ML23038A166
| ML23038A166 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/12/2023 |
| From: | NRC/RGN-III/DORS/OB |
| To: | Energy Harbor Nuclear Corp |
| Greg Roach | |
| Shared Package | |
| ML21188A233 | List: |
| References | |
| Download: ML23038A166 (95) | |
Text
OT-3701-B21_008_RO Rev A JOB PERFORMANCE MEASURE SETUP SHEET System:
B21 - Main and Reheat Steam System Time Critical:
No Alternate Path:
No Setting:
Simulator Applicability:
RO/SRO Safety Function:
3 - Reactor Pressure Control Validated:
15 minutes
References:
SOI-B21 Rev 23 Required Materials: SOI-B21, Nuclear Steam Supply Shutoff, Automatic Depressurization and Nuclear Steam Supply Systems Tasks:
239-527-01-01 Operate MSIVs from H13-P601 Task Standard:
Slow close A OTBD MSIV by placing 1B21-F028A control switch in TEST then depressing & holding 1B21H-S4A PB until A OTBD MSIV is shut then placing 1B21-F028A control switch in Close. Then slow close A INBD MSIV by placing 1B21-F022A control switch in TEST then depressing & holding 1B21H-S3A PB until A INBD MSIV is shut then placing 1B21-F028A control switch in Close per SOI-B21 K / A Data:
239001, Main and Reheat Steam System, A4.01 Ability to manually operate in the control room: MSIVs RO 4.4.
- 1.
Setup Instructions: Reset simulator to IC-157 with Reactor Power less than 75%. All MSIVs open.
If/when candidate identifies correct procedure (SOI-B21, Section 6.2) provide him/her with a YELLOW copy of the procedure.
- 2.
Location / Method: Simulator / performance
- 3.
Initial Condition: Plant conditions are as found. There is a small instrument line crack on Main Steam Line A between the Inboard and Outboard MSIV.
- 4.
Initiating Cue: The Unit Supervisor directs you as a Reactor Operator to slow close the A Inboard and Outboard MSIVs.
Start Time:
End Time:
Candidate:
OT-3701-B21_008_RO Rev A 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-B21 - Nuclear Steam Supply Shutoff, Automatic Depressurization and Nuclear Steam Supply Systems 6.2 Slow Closure of Main Steam Isolation Valves 6.2.1 IF closing one MSIV at power, THEN REVIEW the Precautions and Limitations of IOI-3.
Standard:
Verifies Reactor Power less than 75%.
Instructor Cue:
None Notes:
IOI-3 P&L 2.11 states limit maximum thermal reactor power to 75% with one main steam line out of service.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-B21_008_RO Rev A Step 2 6.2.2 If one or more outboard MSIV(s) need to be closed, THEN PERFORM the following:
6.2.2.a If slow closing MSL A OTBD MSIV, THEN PERFORM the following:
6.2.2.a.1 PLACE the MSL A OTBD MSIV in TEST. 1B21-F028A Critical Step:
Operator places the control switch for MSL A OTBD MSIV, 1B21-F028A in TEST.
Instructor Cue:
None Notes:
Closing an MSIV may cause a perturbation in Rx level/feedwater. If so, inform Candidate that another operator will control feedwater.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 3 6.2.2.a.2 DEPRESS AND HOLD the MSL A OTBD MSIV TEST. 1B21H-S4A 6.2.2.a.3 CONFIRM the MSL A OTBD MSIV closes. 1B21-F028A Critical Step:
Operator depresses and holds 1B21H-S4A Test pushbutton until 1B21-F028A indicates closed.
Instructor Cue:
None Notes:
Releasing the TEST pushbutton prior to placing the MSIV control switch in CLOSE will allow the MSIV to reopen.
It takes approximately 50 seconds for MSIV to shut.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-B21_008_RO Rev A Step 4 6.2.2.a.4 PLACE the MSL A OTBD MSIV in CLOSE. 1B21-F028A Critical Step:
Operator places the control switch for MSL A OTBD in close.
Instructor Cue:
None Notes:
When taking switch from TEST through AUTO to CLOSE, the RED light may illuminate momentarily depending how quickly the Candidate manipulates the switch. This is not a failure as long as the TEST pushbutton remains depressed and the MSIV control switch is placed in CLOSE.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 5 6.2.2.a.5 RELEASE the MSL A OTBD MSIV TEST. 1B21H-S4A Standard:
Operator releases 1B21H-S4A.
Instructor Cue:
None Notes:
If Operator releases switch to early and MSIV strokes open JPM may be a failure if the steps are not reperformed correctly.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-B21_008_RO Rev A Step 6 6.2.3 IF one or more inboard MSIV(s) need to be closed, THEN PERFORM the following:
6.2.3.a IF slow closing MSL A INBD MSIV, 1B21-F022A THEN PERFORM the following:
6.2.3.a.1 PLACE the MSL A INBD MSIV in TEST. 1B21-F022A Critical Step:
Operator places the control switch for MSL A INBD MSIV, 1B21-F022A in TEST.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 7 6.2.3.a.2 DEPRESS AND HOLD the MSL A INBD MSIV TEST. 1B21H-S3A 6.2.3.a.3 CONFIRM the MSL A INBD MSIV closes. 1B21-F022A Critical Step:
Operator depresses and holds 1B21H-S3A, Test pushbutton until 1B21-F022A indicates closed.
Instructor Cue:
None Notes:
Releasing the TEST pushbutton prior to placing the MSIV control switch in CLOSE will allow the MSIV to reopen.
It takes approximately 50 seconds for MSIV to shut.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-B21_008_RO Rev A Step 8 6.2.3.a.4 PLACE the MSL A INBD MSIV in CLOSE. 1B21-F022A Critical Step:
Operator places the control switch for MSL A INBD in close.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 9 6.2.3.a.5 RELEASE the MSL A INBD MSIV TEST. 1B21H-S3A Standard:
Operator releases 1B21H-S3A Instructor Cue:
None Notes:
If Operator releases switch to early and MSIV strokes open JPM may be a failure if the steps are not reperformed correctly.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue: Main Steam Line A Inboard and Outboard MSIVs have been slow closed.
Evaluation Results:
SAT_____
UNSAT_____
End Time:
OT-3701-B21_008_RO Rev A JPM CUE SHEET INITIAL CONDITIONS:
Plant conditions are as found.
There is a small instrument line crack on Main Steam Line A between the Inboard and Outboard MSIV.
INITIATING CUE:
The Unit Supervisor directs you as a Reactor Operator to slow close the A Inboard and Outboard MSIVs.
OT-3701-B33_505B_RO Rev A JOB PERFORMANCE MEASURE SETUP SHEET System:
B33 Reactor Recirculation Time Critical:
No Alternate Path:
Yes Setting:
Simulator Applicability:
RO/SRO Safety Function:
1 - Reactivity Control Validated Time:
23 Minutes
References:
SOI-B33 Rev. 45 Required Material:
SOI-B33 Reactor Recirculation System Task:
202-534-01-01 Startup Reactor Recirculation HPU Task Standard:
Startup both subloops of B HPU, place Subloop 2 in LEAD, take RCIRC FCV MOTION INHIBIT RESET to B position, then Shutdown B HPU when unexpected FCV motion occurs.
K/A:
202002 - Recirculation Flow Control System A4.02, Ability to manually operate and/or monitor in the control room: Hydraulic power unit (BWR 5, 6)
IR RO 3.4 and A4.11 Ability to manually operate and/or monitor in the control room: System lockups/lockouts IR RO 3.8
- 1.
Setup Instructions: Reset simulator to IC-156 for 2022 ILO Exam. Load Schedule File JPM B33-505.sch. Verify Event File JPM B33-505.evt loads.
- 2.
Location / Method: Simulator / Performance
- 3.
Initial Condition: Plant operating at power. Flow control Valve B was locked up 90 minutes ago for replacement of the B2 Operate solenoid. HPU B was shutdown IAW SOI-B33 Section 6.4. B2 Operate solenoid replacement is now complete. Restart of FCV B HPU is required for retest of the solenoid. HPU B was not isolated.
- 4.
Initiating Cue: Unit Supervisor directs you an extra Reactor Operator to perform Hydraulic Power Unit (HPU) B Startup with Subloop 2 in Lead and Subloop 1 in Standby.
Start:
Stop:
Candidate:
OT-3701-B33_505B_RO Rev A 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-B33 REACTOR RECIRCULATION SYSTEM 4.3 Hydraulic Power Unit (HPU) B Startup NOTES
- Simultaneously depressing both Subloop 1 AND 2 READY buttons will reset the HPU trip first hit indicators inside 1H13-P614.
- Fyrquel (HPU hydraulic oil) and its radiolytic decomposition products are known to attack zircalloy cladding. Personnel should be available to check for fyrquel leaks when performing an HPU startup following an extended outage or maintenance.
4.3.1 WHILE starting HPU B, MONITOR Flow Control Valve position.
FCV B 4.3.2 CONFIRM there are no fuse failure lights illuminated on the respective Recirculation Flow Control HPU Modicon Output Modules located inside 1H13-P614.
B 4.3.3 VERIFY HPU B is shutdown.
4.3.4 IF HPU B is isolated to limit FCV B drifting, Standard:
Candidate informs ATC to monitor FCV position, checks for fuse failure lights in back of P614, and observes HPU status lights on front of P614 to determine HPU B is shutdown.
Instructor Cue:
If asked, no fuse failure lights are illuminated.
If asked, there are no leaks at the HPU.
Notes:
Step 4.3.4 is N/A.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-B33_505B_RO Rev A Step 2 NOTES The VALVE POS EXCESSIVE RATE OF CHANGE LOCKUP card, is located in the Recirculation Flow Control Instrument Panel, 1H13-P634.
4.3.5 CHANNEL 1 red light is ON CHANNEL 2 red light is ON R/C/L Rack2 Nest 5 THEN DEPRESS the RESET button located immediately below the ON light.
4.3.5.a CONFIRM the red light is out.
Standard:
Candidate observes both red lights are extinguished.
Instructor Cue:
None Notes:
Card is below the labels.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 3 4.3.6 IF both subloops are being recovered, THEN PERFORM the following:
4.3.6.a SIMULTANEOUSLY DEPRESS the following buttons on NSSS Recorder Panel 1H13-P614:
HPU B.
- Subloop 1 READY
- Subloop 2 READY Critical Step:
Candidate simultaneously depresses both READY pushbuttons.
Instructor Cue:
If asked, no flow control valve motion observed.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-B33_505B_RO Rev A Step 4 4.3.6.b VERIFY the following:
HPU B
- Subloop 1 READY light illuminates Sub loop 1
- Subloop 1 MAINTENANCE light extinguishes Sub loop 1
- Subloop 2 READY light illuminates Subloop 2
- Subloop 2 MAINTENANCE light extinguishes Subloop 2
- FCV B REDNT SUB LOOP INOP alarm clears at 1H13-P680 4.3.7 IF only 1 subloop will be recovered, THEN PERFORM the following:
Standard:
Candidate verifies conditions in Step 4.3.6.b are met.
Instructor Cue:
None Notes:
Step 4.3.7 is N/A.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-B33_505B_RO Rev A Step 5 NOTES
- Readings outside the specified ranges may indicate a failure of the Operate/Isolate valve to reposition.
- For coils which are supposed to be energized, higher than normal current indicates the valve is stuck either partially OR fully in the opposite position.
- Lower than normal current indicates a possible solenoid failure.
4.3.8 CONFIRM current readings for HPU B on the B33 Isolate/Operate Meter Panel in the back of 1H13-P614 are in the following bands:
- B1 ISOLATE 0.5 - 0.75 amps AC.
- B1 OPERATE 0.0 amps AC.
- B2 ISOLATE 0.5 - 0.75 amps AC.
- B2 OPERATE 0.0 amps AC.
Standard:
Candidate confirms the meters are reading within specified ranges.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 6 4.3.9 DEPRESS the oncoming subloop PUMP MTR RUN/FAN MTR RUN button for HPU B at 1H13-P614 Subloop 2 Critical Step:
Candidate depresses PUMP MTR RUN/FAN MTR RUN pushbutton for Subloop 2.
Instructor Cue:
If asked, no flow control valve motion observed.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-B33_505B_RO Rev A Step 7 4.3.10 VERIFY the following for the oncoming subloop:
Subloop 2
- PRESSURIZED light comes on.
NOTES
- After a prolonged HPU shutdown, oil pressure may take 30 to 60 seconds to reach normal operating pressure (1850 to 1950 psig).
- The Actuator Drain amber light may stay illuminated until the oil temperature is in the normal band.
- Oil temperature may increase to the OIL WARM alarm setpoint before stabilizing at the normal operating temperature (120 to 140°F). If the non-operating loop is in standby, an automatic transfer will occur.
4.3.11 IF both subloops were recovered (Step 4.3.3 was performed), AND an automatic transfer is NOT desired, THEN PERFORM the following Standard:
Candidate confirms the status of the above listed lights.
Instructor Cue:
If asked, there are no leaks at the HPU.
If asked oil temperature is 125 °F and stable.
Notes:
Step 4.3.11 is N/A. However, if the Candidate misreads the NOTES (above), they may elect to perform Step 4.3.11. There is no consequence to performing this Step.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-B33_505B_RO Rev A Step 8 4.3.12 DEPRESS the running Subloop LEAD button for the HPU on 1H13-P614.
Subloop 2 Critical Step:
Candidate depresses Subloop 2 LEAD pushbutton.
Instructor Cue:
If asked, no flow control valve motion observed.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 9 4.3.13 CONFIRM the LEAD button backlights.
Subloop 2 4.3.14 CONFIRM the FCV B HPU INOP alarm clears.
4.3.15 CONFIRM the standby Subloops pressure indicates 500 psig (local).
Subloop 1 4.3.16 CONFIRM the following lights for the LEAD Subloop on P614 extinguish within several minutes:
Subloop 2
- PRESS FILTER.
- RETURN LINE FILTER.
4.3.17 IF the HPU has been shutdown for more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4.3.18 IF LIMITER ERROR is not 0%,
Standard:
Candidate confirms the LEAD button backlights, the FCV B HPU INOP alarm clears, the standby Subloops pressure indicates 500 psig, and the FILTER lights extinguish.
Instructor Cue:
For Step 4.3.15, when asked, subloop pressure indicates 350 psig.
Notes:
Steps 4.3.17 and 4.3.18 are N/A SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-B33_505B_RO Rev A Step 10 NOTE With a 0% Servo Error computer point B33EA014, Recirc FCV B Vel Cont Inp-Demand should read approximately 0%.
4.3.19 ADJUST the oncoming RCIRC LOOP FLOW CONTROL slide switch to obtain 0%
SERVO ERROR.
1B33-K603B Standard:
Candidate observes 0% SERVO ERROR.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 11 4.3.20 TAKE the RCIRC FCV MOTION INHIBIT RESET switch to B.
1B33A-S112 Critical Step:
Candidate takes the RCIRC FCV MOTION INHIBIT RESET switch to the B position.
Instructor Cue:
None Notes:
When switch is taken to B position, FCV B will start to open and Candidate is expected to lockup FCV B SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Alternate Path Begins Here
OT-3701-B33_505B_RO Rev A Step 12 Flow Control Valve B starts opening when the Motion Inhibit switch, 1B33A-S112 is reset.
Critical Step:
Candidate shuts down B HPU by arming and depressing the HPU B Shutdown Pushbutton Instructor Cue:
None Notes:
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue:
HPU B was started up, Subloop B2 was placed in LEAD and HPU B was shutdown when FCV movement was detected.
Evaluation Results:
SAT_____
UNSAT_____
End Time:
OT-3701-B33_505B_RO Rev A JPM CUE SHEET INITIAL CONDITIONS:
Plant operating at power.
Flow control Valve B was locked up 90 minutes ago for replacement of the B2 Operate solenoid.
HPU B was shutdown IAW SOI-B33 Section 6.4.
B2 Operate solenoid replacement is now complete.
Restart of FCV B HPU is required for retest of the solenoid.
HPU B was not isolated.
INITIATING CUE:
Unit Supervisor directs you an extra Reactor Operator to perform Hydraulic Power Unit (HPU) B Startup with Subloop 2 in Lead and Subloop 1 in Standby.
OT-3701-C71_003_RO Rev A JOB PERFORMANCE MEASURE SETUP SHEET System:
C71 - Reactor Protection System Time Critical:
No Alternate Path:
No Setting:
Simulator Applicability:
RO/SRO Safety Function:
7 - Instrumentation Validated Time:
18 minutes
References:
SOI-C71 Rev. 25 Required Material:
SOI-C71, RPS Power Supply Distribution Tasks:
212-545-04-01 Bypass/Un-bypass RPS Functions in RPS Channel A/C Task Standard:
Bypass RPS Channels A/C & B/D automatic scrams by placing INST VOL LEVEL HI SCRAM BYPASS CH A & B keylock switch in BYPASS to insert a Rod Block. Then install jumpers on RPS A, B, C,
& D TEST JACK PANELS per SOI-C71 K / A Data:
212000 K4.12 Knowledge of REACTOR PROTECTION SYSTEM design feature(s) and/or interlocks which provide for the following:
Bypassing SCRAM signals. IR RO 3.8
- 1.
Setup Instructions: Reset simulator to a Cold Shutdown IC. For 2022 ILO NRC Exam reset simulator to IC-160. Obtain RPS jumper package from the tool storage area in front of SM desk.
- 2.
Location / Method: Simulator/Performance
- 3.
Initial Condition: The plant is shut down for a refueling outage and is in Mode 4. Under vessel work is scheduled to commence next shift. The work schedule directs bypassing of RPS automatic scrams prior to commencing under vessel work. A PLCO for RPS OPERABILITY has been generated.
- 4.
Initiating Cue: The Unit Supervisor directs you, the Reactor Operator to perform SOI-C71 Sections 7.6 & 7.7 to bypass RPS Channels A/C and B/D automatic scrams.
Start Time:
End Time:
Candidate:
OT-3701-C71_003_RO Rev A 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-C71, RPS POWER SUPPLY DISTRIBUTION 7.6 Bypass of RPS Channel A/C NOTES
- This section bypasses Automatic Scrams only. This section does NOT bypass the Manual Scrams (Arm & Depress, Mode Switch in Shutdown).
- IF it is desired to bypass the Mode Switch in Shutdown manual scram, THEN Section 7.5, Bypassing Reactor Mode Switch Scram must be used.
- Either Bypass of RPS Channel A/C, or Bypass of RPS Channel B/D, or both, may be performed to support testing or other sensitive operations. Performance of these sections could lead to an inadvertent scram signal being generated.
CAUTION This section will cause the RPS Scram function to be made INOPERABLE. Control rods shall NOT be withdrawn while RPS SCRAM function is bypassed.
7.6.1 CONFIRM the following:
- Plant is in Mode 4 or 5.
- With exception of those withdrawn control rods meeting the requirements of T.S. 3.10.4 or 3.10.6, all other control rods are inserted to position 00.
7.6.2 VERIFY one or more the following administrative controls are initiated as appropriate:
- PLCO for RPS OPERABILITY.
- Daily Surveillance Requirement Sheet to confirm control rods inserted to position 00 periodically.
- Prevention of control rod withdrawal verified by a second licensed operator, or other technically qualified member of the plant staff, and logged in the Narrative Log.
- Tagging in accordance with Clearance Program.
OT-3701-C71_003_RO Rev A Standard:
Operator confirms the plant is in Mode 4 and checks all rods at 00 Instructor Cue:
If asked, a Daily Surveillance Requirement Sheet will be generated after RPS channels are bypassed.
Notes:
PLCO generated given in Initial Conditions for Step 7.6.2 SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 2 7.6.3 PLACE INST VOL LEVEL HI SCRAM BYPASS CH A keylock switch in BYPASS to insert a Rod Block.
1C71-S4A 7.6.4 CONFIRM Rod Withdraw Block is indicated on RCIS Rod Motion Display.
Critical Step:
Standard:
Operator places INST VOL LEVEL HI SCRAM BYPASS CH A keylock switch in BYPASS to insert a Rod Block.
Operator confirms Rod Withdraw Block red light is illuminated on P680 Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-C71_003_RO Rev A Step 3 NOTES
- RPS A or C may be individually bypassed as desired.
- The Manual Scram function remains available with jumpers installed.
7.6.5 IF desired to bypass RPS logic channel A on 1H13-P691, THEN USING concurrent verification, INSTALL dedicated jumper on RPS A TEST JACK PANEL 1H13P0691 jacks X1 and 03T.
Critical Step:
Operator installs jumper on RPS A TEST JACK PANEL 1H13P0691 jacks X1 and 03T.
Instructor Cue:
If asked, I am your Concurrent Verifier.
I concur with the jacks you identified.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 4 7.6.6 IF desired to bypass RPS logic channel C on 1H13-P693, THEN USING concurrent verification, INSTALL dedicated jumper on RPS C TEST JACK PANEL 1H13P0693 jacks 4X1 and 23T.
Critical Step:
Operator installs jumper on RPS C TEST JACK PANEL 1H13P0693 jacks 4X1 and 23T.
Instructor Cue:
If asked, I am your Concurrent Verifier.
I concur with the jacks you identified.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-C71_003_RO Rev A Step 5 7.6.7 DOCUMENT Concurrent Verification of required components.
7.6.8 VERIFY the following dedicated Labels:
- REACTOR MODE SWITCH stating, RPS Automatic Scrams are disabled.
- INST VOL LEVEL HI SCRAM BYPASS CH A keylock switch stating, Keylock has been placed in BYPASS in accordance with SOI-C71 to provide a Rod Block.
- RPS A and C Jumpers stating, RPS Automatic Scrams are disabled.
Standard:
Operator hangs/verifies labels on Mode Switch and Inst Vol key lock switch.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 6 7.7 Bypass of RPS Channel B/D NOTES
- This section bypasses Automatic Scrams only. This section does NOT bypass the Manual Scrams (Arm & Depress, Mode Switch in Shutdown).
- IF it is desired to bypass the Mode Switch in Shutdown manual scram, THEN Section 7.5, Bypassing Reactor Mode Switch Scram must be used.
- Either Bypass of RPS Channel A/C, or Bypass of RPS Channel B/D, or both, may be performed to support testing or other sensitive operations. Performance of these sections could lead to an inadvertent scram signal being generated.
CAUTION This section will cause the RPS Scram function to be made INOPERABLE. Control rods shall NOT be withdrawn while RPS SCRAM function is bypassed.
OT-3701-C71_003_RO Rev A 7.7.1 CONFIRM the following:
- Plant is in Mode 4 or 5.
- With exception of those withdrawn control rods meeting the requirements of T.S. 3.10.4 or 3.10.6, all other control rods are inserted to position 00.
7.7.2 VERIFY one or more the following administrative controls are initiated as appropriate:
- PLCO for RPS OPERABILITY.
- Daily Surveillance Requirement Sheet to confirm control rods inserted to position 00 periodically.
- Prevention of control rod withdrawal verified by a second licensed operator, or other technically qualified member of the plant staff, and logged in the Narrative Log.
- Tagging in accordance with Clearance Program.
Standard:
Operator confirms the plant is in Mode 4 and checks all rods at 00 Instructor Cue:
None Notes:
PLCO generated given in Initial Conditions for Step 7.7.2 SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-C71_003_RO Rev A Step 7 7.7.3 PLACE INST VOL LEVEL HI SCRAM BYPASS CH B keylock switch in BYPASS to insert a Rod Block.
1C71-S4B 7.7.4 CONFIRM Rod Withdraw Block is indicated on RCIS Rod Motion Display.
Critical Step:
Standard:
Operator places INST VOL LEVEL HI SCRAM BYPASS CH B keylock switch in BYPASS to insert a Rod Block.
Operator confirms Rod Withdraw Block red light is illuminated on P680 Instructor Cue:
None Notes:
Rod Withdraw Block red light previously illuminated SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 8 NOTES
- RPS B or D may be individually bypassed as desired.
- The Manual Scram function remains available with jumpers installed.
7.7.5 IF desired to bypass RPS logic channel B on 1H13-P692, THEN USING concurrent verification, INSTALL dedicated jumper on RPS B TEST JACK PANEL 1H13P0692 jacks 2X1 and 13T.
Critical Step:
Operator installs jumper on RPS B TEST JACK PANEL 1H13P0692 jacks 2X1 and 13T.
Instructor Cue:
If asked, I am your Concurrent Verifier.
I concur with the jacks you identified.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-C71_003_RO Rev A Step 9 7.7.6 IF desired to bypass RPS logic channel D on 1H13-P694, THEN USING concurrent verification, INSTALL dedicated jumper on RPS D TEST JACK PANEL 1H13P0694 jacks 6X1 and 33T.
Critical Step:
Operator installs jumper on RPS D TEST JACK PANEL 1H13P0694 jacks 6X1 and 33T.
Instructor Cue:
If asked, I am your Concurrent Verifier.
I concur with the jacks you identified.
Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 10 7.7.7 DOCUMENT Concurrent Verification of required components.
7.7.8 VERIFY the following dedicated Labels:
- REACTOR MODE SWITCH stating, RPS Automatic Scrams are disabled.
- INST VOL LEVEL HI SCRAM BYPASS CH A keylock switch stating, Keylock has been placed in BYPASS in accordance with SOI-C71 to provide a Rod Block.
- RPS A and C Jumpers stating, RPS Automatic Scrams are disabled.
Standard:
Operator hangs/verifies label on Inst Vol key lock switch.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-C71_003_RO Rev A Terminating Cue: RPS jumpers installed in test jack panels on P691, P692, P 693, & P694 to bypass Channels A, B, C, & D RPS automatic scrams.
Evaluation Results: SAT_____
UNSAT_____
End Time:
OT-3701-C71_003_RO Rev A JPM CUE SHEET INITIAL CONDITIONS:
- The plant is shut down for a refueling outage and is in Mode 4.
- Under vessel work is scheduled to commence next shift.
- The work schedule directs bypassing of RPS automatic scrams prior to commencing under vessel work.
- A PLCO for RPS OPERABILITY has been generated.
INITIATING CUE:
The Unit Supervisor directs you, the Reactor Operator to perform SOI-C71 Sections 7.6 & 7.7 to bypass RPS Channels A/C and B/D automatic scrams.
OT-3701-E12_507_RO Rev A JOB PERFORMANCE MEASURE SETUP SHEET System:
E12 Residual Heat Removal Time Critical:
No Alternate Path:
Yes Setting:
Simulator Applicability:
RO/SRO Safety Function:
4 - Heat Removal from the Reactor Core 5 - Containment Integrity Validated Time:
8 Minutes
References:
EOP-SPI 3.1 Rev. 6 & EOP-SPI-6.1 Rev. 4, & EOP-SPI 6.2 Rev. 4 Required Material:
EOP-SPI 3.1 Containment Spray Operation EOP-SPI 6.1 RHR A Injection EOP-SPI 6.2 RHR B Injection Task:
205-536-01-01 Realign RHR from one Mode to another Task Standard:
Shift RHR Loop A from Containment Spray to LPCI Injection upon trip of RHR B Pump by performing the following: Override 1E12-F042A to prevent uncontrolled injection; terminate containment spray by resetting Containment Spray initiation logic, and closing E12-F028A and E12-F537A, Spray Shutoff valves before a containment vacuum breaker opens; then open E12-F042A or throttles E12-F053A valve to stabilize and recover RPV level.
K/A:
226001, RHR/LPCI: Containment Spray System Mode - A2 - Ability to (a) predict the impacts of the following on the RHR/LPCI: Containment Spray System Mode; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: A2.20, Loss of coolant accident IR 3.8.
203000, RHR/LPCI: Injection Mode: A2 - Ability to (a) predict the impacts of the following on the RHR/LPCI: Injection Mode and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: A2.02 - Pump trips.
IR: RO 4.0
OT-3701-E12_507_RO Rev A
- 1.
Setup Instructions: Reset simulator to a shutdown IC with a SDV leak and a loss of HP injection and ED in progress @ ~ 700 psig with RHR A spraying Containment and RHR B lined up to inject. LPCS and RHR C tripped. (Reset simulator to IC-161 for 2022 ILO NRC Exam.) Keep simulator in FREEZE and insert Schedule file JPM E12-507.sch.
Place yellow switch cap on HPCS pump and Injection valve. When SPDS comes back, place simulator in RUN momentarily to verify Event file JPM E12-507.evt loads, then place simulator in FREEZE. After Evaluator reads Initiating Cue and directs placing simulator in run, place simulator in RUN. Provide marked up copies of EOP-SPI 3.2 &
EOP-SPI 6.1 & 6.2. Instructor to act as ATC to silence all alarms not on P601.
- 2.
Location / Method: Simulator - Performance
- 3.
Initial Condition: HPCS was tagged out for maintenance. A loss of all high-pressure injection occurred causing entry into the EOPs. LPCS and RHR loops were lined up for injection IAW EOP-SPIs 6.1, 6.2, 6.3, & 6.5. LPCS tripped on overcurrent. RHR C injection valve lost power. Emergency Depressurization was performed. Containment Spray Loop A was initiated due to rising Containment temperature. Currently, RHR B is only source of injection to control RPV level.
- 4.
Initiating Cue: Unit Supervisor directs you, the Balance of Plant Operator, to terminate Containment Spray Loop A then align RHR A in Suppression Pool Cooling.
Start:
Stop:
Operator:
OT-3701-E12_507_RO Rev A 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 3.1 CONTAINMENT SPRAY OPERATION 1.0 IF Containment Spray(s) have been initiated:
Containment pressure cannot be maintained greater than 0 psig, or Directed to terminate Containment Spray operations THEN TERMINATE RHR Containment Spray as follows:
1.1 IF Containment Spray A Loop is in service, then TERMINATE Containment Spray A Loop as follows:
1.1.1 Take LPCI A INJECTION VALVE control switch to CLOSE.
E12-F042A Critical Step Standard Operator takes 1E12-F042A to close.
Containment Spray must be terminated prior to negative pressure in containment as indicated by a containment vacuum breaker opening.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
NOTE LPCI A INJECTION VALVE E12-F042A control switch is overridden closed before resetting Containment Spray logic with a LPCI initiation signal present to prevent uncontrolled LPCI injection into the RPV.
OT-3701-E12_507_RO Rev A Step 2 1.1.2 Verify CNTMT SPRAY A MANUAL INITIATION pushbutton collar in DISARM.
E12A-S63A Standard:
Operator rotates Initiation pushbutton collar to DISARM.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 3 1.1.3 Depress CNTMT SPRAY A SEAL IN RESET pushbutton to reset the Containment Spray initiation logic.
E12A-S64A Critical Step Operator depresses the Seal In Reset pushbutton.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-E12_507_RO Rev A Step 4 1.1.4 Close CNTMT SPRAY A SECOND SHUTOFF.
E12-F537A 1.1.5 If Combustible Gas Mixing System A is not running, then close CNTMT SPRAY A FIRST SHUTOFF.
E12-F028A Critical Step Operator closes 1st and 2nd spray shutoff valves before a containment vacuum breaker opens.
Instructor Cue:
When Operator reports RHR B pump trip or following your RHR B Pump trip update, direct them to establish RPV level band of 150 to 219 inches.
Notes:
When E12-F537A is taken to CLOSE, RHR B pump will trip and RPV level will start to lower.
EOP-SPI 6.1, RHR A Injection contains instructions for shifting from Containment Spray to LPCI injection.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-E12_507_RO Rev A Step 5 EOP-SPI 6.1 RHR A INJECTION ENTRY CONDITIONS This instruction is entered when directed to inject or prepare to inject into the RPV inside or outside the shroud with LPCI A. Injection with this instruction secures Containment Spray A operation and the A Loop of Suppression Pool Cooling if in service.
4.2 Verify RHR A Test Valve to Suppression Pool is closed 1E12-F024A 4.3 IF RHR A is in-service providing Containment Spray, THEN TERMINATE Containment Spray as follows:
Standard:
Operator determines EOP-SPI 6.1 contains the steps to shift from Containment Spray to LPCI injection and verifies EOP-SPI 6.1 Steps 4.2 and 4.3 are complete.
Instructor Cue:
None Notes:
Because of the timing of RHR B trip, Step 4.1 need not be performed.
Steps 4.3.14.3.5 were completed in EOP-SPI 3.1.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 6 4.4 Verify RHR A HXS OUTLET VALVE is OPEN.
1E12-F003A 4.5 Verify RHR A HXS BYPASS VALVE is OPEN.
1E12-F048A Standards:
Operator verifies E12-F003A & E12-F048A valves are open.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-E12_507_RO Rev A Step 7 5.0 Perform the following as needed, while injecting into the RPV:
5.1 When desired to inject inside the shroud, THEN PERFORM the following:
5.1.1 VERIFY the SHUTDOWN COOLING A TO FDW SHUTOFF valve is FULLY CLOSED.
E12-F053A 5.1.2 OPERATE LPCI A INJECTION VALVE.
E12-F042A 5.2 When desired to inject outside the shroud, then perform the following:
5.2.1 At 1H13-P629, verify RHR ISOL BYPASS E12-F053A keylock switch is in BYPASS.
E12AS74 5.2.2 Verify LPCI A INJECTION VALVE is CLOSED.
E12-F042A 5.2.3 Throttle SHUTDOWN COOLING A TO FDW SHUTOFF to the desired flowrate.
E12-F053A Critical Step Operator opens E12-F042A or throttles E12-F053A valve to stabilize and recover RPV level.
Instructor Cue:
None Notes:
In the Initial Conditions, it was given that RHR A was prepared for injection, which means E12-F053A throttle capability was enabled.
Injection outside the shroud is preferred. The Operator may use Step 5.1, which opens the Injection valve, E12-F042A. However, they should transition to the E12-F053A valve.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue:
Containment Spray A loop has been terminated and LPCI injection using the RHR A is restoring/maintaining RPV level 150 - 219.
Evaluation Results:
SAT_____
UNSAT_____
End Time:
OT-3701-E12_507_RO Rev A JPM CUE SHEET INITIAL CONDITIONS:
- HPCS was tagged out for maintenance.
- A loss of all high-pressure injection occurred causing entry into the EOPs.
- LPCS tripped on overcurrent.
- RHR C injection valve lost power.
- Emergency Depressurization was performed.
- Containment Spray Loop A was initiated due to rising Containment temperature.
Unit Supervisor directs you, the Balance of Plant Operator, to terminate Containment Spray Loop A then align RHR A in Suppression Pool Cooling.
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
1 of 14 CONTAINMENT SPRAY OPERATION Effective Date:
Preparer:
Dan Roniger
/ 3-15-2021 Date Approver:
Daniel Roniger for Ed Condo per email
/ 3-15-2021 Date 3-30-2021
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
2 of 14 ENTRY CONDITIONS This instruction is entered when Containment pressure, Containment Average Temperature or hydrogen concentration necessitate spraying of Containment, or when Containment sprays are to be terminated.
SCOPE This instruction provides the necessary actions to manually initiate Containment sprays, both before and after the RHR Containment Spray Loop has been used to vent Containment. The high Drywell pressure interlock is bypassed, if necessary, to allow spray initiation.
This procedure addresses actions required for Emergency Operating Procedure and Severe Accident Guidance procedures.
NECESSARY EQUIPMENT Storage Area 5 Control Room EOP File drawer CC 654:
Two EOP keys AX 599 C/02:
One 12 ft ladder LOCATION OF REQUIRED LOCAL ACTIONS AX 599 C/07, above the RHR A HX Room door:
RHR A FPCC Supplement Cooling Discharge Vlv 1E12-F099A AX 599 C/03, above the RHR B HX Room door:
RHR B FPCC Supplement Cooling Discharge Vlv 1E12-F099B END OF SECTION
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
3 of 14 NOTE Step 1.0 Termination of Containment Sprays. Performed after initiation of Containment Sprays to terminate spray operation.
Step 2.0 Initiates Containment Spray Loop A when system is filled and Vented (Pg 5).
Step 3.0 Initiates Containment Spray Loop B when system is filled and Vented (Pg 7).
Step 4.0 Initiates Containment Spray Loop A when system is aligned for Containment Venting.
Step 5.0 Initiates Containment Spray Loop B when system is aligned for Containment Venting.
NA 1.0 IF Containment Spray(s) have been initiated:
Containment pressure CANNOT be maintained greater than 0 psig, or Desired to terminate Containment Spray operations, THEN TERMINATE RHR Containment Spray as follows:
NA 1.1 IF Containment Spray A Loop is in service, THEN TERMINATE Containment Spray A Loop as follows:
NOTE LPCI A INJECTION VALVE E12-F042A control switch is overridden closed before resetting Containment Spray logic with a LPCI initiation signal present to prevent uncontrolled LPCI injection into the RPV.
1.1.1 TAKE LPCI A INJECTION VALVE control switch to CLOSE.
E12-F042A 1.1.2 VERIFY CNTMT SPRAY A MANUAL INITIATION pushbutton collar in DISARM.
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
4 of 14 1.1.3 DEPRESS CNTMT SPRAY A SEAL IN RESET pushbutton to reset the Containment Spray initiation logic.
E12A-S64A 1.1.4 CLOSE CNTMT SPRAY A SECOND SHUTOFF.
E12-F537A NA 1.1.5 IF Combustible Gas Mixing System A is NOT
- running, THEN CLOSE CNTMT SPRAY A FIRST SHUTOFF.
E12-F028A NA 1.2 IF Containment Spray B Loop is in service, THEN TERMINATE Containment Spray B Loop as follows:
NOTE LPCI B INJECTION VALVE E12-F042B control switch is overridden closed before resetting Containment Spray logic with a LPCI initiation signal present to prevent uncontrolled LPCI injection into the RPV.
1.2.1 TAKE LPCI B INJECTION VALVE control switch to CLOSE.
E12-F042B 1.2.2 VERIFY CNTMT SPRAY B MANUAL INITIATION pushbutton collar in DISARM.
E12A-S63B 1.2.3 DEPRESS CNTMT SPRAY B SEAL IN RESET pushbutton to reset the Containment Spray initiation logic.
E12A-S64B 1.2.4 CLOSE CNTMT SPRAY B SECOND SHUTOFF.
E12-F537B NA 1.2.5 IF Combustible Gas Mixing System B is NOT
- running, THEN CLOSE CNTMT SPRAY B FIRST SHUTOFF.
E12-F028B
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
5 of 14 NA 2.0 RHR Containment Spray Loop A is NOT lined up to vent Containment Containment Spray A loop is available THEN INITIATE Containment Spray A Loop as follows:
NA 2.1 IF Drywell Pressure is less than 1.68 psig, THEN AT H13-P629, PLACE CNTMT SPRAY A HI DW PRESS BYP keylock switch in BYPASS.
2.2 CONFIRM Containment Pressure is above 0.8 psig.
2.3 ARM AND DEPRESS CNTMT SPRAY A MANUAL INITIATION pushbutton.
2.4 VERIFY RHR PUMP A is running.
E12-C002A NA 2.5 IF ESW PUMP A is available, THEN VERIFY ESW PUMP A is running.
P45-C001A NA 2.6 IF ECC PUMP A is available, THEN VERIFY ECC PUMP A is running.
P42-C001A 2.7 VERIFY the following valves are OPEN:
CNTMT SPRAY A FIRST SHUTOFF E12-F028A
CNTMT SPRAY A SECOND SHUTOFF E12-F537A
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
6 of 14 NOTES RHR A HXS BYPASS VALVE E12-F048A will not close within ten minutes after a LOCA initiation signal.
RHR A HXS BYPASS VALVE E12-F048A will only automatically close if RHR A HXS INLET VALVE E12-F047A and RHR A HXS OUTLET VALVE E12-F003A are open.
2.8 VERIFY the following valves are CLOSED:
RHR A TEST VALVE TO SUPR POOL E12-F024A SHUTDOWN COOLING A TO FDW SHUTOFF E12-F053A RHR A HXS BYPASS VALVE (10 minutes)
E12-F048A 2.9 TAKE LPCI A INJECTION VALVE control switch to CLOSE.
E12-F042A NOTE Continuous Containment Spray operation may be desired to control does rates in areas external to Primary Containment such as the Control Room.
2.10 IF desired to maintain continuous Containment Spray operation AND Containment pressure is below 8.0 psig, THEN PERFORM the following:
2.10.1 DEPRESS CNTMT SPRAY A SEAL IN RESET pushbutton to reset the Containment Spray initiation logic.
E12A-S63A 2.10.2 THROTTLE the following to MAINTAIN Containment pressure above 0.5 psig:
RHR A HXS BYPASS VALVE E12-F048A RHR A HXS OUTLET VALVE E12-F003A
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
7 of 14 NA 3.0 RHR Containment Spray Loop B is NOT lined up to vent Containment Containment Spray A loop is NOT initiated Additional Containment Spray is required Containment Spray B loop is available THEN INITIATE Containment Spray B Loop as follows:
NA 3.1 IF Drywell Pressure is less than 1.68 psig, THEN AT H13-P618, PLACE CNTMT SPRAY B HI DW PRESS BYP keylock switch in BYPASS.
E12A-S76 3.2 CONFIRM Containment Pressure is above 0.8 psig.
3.3 ARM AND DEPRESS CNTMT SPRAY B MANUAL INITIATION pushbutton for at least 35 seconds.
E12A-S63B 3.4 VERIFY RHR PUMP B is running.
E12-C002B NA 3.5 IF ESW PUMP B is available, THEN VERIFY ESW PUMP B is running.
P45-C001B NA 3.6 IF ECC PUMP B is available, THEN VERIFY ECC PUMP B is running.
P42-C001B 3.7 VERIFY the following valves are OPEN:
CNTMT SPRAY B FIRST SHUTOFF E12-F028B CNTMT SPRAY B SECOND SHUTOFF E12-F537B
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
8 of 14 NOTES RHR B HXS BYPASS VALVE E12-F048B will not close within ten minutes after a LOCA initiation signal.
RHR B HXS BYPASS VALVE E12-F048B will only automatically close if RHR B HXS INLET VALVE E12-F047B and RHR B HXS OUTLET VALVE E12-F003B are open.
3.7.1 VERIFY the following valves are CLOSED:
RHR B TEST VALVE TO SUPR POOL E12-F024B SHUTDOWN COOLING B TO FDW SHUTOFF E12-F053B RHR B HXS BYPASS VALVE (10 Minutes)
E12-F048B 3.8 TAKE LPCI B INJECTION VALVE control switch to CLOSE.
E12-F042B NOTE Continuous Containment Spray operation may be desired to control does rates in areas external to Primary Containment such as the Control Room.
NA 3.9 IF desired to maintain continuous Containment Spray operation AND Containment pressure is below 8.0 psig, THEN PERFORM the following:
3.9.1 DEPRESS CNTMT SPRAY B SEAL IN RESET pushbutton to reset the Containment Spray initiation logic.
E12A-S64B 3.9.2 THROTTLE the following to maintain Containment Pressure above 0.5 psig:
RHR B HXS BYPASS VALVE E12-F048B RHR B HXS OUTLET VALVE E12-F003B
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
9 of 14 CAUTION System realignment other than as directed in the following step may result in water hammer severe enough to cause pressure boundary failure and subsequent uncontrolled release to the environment.
NA 4.0 RHR Containment Spray Loop A is lined up to vent Containment Containment is currently being vented via RHR Containment Spray Loop A Containment Spray A loop is available THEN INITIATE Containment Spray A Loop as follows:
NA 4.1 IF Containment is currently being vented via Containment Spray Loop A, THEN CLOSE CNTMT SPRAY A FIRST SHUTOFF to secure venting.
E12-F028A 4.2 FILL the drained RHR A piping as follows:
4.2.1 VERIFY CLOSED RHR A HXS OUTLET VALVE. E12-F003A NOTE RHR A HXS OUTLET VALVE E12-F003A is throttled open 3 to 4 seconds to allow the water leg pump to fill up the drained portion of the RHR header.
4.2.2 THROTTLE OPEN RHR A HXS OUTLET VALVE 3 to 4 seconds.
E12-F003A 4.2.3 AT AX 599 C/07, above RHR A HX Room door, CLOSE RHR A FPCC Supplement Cooling Discharge Vlv.
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
10 of 14 4.2.4 VERIFY the following valves are OPEN:
CNTMT SPRAY A FIRST SHUTOFF E12-F028A CNTMT SPRAY A SECOND SHUTOFF E12-F537A 4.2.5 VERIFY the following valves are CLOSED:
LPCI A INJECTION VALVE E12-F042A RHR A HXS BYPASS VALVE E12-F048A RHR A HXS INLET VALVE E12-F047A NA 4.2.6 IF ESW PUMP A is available, THEN VERIFY ESW PUMP A is running.
P45-C001A NA 4.2.7 IF ECC PUMP A is available, THEN VERIFY ECC PUMP A is running.
P42-C001A 4.2.8 START RHR PUMP A.
E12-C002A 4.2.9 OPEN RHR A HXS INLET VALVE.
E12-F047A 4.2.10 WHEN flow is present as indicated on RHR A PUMP FLOW, THEN THROTTLE RHR A HXS OUTLET VALVE slowly to obtain a flow rate of 1000-1500 gpm.
E12-R603A E12-F003A 4.2.11 WHEN approximately four minutes have passed, THEN OPEN RHR A HXS OUTLET VALVE.
E12-F003A
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
11 of 14 CAUTION System realignment other than as directed in the following step may result in water hammer severe enough to cause pressure boundary failure and subsequent uncontrolled release to the environment.
NA 5.0 RHR Containment Spray Loop B is lined up to vent Containment Containment is currently being vented via RHR Containment Spray Loop B Containment Spray B loop is available Containment Spray A loop CANNOT be initiated Additional Containment Spray is required THEN INITIATE Containment Spray B Loop as follows:
NA 5.1 IF Containment is currently being vented via Containment Spray Loop B, THEN CLOSE CNTMT SPRAY B FIRST SHUTOFF to secure venting.
E12-F028B 5.2 FILL the drained RHR B piping as follows:
5.2.1 VERIFY CLOSED RHR B HXS OUTLET VALVE. E12-F003B NOTE RHR B HXS OUTLET VALVE E12-F003B is throttled open 3 to 4 seconds to allow the water leg pump to fill up the drained portion of the RHR header.
5.2.2 THROTTLE OPEN RHR B HXS OUTLET VALVE 3 to 4 seconds.
E12-F003B 5.2.3 AT AX 599 C/03, above RHR B HX Room door, CLOSE RHR B FPCC Supplement Cooling Discharge Vlv.
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
12 of 14 5.2.4 VERIFY the following valves are OPEN:
CNTMT SPRAY B FIRST SHUTOFF E12-F028B CNTMT SPRAY B SECOND SHUTOFF E12-F537B 5.2.5 VERIFY the following valves are CLOSED:
LPCI B INJECTION VALVE E12-F042B RHR B HXS BYPASS VALVE E12-F048B RHR B HXS INLET VALVE E12-F047B NA 5.2.6 IF ESW PUMP B is available, THEN VERIFY ESW PUMP B is running.
P45-C001B NA 5.2.7 IF ECC PUMP B is available, THEN VERIFY ECC PUMP B is running.
P42-C001B 5.2.8 START RHR PUMP B.
E12-C002B 5.2.9 OPEN RHR B HXS INLET VALVE.
E12-F047B 5.2.10 WHEN flow is present as indicated on RHR B PUMP FLOW, THEN THROTTLE RHR B HXS OUTLET VALVE slowly to obtain a flow rate of 1000-1500 gpm.
E12-R603B E12-F003B 5.2.11 WHEN approximately four minutes have passed, THEN OPEN RHR B HXS OUTLET VALVE.
E12-F003B END OF SECTION
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
13 of 14 SCOPE OF REVISION Rev. 6
- 1. Updated the Entry Conditions to include Containment Average Temperature (ATL-2018-0950-ATA-18).
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 3.1
Title:
CONTAINMENT SPRAY OPERATION Use Category:
In-Field Reference Revision:
6 Page:
14 of 14 Control Room Back Panel Locations P654 P631 P610 P640 P655 P621 P628 P670 P622 P692 P652 P669 P623 P632 P672 P653 P651 P671 P625 P693 P873 P613 P614 P804 P803 P604 P600 P884 P845 P885 P619 P634 P680 Printer Area P601 P877 P870 C22 P002 C22 P001 P881 P882 P811 P810 P809 P807 P808 P883 P800 P842 P823 P630 P637 P821 P822 P871 P867 P866 P872 P868 P864 P612 P840 P865 P869 P703 P904 P969 P902 P906 P907 P5001 P642 P629 P740 P742 P744 P746 P702 P741 P743 P745 P747 P748 P706 P704 P702 P710 P714 P701 P707 P711 P717 P713 P715 P694 P691 P970 P618
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.1
Title:
RHR A INJECTION Use Category:
In-Field Reference Revision:
4 Page:
1 of 8 RHR A INJECTION Effective Date:
10-26-17 Preparer:
Daniel Roniger
/ 4-11-17 Date Approver:
Ed Condo
/ 10-18-17 Date
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.1
Title:
RHR A INJECTION Use Category:
In-Field Reference Revision:
4 Page:
2 of 8 ENTRY CONDITIONS This instruction is entered when directed to inject or prepare to inject into the RPV inside or outside the shroud with LPCI A. Injection with this instruction secures Containment Spray A operation and the A Loop of Suppression Pool Cooling if in service.
SCOPE This instruction aligns the RHR A system and provides for controlled injection inside or outside the shroud from LPCI A, by injection via the LPCI A injection valve or by throttling the RHR A to Feedwater isolation valve after bypassing its RHR isolation.
This procedure assumes that the RHR A system is fill and vented or is partially voided due to an Isolation in Mode 3 during shutdown cooling operations. If pumping power was lost during Suppression Pool Cooling or Test Mode operation the RHR A System will need to be fill and vented per Off Normal procedures to make it available for use in the EOPs. ONI-R22-1, ONI-R10-1 and ONI-R10-2 provide guidance for recovery of RHR A after pumping power is lost.
Defeats the Shutdown Cooling Isolation for the SHUTDOWN COOLING A TO FDW SHUTOFF valve, E12-F053A when the RHR ISOL BYPASS E12-F053A E12AS74 keylock switch is in BYPASS.
This procedure address actions required for the Emergency Operating Procedures, and Severe Accident Guidance.
NECESSARY EQUIPMENT Storage Area 5 Control Room EOP File drawer CC 654:
One EOP key LOCATION OF REQUIRED LOCAL ACTIONS None END OF SECTION
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.1
Title:
RHR A INJECTION Use Category:
In-Field Reference Revision:
4 Page:
3 of 8 NOTES Step 1.0 provides guidance for Startup and Operation of RHR A from a Standby Readiness condition and can be performed by memory.
Actions to align for Outside the Shroud injection should NOT delay injection.
NA 1.0 IF RHR A is in Standby Readiness, THEN PERFORM the following:
E12-C002A 1.1 VERIFY the following:
VERIFY RHR PUMP A is RUNNING.
E12-C002A NA IF ESW PUMP A is available, THEN VERIFY ESW PUMP A is RUNNING.
P45-C001A NA IF ECC PUMP A is available, THEN VERIFY ECC PUMP A is RUNNING.
P42-C001A NA 1.2 IF desired to inject Inside the shroud, THEN PERFORM the following:
1.2.1 TAKE LPCI A INJECTION VALVE to OPEN. E12-F042A 1.2.2 GO TO Step 5.0.
NA 1.3 IF desired to inject Outside the shroud, THEN PERFORM the following:
1.3.1 AT 1H13-P629, VERIFY RHR ISOL BYPASS E12-F053A keylock switch is in BYPASS.
E12AS74 1.3.2 VERIFY SHUTDOWN COOLING A TO FDW SHUTOFF is OPEN.
E12-F053A 1.3.3 GO TO Step 5.0.
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.1
Title:
RHR A INJECTION Use Category:
In-Field Reference Revision:
4 Page:
4 of 8 NOTE If an isolation is experienced while RHR A was in Shutdown Cooling, the RHR A system is considered to have voided either due to air entrainment through the pump seals OR flashing of hot water to steam.
NA 2.0 IF RHR A isolated during Shutdown Cooling Operations, THEN REFER TO RHR A SDC Isolation To LPCI Mode Recovery, ONI-SPI A-10 and PERFORM the actions.
NA 3.0 IF the RHR A Pump is NOT running, THEN PERFORM the following:
E12-C002A 3.1 VERIFY LPCI A INJECTION VALVE is CLOSED.
E12-F042A 3.2 PERFORM the following concurrently:
NA IF RHR A keepfill has been lost, THEN REFER TO ONI-SPI A-3, Division 1 ECCS Restoration and PERFORM the required actions for RHR A.
NA IF ESW PUMP A is available, THEN VERIFY ESW PUMP A is RUNNING.
P45-C001A NA IF ECC PUMP A is available, THEN VERIFY ECC PUMP A is RUNNING.
P42-C001A 3.3 VERIFY RHR PUMP A is RUNNING.
E12-C002A
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.1
Title:
RHR A INJECTION Use Category:
In-Field Reference Revision:
4 Page:
5 of 8 4.0 WHEN injection into the RPV with RHR A is desired, THEN PERFORM the following:
NA 4.1 IF RHR A TEST VALVE TO SUPR POOL is OPEN, THEN THROTTLE the following as needed to adjust the RHR A PUMP FLOW 6000-6500 gpm:
E12-F024A RHR A HXS OUTLET VALVE.
E12-F003A RHR A HXS BYPASS VALVE.
E12-F048A 4.2 VERIFY RHR A TEST VALVE TO SUPR POOL is CLOSED.
E12-F024A NA 4.3 IF RHR A is in-service providing Containment Spray, THEN TERMINATE Containment Spray as follows:
4.3.1 VERIFY LPCI A INJECTION VALVE is CLOSED.
E12-F042A 4.3.2 VERIFY CNTMT SPRAY A MANUAL INITIATION pushbutton collar is in DISARM.
E12A-S63A 4.3.3 DEPRESS CNTMT SPRAY A SEAL IN RESET pushbutton to reset the Containment Spray initiation logic.
E12A-S64A NA 4.3.4 IF Combustible Gas Mixing System A is NOT
- running, THEN CLOSE CNTMT SPRAY A FIRST SHUTOFF.
E12-F028A 4.3.5 CLOSE CNTMT SPRAY A SECOND SHUTOFF.
E12-F537A 4.4 VERIFY RHR A HXS OUTLET VALVE is OPEN.
1E12-F003A 4.5 VERIFY RHR A HXS BYPASS VALVE is OPEN.
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.1
Title:
RHR A INJECTION Use Category:
In-Field Reference Revision:
4 Page:
6 of 8 CAUTIONS Rapid injection of water with the Reactor NOT shutdown may induce a large power excursion and result in substantial core damage. With either Inside or Outside the shroud injection, Core damage is more likely at lower RPV Pressures with RPV level below the top of the fuel channel (L1 16.5).
Following a rapid RPV depressurization slowly restore RHR injection to ensure Feedwater piping is full prior to establishing higher injection flow rates.
5.0 PERFORM the following as needed, while injecting into the RPV:
NA 5.1 WHEN desired to inject inside the shroud, THEN PERFORM the following:
5.1.1 VERIFY the SHUTDOWN COOLING A TO FDW SHUTOFF valve is FULLY CLOSED.
E12-F053A 5.1.2 OPERATE LPCI A INJECTION VALVE.
E12-F042A NA 5.2 WHEN desired to inject outside the shroud, THEN PERFORM the following:
5.2.1 AT 1H13-P629, VERIFY RHR ISOL BYPASS E12-F053A keylock switch is in BYPASS.
E12AS74 5.2.2 VERIFY LPCI A INJECTION VALVE is CLOSED.
E12-F042A 5.2.3 THROTTLE SHUTDOWN COOLING A TO FDW SHUTOFF to the desired flowrate.
E12-F053A
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.1
Title:
RHR A INJECTION Use Category:
In-Field Reference Revision:
4 Page:
7 of 8 NOTES Maintain cooldown rate within Tech Spec limits prior to Emergency Depressurization.
Following Emergency Depressurization maximize RHR flow thought heat exchanger; disregard Tech Spec cooldown limits as required, until the RPV is depressurized.
6.0 THROTTLE the following valves to reject heat from Primary Containment:
RHR A HXS BYPASS VALVE.
1E12-F048A RHR A HXS OUTLET VALVE.
1E12-F003A END OF SECTION SCOPE OF REVISION Rev. 4
- 1. Added action to start RHR A based upon system being in standby readiness (601055226).
- 2. Deleted the comp action based upon 5 SRVs for ED, to close the min flow valve at higher RPV pressures. 6 SRVs are now used to ED.
- 3. Removed Restriction on Inside the shroud injection prior to ED based upon acceptance of Issue 1610 which removed the restrictions on inside the shroud injection.
- 4. Deleted use of Isolation Reset to simplify the required actions to those that work in all plant conditions.
- 5. Updated Control Room Back Panel Locations to delete SAS reference.
(601060229)
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.1
Title:
RHR A INJECTION Use Category:
In-Field Reference Revision:
4 Page:
8 of 8 Control Room Back Panel Locations
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.2
Title:
RHR B INJECTION Use Category:
In-Field Reference Revision:
4 Page:
1 of 8 RHR B INJECTION Effective Date:
10-26-17 Preparer:
Daniel Roniger
/ 4-11-17 Date Approver:
Ed Condo
/ 10-18-17 Date
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.2
Title:
RHR B INJECTION Use Category:
In-Field Reference Revision:
4 Page:
2 of 8 ENTRY CONDITIONS This instruction is entered when directed to inject or prepare to inject into the RPV inside or outside the shroud with LPCI B. Injection with this instruction secures Containment Spray B operation and the B Loop of Suppression Pool Cooling if in service.
SCOPE This instruction aligns the RHR B system and provides for controlled injection inside or outside the shroud from LPCI B, by injection via the LPCI B injection valve or by throttling the RHR B to Feedwater isolation valve after bypassing its RHR isolation.
This procedure assumes that the RHR B system is fill and vented or is partially voided due to an Isolation in Mode 3 during shutdown cooling operations. If pumping power was lost during Suppression Pool Cooling or Test Mode operation the RHR B System will need to be fill and vented per Off Normal procedures to make it available for use in the EOPs. ONI-R22-1, ONI-R10-1 and ONI-R10-2 provide guidance for recovery of RHR B after pumping power is lost.
Defeats the Shutdown Cooling Isolation for the SHUTDOWN COOLING B TO FDW SHUTOFF valve, E12-F053B when the RHR ISOL BYPASS E12-F053B E12AS75 keylock switch is in BYPASS.
This procedure address actions required for the Emergency Operating Procedures, and Severe Accident Guidance.
NECESSARY EQUIPMENT Storage Area 5 Control Room EOP File drawer CC 654:
One EOP key LOCATION OF REQUIRED LOCAL ACTIONS None END OF SECTION
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.2
Title:
RHR B INJECTION Use Category:
In-Field Reference Revision:
4 Page:
3 of 8 NOTES Steps 1.0, 5.0 and 6.0 provide guidance for Startup and Operation of RHR B from a Standby Readiness condition and can be performed by memory.
Actions to align for Outside the Shroud should NOT delay injection.
NA 1.0 IF RHR B is in Standby Readiness, THEN PERFORM the following:
E12-C002B 1.1 VERIFY the following:
VERIFY RHR PUMP B is RUNNING.
E12-C002B NA IF ESW PUMP B is available, THEN VERIFY ESW PUMP B is RUNNING.
P45-C001B NA IF ECC PUMP B is available, THEN VERIFY ECC PUMP B is RUNNING.
P42-C001B NA 1.2 IF desired to inject Inside the shroud, THEN PERFORM the following:
1.2.1 TAKE LPCI B INJECTION VALVE to OPEN.
E12-F042B 1.2.2 GO TO Step 5.0.
NA 1.3 IF desired to inject Outside the shroud, THEN PERFORM the following:
1.3.1 AT 1H13-P618, VERIFY RHR ISOL BYPASS E12-F053B keylock switch is in BYPASS.
E12AS73 1.3.2 VERIFY SHUTDOWN COOLING B TO FDW SHUTOFF is OPEN.
E12-F053B 1.3.3 GO TO Step 5.0.
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.2
Title:
RHR B INJECTION Use Category:
In-Field Reference Revision:
4 Page:
4 of 8 NOTE If a is experienced while RHR B was in Shutdown Cooling, the RHR B system is considered to have voided either due to air entrainment through the pump seals OR flashing of hot water to steam.
NA 2.0 IF RHR B isolated in during Shutdown Cooling Operations, THEN REFER TO RHR B SDC Isolation To LPCI Mode Recovery, ONI-SPI B-10, and PERFORM the actions.
NA 3.0 IF the RHR B Pump is NOT running, THEN PERFORM the following:
E12-C002B 3.1 VERIFY LPCI B INJECTION VALVE is CLOSED.
E12-F042B 3.2 PERFORM the following concurrently:
NA IF RHR B keepfill has been lost, THEN REFER TO ONI-SPI B-3, Division 2 ECCS Restoration and PERFORM the required actions for RHR B.
NA IF ESW PUMP B is available, THEN VERIFY ESW PUMP B is RUNNING.
P45-C001B NA IF ECC PUMP B is available, THEN VERIFY ECC PUMP B is RUNNING.
P42-C001B 3.3 VERIFY RHR PUMP B is RUNNING.
E12-C002B
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.2
Title:
RHR B INJECTION Use Category:
In-Field Reference Revision:
4 Page:
5 of 8 4.0 WHEN injection into the RPV with RHR B is desired, THEN PERFORM the following:
NA 4.1 IF RHR B TEST VALVE TO SUPR POOL is OPEN, THEN THROTTLE the following as needed to adjust the RHR B PUMP FLOW 6000-6500 gpm:
E12-F024B RHR B HXS OUTLET VALVE.
E12-F003B RHR B HXS BYPASS VALVE.
E12-F048B 4.2 VERIFY RHR B TEST VALVE TO SUPR POOL is CLOSED.
E12-F024B NA 4.3 IF RHR B system is being used to spray containment, THEN TERMINATE Containment Spray as follows:
4.3.1 VERIFY LPCI B INJECTION VALVE is CLOSED.
E12-F042B 4.3.2 VERIFY CNTMT SPRAY B MANUAL INITIATION pushbutton collar is in DISARM.
E12A-S63B 4.3.3 DEPRESS CNTMT SPRAY B SEAL IN RESET pushbutton to reset the Containment Spray initiation logic.
E12A-S64B NA 4.3.4 IF Combustible Gas Mixing System B is NOT
- running, THEN CLOSE CNTMT SPRAY B FIRST SHUTOFF.
E12-F028B 4.3.5 CLOSE CNTMT SPRAY B SECOND SHUTOFF.
E12-F537B 4.4 VERIFY RHR B HXS OUTLET VALVE is OPEN.
1E12-F003B 4.5 VERIFY RHR B HXS BYPASS VALVE is OPEN.
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.2
Title:
RHR B INJECTION Use Category:
In-Field Reference Revision:
4 Page:
6 of 8 CAUTION Rapid injection of water with the Reactor NOT shutdown may induce a large power excursion and result in substantial core damage. With either Inside or Outside the shroud injection, Core damage is more likely at lower RPV Pressures with RPV level below the top of the fuel channel (L1 16.5).
Following a rapid RPV depressurization slowly restore RHR injection to ensure Feedwater piping is full prior to establishing higher injection flow rates.
5.0 PERFORM the following as needed, while injecting into the RPV:
NA 5.1 WHEN desired to inject inside the shroud, THEN PERFORM the following:
5.1.1 VERIFY the SHUTDOWN COOLING B TO FDW SHUTOFF valve fully CLOSED.
E12-F053B 5.1.2 OPERATE LPCI B INJECTION VALVE.
E12-F042B NA 5.2 WHEN desired to inject outside the shroud, THEN PERFORM the following:
5.2.1 AT 1H13-P618, VERIFY RHR ISOL BYPASS E12-F053B keylock switch is in BYPASS.
E12AS73 5.2.2 VERIFY LPCI B INJECTION VALVE is CLOSED.
E12-F042B 5.2.3 THROTTLE SHUTDOWN COOLING B TO FDW SHUTOFF to the desired flowrate.
E12-F053B
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.2
Title:
RHR B INJECTION Use Category:
In-Field Reference Revision:
4 Page:
7 of 8 NOTES Maintain cooldown rate within Tech Spec limits prior to Emergency Depressurization.
Following Emergency Depressurization maximize RHR flow thought heat exchanger; disregard Tech Spec cooldown limits as required.
6.0 THROTTLE the following valves to reject heat from Primary Containment:
RHR B HXS BYPASS VALVE.
1E12-F048B RHR B HXS OUTLET VALVE.
1E12-F003B END OF SECTION SCOPE OF REVISION Rev. 4
- 1. Added action to start RHR B based upon system being in standby readiness (601055226).
- 2. Deleted the comp action based upon 5 SRVs for ED, to close the min flow valve at higher RPV pressures. 6 SRVs are now used to ED.
- 3. Removed Restriction on Inside the shroud injection prior to ED based upon acceptance of Issue 1610 which removed the restrictions on inside the shroud injection.
- 4. Deleted use of Isolation Reset to simplify the required actions to those that work in all plant conditions.
- 5. Updated Control Room Back Panel Locations to delete SAS reference.
(601060229)
PERRY NUCLEAR POWER PLANT Instruction Number:
EOP-SPI 6.2
Title:
RHR B INJECTION Use Category:
In-Field Reference Revision:
4 Page:
8 of 8 Control Room Back Panel Locations
OT-3701-E51_503_RO Rev A JOB PERFORMANCE MEASURE SETUP SHEET System:
E51, Reactor Core Isolation Cooling Time Critical:
No Alternate Path:
Yes Applicability:
RO/SRO Safety Function:
2 - Reactor Water Inventory Control Validated:
12 minutes
References:
EOP-SPI 6.6 Rev 6 Required Material EOP-SPI 6.6, RCIC Injection And Pressure Control Tasks:
217-565-04-01 Control RPV Level with RCIC Operating in the Injection Mode Task Standard:
Restart RCIC injection by resetting (closing) 1E51-F510; opening 1E51-F510, and opening 1E51-F013. Upon failure of the RCIC Flow Controller the operator takes the controller to Manual and controls RCIC speed to control injection.
K/A Data:
217000 K3.01 Knowledge of the effect that a loss or malfunction of the Reactor Core Isolation Cooling System will have on the following systems or system parameters: Reactor water level. IR: RO 4.2 A4.02 Ability to manually operate and/or monitor in the control room:
Turbine trip throttle valve reset IR: RO 4.0
- 1.
Setup Instructions:
Reset simulator to a shutdown IC with RPV level <L3. For 2022 ILO NRC Exam, reset simulator to IC-159. Leave simulator in FREEZE. Place yellow switch caps on HPCS Pump and Injection valve. Run Schedule file JPM-E51-503; verify Event file JPM-E51-503 loads. Wait for ICS to fall through then place simulator in RUN.
Acknowledge Alarms and allow RPV level to lower to L3 then place simulator in FREEZE.
After the Cue has been read, place the simulator in RUN.
- 2.
Location / Method: Simulator / Perform
- 3.
Initial Condition: The plant experienced a loss of feed and is operating IAW EOP-01.
HPCS is tagged out for maintenance. The Motor Feed Pump tripped on overcurrent.
Reactor water level control band is 150 to 219. RCIC was previously running and was manually tripped prior to the failure of the Motor Feed Pump. Another operator is controlling reactor pressure.
- 4.
Initiating Cue: The Unit Supervisor directs you to maintain RPV level IAW EOP-SPI 6.6, RCIC Injection and Pressure Control.
Start:
Stop:
Candidate:
OT-3701-E51_503_RO Rev A 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 6.6, RCIC Injection and Pressure Control NOTE Steps 1.0 and 2.0 are simple actions and can be performed from memory.
1.0 IF RCIC was manually Tripped during operation, THEN PERFORM the following to recover the RCIC turbine:
1.1 HOLD the RCIC TURBINE TRIP THRT V LATCH in CLOSED, UNTIL fully CLOSED.
1E51-F510 Critical Step:
Candidate holds the control switch for 1E51-F510 in the closed direction until it is fully closed.
Instructor Cue:
When the candidate locates a copy of EOP-SPI-6.6, hand the operator a yellow copy of the procedure.
Notes:
The turnover states that RCIC was manually tripped previously.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-E51_503_RO Rev A Step 2 NOTES
- It may be necessary to mechanically reset the RCIC Trip Throttle Valve if the Trip Throttle Valve position indicator does not indicate open.
- With an initiation signal present, the RCIC INJECTION VALVE receives an Open signal when the RCIC TURBINE TRIP THRT V LATCH is NOT Fully Closed.
CAUTION
- RCIC turbine speed control using RCIC TURBINE TRIP THRT V LATCH 1E51-F510 can be extremely sensitive to changes in valve position. Speed control may be influenced by turbine inlet steam quality and RCIC flow controller settings.
- The RCIC Turbine overspeed is set between 5369 RPM and 5551 RPM 1.2 WHILE maintaining Turbine Speed below 5000 RPM, PERFORM the following concurrently:
- SLOWLY THROTTLE RCIC TURBINE TRIP THRT V LATCH to roll the RCIC Turbine, UNTIL the valve is FULL OPEN.
1E51-F510 Critical Step:
Candidate slowly opens 1E51-F510.
Instructor Cue:
None Notes:
When 1E51-F013 & E51-F510 are open, the RCIC controller fails to 2100 rpm over 15 seconds.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-E51_503_RO Rev A Step 3
- VERIFY RCIC INJECTION VALVE is OPEN.
1E51-F013 Critical Step:
Candidate takes 1E51-F013, RCIC Injection Valve to OPEN.
Instructor Cue:
None Notes:
When 1E51-F013 & E51-F510 are open, the RCIC controller fails to 2100 rpm over 15 seconds.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 4 RCIC flow controller fails to 2100 rpm.
Critical Step:
Candidate takes the RCIC Pump Flow Controller to MANUAL.
Standard:
The candidate observes RCIC Turbine RPM on 1E51-R607 has dropped to 2100 rpm and will identify that the RCIC Pump Flow Controller, 1E51-R600 has failed in AUTOMATIC.
Instructor Cue:
If the candidate informs the evaluator of the need to take manual control of the RCIC turbine, acknowledge the statement.
Notes:
NORM-OP-1002, Conduct of Operations, p. 71, directs the operator to inform the Command SRO of the need and intent to place a controller in manual operation.
Candidate may use ARI-H13-P601-21-F3, RCIC PUMP DISCHARGE FLOW LOW as direction to place controller in MANUAL SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-E51_503_RO Rev A Step 5 RCIC flow controller fails to 2100 rpm.
Critical Step:
Candidate depresses the OPEN push button on the RCIC Flow Controller, 1E51-R600, to raise turbine speed and establish steady-state injection of 700 gpm.
Standard:
The candidate raises turbine speed.
Instructor Cue:
If the candidate report when RCIC is injecting into the RPV, acknowledge the report.
Notes:
The candidate will need to monitor and adjust the RCIC turbine speed as pressure changes.
The controller has two adjustment speeds, FAST & SLOW. This is controlled by the finger pressure placed on the OPEN & CLOSE pushbuttons.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-E51_503_RO Rev A Step 6 1.2 GO TO Step 8.0 NOTE For the CST to be considered available the following conditions must be met:
CAUTION Power to the CST Level instrument heat trace is lost during a Loss of AC Power event.
Verification that the CST level instruments are functional SHALL be completed prior to alignment of the RCIC system to take a suction of the CST.
8.0 The CST is available RCIC PUMP SUPR PL SUCT ISOL is OPEN 1E51-F031 THEN PLACE RCIC suction on the CST as follows:
8.1 AT H13-P629, Card File E21A-Z2-1, REMOVE the following trip units to defeat the RCIC High Suppression Pool Level suction transfer:
- SUPR PL LVL.
E51-N636A
- SUPR PL LVL.
E51-N636E Critical Step:
Candidate removes trip units E51-N636A and E51-N636E Instructor Cue:
None Notes:
If the Candidate delays identification of the controller failure, RCIC suction may shift from the CST to the Suppression Pool since RCIC Min Flow is directed to the SP.
This is only a CRITICAL STEP if RCIC suction has shifted to the Suppression Pool when Step 8.0 is evaluated. Otherwise this step is not applicable.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-E51_503_RO Rev A Step 7 NOTE The control switch for RCIC PUMP SUPR PL SUCT ISOL, 1E51-F031, must be placed in CLOSE prior to RCIC PUMP CST SUCTION VALVE, 1E51-F010, reaching full open or the CST/Supr Pool suction interlock will cause RCIC PUMP CST SUCTION VALVE, 1E51-F010, to close automatically.
8.3 TAKE RCIC PUMP CST SUCTION VALVE to OPEN.
1E51-F010 8.4 TAKE RCIC PUMP SUPR PL SUCT ISOL to CLOSE.
1E51-F031 Critical Step:
Candidate opens 1E51-F010 and closes E51-FO31 Instructor Cue:
None Notes:
Step 8.2 is not applicable.
This is only a CRITICAL STEP if RCIC suction has shifted to the Suppression Pool when Step 8.0 is evaluated. Otherwise this step is not applicable.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-E51_503_RO Rev A Step 8 9.0 PERFORM Steps 10.0, 11.0 and 12.0 as needed to maintain RPV Level and RPV pressure within directed bands.
10.0 WHEN desired to operate RCIC in Pressure Control Mode, THEN PERFORM the following:
11.0 WHEN desired to operate RCIC in Level Control Mode THEN PERFORM the following:
11.1 VERIFY RCIC STEAM SHUTOFF is OPEN.
1E51-F045 11.2 IF transitioning from Pressure Control Mode (Step 10.0) 11.3 TAKE RCIC INJECTION VALVE to OPEN.
1E51-F013 11.4 VERIFY RCIC FIRST TEST VALVE TO CST is CLOSED.
1E51-F022 11.5 MAINTAIN RCIC flow between 350 GPM and 700 GPM, using RCIC pump flow controller.
1E51-R600 Standard:
The candidate verifies proper operation of RCIC IAW Step 11.0 while pressure lowers. RCIC flow should be maintained 350-700 gpm.
Instructor Cue:
None Notes:
Step 10.0 is N/A.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Terminating Cue:
RCIC is injecting into the RPV and level is rising.
Evaluation Results:
SAT_____
UNSAT_____
End Time:
OT-3701-E51_503_RO Rev A JPM CUE SHEET INITIAL CONDITIONS:
- HPCS is tagged out for maintenance.
- The Motor Feed Pump tripped on Over Current.
- Reactor water level control band is 150 to 219.
- RCIC was previously running and was manually tripped prior to the failure of the Motor Feed Pump.
- Another operator is controlling reactor pressure.
INITIATING CUE:
The Unit Supervisor directs you to maintain RPV level IAW EOP-SPI 6.6, RCIC Injection and Pressure Control.
OT-3701-G43_001_RO Rev A JOB PERFORMANCE MEASURE SETUP SHEET System:
G43 - Suppression Pool Makeup System Time Critical:
No Alternate Path:
No Setting:
Simulator Applicability:
RO/SRO Safety Function:
5 - Containment Integrity Validated Time:
7 minutes
References:
EOP-SPI 3.2 Rev. 3 Required Material:
EOP-SPI 3.2, SPMU Initiation Tasks:
002-503-05-01 Initiate SPMU Task Standard:
Initiate SPMU by closing G41-F100, CNTMT POOLS SUPP ISOL, placing G43-S13 and G43-S12, SUPR POOL MAKEUP A & B FULL FLW TEST PERM in TEST, and Arming and Depressing G43-S5 and G43-S7 SUPR PL MAKE-UP A & B MANUAL INITIATION push buttons IAW EOP-SPI 3.2.
K / A Data:
295030 - Low Suppression Pool Water Level - EA1.04 Ability to operate and/or monitor the following as they apply to Low Suppression Pool Water Level: Suppression pool make-up system(s):
Importance: RO 3.5
- 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 2022 ILO Exam, reset to IC-158 - no other actions needed)
- 2.
Location / Method: Simulator / Performance
- 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-02 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 A 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 IF SUPR POOL MAKE-UP A LOGIC is in AUTO AND a Division 1 LOCA signal is present, THEN ARM AND DEPRESS the SUPR PL MAKE-UP A MANUAL INITIATION pushbutton.
G43-S6 G43-S5 2.0 IF SUPR POOL MAKE-UP A LOGIC is in AUTO AND a Division 2 LOCA signal is present, THEN ARM AND DEPRESS the SUPR PL MAKE-UP B MANUAL INITIATION pushbutton.
G43-S6 G43-S5 Standard:
The Operator confirms that Steps 1.0 and 2.0 are N/A.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-G43_001_RO Rev A Step 2 3.0 VERIFY CNTMT POOLS SUPP ISOL is CLOSED.
G41-F100 Critical Step:
Operator closes G41-F100.
Instructor Cue:
None Notes:
None.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 3 4.0 IF SPMU is NOT INITIATED AND electric power is available, THEN INITIATE both divisions of SPMU as follows:
4.1 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): ________________________________________________________________
OT-3701-G43_001_RO Rev A 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.
4.2 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 4.3 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 A Step 5 4.4 ARM AND DEPRESS the SUPR PL MAKE-UP A MANUAL INITIATION pushbutton.
G43-S5 4.5 ARM AND DEPRESS the SUPR PL MAKE-UP B MANUAL INITIATION pushbutton.
G43-S7 Critical Step:
Operator Arms and Depresses G43-S5 and G43-S7.
Instructor Cue:
None Notes:
None.
SAT ___
UNSAT ___
Comment(s): ________________________________________________________________
Step 6 4.6 CONFIRM the following valves are OPEN:
- SUPR PL MAKE-UP A FIRST SHUTOFF.
G43-F030A
- SUPR PL MAKE-UP A SECOND SHUTOFF.
G43-F040A
- SUPR PL MAKE-UP B FIRST SHUTOFF.
G43-F030B
- SUPR PL MAKE-UP B SECOND SHUTOFF.
G43-F040B Standard:
The Operator confirms G43-F030A & G43-F040A and G43-F030B &
G43-F040B are open.
Instructor Cue:
None Notes:
EOP-SPI 3.2 Steps 5.0 & 6.0 are N/A.
UNSAT ___
Comment(s): ________________________________________________________________
OT-3701-G43_001_RO Rev A Terminating Cue: Suppression Pool Makeup was initiated for both A & B trains IAW EOP-SPI 3.2 and SPMU is in progress.
Evaluation Results:
SAT_____
UNSAT_____
End Time:
OT-3701-G43_001_RO Rev A 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.
- 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.
OT-3701_M25_502 Rev A JOB PERFORMANCE MEASURE SETUP SHEET System:
M25/M26 Control Room Ventilation and Emergency Recirc System Time Critical:
No Alternate Path:
Yes Setting:
Simulator Applicability:
RO/SRO Safety Function:
9 - Radioactivity Release Validated Time:
19 Minutes
References:
SOI-M25/26 Rev. 27, ARI-H13-P904-0002 Rev 13, NOP-OP-1002 Rev 17, &
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 by shifting to alternate train by performing the following:
place M25-S7, CONT RM HVAC TRAIN A MODE SELECT, in NORM; recognizes the failure of the system in NORM; then place M25-S7 in EMERGENCY RCIRC. Then stop Return Fan A after recognizing it has failed to stop.
K/A:
290003 - Control Room Ventilation - 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 3.5
- 1.
Setup Instructions: Reset simulator to any IC with M25A running in ER and M25B S/D to Secured Status. (For 2022 ILO Exam, reset to IC 157) 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 Return 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 A 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 A Step 2 7.6.4 PLACE both of the following in NORM:
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): ________________________________________________________________
Alternate Path Starts Here
OT-3701_M25_502 Rev A 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 A 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:
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 A 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 A 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.
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 A 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-R10_002_RO Rev A JOB PERFORMANCE MEASURE SETUP SHEET System:
AC Power Time Critical:
No Alternate Path:
No Applicability:
RO/SRO Safety Function: 6 - Electrical Setting:
Control Room / Plant Validated:
15 minutes
References:
ONI-SPI F-1 Rev 7 Tasks:
066-508-04-01 Respond to a Loss of Off Site Power 066-509-01-01 Place Unit 1 (or Unit 2) SU XFMR in Service 262-534-01-01 Energize Unit 1 Tie Bus TL12, Bus TH12, Bus TH21, Bus L21, or Interbus Transformer.
Task Standard:
Energize buses L20 and TH21 by closing breakers (simulate) L2003, L2006, and EH2101 per ONI-SPI F-1.
K / A Data:
295003 AA1.01 Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: A.C. electrical distribution system Importance 4.0
- 1.
Setup Instructions: None. Operator provided with a copy of ONI-SPI F1 Section 2.0 with Step 2.4 marked up.
- 2.
Location / Method: Control Room / simulation
- 3.
Initial Condition:
- Plant is operating in accordance with ONI R10. Loss of AC Power.
- ONI-SPI F1 Off-Site Power Restoration Sections 1.0 and 2.0 are complete.
- Main Bus 2 - West Bus is energized
- Main Bus 1 - East Bus is energized.
- Disconnect S290 is closed.
- Disconnect S180 is open.
- Bus L10 is NOT available for energization.
- Bus L20 is available for energization
- 4.
Initiating Cue: Unit Supervisor directs you the Reactor Operator to energize Bus L20 and Bus TH21 per ONI-SPI F1 Off-Site Power Restoration.
Start Time:
End Time:
Candidate:
OT-3701-R10_002_RO Rev A 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-SPI F-1, Off-Site Power Restoration Standard:
Operator reviews Initial Conditions and ONI-SPI F-1 and determines that Step 3.4 will need to be completed.
Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s):________________________________________________________________
OT-3701-R10_002_RO Rev A Step 2 3.4 Bus L20 is available to be re-energized Main Bus 1 - East Bus is energized Main Bus 2-West Bus is energized Unit Two Startup Transformer Manual Disconnect S290 is closed Unit One Startup Transformer Manual Disconnect S180 is closed PERFORM Step 3.4.1 to energize Bus L20 from the Unit 2 Startup transformer PERFORM Step 3.4.2 to energize Bus L20 from the Unit 1 Startup transformer Standard:
Operator works thru matrix and determines that Step 3.4.1 is to be performed.
Instructor Cue:
When Candidate approaches and observes panel 2H13-P870 inform him/her that all L breaker green indicating lights are illuminated and all L breaker semaphores indicate green.
Notes:
None SAT ___
UNSAT ___
Comment(s):________________________________________________________________
OT-3701-R10_002_RO Rev A Step 3 3.4.1 Energize bus L20 from the Unit 2 Startup transformer as follows:
3.4.1.a VERIFY the START-UP TRANSFORMER white potential light (secondary windings) is energized.
200-PY-B 3.4.1.b CLOSE the MAIN START-UP SUPPLY BRKR.
L2003 3.4.1.c OBSERVE voltage on BUS L20 VOLTS indicates 12.5-14.3KV.
2R22-R012 Standard:
Verifies white light on and verifies voltage on 2R22-R012.
Critical Step:
Simulates closing L2003 Instructor Cue:
- White potential light is ON;
- L2003 - Initially, Green light is ON and Red light is OFF.
- After closing L2003 - Red light is ON and Green light is OFF and voltage indicate as read (or 13.5 KV if different)
Notes:
None SAT ___
UNSAT ___
Comment(s):________________________________________________________________
Step 4 3.4.1.d GO TO step 3.4.3.
Standard:
Operator proceeds to Step 3.4.3 Instructor Cue:
None Notes:
None SAT ___
UNSAT ___
Comment(s):________________________________________________________________
OT-3701-R10_002_RO Rev A Step 5 3.4.3 WHEN Bus L20 is energized, THEN PERFORM the following to restore Bus TH21:
3.4.3.a CLOSE the INTERBUS TRANSFORMER BRKR to energize LH-2-A.
L2006 3.4.3.b CLOSE the BUS TIE BRKR.
EH2101 3.4.3.c VERIFY BUS TH21 white potential light on 1H13-P877 is energized.
3.4.3.d WHEN time permits, THEN REFER to SOI-2 R10 (4KV) to perform a check of Interbus Transformer.
LH-2-A Standard:
Operator restores power to Bus TH21 and verifies TH21 potential light is ON and directs check of transformer LH2A Critical Step:
Operator simulates closing breakers L2006, and EH2101 Instructor Cue:
- L2006 - Initially, Green light is ON and Red light is OFF;
- After closing L2006 - Red light ON and Green light OFF;
- EH2101 - Initially, Green light ON and Red light OFF;
- After closing EH2101 - Red light ON and Green light OFF and Bus TH21 White potential light is ON.
- Time does not permit for Step 3.4.3.d.
Notes:
Breaker EH2101 in on panel 2H13-P877.
Bus TH21 volts on meter R22-R020A is 4300 volts if read.
SAT ___
UNSAT ___
Comment(s):________________________________________________________________
Terminating Cue: Bus L20 is energized and Bus TH21 is energized.
Evaluation Results:
SAT_____
UNSAT_____
End Time:
OT-3701-R10_002_RO Rev A JPM CUE SHEET INITIAL CONDITIONS:
- Plant is operating in accordance with ONI R10. Loss of AC Power.
- ONI-SPI F1 Off-Site Power Restoration Sections 1.0 and 2.0 are complete
- Main Bus 2 - West Bus is energized
- Main Bus 1 - East Bus is energized.
- Disconnect S290 is closed.
- Disconnect S180 is open.
- Bus L10 is NOT available for energization.
- Bus L20 is available for energization INITIATING CUE:
Unit Supervisor directs you the Reactor Operator to energize Bus L20 and Bus TH21 per ONI-SPI F1 Off-Site Power Restoration.