Cooling as long as it can be realigned to the LPCI mode (either remotely or locally), is NOT otherwise inoperable.
With temperature is less than 200qF the LPCI does NOT need to be declared inoperable when the RHR loop is in Shutdown Cooling as long as it can be realigned to the LPCI mode (either remotely or locally), is NOT otherwise inoperable.
When placing a loop of RHR in Shutdown Cooling greater than 200qF the RHR loop shall be considered inoperable for ALL Modes except Shutdown Cooling Mode of operation due to the possiblilty of system voiding during a Shutdown Cooling Isolation.
When placing a loop of RHR in Shutdown Cooling greater than 200qF the RHR loop shall be considered inoperable for ALL Modes except Shutdown Cooling Mode of operation due to the possiblilty of system voiding during a Shutdown Cooling Isolation.
2.23 When venting or draining the ESW side of the RHR Heat Exchangers the expelled water should NOT be discharged to Radwaste. This lake water will shorten the life of the Radwaste demineralizers and biologically foul the resin which will cause gas buildup in Radwaste shipping containers. The preferred actions are to collect this water in a container which RP and CHEM can sample for release outside the RRA or have RP and CHEM approve running the vent/drain hose to a non-radiological drain. In the event lake water must be drained to a radiological drain, Radwaste shall be informed of amount of lake water to be drained and the drain to receive it.
2.23 When venting or draining the ESW side of the RHR Heat Exchangers the expelled water should NOT be discharged to Radwaste. This lake water will shorten the life of the Radwaste demineralizers and biologically foul the resin which will cause gas buildup in Radwaste shipping containers. The preferred actions are to collect this water in a container which RP and CHEM can sample for release outside the RRA or have RP and CHEM approve running the vent/drain hose to a non-radiological drain. In the event lake water must be drained to a radiological drain, Radwaste shall be informed of amount of lake water to be drained and the drain to receive it.
2.24 If the RHR HX ESW inlet or outlet valves, 1P45-F014A(B) or 1P45-F068A(B), are NOT full open the associated RHR loop shall be declared inoperable. This is because the valves may NOT reposition properly during accident conditions.
2.24 If the RHR HX ESW inlet or outlet valves, 1P45-F014A(B) or 1P45-F068A(B), are NOT full open the associated RHR loop shall be declared inoperable. This is because the valves may NOT reposition properly during accident conditions.
2.25 The RHR pumps should NOT be operated in minimum flow for excessive periods of time. If an RHR pump is operated in minimum flow for greater than 1 hour, a Condition Report should be generated for Engineering to evaluate the effects on the pump.
2.25 The RHR pumps should NOT be operated in minimum flow for excessive periods of time. If an RHR pump is operated in minimum flow for greater than 1 hour, a Condition Report should be generated for Engineering to evaluate the effects on the pump.
2.26 Erosion may occur on the RHR Pump minimum flow lines. Consideration should be given to placing RHR Pumps in the suppression pool cooling/test mode during extended operation rather than leaving them in minimum flow.


2.26 Erosion may occur on the RHR Pump minimum flow lines. Consideration should be given to placing RHR Pumps in the suppression pool cooling/test mode during extended operation rather than leaving them in minimum flow.
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 2.0
PERRY NUCLEAR POWER PLANT SOI-E12 Section 2.0


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 12 of 346
71 Page:
 
12 of 346 2.27 Leakage past the following valves is considered Leakage Outside Containment.
2.27 Leakage past the following valves is considered Leakage Outside Containment.
To control leakage past these valves, they shall be torqued to the following specified values in Mode 1, 2, or 3:
To control leakage past these valves, they shall be torqued to the following specified values in Mode 1, 2, or 3:
x 1E12F0071A - 140 FT/LBS.
x 1E12F0071A - 140 FT/LBS.
 
x 1E12F0072A - 140 FT/LBS x
x 1E12F0072A - 140 FT/LBS
1E12F0511A - 123 FT/LBS.
 
x 1E12F0511A - 123 FT/LBS.
 
x 1E12F0071B - 96 FT/LBS.
x 1E12F0071B - 96 FT/LBS.
 
x 1E12F0072B - 96 FT/LBS x
x 1E12F0072B - 96 FT/LBS
1E12F0511B - 123 FT/LBS.
 
x 1E12F0511B - 123 FT/LBS.
 
x 1E12F0071C - 96 FT/LBS.
x 1E12F0071C - 96 FT/LBS.
x 1E12F0072C - 96 FT/LBS.
x 1E12F0072C - 96 FT/LBS.
1E12F0511B is not normally closed; however, if it should need to be closed due to leakage past 1E12F0071B or 1E12F0072B, it will need to be torqued to 123 FT/LBS.
1E12F0511B is not normally closed; however, if it should need to be closed due to leakage past 1E12F0071B or 1E12F0072B, it will need to be torqued to 123 FT/LBS.
2.28 If a Loop of RHR has been drained that Loop of RHR shall be run in Suppression Pool Cooling/Test Mode (RHR A,B), RHR Loop C Flush/Test Mode (RHR C) to sweep air pockets from portions of the system that cannot be vented prior to the Loop being declared operable.


2.28 If a Loop of RHR has been drained that Loop of RHR shall be run in Suppression Pool Cooling/Test Mode (RHR A,B), RHR Loop C Flush/Test Mode (RHR C) to sweep air pockets from portions of the system that cannot be vented prior to the Loop being declared operable.
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 2.0
PERRY NUCLEAR POWER PLANT SOI-E12 Section 2.0


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 13 of 346
71 Page:
 
13 of 346 2.29 The following table provides torque specifications when manually operating selected valves:
2.29 The following table provides torque specifications when manually operating selected valves:
Valve Hand Wheel Torque 1E12-F010 285 ft-lbs 1E12-F039A(B,C) 206 ft-lbs 1E12-F066A 93 ft-lbs 1E12-F085A 400 inch-lbs 1E12-F502A,C 120 ft-lbs 1E12-F552A 106 ft-lbs 1E12-F599A 30 ft-lbs +25%, -0%
 
1E12-F621 118 ft-lbs 2.30 Observe the following RHR Pump Motor Oil level limitations as can be determined when the pump motors are de-energized:
Valve Hand Wheel Torque
 
1E12-F010 285 ft-lbs
 
1E12-F039A(B,C) 206 ft-lbs
 
1E12-F066A 93 ft-lbs
 
1E12-F085A 400 inch-lbs
 
1E12-F502A,C 120 ft-lbs
 
1E12-F552A 106 ft-lbs
 
1E12-F599A 30 ft-lbs +25%, -0%
 
1E12-F621 118 ft-lbs
 
2.30 Observe the following RHR Pump Motor Oil level limitations as can be determined when the pump motors are de-energized:
 
x RHR Pump A (B, C), 1E12-C002A (B, C) oil levels should be maintained within 7/16 above and below the reference line of the oil reservoir sight glass.
x RHR Pump A (B, C), 1E12-C002A (B, C) oil levels should be maintained within 7/16 above and below the reference line of the oil reservoir sight glass.
x RHR B & C WATER LEG PUMP, 1E12-C003 constant level oiler should be maintained per the specified inches below shaft centerline stated on the Oil Level Plate.
x RHR B & C WATER LEG PUMP, 1E12-C003 constant level oiler should be maintained per the specified inches below shaft centerline stated on the Oil Level Plate.
2.31 RHR A can NOT be operated in Shutdown Cooling when ADHR system is aligned for decay heat removal.
2.31 RHR A can NOT be operated in Shutdown Cooling when ADHR system is aligned for decay heat removal.
2.32 OAI-0502 requires a minimum vent duration of 2 minutes after a solid stream of fluid has been achieved when venting ECCS systems. Steps for venting state for at least 2 minutes. Time of the vent starts when an air free stream is achieved.
2.32 OAI-0502 requires a minimum vent duration of 2 minutes after a solid stream of fluid has been achieved when venting ECCS systems. Steps for venting state for at least 2 minutes. Time of the vent starts when an air free stream is achieved.
END OF SECTION


END OF SECTION
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 7.5
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.5


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 100 of 346
71 Page:
 
100 of 346 7.5 Shifting Shutdown Cooling From Loop A(B) to Loop B(A) 7.5.1 REFER TO Shutdown Cooling Startup and PLACE the Oncoming loop in service.
7.5 Shifting Shutdown Cooling From Loop A(B) to Loop B(A)
Loop B
 
Loop A
7.5.1 REFER TO Shutdown Cooling Startup LoopLoop and PLACE the Oncoming loop in B A service.
7.5.2 REFER TO Shutdown Cooling Shutdown to Standby Readiness and SHUTDOWN the Offgoing RHR loop.
 
Loop A
7.5.2 REFER TO Shutdown Cooling Loop Loop Shutdown to Standby Readiness and A B SHUTDOWN the Offgoing RHR loop.
Loop B
 
END OF SECTION
END OF SECTION


Instruction Number:
PERRY NUCLEAR POWER PLANT Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7
SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 33 of 346
71 Page:
 
33 of 346 4.7 Shutdown Cooling Startup for RHR A(B)
4.7 Shutdown Cooling Startup for RHR A(B)
NOTES x
 
Both Loops of RHR may be placed in Shutdown Cooling by performing all the required Steps for one loop and then performing the required Steps for the other loop.
NOTES
 
x Both Loops of RHR may be placed in Shutdown Cooling by performing all the required Steps for one loop and then performing the required Steps for the other loop.
 
x Local Field Actions maybe required in the following places:
x Local Field Actions maybe required in the following places:
x CC 620 Switchgear rooms to operate disconnect stitches.
x CC 620 Switchgear rooms to operate disconnect stitches.
x AX 620RHR B Penetration Room to operate flush valves.
x AX 620RHR B Penetration Room to operate flush valves.
x AX 574 to operate RHR B to Radwaste Shutoff Valve, 1E12-F504 (RHR B only).
x AX 574 to operate RHR B to Radwaste Shutoff Valve, 1E12-F504 (RHR B only).
NA 4.7.1 A Loss of Shutdown Cooling has NOT occurred NOT Operating in EOPs The Oncoming Shutdown Cooling Loop flowpath has NOT been maintained filled and vented the last 10 days The Oncoming RHR Loop has NOT operated in Shutdown Cooling within the last 10 days Loop A
Loop B
A waiver for the requirement to perform RHR Loop flushing from Operations Manager has NOT been granted THEN PERFORM the following:
4.7.1.a CONFIRM the Oncoming RHR loop RHR SHUTDOWN CLG SUCT valve is closed.
1E12-F006A 1E12-F006B


NA 4.7.1 A Loss of Shutdown Cooling has NOT occurred
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
NOT Operating in EOPs
 
The Oncoming The Oncoming Loop Loop Shutdown Cooling RHR Loop has A B Loop flowpath has NOT operated in NOT been Shutdown Cooling maintained filled within the last and vented the last 10 days 10 days
 
A waiver for the requirement to perform RHR Loop flushing from Operations Manager has NOT been granted
 
THEN PERFORM the following:
 
4.7.1.a CONFIRM the Oncoming RHR loop 1E12-1E12-RHR SHUTDOWN CLG SUCT valve is F006A F006B closed.
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 34 of 346
71 Page:
 
34 of 346 NA 4.7.1.b Information Tag is on the RHR Conductivity Alarm window(s)
NA 4.7.1.b Information Tag is Caution Tag is on 1H13-1H13-on the RHR the RHR P601-P601-Conductivity Alarm Conductivity Alarm 20-G5 17-G5 window(s) window(s)
Caution Tag is on the RHR Conductivity Alarm window(s) 1H13-P601-20-G5 1H13-P601-17-G5 THEN REFER TO Placing RHR Conductivity Alarm In Service and VERIFY the actions are complete.
 
NOTE Both loops of RHR should be flushed when placing SDC into service during non-refueling periods. Only one loop needs to be flushed prior to establishing Shutdown Cooling. The second loop of RHR should be flushed when Mode 4 is reached to make it available for use in the SDC mode. Delaying the flush of the second RHR loop minimizes inoperability time and the time to establish Shutdown Cooling.
THEN REFER TO Placing RHR Conductivity Alarm In Service and VERIFY the actions are complete.
 
NOTE
 
Both loops of RHR should be flushed when placing SDC into service during non-refueling periods. Only one loop needs to be flushed prior to establishing Shutdown Cooling. The second loop of RHR should be flushed when Mode 4 is reached to make it available for use in the SDC mode. Delaying the flush of the second RHR loop minimizes inoperability time and the time to establish Shutdown Cooling.
 
4.7.1.c REFER TO Flush of RHR Loop A(B)
4.7.1.c REFER TO Flush of RHR Loop A(B)
When in Standby Readiness Mode and VERIFY the flush the oncoming loop is complete.
When in Standby Readiness Mode and VERIFY the flush the oncoming loop is complete.
NA 4.7.1.d IF the Suppression Pool water does NOT meet the limits for transfer quality per Chemistry, THEN REFER TO Flush of RHR A(B)
NA 4.7.1.d IF the Suppression Pool water does NOT meet the limits for transfer quality per Chemistry, THEN REFER TO Flush of RHR A(B)
With CST Water and VERIFY the actions complete.
With CST Water and VERIFY the actions complete.
4.7.1.e REFER TO SOI-P45/49 and VERIFY the associated Emergency Service Water System Loop in operation.
Loop A
Loop B
4.7.1.f REFER TO SOI-P42 and VERIFY the associated Emergency Closed Cooling System Loop in operation.
Loop A
Loop B


4.7.1.e REFER TO SOI-P45/49 and VERIFY Loop Loop the associated Emergency Service A B Water System Loop in operation.
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
4.7.1.f REFER TO SOI-P42 and VERIFY the Loop Loop associated Emergency Closed Cooling A B System Loop in operation.
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 35 of 346
71 Page:
 
35 of 346 NOTES x With temperature is less than 200qF the LPCI does NOT need to be declared inoperable for the LPCI Mode when the RHR loop is in Shutdown Cooling as long as it can be realigned to the LPCI mode (either remotely or locally), is NOT otherwise inoperable.
NOTES
 
x With temperature is less than 200qF the LPCI does NOT need to be declared inoperable for the LPCI Mode when the RHR loop is in Shutdown Cooling as long as it can be realigned to the LPCI mode (either remotely or locally), is NOT otherwise inoperable.
 
x When placing a loop of RHR in Shutdown Cooling greater than 200qF the RHR loop shall be considered inoperable for ALL Modes except Shutdown Cooling Mode of operation due to the possiblilty of system voiding during a Shutdown Cooling Isolation.
x When placing a loop of RHR in Shutdown Cooling greater than 200qF the RHR loop shall be considered inoperable for ALL Modes except Shutdown Cooling Mode of operation due to the possiblilty of system voiding during a Shutdown Cooling Isolation.
NA 4.7.2 IF operating in MODE 3, THEN NOTIFY the Unit Supervisior that RHR loop being placed into Shutdown Cooling will be inoperable for ALL Modes except Shutdown Cooling Mode, UNTIL Mode 4 is entered.
NA 4.7.2 IF operating in MODE 3, THEN NOTIFY the Unit Supervisior that RHR loop being placed into Shutdown Cooling will be inoperable for ALL Modes except Shutdown Cooling Mode, UNTIL Mode 4 is entered.
4.7.3 NOTIFY Radiation Protection of the Change to Shutdown Cooling Operation.
4.7.3 NOTIFY Radiation Protection of the Change to Shutdown Cooling Operation.
NA 4.7.4 IF Placing RHR A in service, THEN CONFIRM the ADHR system is NOT in service removing Decay heat.


NA 4.7.4 IF Placing RHR A in service, THEN CONFIRM the ADHR system is NOT in service removing Decay heat.
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 4.7
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 36 of 346
71 Page:
 
36 of 346 NA 4.7.5 Performing Section 7.5, Shifting Shutdown Cooling From Loop A(B) to Loop B(A)
NA 4.7.5 Performing Section 7.5, Shifting Shutdown Cooling From Loop A(B) to Loop B(A)
 
Starting RHR A in Shutdown Cooling Loop A
Starting RHR A in Shutdown Cooling Loop A
 
RHR B pump is NOT running 1E12-C002B THEN VERIFY RHR B SHUTDOWN CLG SUCT valve control switch in CLOSED.
RHR B pump is NOT running 1E12-C002B
1E12-F006B NA 4.7.6 Performing Section 7.5, Shifting Shutdown Cooling From Loop A(B) to Loop B(A)
 
THEN VERIFY RHR B SHUTDOWN 1E12-CLG SUCT valve control switch in F006B CLOSED.
 
NA 4.7.6 Performing Section 7.5, Shifting Shutdown Cooling From Loop A(B) to Loop B(A)
 
Starting RHR B in Shutdown Cooling Loop B
Starting RHR B in Shutdown Cooling Loop B
RHR A pump is NOT running 1E12-C002A THEN VERIFY RHR A SHUTDOWN CLG SUCT valve control switch in CLOSED.
1E12-F006A 4.7.7 VERIFY RHR B HXS SECOND VENT TO SUPR POOL is CLOSED.
1E12-F073B 4.7.8 VERIFY the following:
x RHR SUPR POOL SUCTION VALV keylock switch in CLOSED.
1E12-F004A 1E12-F004B x
RHR HXS BYPASS VALVE is OPEN.
1E12-F048A 1E12-F048B


RHR A pump is NOT running1E12-C002A
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
THEN VERIFY RHR A SHUTDOWN 1E12-CLG SUCT valve control switch in F006A CLOSED.
 
4.7.7 VERIFY RHR B HXS SECOND VENT 1E12-TO SUPR POOL is CLOSED. F073B
 
4.7.8 VERIFY the following:
 
x RHR SUPR POOL SUCTION 1E12-1E12-VALV keylock switch in CLOSED. F004A F004B
 
x RHR HXS BYPASS VALVE is 1E12-1E12-OPEN. F048A F048B Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 37 of 346
71 Page:
 
37 of 346 x
x RHR HXS OUTLET VALVE is 1E12-1E12-OPEN. F003A F003B
RHR HXS OUTLET VALVE is OPEN.
 
1E12-F003A 1E12-F003B NOTE SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, disconnect MCC EF1B07-H can be verified closed by power being present to the valve position indication.
NOTE
4.7.9 VERIFY the SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, valve disconnect is CLOSED.
 
EF1 B07-H 4.7.10 REFER TO SOI-P45/49 and VERIFY Emergency Service Water System Loop in operation.
SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, disconnect MCC EF1B07-H can be verified closed by power being present to the valve position indication.
A B
 
4.7.11 REFER TO SOI-P42 and VERIFY Emergency Closed Cooling System Loop in operation.
4.7.9 VERIFY the SHUTDOWN COOLING EF1 OTBD SUCT ISOL, 1E12-F008, valve B07-H disconnect is CLOSED.
A B
 
NA 4.7.12 SHUTDOWN COOLING OTBD SUCT ISOL is closed SHUTDOWN COOLING INBD SUCT ISOL is closed 1E12-F008 1E12-F009 THEN PERFORM the following:
4.7.10 REFER TO SOI-P45/49 and VERIFY A B Emergency Service Water System Loop in operation.
 
4.7.11 REFER TO SOI-P42 and VERIFY A B Emergency Closed Cooling System Loop in operation.
 
NA 4.7.12 SHUTDOWN SHUTDOWN 1E12-1E12-COOLING OTBD COOLING INBD F008 F009 SUCT ISOL is SUCT ISOL is closed closed
 
THEN PERFORM the following:
 
4.7.12.a WHEN Reactor Vessel pressure is less than 135 psig, THEN VERIFY the following are reset:
4.7.12.a WHEN Reactor Vessel pressure is less than 135 psig, THEN VERIFY the following are reset:
x Trip unit 1B21-N679D (1H13-P694).
x Trip unit 1B21-N679D (1H13-P694).
x Trip unit 1B21-N679A (1H13-P691).
x Trip unit 1B21-N679A (1H13-P691).
x Trip unit 1B21-N679C (1H13-P693).
x Trip unit 1B21-N679C (1H13-P693).
x Trip unit 1B21-N679B (1H13-P692).


x Trip unit 1B21-N679B (1H13-P692).
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 4.7
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 38 of 346
71 Page:
 
38 of 346 4.7.12.b MOMENTARILY DEPRESS BOTH of the following to reset the NS4 logic:
N/A 4.7.12.b MOMENTARILY DEPRESS BOTH of the following to reset the NS4 logic:


x MSL & NS4 OTBD ISOL SEAL IN1B21H RESET. -S32
x MSL & NS4 OTBD ISOL SEAL IN RESET.
1B21H
-S32


x MSL & NS4 INBD ISOL SEAL IN1B21H RESET. -S33
x MSL & NS4 INBD ISOL SEAL IN RESET.
1B21H
-S33


4.7.13 HOLD the Oncoming RHR HXS1E12-1E12-OUTLET VALVE in CLOSE for F003A F003B 54-56 seconds.
4.7.13 HOLD the Oncoming RHR HXS OUTLET VALVE in CLOSE for 54-56 seconds.
1E12-F003A 1E12-F003B NA 4.7.14 IF the Oncoming RHR PUMP MIN FLOW VALVE is energized, THEN PERFORM the following:
1E12-F064A 1E12-F064B


NA 4.7.14 IF the Oncoming RHR PUMP MIN 1E12-1E12-FLOW VALVE is energized, F064A F064B THEN PERFORM the following:
4.7.14.a VERIFY the Oncoming loop RHR PUMP MIN FLOW VALVE is closed.
1E12-F064A 1E12-F064B  


4.7.14.a VERIFY the Oncoming loop RHR1E12-1E12-PUMP MIN FLOW VALVE is closed. F064A F064B
4.7.14.b PERFORM independent verification of the Oncoming RHR PUMP MIN FLOW VALVE position.
1E12-F064A 1E12-F064B  


4.7.14.b PERFORM independent verification of1E12-1E12-the Oncoming RHR PUMP MIN FLOW F064A F064B VALVE position.
4.7.14.c OPEN the Oncoming RHR PUMP MIN FLOW VALVE, 1E12-F064, disconnect.
EF1 B07-CC EF1 D07-CC NOTE RPV level may increase during Quenching steam voids due to flow from the Condensate Transfer System while performing the following steps.
NA 4.7.15 IF SHUTDOWN COOLING OTBD SUCT ISOL is closed, THEN PERFORM the following:
1E12-F008


4.7.14.c OPEN the Oncoming RHR PUMP MINEF1 EF1 FLOW VALVE, 1E12-F064, disconnect. B07-D07-CC CC
4.7.15.a VERIFY SHUTDOWN COOLING INBD SUCT ISOL is closed.
1E12-F009 N/A


NOTE
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
RPV level may increase during Quenching steam voids due to flow from the Condensate Transfer System while performing the following steps.
 
NA 4.7.15 IF SHUTDOWN COOLING OTBD 1E12-SUCT ISOL is closed, F008 THEN PERFORM the following:
 
4.7.15.a VERIFY SHUTDOWN COOLING 1E12-INBD SUCT ISOL is closed. F009 Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 39 of 346
71 Page:
39 of 346 NA 4.7.15.b IF Reactor Temperature is greater than or equal to 200qF, THEN PERFORM the following to collapse steam voids:
4.7.15.b.1 REFER TO Flush Valve Operation and MANUALLY SLOWLY OPEN the Shtdn Cooling Suct Hdr Flush Supply, UNTIL flow noise is heard.
1E12-F315 4.7.15.b.2 WHEN the RHR suction piping has filled for approximately 5 minutes, THEN REFER TO Flush Valve Operation and MANUALLY SLOWLY OPEN the Shtdn Cooling Suct Hdr Flush Supply.
1E12-F315 NA 4.7.15.c IF Reactor Temperature is less than 200qF, THEN REFER TO Flush Valve Operation and MANUALLY OPEN the Shtdn Cooling Suct Hdr Flush Supply.
1E12-F315 4.7.15.d TAKE the SHUTDOWN COOLING OTBD SUCT ISOL to OPEN.
1E12-F008 4.7.16 VERIFY the Oncoming RHR SHUTDOWN CLG SUCT in OPEN.
1E12-F006A 1E12-F006B


NA 4.7.15.b IF Reactor Temperature is greater than or equal to 200qF, THEN PERFORM the following to collapse steam voids:
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
4.7.15.b.1 REFER TO Flush Valve Operation and 1E12-MANUALLY SLOWLY OPEN the F315 Shtdn Cooling Suct Hdr Flush Supply, UNTIL flow noise is heard.
 
4.7.15.b.2 WHEN the RHR suction piping has 1E12-filled for approximately 5 minutes, F315 THEN REFER TO Flush Valve Operation and MANUALLY SLOWLY OPEN the Shtdn Cooling Suct Hdr Flush Supply.
 
NA 4.7.15.c IF Reactor Temperature is less than 200qF, 1E12-THEN REFER TO Flush Valve F315 Operation and MANUALLY OPEN the Shtdn Cooling Suct Hdr Flush Supply.
 
4.7.15.d TAKE the SHUTDOWN COOLING 1E12-OTBD SUCT ISOL to OPEN. F008
 
4.7.16 VERIFY the Oncoming RHR 1E12-1E12-SHUTDOWN CLG SUCT in OPEN. F006A F006B Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 40 of 346
71 Page:
 
40 of 346 NA 4.7.17 IF SHUTDOWN COOLING INBD SUCT ISOL is closed, THEN PERFORM the following:
NA 4.7.17 IF SHUTDOWN COOLING INBD 1E12-SUCT ISOL is closed, F009 THEN PERFORM the following:
1E12-F009 NA 4.7.17.a IF Shtdn Cooling Suct Hdr Flush Supply is closed, THEN REFER TO Flush Valve Operation and MANUALLY SLOWLY OPEN the Shtdn Cooling Suct Hdr Flush Supply.
 
1E12-F315 4.7.17.b HOLD RHR B HXS SECOND VENT TO SUPR POOL in OPEN, UNTIL open.
NA 4.7.17.a IF Shtdn Cooling Suct Hdr Flush 1E12-Supply is closed, F315 THEN REFER TO Flush Valve
1E12-F073B 4.7.17.c WHEN the Suction Header has vented for 5 minutes, THEN HOLD RHR B HXS SECOND VENT TO SUPR POOL in CLOSE, UNTIL closed.
 
1E12-F073B 4.7.17.d REFER TO Flush Valve Operation and CLOSE the Shtdn Cooling Suct Hdr Flush Supply.
Operation and MANUALLY SLOWLY OPEN the Shtdn Cooling Suct Hdr Flush Supply.
1E12-F315 4.7.17.e TAKE SHUTDOWN COOLING INBD SUCT ISOL to OPEN.
 
1E12-F009
4.7.17.b HOLD RHR B HXS SECOND VENT 1E12-TO SUPR POOL in OPEN, UNTIL F073B open.
 
4.7.17.c WHEN the Suction Header has vented 1E12-for 5 minutes, F073B THEN HOLD RHR B HXS SECOND VENT TO SUPR POOL in CLOSE, UNTIL closed.


4.7.17.d REFER TO Flush Valve Operation and 1E12-CLOSE the Shtdn Cooling Suct Hdr F315 Flush Supply.
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
4.7.17.e TAKE SHUTDOWN COOLING INBD 1E12-SUCT ISOL to OPEN. F009 Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 41 of 346
71 Page:
 
41 of 346 CAUTION The following step will reduce Reactor Vessel Water inventory. Reactor Vessel level should be raised to near the high level alarm setpoint prior to this step to prevent exceeding the low level setpoint.
CAUTION
 
The following step will reduce Reactor Vessel Water inventory. Reactor Vessel level should be raised to near the high level alarm setpoint prior to this step to prevent exceeding the low level setpoint.
 
NA 4.7.18 IF Reactor Temperature is greater than 200qF, THEN PERFORM the following to warmup the RHR suction piping:
NA 4.7.18 IF Reactor Temperature is greater than 200qF, THEN PERFORM the following to warmup the RHR suction piping:
 
NA 4.7.18.a IF placing RHR A in Shutdown Cooling, THEN TAKE RHR A TO RADWASTE ISOL to OPEN.
NA 4.7.18.a IF placing RHR A in Shutdown Cooling, 1E12-THEN TAKE RHR A TO RADWASTE F049 ISOL to OPEN.
1E12-F049 NA 4.7.18.b IF placing RHR B in Shutdown Cooling, THEN OPEN RHR B to Radwaste Shutoff Valve.
 
1E12-F504 4.7.18.c VERIFY that Radwaste is ready to receive water from RHR.
NA 4.7.18.b IF placing RHR B in Shutdown Cooling, 1E12-THEN OPEN RHR B to Radwaste F504 Shutoff Valve.
 
4.7.18.c VERIFY that Radwaste is ready to receive water from RHR.
 
4.7.18.d NOTIFY Radwaste that a flush is to be commenced.
4.7.18.d NOTIFY Radwaste that a flush is to be commenced.
4.7.18.e NOTE the Oncoming RHR IN to HXTR Temperature on RHR TEMPERATURES recorder.
Temp: qF 1E12-R601 Pt 1 (red) 1E12-R601 Pt 2 (dark green)
NOTE The dust and oil film, which may accumulate during standby readiness periods, may smoke when heated during the performance of the following steps.
4.7.18.f THROTTLE the RHR TO RADWASTE ISOL in OPEN for 1 to 3 seconds.
1E12-F040


4.7.18.e NOTE the Oncoming RHR IN to HXTR 1E12-1E12-Temperature on RHR R601 R601 TEMPERATURES recorder. Pt 1 Pt 2 (red) (dark green)
PERRY NUCLEAR POWER PLANT Instruction Number:
Temp: qF
SOI-E12 Section 4.7
 
NOTE
 
The dust and oil film, which may accumulate during standby readiness periods, may smoke when heated during the performance of the following steps.
 
4.7.18.f THROTTLE the RHR TO RADWASTE 1E12-ISOL in OPEN for 1 to 3 seconds. F040 Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 42 of 346
71 Page:
 
42 of 346 NA 4.7.18.g RHR DISCH to RW Temperature on the RHR TEMPERATURES recorder is 200qF RHR DISCH to RW Temperature on the RHR TEMPERATURES recorder has stabilized near RPV temperature 1E12-R601 Pt 11 (light green)
NA 4.7.18.g RHR DISCH to RW RHR DISCH to RW 1E12-Temperature on Temperature on R601 the RHR the RHR Pt 11 TEMPERATURES TEMPERATURES (light green) recorder is 200qF recorder has stabilized near RPV temperature
THEN VERIFY RHR TO RADWASTE ISOL is CLOSED.
 
1E12-F040 NA 4.7.18.h IF placing RHR A in Shutdown Cooling, THEN TAKE the RHR A TO RADWASTE ISOL to CLOSE.
THEN VERIFY RHR TO RADWASTE 1E12-ISOL is CLOSED. F040
1E12-F049 NA 4.7.18.i IF placing RHR B in Shutdown Cooling, THEN CLOSE the RHR B to Radwaste Shutoff Valve.
1E12-F504 4.7.18.j NOTIFY Radwaste that the flush has been secured.
4.7.18.k THROTTLE open RHR HXS DUMP VALVE for 1 to 3 seconds.
1E12-F011A 1E12-F011B NA 4.7.18.l RHR IN To HXTR temperature has risen 5-10qF from the initial temperature noted RHR IN To HXTR temperature on the RHR TEMPER-ATURES recorder has stabilized near RPV temperature 10 minutes has elapsed 1E12-R601 Pt 1 (red) 1E12-R601 Pt 2 (dark green)
THEN HOLD RHR HXS DUMP VALVE in CLOSE, UNTIL closed.
1E12-F011A 1E12-F011B


NA 4.7.18.h IF placing RHR A in Shutdown Cooling, THEN TAKE the RHR A TO 1E12-RADWASTE ISOL to CLOSE. F049
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
NA 4.7.18.i IF placing RHR B in Shutdown Cooling, THEN CLOSE the RHR B to 1E12-Radwaste Shutoff Valve. F504
 
4.7.18.j NOTIFY Radwaste that the flush has been secured.
4.7.18.k THROTTLE open RHR HXS DUMP 1E12-1E12-VALVE for 1 to 3 seconds. F011A F011B
 
NA 4.7.18.l RHR IN RHR IN 10 1E12-1E12-To HXTR To HXTR minutes R601 R601 temperature temperature on has Pt 1 Pt 2 has risen the RHR elapsed (red) (dark green) 5-10qF from TEMPER-the initial ATURES temperature recorder has noted stabilized near RPV temperature
 
THEN HOLD RHR HXS DUMP 1E12-1E12-VALVE in CLOSE, UNTIL closed. F011A F011B
 
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 43 of 346
71 Page:
 
43 of 346 4.7.19 HOLD the Oncoming RHR HXS BYPASS VALVE in CLOSE for 59-62 seconds.
4.7.19 HOLD the Oncoming RHR HXS 1E12-1E12-BYPASS VALVE in CLOSE for F048A F048B 59-62 seconds.
1E12-F048A 1E12-F048B 4.7.20 HOLD RHR HXS OUTLET VALVE in CLOSE, UNTIL closed.
 
1E12-F003A 1E12-F003B NA 4.7.21 It is desired to establish the Normal Return Path 1E12-F053A 1E12-F053B RHR Upper Pool Cooling Isol is closed 1E12-F037A 1E12-F037B LPCI Injection Valve is closed 1E12-F042A 1E12-F042B THEN PERFORM the following:
4.7.20 HOLD RHR HXS OUTLET VALVE in 1E12-1E12-CLOSE, UNTIL closed. F003A F003B
NA 4.7.21.a IF the Feedwater System is shutdown, THEN VERIFY the Oncoming RHR loop FDW HDR SHUTOFF is closed, to prevent flow to the feedwater system.
 
1B21-F065A 1B21-F065B
NA 4.7.21 It is desired to establish the Normal 1E12-1E12-Return Path F053A F053B
 
RHR Upper Pool Cooling Isol is closed 1E12-1E12-F037A F037B
 
LPCI Injection Valve is closed 1E12-1E12-F042A F042B
 
THEN PERFORM the following:


NA 4.7.21.a IF the Feedwater System is shutdown, 1B21-1B21-THEN VERIFY the Oncoming RHR F065A F065B loop FDW HDR SHUTOFF is closed, to prevent flow to the feedwater system.
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 44 of 346
71 Page:
 
44 of 346 CAUTIONS x The RHR PUMP MIN FLOW VALVE is downpowered in the closed position. Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
CAUTIONS x The RHR PUMP MIN FLOW VALVE is downpowered in the closed position. Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
 
x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
4.7.21.b INITIATE flow through the SHUTDOWN COOLING TO FDW SHUTOFF as follows:
1E12-F053A 1E12-F053B 4.7.21.b.1 PERFORM the following simultaneously:
x HOLD the SHUTDOWN COOLING TO FDW SHUTOFF in OPEN, UNTIL open.
1E12-F053A 1E12-F053B x
TAKE the RHR PUMP to START. 1E12-C002A 1E12-C002B 4.7.21.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.
1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B 4.7.21.c JOG OPEN the RHR HXS BYPASS VALVE in 1000-2000 gpm increments, UNTIL RHR PUMP FLOW is 6000-7100 gpm.
1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B 4.7.21.d GO TO RHR Shutdown Cooling Operations for RHR A(B).


4.7.21.b INITIATE flow through the 1E12-1E12-SHUTDOWN COOLING TO FDW F053A F053B SHUTOFF as follows:
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
4.7.21.b.1 PERFORM the following simultaneously:
 
x HOLD the SHUTDOWN 1E12-1E12-COOLING TO FDW SHUTOFF in F053A F053B OPEN, UNTIL open.
 
x TAKE the RHR PUMP to START. 1E12-1E12-C002A C002B
 
4.7.21.b.2 WITHIN 8 seconds, THROTTLE 1E12-1E12-RHR HXS BYPASS VALVE, UNTIL F048A F048B RHR PUMP FLOW is at least 1E12-1E12-2575 gpm. R603A R603B
 
4.7.21.c JOG OPEN the RHR HXS BYPASS 1E12-1E12-VALVE in 1000-2000 gpm increments, F048A F048B UNTIL RHR PUMP FLOW is 1E12-1E12-6000-7100 gpm. R603A R603B
 
4.7.21.d GO TO RHR Shutdown Cooling Operations for RHR A(B).
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 45 of 346
71 Page:
 
45 of 346 NA 4.7.22 It is desired to establish the Refuel Return Path 1E12-F037A 1E12-F037B Shutdown Cooling To Fdw Shutoff is closed 1E12-F053A 1E12-F053B LPCI Injection Valve is closed 1E12-F042A 1E12-F042B RHR to Cntmt Pools Spectacle Flange blank is removed 1E12-D501A 1E12-D501B The RPV Head has been removed The Containment Pools are filled THEN PERFORM the following:
NA 4.7.22 It is desired to establish the Refuel 1E12-1E12-Return Path F037A F037B
4.7.22.a MONITOR FPCC SURGE TANK LEVEL while establishing Refuel Mode Shutdown Cooling.
 
G41-R366A G41-R366B (INTENTIONALLY BLANK)
Shutdown Cooling To Fdw Shutoff is 1E12-1E12-closed F053A F053B
 
LPCI Injection Valve is closed 1E12-1E12-F042A F042B
 
RHR to Cntmt Pools Spectacle Flange 1E12-1E12-blank is removed D501A D501B


The RPV Head has been removed
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
The Containment Pools are filled
 
THEN PERFORM the following:
 
4.7.22.a MONITOR FPCC SURGE TANK G41-G41-LEVEL while establishing Refuel Mode R366A R366B Shutdown Cooling.
 
(INTENTIONALLY BLANK)
 
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 46 of 346
71 Page:
 
46 of 346 CAUTIONS x The RHR PUMP MIN FLOW VALVE is downpowered in the closed position. Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
CAUTIONS x The RHR PUMP MIN FLOW VALVE is downpowered in the closed position. Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
 
x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
4.7.22.b INITIATE flow through the RHR UPPER POOL COOLING ISOL as follows:
1E12-F037A 1E12-F037B 4.7.22.b.1 PERFORM the following simultaneously:
x HOLD the RHR UPPER POOL COOLING ISOL in OPEN, UNTIL open.
1E12-F037A 1E12-F037B x
TAKE the RHR PUMP to START. 1E12-C002A 1E12-C002B 4.7.22.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.
1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B 4.7.22.c JOG OPEN the RHR HXS BYPASS VALVE in 1000-2000 gpm increments, UNTIL RHR PUMP FLOW is 7000-7100 gpm.
1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B 4.7.22.d GO TO RHR Shutdown Cooling Operations for RHR A(B).


4.7.22.b INITIATE flow through the RHR 1E12-1E12-UPPER POOL COOLING ISOL as F037A F037B follows:
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
4.7.22.b.1 PERFORM the following simultaneously:
 
x HOLD the RHR UPPER POOL 1E12-1E12-COOLING ISOL in OPEN, F037A F037B UNTIL open.
 
x TAKE the RHR PUMP to START. 1E12-1E12-C002A C002B
 
4.7.22.b.2 WITHIN 8 seconds, THROTTLE 1E12-1E12-RHR HXS BYPASS VALVE, UNTIL F048A F048B RHR PUMP FLOW is at least 1E12-1E12-2575 gpm. R603A R603B
 
4.7.22.c JOG OPEN the RHR HXS BYPASS 1E12-1E12-VALVE in 1000-2000 gpm increments, F048A F048B UNTIL RHR PUMP FLOW is 1E12-1E12-7000-7100 gpm. R603A R603B
 
4.7.22.d GO TO RHR Shutdown Cooling Operations for RHR A(B).
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 47 of 346
71 Page:
 
47 of 346 CAUTIONS x
CAUTIONS
Operation of the RHR Loop with Vessel Injection via the LPCI Injection Line has the potential to result in fatigue failure of incore instrument tubes and burnishing of fuel channels.
 
x Operation of the RHR Loop with Vessel Injection via the LPCI Injection Line has the potential to result in fatigue failure of incore instrument tubes and burnishing of fuel channels.
 
x The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.
x The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.
Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
 
NA 4.7.23 It is desired to establish the Alternate Return Path 1E12-F042A 1E12-F042B Normal Shutdown Cooling return path is unavailable 1E12-F053A 1E12-F053B Refuel Shutdown Cooling return path is unavailable 1E12-F037A 1E12-F037B THEN PERFORM the following:
NA 4.7.23 It is desired to establish the Alternate 1E12-1E12-Return Path F042A F042B
 
Normal Shutdown Cooling return path 1E12-1E12-is unavailable F053A F053B
 
Refuel Shutdown Cooling return path is 1E12-1E12-unavailable F037A F037B
 
THEN PERFORM the following:
 
4.7.23.a REFER TO Alternate Shutdown Cooling Data (Attachment 42) and TAKE Pre-Start Data.
4.7.23.a REFER TO Alternate Shutdown Cooling Data (Attachment 42) and TAKE Pre-Start Data.
(INTENTIONALLY BLANK)


(INTENTIONALLY BLANK)
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 48 of 346
71 Page:
 
48 of 346 CAUTIONS x
CAUTIONS
The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.
 
x The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.
Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
4.7.23.b INITIATE flow through the LPCI INJECTION VALVE as follows:
1E12-F042A 1E12-F042B 4.7.23.b.1 PERFORM the following simultaneously:
x TAKE the LPCI INJECTION VALVE to OPEN.
1E12-F042A 1E12-F042B x
TAKE the RHR PUMP to START. 1E12-C002A 1E12-C002B 4.7.23.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.
1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B 4.7.23.c JOG OPEN the RHR HXS BYPASS VALVE in 1000-2000 gpm increments, UNTIL RHR PUMP FLOW is 2575-7100 gpm.
1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B


4.7.23.b INITIATE flow through the 1E12-1E12-LPCI INJECTION VALVE as follows: F042A F042B
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 4.7
4.7.23.b.1 PERFORM the following simultaneously:
 
x TAKE the LPCI INJECTION 1E12-1E12-VALVE to OPEN. F042A F042B
 
x TAKE the RHR PUMP to START. 1E12-1E12-C002A C002B
 
4.7.23.b.2 WITHIN 8 seconds, THROTTLE 1E12-1E12-RHR HXS BYPASS VALVE, UNTIL F048A F048B RHR PUMP FLOW is at least 1E12-1E12-2575 gpm. R603A R603B
 
4.7.23.c JOG OPEN the RHR HXS BYPASS 1E12-1E12-VALVE in 1000-2000 gpm increments, F048A F048B UNTIL RHR PUMP FLOW is 1E12-1E12-2575-7100 gpm. R603A R603B Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 4.7


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 49 of 346
71 Page:
 
49 of 346 4.7.23.d NOTIFY the following of the use of the Shutdown Cooling return flow to the Vessel via LPCI INJECTION VALVE so the required fuel inspection may be scheduled:
4.7.23.d NOTIFY the following of the use of the 1E12-1E12-Shutdown Cooling return flow to the F042A F042B Vessel via LPCI INJECTION VALVE so the required fuel inspection may be scheduled:
1E12-F042A 1E12-F042B x
 
Reactor Engineering.
x Reactor Engineering.
 
x Outage Planning.
x Outage Planning.
4.7.23.e INITIATE a special report to the NRC in accordance with NOP-OP-1015, Event Notifications.
4.7.23.e INITIATE a special report to the NRC in accordance with NOP-OP-1015, Event Notifications.
4.7.23.f GO TO RHR Shutdown Cooling Operations for RHR A(B).
4.7.23.f GO TO RHR Shutdown Cooling Operations for RHR A(B).
END OF SECTION
END OF SECTION


Instruction Number:
PERRY NUCLEAR POWER PLANT Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6
SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 101 of 346
71 Page:
 
101 of 346 7.6 RHR Shutdown Cooling Operations for RHR A(B)
7.6 RHR Shutdown Cooling Operations for RHR A(B)
NOTES x Normal Design parameters for Shutdown Cooling/Test Mode operation:
 
NOTES
 
x Normal Design parameters for Shutdown Cooling/Test Mode operation:
 
o RHR Pump Flow 7000-7100 gpm.
o RHR Pump Flow 7000-7100 gpm.
o RHR Pump Amps 95-110 Amps.
o RHR Pump Amps 95-110 Amps.
Line 1,081: Line 808:
o RHR HXS RHR Outlet Temp Less than 86qF (Refuel Mode).
o RHR HXS RHR Outlet Temp Less than 86qF (Refuel Mode).
x The following actions can be performed in any logical order or repeated to support current plant conditions.
x The following actions can be performed in any logical order or repeated to support current plant conditions.
7.6.1 OBSERVE the following limitations when in Shutdown Cooling:
7.6.1 OBSERVE the following limitations when in Shutdown Cooling:
x MAINTAIN cooldown rate less than 100qF in any 1 hour period.
x MAINTAIN cooldown rate less than 100qF in any 1 hour period.
x DO NOT allow any RHR piping which has been inadvertently drained to be refilled with water from the Reactor Vessel.
x DO NOT allow any RHR piping which has been inadvertently drained to be refilled with water from the Reactor Vessel.
x MAINTAIN Vessel temperature below 190qF while in Shutdown Cooling.
x MAINTAIN Vessel temperature below 190qF while in Shutdown Cooling.
x WHEN using the normal OR refuel mode return paths, THEN MAINTAIN the following:
x WHEN using the normal OR refuel mode return paths, THEN MAINTAIN the following:
x MAINTAIN RHR Pump flow at 7000-7100 gpm during steady state conditions.


x MAINTAIN RHR Pump flow at 7000-7100 gpm during steady state conditions.
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 7.6
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 102 of 346
71 Page:
 
102 of 346 x MAINTAIN RHR Pump flow at 6000-7100 gpm during system adjustments.
x MAINTAIN RHR Pump flow at 6000-7100 gpm during system adjustments.
x WHEN using the alternate return path, THEN MONITOR the following additional items:
 
1E12-F042A 1E12-F042B x MAINTAIN RHR FLOW in the band 2575-7100 gpm.
x WHEN using the alternate return 1E12-1E12-path, THEN MONITOR the F042A F042B following additional items:
1E12-F042A 1E12-F042B x MAINTAIN RHR H2O DISCH temperature greater than 65qF.
 
1E12-R601 Pt 5 (magenta) 1E12-R601 Pt 6 (orange) 7.6.2 PERFORM the following as needed to maintain desired cooldown rate AND RHR Pump flow 7000-7100 (alternate return path 2575-7100):
x MAINTAIN RHR FLOW in the 1E12-1E12-band 2575-7100 gpm. F042A F042B
1E12-R603A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE.
 
1E12-F003A 1E12-F003B x THROTTLE RHR HXS BYPASS VALVE.
x MAINTAIN RHR H2O DISCH 1E12-1E12-temperature greater than 65qF. R601 R601 Pt 5 Pt 6 (magenta) (orange)
1E12-F048A 1E12-F048B NA 7.6.3 RHR A is in Shutdown Cooling Head spray is desired THEN PERFORM the following:
 
7.6.3.a CONFIRM that the RCIC INJECTION VLV is closed.
7.6.2 PERFORM the following as needed to 1E12-1E12-maintain desired cooldown rate AND R603A R603B RHR Pump flow 7000-7100 (alternate return path 2575-7100):
1E51-F013
 
x THROTTLE RHR HXS OUTLET 1E12-1E12-VALVE. F003A F003B
 
x THROTTLE RHR HXS BYPASS 1E12-1E12-VALVE. F048A F048B
 
NA 7.6.3 RHR A is in Shutdown Cooling
 
Head spray is desired
 
THEN PERFORM the following:


7.6.3.a CONFIRM that the RCIC INJECTION 1E51-VLV is closed. F013 Instruction Number:
PERRY NUCLEAR POWER PLANT Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6
SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 103 of 346
71 Page:
 
103 of 346 NOTE The HD SPRAY FLOW 1E12-R607 indication taps in downstream of the RHR Pump flow 1E12-R603A(B) indicator. Changing head Spray flow does not change RHR Pump flow.
NOTE
7.6.3.b PERFORM the following, UNTIL HD SPRAY FLOW is 500 gpm AND RHR Pump flow 7000-7100 (alternate return path 2575-7100):
 
1E12-R607 1E12-R603A 1E12-R603A x
The HD SPRAY FLOW 1E12-R607 indication taps in downstream of the RHR Pump flow 1E12-R603A(B) indicator. Changing head Spray flow does not change RHR Pump flow.
THROTTLE RHR HXS OUTLET VALVE.
 
1E12-F003A 1E12-F003B x
7.6.3.b PERFORM the following, UNTIL HD 1E12-SPRAY FLOW is 500 gpm AND RHR R607 Pump flow 7000-7100 (alternate return 1E12-1E12-path 2575-7100): R603A R603A
THROTTLE RHR HXS BYPASS VALVE.
 
1E12-F048A 1E12-F048B x
x THROTTLE RHR HXS OUTLET 1E12-1E12-VALVE. F003A F003B
THROTTLE RHR A HEAD SPRAY ISOL.
 
1E12-F023 7.6.3.c WHEN the Rx Vessel pressure is at atmospheric pressure, THEN VERIFY RHR A HEAD SPRAY ISOL is closed.
x THROTTLE RHR HXS BYPASS 1E12-1E12-VALVE. F048A F048B
1E12-F023 NA 7.6.4 IF oncoming loop of ESW was NOT started per SOI-P45/49, THEN PERFORM the following:
 
x THROTTLE RHR A HEAD 1E12-SPRAY ISOL. F023
 
7.6.3.c WHEN the Rx Vessel pressure is at 1E12-atmospheric pressure, F023 THEN VERIFY RHR A HEAD SPRAY ISOL is closed.
 
NA 7.6.4 IF oncoming loop of ESW was NOT started per SOI-P45/49, THEN PERFORM the following:
 
7.6.4.a VERIFY the following:
7.6.4.a VERIFY the following:
x ESW PMP HOUSE VENT SUPP FAN 1, is RUNNING.
1M32-C001A 1M32-C001B x ESW PMP HOUSE EXH LOUVER 70 is OPEN 1M32-F070A 1M32-F070B x ESW PUMP DISCH VALVE is fully OPEN 1P45-F130A 1P45-F130B


x ESW PMP HOUSE VENT SUPP 1M32-1M32-FAN 1, is RUNNING. C001A C001B
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 7.6
x ESW PMP HOUSE EXH LOUVER 1M32-1M32-70 is OPEN F070A F070B
 
x ESW PUMP DISCH VALVE is fully 1P45-1P45-OPEN F130A F130B Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 104 of 346
71 Page:
 
104 of 346 7.6.4.b RECORD ESW flow channel check in the Narrative Log.
7.6.4.b RECORD ESW flow channel check in the Narrative Log.
NA 7.6.4.c IF lake temperature is less than
 
: 34qF, THEN REFER TO SOI-P45/49 and PERFORM de-icing operation.
NA 7.6.4.c IF lake temperature is less than 34qF, THEN REFER TO SOI-P45/49 and PERFORM de-icing operation.
 
7.6.4.d DIRECT Chemistry to perform the following:
7.6.4.d DIRECT Chemistry to perform the following:
x OBTAIN Tech Spec samples of flow through the RHR Heat Exchangers as required.
x OBTAIN Tech Spec samples of flow through the RHR Heat Exchangers as required.
x CHLORINATE ESW as required.
x CHLORINATE ESW as required.
NA 7.6.5 Information Tag is on the RHR Conductivity Alarm window(s)
Caution Tag is on the RHR Conductivity Alarm window(s) 1H13-P601-2 0-G5 1H13-P601-17-G5 THEN REFER TO Placing RHR Conductivity Alarm In Service and VERIFY the actions are complete.
NA 7.6.6 IF the LPCI INJECTION VALVE is
: open, THEN REFER TO Alternate Shutdown Cooling Data (Attachment 42) and TAKE Post-Start Data Alternate Shutdown Cooling Return Path Startup Data.
1E12-F042A 1E12-F042B 7.6.7 PERFORM Independent Verification of the required components for Shutdown Cooling Startup for RHR A(B).


NA 7.6.5 Information Tag is Caution Tag is on 1H13-1H13-on the RHR the RHR P601-2 P601-Conductivity Alarm Conductivity Alarm 0-G5 17-G5 window(s) window(s)
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 7.6
THEN REFER TO Placing RHR Conductivity Alarm In Service and VERIFY the actions are complete.
 
NA 7.6.6 IF the LPCI INJECTION VALVE is 1E12-1E12-open, F042A F042B THEN REFER TO Alternate Shutdown Cooling Data (Attachment 42) and TAKE Post-Start Data Alternate Shutdown Cooling Return Path Startup Data.
 
7.6.7 PERFORM Independent Verification of the required components for Shutdown Cooling Startup for RHR A(B).
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 105 of 346
71 Page:
 
105 of 346 NA 7.6.8 IF RPV temperature is less than 200qF, THEN NOTIFY the Unit Supervisior that RHR loop(s) in Shutdown Cooling may be declared operable for LPCI, Suppression Pool Cooling, Shutdown Cooling and Containment Spray Modes.
NA 7.6.8 IF RPV temperature is less than 200qF, THEN NOTIFY the Unit Supervisior that RHR loop(s) in Shutdown Cooling may be declared operable for LPCI, Suppression Pool Cooling, Shutdown Cooling and Containment Spray Modes.
NA 7.6.9 RPV temperature is less than 200qF Opposite loop of RHR is available for shutdown cooling Loop B
 
Loop A
NA 7.6.9 RPV temperature is less than 200qF
 
Opposite loop of RHR is available for LoopLoop shutdown cooling B A
 
THEN PERFORM the following:
THEN PERFORM the following:
 
7.6.9.a REFER TO Flush of RHR Loop A(B)
7.6.9.a REFER TO Flush of RHR Loop A(B) LoopLoop When in Standby Readiness Mode and B A VERIFY the Opposite loop of RHR has been flushed.
When in Standby Readiness Mode and VERIFY the Opposite loop of RHR has been flushed.
 
Loop B
Loop A
NA 7.6.9.b IF Suppression Pool is NOT transfer quality, THEN REFER TO Flush of RHR A(B)
NA 7.6.9.b IF Suppression Pool is NOT transfer quality, THEN REFER TO Flush of RHR A(B)
With CST Water and VERIFY the actions are complete.
With CST Water and VERIFY the actions are complete.
Instruction Number:
 
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6
PERRY NUCLEAR POWER PLANT Instruction Number:
SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 106 of 346
71 Page:
 
106 of 346 NOTES x The flow path for the RHR Loop operating in Refuel Mode Shutdown Cooling will be:  
NOTES
- RHR Loop A - Separator Storage Well to Reactor Cavity.  
 
- RHR Loop B - Dryer and Fuel Storage Well to Reactor Cavity.
x The flow path for the RHR Loop operating in Refuel Mode Shutdown Cooling will be:
 
- RHR Loop A - Separator Storage Well to Reactor Cavity.
- RHR Loop B - Dryer and Fuel Storage Well to Reactor Cavity.
x This Step can be used during refueling operations as necessary to minimize flow-induced turbulence.
x This Step can be used during refueling operations as necessary to minimize flow-induced turbulence.
 
NA 7.6.10 It is desired to Improve Water Clarity Desire to Align RHR Shutdown Cooling Flow to the Upper Pools THEN PERFORM the following:
NA 7.6.10 It is desired to Desire to Align Improve Water RHR Shutdown Clarity Cooling Flow to the Upper Pools
 
THEN PERFORM the following:
 
7.6.10.a VERIFY the Reactor Vessel Head is removed.
7.6.10.a VERIFY the Reactor Vessel Head is removed.
7.6.10.b VERIFY the Upper Pools are filled.
7.6.10.b VERIFY the Upper Pools are filled.
7.6.10.c VERIFY the RHR to Cntmt Pools Spectacle Flange is aligned with the blank removed and the spacer ring installed.
1E12-D501A 1E12-D501B 7.6.10.d PERFORM the following as need, UNTIL RHR PUMP FLOW is 7000-7100 gpm AND desired flow to the upper pools is established:
1E12-R603A 1E12-R603B x THROTTLE RHR UPPER POOL COOLING ISOL.
1E12-F037A 1E12-F037B x THROTTLE SHUTDOWN COOLING TO FDW SHUTOFF.
1E12-F053A 1E12-F053B


7.6.10.c VERIFY the RHR to Cntmt Pools 1E12-1E12-Spectacle Flange is aligned with the D501A D501B blank removed and the spacer ring installed.
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 7.6
7.6.10.d PERFORM the following as need, 1E12-1E12-UNTIL RHR PUMP FLOW is R603A R603B 7000-7100 gpm AND desired flow to the upper pools is established:
 
x THROTTLE RHR UPPER POOL 1E12-1E12-COOLING ISOL. F037A F037B
 
x THROTTLE SHUTDOWN 1E12-1E12-COOLING TO FDW SHUTOFF. F053A F053B Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 107 of 346
71 Page:
 
107 of 346 NA 7.6.10.e Feedwater is aligned to feed the RPV SHUTDOWN COOLING TO FDW SHUTOFF is closed 1E12-F053A 1E12-F053B THEN OPEN the associated FDW HDR SHUTOFF valve.
NA 7.6.10.e Feedwater is aligned to feed the RPV
1B21-F065A 1B21-F065B NA 7.6.11 RHR UPPER POOL COOLING ISOL is open RHR UPPER POOL COOLING ISOL is throttled 1E12-F037A 1E12-F037B Desired to use the Normal Mode Shutdown Cooling path THEN PERFORM the following:
 
7.6.11.a VERIFY the associated FDW HDR SHUTOFF valve is CLOSED.
SHUTDOWN COOLING TO FDW 1E12-1E12-SHUTOFF is closed F053A F053B
1B21-F065A 1B21-F065B 7.6.11.b PERFORM the following as need, UNTIL RHR PUMP FLOW is 7000-7100 gpm RHR UPPER POOL COOLING ISOL is closed:
1E12-R603A 1E12-F037A 1E12-R603B 1E12-F037B x THROTTLE RHR UPPER POOL COOLING ISOL.
1E12-F037A 1E12-F037B x THROTTLE SHUTDOWN COOLING TO FDW SHUTOFF.
1E12-F053A 1E12-F053B  


THEN OPEN the associated FDW 1B21-1B21-HDR SHUTOFF valve. F065A F065B
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 7.6
NA 7.6.11 RHR UPPER RHR UPPER 1E12-1E12-POOL COOLING POOL COOLING F037A F037B ISOL is open ISOL is throttled
 
Desired to use the Normal Mode Shutdown Cooling path
 
THEN PERFORM the following:
 
7.6.11.a VERIFY the associated FDW HDR 1B21-1B21-SHUTOFF valve is CLOSED. F065A F065B
 
7.6.11.b PERFORM the following as need, 1E12-1E12-UNTIL RHR PUMP FLOW is R603A R603B 7000-7100 gpm RHR UPPER POOL 1E12-1E12-COOLING ISOL is closed: F037A F037B
 
x THROTTLE RHR UPPER POOL 1E12-1E12-COOLING ISOL. F037A F037B
 
x THROTTLE SHUTDOWN 1E12-1E12-COOLING TO FDW SHUTOFF. F053A F053B Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 108 of 346
71 Page:
 
108 of 346 CAUTION Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
CAUTION
NA 7.6.12 Desire to Align RHR Shutdown Cooling Flow to the Normal Mode Desire to Align RHR Shutdown Cooling Flow to the Refuel Mode 1E12-F053A 1E12-F037A 1E12-F053B 1E12-F037B LPCI INJECTION VALVE is open 1E12-F042A 1E12-F042B THEN PERFORM the following:
 
7.6.12.a PERFORM the following as needed to establish RHR PUMP FLOW 2750-3500 gpm, WHILE maintaining desired cooldown rate:
Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.
1E12-R603A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE.
 
1E12-F003A 1E12-F003B x THROTTLE OPEN RHR HXS BYPASS VALVE.
NA 7.6.12 Desire to Align Desire to Align 1E12-1E12-RHR Shutdown RHR Shutdown F053A F053B Cooling Flow to the Cooling Flow to the Normal Mode Refuel Mode 1E12-1E12-F037A F037B
1E12-F048A 1E12-F048B NA 7.6.12.b IF aligning RHR Shutdown Cooling Flow to the Normal Mode, THEN PERFORM the following:
 
7.6.12.b.1 VERIFY the associated FDW HDR SHUTOFF is closed.
LPCI INJECTION VALVE is open 1E12-1E12-F042A F042B
1B21-F065A 1B21-F065B 7.6.12.b.2 HOLD the SHUTDOWN COOLING TO FDW SHUTOFF in OPEN, UNTIL open.
1E12-F053A 1E12-F053B


THEN PERFORM the following:
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 7.6
7.6.12.a PERFORM the following as needed to 1E12-1E12-establish RHR PUMP FLOW R603A R603B 2750-3500 gpm, WHILE maintaining desired cooldown rate:
 
x THROTTLE RHR HXS OUTLET 1E12-1E12-VALVE. F003A F003B
 
x THROTTLE OPEN RHR HXS 1E12-1E12-BYPASS VALVE. F048A F048B
 
NA 7.6.12.b IF aligning RHR Shutdown Cooling Flow to the Normal Mode, THEN PERFORM the following:
 
7.6.12.b.1 VERIFY the associated FDW HDR 1B21-1B21-SHUTOFF is closed. F065A F065B
 
7.6.12.b.2 HOLD the SHUTDOWN COOLING TO 1E12-1E12-FDW SHUTOFF in OPEN, UNTIL F053A F053B open.
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 109 of 346
71 Page:
 
109 of 346 7.6.12.b.3 TAKE the LPCI INJECTION VALVE to CLOSED.
7.6.12.b.3 TAKE the LPCI INJECTION VALVE to 1E12-1E12-CLOSED. F042A F042B
1E12-F042A 1E12-F042B NOTE The flow path for the RHR Loop operating in Refuel Mode Shutdown Cooling will be:
 
NOTE
 
The flow path for the RHR Loop operating in Refuel Mode Shutdown Cooling will be:
 
x RHR Loop A - Separator Storage Well to Reactor Cavity.
x RHR Loop A - Separator Storage Well to Reactor Cavity.
x RHR Loop B - Dryer and Fuel Storage Well to Reactor Cavity.
x RHR Loop B - Dryer and Fuel Storage Well to Reactor Cavity.
NA 7.6.12.c IF aligning RHR Shutdown Cooling Flow to the Refuel Mode, THEN PERFORM the following:
NA 7.6.12.c IF aligning RHR Shutdown Cooling Flow to the Refuel Mode, THEN PERFORM the following:
7.6.12.c.1 VERIFY the Reactor Vessel Head is removed.
7.6.12.c.1 VERIFY the Reactor Vessel Head is removed.
7.6.12.c.2 VERIFY the Upper Pools are filled.
7.6.12.c.2 VERIFY the Upper Pools are filled.
7.6.12.c.3 VERIFY the RHR to Cntmt Pools Spectacle Flange is aligned with the blank removed and the spacer ring installed.
1E12-D501A 1E12-D501B 7.6.12.c.4 HOLD the RHR UPPER POOL COOLING ISOL in OPEN, UNTIL open.
1E12-F037A 1E12-F037B 7.6.12.c.5 TAKE the LPCI INJECTION VALVE to CLOSED.
1E12-F042A 1E12-F042B


7.6.12.c.3 VERIFY the RHR to Cntmt Pools 1E12-1E12-Spectacle Flange is aligned with the D501A D501B blank removed and the spacer ring installed.
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 7.6
7.6.12.c.4 HOLD the RHR UPPER POOL 1E12-1E12-COOLING ISOL in OPEN, UNTIL F037A F037B open.
 
7.6.12.c.5 TAKE the LPCI INJECTION VALVE to 1E12-1E12-CLOSED. F042A F042B Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 110 of 346
71 Page:
 
110 of 346 7.6.12.d PERFORM the following as needed to establish RHR PUMP FLOW 7000-7100 gpm:
7.6.12.d PERFORM the following as needed to 1E12-1E12-establish RHR PUMP FLOW R603A R603B 7000-7100 gpm:
1E12-R603A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE.
 
1E12-F003A 1E12-F003B x THROTTLE OPEN RHR HXS BYPASS VALVE.
x THROTTLE RHR HXS OUTLET 1E12-1E12-VALVE. F003A F003B
1E12-F048A 1E12-F048B NOTE RPV level can be estimated to be 200 gallons per inch of Reactor Vessel Level.
 
x THROTTLE OPEN RHR HXS 1E12-1E12-BYPASS VALVE. F048A F048B
 
NOTE
 
RPV level can be estimated to be 200 gallons per inch of Reactor Vessel Level.
 
NA 7.6.13 IF it is desired to Lower Reactor Level to Radwaste, THEN PERFORM the following:
NA 7.6.13 IF it is desired to Lower Reactor Level to Radwaste, THEN PERFORM the following:
7.6.13.a VERIFY Radwaste System is aligned to receive the flow from RHR.
7.6.13.a VERIFY Radwaste System is aligned to receive the flow from RHR.
7.6.13.b VERIFY that the Reactor coolant temperature is less than 140°F.
7.6.13.b VERIFY that the Reactor coolant temperature is less than 140°F.
7.6.13.c THROTTLE the following valves as needed to establish RHR PUMP FLOW 6000-6500 gpm:
1E12-R603A 1E12-R603B x RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B


7.6.13.c THROTTLE the following valves as 1E12-1E12-needed to establish RHR PUMP FLOW R603A R603B 6000-6500 gpm:
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 7.6
x RHR HXS OUTLET VALVE 1E12-1E12-F003A F003B
 
x RHR HXS BYPASS VALVE 1E12-1E12-F048A F048B Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 111 of 346
71 Page:
111 of 346 NA 7.6.13.d IF it is NOT desired to establish a continuous drain down, THEN THROTTLE the following valves as needed to establish RHR PUMP FLOW 4500 gpm:
1E12-R603A 1E12-R603B x RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B NA 7.6.13.e IF using RHR A, THEN TAKE the RHR A TO RADWASTE ISOL to OPEN.
1E12-F049 NA 7.6.13.f IF using RHR B, THEN OPEN the RHR B To Radwaste Shutoff Valve.
1E12-F504 7.6.13.g NOTIFY Radwaste RPV draining is beginning.
CAUTION Performance of the following step can cause a rapid decrease in RPV level. Discharge flow to Radwaste can drain up to 8/min from the RPV.
7.6.13.h THROTTLE the RHR TO RADWASTE ISOL, UNTIL the desired rate of RPV level decrease is achieved, WHILE maintaining RHR PUMP AMPS less than 95 amps.
1E12-F040 1E12-R100A 1E12-R100B


NA 7.6.13.d IF it is NOT desired to establish a continuous drain down, THEN THROTTLE the following 1E12-1E12-valves as needed to establish RHR R603A R603B PUMP FLOW 4500 gpm:
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 7.6
x RHR HXS OUTLET VALVE 1E12-1E12-F003A F003B
 
x RHR HXS BYPASS VALVE 1E12-1E12-F048A F048B
 
NA 7.6.13.e IF using RHR A, THEN TAKE the RHR A TO 1E12-RADWASTE ISOL to OPEN. F049
 
NA 7.6.13.f IF using RHR B, THEN OPEN the RHR B To Radwaste 1E12-Shutoff Valve. F504
 
7.6.13.g NOTIFY Radwaste RPV draining is beginning.
 
CAUTION
 
Performance of the following step can cause a rapid decrease in RPV level. Discharge flow to Radwaste can drain up to 8/min from the RPV.
 
7.6.13.h THROTTLE the RHR TO RADWASTE 1E12-ISOL, UNTIL the desired rate of RPV F040 level decrease is achieved, WHILE 1E12-1E12-maintaining RHR PUMP AMPS less R100A R100B than 95 amps.
Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 112 of 346
71 Page:
 
112 of 346 NA 7.6.13.i IF continuous drain down is being used, THEN WHILE maintaining RHR PUMP AMPS between 90-95 amps, PERFORM the following as needed to maintain desired heatup AND blowdown rates:
NA 7.6.13.i IF continuous drain down is being used, 1E12-1E12-THEN WHILE maintaining RHR R100A R100A PUMP AMPS between 90-95 amps, PERFORM the following as needed to 1E12-1E12-R603A R603B maintain desired heatup AND blowdown rates:
1E12-R100A 1E12-R603A 1E12-R100A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x THROTTLE RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B x THROTTLE RHR TO RADWASTE ISOL 1E12-F040 NA 7.6.13.j The desired RPV level is achieved Continuous blowdown is no longer required THEN PERFORM the following:
 
7.6.13.j.1 HOLD the RHR TO RADWASTE ISOL in CLOSE, UNTIL closed.
x THROTTLE RHR HXS OUTLET 1E12-1E12-VALVE F003A F003B
1E12-F040 NA 7.6.13.j.2 IF using RHR A, THEN TAKE the RHR A TO RADWASTE ISOL to CLOSE.
 
1E12-F049 NA 7.6.13.j.3 IF using RHR B, THEN CLOSE the RHR B To Radwaste Shutoff Valve.
x THROTTLE RHR HXS BYPASS 1E12-1E12-VALVE F048A F048B
1E12-F504
 
x THROTTLE RHR TO RADWASTE 1E12-ISOL F040


NA 7.6.13.j The desired RPV Continuous level is achieved blowdown is no longer required
PERRY NUCLEAR POWER PLANT Instruction Number:
 
SOI-E12 Section 7.6
THEN PERFORM the following:
 
7.6.13.j.1 HOLD the RHR TO RADWASTE ISOL 1E12-in CLOSE, UNTIL closed. F040
 
NA 7.6.13.j.2 IF using RHR A, THEN TAKE the RHR A TO 1E12-RADWASTE ISOL to CLOSE. F049
 
NA 7.6.13.j.3 IF using RHR B, THEN CLOSE the RHR B To 1E12-Radwaste Shutoff Valve. F504 Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 113 of 346
71 Page:
 
113 of 346 7.6.13.j.4 PERFORM the following as needed to establish RHR PUMP FLOW 7000-7100:
7.6.13.j.4 PERFORM the following as needed to 1E12-1E12-establish RHR PUMP FLOW R603A R603B 7000-7100:
1E12-R603A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE.
 
1E12-F003A 1E12-F003B x THROTTLE RHR HXS BYPASS VALVE.
x THROTTLE RHR HXS OUTLET 1E12-1E12-VALVE. F003A F003B
1E12-F048A 1E12-F048B 7.6.13.j.5 PERFORM independent verification of the required components.
 
NOTE RPV level can be estimated to be 200 gallons per inch of Reactor Vessel Level.
x THROTTLE RHR HXS BYPASS 1E12-1E12-VALVE. F048A F048B
 
7.6.13.j.5 PERFORM independent verification of the required components.
 
NOTE
 
RPV level can be estimated to be 200 gallons per inch of Reactor Vessel Level.
 
NA 7.6.14 IF it is desired to Lower Reactor Level to the Suppression Pool, THEN PERFORM the following:
NA 7.6.14 IF it is desired to Lower Reactor Level to the Suppression Pool, THEN PERFORM the following:
7.6.14.a VERIFY that the Reactor coolant temperature is less than 140°F.
7.6.14.a VERIFY that the Reactor coolant temperature is less than 140°F.
7.6.14.b NOTIFY Radiation Protection of the following:
7.6.14.b NOTIFY Radiation Protection of the following:
x A Suppression Pool evolution will be conducted which may affect suppression pool water level and/or activity.
x A Suppression Pool evolution will be conducted which may affect suppression pool water level and/or activity.
x Surveys should be performed for Containment 599 elevation to evaluate the radiological impact of the evolution.


x Surveys should be performed for Containment 599 elevation to evaluate the radiological impact of the evolution.
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 7.6
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 114 of 346
71 Page:
 
114 of 346 7.6.14.c THROTTLE the following valves as needed to establish RHR PUMP FLOW 6000-6500 gpm:
7.6.14.c THROTTLE the following valves as 1E12-1E12-needed to establish RHR PUMP FLOW R603A R603B 6000-6500 gpm:
1E12-R603A 1E12-R603B x RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B 7.6.14.d THROTTLE the following valves as needed to establish RHR PUMP FLOW 4500 gpm:
 
1E12-R603A 1E12-R603B x RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B 7.6.14.e WHILE maintaining RHR PUMP AMPS less than 95 amps, THROTTLE the RHR HXS DUMP VALVE, UNTIL the desired rate of RPV level decrease is achieved.
x RHR HXS OUTLET VALVE 1E12-1E12-F003A F003B
1E12-R100A 1E12-F011A 1E12-R100B 1E12-F011B 7.6.14.f WHEN the desired RPV level is
 
: achieved, THEN HOLD the RHR HXS DUMP VALVE in CLOSE, UNTIL closed.
x RHR HXS BYPASS VALVE 1E12-1E12-F048A F048B
1E12-F011A 1E12-F011B 7.6.14.g PERFORM the following as needed to establish RHR PUMP FLOW 6900-7100 gpm:
 
1E12-R603A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x THROTTLE RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B
7.6.14.d THROTTLE the following valves as 1E12-1E12-needed to establish RHR PUMP FLOW R603A R603B 4500 gpm:
 
x RHR HXS OUTLET VALVE 1E12-1E12-F003A F003B
 
x RHR HXS BYPASS VALVE 1E12-1E12-F048A F048B
 
7.6.14.e WHILE maintaining RHR PUMP AMPS 1E12-1E12-less than 95 amps, R100A R100B THROTTLE the RHR HXS DUMP 1E12-1E12-VALVE, UNTIL the desired rate of RPV F011A F011B level decrease is achieved.
 
7.6.14.f WHEN the desired RPV level is 1E12-1E12-achieved, F011A F011B THEN HOLD the RHR HXS DUMP VALVE in CLOSE, UNTIL closed.
 
7.6.14.g PERFORM the following as needed to 1E12-1E12-establish RHR PUMP FLOW R603A R603B 6900-7100 gpm:
 
x THROTTLE RHR HXS OUTLET 1E12-1E12-VALVE F003A F003B


x THROTTLE RHR HXS BYPASS 1E12-1E12-VALVE F048A F048B Instruction Number:
PERRY NUCLEAR POWER PLANT Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6
SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 115 of 346
71 Page:
 
115 of 346 7.6.14.h PERFORM independent verification of the required components.
7.6.14.h PERFORM independent verification of the required components.
NA 7.6.15 IF desired to raise Reactor Water Level Using Condensate Transfer and Storage
 
: Water, THEN PERFORM the following:
NA 7.6.15 IF desired to raise Reactor Water Level Using Condensate Transfer and Storage Water, THEN PERFORM the following:
7.6.15.a REFER TO Flush Valve Operation and OPEN the SHTDN COOLING SUCT HDR FLUSH SUPPLY valve.
 
1E12-F315 7.6.15.b WHEN the desired Reactor water level is achieved, THEN REFER TO Flush Valve Operation and CLOSE SHTDN COOLING SUCT HDR FLUSH SUPPLY valve.
7.6.15.a REFER TO Flush Valve Operation and 1E12-OPEN the SHTDN COOLING SUCT F315 HDR FLUSH SUPPLY valve.
1E12-F315 7.6.15.c PERFORM independent verification of the required components.
 
7.6.15.b WHEN the desired Reactor water level 1E12-is achieved, F315 THEN REFER TO Flush Valve Operation and CLOSE SHTDN COOLING SUCT HDR FLUSH SUPPLY valve.
 
7.6.15.c PERFORM independent verification of the required components.
 
7.6.16 WHEN desired to shutdown RHR, THEN PERFORM the following:
7.6.16 WHEN desired to shutdown RHR, THEN PERFORM the following:
7.6.16.a CONFIRM Lowering Reactor Level to Radwaste is NOT in progress.
7.6.16.a CONFIRM Lowering Reactor Level to Radwaste is NOT in progress.
7.6.16.b CONFIRM Lowering Reactor Level to the Suppression Pool is NOT in progress.
7.6.16.b CONFIRM Lowering Reactor Level to the Suppression Pool is NOT in progress.
7.6.16.c CONFIRM Raising Reactor Water Level Using Condensate Transfer and Storage Water is NOT in progress.


7.6.16.c CONFIRM Raising Reactor Water Level Using Condensate Transfer and Storage Water is NOT in progress.
PERRY NUCLEAR POWER PLANT Instruction Number:
Instruction Number:
SOI-E12 Section 7.6
PERRY NUCLEAR POWER PLANT SOI-E12 Section 7.6


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 116 of 346
71 Page:
 
116 of 346 7.6.16.d GO TO Shutdown Cooling Shutdown to Standby Readiness.
7.6.16.d GO TO Shutdown Cooling Shutdown to Standby Readiness.
END OF SECTION


END OF SECTION Instruction Number:
PERRY NUCLEAR POWER PLANT Instruction Number:
PERRY NUCLEAR POWER PLANT SOI-E12
SOI-E12


==Title:==
==Title:==
Use Category:
RESIDUAL HEAT REMOVAL SYSTEM Use Category:
RESIDUAL HEAT REMOVAL SYSTEM In-Field Reference Revision: Page:
In-Field Reference Revision:
71 341 of 346
71 Page:
 
341 of 346 ATTACHMENT 42 - Alternate Shutdown Cooling Data Page 1 of 1 NOTE The LOOP column indicates what must be verified for specific sections/steps.
ATTACHMENT 42 - Alternate Shutdown Cooling Data Page 1 of 1
Shutdown Cooling Loop:
 
Loop A ___ Loop B ___
NOTE
 
The LOOP column indicates what must be verified for specific sections/steps.
 
Shutdown Cooling Loop: Loop A ___ Loop B ___
Pre-Start Data:
Pre-Start Data:
Parameter Instrument Reading Loop 1E12-R601, Pt 1(red) A RHR IN to HXTR 1E12-R601, Pt 2 (dark green)
Parameter Instrument Reading Loop RHR IN to HXTR 1E12-R601, Pt 1(red)
B 1E12-R601, Pt 5 (magenta) A RHR H2O DISCH 1E12-R601, Pt 6 (orange)
A 1E12-R601, Pt 2 (dark green)
B RHR H2O DISCH 1E12-R601, Pt 5 (magenta)
A 1E12-R601, Pt 6 (orange)
B Drywell Avg. Temperature D23ED033 (1D23-R210A(B))
B Drywell Avg. Temperature D23ED033 (1D23-R210A(B))
Reactor Bulk Water Temp. (1)
Reactor Bulk Water Temp.
 
(1)
Post-Start Data:
Post-Start Data:
1E12-R601, Pt 1(red) A RHR IN to HXTR 1E12-R601, Pt 2 (dark green) B
RHR IN to HXTR 1E12-R601, Pt 1(red)
 
A 1E12-R601, Pt 2 (dark green)
1E12-R601, Pt 5 (magenta) A RHR H2O DISCH 1E12-R601, Pt 6 (orange)
B RHR H2O DISCH 1E12-R601, Pt 5 (magenta)
B RHR Pump Flow 1E12-R603A A 1E12-R603B B
A 1E12-R601, Pt 6 (orange)
 
B RHR Pump Flow 1E12-R603A A
1E12-R603B B
Drywell Avg. Temperature D23ED033 (1D23-R210A(B))
Drywell Avg. Temperature D23ED033 (1D23-R210A(B))
Reactor Bulk Water Temp. (1)
Reactor Bulk Water Temp.
 
(1) instrument for this parameter. Record which instrument was used in the instrument column.
instrument for this parameter. Record which instrument was used in the instrument column.
Forward the original to the Responsible System Engineer, PNED/SES Forward a copy to the System Design Engineer, PNED/DES Forward a copy to the Lead Engineer, Piping Analysis, PNED/DES.  
Forward the original to the Responsible System Engineer, PNED/SES
 
Forward a copy to the System Design Engineer, PNED/DES
 
Forward a copy to the Lead Engineer, Piping Analysis, PNED/DES.
OT-3701-G43_00 1_RO Rev 0


JOB PERFORMANCE MEASURE SETUP SHEET
OT-3701-G43_001_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:
 
G43 - Suppression Pool Makeup System Time Critical:
System: G43 -Suppression Pool Makeup System Time Critical: No Alternate Path: No Applicability: RO/SRO Safety Function: 5 -Containment Integrity Setting: Simulator Validated: 7minutes
No Alternate Path:
No Applicability:
RO/SRO Safety Function:
5 - Containment Integrity Setting:
Simulator Validated:
7 minutes


==References:==
==References:==
EOP-SPI 3.2 Rev 1 Tasks: 002-503- 05- 01 Initiate SPMU Task Standard: Initiate SPMU per EOP -SPI 3.2 Required Material: EOP-SPI 3.2, SPMU Initiation K / A Data: 295030 - Ability to operate and/or monitor the following as they apply to Low Suppression Pool Water Level : EA1.04Suppression pool make-up system: Mark-III. Importance: RO 4.0/ SRO 4.0
EOP-SPI 3.2 Rev 1 Tasks:
: 1. Setup Instructions: Reset simulator to a power IC. Insert Malfunctions PC04 to 35%,
002-503-05-01 Initiate SPMU Task Standard:
h13p60118ad3 to OFF, h13p60118e2 to ON, mv011e12f0001 to FAI, ry02_g43k1 to FAI, and ry02_g43k2 to FAI. Insert Remote Function LP03 to OUT. Place simulator in RUN and allow SP level to lower to < 17.8. Take a snapshot.( For 2017 ILO Exam, reset to IC no other actions needed)
Initiate SPMU per EOP-SPI 3.2 Required Material:
: 2. Location / Method: Simulato r / Perform
EOP-SPI 3.2, SPMU Initiation K / A Data:
: 3. Initial Condition: The P lant is at rated power. A leak in the LPCS Suppression Pool Suction line is causing Suppression Pool level to lower. All attempts to stop the leak have failed. The US has entered EOP -2 Primary Containment Control for lowering Suppression Pool level.
295030 - Ability to operate and/or monitor the following as they apply to Low Suppression Pool Water Level: EA1.04 Suppression pool make-up system: Mark-III. Importance: RO 4.0 / SRO 4.0
: 4. Initiating Cue: The Unit supervisor directs you the Reactor Operator to initiate SPMU per EOP -SPI 3.2.
: 1.
 
Setup Instructions: Reset simulator to a power IC. Insert Malfunctions PC04 to 35%,
Start Time: End Time:
h13p60118ad3 to OFF, h13p60118e2 to ON, mv011e12f0001 to FAI, ry02_g43k1 to FAI, and ry02_g43k2 to FAI. Insert Remote Function LP03 to OUT. Place simulator in RUN and allow SP level to lower to < 17.8. Take a snapshot. (For 2017 ILO Exam, reset to IC no other actions needed)
 
: 2.
Candidate:
Location / Method: Simulator / Perform
 
: 3.
OT-3701-G43_00 1_RO Rev 0
Initial Condition: The Plant is at rated power. A leak in the LPCS Suppression Pool Suction line is causing Suppression Pool level to lower. All attempts to stop the leak have failed. The US has entered EOP-2 Primary Containment Control for lowering Suppression Pool level.
 
: 4.
JPM BODY SHEET
Initiating Cue: The Unit supervisor directs you the Reactor Operator to initiate SPMU per EOP-SPI 3.2.
 
Start Time:
Standard: Performer obtains or simulates obtaining a ll materials, procedures, tools, keys, radi os, etc before performing task.
End Time:
Candidate:  


OT-3701-G43_001_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
Standard: Performer follows management expectations with regards to safety and communication standards.
Standard: Performer follows management expectations with regards to safety and communication standards.
 
Step 1 EOP-SPI 3.2, SPMU Initiation 1.0 VERIFY the following keylock switches are in AUTO:
Step 1
 
EOP-SPI 3.2, SPMU Initiation
 
1.0 VERIFY the following keylock switches are in AUTO:
* SUPR POOL MAKE-UP A LOGIC G43-S6
* SUPR POOL MAKE-UP A LOGIC G43-S6
* SUPR POOL MAKE-UP B LOGIC G43-S8
* SUPR POOL MAKE-UP B LOGIC G43-S8 Standard:
 
The Operator locates correct switches on H13-P601 and verifies in AUTO.
Standard: The Operator locates correct switches on H13-P601 and verifies in AUTO.
Instructor Cue:
 
None Notes:
Instructor Cue: None
None SAT ___
 
UNSAT ___
Notes: None SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Step 2 2.0 IF a LOCA signal is present, THEN GO TO Step 5.0 of this instruction.
Standard:
The Operator verifies no LOCA signal present and proceeds to Step 3.0.
Instructor Cue:
If asked, NO LOCA signal present.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Step 2
OT-3701-G43_001_RO Rev 0 Step 3 NOTE Placing SPMU test keylock switches in TEST with the SPMU mode switch in AUTO will automatically open SPMU shutoff valves when a Suppression Pool low-low level condition exists.
 
3.0 AT H13-P869, PLACE SUPR POOL MAKEUP A FULL FLW TEST PERM keylock switch in TEST.
2.0 IF a LOCA signal is present, THEN GO TO Step 5.0 of this instruction.
G43-S13 Critical Step:
 
Operator places G43-S13 in TEST.
Standard: The Operator verifies no LOCA signal present and proceeds to Step 3.0.
Instructor Cue:
 
None Notes:
Instructor Cue: If asked, NO LOCA signal present.
Switch G43-S13 is located on East wall of Simulator SAT ___
 
UNSAT ___
Notes: None SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Step 4 4.0 AT H13-P868, PLACE SUPR POOL MAKEUP B FULL FLW TEST PERM keylock switch in TEST.
G43-S12 Critical Step:
Operator places G43-S12 in TEST.
Instructor Cue:
None Notes:
Switch G43-S12 is located on East wall of Simulator SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


OT-3701-G43_00 1_RO Rev 0
OT-3701-G43_001_RO Rev 0 Step 5 5.0 PERFORM Steps 6.0 and 7.0 in any order with the priority being a division that has electric power readily available 6.0 IF required to Initiate Division 1 SPMU, THEN PERFORM the following:
 
6.1 IF AC power is lost to Division 1 480 Volt AC busses AND Bus EF-1-E-1 is energized, THEN REFER TO Division 3 To Division 1 480 Volt Crosstie, ONI-SPI C-6 concurrently with this procedure to apply power to Division 1 480 Volt AC busses.
Step 3
6.2 ARM AND DEPRESS the SUPR PL MAKE-UP A MANUAL INITIATION pushbutton.
 
G43-S5 Critical Step:
NOTE Placing SPMU test keylock switches in TEST with the SPMU mode switch in AUTO will automatically open SPMU shutoff valves when a Suppression Pool low -low level condition exists.
Operator Arms and Depresses G43-S5.
 
Instructor Cue:
3.0 AT H13-P869, PLACE SUPR POOL MAKEUP A FULL FLW TEST PERM keylock switch in TEST. G43-S13
None Notes:
 
Step 6.1 is N/A.
Critical Step: Operator places G43-S13 in TEST.
SAT ___
 
UNSAT ___
Instructor Cue: None
 
Notes: Switch G43-S13 is located on East wall of Simulator SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Step 4
4.0 AT H13-P868, PLACE SUPR POOL MAKEUP B FULL FLW TEST PERM keylock switch in TEST. G43-S12
Critical Step: Operator places G43-S12in TEST.
Instructor Cue: None
Notes: Switch G43-S12 is located on East wall of Simulator SAT ___ UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-G43_00 1_RO Rev 0
Step 5
5.0 PERFORM Steps 6.0 and 7.0 in any order with the prioritybeing a division that has electric power readily available
NOTES
NOTES
* Normally BOTH divisions of SPMU are initiated. If Division 2 SPMU is successful and alternate power is required to initiate Division 1 SPMU, then it is NOT required to initiate Division 1 SPMU as the SPMU would be completed prior to being able to complete the next step.
* Normally BOTH divisions of SPMU are initiated. If Division 2 SPMU is successful and alternate power is required to initiate Division 1 SPMU, then it is NOT required to initiate Division 1 SPMU as the SPMU would be completed prior to being able to complete the next step.
* Division 3 to Division 1 480 Volt Crosstie, ONI-SPI C-6 provides temporary power to Initiate Suppression Pool Makeup. When power is needed to a component the infield operator needs to be notified so actions to power the component can be completed.
* Division 3 to Division 1 480 Volt Crosstie, ONI-SPI C-6 provides temporary power to Initiate Suppression Pool Makeup. When power is needed to a component the infield operator needs to be notified so actions to power the component can be completed.  


6.0 IF required to Initiate Division 1 SPMU,THEN PERFORM the following:
OT-3701-G43_001_RO Rev 0 Step 6 6.3 CONFIRM the following valves are OPEN:
 
* SUPR PL MAKE-UP A FIRST SHUTOFF.
6.1 IF AC power is lost to Division 1 480 Volt AC busses AND Bus EF E-1 is energized,THEN REFER TO Division 3 To Division 1 480 Volt Crosstie, ONI-SP I C-6 concurrently with this procedure to apply power to Division 1 480 Volt AC busses.
G43-F030A
 
* SUPR PL MAKE-UP A SECOND SHUTOFF.
6.2 ARM AND DEPRESS the SUPR PL MAKE -UP A MANUAL INITIATION pushbutton. G43-S5
G43-F040A Standard:
 
The Operator confirms G43-F030A and G43-F040A open.
Critical Step: Operator Arms and Depress es G43 -S5.
Instructor Cue:
 
None Notes:
Instructor Cue: None
None SAT ___
 
UNSAT ___
Notes: Step 6.1 is N/A.
Comment(s): ________________________________________________________________
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701-G43_00 1_RO Rev 0
 
Step 6
 
6.3 CONFIRM the following valves are OPEN:
* SUPR PL MAKE-UP A FIRST SHUTOFF. G43-F030A
* SUPR PL MAKE-UP A SECOND SHUTOFF. G43-F040A
 
Standard: The Operator confirms G43-F030A and G43 -F040A open.
 
Instructor Cue: None
 
Notes: None SAT ___ UNSAT ___


OT-3701-G43_001_RO Rev 0 Step 7 7.0 IF required to Initiate Division 2 SPMU, THEN PERFORM the following:
7.1 IF AC power is lost to Division 2 480 Volt AC busses AND Bus EF-1-E-1 is energized, THEN REFER TO Division 3 To Division 2 480 Volt Crosstie, ONI-SPI C-7 concurrently with this procedure to apply power to Division 2 480 Volt AC busses.
7.2 ARM AND DEPRESS the SUPR PL MAKE-UP B MANUAL INITIATION pushbutton.
G43-S7 Critical Step:
Operator Arms and Depresses G43-S7.
Instructor Cue:
None Notes:
Step 7.1 is N/A.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
OT-3701-G43_00 1_RO Rev 0
Step 7
NOTES
NOTES
* Normally BOTH divisions of SPMU a re initiated. If Division 1 SPMU is successful and alternate power is required to initiate Division 2 SPMU, then it is NOT required to initiate Division 2 SPMU as the SPMU would be completed prior to being able to complete the next step.
* Normally BOTH divisions of SPMU are initiated. If Division 1 SPMU is successful and alternate power is required to initiate Division 2 SPMU, then it is NOT required to initiate Division 2 SPMU as the SPMU would be completed prior to being able to complete the next step.
* Division 3 to Division 2 480 Volt Crosstie, ONI-SPI C-7 provides temporary power to Initiate Suppression Pool Makeup. When power is needed to a component the infield operator needs to be notified so actions to power the component can be completed.
* Division 3 to Division 2 480 Volt Crosstie, ONI-SPI C-7 provides temporary power to Initiate Suppression Pool Makeup. When power is needed to a component the infield operator needs to be notified so actions to power the component can be completed.  


7.0 IF required to Initiate Division 2 SPMU,THEN PERFORM the following:
OT-3701-G43_001_RO Rev 0 Step 8 7.3 CONFIRM the following valves are OPEN:
7.1 IF AC power is lost to Division 2 480 Volt AC busses AND Bus EF E-1 is energized, THEN REFER TO Division 3 To Division 2 480 Volt Crosstie, ONI-SP I C-7 concurrently with this procedure to apply power to Division 2 480 Volt AC busses.
* SUPR PL MAKE-UP B FIRST SHUTOFF.
7.2 ARM AND DEPRESS the SUPR PL MAKE -UP B MANUAL INITIATION pushbutton. G43-S7
G43-F030B
* SUPR PL MAKE-UP B SECOND SHUTOFF.
G43-F040B Standard:
The Operator confirms the SPMU valves are open and that suppression pool level is rising.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Critical Step: Operator Arms and Depress es G43 -S7.
OT-3701-G43_001_RO Rev 0 Step 9 8.0 IF the CNTMT POOLS SUPP ISOL valve is OPEN, THEN ISOLATE flow to the upper Pools as follows: G41-F100 8.1 IF AC power is lost to Division 1 480 Volt AC busses AND Bus EF-1-E-1 is energized, THEN REFER TO Division 3 To Division 1 480 Volt Crosstie, ONI-SPI C-6 concurrently with this procedure to apply power to Division 1 480 Volt AC busses.
 
8.2 VERIFY CLOSED CNTMT POOLS SUPP ISOL.
Instructor Cue: None
G41-F100 Critical Step:
 
Operator closes G41-F100.
Notes: Step 7.1 is N/A.
Instructor Cue:
SAT ___ UNSAT ___
None Notes:
 
Step 8.1 is N/A.
Comment(s): ________________________________________________________________
 
OT-3701-G43_00 1_RO Rev 0
 
Step 8
 
7.3 CONFIRM the following valves are OPEN:
* SUPR PL MAKE-UP B FIRST SHUTOFF. G43-F030B
* SUPR PL MAKE-UP B SECOND SHUTOFF. G43-F040B
 
Standard: The Operator confirms the SPMU valves are open and that suppression pool level is rising.
 
Instructor Cue: None
 
Notes: None SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701-G43_00 1_RO Rev 0
 
Step 9
 
NOTE Division 3 to Division 1 480 Volt Crosstie, ONI-SPI C-6 provides temporary power to isolate flow to the upper pools. When power is needed to a component the infield operator needs to be notified so actions to power the component can be completed.
 
8.0 IF the CNTMT POOLS SUPP ISOL valve is OPEN, THEN ISOLATE flow to the upper Pools as follows: G41 -F100 8.1 IF AC power is lost to Division 1 480 Volt AC busses AND Bus EF E-1 is energized, THEN REFER TO Division 3 To Division 1 480 Volt Crosstie, ONI-SPI C -6 concurrently with this procedure to apply power to Division 1 480 Volt AC busses.
8.2 VERIFY CLOSED CNTMT POOLS SUPP ISOL. G41-F100
 
Critical Step: Operator closes G41 -F100.
 
Instructor Cue: None
 
Notes: Step 8.1 is N/A.
Terminate the JPM.
Terminate the JPM.
SAT ___ UNSAT ___
SAT ___
 
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
 
Terminating Cue: Reports to Unit Supervisor that EOP-SPI 3.2 is complete and SPMU is in progress.
Terminating Cue: Reports to Unit Supervisor that EOP -SPI 3.2 is complete and SPMU is in progress.
Evaluation Results:
 
SAT_____
Evaluation Results: SAT_____ UNSAT_____
UNSAT_____
 
End Time:
End Time:
NOTE Division 3 to Division 1 480 Volt Crosstie, ONI-SPI C-6 provides temporary power to isolate flow to the upper pools. When power is needed to a component the infield operator needs to be notified so actions to power the component can be completed.


OT-3701-G43_00 1_RO Rev 0
OT-3701-G43_001_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:
 
JPM CUE SHEET
 
IN IT IA L
* The Plant is at rated power.
* The Plant is at rated power.
CONDITIONS:
* A leak in the LPCS Suppression Pool Suction line is causing Suppression Pool level to lower.
* A leak in the LPCS Suppression Pool Suction line is causing Suppression Pool level to lower.
* All attempts to stop the leak have failed.
* All attempts to stop the leak have failed.
* The US has entered EOP-2 Primary Containment Control for lowering Suppression Pool level.
* The US has entered EOP-2 Primary Containment Control for lowering Suppression Pool level.
INITIATING CUE:
The Unit Supervisor directs you the Reactor Operator to initiate SPMU per EOP-SPI 3.2.


IN IT IA T ING CUE: The Unit Supervisor directs you the Reactor Operator to initiate SPMU per EOP-SPI 3.2.
OT-3701_M25_502 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:
 
M25/M26 Control Room Ventilation and Emergency Recirc System Time Critical:
OT-3701_M25_502 Rev 0
No Alternate Path:
 
Yes Applicability:
JOB PERFORMANCE MEASURE SETUP SHEET
RO/SRO Safety Function:
 
9 - Radioactivity Release Validated Time:
System: M25/M26 Control Room Ventilation and Emergency Recirc System Time Critical: No Alternate Path: Yes Applicability: RO/SRO Safety Function: 9-Radioactivity Release Validated Time : 19Minutes
19 Minutes


==References:==
==References:==
SOI-M25/26 Rev. 24, ARI-H13-P904- 0002Rev 1 1, NOP -OP-1002Rev 12, &
SOI-M25/26 Rev. 24, ARI-H13-P904-0002 Rev 11, NOP-OP-1002 Rev 12, &
Cyc-14 T/O EPY-M25- 005 Required Material: SOI-M25/26, Control Room HVAC And Emergency Recirculating System Task: 037-532- 01- 01 Shift from (Manual) EMERG RCIRC to NORM 037-524- 01- 01 Respond to Alarms Task Standard: Shift Control Room HVAC from Emergency Recircto NORMAL and respond to low flow alarm.
Cyc-14 T/O EPY-M25-005 Required Material:
K/A: 290003 -A2. 03 Ability to (a) predict the impacts of the following on the CONTROL ROOM HVAC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Initiation/reconfiguration failure. Importance: RO 3.4 SRO 3.6
SOI-M25/26, Control Room HVAC And Emergency Recirculating System Task:
: 1. Setup Instructions: Reset simulator to any IC with M25A running in ER and M25B S/D to Secured Status. (For 2017 ILO Exam, reset to IC 64) Insert Schedule file JPM-M25-502.sch and verify Event file JPM -M25-502.evt loads. A cknowledge alarms. Place a Yellow Switch Cap s on M25 B Supply Fanand M26 B Emergency Recirc Fan.Provide Operator with Yellow copy of SOI -
037-532-01-01 Shift from (Manual) EMERG RCIRC to NORM 037-524-01-01 Respond to Alarms Task Standard:
M25/26.
Shift Control Room HVAC from Emergency Recirc to NORMAL and respond to low flow alarm.
: 2. Location / Method: Simulator / Performance
K/A:
: 3. Initial Condition: Control Room Ventilation is running in Emergency Recirc for a monthly Div. 2 diesel run, which is now complete. CRHVAC Supply Fan B is tagged out to replace a broke n belt.
290003 - A2.03 Ability to (a) predict the impacts of the following on the CONTROL ROOM HVAC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Initiation/reconfiguration failure. Importance: RO 3.4 SRO 3.6
: 4. Initiating Cue: The Unit Supervisor directs you,the Reactor Operator,to shift Control Room Ventilation to NORMAL.
: 1.
 
Setup Instructions: Reset simulator to any IC with M25A running in ER and M25B S/D to Secured Status. (For 2017 ILO Exam, reset to IC 64) Insert Schedule file JPM-M25-502.sch and verify Event file JPM-M25-502.evt loads. Acknowledge alarms. Place a Yellow Switch Caps on M25 B Supply Fan and M26 B Emergency Recirc Fan. Provide Operator with Yellow copy of SOI-M25/26.
Start Time : Stop Time :
: 2.
 
Location / Method: Simulator / Performance
Candidate:
: 3.
 
Initial Condition: Control Room Ventilation is running in Emergency Recirc for a monthly Div. 2 diesel run, which is now complete. CR HVAC Supply Fan B is tagged out to replace a broken belt.
OT-3701_M25_502 Rev 0
: 4.
 
Initiating Cue: The Unit Supervisor directs you, the Reactor Operator, to shift Control Room Ventilation to NORMAL.
JPM BODY SHEET
Start Time:
 
Stop Time:
Standard: Performer obtains or simulates obtaining all mater ials, procedures, tools, keys, radios, etc before performing task.
Candidate:  


OT-3701_M25_502 Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
Standard: Performer follows management expectations with regards to safety and communication standards.
Standard: Performer follows management expectations with regards to safety and communication standards.
 
Step 1 SOI-M25/26, Control Room HVAC And Emergency Recirculating System 7.6 Shifting From EMERG RCIRC To NORM 7.6.1 IF the CONT RM HVAC A INBD SUPP DMPR is closed, THEN PERFORM Reset of Emergency Recirculation Auto Initiation.
Step 1
 
SOI-M25/26, Control Room HVAC And Emergency Recirculating System
 
7.6 Shifting From EMERG RCIRC To NORM
 
7.6.1 IF the CONT RM HVAC A INBD SUPP DMPR is closed, THEN PERFORM Reset of Emergency Recirculation Auto Initiation.
M25-F020B 7.6.2 IF the CONT RM HVAC B INBD SUPP DMPR is closed, THEN PERFORM Reset of Emergency Recirculation Auto Initiation.
M25-F020B 7.6.2 IF the CONT RM HVAC B INBD SUPP DMPR is closed, THEN PERFORM Reset of Emergency Recirculation Auto Initiation.
M25-F020A 7.6.3 IF the electric heater is in service, THEN PERFORM the following:
M25-F020A 7.6.3 IF the electric heater is in service, THEN PERFORM the following:
Standard:
Steps 7.6.1, 7.6.2, and 7.6.3 are N/A.
Instructor Cue:
None.
Notes:
None.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Standard: Steps 7.6.1, 7.6.2, and 7.6.3 are N/A.
OT-3701_M25_502 Rev 0 Step 2 7.6.4 PLACE both of the following in NORM:
 
* CONT RM HVAC TRAIN A MODE SELECT M25-S7
Instructor Cue: None.
* CONT RM HVAC TRAIN B MODE SELECT M25-S8 Critical Step:
 
Operator places M25-S7 in NORM.
Notes: None.
Instructor Cue:
 
None.
SAT ___ UNSAT ___
Notes:
 
Operator should place M25-S8 in NORM, as this causes multiple B side dampers to realign. However, with M25B train S/D, placing & M25-S8 in NORM will not have any effect and is not Critical.
About 60 seconds after placing S7 in NORM, CONT RM HVAC RETURN FAN A, M25-C002A will alarm on Low Flow.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Step 3 7.6.1 CONFIRM components are in the proper configuration in accordance with the appropriate attachment:
* Train A in Operation and Train B Shutdown (Attachment 5)
Standard:
Operator commences verifying component lineup.
Instructor Cue:
If asked to report positions of M24-F051A & F051B, - Both open.
Notes:
Return Fan low flow annunciator (P904-02-A1) will alarm while operator is verifying component lineup.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


OT-3701_M25_502 Rev 0
OT-3701_M25_502 Rev 0 Step 4 ARI-H13-P904-0002-A1 1.0 CAUSE OF ALARM 1.1 Flow through CONT RM HVAC RETURN FAN A, M25-C002A, less than 24,000 CFM, as sensed by M25-N700A, when fan is running 4.0 SUBSEQUENT OPERATOR ACTIONS 4.1 DETERMINE 0M25 flow.
 
M25-K120A 4.2 REFER TO SOI-M25/26 and SHIFT to HVAC Train B in the desired operating mode.
Step 2
Standard:
 
Operator reviews ARI and suggests course of action.
7.6.4 PLACE both of the following in NORM:
Instructor Cue:
* CONT RM HVAC TRAIN AMODE SELECT M25-S7
If Operator requests flow data from NLO, respond, Flow is 20,000 CFM.
* CONT RM HVAC TRAIN B MODE SELECT M25-S8
 
Critical Step: Operator places M25-S7 in NORM.
 
Instructor Cue: None.
 
Notes: Operator shouldplace M25 -S8 in NORM, as this causes multiple B side dampers to realign. However, w ith M25B train S/D, placing & M25-S8 in NORM will not have any effect and is not Critical.
 
About 60 seconds after placing S7 in NORM, CONT RM HVAC RETURN FAN A, M25 -C002A will alarm on Low Flow.
 
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
Step 3
 
7.6.1 CONFIRM components are in the proper configuration in accordance withthe appropriate attachment:
* Train A in Operation and Train B Shutdown(Attachment 5)
 
Standard: Operator commences verifying component lineup.
 
Instructor Cue: If asked to report positions of M24-F051A & F051B, - Both open.
 
Notes: Return Fan low flow annunciator ( P904- 02-A1) willalarm while operator is verifying component lineup.
 
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701_M25_502 Rev 0
 
Step 4
 
ARI-H13-P904- 0002-A1
 
1.0 CAUSE OF ALARM 1.1 Flow through CONT RM HVAC RETURN FAN A, M25-C002A, less than 24,000 CFM, as sensed byM25-N700A, when fan is running 4.0 SUBSEQUENT OPERATOR ACTIONS 4.1 DETERMINE 0M25 flow. M25-K120A 4.2 REFER TO SOI-M25/26 and SHIFT toHVAC Train B in the desired operatingmode.
 
Standard: Operator reviews ARI and suggests course of action.
 
Instructor Cue: If Operator requests flow data from NLO, respond, Flow is 20,000 CFM.
 
If Operator asks NLO about M25-F110A, report it does not appear to be full open.
If Operator asks NLO about M25-F110A, report it does not appear to be full open.
If Operator does not suggest a course of action, ask what they recommend.
Notes:
Per the ARI, the Operator should shift to the B train in the NORMAL mode. However, since B train Supply and Emergency Recirc fans are tagged out, the shift cannot occur. In this instance, shifting A train back to Emergency Recirc mode will solve the problem as ER Mode stops the Return Fan.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


If Operator does not suggest a course of action, ask wha t they recommend.
OT-3701_M25_502 Rev 0 Step 5 SOI-M25/26, Control Room HVAC And Emergency Recirculating System 7.5 Shifting From NORM Or SMOKE CLEAR To EMERG RCIRC 7.5.1 PLACE both of the following in EMERG RCIRC:
Notes: Per the ARI, the Operator should shift to the B train in the NORMAL mode. However, since B train Supply and Emergency Recirc fans are tagged out, the shift cannot occur. In this instance, shifting A train back to Emergency Recircmode will solve the problem as ER Mode stops the Return Fan.
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701_M25_502 Rev 0
 
Step 5
 
SOI-M25/26, Control Room HVAC And Emergency Recirculating System
 
7.5 Shifting From NORM Or SMOKE CLEAR To EMERG RCIRC
 
7.5.1 PLACE both of the following inEMERG RCIRC:
* CONT RM HVAC TRAIN A MODE SELECT M25-S7
* CONT RM HVAC TRAIN A MODE SELECT M25-S7
* CONT RM HVAC TRAIN B MODE SELECT M25-S8
* CONT RM HVAC TRAIN B MODE SELECT M25-S8 Critical Step:
 
Operator places M25-S7 in EMERG RCIRC.
Critical Step: Operator places M25-S7 in EMERG RCIRC.
Instructor Cue:
 
None Notes:
Instructor Cue: None
Operator should place M25-S8 in EMERG RECIRC, as this causes multiple B side dampers to realign. However, with M25B train S/D, placing & M25-S8 in EMERG RCIRC will not have any effect and is not Critical.
 
SAT ___
Notes: Operator shouldplace M25 -S8 in EMERG RECIRC, as this causes multiple B side dampers to realign. However, with M25B train S/D, placing & M25-S8 in EMERG RCIRCwill not have any effect and is not Critical.
UNSAT ___
 
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Step 6 7.5.2 CONFIRM components are in the proper configuration in accordance with the appropriate attachment:
* Train A in Operation and Train B Shutdown (Attachment 5)
Standard:
Operator commences verifying component lineup.
Instructor Cue:
If asked to report positions of M24-F051A & F051B, - Both Closed.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Step 6
OT-3701_M25_502 Rev 0 Step 7 ATTACHMENT 5 - Configuration with Train A in Operation and Train B Shutdown Train A Components M25-S7 & S8 Position NORM EMERG RCIRC SMOKE CLEAR CONT RM HVAC RETURN FAN A, M25-C002A ON OFF ON Critical Step:
 
Operator stops Return Fan A.
7.5.2 CONFIRM components are in the proper configuration in accordance withthe appropriate attachment:
Instructor Cue:
* Train A in Operation and Train B Shutdown(Attachment 5)
If Operator does not stop Return Fan A or doesnt suggest a course of action, ask what they recommend.
 
Standard: Operator commences verifying component lineup.
 
Instructor Cue: If asked to report positions of M24-F051A & F051B, - Both Closed.
 
Notes: None
 
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701_M25_502 Rev 0
 
Step 7
 
ATTACHMENT 5 - Config uration with Train A in Operation and Train B Shutdown
 
Train A Components M25-S7 & S8 Position NORM EMERG SMOKE RCIRC CLEAR CONT RM HVAC RETURN FAN A, M25-C002A ON OFF ON
 
Critical Step: Operator stops Return Fan A.
 
Instructor Cue: If Operator does not stop Return Fan A or doesnt suggest a course of action, ask what they recommend.
If Operator contacts NLO to ask if Return fan is still running, inform Operator that the Return fan is running.
If Operator contacts NLO to ask if Return fan is still running, inform Operator that the Return fan is running.
 
Notes:
Notes: During confirmation of components the operator should notice that the Return Fan failed to stop and M25-F110A damper is in mid-position and should inform evaluator that he is taking the fan control switch to STOP.
During confirmation of components the operator should notice that the Return Fan failed to stop and M25-F110A damper is in mid-position and should inform evaluator that he is taking the fan control switch to STOP.
 
Per NOP-OP-1002, Conduct of Operations, Step 4.10.3 Automatic System Response Versus Manual Actions:
Per NOP-OP-1002, Conduct of Operations, Step 4.10.3 Automatic System Response Versus Manual Actions:
: 5. If automatic actions fail to occur when required, it is the responsibility of the operator to take manual actions to perform the system or component function. Pump or component auto start failures are examples where operators are expected to take manual action.
: 5. If automatic actions fail to occur when required, it is the responsibility of the operator to take manual actions to perform the system or component function. Pump or component auto start failures are examples where operators are expected to take manual action.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


SAT ___ UNSAT ___
OT-3701_M25_502 Rev 0 Step 7 7.5.3 IF train is being shifted due to an emergency condition, THEN TAKE the following to CLOSE:
 
7.5.4 Control Room relative humidity is 70%
Comment(s): ________________________________________________________________
Control Room relative humidity is unknown TAKE the CONT RM EMG RCIRC ELEC HTG CONT to START.
 
M26-D001A M26-D001B Standard:
OT-3701_M25_502 Rev 0
Steps 7.5.3 and 7.5.4 are N/A.
 
Instructor Cue:
Step 7
None Notes:
 
Operator will check humidity on ICS.
7.5.3 IF train is being shifted due to anemergency condition,THEN TAKE the following to CLOSE:
Terminate the JPM SAT ___
 
UNSAT ___
7.5.4 Control Room Controom relative humidity retiveumidity is 70% is unknown TAKEhe CONT RMMGRC M - M -
ONT toR D D
 
Standard: Steps 7.5.3 and 7.5.4 are N/A.
 
Instructor Cue: None
 
Notes: Operator will check humidity on ICS.
 
Terminate the JPM
 
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Terminating Cue:
A Train of Control Room Ventilation is running in Emergency Recirc and Return Fan A is shutdown.
Evaluation Results:
SAT_____
UNSAT_____
End Time:


Terminating Cue: A Train of Control Room Ventilation is running in Emergency Recirc and Return Fan A is shutdown.
OT-3701_M25_502 Rev 0 JPM CUE SHEET INITIAL CONDITIONS:
 
* Control Room Ventilation is running in Emergency Recirc for a monthly Div. 2 diesel run, which is now complete.
Evaluation Results: SAT_____ UNSAT_____
 
End Time:
 
OT-3701_M25_502 Rev 0
 
JPM CUE SHEET
 
IN IT IA L
* Control Room Ventilation is running in Emergency Recirc for a monthly CONDITIONS: Div. 2 diesel run, which is now complete.
* CR HVAC Supply Fan B is tagged out to replace a broken belt.
* CR HVAC Supply Fan B is tagged out to replace a broken belt.
INITIATING CUE:
The Unit Supervisor directs you, the Reactor Operator, to shift Control Room Ventilation to NORMAL.


IN IT IA T ING CUE: The Unit Supervisor directs you,the Reactor Operator,to shift Control Room Ventilation to NORMAL.
OT-3701-D51_303_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:
 
D51 Seismic Monitoring System Time Critical:
OT-3701-D51_303_RO Rev 0
Yes Alternate Path:
 
No Applicability:
JOB PERFORMANCE MEASURE SETUP SHEET
RO/SRO Safety Function:
 
2 - Reactor Water Inventory Control Setting:
System: D51 Seismic Monitoring System Time Critical: Yes Alternate Path: No Applicability: RO/SRO Safety Function: 2-Reactor Water Inventory Control Setting: Plant (non-RRA)
Plant (non-RRA)
Validated Time: 25Minutes
Validated Time:
25 Minutes


==References:==
==References:==
ONI-D51 Rev 20 SOI-P72 Rev 9 Required Material ONI-D51 -Earthquake Attachment 3 Task: 029-502- 01- 04 Operate Plant Underdrain Pumps 276-504- 01- 01 Monitor the Service Water System Operation 277-508- 01- 01 Monitor ESW System Operation Task Standard: Perform outside inspection for earthquake damage and shutdown Underdrain Pumpper ONI -D51 Attachment 3.
ONI-D51 Rev 20 SOI-P72 Rev 9 Required Material ONI-D51 - Earthquake Attachment 3 Task:
K/AData: 203000Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: Injection Mode: -K6.10, Component cooling water systems IR 3.0 / 3.1.
029-502-01-04 Operate Plant Underdrain Pumps 276-504-01-01 Monitor the Service Water System Operation 277-508-01-01 Monitor ESW System Operation Task Standard:
219000 Ability to (a) predict the impacts of the following on the RHR/LPCI: Torus/Suppression Pool CoolingMode; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: -A2.15 Loss of, or inadequate, heat exchanger cooling flow IR 3.3/ 3.4
Perform outside inspection for earthquake damage and shutdown Underdrain Pump per ONI-D51 Attachment 3.
: 1. Setup Instructions: Provide Operator with a copy of ONI -D51 Attachment 3
K/A Data:
: 2. Location / Method: Plant / Simulation
203000 Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: Injection Mode: - K6.10, Component cooling water systems IR 3.0 / 3.1.
: 3. Initial Condition: OBE Earthquake has occurred; Five minutes ago, the Unit Supervisor entered ONI-D51.
219000 Ability to (a) predict the impacts of the following on the RHR/LPCI: Torus/Suppression Pool Cooling Mode; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: - A2.15 Loss of, or inadequate, heat exchanger cooling flow IR 3.3 / 3.4
: 4. Initiating Cue: The Unit Supervisor directs you as a Pla nt Operator to perform Attachment 3 of ONI-D51. This JPM is Time Critical
: 1.
Setup Instructions: Provide Operator with a copy of ONI-D51 Attachment 3
: 2.
Location / Method: Plant / Simulation
: 3.
Initial Condition: OBE Earthquake has occurred; Five minutes ago, the Unit Supervisor entered ONI-D51.
: 4.
Initiating Cue: The Unit Supervisor directs you as a Plant Operator to perform of ONI-D51. This JPM is Time Critical Start time End time Operator


Start time End time
OT-3701-D51_303_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
 
Standard: Performer follows management expectations with regards to safety and communication standards.
Operator
Step 1 ONI-D51 - Earthquake - Outside Actions 3.0 PROCEDURE 3.1 ESW Inspection 3.1.1 OBSERVE the following for possible indication of intake structure, intake tunnel or discharge tunnel damage:
 
OT-3701-D51_303_RO Rev 0
 
JPM BODY SHEET
 
Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
 
Standard: Performer follows management expectati ons with regards to safety and communication standards.
 
Step 1
 
ONI-D51 -Earthquake Attachment 3 - Outside Actions 3.0 PROCEDURE
 
NOTE The first ESW Inspection is required to be completed within 30 minutes of an OBE.
 
3.1 ESW Inspection 3.1.1 OBSERVE the following for possible indication of intake structure, intake tunnel or discharge tunnel damage:
* ESW forebay level
* ESW forebay level
* ESW forebay water clarity
* ESW forebay water clarity
* Discharge tunnel entrance water level
* Discharge tunnel entrance water level Critical Step:
 
Operator performs ESW inspection within 30 minutes.
Critical Step: Operator performs ESW inspection within 30 minutes.
Instructor Cue:
 
ESW Forebay level is approximately 1 foot lower than recorded on Rounds this morning. Other conditions are as-found Notes:
Instructor Cue: ESW Forebay level is approximately 1 foot lower than recorded on Rounds thismorning. Other conditions are as-found Notes: ESW forebay level gauge is under north steps in ESW pumphouse. ESW forebay inspection must be done north of the screens. Service Water Weir markings are in 1 foot increments. ( Water level is n ormally 18 t o 24 over the weir).
ESW forebay level gauge is under north steps in ESW pumphouse. ESW forebay inspection must be done north of the screens. Service Water Weir markings are in 1 foot increments. (Water level is normally 18 to 24 over the weir).
Operator should inform the Control Room when ESW inspection done.
Operator should inform the Control Room when ESW inspection done.
SAT ___ UNSAT ___
SAT ___
 
UNSAT ___
Comment(s): Time Complete for Time Critical Step ___________________
Comment(s): Time Complete for Time Critical Step ___________________
NOTE The first ESW Inspection is required to be completed within 30 minutes of an OBE.


OT-3701-D51_303_RO Rev 0
OT-3701-D51_303_RO Rev 0 Step 2 3.1.2 CONTACT Engineering if any indication of blockage is noted.
 
Step 2
 
3.1.2 CONTACT Engineering if any indication of blockage is noted.
3.1.3 REPEAT the inspection in Step 3.1.1 within 3 hours and once every 24 hours thereafter UNTIL Engineering has determined the inspections are no longer necessary.
3.1.3 REPEAT the inspection in Step 3.1.1 within 3 hours and once every 24 hours thereafter UNTIL Engineering has determined the inspections are no longer necessary.
 
Standard:
Standard: Operator contacts Engineering to report lower forebay level.
Operator contacts Engineering to report lower forebay level.
 
Instructor Cue:
Instructor Cue: Respond as Engineering
Respond as Engineering Notes:
 
None.
Notes: None.
SAT ___
SAT ___ UNSAT ___
UNSAT ___
 
Step 3 3.2 Underdrain Pump Shutdown 3.2.1 PERFORM the following:
Step 3
 
NOTE Underdrain Pumps, P72-C001E, is controlled from Underdrain Pump Local Control Station H51-P338E at Unit 1 Aux. Boiler Bldg. Elev. 620'.
 
3.2 Underdrain Pump Shutdown 3.2.1 PERFORM the following:
* VERIFY UNDERDRAIN PUMPS control switch in OFF P72-C001E
* VERIFY UNDERDRAIN PUMPS control switch in OFF P72-C001E
* VERIFY all Temporary Underdrain Pumps are shutdown at the local control panels.
* VERIFY all Temporary Underdrain Pumps are shutdown at the local control panels.
 
Critical Step:
Critical Step: Operator simulates placing the P72-C001E in OFF, and verifying all temporary underdrain pumps are shutdown.
Operator simulates placing the P72-C001E in OFF, and verifying all temporary underdrain pumps are shutdown.
 
Instructor Cue:
Instructor Cue:
* Initially, P72 -C001E is in AUTO.
* Initially, P72-C001E is in AUTO.
* P72-C001E Switch in OFF (when operator simulates placing in OFF)
* P72-C001E Switch in OFF (when operator simulates placing in OFF)
* Temporary underdrain pumps are shutdown.
* Temporary underdrain pumps are shutdown.
Notes: Terminate the JPM.
Notes:
 
Terminate the JPM.
SAT ___ UNSAT ___
SAT ___
 
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
NOTE Underdrain Pumps, P72-C001E, is controlled from Underdrain Pump Local Control Station H51-P338E at Unit 1 Aux. Boiler Bldg. Elev. 620'.


OT-3701-D51_303_RO Rev 0
OT-3701-D51_303_RO Rev 0 Terminating Cue: Operator completes ESW inspection within 30 minutes, and placed Underdrain Pump switch in OFF.
 
Evaluation Results: SAT_____
Terminating Cue: Operator completes ESW inspection within 30 minutes, and placed Underdrain Pump switch in OFF.
UNSAT_____
End time


Evaluation Results: SAT_____ UNSAT_____
OT-3701-D51_303_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:
* OBE Earthquake has occurred;
* Five minutes ago, the Unit Supervisor entered ONI-D51.
INITIATING CUE:
The Unit Supervisor directs you as a Plant Operator to perform Attachment 3 of ONI-D51.
This JPM is Time Critical


End time
OT-3701-P54_003_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:
 
Fire Protection Time Critical:
OT-3701-D51_303_RO Rev 0
No Alternate path:
 
No Applicability:
JPM CUE SHEET
RO/SRO Safety Function:
 
8 - Plant Service Systems Setting:
IN IT IA L
Plant (RRA)
* OBE Earthquake has occurred; CONDITIONS:
Validated:
* Five minutes ago, the Unit Supervisor entered ONI -D51.
28 minutes
 
IN IT IA T ING CUE: The Unit Supervisor directs you as a Pla nt Operator to perform Attachment 3 of ONI-D51.
This JPM is Time Critical
 
OT-3701-P54_003_RO Rev 0
 
JOB PERFORMANCE MEASURE SETUP SHEET
 
System: Fire Protection Time Critical: No Alternate path: No Applicability: RO/SRO Safety Function: 8 - Plant Service Systems Setting: Plant (RRA)
Validated: 28minutes


==References:==
==References:==
SOI-P54 (WTR) Rev 23 Task Standard: Initiate Deluge manually on Main Transformer C and Isophase Bus Duct per SOI -P54(WTR)
SOI-P54 (WTR) Rev 23 Task Standard:
Task #: 286-511- 04- 04 Perform Manual Initiation of Transformer, Isophase Bus Duct, or Hydrogen Seal Oil Deluge System Required Material: SOI-P54 (WTR), Fire Pr otection System -Water Section 7.2 K / A Data: 600000 AK1.02 Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Fighting 2.9 / 3.1 AA1.08Ability to operate and / or monitor the following as they apply to Pla nt Fire On Site:Fire fighting equipment used on each class of fire 2.6 / 2.9
Initiate Deluge manually on Main Transformer C and Isophase Bus Duct per SOI-P54(WTR)
: 1. Setup Instructions: When operator requests, provide operator with copy of SOI -
Task #:
P54(WTR).
286-511-04-04 Perform Manual Initiation of Transformer, Isophase Bus Duct, or Hydrogen Seal Oil Deluge System Required Material:
: 2. Location / Method: Plant / Simulation
SOI-P54 (WTR), Fire Protection System - Water Section 7.2 K / A Data:
: 3. Initial Condition: A fire has been r eported in C phase of the Main Transformer. The US has entered ONI-P54, FIRE. The Main Transformers and main generator have been deenergized.
600000 AK1.02 Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Fighting 2.9 / 3.1 AA1.08 Ability to operate and / or monitor the following as they apply to Plant Fire On Site: Firefighting equipment used on each class of fire 2.6 / 2.9
: 4. Initiating Cue: The Unit Supervisor directs you as the Field Supervisor to initiate deluge on the C Main Transformer.
: 1.
Setup Instructions: When operator requests, provide operator with copy of SOI-P54(WTR).
: 2.
Location / Method: Plant / Simulation
: 3.
Initial Condition: A fire has been reported in C phase of the Main Transformer. The US has entered ONI-P54, FIRE. The Main Transformers and main generator have been deenergized.
: 4.
Initiating Cue: The Unit Supervisor directs you as the Field Supervisor to initiate deluge on the C Main Transformer.
Start Time:
End Time:
Candidate:


Start Time: End Time:
OT-3701-P54_003_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.
 
Standard: Performer follows management expectations with regards to safety and communication standards.
Candidate:
Step 1 SOI-P54(WTR), FIRE PROTECTION SYSTEM - WATER 2.0 PRECAUTIONS AND LIMITATIONS 2.5 When any Main Transformer Deluge System is initiated for the purpose of combating a fire, the Isophase Bus Duct Deluge shall also be initiated.
 
OT-3701-P54_003_RO Rev 0
 
JPM BODY SHEET
 
Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing t ask.
 
Standard: Performer follows management expectati ons with regards to safety and communication standards.
 
Step 1
 
SOI-P54(WTR), FIRE PROTECTION SYSTEM - WATER
 
2.0 PRECAUTIONS AND LIMITATIONS
 
2.5 When any Main Transformer Deluge System is initiated for the purpose of combating a fire, the Isophase Bus Duct Deluge shall also be initiated.
2.16 The Deluge Systems of the three Main Transformers AND two Startup Transformers shall be aligned to support manual initiation only.
2.16 The Deluge Systems of the three Main Transformers AND two Startup Transformers shall be aligned to support manual initiation only.
Standard:
The Operator reviews SOI-P54(WTR) and determines deluge must be manually initiated.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Standard: The Operator reviews SOI-P54(WTR) and determines deluge must be manually initiated.
OT-3701-P54_003_RO Rev 0 Step 2 7.2 Emergency/Manual Deluge Initiation (Transformer, Isophase Bus Duct, and Hydrogen Seal Oil)
 
Standard:
Instructor Cue: None
The Operator determines that the Isophase Bus Duct Deluge shall also be initiated.
 
Instructor Cue:
Notes: None SAT ___ UNSAT ___
None Notes:
 
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
OT-3701-P54_003_RO Rev 0
Step 2
7.2 Emergency/Manual Deluge Initiation (Transformer, Isophase Bus Duct, and Hydrogen Seal Oil)
NOTES
NOTES
* Attachment 14 contains a li sting of the components used in this section.
* Attachment 14 contains a listing of the components used in this section.
* The following section may be performed by the Fire Brigade, Fire Protection Personnel, Operators or other individuals as required.
* The following section may be performed by the Fire Brigade, Fire Protection Personnel, Operators or other individuals as required.
* When any Main Transformer Deluge System is initiated for the purpose of combati ng a fire, the Isophase Bus Duct Deluge shall also be initiated.
* When any Main Transformer Deluge System is initiated for the purpose of combating a fire, the Isophase Bus Duct Deluge shall also be initiated.  
 
Standard: The Operator determines that the Isophase Bus Duct Deluge shall also be initiated.
 
Instructor Cue: None
 
Notes: None SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701-P54_003_RO Rev 0
 
Step 2
 
7.2.1 VERIFY OPEN the (C Main Transformer deluge ) system SupplyIsolation Valve.
1P54-F900
 
Critical Step: Operator refers to Attachment 14to obtain correct valve number and simulates opening the C Ma in Transformer Supply Isolation valve.


OT-3701-P54_003_RO Rev 0 Step 2 7.2.1 VERIFY OPEN the (C Main Transformer deluge) system Supply Isolation Valve.
1P54-F900 Critical Step:
Operator refers to Attachment 14 to obtain correct valve number and simulates opening the C Main Transformer Supply Isolation valve.
Instructor Cue:
Instructor Cue:
* As Operator is opening valve, The Supply Isolation Valve stem is extending.
* As Operator is opening valve, The Supply Isolation Valve stem is extending.
* The Supply Isolation Valve is Open.
* The Supply Isolation Valve is Open.
* If asked, no flow noise is heard.
* If asked, no flow noise is heard.
 
Notes:
Notes: None SAT ___ UNSAT ___
None SAT ___
 
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Step 3 7.2.2 OPEN the (C Main Transformer) Manual Initiation Valve door at the associated deluge valve.
1P54-F904 Standard:
Operator simulates breaking door seal and simulates opening Manual Initiation Valve door.
Instructor Cue:
None Notes:
When operator simulates opening valve door, show picture #1 of Manual Initiation Valve.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Step 3
OT-3701-P54_003_RO Rev 0 Step 4 7.2.3 PULL the (C Main Transformer) valve forward.
 
1P54-F904 Critical Step:
7.2.2 OPEN the ( C Main Transformer) Manual Initiation Valve door at the associated deluge valve.
Operator refers to Attachment 14 to obtain correct valve number and simulates opening the C Main Transformer Manual Initiation valve.
1P54-F904
 
Standard: Operator simulates breaking door seal and simulates opening Man ual Initiation Valve door.
 
Instructor Cue: None
 
Notes: When operator simulates opening valve door, show picture #1of Manual Initiation Valve.
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
 
OT-3701-P54_003_RO Rev 0
 
Step 4
 
7.2.3 PULL the ( C Main Transformer) valve forward.
1P54-F904
 
Critical Step: Operator refers to Attachment 14to obtain correct valve number and simulates opening the C Main Transformer Manual Initiation valve.
 
Instructor Cue:
Instructor Cue:
* The Manual Initiation Valve is Open.
* The Manual Initiation Valve is Open.
* If asked, flow noise is heard when BOTH the Supply Isolation and the Manual Initiation Valves are opened.
* If asked, flow noise is heard when BOTH the Supply Isolation and the Manual Initiation Valves are opened.
 
Notes:
Notes: When operator identifies Manual Initiation Valve enclosure, show Picture #1 of Manual Initiation Valve.
When operator identifies Manual Initiation Valve enclosure, show Picture #1 of Manual Initiation Valve.
SAT ___ UNSAT ___
SAT ___
 
UNSAT ___
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
 
Step 5 7.2.1 VERIFY OPEN the (Isophase Bus Duct deluge) system Supply Isolation Valve.
Step 5
1P54-F1460 Critical Step:
 
Operator refers to Attachment 14 to obtain correct valve number and simulates opening the Isophase Bus Duct Supply Isolation valve.
7.2.1 VERIFY OPEN the (Isophase Bus Duct deluge ) system SupplyIsolation Valve.
1P54-F1460
 
Critical Step: Operator refers to Attachment 14 to obtain correct valve number and simulates opening the Isophase Bus Duct Su pply Isolation valve.
 
Instructor Cue:
Instructor Cue:
* As Operator is opening valve, The Supply Isolation Valve stem is extending.
* As Operator is opening valve, The Supply Isolation Valve stem is extending.
* The Supply Isolation Valve is Open.
* The Supply Isolation Valve is Open.
* If asked, no flow noise is heard.
* If asked, no flow noise is heard.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Notes: None SAT ___ UNSAT ___
OT-3701-P54_003_RO Rev 0 Step 6 7.2.2 OPEN the (Isophase Bus Duct) Manual Initiation Valve door at the associated deluge valve.
 
Standard:
Comment(s): ________________________________________________________________
Operator simulates breaking door seal and simulates opening Manual Initiation Valve door.
 
Instructor Cue:
OT-3701-P54_003_RO Rev 0
None Notes:
 
When operator simulates opening valve door, show picture #2 of Manual Initiation Valve.
Step 6
SAT ___
 
UNSAT ___
7.2.2 OPEN the ( Isophase Bus Duct) Manual Initiation Valve door at the associated deluge valve.
 
Standard: Operator simulates breaking door seal and simulates opening Manual Initiation Valve door.
 
Instructor Cue: None
 
Notes: When operator simulates opening valve door, show picture #2of Manual Initiation Valve.
SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
 
Step 7 7.2.3 PULL the (Isophase Bus Duct) valve forward.
Step 7
1P54-F1464 Critical Step:
 
Operator refers to Attachment 14 to obtain correct valve number and simulates opening the Isophase Bus Duct Manual Initiation valve.
7.2.3 PULL the ( Isophase Bus Duct) valve forward.
1P54-F1464
 
Critical Step: Operator refers to Attachment 14to obtain correct valve number and simulates opening the Isophase Bus Duct Manual Initiation valve.
 
Instructor Cue:
Instructor Cue:
* The Manual Initiation Valve is Open.
* The Manual Initiation Valve is Open.
* If asked, flow noise is heard when BOTH the Supply Isolation and the Manual Initiation Valves are opened.
* If asked, flow noise is heard when BOTH the Supply Isolation and the Manual Initiation Valves are opened.
Notes:
When operator identifies Manual Initiation Valve enclosure, show Picture #2 of Manual Initiation Valve.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________


Notes: When operator identifies Manual Initiation Valve enclosure, show Picture #2 of Manual Initiation Val ve.
OT-3701-P54_003_RO Rev 0 Step 8 7.2.4 IF Manual-Electric Initiation is desired, THEN BREAK the glass on the Manual Release Station for the associated deluge system.
SAT ___ UNSAT ___
Standard:
 
Step 7.2.4 is N/A as Manual-Electric Initiation is not available.
Comment(s): ________________________________________________________________
Instructor Cue:
 
None Notes:
OT-3701-P54_003_RO Rev 0
Terminate JPM SAT ___
 
UNSAT ___
Step 8
 
7.2.4 IF Manual-Electric Initiation is desired, THEN BREAK the glass on the Manual Release Station for the associated deluge system.
 
Standard : Step 7.2.4 is N/A as Manual -Electric Initiation is not available.
 
Instructor Cue: None
 
Notes: Terminate JPM SAT ___ UNSAT ___
 
Comment(s): ________________________________________________________________
Comment(s): ________________________________________________________________
Terminating Cue: Manual deluge on Main Transformer C and the Isophase Bus Duct has been initiated per SOI-P54 section 7.2.
Evaluation Results:
SAT_____
UNSAT_____
End Time


Terminating Cue: Manual deluge on Main Transformer C and the Isophase Bus Duct has been initiated per SOI -P54 section 7.2.
OT-3701-P54_003_RO Rev 0 Picture # 1


Evaluation Results: SAT_____ UNSAT_____
OT-3701-P54_003_RO Rev 0 Picture # 2


End Time
OT-3701-P54_003_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:
 
OT-3701-P54_003_RO Rev 0
 
Picture # 1
 
OT-3701-P54_003_RO Rev 0 Picture # 2
 
OT-3701-P54_003_RO Rev 0
 
JPM CUE SHEET
 
IN IT IA L
* A fire has been reported in C phase of the Main Transformer.
* A fire has been reported in C phase of the Main Transformer.
CONDITIONS:
* The US has entered ONI-P54, FIRE.
* The US has entered ONI-P54, FIRE.
* The Main Transformers and main generator have been deenergized.
* The Main Transformers and main generator have been deenergized.
 
INITIATING CUE:
IN IT IA T ING CUE: The Unit Supervisor directs you as the Field Supervisor to initiate deluge on the C Main Transformer.
The Unit Supervisor directs you as the Field Supervisor to initiate deluge on the C Main Transformer.}}
 
- 10 -}}

Latest revision as of 16:56, 27 November 2024

2017 Perry Retake Exam Administered Simulator and In-Plant JPMs
ML22146A083
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 07/18/2017
From: Randy Baker
NRC/RGN-III/DRS/OLB
To:
Baker R
Shared Package
ML17142A161 List:
References
Download: ML22146A083 (93)
v • d • e


Text

OT-3701-E12_506_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:

E12, Residual Heat Removal Time Critical:

No Alternate Path:

Yes Applicability:

RO Safety Function:

4 - Heat Removal From The Core Setting:

Simulator Validated:

36 minutes

References:

SOI-E12 Rev. 71 & ONI-E12-2 Rev. 38 Required Material SOI-E12 - Residual Heat Removal System Tasks:

205-535-01-01 Warmup and Initiate Shutdown Cooling from Standby Readiness Task Standard:

Initiate SDC in Alternate Return Path mode prior to exceeding 200° F in vessel.

K/A Data:

205000 Ability to (a) predict the impacts of the following on the Shutdown Cooling System (RHR Shutdown Cooling Mode); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.06 SDC/RHR pump trips.

Importance RO 3.4 / SRO 3.5. A2.10 R Valve operation. Importance: RO 2.9 SRO 2.9 Ability to manually operate and/or monitor in the control room: A4.01 SDC/RHR pumps Importance RO 3.7 / SRO 3.7. A4.03 SDC/RHR discharge valves Importance RO 3.6 / SRO 3.5. A4.09 System flow. Importance RO 3.1 / SRO 3.1

OT-3701-E12_506_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET contd.

1.

Simulator Setup Instructions: Reset simulator to a shutdown IC with RPV temperature about 160°. Insert malfunctions mv06_1e12f0053a & cb01_1e12C0002b for F053A failure and RHR B pump breaker trip. Set decay heat level to obtain a H/U rate of ~

40°/hr (~8.83E6 watts). Maintain reactor vessel level between 260 and 270 inches using G33 blowdown. Simulator driver to control vessel level. Complete necessary portions of SOI-E12 Sect 4.7 through Step 4.7.18. Provide marked-up copy of SOI-E12. For 2017 ILO: Reset simulator to IC 68. Load schedule E12-506. Place simulator in freeze.

Place simulator in run after reading Initial Conditions to Operator. Remove 2 from SOI and give to Evaluator.

2.

Location / Method: Simulator / performance

3.

Initial Condition: The plant shutdown due to scram yesterday. Currently in Mode 4 and the Unit Supervisor is operating in IOI-12, Maintaining Cold Shutdown. RHR B was operating in Shutdown Cooling when the pump tripped 20 minutes ago. The Unit Supervisor has entered ONI-E12-2 Loss of Decay Heat Removal. Reactor Recirculation pumps are in operation. Reactor temperature band is 135 to 145° F. RPV temperature was 140° F prior to trip. Current RPV temperature is ~160° F. The RO shifting SDC loops became ill.

4.

Initiating Cue: The Unit Supervisor directs you the Reactor Operator to continue shifting Shutdown Cooling loops from B to A using RHR A through the Normal Return Path.

Section 4.7 Shutdown Cooling Startup for RHR A is complete through Step 4.7.18.

Monitor Reactor Temperature per IOI-12.

Start Time:

End Time:

Operator:

OT-3701-E12_506_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SOI-E12, RESIDUAL HEAT REMOVAL SYSTEM 2.0 Precautions And Limitations 2.2 Observe the following limitations during the operation of the RHR pumps:

  • Do not operate the RHR pump against a shutoff head for greater than 8 seconds.

2.6 Operation of the LPCI mode of RHR with injection flow to the vessel shall only be done in an accident condition, a plant emergency condition, or an approved test condition of short duration. ONI-E12-2, Loss of Decay Heat Removal, and IOI-11, Shutdown From Outside Control Room, direct the use of the LPCI injection lines as Alternate Shutdown Cooling flow paths. Use of this flow path is still subject to reportability (as described in PAP-1604) when used for Alternate Shutdown Cooling.

4.7 Shutdown Cooling Startup for RHR A(B)

Operator reviews place-kept copy of SOI-E12 including Precautions and Limitations and panel H13-P601.

Standard:

The Operator reviews place-kept copy of SOI-E12 Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 2 4.7.19 Hold the Oncoming RJR HXS BYPASS VALVE in CLOSE for 59-62 seconds.

1E12-F048A Critical Step:

The Operator closes 1E12-F048A for 59-62 seconds.

Instructor Cue:

None Notes:

If the Operator fails to close the valve inside this time band, this Critical Step can be recovered in JPM Step 9.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 3 4.7.20 Hold the Oncoming RHR HXS OUTLET VALVE in CLOSE until closed.

1E12-F003A Critical Step:

The Operator closes 1E12-F003A.

Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 4 4.7.21 It is desired to establish the Normal Return Path 1E12-F053A 1E12-F053B RHR Upper Pool Cooling Isol is closed 1E12-F037A 1E12-F037B LPCI Injection Valve is closed 1E12-F042A 1E12-F042B THEN PERFORM the following:

4.7.21.a IF the Feedwater System is shutdown, THEN VERIFY the Oncoming RHR loop FDW HDR SHUTOFF is closed, to prevent flow to the feedwater system.

1B21-F065A 1B21-F065B Standard:

The Operator observes that feedwater is shutdown and the B21-F065s are closed.

Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 5 CAUTIONS

  • The RHR PUMP MIN FLOW VALVE is downpowered in the closed position. Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.
  • Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

4.7.21.b INITIATE flow through the SHUTDOWN COOLING TO FDW SHUTOFF as follows:

1E12-F053A 4.7.21.b.1 PERFORM the following simultaneously:

1E12-F053A

  • TAKE the RHR PUMP to START.

1E12-C002A 4.7.21.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.

Standard The Operator starts to open 1E12-F053A and starts RHR A pump.

Critical Step:

If the operator starts the RHR pump, he must shut it down.

Instructor Cue:

If necessary, after report of valve failure, if pump was started, question operator on a course of action.

Direct Operator to establish shutdown cooling.

Notes:

Operator may or may not start pump if he notices failure of 1E12-F053A.

1E12-F053A is failed closed and will lose indication simulating blown fuse. If Operator started pump, the Minimum Flow Valve was down-powered per step 4.7.10.c and the pump will not have minimum flow protection.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 6 4.7.22 It is desired to establish the Refuel Return Path 1E12-F037A 1E12-F037B Operator determines that this step is N/A.

Standard:

This Step is N/A. The Operator cannot use Refuel Mode Path.

Instructor Cue:

None Notes:

Plant not in Mode 5, Vessel Head installed.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 7 CAUTION Operation of the RHR Loop with Vessel Injection via the LPCI Injection Line has the potential to result in fatigue failure of incore instrument tubes and burnishing of fuel channels.

The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.

Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.

Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

4.7.23 It is desired to establish the Alternate Return Path 1E12-F042A 1E12-F042B Normal Shutdown Cooling return path is unavailable 1E12-F053A 1E12-F053B Refuel Shutdown Cooling return path is unavailable 1E12-F037A 1E12-F037B THEN PERFORM the following:

4.7.23.a REFER TO Alternate Shutdown Cooling Data (Attachment 42) and TAKE Pre-Start Data.

Standard:

The Operator requests/obtains/completes Attachment 42.

Instructor Cue:

None Notes:

When Operator goes to green book to obtain Att-42, provide him with a Yellow copy of Attachment 42.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 8 CAUTIONS

  • The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.

Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.

  • Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

4.7.23.b INITIATE flow through the LPCI INJECTION VALVE as follows:

1E12-F042A 4.7.23.b.1 PERFORM the following simultaneously:

  • TAKE the LPCI INJECTION VALVE to OPEN.

1E12-F042A

  • TAKE the RHR PUMP to START.

1E12-C002A Critical Step:

The Operator takes 1E12-F042A to OPEN and starts RHR A pump.

Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 9 4.7.23.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.

1E12-F048A 1E12-R603A 4.7.23.c JOG OPEN the RHR HXS BYPASS VALVE in 1000-2000 gpm increments, UNTIL RHR PUMP FLOW is 2575-7100 gpm.

1E12-F048A 1E12-R603A Critical Step:

Within 8 seconds the Operator opens 1E12-F048A until flow is > 2575 gpm then controls flow within directed band.

Instructor Cue:

Reactor coolant temperature band is 135 to 145 deg F Notes:

If JPM Step 2 was performed correctly, this Step is not Critical.

Reactor coolant temperature should be between 165 and 180 degrees if Operator establishes flow with some urgency. If Operator delays and spends time reviewing the procedure, Reactor temperature could be as high as 190 degrees. Initial flow will be 3500 gpm. Temperature indication will be RHR Out on SPDS or Point 5 on recorder with E12-F003A closed.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 10 4.7.23.d NOTIFY the following of the use of the Shutdown Cooling return flow to the Vessel via LPCI INJECTION VALVE so the required fuel inspection may be scheduled:

  • Reactor Engineering.
  • Outage Planning.

4.7.23.e INITIATE a special report to the NRC in accordance with NOP-OP-1015, Event Notifications.

4.7.23.f GO TO RHR Shutdown Cooling Operations for RHR A(B).

Standard:

The Operator will proceed to Section 7.6, RHR Shutdown Cooling Operations for RHR A(B).

Instructor Cue:

Steps 4.7.23.d & e are being performed by the Shift Manager.

Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 11 7.6 RHR Shutdown Cooling Operations for RHR A(B)

NOTES Normal Design parameters for Shutdown Cooling/Test Mode operation:

RHR Pump Flow 7000-7100 gpm.

RHR Pump Amps95-110 Amps.

RHR A Head Spray Flow 0 - 500 gpm.

RHR Suction Pressure Less than 135 psig.

RHR HX ESW Outlet Temps Less than 108oF.

RHR Pump Suct Temp Less than 100oF (Refuel Mode).

RHR HXS RHR Outlet Temp Less than 86oF (Refuel Mode).

The following actions can be performed in any logical order or repeated to support current plant conditions.

Step 11 - Continued next page

OT-3701-E12_506_RO Rev 0 Step 11 - Continued 7.6.1 OBSERVE the following limitations when in Shutdown Cooling:

  • MAINTAIN cooldown rate less than 100oF in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
  • DO NOT allow any RHR piping which has been inadvertently drained to be refilled with water from the Reactor Vessel.
  • WHEN using the normal OR refuel mode return paths, THEN MAINTAIN the following:
  • MAINTAIN RHR Pump flow at 7000-7100 gpm during steady state conditions.
  • MAINTAIN RHR Pump flow at 6000-7100 gpm during system adjustments.
  • WHEN using the alternate return path, THEN MONITOR the following additional items:
  • MAINTAIN RHR H2O DISCH temperature greater than 65°F. 1E12-R601 Pt 5

Standard:

The Operator establishes flow of 2575-7100 gpm.

Instructor Cue:

None Notes:

Reactor temperature will increase steadily if cooling is not established.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-E12_506_RO Rev 0 Step 12 7.6.2 PERFORM the following as needed to maintain desired cooldown rate AND RHR Pump flow 7000-7100 (alternate return path 2575-7100):

1E12-R603A 1E12-R603B:

  • THROTTLE RHR HXS OUTLET VALVE.

1E12-F003A

  • THROTTLE RHR HXS BYPASS VALVE.

1E12-F048A Critical Step:

The Operator throttles opens 1E12-F003A and 1E12-F048A is throttled close to establish a cooldown.

Instructor Cue:

Establish a cooldown to restore temperature within band of 135 to 145 degrees.

Notes:

Exceeding 200 degrees Reactor Water temperature would be a failure.

200 degrees is a MODE change.

Operator can establish full cooling and not have a problem with 100 degrees per hour.

Terminate JPM once satisfied with cooldown rate.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Shutdown Cooling Flow established through Alternate Return path, a cooldown rate has been established and Reactor Water Temperature is maintained less than 200 degrees.

Evaluation Results:

SAT_____

UNSAT_____

End Time

OT-3701-E12_506_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

  • The plant shutdown due to scram yesterday.
  • Currently in Mode 4 and the Unit Supervisor is operating in IOI-12 Maintaining Cold Shutdown.
  • Reactor temperature band is 135 to 145 degrees F.
  • RPV temperature was 140 degrees F prior to trip.
  • Current RPV temperature is 160° F.
  • The RO shifting SDC loops became ill.

INITIATING CUE:

  • The Unit Supervisor directs you the Reactor operator to continue shifting Shutdown Cooling loops from B to A using RHR A through the Normal Return Path. Section 4.7
  • Monitor Reactor Temperature per IOI-12.

PERRY NUCLEAR POWER PLANT Instruction Number:

SOI-E12

Title:

RESIDUAL HEAT REMOVAL SYSTEM Use Category:

In-Field Reference Revision:

71 Page:

1 of 346 RESIDUAL HEAT REMOVAL SYSTEM Effective Date:

5-2-17 Preparer:

Michael Garnett

/ 4-4-17 Date Approver:

Ed Condo

/ 4-6-17 Date Working Copy - Verified Today

PERRY NUCLEAR POWER PLANT Instruction Number:

SOI-E12

Title:

RESIDUAL HEAT REMOVAL SYSTEM Use Category:

In-Field Reference Revision:

71 Page:

2 of 346 TABLE OF CONTENTS PAGE 1.0

SCOPE 7

2.0

PRECAUTIONS AND LIMITATIONS 7

3.0

PREREQUISITES 14

4.0

STARTUP 15

4.1

Startup to Standby 15

4.2

LPCI Automatic Initiation 22

4.3

LPCI Manual Pushbutton Initiation 25

4.4

LPCI Manual Startup 26

4.5

Containment Spray Automatic Initiation 28

4.6

Startup for RHR A(B) for Suppression Pool Cooling/Test Mode Operation or Suppression Pool Pumpdown to Radwaste 30

4.7

Shutdown Cooling Startup for RHR A(B) 33

4.8

RHR Loop C Flush/Test Mode Startup 50

4.9

Alternate Keep Fill Startup 53

4.10

Fuel Pool Cooling Assist Startup 55

4.11

Water Leg Pump Startup 59

4.12

Placing RHR Conductivity Alarm In Service 64

5.0

NORMAL OPERATIONS/DATA 65

6.0

SHUTDOWN 66

6.1

LPCI Shutdown to Standby Readiness 66

6.2

Suppression Pool Cooling/Test Mode Shutdown to Standby Readiness for RHR A(B) 68

6.3

Shutdown Cooling Shutdown to Standby Readiness for RHR A(B) 70

6.4

Shutdown from Standby Readiness to Secured Status 77

6.5

RHR Loop C Test Mode Shutdown to Standby Readiness 80

6.6

Fuel Pool Cooling Assist Shutdown 81

6.7

Alternate Keep Fill Shutdown 84

6.8

Removing RHR Conductivity Alarm From Service 87

7.0

SYSTEM OPERATIONS 88

7.1

LPCI Operations 88

7.2

Suppression Pool Cooling/Test Mode Operations for RHR A(B) 91

7.3

Suppression Pool Pumpdown to Radwaste 96

7.4

Raising Suppression Pool Level Using Condensate Transfer and Storage Water with RHR in Suppression Pool Cooling 99

7.5

Shifting Shutdown Cooling From Loop A(B) to Loop B(A) 100

7.6

RHR Shutdown Cooling Operations for RHR A(B) 101

7.7

Fill and Vent of RHR A(B,C) 117

7.8

Fill and Vent of RHR Prerequisites 120

PERRY NUCLEAR POWER PLANT Instruction Number:

SOI-E12 Section 1.0

Title:

RESIDUAL HEAT REMOVAL SYSTEM Use Category:

In-Field Reference Revision:

71 Page:

7 of 346 1.0 SCOPE This instruction provides the detailed operating instructions for the Residual Heat Removal (RHR) System.

2.0 PRECAUTIONS AND LIMITATIONS 2.1 Portions of this system are covered by Technical Specifications; these include the equipment and controls necessary to support RHR system operation in the following modes:

x Low Pressure Coolant Injection (LPCI) x Containment Spray x

Suppression Pool Cooling x

Shutdown Cooling Also, this system has controls which are related to T.S. 3.3.3.2, Remote Shutdown System.

2.2 Observe the following limitations during the operation of the RHR pumps:

x Do NOT operate the RHR pump against a shutoff head for greater than 8 seconds.

x All pump trips shall be investigated prior to restarting the pump, except during emergency conditions in which operation of the pump is required to provide protection of the plant or public.

x Observe the following pump restart limitations:

x The motor may be started twice successively from ambient temperature or once from rated motor temperature.

x Repetitive starts are governed by motor operating temperature. In absence of thermal devices to determine machine temperature, the following can be used as a guide: the motor can be assumed to have returned to rated temperature after 80 minutes idle time or 30 minutes running time, after which time another start is permissible.

PERRY NUCLEAR POWER PLANT Instruction Number:

SOI-E12 Section 2.0

Title:

RESIDUAL HEAT REMOVAL SYSTEM Use Category:

In-Field Reference Revision:

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8 of 346 x

Limit RHR pump flow as follows:

x 8520 gpm with flow bypassing the RHR heat exchangers. This limit is based on RHR Pump runout flow.

x 7800 gpm with flow through the RHR heat exchangers. This limit is based on RHR heat exchanger maximum flow.

2.3 Any time it is suspected that the RHR Loops are NOT filled or the system has been breached, fill and vent the RHR Loop as applicable.

2.4 The reactor shall be placed and maintained in a Cold Shutdown condition whenever a loop of RHR is used in the Fuel Pool Cooling Assist mode.

2.5 The disconnect, MCC EF1B07-H, for SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, shall be closed only to perform Shutdown Cooling or related shutdown operations. It shall be open during all other conditions to satisfy 10CFR50 Appendix R considerations.

2.6 Operation of the LPCI mode of RHR with injection flow to the vessel shall only be done in an accident condition, a plant emergency condition, or an approved test condition of short duration. ONI-E12-2, Loss of Decay Heat Removal, and IOI-11, Shutdown From Outside Control Room, direct the use of the LPCI injection lines as Alternate Shutdown Cooling flow paths. Use of this flow path is still subject to reportability (as described in NOP-OP-1015, Event Notifications) when used for Alternate Shutdown Cooling.

2.7 Water Hammer:

Do NOT start a pump in the effected loop prior to ensuring the loop is filled. This could result in water hammer in a loop that is severe enough to cause component damage or pressure boundary failure. Potential causes of voiding include:

x A loss of pumping power with RHR A(B) TEST VALVE TO SUPR POOL, 1E12-F024A(B), open.

x A Division 1(2) RHR Isolation during Shutdown Cooling Operation may allow steam voids to form.

x Opening RHR A(B) SUPR POOL SUCTION VALVE, 1E12-F004A(B), when the RHR Pump A(B) suction piping is filled with water that is at greater than 200qF.

PERRY NUCLEAR POWER PLANT Instruction Number:

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RESIDUAL HEAT REMOVAL SYSTEM Use Category:

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9 of 346 x

Deviation from written instructions when operating the system.

x Maintenance or testing on portions of the system that require realigning valves.

2.8 If it becomes necessary to close RHR A(B) TO CNTMT SHUTOFF, 1E12-F027A(B), then to prevent back leakage or thermal changes from over pressurizing the isolated piping refer to RHR A(B) To Cntmt Shutoff 1E12-F027A(B) Operation and perform the actions.

2.9 If the RHR PUMP A(B,C), MIN FLOW VALVE, 1E12-F064A(B,C), is NOT capable of opening to provide minimum flow (except as allowed in 3.5.2 for Shutdown Cooling),

Then declare RHR Pump A(B,C) INOPERABLE and take one of the following actions:

x Ensure RHR Pump A(B,C), 1E12-C002A(B,C) breaker open with its control power fuses removed.

x Provide increased monitoring whenever RHR Pump A(B,C) is in operation to ensure RHR A(B,C) does NOT operate at less than 1650 gpm for greater than 8 seconds.

x If RHR A(B) Pump is operated at less than 1650 gpm for greater than 8 seconds, an Engineering analysis of RHR Pump A(B,C) shall be performed prior to declaring RHR Pump A(B,C) OPERABLE.

2.10 Operation of RHR Loop A in the Test Mode or Suppression Pool Cooling when SPCU is in operation through the Suppression Pool Return Line Bypassing RHR A could result in loss of flow to the SPCU pump.

2.11 If LPCS & RHR A WATER LEG PUMP, 1E21-C002, or RHR B & C WATER LEG PUMP, 1E12-C003, are shutdown, Then the respective Feedwater Leakage Control System (N27A or N27B), will become inoperable.

2.12 If RHR A, B, or C are placed on alternate keep fill or the respective Waterleg pump is shutdown the affected RHR loop will be inoperable.

2.13 To provide a suction to the LPCS & RHR A WATER LEG PUMP, 1E21-C002, the LPCS SUPR POOL SUCTION VALVE, 1E21-F001, must be open.

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10 of 346 2.14 To provide suction to the RHR B & C WATER LEG PUMP, 1E12-C003, the RHR C SUPR POOL SUCTION VALVE, 1E12-F105, must be open.

2.15 Prior to placing RHR in Shutdown Cooling mode, RPV pressure shall be less than 135 psig.

2.16 RP should be notified prior to conducting Suppression Pool evolutions, so the survey frequency may be increased as necessary.

2.17 Opening of RHR PUMP A(B) MIN FLOW VALVE, 1E12-F064A(B) or RHR A(B)

UPPER POOL COOLING ISOL, 1E12-F037A(B), while in shutdown cooling could result in the draining of the vessel. Do NOT allow any RHR piping, which has been inadvertently drained down, to refill with Reactor Vessel Water.

2.18 Valve alignments and system manipulations on the RHR system when SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, and SHUTDOWN COOLING INBD SUCT ISOL, 1E12-F009, are open shall be supervised by the Shift Manager or Unit Supervisor when required by OAI-0201 Section 4.4.2.

2.19 LPCI operability requires flow both through the RHR Heat Exchangers and the RHR Heat Exchanger Bypass line; therefore, anytime RHR A(B) HXS INLET VALVE, 1E12-F047A(B), is NOT open or either RHR A(B) HXS OUTLET VALVE, 1E12-F003A(B), or RHR A(B) HXS BYPASS VALVE, 1E12-F048A(B), is NOT capable of automatically opening LPCI shall be declared INOPERABLE.

2.20 When 1E12-F024A(B) is open, system flow through 1E12-F024A(B) shall be maintained greater than 6000 gpm. 6000 gpm is the minimum flow allowable to prevent voiding at the high point in the RHR system piping. The normal Suppression Pool Cooling/Test Mode flow is 7100-7300 gpm.

2.21 The pump rotation during fill and vent operations shall be minimized.

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11 of 346 2.22 Operating the RHR System in a Secondary Mode of operation, except Shutdown Cooling, will *INOP the LPCI mode of RHR due to the system being unable to realign within the Technical Specification response time requirements.

With temperature is less than 200qF the LPCI does NOT need to be declared inoperable when the RHR loop is in Shutdown Cooling as long as it can be realigned to the LPCI mode (either remotely or locally), is NOT otherwise inoperable.

When placing a loop of RHR in Shutdown Cooling greater than 200qF the RHR loop shall be considered inoperable for ALL Modes except Shutdown Cooling Mode of operation due to the possiblilty of system voiding during a Shutdown Cooling Isolation.

2.23 When venting or draining the ESW side of the RHR Heat Exchangers the expelled water should NOT be discharged to Radwaste. This lake water will shorten the life of the Radwaste demineralizers and biologically foul the resin which will cause gas buildup in Radwaste shipping containers. The preferred actions are to collect this water in a container which RP and CHEM can sample for release outside the RRA or have RP and CHEM approve running the vent/drain hose to a non-radiological drain. In the event lake water must be drained to a radiological drain, Radwaste shall be informed of amount of lake water to be drained and the drain to receive it.

2.24 If the RHR HX ESW inlet or outlet valves, 1P45-F014A(B) or 1P45-F068A(B), are NOT full open the associated RHR loop shall be declared inoperable. This is because the valves may NOT reposition properly during accident conditions.

2.25 The RHR pumps should NOT be operated in minimum flow for excessive periods of time. If an RHR pump is operated in minimum flow for greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, a Condition Report should be generated for Engineering to evaluate the effects on the pump.

2.26 Erosion may occur on the RHR Pump minimum flow lines. Consideration should be given to placing RHR Pumps in the suppression pool cooling/test mode during extended operation rather than leaving them in minimum flow.

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12 of 346 2.27 Leakage past the following valves is considered Leakage Outside Containment.

To control leakage past these valves, they shall be torqued to the following specified values in Mode 1, 2, or 3:

x 1E12F0071A - 140 FT/LBS.

x 1E12F0072A - 140 FT/LBS x

1E12F0511A - 123 FT/LBS.

x 1E12F0071B - 96 FT/LBS.

x 1E12F0072B - 96 FT/LBS x

1E12F0511B - 123 FT/LBS.

x 1E12F0071C - 96 FT/LBS.

x 1E12F0072C - 96 FT/LBS.

1E12F0511B is not normally closed; however, if it should need to be closed due to leakage past 1E12F0071B or 1E12F0072B, it will need to be torqued to 123 FT/LBS.

2.28 If a Loop of RHR has been drained that Loop of RHR shall be run in Suppression Pool Cooling/Test Mode (RHR A,B), RHR Loop C Flush/Test Mode (RHR C) to sweep air pockets from portions of the system that cannot be vented prior to the Loop being declared operable.

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13 of 346 2.29 The following table provides torque specifications when manually operating selected valves:

Valve Hand Wheel Torque 1E12-F010 285 ft-lbs 1E12-F039A(B,C) 206 ft-lbs 1E12-F066A 93 ft-lbs 1E12-F085A 400 inch-lbs 1E12-F502A,C 120 ft-lbs 1E12-F552A 106 ft-lbs 1E12-F599A 30 ft-lbs +25%, -0%

1E12-F621 118 ft-lbs 2.30 Observe the following RHR Pump Motor Oil level limitations as can be determined when the pump motors are de-energized:

x RHR Pump A (B, C), 1E12-C002A (B, C) oil levels should be maintained within 7/16 above and below the reference line of the oil reservoir sight glass.

x RHR B & C WATER LEG PUMP, 1E12-C003 constant level oiler should be maintained per the specified inches below shaft centerline stated on the Oil Level Plate.

2.31 RHR A can NOT be operated in Shutdown Cooling when ADHR system is aligned for decay heat removal.

2.32 OAI-0502 requires a minimum vent duration of 2 minutes after a solid stream of fluid has been achieved when venting ECCS systems. Steps for venting state for at least 2 minutes. Time of the vent starts when an air free stream is achieved.

END OF SECTION

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SOI-E12 Section 7.5

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100 of 346 7.5 Shifting Shutdown Cooling From Loop A(B) to Loop B(A) 7.5.1 REFER TO Shutdown Cooling Startup and PLACE the Oncoming loop in service.

Loop B

Loop A

7.5.2 REFER TO Shutdown Cooling Shutdown to Standby Readiness and SHUTDOWN the Offgoing RHR loop.

Loop A

Loop B

END OF SECTION

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SOI-E12 Section 4.7

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33 of 346 4.7 Shutdown Cooling Startup for RHR A(B)

NOTES x

Both Loops of RHR may be placed in Shutdown Cooling by performing all the required Steps for one loop and then performing the required Steps for the other loop.

x Local Field Actions maybe required in the following places:

x CC 620 Switchgear rooms to operate disconnect stitches.

x AX 620RHR B Penetration Room to operate flush valves.

x AX 574 to operate RHR B to Radwaste Shutoff Valve, 1E12-F504 (RHR B only).

NA 4.7.1 A Loss of Shutdown Cooling has NOT occurred NOT Operating in EOPs The Oncoming Shutdown Cooling Loop flowpath has NOT been maintained filled and vented the last 10 days The Oncoming RHR Loop has NOT operated in Shutdown Cooling within the last 10 days Loop A

Loop B

A waiver for the requirement to perform RHR Loop flushing from Operations Manager has NOT been granted THEN PERFORM the following:

4.7.1.a CONFIRM the Oncoming RHR loop RHR SHUTDOWN CLG SUCT valve is closed.

1E12-F006A 1E12-F006B

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34 of 346 NA 4.7.1.b Information Tag is on the RHR Conductivity Alarm window(s)

Caution Tag is on the RHR Conductivity Alarm window(s) 1H13-P601-20-G5 1H13-P601-17-G5 THEN REFER TO Placing RHR Conductivity Alarm In Service and VERIFY the actions are complete.

NOTE Both loops of RHR should be flushed when placing SDC into service during non-refueling periods. Only one loop needs to be flushed prior to establishing Shutdown Cooling. The second loop of RHR should be flushed when Mode 4 is reached to make it available for use in the SDC mode. Delaying the flush of the second RHR loop minimizes inoperability time and the time to establish Shutdown Cooling.

4.7.1.c REFER TO Flush of RHR Loop A(B)

When in Standby Readiness Mode and VERIFY the flush the oncoming loop is complete.

NA 4.7.1.d IF the Suppression Pool water does NOT meet the limits for transfer quality per Chemistry, THEN REFER TO Flush of RHR A(B)

With CST Water and VERIFY the actions complete.

4.7.1.e REFER TO SOI-P45/49 and VERIFY the associated Emergency Service Water System Loop in operation.

Loop A

Loop B

4.7.1.f REFER TO SOI-P42 and VERIFY the associated Emergency Closed Cooling System Loop in operation.

Loop A

Loop B

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35 of 346 NOTES x With temperature is less than 200qF the LPCI does NOT need to be declared inoperable for the LPCI Mode when the RHR loop is in Shutdown Cooling as long as it can be realigned to the LPCI mode (either remotely or locally), is NOT otherwise inoperable.

x When placing a loop of RHR in Shutdown Cooling greater than 200qF the RHR loop shall be considered inoperable for ALL Modes except Shutdown Cooling Mode of operation due to the possiblilty of system voiding during a Shutdown Cooling Isolation.

NA 4.7.2 IF operating in MODE 3, THEN NOTIFY the Unit Supervisior that RHR loop being placed into Shutdown Cooling will be inoperable for ALL Modes except Shutdown Cooling Mode, UNTIL Mode 4 is entered.

4.7.3 NOTIFY Radiation Protection of the Change to Shutdown Cooling Operation.

NA 4.7.4 IF Placing RHR A in service, THEN CONFIRM the ADHR system is NOT in service removing Decay heat.

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36 of 346 NA 4.7.5 Performing Section 7.5, Shifting Shutdown Cooling From Loop A(B) to Loop B(A)

Starting RHR A in Shutdown Cooling Loop A

RHR B pump is NOT running 1E12-C002B THEN VERIFY RHR B SHUTDOWN CLG SUCT valve control switch in CLOSED.

1E12-F006B NA 4.7.6 Performing Section 7.5, Shifting Shutdown Cooling From Loop A(B) to Loop B(A)

Starting RHR B in Shutdown Cooling Loop B

RHR A pump is NOT running 1E12-C002A THEN VERIFY RHR A SHUTDOWN CLG SUCT valve control switch in CLOSED.

1E12-F006A 4.7.7 VERIFY RHR B HXS SECOND VENT TO SUPR POOL is CLOSED.

1E12-F073B 4.7.8 VERIFY the following:

x RHR SUPR POOL SUCTION VALV keylock switch in CLOSED.

1E12-F004A 1E12-F004B x

RHR HXS BYPASS VALVE is OPEN.

1E12-F048A 1E12-F048B

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37 of 346 x

RHR HXS OUTLET VALVE is OPEN.

1E12-F003A 1E12-F003B NOTE SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, disconnect MCC EF1B07-H can be verified closed by power being present to the valve position indication.

4.7.9 VERIFY the SHUTDOWN COOLING OTBD SUCT ISOL, 1E12-F008, valve disconnect is CLOSED.

EF1 B07-H 4.7.10 REFER TO SOI-P45/49 and VERIFY Emergency Service Water System Loop in operation.

A B

4.7.11 REFER TO SOI-P42 and VERIFY Emergency Closed Cooling System Loop in operation.

A B

NA 4.7.12 SHUTDOWN COOLING OTBD SUCT ISOL is closed SHUTDOWN COOLING INBD SUCT ISOL is closed 1E12-F008 1E12-F009 THEN PERFORM the following:

4.7.12.a WHEN Reactor Vessel pressure is less than 135 psig, THEN VERIFY the following are reset:

x Trip unit 1B21-N679D (1H13-P694).

x Trip unit 1B21-N679A (1H13-P691).

x Trip unit 1B21-N679C (1H13-P693).

x Trip unit 1B21-N679B (1H13-P692).

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38 of 346 4.7.12.b MOMENTARILY DEPRESS BOTH of the following to reset the NS4 logic:

x MSL & NS4 OTBD ISOL SEAL IN RESET.

1B21H

-S32

x MSL & NS4 INBD ISOL SEAL IN RESET.

1B21H

-S33

4.7.13 HOLD the Oncoming RHR HXS OUTLET VALVE in CLOSE for 54-56 seconds.

1E12-F003A 1E12-F003B NA 4.7.14 IF the Oncoming RHR PUMP MIN FLOW VALVE is energized, THEN PERFORM the following:

1E12-F064A 1E12-F064B

4.7.14.a VERIFY the Oncoming loop RHR PUMP MIN FLOW VALVE is closed.

1E12-F064A 1E12-F064B

4.7.14.b PERFORM independent verification of the Oncoming RHR PUMP MIN FLOW VALVE position.

1E12-F064A 1E12-F064B

4.7.14.c OPEN the Oncoming RHR PUMP MIN FLOW VALVE, 1E12-F064, disconnect.

EF1 B07-CC EF1 D07-CC NOTE RPV level may increase during Quenching steam voids due to flow from the Condensate Transfer System while performing the following steps.

NA 4.7.15 IF SHUTDOWN COOLING OTBD SUCT ISOL is closed, THEN PERFORM the following:

1E12-F008

4.7.15.a VERIFY SHUTDOWN COOLING INBD SUCT ISOL is closed.

1E12-F009 N/A

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39 of 346 NA 4.7.15.b IF Reactor Temperature is greater than or equal to 200qF, THEN PERFORM the following to collapse steam voids:

4.7.15.b.1 REFER TO Flush Valve Operation and MANUALLY SLOWLY OPEN the Shtdn Cooling Suct Hdr Flush Supply, UNTIL flow noise is heard.

1E12-F315 4.7.15.b.2 WHEN the RHR suction piping has filled for approximately 5 minutes, THEN REFER TO Flush Valve Operation and MANUALLY SLOWLY OPEN the Shtdn Cooling Suct Hdr Flush Supply.

1E12-F315 NA 4.7.15.c IF Reactor Temperature is less than 200qF, THEN REFER TO Flush Valve Operation and MANUALLY OPEN the Shtdn Cooling Suct Hdr Flush Supply.

1E12-F315 4.7.15.d TAKE the SHUTDOWN COOLING OTBD SUCT ISOL to OPEN.

1E12-F008 4.7.16 VERIFY the Oncoming RHR SHUTDOWN CLG SUCT in OPEN.

1E12-F006A 1E12-F006B

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40 of 346 NA 4.7.17 IF SHUTDOWN COOLING INBD SUCT ISOL is closed, THEN PERFORM the following:

1E12-F009 NA 4.7.17.a IF Shtdn Cooling Suct Hdr Flush Supply is closed, THEN REFER TO Flush Valve Operation and MANUALLY SLOWLY OPEN the Shtdn Cooling Suct Hdr Flush Supply.

1E12-F315 4.7.17.b HOLD RHR B HXS SECOND VENT TO SUPR POOL in OPEN, UNTIL open.

1E12-F073B 4.7.17.c WHEN the Suction Header has vented for 5 minutes, THEN HOLD RHR B HXS SECOND VENT TO SUPR POOL in CLOSE, UNTIL closed.

1E12-F073B 4.7.17.d REFER TO Flush Valve Operation and CLOSE the Shtdn Cooling Suct Hdr Flush Supply.

1E12-F315 4.7.17.e TAKE SHUTDOWN COOLING INBD SUCT ISOL to OPEN.

1E12-F009

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41 of 346 CAUTION The following step will reduce Reactor Vessel Water inventory. Reactor Vessel level should be raised to near the high level alarm setpoint prior to this step to prevent exceeding the low level setpoint.

NA 4.7.18 IF Reactor Temperature is greater than 200qF, THEN PERFORM the following to warmup the RHR suction piping:

NA 4.7.18.a IF placing RHR A in Shutdown Cooling, THEN TAKE RHR A TO RADWASTE ISOL to OPEN.

1E12-F049 NA 4.7.18.b IF placing RHR B in Shutdown Cooling, THEN OPEN RHR B to Radwaste Shutoff Valve.

1E12-F504 4.7.18.c VERIFY that Radwaste is ready to receive water from RHR.

4.7.18.d NOTIFY Radwaste that a flush is to be commenced.

4.7.18.e NOTE the Oncoming RHR IN to HXTR Temperature on RHR TEMPERATURES recorder.

Temp: qF 1E12-R601 Pt 1 (red) 1E12-R601 Pt 2 (dark green)

NOTE The dust and oil film, which may accumulate during standby readiness periods, may smoke when heated during the performance of the following steps.

4.7.18.f THROTTLE the RHR TO RADWASTE ISOL in OPEN for 1 to 3 seconds.

1E12-F040

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42 of 346 NA 4.7.18.g RHR DISCH to RW Temperature on the RHR TEMPERATURES recorder is 200qF RHR DISCH to RW Temperature on the RHR TEMPERATURES recorder has stabilized near RPV temperature 1E12-R601 Pt 11 (light green)

THEN VERIFY RHR TO RADWASTE ISOL is CLOSED.

1E12-F040 NA 4.7.18.h IF placing RHR A in Shutdown Cooling, THEN TAKE the RHR A TO RADWASTE ISOL to CLOSE.

1E12-F049 NA 4.7.18.i IF placing RHR B in Shutdown Cooling, THEN CLOSE the RHR B to Radwaste Shutoff Valve.

1E12-F504 4.7.18.j NOTIFY Radwaste that the flush has been secured.

4.7.18.k THROTTLE open RHR HXS DUMP VALVE for 1 to 3 seconds.

1E12-F011A 1E12-F011B NA 4.7.18.l RHR IN To HXTR temperature has risen 5-10qF from the initial temperature noted RHR IN To HXTR temperature on the RHR TEMPER-ATURES recorder has stabilized near RPV temperature 10 minutes has elapsed 1E12-R601 Pt 1 (red) 1E12-R601 Pt 2 (dark green)

THEN HOLD RHR HXS DUMP VALVE in CLOSE, UNTIL closed.

1E12-F011A 1E12-F011B

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43 of 346 4.7.19 HOLD the Oncoming RHR HXS BYPASS VALVE in CLOSE for 59-62 seconds.

1E12-F048A 1E12-F048B 4.7.20 HOLD RHR HXS OUTLET VALVE in CLOSE, UNTIL closed.

1E12-F003A 1E12-F003B NA 4.7.21 It is desired to establish the Normal Return Path 1E12-F053A 1E12-F053B RHR Upper Pool Cooling Isol is closed 1E12-F037A 1E12-F037B LPCI Injection Valve is closed 1E12-F042A 1E12-F042B THEN PERFORM the following:

NA 4.7.21.a IF the Feedwater System is shutdown, THEN VERIFY the Oncoming RHR loop FDW HDR SHUTOFF is closed, to prevent flow to the feedwater system.

1B21-F065A 1B21-F065B

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44 of 346 CAUTIONS x The RHR PUMP MIN FLOW VALVE is downpowered in the closed position. Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.

x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

4.7.21.b INITIATE flow through the SHUTDOWN COOLING TO FDW SHUTOFF as follows:

1E12-F053A 1E12-F053B 4.7.21.b.1 PERFORM the following simultaneously:

x HOLD the SHUTDOWN COOLING TO FDW SHUTOFF in OPEN, UNTIL open.

1E12-F053A 1E12-F053B x

TAKE the RHR PUMP to START. 1E12-C002A 1E12-C002B 4.7.21.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.

1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B 4.7.21.c JOG OPEN the RHR HXS BYPASS VALVE in 1000-2000 gpm increments, UNTIL RHR PUMP FLOW is 6000-7100 gpm.

1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B 4.7.21.d GO TO RHR Shutdown Cooling Operations for RHR A(B).

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45 of 346 NA 4.7.22 It is desired to establish the Refuel Return Path 1E12-F037A 1E12-F037B Shutdown Cooling To Fdw Shutoff is closed 1E12-F053A 1E12-F053B LPCI Injection Valve is closed 1E12-F042A 1E12-F042B RHR to Cntmt Pools Spectacle Flange blank is removed 1E12-D501A 1E12-D501B The RPV Head has been removed The Containment Pools are filled THEN PERFORM the following:

4.7.22.a MONITOR FPCC SURGE TANK LEVEL while establishing Refuel Mode Shutdown Cooling.

G41-R366A G41-R366B (INTENTIONALLY BLANK)

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46 of 346 CAUTIONS x The RHR PUMP MIN FLOW VALVE is downpowered in the closed position. Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.

x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

4.7.22.b INITIATE flow through the RHR UPPER POOL COOLING ISOL as follows:

1E12-F037A 1E12-F037B 4.7.22.b.1 PERFORM the following simultaneously:

x HOLD the RHR UPPER POOL COOLING ISOL in OPEN, UNTIL open.

1E12-F037A 1E12-F037B x

TAKE the RHR PUMP to START. 1E12-C002A 1E12-C002B 4.7.22.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.

1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B 4.7.22.c JOG OPEN the RHR HXS BYPASS VALVE in 1000-2000 gpm increments, UNTIL RHR PUMP FLOW is 7000-7100 gpm.

1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B 4.7.22.d GO TO RHR Shutdown Cooling Operations for RHR A(B).

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47 of 346 CAUTIONS x

Operation of the RHR Loop with Vessel Injection via the LPCI Injection Line has the potential to result in fatigue failure of incore instrument tubes and burnishing of fuel channels.

x The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.

Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.

x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

NA 4.7.23 It is desired to establish the Alternate Return Path 1E12-F042A 1E12-F042B Normal Shutdown Cooling return path is unavailable 1E12-F053A 1E12-F053B Refuel Shutdown Cooling return path is unavailable 1E12-F037A 1E12-F037B THEN PERFORM the following:

4.7.23.a REFER TO Alternate Shutdown Cooling Data (Attachment 42) and TAKE Pre-Start Data.

(INTENTIONALLY BLANK)

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48 of 346 CAUTIONS x

The RHR PUMP MIN FLOW VALVE is downpowered in the closed position.

Throttling open the RHR HXS BYPASS VALVE, 1E12-F048A(B) after starting the pump ensures pump min flow requirements are met following pump start.

x Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

4.7.23.b INITIATE flow through the LPCI INJECTION VALVE as follows:

1E12-F042A 1E12-F042B 4.7.23.b.1 PERFORM the following simultaneously:

x TAKE the LPCI INJECTION VALVE to OPEN.

1E12-F042A 1E12-F042B x

TAKE the RHR PUMP to START. 1E12-C002A 1E12-C002B 4.7.23.b.2 WITHIN 8 seconds, THROTTLE RHR HXS BYPASS VALVE, UNTIL RHR PUMP FLOW is at least 2575 gpm.

1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B 4.7.23.c JOG OPEN the RHR HXS BYPASS VALVE in 1000-2000 gpm increments, UNTIL RHR PUMP FLOW is 2575-7100 gpm.

1E12-F048A 1E12-R603A 1E12-F048B 1E12-R603B

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49 of 346 4.7.23.d NOTIFY the following of the use of the Shutdown Cooling return flow to the Vessel via LPCI INJECTION VALVE so the required fuel inspection may be scheduled:

1E12-F042A 1E12-F042B x

Reactor Engineering.

x Outage Planning.

4.7.23.e INITIATE a special report to the NRC in accordance with NOP-OP-1015, Event Notifications.

4.7.23.f GO TO RHR Shutdown Cooling Operations for RHR A(B).

END OF SECTION

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101 of 346 7.6 RHR Shutdown Cooling Operations for RHR A(B)

NOTES x Normal Design parameters for Shutdown Cooling/Test Mode operation:

o RHR Pump Flow 7000-7100 gpm.

o RHR Pump Amps95-110 Amps.

o RHR A Head Spray Flow 0 - 500 gpm.

o RHR Suction Pressure Less than 135 psig.

o RHR HX ESW Outlet Temps Less than 108qF.

o RHR Pump Suct Temp Less than 100qF (Refuel Mode).

o RHR HXS RHR Outlet Temp Less than 86qF (Refuel Mode).

x The following actions can be performed in any logical order or repeated to support current plant conditions.

7.6.1 OBSERVE the following limitations when in Shutdown Cooling:

x MAINTAIN cooldown rate less than 100qF in any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.

x DO NOT allow any RHR piping which has been inadvertently drained to be refilled with water from the Reactor Vessel.

x MAINTAIN Vessel temperature below 190qF while in Shutdown Cooling.

x WHEN using the normal OR refuel mode return paths, THEN MAINTAIN the following:

x MAINTAIN RHR Pump flow at 7000-7100 gpm during steady state conditions.

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102 of 346 x MAINTAIN RHR Pump flow at 6000-7100 gpm during system adjustments.

x WHEN using the alternate return path, THEN MONITOR the following additional items:

1E12-F042A 1E12-F042B x MAINTAIN RHR FLOW in the band 2575-7100 gpm.

1E12-F042A 1E12-F042B x MAINTAIN RHR H2O DISCH temperature greater than 65qF.

1E12-R601 Pt 5 (magenta) 1E12-R601 Pt 6 (orange) 7.6.2 PERFORM the following as needed to maintain desired cooldown rate AND RHR Pump flow 7000-7100 (alternate return path 2575-7100):

1E12-R603A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE.

1E12-F003A 1E12-F003B x THROTTLE RHR HXS BYPASS VALVE.

1E12-F048A 1E12-F048B NA 7.6.3 RHR A is in Shutdown Cooling Head spray is desired THEN PERFORM the following:

7.6.3.a CONFIRM that the RCIC INJECTION VLV is closed.

1E51-F013

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103 of 346 NOTE The HD SPRAY FLOW 1E12-R607 indication taps in downstream of the RHR Pump flow 1E12-R603A(B) indicator. Changing head Spray flow does not change RHR Pump flow.

7.6.3.b PERFORM the following, UNTIL HD SPRAY FLOW is 500 gpm AND RHR Pump flow 7000-7100 (alternate return path 2575-7100):

1E12-R607 1E12-R603A 1E12-R603A x

THROTTLE RHR HXS OUTLET VALVE.

1E12-F003A 1E12-F003B x

THROTTLE RHR HXS BYPASS VALVE.

1E12-F048A 1E12-F048B x

THROTTLE RHR A HEAD SPRAY ISOL.

1E12-F023 7.6.3.c WHEN the Rx Vessel pressure is at atmospheric pressure, THEN VERIFY RHR A HEAD SPRAY ISOL is closed.

1E12-F023 NA 7.6.4 IF oncoming loop of ESW was NOT started per SOI-P45/49, THEN PERFORM the following:

7.6.4.a VERIFY the following:

x ESW PMP HOUSE VENT SUPP FAN 1, is RUNNING.

1M32-C001A 1M32-C001B x ESW PMP HOUSE EXH LOUVER 70 is OPEN 1M32-F070A 1M32-F070B x ESW PUMP DISCH VALVE is fully OPEN 1P45-F130A 1P45-F130B

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104 of 346 7.6.4.b RECORD ESW flow channel check in the Narrative Log.

NA 7.6.4.c IF lake temperature is less than

34qF, THEN REFER TO SOI-P45/49 and PERFORM de-icing operation.

7.6.4.d DIRECT Chemistry to perform the following:

x OBTAIN Tech Spec samples of flow through the RHR Heat Exchangers as required.

x CHLORINATE ESW as required.

NA 7.6.5 Information Tag is on the RHR Conductivity Alarm window(s)

Caution Tag is on the RHR Conductivity Alarm window(s) 1H13-P601-2 0-G5 1H13-P601-17-G5 THEN REFER TO Placing RHR Conductivity Alarm In Service and VERIFY the actions are complete.

NA 7.6.6 IF the LPCI INJECTION VALVE is

open, THEN REFER TO Alternate Shutdown Cooling Data (Attachment 42) and TAKE Post-Start Data Alternate Shutdown Cooling Return Path Startup Data.

1E12-F042A 1E12-F042B 7.6.7 PERFORM Independent Verification of the required components for Shutdown Cooling Startup for RHR A(B).

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105 of 346 NA 7.6.8 IF RPV temperature is less than 200qF, THEN NOTIFY the Unit Supervisior that RHR loop(s) in Shutdown Cooling may be declared operable for LPCI, Suppression Pool Cooling, Shutdown Cooling and Containment Spray Modes.

NA 7.6.9 RPV temperature is less than 200qF Opposite loop of RHR is available for shutdown cooling Loop B

Loop A

THEN PERFORM the following:

7.6.9.a REFER TO Flush of RHR Loop A(B)

When in Standby Readiness Mode and VERIFY the Opposite loop of RHR has been flushed.

Loop B

Loop A

NA 7.6.9.b IF Suppression Pool is NOT transfer quality, THEN REFER TO Flush of RHR A(B)

With CST Water and VERIFY the actions are complete.

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106 of 346 NOTES x The flow path for the RHR Loop operating in Refuel Mode Shutdown Cooling will be:

- RHR Loop A - Separator Storage Well to Reactor Cavity.

- RHR Loop B - Dryer and Fuel Storage Well to Reactor Cavity.

x This Step can be used during refueling operations as necessary to minimize flow-induced turbulence.

NA 7.6.10 It is desired to Improve Water Clarity Desire to Align RHR Shutdown Cooling Flow to the Upper Pools THEN PERFORM the following:

7.6.10.a VERIFY the Reactor Vessel Head is removed.

7.6.10.b VERIFY the Upper Pools are filled.

7.6.10.c VERIFY the RHR to Cntmt Pools Spectacle Flange is aligned with the blank removed and the spacer ring installed.

1E12-D501A 1E12-D501B 7.6.10.d PERFORM the following as need, UNTIL RHR PUMP FLOW is 7000-7100 gpm AND desired flow to the upper pools is established:

1E12-R603A 1E12-R603B x THROTTLE RHR UPPER POOL COOLING ISOL.

1E12-F037A 1E12-F037B x THROTTLE SHUTDOWN COOLING TO FDW SHUTOFF.

1E12-F053A 1E12-F053B

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107 of 346 NA 7.6.10.e Feedwater is aligned to feed the RPV SHUTDOWN COOLING TO FDW SHUTOFF is closed 1E12-F053A 1E12-F053B THEN OPEN the associated FDW HDR SHUTOFF valve.

1B21-F065A 1B21-F065B NA 7.6.11 RHR UPPER POOL COOLING ISOL is open RHR UPPER POOL COOLING ISOL is throttled 1E12-F037A 1E12-F037B Desired to use the Normal Mode Shutdown Cooling path THEN PERFORM the following:

7.6.11.a VERIFY the associated FDW HDR SHUTOFF valve is CLOSED.

1B21-F065A 1B21-F065B 7.6.11.b PERFORM the following as need, UNTIL RHR PUMP FLOW is 7000-7100 gpm RHR UPPER POOL COOLING ISOL is closed:

1E12-R603A 1E12-F037A 1E12-R603B 1E12-F037B x THROTTLE RHR UPPER POOL COOLING ISOL.

1E12-F037A 1E12-F037B x THROTTLE SHUTDOWN COOLING TO FDW SHUTOFF.

1E12-F053A 1E12-F053B

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108 of 346 CAUTION Maintain RHR Shutdown Cooling flow greater than 2575 gpm to ensure that the RHR PUMP A(B) has adequate minimum flow.

NA 7.6.12 Desire to Align RHR Shutdown Cooling Flow to the Normal Mode Desire to Align RHR Shutdown Cooling Flow to the Refuel Mode 1E12-F053A 1E12-F037A 1E12-F053B 1E12-F037B LPCI INJECTION VALVE is open 1E12-F042A 1E12-F042B THEN PERFORM the following:

7.6.12.a PERFORM the following as needed to establish RHR PUMP FLOW 2750-3500 gpm, WHILE maintaining desired cooldown rate:

1E12-R603A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE.

1E12-F003A 1E12-F003B x THROTTLE OPEN RHR HXS BYPASS VALVE.

1E12-F048A 1E12-F048B NA 7.6.12.b IF aligning RHR Shutdown Cooling Flow to the Normal Mode, THEN PERFORM the following:

7.6.12.b.1 VERIFY the associated FDW HDR SHUTOFF is closed.

1B21-F065A 1B21-F065B 7.6.12.b.2 HOLD the SHUTDOWN COOLING TO FDW SHUTOFF in OPEN, UNTIL open.

1E12-F053A 1E12-F053B

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109 of 346 7.6.12.b.3 TAKE the LPCI INJECTION VALVE to CLOSED.

1E12-F042A 1E12-F042B NOTE The flow path for the RHR Loop operating in Refuel Mode Shutdown Cooling will be:

x RHR Loop A - Separator Storage Well to Reactor Cavity.

x RHR Loop B - Dryer and Fuel Storage Well to Reactor Cavity.

NA 7.6.12.c IF aligning RHR Shutdown Cooling Flow to the Refuel Mode, THEN PERFORM the following:

7.6.12.c.1 VERIFY the Reactor Vessel Head is removed.

7.6.12.c.2 VERIFY the Upper Pools are filled.

7.6.12.c.3 VERIFY the RHR to Cntmt Pools Spectacle Flange is aligned with the blank removed and the spacer ring installed.

1E12-D501A 1E12-D501B 7.6.12.c.4 HOLD the RHR UPPER POOL COOLING ISOL in OPEN, UNTIL open.

1E12-F037A 1E12-F037B 7.6.12.c.5 TAKE the LPCI INJECTION VALVE to CLOSED.

1E12-F042A 1E12-F042B

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110 of 346 7.6.12.d PERFORM the following as needed to establish RHR PUMP FLOW 7000-7100 gpm:

1E12-R603A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE.

1E12-F003A 1E12-F003B x THROTTLE OPEN RHR HXS BYPASS VALVE.

1E12-F048A 1E12-F048B NOTE RPV level can be estimated to be 200 gallons per inch of Reactor Vessel Level.

NA 7.6.13 IF it is desired to Lower Reactor Level to Radwaste, THEN PERFORM the following:

7.6.13.a VERIFY Radwaste System is aligned to receive the flow from RHR.

7.6.13.b VERIFY that the Reactor coolant temperature is less than 140°F.

7.6.13.c THROTTLE the following valves as needed to establish RHR PUMP FLOW 6000-6500 gpm:

1E12-R603A 1E12-R603B x RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B

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111 of 346 NA 7.6.13.d IF it is NOT desired to establish a continuous drain down, THEN THROTTLE the following valves as needed to establish RHR PUMP FLOW 4500 gpm:

1E12-R603A 1E12-R603B x RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B NA 7.6.13.e IF using RHR A, THEN TAKE the RHR A TO RADWASTE ISOL to OPEN.

1E12-F049 NA 7.6.13.f IF using RHR B, THEN OPEN the RHR B To Radwaste Shutoff Valve.

1E12-F504 7.6.13.g NOTIFY Radwaste RPV draining is beginning.

CAUTION Performance of the following step can cause a rapid decrease in RPV level. Discharge flow to Radwaste can drain up to 8/min from the RPV.

7.6.13.h THROTTLE the RHR TO RADWASTE ISOL, UNTIL the desired rate of RPV level decrease is achieved, WHILE maintaining RHR PUMP AMPS less than 95 amps.

1E12-F040 1E12-R100A 1E12-R100B

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112 of 346 NA 7.6.13.i IF continuous drain down is being used, THEN WHILE maintaining RHR PUMP AMPS between 90-95 amps, PERFORM the following as needed to maintain desired heatup AND blowdown rates:

1E12-R100A 1E12-R603A 1E12-R100A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x THROTTLE RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B x THROTTLE RHR TO RADWASTE ISOL 1E12-F040 NA 7.6.13.j The desired RPV level is achieved Continuous blowdown is no longer required THEN PERFORM the following:

7.6.13.j.1 HOLD the RHR TO RADWASTE ISOL in CLOSE, UNTIL closed.

1E12-F040 NA 7.6.13.j.2 IF using RHR A, THEN TAKE the RHR A TO RADWASTE ISOL to CLOSE.

1E12-F049 NA 7.6.13.j.3 IF using RHR B, THEN CLOSE the RHR B To Radwaste Shutoff Valve.

1E12-F504

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113 of 346 7.6.13.j.4 PERFORM the following as needed to establish RHR PUMP FLOW 7000-7100:

1E12-R603A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE.

1E12-F003A 1E12-F003B x THROTTLE RHR HXS BYPASS VALVE.

1E12-F048A 1E12-F048B 7.6.13.j.5 PERFORM independent verification of the required components.

NOTE RPV level can be estimated to be 200 gallons per inch of Reactor Vessel Level.

NA 7.6.14 IF it is desired to Lower Reactor Level to the Suppression Pool, THEN PERFORM the following:

7.6.14.a VERIFY that the Reactor coolant temperature is less than 140°F.

7.6.14.b NOTIFY Radiation Protection of the following:

x A Suppression Pool evolution will be conducted which may affect suppression pool water level and/or activity.

x Surveys should be performed for Containment 599 elevation to evaluate the radiological impact of the evolution.

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114 of 346 7.6.14.c THROTTLE the following valves as needed to establish RHR PUMP FLOW 6000-6500 gpm:

1E12-R603A 1E12-R603B x RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B 7.6.14.d THROTTLE the following valves as needed to establish RHR PUMP FLOW 4500 gpm:

1E12-R603A 1E12-R603B x RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B 7.6.14.e WHILE maintaining RHR PUMP AMPS less than 95 amps, THROTTLE the RHR HXS DUMP VALVE, UNTIL the desired rate of RPV level decrease is achieved.

1E12-R100A 1E12-F011A 1E12-R100B 1E12-F011B 7.6.14.f WHEN the desired RPV level is

achieved, THEN HOLD the RHR HXS DUMP VALVE in CLOSE, UNTIL closed.

1E12-F011A 1E12-F011B 7.6.14.g PERFORM the following as needed to establish RHR PUMP FLOW 6900-7100 gpm:

1E12-R603A 1E12-R603B x THROTTLE RHR HXS OUTLET VALVE 1E12-F003A 1E12-F003B x THROTTLE RHR HXS BYPASS VALVE 1E12-F048A 1E12-F048B

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115 of 346 7.6.14.h PERFORM independent verification of the required components.

NA 7.6.15 IF desired to raise Reactor Water Level Using Condensate Transfer and Storage

Water, THEN PERFORM the following:

7.6.15.a REFER TO Flush Valve Operation and OPEN the SHTDN COOLING SUCT HDR FLUSH SUPPLY valve.

1E12-F315 7.6.15.b WHEN the desired Reactor water level is achieved, THEN REFER TO Flush Valve Operation and CLOSE SHTDN COOLING SUCT HDR FLUSH SUPPLY valve.

1E12-F315 7.6.15.c PERFORM independent verification of the required components.

7.6.16 WHEN desired to shutdown RHR, THEN PERFORM the following:

7.6.16.a CONFIRM Lowering Reactor Level to Radwaste is NOT in progress.

7.6.16.b CONFIRM Lowering Reactor Level to the Suppression Pool is NOT in progress.

7.6.16.c CONFIRM Raising Reactor Water Level Using Condensate Transfer and Storage Water is NOT in progress.

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116 of 346 7.6.16.d GO TO Shutdown Cooling Shutdown to Standby Readiness.

END OF SECTION

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341 of 346 ATTACHMENT 42 - Alternate Shutdown Cooling Data Page 1 of 1 NOTE The LOOP column indicates what must be verified for specific sections/steps.

Shutdown Cooling Loop:

Loop A ___ Loop B ___

Pre-Start Data:

Parameter Instrument Reading Loop RHR IN to HXTR 1E12-R601, Pt 1(red)

A 1E12-R601, Pt 2 (dark green)

B RHR H2O DISCH 1E12-R601, Pt 5 (magenta)

A 1E12-R601, Pt 6 (orange)

B Drywell Avg. Temperature D23ED033 (1D23-R210A(B))

Reactor Bulk Water Temp.

(1)

Post-Start Data:

RHR IN to HXTR 1E12-R601, Pt 1(red)

A 1E12-R601, Pt 2 (dark green)

B RHR H2O DISCH 1E12-R601, Pt 5 (magenta)

A 1E12-R601, Pt 6 (orange)

B RHR Pump Flow 1E12-R603A A

1E12-R603B B

Drywell Avg. Temperature D23ED033 (1D23-R210A(B))

Reactor Bulk Water Temp.

(1) instrument for this parameter. Record which instrument was used in the instrument column.

Forward the original to the Responsible System Engineer, PNED/SES Forward a copy to the System Design Engineer, PNED/DES Forward a copy to the Lead Engineer, Piping Analysis, PNED/DES.

OT-3701-G43_001_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:

G43 - Suppression Pool Makeup System Time Critical:

No Alternate Path:

No Applicability:

RO/SRO Safety Function:

5 - Containment Integrity Setting:

Simulator Validated:

7 minutes

References:

EOP-SPI 3.2 Rev 1 Tasks:

002-503-05-01 Initiate SPMU Task Standard:

Initiate SPMU per EOP-SPI 3.2 Required Material:

EOP-SPI 3.2, SPMU Initiation K / A Data:

295030 - Ability to operate and/or monitor the following as they apply to Low Suppression Pool Water Level: EA1.04 Suppression pool make-up system: Mark-III. Importance: RO 4.0 / SRO 4.0

1.

Setup Instructions: Reset simulator to a power IC. Insert Malfunctions PC04 to 35%,

h13p60118ad3 to OFF, h13p60118e2 to ON, mv011e12f0001 to FAI, ry02_g43k1 to FAI, and ry02_g43k2 to FAI. Insert Remote Function LP03 to OUT. Place simulator in RUN and allow SP level to lower to < 17.8. Take a snapshot. (For 2017 ILO Exam, reset to IC no other actions needed)

2.

Location / Method: Simulator / Perform

3.

Initial Condition: The Plant is at rated power. A leak in the LPCS Suppression Pool Suction line is causing Suppression Pool level to lower. All attempts to stop the leak have failed. The US has entered EOP-2 Primary Containment Control for lowering Suppression Pool level.

4.

Initiating Cue: The Unit supervisor directs you the Reactor Operator to initiate SPMU per EOP-SPI 3.2.

Start Time:

End Time:

Candidate:

OT-3701-G43_001_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 EOP-SPI 3.2, SPMU Initiation 1.0 VERIFY the following keylock switches are in AUTO:

  • SUPR POOL MAKE-UP A LOGIC G43-S6
  • SUPR POOL MAKE-UP B LOGIC G43-S8 Standard:

The Operator locates correct switches on H13-P601 and verifies in AUTO.

Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 2 2.0 IF a LOCA signal is present, THEN GO TO Step 5.0 of this instruction.

Standard:

The Operator verifies no LOCA signal present and proceeds to Step 3.0.

Instructor Cue:

If asked, NO LOCA signal present.

Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-G43_001_RO Rev 0 Step 3 NOTE Placing SPMU test keylock switches in TEST with the SPMU mode switch in AUTO will automatically open SPMU shutoff valves when a Suppression Pool low-low level condition exists.

3.0 AT H13-P869, PLACE SUPR POOL MAKEUP A FULL FLW TEST PERM keylock switch in TEST.

G43-S13 Critical Step:

Operator places G43-S13 in TEST.

Instructor Cue:

None Notes:

Switch G43-S13 is located on East wall of Simulator SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 4 4.0 AT H13-P868, PLACE SUPR POOL MAKEUP B FULL FLW TEST PERM keylock switch in TEST.

G43-S12 Critical Step:

Operator places G43-S12 in TEST.

Instructor Cue:

None Notes:

Switch G43-S12 is located on East wall of Simulator SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-G43_001_RO Rev 0 Step 5 5.0 PERFORM Steps 6.0 and 7.0 in any order with the priority being a division that has electric power readily available 6.0 IF required to Initiate Division 1 SPMU, THEN PERFORM the following:

6.1 IF AC power is lost to Division 1 480 Volt AC busses AND Bus EF-1-E-1 is energized, THEN REFER TO Division 3 To Division 1 480 Volt Crosstie, ONI-SPI C-6 concurrently with this procedure to apply power to Division 1 480 Volt AC busses.

6.2 ARM AND DEPRESS the SUPR PL MAKE-UP A MANUAL INITIATION pushbutton.

G43-S5 Critical Step:

Operator Arms and Depresses G43-S5.

Instructor Cue:

None Notes:

Step 6.1 is N/A.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

NOTES

  • Normally BOTH divisions of SPMU are initiated. If Division 2 SPMU is successful and alternate power is required to initiate Division 1 SPMU, then it is NOT required to initiate Division 1 SPMU as the SPMU would be completed prior to being able to complete the next step.
  • Division 3 to Division 1 480 Volt Crosstie, ONI-SPI C-6 provides temporary power to Initiate Suppression Pool Makeup. When power is needed to a component the infield operator needs to be notified so actions to power the component can be completed.

OT-3701-G43_001_RO Rev 0 Step 6 6.3 CONFIRM the following valves are OPEN:

  • SUPR PL MAKE-UP A FIRST SHUTOFF.

G43-F030A

  • SUPR PL MAKE-UP A SECOND SHUTOFF.

G43-F040A Standard:

The Operator confirms G43-F030A and G43-F040A open.

Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-G43_001_RO Rev 0 Step 7 7.0 IF required to Initiate Division 2 SPMU, THEN PERFORM the following:

7.1 IF AC power is lost to Division 2 480 Volt AC busses AND Bus EF-1-E-1 is energized, THEN REFER TO Division 3 To Division 2 480 Volt Crosstie, ONI-SPI C-7 concurrently with this procedure to apply power to Division 2 480 Volt AC busses.

7.2 ARM AND DEPRESS the SUPR PL MAKE-UP B MANUAL INITIATION pushbutton.

G43-S7 Critical Step:

Operator Arms and Depresses G43-S7.

Instructor Cue:

None Notes:

Step 7.1 is N/A.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

NOTES

  • Normally BOTH divisions of SPMU are initiated. If Division 1 SPMU is successful and alternate power is required to initiate Division 2 SPMU, then it is NOT required to initiate Division 2 SPMU as the SPMU would be completed prior to being able to complete the next step.
  • Division 3 to Division 2 480 Volt Crosstie, ONI-SPI C-7 provides temporary power to Initiate Suppression Pool Makeup. When power is needed to a component the infield operator needs to be notified so actions to power the component can be completed.

OT-3701-G43_001_RO Rev 0 Step 8 7.3 CONFIRM the following valves are OPEN:

  • SUPR PL MAKE-UP B FIRST SHUTOFF.

G43-F030B

  • SUPR PL MAKE-UP B SECOND SHUTOFF.

G43-F040B Standard:

The Operator confirms the SPMU valves are open and that suppression pool level is rising.

Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-G43_001_RO Rev 0 Step 9 8.0 IF the CNTMT POOLS SUPP ISOL valve is OPEN, THEN ISOLATE flow to the upper Pools as follows: G41-F100 8.1 IF AC power is lost to Division 1 480 Volt AC busses AND Bus EF-1-E-1 is energized, THEN REFER TO Division 3 To Division 1 480 Volt Crosstie, ONI-SPI C-6 concurrently with this procedure to apply power to Division 1 480 Volt AC busses.

8.2 VERIFY CLOSED CNTMT POOLS SUPP ISOL.

G41-F100 Critical Step:

Operator closes G41-F100.

Instructor Cue:

None Notes:

Step 8.1 is N/A.

Terminate the JPM.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Reports to Unit Supervisor that EOP-SPI 3.2 is complete and SPMU is in progress.

Evaluation Results:

SAT_____

UNSAT_____

End Time:

NOTE Division 3 to Division 1 480 Volt Crosstie, ONI-SPI C-6 provides temporary power to isolate flow to the upper pools. When power is needed to a component the infield operator needs to be notified so actions to power the component can be completed.

OT-3701-G43_001_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

  • The Plant is at rated power.
  • A leak in the LPCS Suppression Pool Suction line is causing Suppression Pool level to lower.
  • All attempts to stop the leak have failed.

INITIATING CUE:

The Unit Supervisor directs you the Reactor Operator to initiate SPMU per EOP-SPI 3.2.

OT-3701_M25_502 Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:

M25/M26 Control Room Ventilation and Emergency Recirc System Time Critical:

No Alternate Path:

Yes Applicability:

RO/SRO Safety Function:

9 - Radioactivity Release Validated Time:

19 Minutes

References:

SOI-M25/26 Rev. 24, ARI-H13-P904-0002 Rev 11, NOP-OP-1002 Rev 12, &

Cyc-14 T/O EPY-M25-005 Required Material:

SOI-M25/26, Control Room HVAC And Emergency Recirculating System Task:

037-532-01-01 Shift from (Manual) EMERG RCIRC to NORM 037-524-01-01 Respond to Alarms Task Standard:

Shift Control Room HVAC from Emergency Recirc to NORMAL and respond to low flow alarm.

K/A:

290003 - A2.03 Ability to (a) predict the impacts of the following on the CONTROL ROOM HVAC; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Initiation/reconfiguration failure. Importance: RO 3.4 SRO 3.6

1.

Setup Instructions: Reset simulator to any IC with M25A running in ER and M25B S/D to Secured Status. (For 2017 ILO Exam, reset to IC 64) Insert Schedule file JPM-M25-502.sch and verify Event file JPM-M25-502.evt loads. Acknowledge alarms. Place a Yellow Switch Caps on M25 B Supply Fan and M26 B Emergency Recirc Fan. Provide Operator with Yellow copy of SOI-M25/26.

2.

Location / Method: Simulator / Performance

3.

Initial Condition: Control Room Ventilation is running in Emergency Recirc for a monthly Div. 2 diesel run, which is now complete. CR HVAC Supply Fan B is tagged out to replace a broken belt.

4.

Initiating Cue: The Unit Supervisor directs you, the Reactor Operator, to shift Control Room Ventilation to NORMAL.

Start Time:

Stop Time:

Candidate:

OT-3701_M25_502 Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SOI-M25/26, Control Room HVAC And Emergency Recirculating System 7.6 Shifting From EMERG RCIRC To NORM 7.6.1 IF the CONT RM HVAC A INBD SUPP DMPR is closed, THEN PERFORM Reset of Emergency Recirculation Auto Initiation.

M25-F020B 7.6.2 IF the CONT RM HVAC B INBD SUPP DMPR is closed, THEN PERFORM Reset of Emergency Recirculation Auto Initiation.

M25-F020A 7.6.3 IF the electric heater is in service, THEN PERFORM the following:

Standard:

Steps 7.6.1, 7.6.2, and 7.6.3 are N/A.

Instructor Cue:

None.

Notes:

None.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701_M25_502 Rev 0 Step 2 7.6.4 PLACE both of the following in NORM:

  • CONT RM HVAC TRAIN A MODE SELECT M25-S7
  • CONT RM HVAC TRAIN B MODE SELECT M25-S8 Critical Step:

Operator places M25-S7 in NORM.

Instructor Cue:

None.

Notes:

Operator should place M25-S8 in NORM, as this causes multiple B side dampers to realign. However, with M25B train S/D, placing & M25-S8 in NORM will not have any effect and is not Critical.

About 60 seconds after placing S7 in NORM, CONT RM HVAC RETURN FAN A, M25-C002A will alarm on Low Flow.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 3 7.6.1 CONFIRM components are in the proper configuration in accordance with the appropriate attachment:

  • Train A in Operation and Train B Shutdown (Attachment 5)

Standard:

Operator commences verifying component lineup.

Instructor Cue:

If asked to report positions of M24-F051A & F051B, - Both open.

Notes:

Return Fan low flow annunciator (P904-02-A1) will alarm while operator is verifying component lineup.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701_M25_502 Rev 0 Step 4 ARI-H13-P904-0002-A1 1.0 CAUSE OF ALARM 1.1 Flow through CONT RM HVAC RETURN FAN A, M25-C002A, less than 24,000 CFM, as sensed by M25-N700A, when fan is running 4.0 SUBSEQUENT OPERATOR ACTIONS 4.1 DETERMINE 0M25 flow.

M25-K120A 4.2 REFER TO SOI-M25/26 and SHIFT to HVAC Train B in the desired operating mode.

Standard:

Operator reviews ARI and suggests course of action.

Instructor Cue:

If Operator requests flow data from NLO, respond, Flow is 20,000 CFM.

If Operator asks NLO about M25-F110A, report it does not appear to be full open.

If Operator does not suggest a course of action, ask what they recommend.

Notes:

Per the ARI, the Operator should shift to the B train in the NORMAL mode. However, since B train Supply and Emergency Recirc fans are tagged out, the shift cannot occur. In this instance, shifting A train back to Emergency Recirc mode will solve the problem as ER Mode stops the Return Fan.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701_M25_502 Rev 0 Step 5 SOI-M25/26, Control Room HVAC And Emergency Recirculating System 7.5 Shifting From NORM Or SMOKE CLEAR To EMERG RCIRC 7.5.1 PLACE both of the following in EMERG RCIRC:

  • CONT RM HVAC TRAIN A MODE SELECT M25-S7
  • CONT RM HVAC TRAIN B MODE SELECT M25-S8 Critical Step:

Operator places M25-S7 in EMERG RCIRC.

Instructor Cue:

None Notes:

Operator should place M25-S8 in EMERG RECIRC, as this causes multiple B side dampers to realign. However, with M25B train S/D, placing & M25-S8 in EMERG RCIRC will not have any effect and is not Critical.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 6 7.5.2 CONFIRM components are in the proper configuration in accordance with the appropriate attachment:

  • Train A in Operation and Train B Shutdown (Attachment 5)

Standard:

Operator commences verifying component lineup.

Instructor Cue:

If asked to report positions of M24-F051A & F051B, - Both Closed.

Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701_M25_502 Rev 0 Step 7 ATTACHMENT 5 - Configuration with Train A in Operation and Train B Shutdown Train A Components M25-S7 & S8 Position NORM EMERG RCIRC SMOKE CLEAR CONT RM HVAC RETURN FAN A, M25-C002A ON OFF ON Critical Step:

Operator stops Return Fan A.

Instructor Cue:

If Operator does not stop Return Fan A or doesnt suggest a course of action, ask what they recommend.

If Operator contacts NLO to ask if Return fan is still running, inform Operator that the Return fan is running.

Notes:

During confirmation of components the operator should notice that the Return Fan failed to stop and M25-F110A damper is in mid-position and should inform evaluator that he is taking the fan control switch to STOP.

Per NOP-OP-1002, Conduct of Operations, Step 4.10.3 Automatic System Response Versus Manual Actions:

5. If automatic actions fail to occur when required, it is the responsibility of the operator to take manual actions to perform the system or component function. Pump or component auto start failures are examples where operators are expected to take manual action.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701_M25_502 Rev 0 Step 7 7.5.3 IF train is being shifted due to an emergency condition, THEN TAKE the following to CLOSE:

7.5.4 Control Room relative humidity is 70%

Control Room relative humidity is unknown TAKE the CONT RM EMG RCIRC ELEC HTG CONT to START.

M26-D001A M26-D001B Standard:

Steps 7.5.3 and 7.5.4 are N/A.

Instructor Cue:

None Notes:

Operator will check humidity on ICS.

Terminate the JPM SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue:

A Train of Control Room Ventilation is running in Emergency Recirc and Return Fan A is shutdown.

Evaluation Results:

SAT_____

UNSAT_____

End Time:

OT-3701_M25_502 Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

  • Control Room Ventilation is running in Emergency Recirc for a monthly Div. 2 diesel run, which is now complete.
  • CR HVAC Supply Fan B is tagged out to replace a broken belt.

INITIATING CUE:

The Unit Supervisor directs you, the Reactor Operator, to shift Control Room Ventilation to NORMAL.

OT-3701-D51_303_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:

D51 Seismic Monitoring System Time Critical:

Yes Alternate Path:

No Applicability:

RO/SRO Safety Function:

2 - Reactor Water Inventory Control Setting:

Plant (non-RRA)

Validated Time:

25 Minutes

References:

ONI-D51 Rev 20 SOI-P72 Rev 9 Required Material ONI-D51 - Earthquake Attachment 3 Task:

029-502-01-04 Operate Plant Underdrain Pumps 276-504-01-01 Monitor the Service Water System Operation 277-508-01-01 Monitor ESW System Operation Task Standard:

Perform outside inspection for earthquake damage and shutdown Underdrain Pump per ONI-D51 Attachment 3.

K/A Data:

203000 Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: Injection Mode: - K6.10, Component cooling water systems IR 3.0 / 3.1.

219000 Ability to (a) predict the impacts of the following on the RHR/LPCI: Torus/Suppression Pool Cooling Mode; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: - A2.15 Loss of, or inadequate, heat exchanger cooling flow IR 3.3 / 3.4

1.

Setup Instructions: Provide Operator with a copy of ONI-D51 Attachment 3

2.

Location / Method: Plant / Simulation

3.

Initial Condition: OBE Earthquake has occurred; Five minutes ago, the Unit Supervisor entered ONI-D51.

4.

Initiating Cue: The Unit Supervisor directs you as a Plant Operator to perform of ONI-D51. This JPM is Time Critical Start time End time Operator

OT-3701-D51_303_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 ONI-D51 - Earthquake - Outside Actions 3.0 PROCEDURE 3.1 ESW Inspection 3.1.1 OBSERVE the following for possible indication of intake structure, intake tunnel or discharge tunnel damage:

  • ESW forebay level
  • ESW forebay water clarity
  • Discharge tunnel entrance water level Critical Step:

Operator performs ESW inspection within 30 minutes.

Instructor Cue:

ESW Forebay level is approximately 1 foot lower than recorded on Rounds this morning. Other conditions are as-found Notes:

ESW forebay level gauge is under north steps in ESW pumphouse. ESW forebay inspection must be done north of the screens. Service Water Weir markings are in 1 foot increments. (Water level is normally 18 to 24 over the weir).

Operator should inform the Control Room when ESW inspection done.

SAT ___

UNSAT ___

Comment(s): Time Complete for Time Critical Step ___________________

NOTE The first ESW Inspection is required to be completed within 30 minutes of an OBE.

OT-3701-D51_303_RO Rev 0 Step 2 3.1.2 CONTACT Engineering if any indication of blockage is noted.

3.1.3 REPEAT the inspection in Step 3.1.1 within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> and once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter UNTIL Engineering has determined the inspections are no longer necessary.

Standard:

Operator contacts Engineering to report lower forebay level.

Instructor Cue:

Respond as Engineering Notes:

None.

SAT ___

UNSAT ___

Step 3 3.2 Underdrain Pump Shutdown 3.2.1 PERFORM the following:

  • VERIFY UNDERDRAIN PUMPS control switch in OFF P72-C001E
  • VERIFY all Temporary Underdrain Pumps are shutdown at the local control panels.

Critical Step:

Operator simulates placing the P72-C001E in OFF, and verifying all temporary underdrain pumps are shutdown.

Instructor Cue:

  • Initially, P72-C001E is in AUTO.
  • P72-C001E Switch in OFF (when operator simulates placing in OFF)
  • Temporary underdrain pumps are shutdown.

Notes:

Terminate the JPM.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

NOTE Underdrain Pumps, P72-C001E, is controlled from Underdrain Pump Local Control Station H51-P338E at Unit 1 Aux. Boiler Bldg. Elev. 620'.

OT-3701-D51_303_RO Rev 0 Terminating Cue: Operator completes ESW inspection within 30 minutes, and placed Underdrain Pump switch in OFF.

Evaluation Results: SAT_____

UNSAT_____

End time

OT-3701-D51_303_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

  • Five minutes ago, the Unit Supervisor entered ONI-D51.

INITIATING CUE:

The Unit Supervisor directs you as a Plant Operator to perform Attachment 3 of ONI-D51.

This JPM is Time Critical

OT-3701-P54_003_RO Rev 0 JOB PERFORMANCE MEASURE SETUP SHEET System:

Fire Protection Time Critical:

No Alternate path:

No Applicability:

RO/SRO Safety Function:

8 - Plant Service Systems Setting:

Plant (RRA)

Validated:

28 minutes

References:

SOI-P54 (WTR) Rev 23 Task Standard:

Initiate Deluge manually on Main Transformer C and Isophase Bus Duct per SOI-P54(WTR)

Task #:

286-511-04-04 Perform Manual Initiation of Transformer, Isophase Bus Duct, or Hydrogen Seal Oil Deluge System Required Material:

SOI-P54 (WTR), Fire Protection System - Water Section 7.2 K / A Data:

600000 AK1.02 Knowledge of the operation applications of the following concepts as they apply to Plant Fire On Site: Fire Fighting 2.9 / 3.1 AA1.08 Ability to operate and / or monitor the following as they apply to Plant Fire On Site: Firefighting equipment used on each class of fire 2.6 / 2.9

1.

Setup Instructions: When operator requests, provide operator with copy of SOI-P54(WTR).

2.

Location / Method: Plant / Simulation

3.

Initial Condition: A fire has been reported in C phase of the Main Transformer. The US has entered ONI-P54, FIRE. The Main Transformers and main generator have been deenergized.

4.

Initiating Cue: The Unit Supervisor directs you as the Field Supervisor to initiate deluge on the C Main Transformer.

Start Time:

End Time:

Candidate:

OT-3701-P54_003_RO Rev 0 JPM BODY SHEET Standard: Performer obtains or simulates obtaining all materials, procedures, tools, keys, radios, etc before performing task.

Standard: Performer follows management expectations with regards to safety and communication standards.

Step 1 SOI-P54(WTR), FIRE PROTECTION SYSTEM - WATER 2.0 PRECAUTIONS AND LIMITATIONS 2.5 When any Main Transformer Deluge System is initiated for the purpose of combating a fire, the Isophase Bus Duct Deluge shall also be initiated.

2.16 The Deluge Systems of the three Main Transformers AND two Startup Transformers shall be aligned to support manual initiation only.

Standard:

The Operator reviews SOI-P54(WTR) and determines deluge must be manually initiated.

Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-P54_003_RO Rev 0 Step 2 7.2 Emergency/Manual Deluge Initiation (Transformer, Isophase Bus Duct, and Hydrogen Seal Oil)

Standard:

The Operator determines that the Isophase Bus Duct Deluge shall also be initiated.

Instructor Cue:

None Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

NOTES

  • Attachment 14 contains a listing of the components used in this section.
  • The following section may be performed by the Fire Brigade, Fire Protection Personnel, Operators or other individuals as required.
  • When any Main Transformer Deluge System is initiated for the purpose of combating a fire, the Isophase Bus Duct Deluge shall also be initiated.

OT-3701-P54_003_RO Rev 0 Step 2 7.2.1 VERIFY OPEN the (C Main Transformer deluge) system Supply Isolation Valve.

1P54-F900 Critical Step:

Operator refers to Attachment 14 to obtain correct valve number and simulates opening the C Main Transformer Supply Isolation valve.

Instructor Cue:

  • As Operator is opening valve, The Supply Isolation Valve stem is extending.
  • The Supply Isolation Valve is Open.
  • If asked, no flow noise is heard.

Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 3 7.2.2 OPEN the (C Main Transformer) Manual Initiation Valve door at the associated deluge valve.

1P54-F904 Standard:

Operator simulates breaking door seal and simulates opening Manual Initiation Valve door.

Instructor Cue:

None Notes:

When operator simulates opening valve door, show picture #1 of Manual Initiation Valve.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-P54_003_RO Rev 0 Step 4 7.2.3 PULL the (C Main Transformer) valve forward.

1P54-F904 Critical Step:

Operator refers to Attachment 14 to obtain correct valve number and simulates opening the C Main Transformer Manual Initiation valve.

Instructor Cue:

  • The Manual Initiation Valve is Open.
  • If asked, flow noise is heard when BOTH the Supply Isolation and the Manual Initiation Valves are opened.

Notes:

When operator identifies Manual Initiation Valve enclosure, show Picture #1 of Manual Initiation Valve.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 5 7.2.1 VERIFY OPEN the (Isophase Bus Duct deluge) system Supply Isolation Valve.

1P54-F1460 Critical Step:

Operator refers to Attachment 14 to obtain correct valve number and simulates opening the Isophase Bus Duct Supply Isolation valve.

Instructor Cue:

  • As Operator is opening valve, The Supply Isolation Valve stem is extending.
  • The Supply Isolation Valve is Open.
  • If asked, no flow noise is heard.

Notes:

None SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-P54_003_RO Rev 0 Step 6 7.2.2 OPEN the (Isophase Bus Duct) Manual Initiation Valve door at the associated deluge valve.

Standard:

Operator simulates breaking door seal and simulates opening Manual Initiation Valve door.

Instructor Cue:

None Notes:

When operator simulates opening valve door, show picture #2 of Manual Initiation Valve.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Step 7 7.2.3 PULL the (Isophase Bus Duct) valve forward.

1P54-F1464 Critical Step:

Operator refers to Attachment 14 to obtain correct valve number and simulates opening the Isophase Bus Duct Manual Initiation valve.

Instructor Cue:

  • The Manual Initiation Valve is Open.
  • If asked, flow noise is heard when BOTH the Supply Isolation and the Manual Initiation Valves are opened.

Notes:

When operator identifies Manual Initiation Valve enclosure, show Picture #2 of Manual Initiation Valve.

SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

OT-3701-P54_003_RO Rev 0 Step 8 7.2.4 IF Manual-Electric Initiation is desired, THEN BREAK the glass on the Manual Release Station for the associated deluge system.

Standard:

Step 7.2.4 is N/A as Manual-Electric Initiation is not available.

Instructor Cue:

None Notes:

Terminate JPM SAT ___

UNSAT ___

Comment(s): ________________________________________________________________

Terminating Cue: Manual deluge on Main Transformer C and the Isophase Bus Duct has been initiated per SOI-P54 section 7.2.

Evaluation Results:

SAT_____

UNSAT_____

End Time

OT-3701-P54_003_RO Rev 0 Picture # 1

OT-3701-P54_003_RO Rev 0 Picture # 2

OT-3701-P54_003_RO Rev 0 JPM CUE SHEET INITIAL CONDITIONS:

  • The US has entered ONI-P54, FIRE.

INITIATING CUE:

The Unit Supervisor directs you as the Field Supervisor to initiate deluge on the C Main Transformer.

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