ML093430209
| ML093430209 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/07/2009 |
| From: | Bruno Caballero NRC/RGN-II/DRS/OLB |
| To: | Southern Nuclear Operating Co |
| References | |
| 50-321/09-302, 50-366/09-302 | |
| Download: ML093430209 (140) | |
Text
FACILITY NAME: _....;..H;.;..A.;..;.T...;;;;,C...;;..;H'---________
Section 5 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 DRAFT SIM/IN-PLANT JPMS CONTENTS:
o Draft SIMULATOR liN-PLANT JPMs Location of Electronic Files:
O:\\Hatch Examinations\\lnitial Exam 2009-302 Submitted By:
- ==Bru
- ..=n=o-=C:..=;ab::...:::;al=.;:leo=...::ro_____ V erified BY:-fI.-,f---IM~J-L-~~~--
FACILITY NAME: _....;.H..:.:.A..:..:T:....;:C:..:..H~ _________ _
Section 5 REPORT NUMBER: 05000321/2009302 AND 05000366/2009302 DRAFT SIM/IN-PLANT JPMS CONTENTS:
o Draft SIMULATOR liN-PLANT JPMs Location of Electronic Files:
O:\\Hatch Examinations\\lnitial Exam 2009-302 Submitted By:
Bruno Caballero Verified By:--If--,~----=-'~~~~ __
TITLE DRAFT Southern
. I. Hatch uclear uclear Plant Operations Training JPM Simulator 1 START A RECIRC MG SET / Adjustable Speed Drive (ASD) FROM THE CONTROL ROOM DALE MORAN Im(;OMMENl)~])
NIR l\\'fEf)lA.NJ)I\\11lER LR-JP-04.02-21
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TITLE DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 1 START A RECIRC MG SET / Adjustable Speed Drive (ASD) FROM THE CONTROL ROOM AUTHOR MEDIA NUMBER TIME DALE MORAN LR-JP-04.02-21 38.0 Minutes RECOMMENDED BY APPROVED BY DATE NIR
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Media Number:
\\ Rey.
- .********J)~te ** *******
.......*.........ii ***i
- ** *in_......*......... ***j...~..i].:~i__i *. ***.**.*<>i...* :
- i47 inches as indicated on GEMAC.
B.
Use rfB31_29 and open Seal purge valve B31-F016A.
C.
Open Reactor Recirc Pump Suction Valves, 2B31-F023A and 2B31-F023B.
D.
Tum OFF the SPDS screens.
E.
Acknowledge/Reset annunciators
- 5. NOTE: Key 1 is to be activated after "A" Recirc Pump is running normally
- 3.
PLACE the Simulator in FREEZE until the INmA TING CUE is given.
- 4.
ESTIMATED Simulator SETUP TIME:
10 Minutes SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #101 and leave in FREEZE.
- 2.
INSERT the following MALFUNCTIONS:
MALF#
TITLE FINAL RAMP KEY VALUE RATE mf60211146 Window 2: ASD A Fatal Fault (Annunciator 1
On) mf60211170 Window 26: ASD A Cooling Fault 1
(Annunciator On) mf60211 169 Window 25: ASD A Cooling Trouble 1
(Annunciator On)
- 3.
INSERT the following 10 OVERRIDES:
OR#
DESCRIPTION FINAL RAMP Key VALUE RATE
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loB31-ASD A - Cooling Normal OFF 1
DS42AWI
- 4.
Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A.
Raise RWL to >47 inches as indicated on GEMAC.
B.
Use rfB3L29 and open Seal purge valve B31-F016A.
C.
Open Reactor Recirc Pump Suction Valves, 2B31-F023A and 2B31-F023B.
D.
Turn OFF the SPDS screens.
E.
Acknowledge/Reset annunciators
- 5. NOTE: Key 1 is to be activated after "A" Recirc Pump is running normally
- 3.
PLACE the Simulator in FREEZE until the INmATING CUE is given.
- 4.
ESTIMATED Simulator SETUP TIME:
10 Minutes
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
Unit 2 is in cold shutdown
- 2.
SPDS is Out of Service and being worked.
- 3.
"A" Recirc Pump is required for forced circulation.
- 4.
CRD seal purge is in service with 1.9 gpm flow to the "A" seals.
S.
Maintenance has performed all applicable sections for venting/purging of the "A" Recirc Pump seals IAW 52CM-B31-003-0.
- 6.
34S0-B31-001-2 Attachment 5 "Recirc Pump Startup Prerequisites" was just completed and is SAT for a start of the "A" Recirc Pump.
INITIATING CUES:
Start 2A Recirc Pump IA W, 34S0-B31-00l-2 "Reactor Recirculation System" Section 7.1.3.
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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
Unit 2 is in cold shutdown
- 2.
SPDS is Out of Service and being worked.
- 3.
"A" Recirc Pump is required for forced circulation.
- 4.
CRD seal purge is in service with 1.9 gpm flow to the "A" seals.
S.
Maintenance has performed all applicable sections for venting/purging of the "A" Recirc Pump seals IA W 52CM-B31-003-0.
- 6.
34S0-B31-001-2 Attachment 5 "Recirc Pump Startup Prerequisites" was just completed and is SAT for a start of the "A" Recirc Pump.
INITIATING CUES:
Start 2A Recirc Pump IA W, 34S0-B31-001-2 "Reactor Recirculation System" Section 7.1.3.
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5'l'$;P clf<
For INITIAL Operator Programs:
LR-JP-04.02-21 Page 4 of8
- .*.Si\\T1IJ~SA'l' (COMMENTS For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRmCAL STEPS must be completed for Satisfactory Performance.
NOTE: Unless otherwise indicated, all actions are carried out at paneI2Hll-P601.
- 1. Operator obtains procedure and Operator has obtained 34S0-reviews the procedure's precautions B31-001-2 and reviewed the and limitations.
precautions and limitations.
- 2. Refer to correct procedural section.
Operator refers to section 7.1.3 and then refers to section 7.1.2.1.
- 3. Depress the ASD A Fault Reset Operator depresses the ASD A pushbutton to reset all ASDlRecirc Fault Reset pushbutton.
annunciators whose conditions have cleared.
- 4. Confirm all remaining annunciators Operator observes no other have been addressed.
annunciators in alarm to inhibit Recirc Pump A startup.
START TIME: ___ _
SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT:
WHEN addressed by the Operator, INFORM the Operator that the ASD Cooling Water System has been in service for a minimum of two hours per Section 7.1.1.1, Startup Of The ASD A Cooling System S. Confirm the ASD A Cooling System Operator confirms the ASD A SAT I UNSAT has been in operation for a minimum Cooling System has been in of two hours operation for a minimum of two hours PROMPT:
WHEN the Operator addresses Cooling Water Conductivity, INFORM the Operator, the ASD SPDS screens or locally at ASD A Cooling Cabinet 2B31-S002AG that cooling system conductivity is <1 [!S.
PROMPT:
WHEN the Operator addresses which NXG Computer is in control, INFORM the Operator, the B NXG Computer is in control
(** Indicates critical step)
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STEP PERFORMANCE STEP STANDARD For INITIAL Operator Programs:
LR-JP-04.02-21 Page 4 of 8 SATIUNSAT (COMMENTS For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRmCAL STEPS must be completed for Satisfactory Performance.
START TIl\\1E: ___ _
NOTE: Unless otherwise indicated, all actions are carried out at pane12HII-P601.
- 1. Operator obtains procedure and Operator has obtained 34S0-SAT/UNSAT reviews the procedure's precautions B31-001-2 and reviewed the and limitations.
precautions and limitations.
- 2. Refer to correct procedural section.
Operator refers to section 7.1.3 SAT/UNSAT and then refers to section 7.1.2.1.
- 3. Depress the ASD A Fault Reset Operator depresses the ASD A SAT I UNSAT pushbutton to reset all ASDlRecirc Fault Reset pushbutton.
annunciators whose conditions have cleared.
- 4. Confirm all remaining annunciators Operator observes no other SAT/UNSAT have been addressed.
annunciators in alarm to inhibit Recirc Pump A startup.
PROMPT:
WHEN addressed by the Operator, INFORM the Operator that the ASD Cooling Water System has been in service for a minimum of two hours per Section 7.1.1.1, Startup Of The ASD A Cooling System S. Confirm the ASD A Cooling System Operator confirms the ASD A SAT/UNSAT has been in operation for a minimum Cooling System has been in of two hours operation for a minimum of two hours PROMPT:
WHEN the Operator addresses Cooling Water Conductivity, INFORM the Operator, the ASD SPDS screens or locally at ASD A Cooling Cabinet 2B31-S002AG that cooling system
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conductivity is <1 !AS.
PROMPT:
WHEN the Operator addresses which NXG Computer is in control, INFORM the Operator, the B NXG Computer is in control
(** Indicates critical step)
- 6. Confirm locally at 2B31-S002AC, ASD A FPC Cabinet:
- Conductivity is <1 IlS
- NXG 'B' Computer Control Power Supply is in control
Operator sends an SO to 2B31-S002AC, ASD A FPC Cabinet to confirm:
- Conductivity is <1 IlS
- NXG 'B' Computer Control Power Supply is in control Operator confirms ASD A COOLING NORMAL light is illuminated.
LR-JP-04.02-21 Page 5 of8
.* SJ\\'l'1UJN~A'l'..
. **eOMMENTS**
SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT:
WHEN the Operator addresses Bypassed Cells, INFORM the Operator there are no Bypassed Cells.
- 8. Verify that any ASD Power Cell that Operator confirms there are no SAT/UNSAT is BYPASSED, has been addressed.
bypassed cells.
- 9. Confirm OPEN or OPEN Reactor Operator confirms PUMP SAT/UNSAT Recirc Pump Suction Valve, 2B31-SUCTION VLV, 2B31-F023A is F023 A.
OPEN, red light illuminated.
- 10. Confirm or start Reactor Recirc 2A At panel2H11-P657, Operator SAT/UNSAT ASD Room Cooler 2T41-B012.
confirms 2T4l-BOl2 is RUNNING, red light illuminated.
- 11. Confirm/Close Reactor Recirc Pump Operator confirms PUMP DISCH SAT/UNSAT Discharge Valve, 2B31-F031A.
VLV 2B31-F031A is CLOSED, green light illuminated.
Shutdown pushbutton.
1~7~~~
!;ri2;{!;,thA~SJ).~~:()~t~~~1*.~.L!L~1_i*
- .***..**. Operator positions the ASD A SAT/UNSAT
\\<i I~,""';;'.:n -'F./'t'
..........*.. /**~-:T control switch to START.
';:'J.~;~,<<<...............<<,.<.....'i
- 14. Confirm the following:
Operator confirms the following:
- The ASD A PRE-CHARGING
- After - 30 seconds, the ASD A
- - 30 seconds, the ASD A SAT/UNSAT PRE-CHARGING light PRE-CHARGING light J
extinguishes.
extinguishes.
(** Indicates critical step)
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(
"TEP
- 6.
- 7.
PERFO~NCESTEP Confirm locally at 2B31-S002AC, ASD A FPC Cabinet:
- Conductivity is < 1 flS
- NXG 'B' Computer Control Power Supply is in control Confirm ASD A COOLING NORMAL light is illuminated on 2HII-P602.
STANDARD Operator sends an SO to 2B31-S002AC, ASD A FPC Cabinet to confirm:
- Conductivity is <1 flS
- NXG 'B' Computer Control Power Supply is in control Operator confirms ASD A COOLING NORMAL light is illuminated.
LR -JP-04.02-21 Page 5 of 8 SATIUNSAT COMMENTS SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT:
WHEN the Operator addresses Bypassed Cells, INFORM the Operator there are no Bypassed Cells.
- 8. Verify that any ASD Power Cell that Operator confirms there are no SAT/UNSAT is BYPASSED, has been addressed.
bypassed cells.
- 9. Confirm OPEN or OPEN Reactor Operator confirms PUMP SAT/UNSAT Recirc Pump Suction Valve, 2B31-SUCTION VLV, 2B31-F023A is F023 A.
OPEN, red light illuminated.
- 10. Confirm or start Reactor Recirc 2A At paneI2HII-P657, Operator SAT/UNSAT ASD Room Cooler 2T41-B012.
confirms 2T41-B012 is RUNNING, red light illuminated.
- 11. Confirm/Close Reactor Recirc Pump Operator confirms PUMP DISCH SAT/UNSAT Discharge Valve, 2B31-F031A.
VLV 2B31-F031A is CLOSED, green light illuminated.
Shutdown pushbutton.
control switch to START.
- 14. Confirm the following:
Operator confirms the following:
- The ASD A PRE-CHARGING
- After -30 seconds, the ASD A
- -30 seconds, the ASD A SAT/UNSAT PRE-CHARGING light PRE-CHARGING light j
extinguishes.
extinguishes.
(** Indicates critical step)
- The ASD A Input Breaker CLOSES (the red light above the ASD A control switch illuminates and the green light extinguishes ).
- The ASD A START pushbutton light illuminates.
- 15. Refer to correct procedure section.
- ASD A Input Breaker CLOSES (the red light above the ASD A control switch illuminates and the green light extinguishes).
- ASD A START pushbutton light illuminates.
Operator returns to procedural section 7.1.3.
Operator confirms RPT Breakers 2C71-CB3A and 2C71-CB4A are CLOSED, red lights illuminated.
LR-JP-04.02-21 Page 6 of 8 SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT PROMPT:
IF addressed by the Operator, INFORM the Operator that a CRD Pump is in service to supply Seal Purge Flow.
. PROMPT:
IF addressed by the Operator, INFORM the Operator that Seal Purge Isolation Valve 2B31-F016A is open.
I I
PROMPT:
IF addressed by the Operator, INFORM the Operator the seals have been vented/purged lAW 52CM-B31-003-0.
- 17. Confirm OPEN or OPEN Reactor Operator observes PUMP SAT/UNSAT Recirc Pump Suction Valve, 2B31-SUCTION VL V, F023A.
2B31-F023A is OPEN, red light illuminated.
PROMPT:
IF the Operator addresses the Seal Flow Regulator, then INFORM the Operator that, per initial conditions, the local flow indicator is reading 1.9 gpm.
PROMPT:
IF addressed by the Operator, INFORM the Operator the seals have been vented/purged lAW 52CM-B31-003-0.
- 18. Confirm Reactor Recirc Pump Operator verifies PUMP DISCH SAT/UNSAT Discharge Valve, 2B31-F031B is VLV 2B31-F031B is CLOSED, CLOSED green light illuminated.
(** Indicates critical step)
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LR-JP-04.02-21 Page 6 of 8
~TEP PERFO~IANCESTEP STANDARD SATIUNSAT (COMMENTS)
I I
- The ASD A Input Breaker
- ASD A Input Breaker SAT/UNSAT CLOSES (the red light above CLOSES (the red light the ASD A control switch above the ASD A control illuminates and the green light switch illuminates and the extinguishes).
green light extinguishes).
- The ASD A START
- ASD A START SAT/UNSAT pushbutton light illuminates.
pushbutton light illuminates.
- 15. Refer to correct procedure section.
Operator returns to procedural SAT/UNSAT section 7.1.3.
- 16. Confirm CLOSED/CLOSE RPT Operator confirms RPT Breakers SAT/UNSAT Breakers 2C7l-CB3A and 2C7l-2C7l-CB3A and 2C7l-CB4A are CB4A.
CLOSED, red lights illuminated.
PROMPT:
IF addressed by the Operator, INFORM the Operator that a CRD Pump is in service to supply Seal Purge Flow.
PROMPT:
IF addressed by the Operator, INFORM the Operator that Seal Purge Isolation Valve 2B31-FO l6A is open.
PROMPT:
IF addressed by the Operator, INFORM the Operator the seals have been vented/purged IA W 52CM-B3l-003-0.
- 17. Confirm OPEN or OPEN Reactor Operator observes PUMP SAT/UNSAT Recirc Pump Suction Valve, 2B3l-SUCTION VLV, F023A.
2B31-F023A is OPEN, red light illuminated.
PROMPT:
IF the Operator addresses the Seal Flow Regulator, then INFORM the Operator that, per initial conditions, the local flow indicator is reading 1.9 gpm.
PROMPT:
IF addressed by the Operator, INFORM the Operator the seals have been vented/purged IA W 52CM-B3l-003-0.
- 18. Confirm Reactor Recirc Pump Operator verifies PUMP DISCH SAT/UNSAT Discharge Valve, 2B31-F031B is VLV 2B3l-F031B is CLOSED, CLOSED green light illuminated.
(** Indicates critical step)
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- 19. Confirm RWL is greater than +32 At pane12HII-P603, the inches.
Operator VERIFIES that RWL is greater than +32 inches.
LR-JP-04.02-21 Page 7 of8
.,ii$i\\Tll:lNSA'f (POMMEN'FS SAT/UNSAT PROMPT:
IF addressed by the Operator, INFORM the Operator that Attachment 5 was complete and acceptable within the last 15 minutes.
- 20. Confirm/Close Reactor Recirc Pump Operator confirms PUMP DISCH SAT/UNSAT Discharge Valve, 2B31-F031A.
VLV 2B31-F031A is CLOSED, green light illuminated.
- 21. Confirm ASD A START pushbutton Operator confirms ASD A SAT/UNSAT indicating lamp is illuminated.
START pushbutton indicating lamp is illuminated
- ~22*i *****~****~.c.. *~$silie;~§e~!fT~~~;;.**.*******........ Operator depresses ASD START SAT/UNSAT
<~~~hl1u()n'r..
- '.*.i................, <
.***...,;;:>i...>.. '. PUSH BUTTON.
- 23. Confirm the following:
Operator confirms the following:
- The ASD A STARTING light
- The ASD A START light
- The ASD A START light extinguishes.
extinguishes.
- 2B31-F031A, Recirc Pump A
- 2B31-F031A, Recirc SAT/UNSAT Disch Vlv, starts to JOG Pump A Disch Vlv, starts OPEN 2 seconds after the to JOG OPEN 2 seconds ASD A STARTING light after the ASD A illuminates.
STARTING light illuminates.
- The ASD A speed increases to
-370 RPM on 2B31-R660A increases to -370 RPM on and -22% on 2B3l-R661A in 2B31-R660A and -22%
about 4 seconds.
on 2B31-R661A in about 4 seconds.
- The ASD A RUNNING light
- The ASD A RUNNING SAT/UNSAT illuminates.
light illuminates.
- The ASD A STARTING light
- The ASD A STARTING SAT/UNSAT extinguishes.
light extinguishes.
(** Indicates critical step)
(
~TEP
- 19.
PERFO~CESTEP Confirm RWL is greater than +32 inches.
STANDARD At paneI2HI1-P603, the Operator VERIFIES that RWL is greater than +32 inches.
LR-JP-04.02-21 Page 7 of 8 SATIUNSAT COMMENTS SAT/UNSAT PROMPT:
IF addressed by the Operator, INFORM the Operator that Attachment 5 was complete and acceptable within the last 15 minutes.
- 20. Confirm/Close Reactor Recirc Pump Operator confirms PUMP DISCH SAT/UNSAT Discharge Valve, 2B31-F031A.
VLV 2B31-F031A is CLOSED, green light illuminated.
- 21. Confirm ASD A START pushbutton Operator confirms ASD A SAT I UNSAT indicating lamp is illuminated.
START pushbutton indicating lamp is illuminated
PUSH BUTTON.
- 23. Confirm the following:
Operator confirms the following:
- The ASD A STARTING light
- the ASD A STARTING SAT/UNSAT illuminates light illuminates.
- The ASD A START light
- The ASD A START light extinguishes.
extinguishes.
- 2B31-F031A, Recirc Pump A
- 2B31-F031A, Recirc SAT I UNSAT Disch Vlv, starts to JOG Pump A Disch Vlv, starts OPEN 2 seconds after the to JOG OPEN 2 seconds ASD A STARTING light after the ASD A illuminates.
STARTING light illuminates.
- The ASD A speed increases to
- The ASD A speed SAT/UNSAT
-370 RPM on 2B31-R660A increases to -370 RPM on and -22% on 2B31-R661A in 2B31-R660A and -22%
about 4 seconds.
on 2B31-R661A in about 4 seconds.
- The ASD A RUNNING light
- The ASD A RUNNING SAT/UNSAT illuminates.
light illuminates.
- The ASD A STARTING light
light extinguishes.
(** Indicates critical step)
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- 2B31-F031A, Recirc Pump A Disch Vlv, is FULL OPEN
<96 seconds after the Recirc ASD A STARTING light illuminates.
- Recirc A Flow, indicates 11,000 - 13,000 GPM on 2B31-R617.
2B31-F031A, Recirc Pump A Disch Vlv, is FULL OPEN <96 seconds after the Recirc ASD A STARTlNG light illuminates.
Recirc A Flow, indicates 11,000 - 13,000 GPM on 2B31-R617.
LR-JP-04.02-21 Page 8 of8
- .*.*.**~~1'(UN~,l\\':f
- . (COl\\1MENTS..
SAT/UNSAT SAT I UNSAT PROMPT:
WHEN the operator addresses Attachment 5, lNFORM the operator that another operator will complete Attachment 5.
- 24. Complete remainder of Attachment 5.
Operator has verified Attachment 5 will be completed.
NOTE: Simulator Instructor to Activate Key 1 now.
Operator places the ASD A control switch to the STOP position within 5 minutes of receiving the alarm.
NOTE: The terminating cue shall be given to the Operator when:
With no reasonable progress, the Operator exceeds double the allotted time.
Operator has tripped ASD A.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
SAT/UNSAT SAT I UNSAT END TIME: ___
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~TEP PERFO~NCESTEP 2B31-F031A, Recirc Pump A Disch Vlv, is FULL OPEN
<96 seconds after the Recirc ASD A STARTING light illuminates.
Recirc A Flow, indicates 11,000 - 13,000 GPM on 2B31-R617.
STANDARD 2B31-F031A, Recirc Pump A Disch Vlv, is FULL OPEN <96 seconds after the Recirc ASD A STARTING light illuminates.
Recirc A Flow, indicates 11,000 - 13,000 GPM on 2B31-R617.
LR-JP-04.02-21 Page 8 of 8 SATIUNSAT (COMMENTS SAT/UNSAT SAT/UNSAT PROMPT:
WHEN the operator addresses Attachment 5, INFORM the operator that another operator will complete Attachment 5.
- 24. Complete remainder of Attachment 5.
Operator has verified Attachment 5 will be completed.
NOTE: Simulator Instructor to Activate Key 1 now.
- 25. Respond to annunciator 602-102 ASD Operator places the ASD A A FATAL FAULT control switch to the STOP position within 5 minutes of receiving the alarm.
NOTE: The terminating cue shall be given to the Operator when:
With no reasonable progress, the Operator exceeds double the allotted time.
Operator has tripped ASD A.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
SAT/UNSAT SAT I UNSAT END TIME: ___ _
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
Unit 2 is in cold shutdown
- 2.
SPDS is Out of Service and being worked.
- 3.
"A" Recirc Pump is required for forced circulation.
- 4.
CRD seal purge is in service with 1.9 gpm flow to the "A" seals.
- 5.
Maintenance has performed all applicable sections for venting/purging of the "A" Recirc Pump seals lAW 52CM-B31-003-0.
- 6.
34S0-B31-001-2 Attachment 5 "Recirc Pump Startup Prerequisites" was just completed and is SAT for a start of the "A" Recirc Pump.
INITIATING CUES:
Start 2A Recirc Pump lAW, 34S0-B31-00l-2 "Reactor Recirculation System" Section 7.1.3.
(
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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
Unit 2 is in cold shutdown
- 2.
SPDS is Out of Service and being worked.
- 3.
"A" Recirc Pump is required for forced circulation.
- 4.
CRD seal purge is in service with 1.9 gpm flow to the "A" seals.
- 5.
Maintenance has performed all applicable sections for venting/purging of the "A" Recirc Pump seals IA W 52CM-B31-003-0.
- 6.
34S0-B31-00 1-2 Attachment 5 "Recirc Pump Startup Prerequisites" was just completed and is SAT for a start of the "A" Recirc Pump.
INITIATING CUES:
Start 2A Recirc Pump IA W, 34S0-B31-001-2 "Reactor Recirculation System" Section 7.1.3.
N/R DRAFT Southern E. I. Hatch uclear uclear Plant Operations Training JPM Simulator 2
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TITLE DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 2 RESTORE AND MAINTAIN RWL WITHIN A SPECIFIED RANGE USING RHRSW AUTHOR MEDIA NUMBER TIME J W Pendlebury LR-JP-34.12-11 12.0 Minutes RECOMMENDED BY APPROVED BY DATE N/R
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING 06 11102100 Include ective number 07 03112120 Include initial statement Media Number:
08 06114/05 Revised Initial License statement for successful completion 09 04/21106 Remove Cues 10 05119/07 Remove EI1-F003 and F048 to match the 11 09/18/08 For Unit 1, added critical steps to open F068AIB to reflect Page 1 of 1 LR-JP-34.12 RAB DHG RAB RAB RAB RAB RAB RAB DHG RAB JWP RAB
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SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERA TIONS TRAINING Media Number:
LR-JP-34.12 Rev~
Date Reason for Revision Author's Supv's No.
Initials Initials 06 11/02/00 Include objective number RAB DHG 07 03/12120 Include initial Operator statement RAB RAB 08 06/14/05 Revised Initial License statement for successful completion RAB RAB 09 04121106 Remove Response Cues RAB RAB 10 05/19/07 Remove Ell-F003 and F048 to match the procedure.
DHG RAB 11 09118/08 For Unit 1, added critical steps to open F068AJB to JWP RAB reflect plant procedure.
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LR-JP-34.12-11 Page 1 of7 UNIT 1 (X)
UNIT 2 (X)
RESTORE AND MAINTAIN RWL WITIDN A SPECIFIED RANGE USING RHRSW LR-JP-34.12-11 The task shall be completed when the Operator has successfully started one loop of RHRSW with at least one RHRSW pump injecting into the Reactor per 31EO-EOP-11O.
034.012 034.012.A PLANT HATCH JTA IMPORTANCE RATING:
RO 3.86 SRO Not Available KIA CATALOG NUMBER:
29S031EA108 KIA CATALOG JTA IMPORTANCE RATING:
RO 3.80 SRO 3.90 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
(current version)
Key for RHRSW Manual Override APPROXIMATE COMPLETION TIME:
12.0 Minutes 110-2 (current version)
Key for RHRSW Manual Override SIMULATOR SETUP:
REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE
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TASK TITLE:
JPMNUMBER:
UNIT 1 (X)
RESTORE AND MAINTAIN RWL WITHIN A SPECIFIED RANGE USING RHRSW LR-JP-34.12-11 LR-JP-34.12-11 Page 1 of7 UNIT 2 (X)
TASK STANDARD:
The task shall be completed when the Operator has successfully started one loop of RHRSW with at least one RHRSW pump injecting into the Reactor per 31EO-EOP-IlO.
TASK NUMBER:
034.012 OBJECTIVE NUMBER: 034.012.A PLANT HATCH JTA IMPORTANCE RATING:
RO 3.86 SRO Not Available KIA CATALOG NUMBER:
295031EA108 KIA CATALOG JTA IMPORTANCE RATING:
RO 3.80 SRO 3.90 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
I GENERAL
REFERENCES:
Unit 1 Unit 2 31EO-EOP-ll 0-1 31EO-EOP-II0-2 31EO-EOP-015-1 31EO-EOP-015-2 (current versions)
(current versions)
I REQllRED MATERIALS:
Unit 1 Unit 2 31EO-EOP-llO-l 31EO-EOP-llO-2 (current version)
(current version)
Key for RHRSW Manual Key for RHRSW Manual Override Override APPROXIMATE COMPLETION TIME:
12.0 Minutes SIMULATOR SETUP:
REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE
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SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #113 and leave in FREEZE.
LR-IP-34.12-11 Page 2 of7
- ..s*J\\1'lIJ~S.A.l'.****.*.
(CQMl\\fgN,.'.rS.
- 2.
Make sure RECORDER POWER is TURNED ON. Roll Chart Recorders and Process Computer Typers forward. Ensure any information printed on the Process Computer Typer from previous ICs is removed.
- 3.
INSERT the following MALFUNCTIONS:
1/>* ****.. *.. * ** i./*
>...../ *.
FINAL.*.. RAMP ACT.
1.**.MA,t,)'#
I*
1.**.. (_..................
VALVE. iRATE **TIME mfB21 _48A Steam Line A Break (After Restrictor) (Var) 100 100 00000 mfG31 - 242 RWCU Non-Iso! Leak (0-10000 gpm) 7 100 00000 mfE41 - 107 HPCI Failure to Start (FOOl Stuck) 00000 mfE51 - 110 RCIC Turbine Trip 00000 mfSlI 227B SUT 2D Failure 00000 mfElI - 1I5A RHR Pump A Trip 00000 mfElI - 1I5B RHR Pump B Trip 00000 mfElI - 1I5C RHR Pump C Trip 00000 mfE11 - 1I5D RHR Pump D Trip 00000 mfE21 - 102A Core Spray Pump A Trip 00000 mfE21 - 102B Core Spray Pump B Trip 00000 mfC11 - 30A Control Rod Drive Pump A Trip 00000 mfClI - 30B Control Rod Drive Pump B Trip 00000
- 4.
INSERT the following REMOTE FUNCTIONS:
STATUS rfEll167 2E11-FO 17 A&B Override 5 Min Timer ORIDE rfP64-332 Drywell Chillers B006A Lockout Reset RESET rfp64-333 Drywell Chillers B006B Lockout Reset RESET
(** Indicates critical step)
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~TEP PERFORMANCE STEP STANDARD SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #113 and leave in FREEZE.
LR-JP-34.12-11 Page 2 of7 SATIUNSAT (COMMENTS
- 2.
Make sure RECORDER POWER is TURNED ON. Roll Chart Recorders and Process Computer Typers forward. Ensure any information printed on the Process Computer Typer from previous ICs is removed.
- 3.
INSERT the following MALFUNCTIONS:
MALF#
TITLE FINAL RAMP ACT.
VALUE RATE TIME mfB21_48A Steam Line A Break (After Restrictor) (Var) 100 100 00000 mfG31_242 RWCU Non-Isol Leak (0-10000 gpm) 7 100 00000 mfE4L107 HPCI Failure to Start (FOO 1 Stuck) 00000 mfE51_11O RCIC Turbine Trip 00000 mfSll_227B SUT 2D Failure 00000 mfEILl15A RHR Pump A Trip 00000 mfEll_115B RHR Pump B Trip 00000 mfEILl15C RHR Pump C Trip 00000 mfEll_115D RHR Pump D Trip 00000 mfE21_102A Core Spray Pump A Trip 00000 mfE21_102B Core Spray Pump B Trip 00000 mfCll_30A Control Rod Drive Pump A Trip 00000 mfCll_30B Control Rod Drive Pump B Trip 00000
- 4.
INSERT the following REMOTE FUNCTIONS:
REM #
DESCRIPTION STATUS rfEl1167 2Ell-F017A&B Override 5 Min Timer ORIDE rfP64-332 Drywell Chillers B006A Lockout Reset RESET rfp64-333 Drywell Chillers B006B Lockout Reset RESET
(** Indicates critical step)
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 has had a LOCA.
- 2. RWL is below the Top of Active Fuel and decreasing.
- 4. SUT "2D" is de-energized.
- 5. RHR pumps" A, B, C, & D" have tripped.
- 6. Core Spray pumps "A" and B" have tripped.
- 7. The EOP jumpers to override the 5 minute timer have been installed for 2EII-F017A & B.
INITIATING CUES:
lAW 31EO-EOP-IlO-2, "Alternate RPV Water Level Control" maximize injection of RHRSW into the reactor using the "A" loop.
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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 has had a LOCA.
- 2. RWL is below the Top of Active Fuel and decreasing.
- 4. SUT "2D" is de-energized.
- 5. RHR pumps" A, B, C, & D" have tripped.
- 6. Core Spray pumps "A" and B" have tripped.
- 7. The EOP jumpers to override the 5 minute timer have been installed for 2EI1-F017A & B.
INITIATING CUES:
lAW 31EO-EOP-IlO-2, "Alternate RPV Water Level Control" maximize injection of RHRSW into the reactor using the "A" loop.
- 1.
- 2.
- 3.
- 4.
For INITIAL Operator Programs:
LR-JP-34.12-11 Page 5 of7 For O.JT/O.JE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRmCAL STEPS must be completed for Satisfactory Performance.
Operator identifies the materials that Operator identifies the required are required.
materials and where to obtain them.
Confirm that RHR Loop A is not At paneI2HU-P601, the operating in the LPCI mode.
Operator has VERIFIED that RHR Loop A is not operating in the LPCI mode.
Confirm or stop RHR Pumps At panel 2HII-P601, RHR 2EII-COO2A and C.
PUMPs 2EII-C002A and C are STOPPED, green lights illuminated.
Confirm or close the following valves:
At paneI2HII-P601, the 2EU-FOlD following valves are CLOSED, green light illuminated:
2EII-F016A RHR CROSSTIE VLV, 2EII-F028A 2EU-FOlD 2EU-F017A CNMT SPRAY OUTBD VLV, 2EII-F068A 2EU-F016A TORUS SPRAY OR TEST VLV, 2EII-F028A RHR OUTBD INJ VLV, 2EU-F017A HXDISCHVLV, 2EII-F068A START TIME: ___ _
SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT:
2EII-FOlD is normally de-energized in the closed position. If the Operator indicates that this is the condition of the valve, that portion of Step 4 is acceptable.
(** Indicates critical step)
IF the Operator requests the SO to verify the valve position, as SO, INFORM the Operator that valve 2EII-FOlD has been verified closed locally.
(
- 1.
- 2.
- 3.
- 4.
PERFO~CESTEP STANDARD For INITIAL Operator Programs:
LR-JP-34.12-11 Page 5 of7 SATIUNSAT COMMENTS For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
Operator identifies the materials that Operator identifies the required are required.
materials and where to obtain them.
Confirm that RHR Loop A is not At panel2HII-P601, the operating in the LPCI mode.
Operator has VERIFIED that RHR Loop A is not operating in the LPCI mode.
Confirm or stop RHR Pumps At panel2HII-P601, RHR 2E ll-C002A and C.
PUMPs 2E ll-C002A and C are STOPPED, green lights illuminated.
Confirm or close the following valves:
At panel2HII-P601, the 2EII-FOlO following valves are CLOSED, green light illuminated:
2EII-FOI6A RHR CROSSTIE VLV, 2EII-F028A 2EII-FOlO 2Ell-FOI7A CNMT SPRAY OUTBD VLV, 2EII-F068A 2EII-FOl6A TORUS SPRAY OR TESTVLV, 2EII-F028A RHR OUTBD INJ VLV, 2Ell-F017A HX DISCH VLV, 2EII-F068A START TIME: ___ _
SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT:
2E 11-FO 1 0 is normally de-energized in the closed position. If the Operator indicates that this is the condition of the valve, that portion of Step 4 is acceptable.
(** Indicates critical step)
IF the Operator requests the SO to verify the valve position, as SO, INFORM the Operator that valve 2EII-FOlO has been verified closed locally.
LR-JP-34.12-11 Page 6 of7 S~'J:lUN~A.'f COMMEN'lS IF the Operator wants the valve energized, the simulator Operator should TOGGLE REMOTE FUNCTION rfE11135, "Ell-POW Breaker Rackout," to ON.
At pane12HII-P601, the following valves are OPEN, red light illuminated:
RHR INBD INJ VLV, 2EII-F015A RHRSW CROSSTIE VLV, 2EI1-F073A RHRSW VLV, 2Ell-F075A SAT/UNSAT
- 6. Prelube RHRSW Pumps At panel 2H Il-P60 1, the RHR SERVICE WATER LUBE SAT/UNSAT 2E ll-COOlA C.
- 9. Open Service Water Crosstie Valves 2Ell-F1l9A and B, if required.
V ALVES push-button has been DEPRESSED for RHRSW Loop A pumps.
At pane12HII-P601, the Division I SERVICE 'V A TER PUMP CONTROL switch 2El1-S is in MANUAL OVERRD.
At panel 2H11-P60 1, SERVICE
'VATER PUMP 2E11-COOlA and C are RUNNING, red light illuminated.
The Operator has identified that SERV WTR CROSSTlE VLV 2Ell-F1l9A(B) does not need to be opened.
SAT I UNSAT SAT/UNSAT SAT/UNSAT NOTE: RHRSW System has no inoperable components and is capable of injecting to the vessel without the crosstie valve being opened. Only the A loop of RHRSW is needed.
- 10. Throttle RHR Outbd Injection Valve, At paneI2HII-P601, RHR SAT/UNSAT 2Ell-P017A, to control injection OUTBD INJ VLV, 2EII-P017A is THROTTLED CLOSED, to maintain injection flow at 8800 gpm flow increasing on RHR FLOW, 2EII-R603A.
(** Indicates critical step)
(
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
PERFORMANCE STEP STANDARD LR-}P-34.12-11 Page 6 of7 SATIUNSAT COMMENTS IF the Operator wants the valve energized, the simulator Operator should TOGGLE REMOTE FUNCTION rfE11135, "E11-FOlO Breaker Rackout," to ON.
Open the following valves:
At panel 2H 11-P60 1, the SAT/UNSAT 2E11-F0l5A following valves are OPEN, red light illuminated:
2EI1-F073A RHR INBD IN} VLV, 2E11-F075A 2E11-F0l5A RHRSW CROSSTIE VLV, 2E11-F073A RHRSW VLV, 2E11-F075A Prelube RHRSW Pumps At panel 2H11-P60 1, the RHR SAT/UNSAT 2E II-COOl A and C.
SERVICE WATER LUBE VALVES push-button has been DEPRESSED for RHRSW Loop A pumps.
Place RHR Service Water Pump At paneI2H11-P601, the Division SAT/UNSAT Control switch in MANUAL I SERVICE WATER PUMP OVERRD position.
CONTROL switch 2E11-S19A is in MANUAL OVERRD.
Start RHRS W Pumps At paneI2H11-P601, SERVICE SAT/UNSAT 2E11-C001A and C.
WATER PUMP 2E11-C001A and C are RUNNING, red light illuminated.
Open Service Water Crosstie Valves The Operator has identified that SAT/UNSAT 2E11-Fl19A and B, if required.
SERV WTR CROSSTIE VLV 2E11-F119A(B) does not need to be opened.
NOTE: RHRSW System has no inoperable components and is capable of injecting to the vessel without the crosstie valve being opened. Only the A loop of RHRSW is needed.
Throttle RHR Outbd Injection Valve, At paneI2H11-P601, RHR SAT/UNSAT 2E 11-FO 17 A, to control injection OUTBD IN} VLV, 2E11-F017A is THROTTLED CLOSED, to maintain injection flow at 8800 gpm flow increasing on RHR FLOW, 2E11-R603A.
(** Indicates critical step)
PROMPT:
PROMPT:
LR-JP-34.12-11 Page 7 of7
.$AIl'/tn~SA.':l'.'..
(QONWEN'fS****
IF the Operator addresses RWL band, as the Shift Supervisor, INFORM the Operator that another Operator has been directed to control flowlRWL.
IF the Operator addresses system restoration, as the Shift Supervisor, INFORM the Operator that it is not desired at this time.
END TIME: ___ _
NOTE: The terminating cue shall be given to the Operator when:
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
(
PROMPT:
PROMPT:
PERFORMANCE STEP STANDARD LR-JP-34.12-11 Page 7 of7 SATIUNSAT (COMMENTS IF the Operator addresses RWL band, as the Shift Supervisor, INFORM the Operator that another Operator has been directed to control flowlRWL.
IF the Operator addresses system restoration, as the Shift Supervisor, INFORM the Operator that it is not desired at this time.
END TIME: ___ _
NOTE:
The terminating cue shall be given to the Operator when:
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 has had a LOCA.
- 2. RWL is below the Top of Active Fuel and decreasing.
- 4. SUT "2D" is de-energized.
- 5. RHR pumps" A, B, C, & D" have tripped.
- 6. Core Spray pumps "A" and B" have tripped.
- 7. The EOP jumpers to override the 5 minute timer have been installed for 2EII-F017A & B.
INITIATING CUES:
lAW 31EO-EOP-IlO-2, "Alternate RPV Water Level Control" maximize injection ofRHRSW into the reactor using the "A" loop.
(
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 has had a LOCA.
- 2. RWL is below the Top of Active Fuel and decreasing.
- 4. SUT "2D" is de-energized.
- 5. RHR pumps" A, B, C, & D" have tripped.
- 6. Core Spray pumps "A" and B" have tripped.
- 7. The EOP jumpers to override the 5 minute timer have been installed for 2Ell-FOl7A & B.
INITIATING CUES:
IA W 3lEO-EOP-llO-2, "Alternate RPV Water Level Control" maximize injection ofRHRSW into the reactor using the "A" loop.
DRAFT Southern E. I. Hatch uclear uclear Plant Operations Training JPM Simulator 3 R. A. BELCHER LR-IP-20198-06 R£(+/-6*N}j:eI>BM"****
- i\\.PPROVEU*.* *. BY N/R Energy to Serve Your World SM
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DRAFT Southern Nuclear E. I. Hatch Nuclear Plant TITLE Operations Training JPM Simulator 3 EMERGENCY DEPRESS THE REACTOR USING THE HEAD VENTSIDRYWELL COOLERS AUTHOR MEDIA NUMBER R. A. BELCHER LR-IP-20198-06 RECOMMENDED BY APPROVED BY N/R 20 Minutes DATE Energy to Serve Your World sM
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number:
LR-JP-20198 00 01 02 03 04 05 06 08/05/96 Initial development RAB 03/05/99 Revised due to new simulator computer.
SCB 03/13/00 Format modification, change time allowance based on RAB running, modify title 11106/00 Include objective number 03/19/02 Include initial operator statement 06121105 Revised Initial License statement for successful completion 05/08/06 Remove Response Cues RAB RAB RAB RAB su:pv.'s*.* *. *****
Initials***
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I SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number:
LR-JP-20198 Rev. No.
Date Reason for Revision Author's Supv's Initials Initials 00 08/05/96 Initial development RAB DHG 01 03/05/99 Revised due to new simulator computer.
SCB DHG 02 03/13/00 Format modification, change time allowance based on RAB DHG running, modify title 03 11/06/00 Include objective number RAB DHG 04 03/19/02 Include initial operator statement RAB RAB 05 06/21105 Revised Initial License statement for successful RAB RAB completion 06 05/08/06 Remove Response Cues RAB RAB
LR-JP-20198-06 Page 1 of7 UNIT 1 ()
UNIT 2 (X)
EMERGENCY DEPRESS THE REACTOR USING THE HEAD VENTSIDRYWELL COOLERS
.. LR-JP-20198-06 The task shall be complete when the operator has initiated the emergency depress process with the Head VentslDrywell Coolers, per 31EO-EOP-108-2.
201.098
'C;)ll.J:¢G17W'iN:wMBEJl.: 201.098.A PLANT HATCH JTA IMPORTANCE RATING:
RO 4.57 SRO 3.66 KIA CATALOG NUMBER: 295025A1.01 KIA CATALOG JTA IMPORTANCE RATING:
RO 2.9 SRO 3.0 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
APPROXIMATE COMPLETION TIME:
20 Minutes SIMULATOR SETUP:
REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE
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LR-JP-20l98-06 Page 1 of7 UNIT 1 ()
UNIT 2 (X)
TASK TITLE:
JPMNUMBER:
TASK STANDARD:
TASK NUMBER:
EMERGENCY DEPRESS THE REACTOR USING THE HEAD VENTSIDRYWELL COOLERS LR-JP-20l98-06 The task shall be complete when the operator has initiated the emergency depress process with the Head VentslDrywell Coolers, per 3lEO-EOP-108-2.
201.098 OBJECTIVE NUMBER: 201.098.A PLANT HATCH JTA IMPORTANCE RATING:
RO 4.57 SRO 3.66 KIA CATALOG NUMBER: 295025A1.0l KIA CATALOG JTA IMPORTANCE RATING:
RO 2.9 SRO 3.0 OPERA TOR APPLICABILITY:
Nuclear Plant Operator (NPO)
I GENERAL
REFERENCES:
Unit 2 3lEO-EOP-108-2 34S0-T47-00l-2 34S0-T 48-002-2 I REQUIRED MATERIALS:
Unit 2 3lEO-EOP-l08-2 34S0-T47-00l-2 34S0-T48-002-2 APPROXIMA TE COMPLETION TIME:
20 Minutes SIMULATOR SETUP:
REFER TO SlMULATOR SETUP SHEET ON THE FOLLOWING PAGE
SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #113 and leave in FREEZE.
- 2.
INSERT the following MALFUNCTIONS:
LR-JP-20198-06 Page 2 of7 1;'5'}
>1
- ......*.*..*....*...... *l/.....c>>.(.../\\... *RATE ******1'1$<
mfB21_129A Main Steam Relief Valve A Fails Stuck 00000 mfB2L129B Main Steam Relief Valve A Fails Stuck 00000 mfB21_129C Main Steam Relief Valve A Fails Stuck 00000 mfB2L129D Main Steam Relief Valve A Fails Stuck 00000 mfB2L129E Main Steam Relief Valve A Fails Stuck 00000 mfB21_129F Main Steam Relief Valve A Fails Stuck 00000 mfB21_129G Main Steam Relief Valve A Fails Stuck 00000 mfB21_129H Main Steam Relief Valve A Fails Stuck 00000 mfB2L129K Main Steam Relief Valve A Fails Stuck 00000 mfB21_129L Main Steam Relief Valve A Fails Stuck 00000 mfB21_129M Main Steam Relief Valve A Fails Stuck 00000 mfB21_123A Steam Line A Break (Before Restrictor) (VAR)
.1 Key 1 mtE41_235B HPCI Fails To Auto Start On Hi Drywell Press
- 3.
INSERT the following SIMULATOR VALUE OVERRIDES (SVO):
FINAL:RAMp ACT.
VAlJtJE.
- RATE**.*. TIME svoT48140 Water Level in Torus 115 100 00000
- 4.
INSERT the following REMOTE FUNCTIONS:
rtP64194 Drywell Chillers B006A & B LOCAILOSP Trip Links BYPASS SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #113 and leave in FREEZE.
- 2.
INSERT the following MALFUNCTIONS:
MALF#
TITLE FINAL VALUE mfB21_129A Main Stearn Relief Valve A Fails Stuck rnfB2L129B Main Stearn Relief Valve A Fails Stuck mfB21_129C Main Stearn Relief Valve A Fails Stuck mfB21_129D Main Stearn Relief Valve A Fails Stuck mfB2L129E Main Stearn Relief Valve A Fails Stuck rnfB21_129F Main Stearn Relief Valve A Fails Stuck mfB21_129G Main Stearn Relief Valve A Fails Stuck
(
mfB21_129H Main Stearn Relief Valve A Fails Stuck mfB2L129K Main Stearn Relief Valve A Fails Stuck mfB21_129L Main Stearn Relief Valve A Fails Stuck rnfB21_129M Main Stearn Relief Valve A Fails Stuck rnfB21_123A Stearn Line A Break (Before Restrictor) (VAR)
.1 mfE41_235B HPCI Fails To Auto Start On Hi Drywell Press
- 3.
INSERT the following SIMULATOR VALUE OVERRIDES (SVO):
SVO#
DESCRIPTION FINAL VALUE svoT48140 Water Level in Torus 115
- 4.
INSERT the following REMOTE FUNCTIONS:
REM #
DESCRIPTION rfP64194 Drywell Chillers B006A & B LOCAJLOSP Trip Links
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RAMP RATE RAMP RATE 100 LR-IP-20198-06 Page 20f7 ACT.
TIME 00000 00000 00000 00000 00000 00000 00000 00000 00000 00000 00000 Key I ACT.
TIME 00000 STATUS BYPASS
LR-JP-20198-06 Page 3 of7
- 5.
Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A.
On 2H11-P700 place the key switch for the Drywell Chillers to Override B.
ACTIVATE the steam break (Key 1) and then DELETE after drywell pressure LOCA signal is reached.
C.
Perform RC-1, RC-2, and TC-1 and RWL to the normal band.
D.
Close the MSNs.
E.
Acknowledge annunciators.
- 6.
PLACE the Simulator in FREEZE until the INITIATING CUE is given.
- 7.
ESTIMATED Simulator SETUP TIME:
20 Minutes
(
LR-JP-20198-06 Page 3 of7
- 5.
Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A.
On 2HII-P700 place the key switch for the Drywell Chillers to Override B.
ACTIVATE the steam break (Key 1) and then DELETE after drywell pressure LOCA signal is reached.
C.
Perform RC-l, RC-2, and TC-l and RWL to the normal band.
D.
Close the MSIVs.
E.
Acknowledge annunciators.
- 6.
PLACE the Simulator in FREEZE until the INITIATING CUE is given.
- 7.
ESTIMATED Simulator SETUP TIME:
20 Minutes
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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
A seismic event has caused a small steam leak in the drywell and an unisolable leak in the Torus.
- 2.
Attempts to raise Torus water level have been unsuccessfuL
- 3.
3 1 EO-EOP-O 1 2-2 (PC-l) is in progress.
- 4.
The Reactor has been shutdown
- 5.
The Shift Supervisor has determined that the plant cannot be maintained in the SAFE Region of the Heat Capacity Temperature Limit and decided to Emergency Depress the Reactor.
- 6.
31EO-EOP-OlS-2 (CP-l) is in progress.
- 7.
An attempt was made to Emergency Depress with the SRVs, but they have failed to open.
- 8.
Other methods of Alternate Emergency Depress have been unsuccessfuL
- 9.
Drywell Chillers have been placed in service per 34S0-P64-001-2 with the LOCA trips overridden.
- 10.
Standby Gas Treatment System is running with suction from the Reactor Building per 34S0-T46-001-2.
INITIATING CUES:
Depressurize the Reactor using the Head VentslDrywell Coolers per 3IEO-EOP-108-2.
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f (
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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
- 2.
- 3.
- 4.
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
A seismic event has caused a small steam leak in the drywell and an unisolable leak in the Torus.
Attempts to raise Torus water level have been unsuccessful.
3 1 EO-EOP-Ol 2-2 (PC-I) is in progress.
The Reactor has been shutdown The Shift Supervisor has determined that the plant cannot be maintained in the SAFE Region of the Heat Capacity Temperature Limit and decided to Emergency Depress the Reactor.
3 1 EO-EOP-Ol 5-2 (CP-I) is in progress.
An attempt was made to Emergency Depress with the SRVs, but they have failed to open.
Other methods of Alternate Emergency Depress have been unsuccessful.
Drywell Chillers have been placed in service per 34S0-P64-00l-2 with the LOCA trips overridden.
Standby Gas Treatment System is running with suction from the Reactor Building per 34S0-T46-001-2.
INITIATING CUES:
Depressurize the Reactor using the Head Vents/Drywell Coolers per 3 1 EO-EOP-108-2.
For INITIAL Operator Programs:
LR-JP-20198-06 Page 5 of7 For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
- 1. Obtain the procedure needed to perform the task.
Operator obtains 31EO-EOP-lOS-
- 2.
At 2HII-P657, the operator places the LOCA Override Sys A Fans keylock switch to BYPASS.
At 2HII-P654, the operator places the LOCA Override Sys B Fans keylock switch to BYPASS.
START TIME: ___ _
SAT I UNSAT SAT/UNSAT SAT/UNSAT NOTE: The two LOCA override switches allows the cooling system to auto restart. If the operator attempts to manipulate the system per the startup section of 34S0-T47-001-2 then the critical step is UNSAT unless the operator has running:
- BOTH 2T47-B007A and 2T47-B007B
- BOTH 2T47-COOIA and 2T47-COOIB
- BOTH 2T47-C002A and 2T47-C002B
- EITHER 2T47-B008A or 2T47-BOO8B
- EITHER 2T47-B009A or 2T47-BOO9B
- EITHER 2T47-BOlOA or 2T47-BOlOB
- 4. Obtain the procedure needed to Operator obtains 34S0-T4S-002-SAT I UNSAT perform the task.
2 or placard to vent the drywell.
NOTE: Only one loop is critical and needs to be vented. Steps 5-7 are for the "A" side and steps 8-10 are for the "B" side.
(** Indicates critical step)
At 2HII-P657, the operator places the control switch for 2T4S-F334A, Drywell Vent Isol Vlv to OPEN.
SAT/UNSAT/NA
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,TEP PERFORMANCE STEP For INITIAL Operator Programs:
STANDARD LR-JP-20198-06 Page 5 of7 SATIUNSAT (COMMENTS For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
- 1.
- 2.
- 3.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
Obtain the procedure needed to Operator obtains 31EO-EOP-108-perform the task.
- 2.
Override the LOCA trip signal for At 2H11-P657, the operator System "A".
places the LOCA Override Sys A Fans keylock switch to BYPASS.
Override the LOCA trip signal for At 2H11-P654, the operator System "B".
places the LOCA Override Sys B Fans keylock switch to BYPASS.
START TIME: ___ _
SAT/UNSAT SAT/UNSAT SAT I UNSAT NOTE: The two LOCA override switches allows the cooling system to auto restart. If the operator attempts to manipulate the system per the startup section of 34S0-T47-001-2 then the critical step is UNSA T unless the operator has running:
- BOTH 2T47-B007A and 2T47-B007B
- BOTH 2T47-C001A and 2T47-C001B
- BOTH 2T47-C002A and 2T47-C002B
- EITHER 2T47-B008A or 2T47-B008B
- EITHER 2T47-B009A or 2T47-BOO9B
- EITHER 2T47-BOlOA or 2T47-BOlOB
- 4. Obtain the procedure needed to Operator obtains 34S0-T48-002-SAT/UNSAT perform the task.
2 or placard to vent the drywell.
NOTE: Only one loop is critical and needs to be vented. Steps 5-7 are for the "A" side and steps 8-10 are for the "B" side.
- 5~ OPEN 2T48-F334A, Drywell Vent At 2H11-P657, the operator SAT/UNSAT/NA Isol Vlv.
places the control switch for 2T48-F334A, Drywell Vent Isol Vlv to OPEN.
(** Indicates critical step)
- 11. At 2HI1-P602, Place the following pump control switches to PULL TO LOCK:
III DI\\V Equipment Drain pump 2GII-C006A
- DfW Equipment Drain Pump 2GII-C006B
- D/W Floor Drain Pump 2GII-COOIA
., D/W Floor Drain Pump 2G11-COOIB
(** Indicates critical step)
At 2HI1-P657, the operator places control switch for 2T48-F335A, DryweU Isol Vlv to OPEN.
At 2HI1-P657, the operator increases the controller output on 2T48-R615A, Drywell Flow Controller for with demand greater than zero.
LR-JP-20198-06 Page 60f7
/UNSAT/NA IUNSAT/NA At 2HII-P654, the operator SAT I UNSAT I places the control switch for 2T48-F334B, DryweU Vent Isol Vlv to OPEN.
At 2HII-P654, the operator SAT I UNSAT INA places the control switch for 2T48-F335B, Drywell Vent Isol Vlv to OPEN.
2HII-P654, the operator SAT I UNSAT I NA increases the controller output on 2T48-R615B, Drywell Flow Controller for F336B with demand greater zero.
At 2Hll-P602, DRYWELL SUMP CONTROLS, the operator places the following pump control switches are in PULL TO LOCK:
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N/R Energy to Serve Your World SM
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DRAFT Southern Nuclear E. I. Hatch Nuclear Plant TITLE Operations Training JPM Simulator 4 ROLL THE MAIN TURBINE FROM 800 TO 1800 RPM AUTHOR MEDIA NUMBER R. A. BELCHER LR-JP-17.15-0SA RECOMMENDED BY APPROVED BY N/R TIME 20.0 Minutes DATE Energy to Serve Your World SM
I SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number:
LR-JP-17.15 i*************************
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- .* *** I.)ilt~*.*.*.* <..****** ii/)?.........i *ReasQnfo:rll~Visi9Jl i
Initials** *.*******.. Iuitials***
00 07/05/96 Initial development RAB SMC 01 03/05/99 Revised due to new simulator computer.
SCB DHG 02 02/07/00 Format modification RAB DHG 03 11/02/00 Include objective number, TLB comment, changed RAB DHG required oil temperature for Step 33 04 01/03/02 Procedure changes RLS DHG 05 03/11/02 Include initial operator statement RAB RAB 06 03/08/05 Changed RO to NPO, added statement ensuring the ELJ RAB procedure is the current version, changed procedure designations from -2S to -2, changed setup from IC 106 to IC 108.
07 06/13/05 Revised Initial License statement for successful RAB RAB completion 08 04/18/06 Remove Response Cues RAB RAB
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I SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number:
LR-JP-17.15 Rev. No.
Date Reason for Revision Author's Supv's Initials Initials 00 07/05/96 Initial development RAB SMC 01 03/05/99 Revised due to new simulator computer.
SCB DHG 02 02/07/00 Format modification RAB DHG 03 11/02/00 Include objective number, TLB comment, changed RAB DHG required oil temperature for Step 33 04 01/03/02 Procedure changes RLS DHG 05 03/11102 Include initial operator statement RAB RAB 06 03/08/05 Changed RO to NPO, added statement ensuring the ELJ RAB procedure is the current version, changed procedure designations from -2S to -2, changed setup from IC 106 to IC 108.
07 06/13/05 Revised Initial License statement for successful RAB RAB completion 08 04/18/06 Remove Response Cues RAB RAB
LR-JP-17.15-08 Page 1 of7 UNIT 1
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UNIT 2 (X)
- .J'P~Ntil\\f~EJi:g.\\
T£Sk.sTA:Njj~I{D:**
ROLL THE MAIN TURBINE FROM 800 TO 1800 RPM LR-JP-17.15-08 The task shall be completed when the Main Turbine has been rolled from 800 to 1800 rpm per 34S0-N30-001-2.
017.015 PLANT HATCH JTA IMPORTANCE RATING:
NPO 2.25 SRO 2.83 KIA CATALOG NUMBER: 245000A4.06 KIA CATALOG JTA IMPORTANCE RATING:
NPO 2.7 SRO 2.6 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
APPROXIMATE COMPLETION TIME:
20.0 Minutes SIMULATOR SETUP:
REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE LR-IP-17.15-0S Page 1 of7 UNIT 1
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UNIT 2 eX)
TASK TITLE:
JPMNUMBER:
TASK STANDARD:
TASK NUMBER:
ROLL THE MAIN TURBINE FROM SOO TO IS00 RPM LR-IP-17.15-0S The task shall be completed when the Main Turbine has been rolled from SOO to IS00 rpm per 34S0-N30-00l-2.
017.015 OBJECTIVE NUMBER: 017.0l5.A PLANT HATCH JTA IMPORTANCE RATING:
NPO 2.25 SRO 2.S3 KIA CATALOG NUMBER: 245000A4.06
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KIA CATALOG JTA IMPORTANCE RATING:
NPO 2.7 SRO 2.6 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
I GENERAL
REFERENCES:
Unit 2 34GO-OPS-001-2 (current version) 34S0-N30-001-2 (current version)
I REQUIRED MATERIALS:
Unit 2 34S0-N30-00l-2 (current version)
APPROXIMATE COMPLETION TIME:
20.0 Minutes SIMULATOR SETUP:
REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE
SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #108 and place in RUN.
- 2.
INSERT the following OVERRIDES:
diN34-C003 MOTOR SUCT PMP diN34-C005 TURN GEAR OIL PMP
- 3.
INSERT the following MALFUNCTION:
OFF OFF LR-JP-17.15-08 Page 2 of7 1
1
- "_0._
MALF.#
DELAY
- .. KEy mtN34_140 Main Turbine Quill Shaft Oil Pump Fail 2
- 4. START Motor Suction Pump.
NOTE: The Turbine will trip at 1300 RPMs if the Motor Suction Pump is NOT running.
- 5. SELECT a Turbine Speed of 800 RPMs, Acceleration FAST.
- 6. AFTER Turbine is at 800 RPMS select Acceleration MED.
- 7.
SELECT the EX21 00 screen and place "Regulator Control" in "Auto".
- 8. SELECT the "Control" "Speed" screen (the normal Turbine Speed! Acceleration Screen).
- 9.
WITH the Turbine at 800 RPMS, PLACE the Simulator in FREEZE until the INITIATING CUE is given.
- 10.
Markup 34S0-N30-001-2 up to, but not including, step 7.1.5.40.
- 11. ESTIMATED Simulator SETUP TIME:
15 Minutes NOTE: Consider an event trigger to automatically delete the Motor and Turning Gear Oil Pump overrides when the operator places the control switch to RUN. If not, then manually delete the overrides when the pumps are started.
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SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #108 and place in RUN.
- 2.
INSERT the following OVERRIDES:
OR#
DESCRIPTION diN34-C003 MOTOR SUCT PMP diN34-C005 TURN GEAR OIL PMP
- 3.
INSERT the following MALFUNCTION:
MALF#
DESCRIPTION mfN34_l40 Main Turbine Quill Shaft Oil Pump Fail
- 4. START Motor Suction Pump.
LR-JP-17.l5-08 Page 20f7 FINAL KEY OFF 1
OFF 1
DELAY KEY 2
NOTE: The Turbine will trip at 1300 RPMs if the Motor Suction Pump is NOT running.
- 5. SELECT a Turbine Speed of 800 RPMs, Acceleration FAST.
- 6. AFTER Turbine is at 800 RPMS select Acceleration MED.
- 7.
SELECT the EX2l 00 screen and place "Regulator Control" in "Auto".
- 8.
SELECT the "Control" "Speed" screen (the normal Turbine Speed! Acceleration Screen).
- 9.
WITH the Turbine at 800 RPMS, PLACE the Simulator in FREEZE until the INITIATING CUE is given.
- 10.
Markup 34S0-N30-00l-2 up to, but not including, step 7.1.5.40.
- 11. ESTIMATED Simulator SETUP TIME:
15 Minutes NOTE: Consider an event trigger to automatically delete the Motor and Turning Gear Oil Pump overrides when the operator places the control switch to RUN. If not, then manually delete the overrides when the pumps are started.
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
A plant startup is in progress.
- 2.
The Turbine Vibration Trip Bypass switch is in NORMAL
- 3.
The Main Turbine is rolling at 800 rpms to increase lube oil temperatures.
- 4.
Lube Oil temperatures have increased sufficiently.
- 5.
34S0-N30-001-2, "Main Turbine Operations," is complete up to Step 7.1.5.39.2
- 6.
There are no turbine checks required at 1500 rpms.
INITIATING CUES:
Increase the Main Turbine speed to rated conditions per 34S0-N30-001-2, starting at Step 7.1.5.40
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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
A plant startup is in progress.
- 2.
The Turbine Vibration Trip Bypass switch is in NORMAL
- 3.
The Main Turbine is rolling at 800 rpms to increase lube oil temperatures.
- 4.
Lube Oil temperatures have increased sufficiently.
- 5.
34S0-N30-00l-2, "Main Turbine Operations," is complete up to Step 7.1.5.39.2
- 6.
There are no turbine checks required at 1500 rpms.
INITIATING CUES:
Increase the Main Turbine speed to rated conditions per 34S0-N30-00l-2, starting at Step 7.1.5040
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For INITIAL Operator Programs:
LR-JP-17.15-08 Page 4 of7 For O.JT/O.JE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRIDCAL STEPS must be completed for Satisfactory Performance.
NOTE: All manipulations are performed at 2H11-P650 unless otherwise indicated.
- 1. Operator obtains the procedure needed Operator has obtained to perform the task 34S0-N30-001-2 and refers to section 7.1.5.40 and then to 7.1.5.41.
START TIME: ___
SAT/UNSAT PROMPT: IF the operator asks about selection of an acceleration rate, THEN inform him to select MED.
SELECT Speed Cmd RPM SAT/UNSAT
- Rated (1800)**
- 3. Once 900 rpm is reached STOP the Operator, at 900 rpms, stops the SAT I UNSAT Shaft Lift Pumps.
Shaft Lift Pumps by placing the control switch in OFF PULL TO LOCK.
Operator selects **Manual ** for SAT/UNSAT Regulator Control on the EX2100 screen.
- 5. At 1000 rpm, select Acceleration Operator, at 1000 rpms, selects SAT/UNSAT RPM/min Fast (180)
Speed Control, Acceleration RPM/min Fast (180)
- 6. At 1200 rpm, SELECT Speed Control, Operator leaves Speed Control, SAT/UNSAT Acceleration rpm/min desired rate:
Acceleration RPM/min selected Med (90) OR Fast (180).
to Fast (180).
PROMPT: IF Operator inquires as to desired acceleration rate at 1200 rpms, THEN inform the operator that FAST (180) is the correct rate.
(** Indicates critical step)
~TEP PERFO~CESTEP For INITIAL Operator Programs:
STANDARD LR-JP-17.15-08 Page 4 of7 SATIUNSAT (COMMENTS)
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
NOTE: All manipulations are performed at 2H11-P650 unless otherwise indicated.
- 1. Operator obtains the procedure needed Operator has obtained to perform the task 34S0-N30-001-2 and refers to section 7.1.5.40 and then to 7.1.5.41.
START TIME: ___ _
SAT/UNSAT PROMPT: IF the operator asks about selection of an acceleration rate, THEN inform him to select MED.
- 2. SELECT Speed of 1800 RPM.
SELECT Speed Cmd RPM SAT/UNSAT
- Rated (1800)**
- 3. Once 900 rpm is reached STOP the Operator, at 900 rpms, stops the SAT/UNSAT Shaft Lift Pumps.
Shaft Lift Pumps by placing the control switch in OFF PULL TO LOCK.
- 4. SELECT **Manual ** for Regulator Operator selects **Manual** for SAT/UNSAT Control on the EX2100screen.
Regulator Control on the EX21 00 screen.
- 5. At 1000 rpm, select Acceleration Operator, at 1000 rpms, selects SAT/UNSAT RPM/min Fast (180)
Speed Control, Acceleration RPM/min Fast (180)
- 6. At 1200 rpm, SELECT Speed Control, Operator leaves Speed Control, SAT/UNSAT Acceleration rpm/min desired rate:
Acceleration RPM/min selected Med (90) OR Fast (180).
to Fast (180).
PROMPT: IF Operator inquires as to desired acceleration rate at 1200 rpms, THEN inform the operator that FAST (180) is the correct rate.
(** Indicates critical step)
- STEP,
- If
- 7.
- 8.
- 9.
- 10.
- 12.
- 13.
- 14.
OBSERVE Turbine Speed increase and levels at approximately 1800 rpm CONFIRM annunciator 650-150, TURB SUPV TRIP BYPASS TURB VIB TRIP BYPASS, is clear.
CONFIRM Main Shaft Pump Discharge pressure is between 210 and 250 PSIG PERFORM the following:
- Stop 2N34-C003, Motor Suction Pump
- PLACE 2N34-C003 in the AUTO START position PERFORM the following:
- STOP 2N34-C005, Turbine Turning Gear Oil Pump.
- PLACE 2N34-C005 in the AUTO START position.
CONFIRM 2N39-COOl, Turbine Turning Gear Motor control switch, is in the AUTO PULL position.
PLACE the Shaft Lift Pumps control switch in the AUTO START Position.
(** Indicates critical step)
Operator observes Turbine Speed increase and levels at approximately 1800 rpm on the DEHC screen.
Operator confirms annunciator 650-150, TURB SUPV TRIP BYPASS TURB VIB TRIP BYPASS, is clear.
Operator confirms Main Shaft Pump Discharge pressure is between 210 and 250 PSIG on the
- *Monitor* * ~ **lube oil**
screen.
- Operator stops 2N34-C003, Motor Suction Pump by placing its control switch to OFF.
- Operator places control switch for 2N34-C003 in the AUTO START position
- Operator stops 2N34-C005, Turbine Turning Gear Oil Pump by placing its control switch to OFF.
- Operator places control switch for 2N34-C005 in the AUTO START position.
Operator confirms the control switch for 2N39-COO 1, Turbine Turning Gear Motor control switch, is in the AUTO PULL position.
Operator places the Shaft Lift Pumps control switch in the AUTO START Position.
LR-JP-17.15-08 Page 5 of7 SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT
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STEP
- 7.
- 8.
- 9.
- 10.
- 12.
- 13.
- 14.
PERFO~NCESTEP OBSERVE Turbine Speed increase and levels at approximately 1800 rpm CONFIRM annunciator 650-150, TURB SUPV TRIP BYPASS TURB VIB TRIP BYPASS, is clear.
CONFIRM Main Shaft Pump Discharge pressure is between 210 and 250 PSIG PERFORM the following:
- Stop 2N34-C003, Motor Suction Pump
- PLACE 2N34-C003 in the AUTO START position PERFORM the following:
- STOP 2N34-C005, Turbine Turning Gear Oil Pump.
- PLACE 2N34-C005 in the AUTO START position.
CONFIRM 2N39-COOl, Turbine Turning Gear Motor control switch, is in the AUTO PULL position.
PLACE the Shaft Lift Pumps control switch in the AUTO START Position.
(** Indicates critical step)
STANDARD Operator observes Turbine Speed increase and levels at approximately 1800 rpm on the DEHC screen.
Operator confirms annunciator 650-150, TURB SUPV TRIP BYPASS TURB VIB TRIP BYPASS, is clear.
Operator confirms Main Shaft Pump Discharge pressure is between 210 and 250 PSIG on the
- *Monitor* * ----+ **lube oil **
screen.
- Operator stops 2N34-C003, Motor Suction Pump by placing its control switch to OFF.
- Operator places control switch for 2N34-C003 in the AUTO START position
- Operator stops 2N34-C005, Turbine Turning Gear Oil Pump by placing its control switch to OFF.
- Operator places control switch for 2N34-C005 in the AUTO START position.
Operator confirms the control switch for 2N39-C001, Turbine Turning Gear Motor control switch, is in the AUTO PULL position.
Operator places the Shaft Lift Pumps control switch in the AUTO START Position.
LR-JP-17.15-08 Page 5 of7 SATIUNSAT (COMMENTS SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT
- 15. CONFlRM 2P41-R61O, Main Turbine Lube Oil Temp, is between 110°F and 120°F Operator confirms on 2P41-R61O, that Main Turbine Lube Oil Temp, is between 110°F and 120°F LR-JP-17.15-08 Page 6 of7 SAT/UNSAT Simulator Instructor Note: First:
Insure oil pumps have been manually turned off by the operator, then activate overrides (Key 1 )levent trigger for the lube oil pumps.
Second: Activate Quill Shaft Failure malfunction (Key 2)
- 17. Respond to Quill Shaft Failure Operator refers to annunciator SAT/UNSAT annunciator.
procedure 650-152 for Quill Shaft Failure.
- 18. Confirm Turbine 200 psig oil pressure Operator observes that Turbine SAT/UNSAT is below 60 psig.
200 psig oil pressure is below 60 psig as indicated by 2N34-R601C.
Simulator Instructor Note: For the next two steps, if an event trigger is not available, then IMMEDIA TEL Y delete the associated oil pump override when the control switch is taken to RUN.
Operator starts the TGOP by placing it's control switch to RUN.
SAT/UNSAT NOTE: TGOP required for lift pump operation. IA W 34S0-N30-001-2 precaution 5.2.8, "No more than two shaft lift pumps may be OFF WHEN turbine speed is < 900 RPMs.
- 20. Confirm running or start MSP.
Operator starts the MSP by SAT/UNSAT placing it's control switch to RUN
- 21. If Turbine Trips, enter 34S0-N30-Operator refers to 34S0-N30-SAT/UNSAT 001-2.
001-2.
PROMPT: WHEN operator refers to 34S0-N30-001-2, THEN inform the operator that another operator will carry out the actions for a Turbine Trip.
(** Indicates critical step)
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STEP
- 15.
PERFORMANCE STEP CONFIRM 2P41-R61O, Main Turbine Lube Oil Temp, is between 110°F and 120°F STANDARD Operator confirms on 2P41-R61O, that Main Turbine Lube Oil Temp, is between 110°F and 120°F LR-JP-17.15-08 Page 60f7 SATIUNSAT (COMMENTS SAT/UNSAT Simulator Instructor Note: First:
Insure oil pumps have been manually turned off by the operator, then activate overrides (Key 1)/event trigger for the lube oil pumps.
Second: Activate Quill Shaft Failure malfunction (Key 2)
- 17. Respond to Quill Shaft Failure Operator refers to annunciator SAT/UNSAT annunciator.
procedure 650-152 for Quill Shaft Failure.
- 18. Confirm Turbine 200 psig oil pressure Operator observes that Turbine SAT/UNSAT is below 60 psig.
200 psig oil pressure is below 60 psig as indicated by 2N34-R601C.
Simulator Instructor Note: For the next two steps, if an event trigger is not available, then
- 19.
IMMEDIA TEL Y delete the associated oil pump override when the control switch is taken to RUN.
Confirm running or start TGOP.
Operator starts the TGOP by SAT/UNSAT placing it's control switch to RUN.
NOTE: TGOP required for lift pump operation. IA W 34S0-N30-001-2 precaution 5.2.8, "No more than two shaft lift pumps may be OFF WHEN turbine speed is < 900 RPMs.
- 20. Confirm running or start MSP.
Operator starts the MSP by SAT/UNSAT placing it's control switch to RUN
- 21. If Turbine Trips, enter 34S0-N30-Operator refers to 34S0-N30-SAT/UNSAT 001-2.
001-2.
PROMPT: WHEN operator refers to 34S0-N30-001-2, THEN inform the operator that another operator will carry out the actions for a Turbine Trip.
(** Indicates critical step)
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
A plant startup is in progress.
- 2.
The Turbine Vibration Trip Bypass switch is in NORMAL
- 3.
The Main Turbine is rolling at 800 rpms to increase lube oil temperatures.
- 4.
Lube Oil temperatures have increased sufficiently.
- 5.
34S0-N30-001-2, "Main Turbine Operations," is complete up to Step 7.1.5.39.2
- 6.
There are no turbine checks required at 1500 rpms.
INITIATING CUES:
Increase the Main Turbine speed to rated conditions per 34S0-N30-001-2, starting at Step 7.1.5.40
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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
A plant startup is in progress.
- 2.
The Turbine Vibration Trip Bypass switch is in NORMAL
- 3.
The Main Turbine is rolling at 800 rpms to increase lube oil temperatures.
- 4.
Lube Oil temperatures have increased sufficiently.
- 5.
34S0-N30-001-2, "Main Turbine Operations," is complete up to Step 7.1.5.39.2
- 6.
There are no turbine checks required at 1500 rpms.
INITIATING CUES:
Increase the Main Turbine speed to rated conditions per 34S0-N30-001-2, starting at Step 7.1.5.40
NIR DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 5 SOUTHERN..
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COMPANY Energy to Serve Your World SM
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TITLE DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 5 LOWER TORUS WATER LEVEL AUTHOR MEDIA NUMBER F.N.FAGAN LR -lP-HL T5-S5 RECOMMENDED BY APPROVED BY N/R TIME Minutes DATE Energy to Serve Your World sM
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING 00 Initial development Page 1 of 1 Media Number:
FNF
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SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Rev. No.
Date Reason for Revision 00 fuitial development Page 1 of 1 Media Number:
Author's Supv's Initials Initials FNF
Page 1 of 6 UNIT 1 0
UNIT 2 (X)
TASkiNJJMfJiR£ Lower Torus Water Level LR-JP-HLTS-SS The task shall be complete when the operator has lowered torus water level to 148".
OB.r~~l'lvEl'l"M'ERi E11-RHR-LP-00701,013.004.A PLANT HATCH JTA IMPORTANCE RATING:
RO SRO KIA CATALOG NUMBER: 223001A2.11 KIA CATALOG JTA IMPORTANCE RATING:
RO 3.6 SRO 3.8 OPERATOR APPLICABILITY:
Reactor Operator (RO)
APPROXIMATE COMPLETION TIME:
20 Minutes SIMULATOR SETUP:
See next page.
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Page 1 of 6 UNIT 1 0
UNIT 2 (X)
TASK TITLE:
JPMNUMBER:
TASK STANDARD:
TASK NUMBER:
Lower Torus Water Level LR-JP-HLT5-S5 The task shall be complete when the operator has lowered torus water level to 148".
OBJECTIVE NUMBER:
E11-RHR-LP-00701,013.004.A PLANT HATCH JTA IMPORTANCE RATING:
RO SRO KIA CATALOG NUMBER: 223001A2.11 KIA CATALOG JTA IMPORTANCE RATING:
RO 3.6 SRO 3.8 OPERATOR APPLICABILITY:
Reactor Operator (RO)
I GENERAL
REFERENCES:
Unitl & 2 34S0-Ell-010-2 I REQUIRED MATERIALS:
Unit 1 & 2 34S0-E11-010-2, Section 7.4.5 APPROXIMA TE COMPLETION TIME:
20 Minutes SIMULATOR SETUP:
See next page.
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SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to an IC 113 and leave in place in FREEZE.
- 2.
INSERT the following REMOTE FUNCTIONS:
rfE2L214 E21-F002A Suction From CST to CS Pump A rfE2L215 E21-FOO2B Suction From CST to CS Pump B
- 3.
INSERT the following OVERRIDES:
loEII-F003AR2 RHR A HT EXCH OUTLET loEII-F047AR2 RHR A HT EXCH INLET
- 4.
Place the simulator in RUN.
FINA-LlU\\MI>
VALtJE****Ml'E.
OPEN OPEN OFF OFF 1
2 LR-IP-2521O-02 Page 2 of6
- 5.
Allow Torus Level to increase to 149.5", insure annunciator "Torus Water Level HighlLow" in alarm, THEN return rfE21_214 and rfE21_215 to NORM.
- 6.
PLACE the Simulator in FREEZE until the INITIATING CUE is given.
- 7.
ESTIMATED Simulator SETUP TIME:
5 Minutes 2
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SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to an IC 113 and leave in place in FREEZE.
- 2.
INSERT the following REMOTE FUNCTIONS:
RF#
TITLE FINAL VALUE rtE2L214 E21-FOO2A Suction From CST to CS Pump A OPEN rtE2L215 E21-F002B Suction From CST to CS Pump B OPEN
- 3.
INSERT the following OVERRIDES:
OR#
TITLE FINAL VALUE 10EII-F003AR2 RHR A HT EXCH OUTLET OFF 10E1I-F047AR2 RHR A HT EXCH INLET OFF
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- 4.
Place the simulator in RUN.
RAMP RATE RAMP RATE LR-IP-25210-02 Page 2 of6 Key KEY 1
2
- 5.
Allow Torus Level to increase to 149.5", insure annunciator "Torus Water Level HighlLow" in alarm, THEN return rtE21_214 and rfE21_215 to NORM.
- 6.
PLACE the Simulator in FREEZE until the INITIATING CUE is given.
- 7.
ESTIMATED Simulator SETUP TIME:
5 Minutes 2
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UNIT 2 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 is at normal full power operations.
- 2. Annunciator 602-235 "Torus Water Level Higb/Low" is in alarm
- 3. Known and documented Torus in-leakage has caused torus level to increase to 149.5"
- 4. Both loops of RHR has been filled and vented IA W 34SV -SUV -017-2, "Core Spray and RHR Keepfill and RHR Cross Header Valve Check".
INITIATING CUES:
The Shift Supervisor directs that Torus Water Level be lowered to 148" IA W 34S0-E11-01O-2, Residual Heat Removal System, Section 7.4.5.
(
UNIT 2 READ AND GIVE A COPY TO THE OPERA TOR INITIAL CONDITIONS:
- 1. Unit 2 is at normal full power operations.
- 2. Annunciator 602-235 "Torus Water Level HighfLow" is in alarm
- 3. Known and documented Torus in-leakage has caused torus level to increase to 149.5"
- 4. Both loops of RHR has been filled and vented IA W 34SV -SUV -017-2, "Core Spray and RHR Keepfill and RHR Cross Header Valve Check".
INITIATING CUES:
The Shift Supervisor directs that Torus Water Level be lowered to 148" lAW 34S0-E11-01O-2, Residual Heat Removal System, Section 7.4.5.
I.
I For INITIAL Operator Programs:
Page 4 of6
§'!]?lJ.Tl'fSA~.
- 'COMMENTS For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
NOTE: Unless otherwise indicated, all manipulations are on 2PII-P601.
- 1. The operator obtains the correct Operator obtains 34S0-EII-010-procedure.
2 and refers to section 7.4.5.2
- 2. CONFIRM Radwaste is capable of Operator calls Radwaste to ask if receiving the amount of water to be it is capable of receiving water.
transferred.
START TIME: ___ _
SAT/UNSAT SAT/UNSAT PROMPT: WHEN operator calls Radwaste, THEN ask the operator how many gallons of water should be expected.
Operator informs Radwaste that SAT I UNSAT approximately 8,550
(+ or
- 2,850) are expected.
PROMPT: WHEN informed of the number of gallons to expect, THEN tell the operator that Radwaste is capable and ready to receive the water.
Operator OPENS 2EII-F049, RHR To Radwaste Vlv by placing its control switch to OPEN at 2HII-P602, red light illuminated.
- 5. CLOSE 2EII-F003B, Hx Outlet Vlv Operator CLOSES 2EII-F003B, Hx Outlet Vlv by placing its control switch to CLOSE, green light illuminated.
SAT/UNSAT SAT I UNSAT NOTEIPROMPT: Stroke time for F047B is approximately 80 seconds. IF desired, notify Simulator Instructor to activate Key 2 and THEN tell candidate, that using time compression, the valve is closed.
- 6. CLOSE 2EII-F047B, Hx Inlet Vlv.
Operator CLOSES 2EI1-F047B, SAT/UNSAT Hx Inlet Vlv by placing its control switch to CLOSE, green light illuminated.
(** Indicates critical step)
(
(
I I
(
I PERFOR~CESTEP STANDARD For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
Page 4 of6 SATIUNSAT COMMENTS NOTE: Unless otherwise indicated, all manipulations are on 2PII-P601.
START TIME: ___ _
- 1. The operator obtains the correct Operator obtains 34S0-EII-010-SAT/UNSAT procedure.
2 and refers to section 7.4.5.2
- 2. CONFIRM Radwaste is capable of Operator calls Radwaste to ask if SAT/UNSAT receiving the amount of water to be it is capable of receiving water.
transferred.
PROMPT: WHEN operator calls Radwaste, THEN ask the operator how many gallons of water should be expected.
- 3. Informs Radwaste of the number of Operator informs Radwaste that SAT/UNSAT gallons expected.
approximately 8,550 gallons (+ or
- 2,850) are expected.
PROMPT: WHEN informed of the number of gallons to expect, THEN tell the operator that Radwaste is capable and ready to receive the water.
RHR To Radwaste Vlv by placing its control switch to OPEN at 2HII-P602, red light illuminated.
- 5. CLOSE 2EII-F003B, Hx Outlet Vlv Operator CLOSES 2EII-F003B, SAT I UNSAT Hx Outlet Vlv by placing its control switch to CLOSE, green light illuminated.
NOTEIPROMPT: Stroke time for F047B is approximately 80 seconds. IF desired, notify Simulator Instructor to activate Key 2 and THEN tell candidate, that using time compression, the valve is closed.
- 6. CLOSE 2EII-F047B, Hx Inlet Vlv.
Operator CLOSES 2EII-F047B, SAT IUNSAT Hx Inlet VI v by placing its control switch to CLOSE, green light illuminated.
(** Indicates critical step)
Page 5 of6 Si\\.l1ruNS~l'..
'.COMMENTS NOTEIPROMPT: Stroke time for F047B is approximately SO seconds. IF desired, notify Simulator Instructor to activate Key 2 and THEN tell candidate, that using time compression, the valve is closed.
- 7. CONFIRM OPEN/OPEN 2Ell-F04SB, Hx Bypass Vlv.
- 8. Monitor Suppression Pool level.
- 10. Dispatch an operator to locally check the RHR pump for seal leakage.
Operator CONFIRMS OPEN/OPEN 2EII-F04SB, Hx Bypass Vlv by observing red light illuminated.
Monitor Suppression Pool level on 2T4S-R607A at 2HII-P602 OR on 2T4S-R607B at 2Hll-P654.
Operator STARTS RHR Pump B OR D by placing its control switch to START, red light illuminated.
Operator dispatches an operator to locally check the RHR pump for sealleaka e.
SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT Simulator Instructor PROMPT:
After approximately 5 minutes, report back to the operator that there is no seal leakage.
- 11. CONFIRM RHR discharge water temperature is < 200°F.
(** Indicates critical step)
Operator CONFIRMS RHR discharge water temperature is <
200°F, as read on 2T47-R627, point 3 at aneI2HII-P650.
Operator slowly THROTTLES OPEN 2EII-F040, RHR To Radwaste Vlv by placing its control switch to OPEN, red light illuminated.
WHEN the Suppression Pool level is lowered to 14S" (+ or -
.5"), Operator CLOSES 2E 11-F040, RHR To Radwaste Vlv by placing its control switch to CLOSE, green light illuminated.
WHEN the Suppression Pool level is lowered to 14S" (+ or -
.5"), Operator STOPS the Loop B operating RHR Pump by placing its control switch to STOP, green light illuminated.
SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT PERFO~CESTEP STANDARD Page 5 of6 SATIUNSAT COMMENTS NOTEIPROMPT: Stroke time for F047B is approximately 80 seconds. IF desired, notify Simulator Instructor to activate Key 2 and THEN tell candidate, that using time compression, the valve is closed.
- 7. CONFIRM OPEN/OPEN 2EII-Operator CONFIRMS SAT/UNSAT F048B, Hx Bypass Vlv.
OPEN/OPEN 2EII-F048B, Hx Bypass Vlv by observing red light illuminated.
- 8. Monitor Suppression Pool level.
Monitor Suppression Pool level SAT/UNSAT on 2T48-R607A at 2HII-P602 OR on 2T48-R607B at 2Hll-P654.
- 10. Dispatch an operator to locally check Operator dispatches an operator SAT/UNSAT the RHR pump for seal leakage.
to locally check the RHR pump for seal leakage.
Simulator Instructor PROMPT:
After approximately 5 minutes, report back to the operator that there
(
is no seal leakage.
\\
discharge water temperature is <
200°F, as read on 2T47-R627, point 3 at paneI2HII-P650.
- 12. Slowly THROTTLE OPEN 2EII-Operator slowly THROTTLES SAT/UNSAT F040, RHR To Radwaste Vlv.
OPEN 2Ell-F040, RHR To Radwaste Vlv by placing its control switch to OPEN, red light illuminated.
.5"), Operator CLOSES 2Ell-Radwaste Vlv.
F040, RHR To Radwaste Vlv by placing its control switch to CLOSE, green light illuminated.
- 14. STOP the Loop B operating RHR WHEN the Suppression Pool SAT/UNSAT Pump.
level is lowered to 148" (+ or -
.5"), Operator STOPS the Loop B operating RHR Pump by placing its control switch to STOP, green light illuminated.
(
(** Indicates critical step)
WHEN the Suppression Pool level is lowered to 148" (+ or-
.5"), Operator CLOSES 2E 11-F049, RHR To Radwaste Vlv at 2HII-P602 by placing its control switch to CLOSE, green light illuminated.
Page 6 of6
$~l'4JN$l\\i'lJ COMMENTS'*****
SAT I UNSAT NOTE: Only one of three items (closing F049, F040 or stopping the pump) is critical.
- 16. OPEN 2EII-F003B, Hx Outlet Vlv.
Operator OPENS 2Ell-FOO3B, SAT I UNSAT Hx Outlet Vlv by placing its control switch to OPEN, red light illuminated.
- 17. OPEN 2EII-F047B, Hx Inlet Vlv.
Operator OPENS 2EII-F047B, SAT/UNSAT Hx Inlet Vlv by placing its control switch to OPEN, red light illuminated.
- 18. PLACE the RHR Loop B in standby Operator indicates that RHR SAT/UNSAT in accordance with the STANDBY Loop B is to be placed in section of this procedure.
STANDBY.
t'ROMPT: WHEN the Operator mdIcates that Loop B IS to be placed m STANDBY, THEN mform the operator that another operator will perform this.
NOTE: The terminating cue shall be given to the Operator when:
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
END TIME: ___ _
(
(
PERFORMANCE STEP
-*15. CLOSE 2EII-F049, RHR To RadwasteVlv.
STANDARD WHEN the Suppression Pool level is lowered to 148" (+ or-
.5"), Operator CLOSES 2Ell-F049, RHR To Radwaste Vlv at 2HII-P602 by placing its control switch to CLOSE, green light illuminated.
Page 6 of6 SATIUNSAT COMMENTS SAT/UNSAT NOTE: Only one of three items (closing F049, F040 or stopping the pump) is critical.
- 16. OPEN 2EII-F003B, Hx Outlet Vlv.
Operator OPENS 2EII-FOO3B, SAT/UNSAT Hx Outlet Vlv by placing its control switch to OPEN, red light illuminated.
- 17. OPEN 2EII-F047B, Hx Inlet Vlv.
Operator OPENS 2EII-F047B, SAT/UNSAT Hx Inlet Vlv by placing its control switch to OPEN, red light illuminated.
- 18. PLACE the RHR Loop B in standby Operator indicates that RHR SAT/UNSAT in accordance with the STANDBY Loop B is to be placed in section of this procedure.
STANDBY.
J!ROMPT: WHEN the Operator indicates that Loop B is to be placed in STANDBY, THEN inform the operator that another operator will perform this.
NOTE:
The terminating cue shall be given to the Operator when:
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
END TIME: ___ _
(** Indicates critical step)
UNIT 2 READ AND GIVE A COpy TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 is at normal full power operations.
- 2. Annunciator 602-235 "Torus Water Level High/Low" is in alarm
- 3. Known and documented Torus in-leakage has caused torus level to increase to 149.5"
- 4. Both loops ofRHR has been filled and vented lAW 34SV-SUV-017-2, "Core Spray and RHR Keepfill and RHR Cross Header Valve Check".
INITIATING CUES:
The Shift Supervisor directs that Torus Water Level be lowered to 148" lAW 34S0-EII-010-2, Residual Heat Removal System, Section 7.4.5.
(
UNIT 2 READ AND GIVE A COPY TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 is at normal full power operations.
- 2. Annunciator 602-235 "Torus Water Level High/Low" is in alarm
- 3. Known and documented Torus in-leakage has caused torus level to increase to 149.5"
- 4. Both loops ofRHR has been filled and vented lAW 34SV-SUV-017-2, "Core Spray and RHR Keepfill and RHR Cross Header Valve Check".
INITIATING CUES:
The Shift Supervisor directs that Torus Water Level be lowered to 148" lAW 34S0-EII-0I0-2, Residual Heat Removal System, Section 7.4.5.
N/R DRAFT Southern uclear E. I. Hatch Nuclear Plant Operations Training JPlVl Simulator 6
(
TITLE DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 6 RE-ENERGIZE BUS WITH DIESEL GENERATOR AUTHOR MEDIA NUMBER A.D. YAWN LR-JP-28.06A-02 RECOMMENDED BY APPROVED BY N/R TIME 10 Minutes DATE
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number:
LR-JP-28.06A te:.i*iir,Jti****I/
...... -'_<L ___ ¥A~~,*.(~<i.. >...............//
..... Author's**S9:11V'S
.~,.;
1
...**....* *,.j/;ii*... i.*...... i--;.... iT""'~C~.10~YU........i
....................*...... >.\\ Initials* lllitlal$
00 06/01/07 Initial development DHG BKW 01 02 6126/07 Modify The Malfunction Numbers 10/23/08 Removed critical step requirement from step to lower voltage to 57 Hz; Clarified action required to complete critical task to match procedure step.
DHG RAE ADY RSG
(
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number:
LR-JP-28.06A Rev.
Date Reason for Revision Author's Supv's No.
Initials Initials 00 06/01/07 Initial development DHG BKW 01 6/26/07 Modify The Malfunction Numbers DHG RAE 02 10123/08 Removed critical step requirement from step to lower ADY RSG voltage to 57 Hz; Clarified action required to complete critical task to match procedure step.
UNIT 1
()
LR-JP-28.06A-02 Page 1 of 5 UNIT 2 (X)
POWER A DEENERGIZED BUS FROM A DIESEL GENERATOR, ALTERNATE PATH LR-JP-28.06A-02 The task shall be completed when the Operator has powered the 4160 VAC Emergency Bus "2E" successfully from the 2A Emergency Diesel per 34AB-R43-001-2.
028.006 AND 028.023 PLANT HATCH JTA IMPORTANCE RATING:
RO 4.14 SRO 3.30 KIA CATALOG NUMBER: 295003A1.02 KIA CATALOG JTA IMPORTANCE RATING:
RO 4.2 SRO 4.3 OPERA TOR APPLICABILITY:
Nuclear Plant Operator (NPO)
(current versions)
(current version)
APPROXIMATE COMPLETION TIME:
7.0 Minutes SIMULATOR SETUP:
REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE UNIT 1
()
LR-JP-28.06A-02 Page 1 of 5 UNIT 2 (X)
TASK TITLE:
POWER A DEENERGIZED BUS FROM A DIESEL GENERATOR, ALTERNATE PATH JPMNUMBER:
TASK STANDARD:
TASK NUMBER:
LR-JP-28.06A-02 The task shall be completed when the Operator has powered the 4160 VAC Emergency Bus "2E" successfully from the 2A Emergency Diesel per 34AB-R43-001-2.
028.006 AND 028.023 OBJECTIVE NUMBER: 028.006.C PLANT HATCH JTA IMPORTANCE RATING:
RO 4.14 SRO 3.30 KIA CATALOG NUMBER: 295003A1.02 KIA CATALOG JTA IMPORTANCE RATING:
RO 4.2 SRO 4.3 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
I :;ENERAL REFERENCES Unit 2 34AR-652-102-2 34S0-R43-001-2 34AB-R43-001-2 (current versions)
I REQUIRED MATERIALS:
Unit 2 34AB-R43-001-2 (current version)
APPROXIMATE COMPLETION TIME:
7.0 Minutes SIMULATOR SETUP:
REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE
SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to 100% Power and leave in FREEZE.
- 2.
INSERT the following MALFUNCTIONS:
4KV Bus 2E Fault DIESEL GEN FAILURE TO Auto START 2A mf65211684 GEN FIELD GROUND (ANNUNCIATOR ON)
- 2.
INSERT the following OVERRIDES:
loR43-S251 Diesel 2A Mode Sel SW LR-JP-28.06A-02 Page 2 of 5
'IN~1i
~MP* **** j\\t;rr~ **
. VA'LUERATE. ******TlME.
99999 0000
- .AqT.
TIl\\tm..
OFF
- 3.
Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A.
Activate malfunction mfR22_182.
B.
Hold the "A" EDG speed switch to slower for approximately 5 seconds.
C.
Remove malfunction mfR22_182.
- 4.
PLACE the Simulator in FREEZE until the INITIATING CUE is given.
- s.
ESTIMATED Simulator SETUP TIME:
10 Minutes
(
SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to 100% Power and leave in FREEZE.
- 2.
INSERT the following MALFUNCTIONS:
MALF#
TITLE mfR22_182 4KV Bus 2E Fault mfR43_62A DIESEL GEN FAILURE TO Auto START 2A rnf65211684 GEN FIELD GROUND (ANNUNCIATOR ON)
- 2.
INSERT the following OVERRIDES:
MALF#
TITLE loR43-S251 Diesel2A Mode Sel SW (note: this is the System Operative Light)
FINAL RAMP VALUE RATE FINAL RAMP VALUE RATE OFF LR-JP-28.06A-02 Page 2 of 5 ACT.
TIME 99999 0000 ACT.
TIME
- 3.
Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A. Activate malfunction mfR22_182.
B.
Hold the "A" EDG speed switch to slower for approximately 5 seconds.
C. Remove malfunction mfR22_182.
- 4.
PLACE the Simulator in FREEZE until the INITIATING CUE is given.
- 5.
ESTIMATED Simulator SETUP TIME:
10 Minutes
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The 4160 VAC 2E Bus is de-energized.
- 2.
The 2A Emergency Diesel Generator has failed to start.
- 3.
Normal AC power is available to all other electrical distribution switchgear.
- 4.
34AR-652-102, LOSS OF OFFSITE POWER, is in progress.
INITIATING CUES:
Start the 2A Emergency Diesel Generator and Energize the 2E 4160 V AC Bus, per 34AB-R43-001-2.
(
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The 4160 VAC 2E Bus is de-energized.
- 2.
The 2A Emergency Diesel Generator has failed to start.
- 3.
Normal AC power is available to all other electrical distribution switchgear.
- 4.
34AR-652-102, LOSS OF OFFSITE POWER, is in progress.
INITIATING CUES:
Start the 2A Emergency Diesel Generator and Energize the 2E 4160 VAC Bus, per 34AB-R43-001-2.
(
For INITIAL Operator Programs:
LR-JP-28.06A-02 Page 4 of 5
- S4TIUNSAT COMMENTS For O,lT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
Note: The JPM uses the steps from 34AB-R43-00l-2, PLACARD, manual Startup and Tying of Emergency diesel generator." The student may select to use the procedure steps from the body of the procedure which is allowable.
NOTE: All actions are performed on paneI2HII-P652.
- 1. Confirms EDG 2A is NOT running.
- 2. Verify the Auto Start System Operative Light is lit.
The operator the student verifies CLEAR Diesel Auto Start Sys Operative light is illuminated and the Red Diesel Start light is extinguished.
The operator determines the Auto Start System Operative Light is NOT lit.
I** <**~.1?epressit~e<:[)i~selSl1utdovvl1Rela)'
The operator depresses the Diesel I...................pushputtqn
....*............*..*.***.............*.**..... *.....*.***. Shutdown Relay pushbutton.
START TIME: ___ _
Simulator Operator Note: When pushbutton is depressed, remove the Emergency Shutdown alarm and the override on the System Operative light.
PROMPT: WHEN the above override is removed, THEN inform operator of time compression, 110 seconds have passed.
(** Indicates critical step)
The operator momentarily places the 2A EDG START/STOP switch to start.
(
STEP PERFORMANCE STEP STANDARD For INITIAL Operator Programs:
LR-JP-28.06A-02 Page 4 of5 SATIUNSAT COMMENTS For O.JT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
Note: The JPM uses the steps from 34AB-R43-001-2, PLACARD, manual Startup and Tying of Emergency diesel generator." The student may select to use the procedure steps from the body of the procedure which is allowable.
START TIME: ___ _
NOTE: All actions are performed on panel 2HII-P652.
- 1. Confirms EDG 2A is NOT running.
The operator the student verifies CLEAR Diesel Auto Start Sys Operative light is illuminated and the Red Diesel Start light is extinguished.
- 2. Verify the Auto Start System The operator determines the Auto Operative Light is lit.
Start System Operative Light is NOT lit.
- 3. Depress the Diesel Shutdown Relay The operator depresses the Diesel pushbutton Shutdown Relay pushbutton.
Simulator Operator Note: When pushbutton is depressed, remove the Emergency Shutdown alarm and the override on the System Operative light.
PROMPT: WHEN the above override is removed, THEN inform operator of time compression, 110 seconds have passed.
- 4. Place the EDG START/STOP switch The operator momentarily places to START.
the 2A EDG START/STOP switch to start.
(** Indicates critical step)
- 5. Verify the EDG has started.
- 6. Verify the "E" 4160 V AC bus is energized.
- 7. Using Diesel Gen 2A(C) Speed Adjust, lower frequency to 57 Hz.
- 9. Verify the "E" bus is energized.
- 10. Refers to 34AB-R43-001-2.
The operator verifies the "CLEAR Diesel Auto Start Sys Operative" light extinguishes and the "Red Diesel Start" light illuminates.
The operator observes voltage on the "E" 4160 VAC bus equals "0" V AC and answers procedure step with "NO".
At paneI2HI1-P652, the Diesel Gen 2A SPEED ADJUST switch has been taken to LOWER until frequency is 57 Hz.
At panel 2HII-P652, the Diesel Gen 2A SPEED ADJUST switch has been taken to RAISE until frequency is 60 Hz. (Critical action is EDG output breaker closing)
The operator observes voltage on the "E" 4160 VAC bus equals "4160" VAC and answers procedure step with "Yes".
Refers back to the body of 34AB-R43-001-2, and ensures all steps have been completed.
NOTE: The terminating cue shall be given to the Operator when:
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
LR-JP-28.06A-02 Page 5 of5 END TIME: ___ _
(
STEP
- 5.
- 6.
- 7.
- 8.
- 9.
- 10.
PERFORMANCE STEP STANDARD Verify the EDG has started.
The operator verifies the "CLEAR Diesel Auto Start Sys Operative" light extinguishes and the "Red Diesel Start" light illuminates.
Verify the "E" 4160 VAC bus is The operator observes voltage on energized.
the "E" 4160 V AC bus equals "0" V AC and answers procedure step with "NO".
Using Diesel Gen 2A(C) Speed At panel 2H11-P652, the Diesel Adjust, lower frequency to 57 Hz.
Gen 2A SPEED ADJUST switch has been taken to LOWER until frequency is 57 Hz.
Using Diesel Gen 2A(C) Speed At paneI2H11-P652, the Diesel Adjust, raise frequency to 60 Hz.
Gen 2A SPEED ADJUST switch has been taken to RAISE until frequency is 60 Hz. (Critical action is EDG output breaker closing)
Verify the "E" bus is energized.
The operator observes voltage on the "E" 4160 V AC bus equals "4160" VAC and answers procedure step with "Yes".
Refers to 34AB-R43-001-2.
Refers back to the body of 34AB-R43-00l-2, and ensures all steps have been completed.
NOTE: The terminating cue shall be given to the Operator when:
With no reasonable progress, the Operator exceeds double the allotted time.
Operator states the task is complete.
(
TERMINATING CUE: We will stop here.
(** Indicates critical step)
LR-JP-28.06A-02 Page 5 of 5 SATIUNSAT COMMENTS END TIME: ___ _
(
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The 4160 V AC 2E Bus is de-energized.
- 2.
The 2A Emergency Diesel Generator has failed to start.
- 3.
Normal AC power is available to all other electrical distribution switchgear.
- 4.
34AR-652-102, LOSS OF OFFSITE POWER, is in progress.
INITIATING CUES:
Start the 2A Emergency Diesel Generator and Energize the 2E 4160 V AC Bus, per 34AB-R43-001-2.
(
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The 4160 V AC 2E Bus is de-energized.
- 2.
The 2A Emergency Diesel Generator has failed to start.
- 3.
Normal AC power is available to all other electrical distribution switchgear.
- 4.
34AR-652-102, LOSS OF OFFSITE POWER, is in progress.
INITIATING CUES:
Start the 2A Emergency Diesel Generator and Energize the 2E 4160 VAC Bus, per 34AB-R43-001-2.
N/R DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 7 SOUTHERN..
\\
COMPANY Energy to Serve Your World SM
(
TITLE DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 7 CONDUCT A ROD WORTH MINIMIZER (RWM) FUNCTIONAL TEST (FAILURE)
AUTHOR MEDIA NUMBER TIME R. A. BELCHER LR-JP-2S032-0S 10.0 Minutes RECOMMENDED BY APPROVED BY DATE N/R Energy to Serve Your WOrld sM
I SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number:
LR*JP*2S032
.ii¥:~~~~~~**********<./ i<.........*......
- .</**/.*1"iK:,..L:i.. 1'~. L*;.;*.~L~3.}<r*..... "'LSi:\\ ~~th'?t'~: ~Up~'s<.
... <//~~te.. iiF
.**...*...... \\<. *.*.*..*..****..../y.!...........................*.. *.i;.\\'i;:'~f\\r~~.i.i;,*.* ** *
<Initial~
. Initials' 00 11115/99 Initial development RAB DHG 01 11/06/00 Include objective number RAB DHG 02 03119102 Include initial operator statement RAB RAB 03 03117/05 Deleted "S" from procedure numbers, changed ARB DHG Revision and Rev. numbers to "Current Version".
Changed to Nuclear Plant Operator. Updated Simulator IC# and added "Prompt" for sequence control mode.
04 06127/05 Revised Initial License statement for successful RAB RAB completion 05 06/30105 Remove Response Cues RAB RAB
(
\\
I SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number:
LR-JP-2S032 Rev. No.
Date Reason for Revision Author's Supv's Initials Initials 00 11115/99 Initial development RAB DHG 01 11/06/00 Include objective number RAB DHG 02 03119102 Include initial operator statement RAB RAB 03 03/17/05 Deleted "S" from procedure numbers, changed ARB DHG Revision and Rev. numbers to "Current Version".
Changed to Nuclear Plant Operator. Updated Simulator IC# and added "Prompt" for sequence control mode.
04 06/27/05 Revised Initial License statement for successful RAB RAB completion 05 06/30105 Remove Response Cues RAB RAB
LR-JP-25032-05 Page 1 of7 UNIT 1 0
UNIT 2 (X)
CONDUCT A ROD WORTH MINIMIZER (RWM)
FUNCTIONAL TEST (FAILURE)
LR-JP-25032-05 The task shall be completed when the operator has successfully conducted the Rod Worth Minimizer Functional Test per 34GO-OPS-00 1.
001.014 PLANT HATCH JTA IMPORTANCE RATING:
RO 3.40 SRO 2.85 KIA CATALOG NUMBER: 201 006A302 KIA CATALOG JTA IMPORTANCE RATING:
RO 3.5 SRO 3.4 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
APPROXIMATE COMPLETION TIME:
10.0 Minutes SIMULATOR SETUP:
REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE
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UNIT 1 0
LR-JP-25032-05 Page 1 of7 UNIT 2 (X)
TASK TITLE:
CONDUCT A ROD WORTH MINIMIZER (RWM)
FUNCTIONAL TEST (FAILURE)
JPMNUMBER:
LR-JP-25032-05 TASK STANDARD:
The task shall be completed when the operator has successfully conducted the Rod Worth Minimizer Functional Test per 34GO-OPS-00 1.
TASK NUMBER:
001.014 OBJECTIVE NUMBER: 001.014.A PLANT HATCH JTA IMPORTANCE RATING:
RO 3.40 SRO 2.85 KIA CATALOG NUMBER: 201 006A302 KIA CATALOG JTA IMPORTANCE RATING:
RO 3.5 SRO 3.4 OPERATOR APPLICABILITY:
Nuclear Plant Operator (NPO)
I GENERAL
REFERENCES:
Unit 1 Unit 2 34GO-OPS-00l-1 34GO-OPS-00 1-2 34GO-OPS-065-0 34GO-OPS-065-0 34AB-C 11-004-1 34AB-C11-004-2 Control Rod Movement Control Rod Movement Sequence Sequence (current versions)
(current versions)
I REQUIRED MATERIALS:
Unit 1 Unit 2 34GO-OPS-001-1 Att 5 34GO-OPS-001-2 Att 5 (current version)
(current version)
Control Rod Movement Control Rod Movement Sequence Sequence
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APPROXIMA TE COMPLETION TIME:
10.0 Minutes SIMULATOR SETUP:
REFER TO SIMULATOR SETUP SHEET ON THE FOLLOWING PAGE
(
\\
\\-'--
_,' __,"c PEuoRMANcE8'tEp***
SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #102 and leave in FREEZE.
- 2.
INSERT the following ORS OVERRIDES:
RWM Mode Switch
- 3. INSERT the following MALFUNCTIONS:
BYPASS LR-JP-25032-05 Page 20f7
- SATIl);NS,A1' (CQJ\\tMEN'l'S.
1
. *****Jj'lNAI1lWVIP VAEvERAT.E mfC12 24 50-31 Control Rod 50-31Drift Out 3
Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A.
Reset all annunciators.
B.
Place Rx Mode Switch to Startup.
B.
Select a control rod from Step 1 and initialize the RWM by pushing the ETC button on the operator display.
C.
Verify that all RWM rod blocks are clear and the Rod Sequence Selector Switch is in A12 (B12).
4 PLACE the Simulator in FREEZE until the crew assumes the shift.
5 ESTIMATED Simulator SETUP TIME:
10 Minutes
(** Indicates critical step)
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LR-JP-25032-05 Page 2 of7 STEP PERFO~CESTEP STANDARD SATIUNSAT (COMMENTS SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #102 and leave in FREEZE.
- 2.
INSERT the following ORS OVERRIDES:
TAG #
DESCRIPTION STATUS Key diC9l_JOOl RWM Mode Switch BYPASS 1
- 3.
INSERT the following MALFUNCTIONS:
MALF#
TITLE FINAL RAMP Key VALUE RATE mfC12 24 50-31 Control Rod 50-31Drift Out 3
Take the Simulator OUT OF FREEZE and PERFORM the following MANIPULATIONS:
A.
Reset all annunciators.
B.
Place Rx Mode Switch to Startup.
B.
Select a control rod from Step 1 and initialize the RWM by pushing the ETC button on the operator display.
C.
Verify that all R WM rod blocks are clear and the Rod Sequence Selector Switch is in A12 (B12).
4 PLACE the Simulator in FREEZE until the crew assumes the shift.
5 ESTIMATED Simulator SETUP TIME:
10 Minutes
(** Indicates critical step)
- 1.
For INITIAL Operator Programs:
LR-JP-25032-05 Page 4 of7 S..t'I'~$:At CQMMEN']JS For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
Operator confirms that power is Operator has VERIFIED power is turned on to the Refueling Bridge.
turned on to the Refueling Bridge.
START TIME: ___ _
SAT/UNSAT PROMPT:
WHEN the operator addresses confirming power on the Refueling Bridge, as the SO, INFORM the operator that the Refueling Bridge has power.
- 2. Confirm RMCS/RWM ROD BLOCK At paneI2HII-P603, the operator SAT/UNSAT OR SYS TROUBLE annunciator is VERIFIES that the annunciator clear.
603-239, RMCS/RWM ROD BLOCK OR SYS TROUBLE, is extinguished.
PROMPT:
WHEN the operator addresses Section 1.3, INFORM the operator that the STA has completed all of Section 1.3.
- 3. Confirm R WM keylock switches are At paneI2HII-P603, the SAT/UNSAT in OPERATE.
Operator's Display keylock switch is in OPERATE.
Operator IDENTIFIES that the keylock switch at panel 2Hll-P616 must also be in OPERATE.
PROMPT:
WHEN the operator addresses the Instrument Console keylock switch on paneI2HII-P616, INFORM the operator it is in the OPERATE position.
(** Indicates critical step)
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STEP
- 1.
PERFO~NCESTEP STANDARD For INITIAL Operator Programs:
LR-JP-25032-05 Page 4 of7 SATIUNSAT COMMENTS For OJTIOJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
Operator confirms that power is Operator has VERIFIED power is turned on to the Refueling Bridge.
turned on to the Refueling Bridge.
START TIME: ___ _
SAT I UNSAT PROMPT:
WHEN the operator addresses confirming power on the Refueling Bridge, as the SO, INFORM the operator that the Refueling Bridge has power.
- 2. Confirm RMCS/RWM ROD BWCK At paneI2H11-P603, the operator SAT/UNSAT OR SYS TROUBLE annunciator is VERIFIES that the annunciator clear.
603-239, RMCS/RWM ROD BLOCK OR SYS TROUBLE, is extinguished.
PROMPT:
WHEN the operator addresses Section 1.3, INFORM the operator that the STA has completed all of Section 1.3.
Operator's Display keylock switch is in OPERATE.
Operator IDENTIFIES that the keylock switch at panel 2Hll-P616 must also be in OPERATE.
PROMPT:
WHEN the operator addresses the Instrument Console keylock switch on paneI2H11-P616, INFORM the operator it is in the OPERATE position.
(** Indicates critical step)
- 4.
- 5.
Confirm Step 01 is displayed on At panel2H11-P603, the operator RWM Operator's Display.
has VERIFIED that 01 is displayed on the R WM Operator's Display.
Confirm the Reactor Mode switch is At panel2H11-P603, the operator in START & HOT STBY.
places or CONFIRMS the Reactor Mode switch is in START & HOT STBY.
LR-JP-25032-05 Page 5 of7
'$~1'tlJ~sf\\*.... *
- .ifeOMMltl'l'fS*****
SAT/UNSAT SAT/UNSAT NOTE: This step should only require the operator to confirm the mode switch position. This is one of the initial conditions given to the operator at the beginning of the task.
matrix pushbuttons, rod 22-51 is selected At the RWM operator's display, the operator has CONFIRMED the following messages are displayed:
-"SE" "WB"
-"BLOCK: WITHDRAW".
IUNSAT NOTE: If the operator selects any rod not in Step 1 of the RWM Sequence, he will still receive the same indications as a Step 2 rod.
At panel2H11-P603, the operator positions Rod Movement Control Switch to OUTNOTCH and VERIFIES no rod motion occurred.
SAT/UNSAT PROMPT: WHEN the operator asks the STA for RWM step that has a Group 3 rod in it, INFORM the operator to select Step 07.
(** Indicates critical step)
STEP
- 4.
S.
- 6.
- 7.
PERFORMANCE STEP Confirm Step 01 is displayed on RWM Operator's Display.
Confirm the Reactor Mode switch is in START & HOT STBY.
STANDARD At paneI2HII-P603, the operator has VERIFIED that 01 is displayed on the RWM Operator's Display.
At paneI2HII-P603, the operator places or CONFIRMS the Reactor Mode switch is in START & HOT STBY.
LR-JP-25032-05 Page 5 of7 SATIUNSAT (COMMENTS)
SAT/UNSAT SAT/UNSAT NOTE: This step should only require the operator to confirm the mode switch position. This is one of the initial conditions given to the operator at the beginning of the task.
Select a rod from Step 2 of the Rod At paneI2H11-P603, using the SAT/UNSAT Worth Minimizer Sequence and verify CONTROL ROD SELECT system response.
matrix pushbuttons, rod 22-51 is selected AND At the RWM operator's display, the operator has CONFIRMED the following messages are displayed:
-"SE" "WB"
-"BLOCK: WITHDRAW".
NOTE: If the operator selects any rod not in Step 1 of the RWM Sequence, he will still receive the same indications as a Step 2 rod.
Attempt to withdraw the selected rod.
At pane12HII-P603, the operator SAT/UNSAT positions Rod Movement Control Switch to OUTNOTCH and VERIFIES no rod motion occurred.
PROMPT: WHEN the operator asks the STA for RWM step that has a Group 3 rod in it, INFORM the operator to select Step 07.
(** Indicates critical step)
(
(
At I-P603, using CONTROL ROD SELECT matrix pushbuttons, rod 02-23 is SELECTED At the RWM operator's dispJay, the operator has CONFIRlviED the following messages are displayed:
-"SE" "WB"
-"BLOCK: \\VITHDRA W".
At pane12HI1-P603, the operator positions Rod Movement Control Switch to OUTNOTCH and VERIFIES no rod motion occurred.
LR-JP-2S032-0S Page 6 of7 SAT/UNSAT SAT/UNSAT NOTE: BEFORE the operator selects this next control rod, ACTIVATE KEY 1 (to bypass RWM and cause a rod drift).
PROMPT: WHEN the operator asks the STA for RWM step that has a Group 4 rod in it, INFORM the operator to select Step 13.
PROMPT:
At pane12HII-P603, using CONTROL ROD SELECT
. matrix pushbuttons, rod 50-31 is SELECTED AND At the RWM operator's display, the operator has CO~"'FIRMED the following messages are displayed:
-"SE" "WB"
-"BLOCK: WITHDRAW".
At pane12HI1-P603, the operator positions Rod Movement Control Switch to OUTNOTCH and
.. recognizes rod motion HAS occurred.
IF addressed by the operator, INFORM the operator that the STA has confirmed the RWM Scram Buffers are clear and ready to accept data.
(** Indicates critical step)
SAT/UNSAT SAT I UNSAT
(
(
STEP
- 8.
- 9.
- 10.
- 11.
PERFORMANCE STEP Select a rod from Group 3 of the Rod Worth Minimizer Sequence and verify system response.
Attempt to withdraw the selected rod.
STANDARD At panel2H11-P603, using the CONTROL ROD SELECT matrix pushbuttons, rod 02-23 is SELECTED from AND At the RWM operator's display, the operator has CONFIRMED the following messages are displayed:
-"SE" "WB"
-"BLOCK: WITHDRA W".
At panel2H11-P603, the operator positions Rod Movement Control Switch to OUTNOTCH and VERIFIES no rod motion occurred.
LR-JP-25032-05 Page 6 of7 SATIUNSAT (COMMENTS)
SAT I UNSAT SAT/UNSAT NOTE: BEFORE the operator selects this next control rod, ACTIVATE KEY 1 (to bypass RWM and cause a rod drift).
PROMPT: WHEN the operator asks the STA for RWM step that has a Group 4 rod in it, INFORM the operator to select Step 13.
Select a rod from Group 4 of the Rod At panel2H11-P603, using the SAT/UNSAT Worth Minimizer Sequence and verify CONTROL ROD SELECT system response matrix pushbuttons, rod 50-31 is SELECTED AND At the RWM operator's display, the operator has CONFIRMED the following messages are displayed:
-"SE" "WB"
-"BLOCK: WITHDRA W".
Attempt to withdraw the selected rod.
At panel 2H11-P603, the operator SAT/UNSAT positions Rod Movement Control Switch to OUTNOTCH and recognizes rod motion HAS occurred.
PROMPT:
IF addressed by the operator, INFORM the operator that the ST A has confirmed the RWM Scram Buffers are clear and ready to accept data.
(** Indicates critical step)
- 12. fusert the control rod and inform the SS that the RWM test failed.
At paneI2HII-P603, the operator moves the Rod Movement Control Switch to IN to INSERT the control rod.
The operator informs the Shift Supervisor the control rod is drifting out.
LR-JP-25032-05 Page 7 of7
<SAl'lUNSA'l'***.<..
- '(CO;MMEN'l'S..
SAT I UNSAT SAT/UNSAT PROMPT: WHEN informed that the rod is drifting out, THEN direct the operator to enter 34AB-Cll-004-2 "Mispositioned Control Rods" and perform section 4.4
- 14. Obtain 34AB-CII-004-2 "Mispositioned Control Rods.
Operator obtains 34AB-C 11-004-2 "Mispositioned Control Rods" and refers to section 4.4.
Operator inserts a manual reactor scram.
NOTE: The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
SAT/UNSAT SAT I UNSAT END TIME: ___ _
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~TEP
- 12.
- 13.
PERFO~NCESTEP Insert the control rod and inform the SS that the RWM test failed.
Informs the Shift Supervisor the control rod is drifting out.
STANDARD At paneI2HII-P603, the operator moves the Rod Movement Control Switch to IN to INSERT the control rod.
The operator informs the Shift Supervisor the control rod is drifting out.
LR-JP-25032-05 Page 7 of7 SATIUNSAT (COMMENTS SAT/UNSAT SAT/UNSAT PROMPT: WHEN informed that the rod is drifting out, THEN direct the operator to enter 34AB-Cl1-004-2 "Mispositioned Control Rods" and perform section 4.4 I
- 14.
- 15.
Obtain 34AB-CII-004-2 Operator obtains 34AB-CII-004-
"Mispositioned Control Rods.
2 "Mispositioned Control Rods" and refers to section 4.4.
Insert a scram.
Operator inserts a manual reactor scram.
NOTE: The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
SAT I UNSAT SAT/UNSAT END TIME: ___ _
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. A Unit 2 plant startup is commencing and the Reactor Mode Switch is in START & HOT STBY.
- 2. All systems required for plant startup are in service. Permission for Reactor startup has been given.
- 3. 34GO-OPS-OOl-2, "Plant Startup," is in progress.
- 4. The Rod Worth Minimizer Functional Test is the next startup action to be completed
- 5. For the RWM test, Reactor Engineering has directed that the first rod in the selected groupe s) be tested.
INITIATING CUES:
Perform the Rod Worth Minimizer Functional Test using Attachment 5 of 34GO-OPS-OOl-2.
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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. A Unit 2 plant startup is commencing and the Reactor Mode Switch is in START & HOT STBY.
- 2. All systems required for plant startup are in service. Permission for Reactor startup has been given.
- 3. 34GO-OPS-OOI-2, "Plant Startup," is in progress.
- 4. The Rod Worth Minimizer Functional Test is the next startup action to be completed
- 5. For the RWM test, Reactor Engineering has directed that the first rod in the selected group(s) be tested.
INITIATING CUES:
Perform the Rod Worth Minimizer Functional Test using Attachment 5 of 34GO-OPS-OOl-2.
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
PLANT STARTUP ATTACHMENT...1:
TITLE:
WELDED CONTACTS CHECK DOCUMENT NUMBER:
34GO-OPS-00 1-2 CONTINUOUS I
1.0 Check the rod select relays for welded contacts as follows:
1.1 Select rod 18-03.
1.2 Confirm that 18-03 is the selected rod AND PAGE 58 OF 78 VERSION NO:
38.21 ATTACHMENT PAGE:
1 OF 1 only rod 18-03 is selected, by observing that only 18-03 lamps are ILLUMINATED on the Full Core Display Panel AND on the Rod Select Panel.
1.3 Continue to select rods, proceeding from left to right AND from bottom to top on the select matrix UNTIL all rods have been selected once.
1.4 Confirm for all rods selected that only the intended rod for selection is selected.
1.5 Select rod 34-51.
1.6 Confirm that 34-51 is the selected rod AND only rod 34-51 is selected by observing that only 34-51 lamps are ILLUMINATED on the Full Core Display Panel AND on the Rod Select Panel.
1.7 Continue to select rods, proceeding from right to left AND from top to bottom on the select matrix UNTIL all rods have been selected.
1.8 Confirm for all rods selected that only the intended rod for selection is selected.
OPS-1072 Ver. N/A G16.030 MGR-0009 Rev. 5.0
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SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
PLANT STARTUP ATTACHMENT...1:.
TITLE:
WELDED CONTACTS CHECK DOCUMENT NUMBER:
34GO-OPS-00 1-2 CONTINUOUS I
1.0 Check the rod select relays for welded contacts as follows:
1.1 Select rod 18-03.
1.2 Confirm that 18-03 is the selected rod AND PAGE 58 OF 78 VERSION NO:
38.21 ATTACHMENT PAGE:
1 OF 1 only rod 18-03 is selected, by observing that only 18-03 lamps are ILLUMINATED on the Full Core Display Panel AND on the Rod Select Panel.
1.3 Continue to select rods, proceeding from left to right AND from bottom to top on the select matrix UNTIL all rods have been selected once.
1.4 Confirm for all rods selected that only the intended rod for selection is selected.
1.5 Select rod 34-51.
1.6 Confirm that 34-51 is the selected rod AND only rod 34-51 is selected by observing that only 34-51 lamps are ILLUMINATED on the Full Core Display Panel AND on the Rod Select Panel.
1.7 Continue to select rods, proceeding from right to left AND from top to bottom on the select matrix UNTIL all rods have been selected.
1.8 Confirm for all rods selected that only the intended rod for selection is selected.
OPS-1072 Ver. N/A G16.030 MGR-0009 Rev. 5.0
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
TITLE:
PLANT STARTUP ATTACHMENT ~
RWM OPERABILITY CHECK PAGE 60 OF 78 DOCUMENT NUMBER:
VERSION NO:
34GO-OPS-001-2 38.21 ATTACHMENT PAGE:
20F2 1.6 Place OR confirm the Reactor Mode switch in START & HOT STBY position.
1.7 Select a rod from step 2 of the RWM Sequence AND perform the following:
1.7.1 Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.
1.7.2 Attempt to withdraw the selected rod AND confirm no rod motion occurs.
1.8 Have the STAlReactor Engineering determine a RWM step that contains a RWM Sequence Rod Group 3 Control Rod.
Step #: ____ _
1.9 Select a rod from the step number listed above of the RWM Sequence AND perform the following:
1.9.1 Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.
1.9.2 Attempt to withdraw the selected rod AND confirm no rod motion occurs.
1.10 Have the ST AlReactor Engineering determine a RWM step that contains a RWM Sequence Rod Group 4 Control Rod.
Step #: ____ _
1.11 Select a rod from the step number listed above of the RWM sequence AND perform the following:
1.11.1 Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.
1.11.2 Attempt to withdraw the selected rod AND confirm no rod motion occurs.
2.0 Have the STA confirm the RWM scram buffers are clear AND ready to accept data.
OPS-1073 Ver. N/A G16.030 MGR-0009 Rev. 5.0
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SOUTHERN NUCLEAR PLANT E.!. HATCH PAGE 60 OF 78 DOCUMENT TITLE:
DOCUMENT NUMBER:
34GO-OPS-001-2 VERSION NO:
38.21 PLANT STARTUP ATTACHMENT...§.
TITLE:
RWM OPERABILITY CHECK ATTACHMENT PAGE:
20F2 1.6 Place OR confirm the Reactor Mode switch in START & HOT STBY position.
1.7 Select a rod from step 2 of the RWM Sequence AND perform the following:
1.7.1 Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.
1.7.2 Attempt to withdraw the selected rod AND confirm no rod motion occurs.
1.8 Have the STAIReactor Engineering determine a RWM step that contains a RWM Sequence Rod Group 3 Control Rod.
1.9 1.9.1 1.9.2 1.10 Step #: ____ _
Select a rod from the step number listed above of the RWM Sequence AND perform the following:
Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.
Attempt to withdraw the selected rod AND confirm no rod motion occurs.
Have the ST AlReactor Engineering determine a RWM step that contains a RWM Sequence Rod Group 4 Control Rod.
Step #: ____ _
1.11 Select a rod from the step number listed above of the RWM sequence AND perform the following:
1.11.1 Confirm "SE" appears on the RWM Operator's Display AND the message section confirms a withdrawal block exists due to a select error.
1.11.2 Attempt to withdraw the selected rod AND confirm no rod motion occurs.
2.0 Have the STA confirm the RWM scram buffers are clear AND ready to accept data.
OPS-1073 Ver. N/A G16.030 MGR-0009 Rev. 5.0
N/R DRAFT Southern Nuclear E. I. Hatch uclear Plant Operations Training JPM Energy to Serve Your World SM
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TITLE DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM Simulator 8 LOSS OF AIR ACTIONS FOR RX BLDG VENTILATION AUTHOR MEDIA NUMBER TIME F.N.FAGAN LR-IP-NRC-SIM8 20 Minutes RECOMMENDED BY APPROVED BY DATE N/R Energy to Serve Your World sM
I SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING 00 05118/09 Initial development Page 1 of 1 Media Number: LR-JP-NRC-SIM8 FNF
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I SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Rev. No.
Date Reason for Revision 00 05/18/09 Initial development Page 1 of 1 Media Number: LR-JP-NRC-SIM8 Author's Supv's Initials Initials FNF
Page 1 of8 UNIT 1 0
UNIT 2 (X)
Recognize and Respond to an Instrument and Service Air Failure LR-JP-NRC-SIM8 The task shall be complete when the operator has completed 34AB-P51-00l-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air.
H-OPR0200.025 200.025.C from SG50273 PLANT HATCH JTA IMPORTANCE RATING:
RO 3.93 SRO 3.61 KIA CATALOG NUMBER: 295019AK2.08 KIA CATALOG JTA IMPORTANCE RATING:
RO 2.8 SRO 2.9 OPERATOR APPLICABILITY: RO APPROXIMATE COMPLETION TIME:
20 Minutes SIMULATOR SETUP:
See the next sheet.
Page 1 of 8 UNIT 1 0
UNIT 2 (X)
TASK TITLE:
JPMNUMBER:
TASK STANDARD:
TASK NUMBER:
Recognize and Respond to an Instrument and Service Air Failure LR-JP-NRC-SIM8 The task shall be complete when the operator has completed 34AB-P51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air.
H-OPR0200.025 OBJECTIVE NUMBER:
200.025.C from SG50273 PLANT HATCH JTA IMPORTANCE RATING:
RO 3.93 SRO 3.61 KIA CATALOG NUMBER: 295019AK2.08
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KIA CATALOG JTA IMPORTANCE RATING:
(
RO 2.8 SRO 2.9 OPERA TOR APPLICABILITY:
RO I GENERAL
REFERENCES:
Unit 1 & 2 34AB-P51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" I REQUIRED MATERIALS:
Unit 1 & 2 34AB-P51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" completed through step 4.13.
APPROXIMATE COMPLETION TIME:
20 Minutes SIMULATOR SETUP:
See the next sheet.
Page 1 of 8 SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #113 and place in RUN.
- 2. INSERT the following MALFUNCTIONS:
1fI~A\\;J,i...~l\\tfl'A\\~'.I.'~....
VA£DE.ltAl'E... ***1'IME*
mfP5 L222A Service Air Compressor 2A Trip mfP5 L222B Service Air Compressor 2B Trip mfP5 L222C Service Air Compressor 2C Trip mfP52_191 Instrument Air Leakage mfC7L59 Spurious Reactor Scram
- 3. Insert the below overrides and create event triggers as follow:
If SBGT "A" is placed in RUN then delete the override of SBGT "B".
If SBGT "B" is placed in RUN then delete the override of SBGT "A".
diT46-DOOlA-1 SBGTS A FanlFilter OFF diT46-DOOlB-1 SBGTS B Fan/Filter OFF loP52-565G2 Rx Bldg Inst. N2 to Noninter. Ser. Vlv.
OFF loP52-565R1 Rx Bldg Inst. N2 to Noninter. Ser. Vlv.
ON
- 4. Place RCIC in service, injecting into the vessel, with level slowly rising (this is to prevent the auto start of SBGT).
- 5.
Allow the simulator to run until the SBGT air operated valves (FOO 112/3) fail open (-4 minutes)
- 6.
Mark up 34AB-P51-00l-2 up to, but not including, step 4.14.
- 7.
PLACE the Simulator in FREEZE until the INITIATING CUE is given.
- 8.
ESTIMATED Simulator SETUP TIME:
10 Minutes
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(
Page 1 of 8 SIMULATOR SETUP Simulator Initial Conditions:
- 1.
RESET the Simulator to IC #113 and place in RUN.
- 2. INSERT the following MALFUNCTIONS:
MALF#
TITLE FINAL RAMP ACT.
VALUE RATE TIME mfP51_222A Service Air Compressor 2A Trip mfP51_222B Service Air Compressor 2B Trip mfP51_222C Service Air Compressor 2C Trip mfP52_191 Instrument Air Leakage mfC71_59 Spurious Reactor Scram
- 3. Insert the below overrides and create event triggers as follow:
If SBGT "A" is placed in RUN then delete the override of SBGT "B".
If SBGT "B" is placed in RUN then delete the override of SBGT "A".
OVERIDE#
TITLE FINAL VALUE diT46-DOOIA-1 SBGTS A FanIFilter OFF diT46-DOOlB-1 SBGTS B FanlFilter OFF loP52-565G2 Rx Bldg Inst. N2 to Noninter. Ser. Vlv.
OFF loP52-565R1 Rx Bldg Inst. N2 to Noninter. Ser. Vlv.
ON
- 4.
Place RCIC in service, injecting into the vessel, with level slowly rising (this is to prevent the auto start of SBGT).
- 5.
Allow the simulator to run until the SBGT air operated valves (FOO 112/3) fail open (-4 minutes)
- 6.
Mark up 34AB-P51-00l-2 up to, but not including, step 4.14.
- 7.
PLACE the Simulator in FREEZE until the INmATING CUE is given.
- 8.
ESTIMATED Simulator SETUP TIME:
10 Minutes
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 has lost all Service Air Compressors and they can not be restarted.
- 2. Electrical Maintenance and I&C are checking all air system electrical circuits.
- 3. The reactor has been scrammed and 34AB-C71-00l-2, "Scram Procedure" is being carried out.
- 4. 34 AB-P51-00 1-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" has been partially completed.
INITIATING CUES:
Complete procedure 34AB-P51-001-2 starting at step 4.14.
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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 has lost all Service Air Compressors and they can not be restarted.
- 2. Electrical Maintenance and I&C are checking all air system electrical circuits.
- 3. The reactor has been scrammed and 34AB-C71-001-2, "Scram Procedure" is being carried out.
- 4. 34AB-P51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" has been partially completed.
INITIATING CUES:
Complete procedure 34AB-P51-001-2 starting at step 4.14.
Page 3 of?
For INITIAL Operator Programs:
For OJT/O.JE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
PROMPT:
Provide the operator with 34AB-P51-001-2 completed up to section 4.13.
START TIME: ___ _
- 1. The operator starts at the correct step.
Operator refers to 34AB-P51-SAT/UNSAT 001-2 and starts at step 4.14.
- 2. Determine if Control Air header On panel 2H11-P650, Control Air SAT/UNSAT Pressure is below 45 PSIG AND NOT Pressure, 2P52-R600, the increasing.
operator observes pressure is less then 45 psig and not increasing.
NOTES:
- If the operator attempts to first start the "A" SBGT, complete steps 3-9 and skip steps 10-16
- If the operator attempts to first start the "B" SBGT, complete steps 10-16 and skip steps 3-9.
- All "A" controls are located on 2H11-P65?
- All "B" controls are located on 2H22-P654.
- SBGT air operated valves FOO1/2/3 fail in the OPEN position.
- 3. OPEN 2T46-F003A, Fltr Inlet from The operator places the keylock SAT I UNSATI NA Refuel FIr.
switch for 2T46-F003A, FItr Inlet from Refuel FIr, to OPEN.
AND/OR Open 2T46-F001A, FItr Inlet from Rx The operator places the keylock SAT I UNSATI NA Bldg.
switch for 2T46-FOOlA, FItr Inlet from Rx Bldg, to OPEN.
- 4. PLACE SBGT A in RUN position The operator places the control SAT I UNSAT switch for SBGT A to RUN.
NOTE: The operator should note that SBGT "A" does not start and continue with SBGT "B" start.
The operator places the keylock SAT I UNSAT I NA switch for 2T46-F003B, FItr Inlet from Refuel FIr, to OPEN.
The operator places the keylock SAT I UNSAT I NA switch for 2T46-F001B, FItr Inlet from Rx to OPEN.
(** Indicates critical step)
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PERFORMANCE STEP For INITIAL Operator Programs:
STANDARD Page 3 of7 SATIUNSAT (COMMENTS)
For O.JT/O,JE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRmCAL STEPS must be completed for Satisfactory Performance.
PROMPT:
Provide the operator with 34AB-P51-001-2 completed up to section 4.13.
START TIME: ___ _
- 1. The operator starts at the correct step.
Operator refers to 34AB-P5l-SAT/UNSAT 001-2 and starts at step 4.14.
- 2. Determine if Control Air header On paneI2H11-P650, Control Air SAT/UNSAT Pressure is below 45 PSIG AND NOT Pressure, 2P52-R600, the increasing.
operator observes pressure is less then 45 psig and not increasing.
NOTES:
- If the operator attempts to first start the "A" SBGT, complete steps 3-9 and skip steps 10-16
- If the operator attempts to first start the "B" SBGT, complete steps 10-16 and skip steps 3-9.
- All "A" controls are located on 2HIl-P657.
- All "B" controls are located on 2H22-P654.
- SBGT air operated valves F0011213 fail in the OPEN position.
- 3. OPEN 2T46-F003A, Fltr Inlet from The operator places the keylock SAT/UNSAT/NA Refuel FIr.
switch for 2T46-F003A, Fltr Inlet from Refuel FIr, to OPEN.
AND/OR Open 2T46-F001A, FItr Inlet from Rx The operator places the keylock SAT I UNSATI NA Bldg.
switch for 2T46-FOOlA, FItr Inlet from Rx Bldg, to OPEN.
NOTE: The operator should note that SBGT "A" does not start and continue with SBGT "B" start.
- 5. OPEN 2T46-F003B, Fltr Inlet from The operator places the key lock SAT/UNSAT/NA Refuel FIr.
switch for 2T46-F003B, Fltr Inlet from Refuel FIr, to OPEN.
AND/OR Open 2T46-FOOlB,Fltr Inlet from Rx The operator places the keylock SAT/UNSAT/NA Bldg.
switch for 2T46-FOOIB, FItr Inlet from Rx Bldg, to OPEN.
(** Indicates critical step)
- 7. CONFIRM 2T46-F002B OPENS.
- 8. CONFIRM SBGT B HTR Red Light ILLUMINATES
NOTES:
The operator places the control switch for SBGT B in RUN.
The operator observes 2T46-F002B red light ILLUMINATED.
The operator observes SBGT B HTR Red Li ht ILLUMINATED.
The operator observes SBGT flow between 1500-4000 scfm on 2U41-R600.
Page 4 of7 SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT
- If the operator attempts to first start the" A" SBGT, complete steps 3-9 and skip steps 10-16
- If the operator attempts to first start the "B" SBGT, complete steps 10-16 and skip steps 3-9.
- All "A" controls are located on 2HII-P657.
- All "B" controls are located on 2H22-P654.
- SBGT air operated valves FOO1l2/3 fail in the OPEN position.
- 10. OPEN 2T46-F003B, Fltr Inlet from The operator places the keylock SAT/UNSAT/NA Refuel FIr.
switch for 2T46-F003B, Fltr Inlet from Refuel Flr, to OPEN.
AND/OR Open 2T46-FOOIB, Fltr Inlet from Rx The operator places the keylock SAT/UNSAT/NA Bldg.
switch for 2T46-FOOIB, Fltr Inlet from Rx Bldg, to OPEN.
- 11. PLACE SBGT B in RUN position The operator places the control SAT/UNSAT switch for SBGT B in RUN.
NOTE: The operator should note that SBGT "B" does not start and continue with SBGT "A" start.
- 14. CONFIRM 2T46-F002A OPENS.
- 15. CONFIRM SBGT A HTR Red Light ILLUMINATES
(** Indicates critical step)
The operator places the keylock SAT / UNSAT / NA switch for 2T46-F003A, Fltr Inlet from Refuel Flr, to OPEN.
The operator places the keylock SAT / UNSAT / NA switch for 2T46-FOOIA, Fltr Inlet from Rx Bldg, to OPEN.
The operator places the control SAT / UNSAT switch for SBGT A to RUN.
The operator observes 2T46-F002A red light LLUMINATED.
The operator observes SBGT A HTR Red Light ILLUMINATED.
The operator observes SBGT flow between 1500-4000 sefm on 2T41-R618.
SAT/UNSAT SAT/UNSAT SAT/UNSAT
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PERFORMANCE STEP r-*6. PLACE SBGT B in RUN position
- 7. CONFIRM 2T46-F002B OPENS.
- 8. CONFIRM SBGT B HTR Red Light ll.,LUMINA TES
NOTES:
STANDARD The operator places the control switch for SBGT B in RUN.
The operator observes 2T46-F002B red light llLUMINA TED.
The operator observes SBGT B HTR Red Light ll.,LUMINATED.
The operator observes SBGT flow between 1500-4000 sefm on 2U41-R600.
Page 4 of7 SATIUNSAT (COMMENTS SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT
- If the operator attempts to first start the "A" SBGT, complete steps 3-9 and skip steps 10-16
- If the operator attempts to first start the "B" SBGT, complete steps 10-16 and skip steps 3-9.
- All "A" controls are located on 2H11-P657.
- All "B" controls are located on 2H22-P654.
- SBGT air operated valves FOO1l2/3 fail in the OPEN position.
- 10. OPEN 2T46-F003B, Fltr Inlet from The operator places the keylock SAT I UNSATI NA Refuel FIr.
switch for 2T46-F003B, Fltr Inlet from Refuel FIr, to OPEN.
AND/OR Open 2T46-F001B, Fltr Inlet from Rx The operator places the keylock SAT/UNSAT/NA Bldg.
switch for 2T46-F001B, FItr Inlet from Rx Bldg, to OPEN.
- 11. PLACE SBGT B in RUN position The operator places the control SAT/UNSAT switch for SBGT B in RUN.
NOTE: The operator should note that SBGT "B" does not start and continue with SBGT "A" start.
- 12. OPEN 2T46.. F003A, FItr Inlet from The operator places the keylock SAT/UNSAT/NA Refuel FIr; -
switch for 2T46-F003A, Fltr Inlet AND/OR from Refuel FIr, to OPEN.
Open 2T46-F001A,FItr Inletfrom The operator places the keylock SAT/UNSAT/NA Rx Bldg.
switch for 2T46-F001A, FItr Inlet from Rx Bldg, to OPEN.
- 14. CONFIRM 2T46-F002A OPENS.
The operator observes 2T46-SAT/UNSAT F002A red light LLUMINA TED.
- 15. CONFIRM SBGT A HTR Red Light The operator observes SBGT A SAT/UNSAT ll.,LUMINA TES HTR Red Light ilLUMINATED.
flow between 1500-4000 sefm on 2T41-R618.
(** Indicates critical step)
Page 5 of7 NOTE: If a fan is NOT running and does NOT auto start, then the step is NOT critical. The step is to be marked SAT if, after the operator is done, the fan is NOT running (green light illuminated).
(** Indicates critical step)
On pane12HI1-P654 the operator places control switch 2U41-COOlA, Turb Bldg Vent Supply Fan, to the OFF position, green Ii ht illuminated.
On pane12HI1-P654 the operator places control switch for 2U41-COOlB, Turb Bldg Vent Supply Fan, to the OFF position, green Ii O"ht illuminated.
On panel 2HI1-P654 the operator places control switch for 2U41-C002A, Turh Bldg Vent Exhaust Fan, to the OFF position, green light illuminated.
On pane12HI1-P654 the operator places control switch for 2U41-C002B, Turb Bldg Exhaust Fan, to the OFF position, green light illuminated.
On pane12HII-P657 the operator places control switch for 2T41-COOlA, Rx Bldg Vent Supply Fan, to the OFF position, green light iHurninated.
On pane12HII-P657 the operator places control switch for to the OFF position, green light illuminated.
On pane12HI1-P657 the operator places control switch for 2T41-COOlB, Rx Bldg Vent Supply Fan, to the OFF position,' green light illuminated.
On pane12HII-P657 the operator places control switch for 2T41-C007B, Rx Bldg Vent Exhaust Fan, to the OFF position, green light illuminated.
IUNSAT IUNSAT SAT I UNSAT IUNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT
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PERFOR~NCESTEP STANDARD Page 5 of7 SATIUNSAT (COMMENTS)
NOTE: If a fan is NOT running and does NOT auto start, then the step is NOT critical. The step is to be marked SAT if, after the operator is done, the fan is NOT running (green light illuminated).
- 17. TRIP 2U4l-COOlA, Turb Bldg Vent On panel2Hll-P654 the operator SAT/UNSAT Supply Fan places control switch for 2U4l-COOlA, Turb Bldg Vent Supply Fan, to the OFF position, green light illuminated.
- 18. TRIP 2U4l-COOlB, Turb Bldg Vent On panel2Hll-P654 the operator SAT I UNSAT Supply Fan places control switch for 2U4l-COOlB, Turb Bldg Vent Supply Fan, to the OFF position, green light illuminated.
- 19. TRIP 2U41-C002A, Turb Bldg Vent On panel 2Hll-P654 the operator SAT/UNSAT Exhaust Fan places control switch for 2U4l-C002A, Turb Bldg Vent Exhaust Fan, to the OFF position, green light illuminated.
- 20. TRIP 2U41-C002B, Turb Bldg Vent On panel2Hll-P654 the operator SAT I UNSAT Exhaust Fan places control switch for 2U4l-C002B, Turb Bldg Vent Exhaust Fan, to the OFF position, green light illuminated.
- 21. TRIP 2T4l-COOIA, Rx Bldg Vent On panel2Hll-P657 the operator SAT/UNSAT Supply Fan places control switch for 2T4l-COOlA, Rx Bldg Vent Supply Fan, to the OFF position, green light illuminated.
- 22. TRIP 2T4l-COOlB, Rx Bldg Vent On panel2Hll-P657 the operator SAT/UNSAT Supply Fan places control switch for to the OFF position, green light illuminated.
- 23. TRIP 2T 4l-C007 A, Rx Bldg Vent On panel2Hll-P657 the operator SAT/UNSAT Exhaust Fan places control switch for 2T4l-COOlB, Rx Bldg Vent Supply Fan, to the OFF position,' green light illuminated.
- 24. TRIP 2T4l-COO7B, Rx Bldg Vent On panel2Hll-P657 the operator SAT/UNSAT Exhaust Fan places control switch for 2T4l-C007B, Rx Bldg Vent Exhaust Fan, to the OFF position, green light illuminated.
(** Indicates critical step)
- 31. Confirm OPEN/OPEN 2N21-F0l4, Condensate Demineralizer Bypass Valve.
On pane12HI1-P657 the operator places control switch for B0l7 Fan 1, Bldg Recife Fan, to the OFF position, green light illuminated.
On pane12HII-P657 the operator places control switch 2T41-B0l7 Fan Rx Bldg to the OFF position, green light illuminated.
On panel I-P657 the operator places control switch 2T41-COO2A, Refuel FIr Vent Supply Fan, to the OFF position, green light illuminated.
On pane12HII-P657 the operator places control switch for 2T41-C002B, Refuel FIr Vent Supply
. Fan, to the OFF position, green light illuminated.
On pane12HII-P657 operator places control switch for 2T41-C005A, Refuel FIr Vent Exh Fan, to the OFF position, green light illuminated.
On panel 2HI1-P657 the operator places control switch 2T41-C005B, Refuel FIr Vent Exh Fan, to the OFF position, green light illuminated.
The operator an SO to confirm OPEN/OPEN 2N21-FO 14, Condensate Demineralizer Bypass Valve, at pane12N21-POOL Page 6 of7 SAT!
IUNSAT SAT I UNSAT SATIUNSAT SAT!UNSAT SAT/UNSAT SAT/UNSAT PROMPT:
WHEN the operator sends an SO to confirm the valve is open, THEN using time compression inform the operator that the Condensate Demineralizer Bypass valve is open.
NOTE: 2T48-F026127 are normally open and de-energized.
'ROMPT:
IF the operator asks about the status of 2T48-F026127, THEN inform the operator that they are de-energized but open.
(** Indicates critical step)
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PERFO~NCESTEP 1'*25. TRIP 2T41-B017 Fan 1, Rx Bldg Recirc Fan
- 26. TRIP 2T41-B017 Fan 2, Rx Bldg Recirc Fan
- 27. TRIP 2T41-C002A, Refuel FIr Vent Supply Fan
- 28. TRIP 2T41-C002B, Refuel Fir Vent Supply Fan
- 29. TRIP 2T41-C005A, Refuel Fir Vent Exh Fan
- 30. TRIP 2T41-C005B, Refuel FIr Vent ExhFan
- 31. Confirm OPEN/OPEN 2N21-F014, Condensate Demineralizer Bypass Valve.
STANDARD On pane12H11-P657 the operator places control switch for 2T41-B017 Fan 1, Rx Bldg Recirc Fan, to the OFF position, green light illuminated.
On pane12H11-P657 the operator places control switch for 2T41-BOl7 Fan 2, Rx Bldg Recirc Fan, to the OFF position, green light illuminated.
On pane12H11-P657 the operator places control switch for 2T41-C002A, Refuel FIr Vent Supply Fan, to the OFF position, green light illuminated.
On pane12HII-P657 the operator places control switch for 2T41-C002B, Refuel FIr Vent Supply Fan, to the OFF position, green light illuminated.
On pane12HII-P657 the operator places control switch for 2T41-C005A, Refuel Fir Vent Exh Fan, to the OFF position, green light illuminated.
On pane12HII-P657 the operator places control switch for 2T41-C005B, Refuel FIr Vent Exh Fan, to the OFF position, green light illuminated.
The operator sends an SO to confirm OPEN/OPEN 2N21-F014, Condensate Demineralizer Bypass Valve, at panel 2N21-POOL Page 6 of7 SATIUNSAT (COMMENTS SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT:
WHEN the operator sends an SO to confirm the valve is open, THEN using time compression inform the operator that the Condensate Demineralizer Bypass valve is open.
NOTE: 2T48-F026!27 are normally open and de-energized.
'ROMPT:
IF the operator asks about the status of 2T48-F026!27, THEN inform the operator that they are de-energized but open.
(** Indicates critical step)
- 34. Confirm OPEN/OPEN 2P52-F565, Rx Bldg Inst N2 To Non-Int Air E1185 Iso1 Vlv, on paneI2HII-P700.
The operator confirms OPEN/OPEN 2T48-F026, CAD B Nitrogen Makeup Outbd Isol valve.
The operator confirms OPEN/OPEN 2T48-F027, CAD A Nitrogen Makeup Inbd Isol valve.
The operator confirms OPEN/OPEN 2P52-F565, Rx Bldg Inst N2 To Non-Int Air El 185 Iso1 Vlv, on pane12Hll-P700, red light illuminated.
Page 7 of7
!SA1'ItJN$i\\.T COMMENTS SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT: IF the operator asks about air leaks, THEN inform the operator there are no indications of a leak.
PROMPT: IF the operator asks about OR attempts to start an air compressor, THEN inform the operator that the compressors can not be started and Electrical Maintenance and I&C are checking all electrical circuits.
- 35.
- 36.
Check annunciators Operator checks to see if the annunciators on 2HII-P700 are in alarm:
- Control Bldg Service Air Shutoff (700-234)
- Instr Air Dryer Malfunction (700-205)
Notify Plant Management and System Operator notifies:
Load Dispatcher.
- Plant Management
- System Load Dispatcher NOTE: The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
(** Indicates critical step)
SAT /UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT END TIME: ___ _
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PERFO~CESTEP
- 34. Confirm OPEN/OPEN 2P52-F565, Rx Bldg Inst N2 To Non-Int Air El185 Isol Vlv, on pane12Hll-P700.
STANDARD The operator confirms OPEN/OPEN 2T48-F026, CAD B Nitrogen Makeup Outbd Isol valve.
The operator confirms OPEN/OPEN 2T48-F027, CAD A Nitrogen Makeup Inbd Isol valve.
The operator confirms OPEN/OPEN 2P52-F565, Rx Bldg Inst N2 To Non-Int Air El 185 Isol Vlv, on pane12Hll-P700, red light illuminated.
Page 7 of7 SATIUNSAT COMMENTS SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT: IF the operator asks about air leaks, THEN inform the operator there are no indications of a leak.
PROMPT: IF the operator asks about OR attempts to start an air compressor, THEN inform the operator that the compressors can not be started and Electrical Maintenance and I&C are checking all electrical circuits.
- 35.
- 36.
Check annunciators Operator checks to see if the annunciators on 2Hll-P700 are in alarm:
- Control Bldg Service Air Shutoff (700-234)
- Instr Air Dryer Malfunction (700-205)
Notify Plant Management and System Operator notifies:
Load Dispatcher.
NOTE:
- Plant Management
- System Load Dispatcher The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT END TIME: ___ _
(** Indicates critical step)
UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 has lost all Service Air Compressors and they can not be restarted.
- 2. Electrical Maintenance and I&C are checking all air system electrical circuits.
- 3. The reactor has been scrammed and 34AB-C71-001-2, "Scram Procedure" is being carried out.
- 4. 34AB-P51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" has been partially completed.
INITIATING CUES:
Complete procedure 34AB-P51-001-2 starting at step 4.14.
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UNIT 2 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1. Unit 2 has lost all Service Air Compressors and they can not be restarted.
- 2. Electrical Maintenance and I&C are checking all air system electrical circuits.
- 3. The reactor has been scrammed and 34AB-C71-001-2, "Scram Procedure" is being carried out.
- 4. 34 AB-P 51-001-2 "Loss Of Instrument And Service Air System Or Water Intrusion Into The Service Air System" has been partially completed.
INITIATIN G CUES:
Complete procedure 34AB-P51-001-2 starting at step 4.14.
DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM PLANT 1 SOUTHERN.'
COMPANY Energy to Serve Your World SM
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DRAFT Southern Nuclear E. I. Hatch Nuclear Plant TITLE Operations Training JPM PLANT 1 VENT THE SCRAM AIR HEADER AUTHOR MEDIA NUMBER R. A. BELCHER LR-JP-1O.15-14 RECOMMENDED BY APPROVED BY TIME 10 Minutes DATE Energy to Serve Your World SM
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Page 1 of 1 Media Number:
LR*JP*I0.15 I
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERA TIONS TRAINING Rev. No.
Date Reason for Revision Page 1 of 1 Media Number:
LR-JP-IO.15 Author's Supv's Initials Initials
LR-JP-1O.15-14 Page 1 of 3 UNIT 1 (X)
UNIT 2 0
- TASjffXiJ)ii.
.J}l£I'~.E~t.<
VENT THE SCRAM AIR HEADER LR-JP-1O.15-14 The task shall be completed when the operator has successfully vented the scram air header per 31EO-EOP-l 03.
010.015 PLANT HATCH JTA IMPORTANCE RATING:
RO 4.50 SRO 3.65 KIA CATALOG NUMBER: 295015K2.11 KIA CATALOG JTA IMPORTANCE RATING:
RO 3.5 SRO 3.7 OPERATOR APPLICABILITY:
RO (current version) 31EO-EOP-Oll-l (current version)
APPROXIMATE COMPLETION TIME:
10 Minutes SIMULATOR SETUP:
NI A LR-JP-1O.15-14 Page 1 of 3 UNIT 1 (X)
UNIT 2 0
TASK TITLE:
VENT THE SCRAM AIR HEADER JPMNUMBER:
TASK STANDARD:
TASK NUMBER:
LR-JP-1O.15-14 The task shall be completed when the operator has successfully vented the scram air header per 31EO-EOP-103.
010.015 OBJECTIVE NUMBER: 010.015.0 PLANT HATCH JTA IMPORTANCE RATING:
RO 4.50 SRO 3.65 KIA CATALOG NUMBER: 295015K2.11
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KIA CATALOG JTA IMPORTANCE RATING:
RO 3.5 SRO 3.7 OPERA TOR APPLICABILITY:
RO I GENERAL
REFERENCES:
Unit 1 31EO-EOP-103-1 (current version) 31EO-EOP-Oll-1 (current version)
I REQUIRED MATERIALS:
Unit 1 31EO-EOP-103-1 (current revision)
APPROXIMATE COMPLETION TIME:
10 Minutes SIMULATOR SETUP:
N/A
UNITl READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
A Reactor scram signal has been received and all the control rods did not insert to Position 02 and Reactor power is greater than 10%.
- 2.
ATWS with 31EO-EOP-103-1 being performed
- 3.
ARI initiated and has been reset
- 4.
OATC is driving rod per section, per 31EO-EOP-103-1 section 3.7 and 3.8.
- 5.
OATC reports panellHll-P603 indications are:
- Blue Scram Lights - NOT illuminated INITIATING CUES:
IA W 31EO-EOP-103-1, Section 3.0, determine and perform actions to insert control rods.
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UNITl READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
A Reactor scram signal has been received and all the control rods did not insert to Position 02 and Reactor power is greater than 10%.
- 2.
A TWS with 31EO-EOP-103-1 being performed
- 3.
ARI initiated and has been reset
- 4.
OATC is driving rod per section, per 31EO-EOP-103-1 section 3.7 and 3.8.
- 5.
OATC reports panel1H11-P603 indications are:
- Blue Scram Lights - NOT illuminated INITIATING CUES:
lAW 31EO-EOP-103-1, Section 3.0, determine and perform actions to insert control rods.
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For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
- 1. Obtain the procedure.
Operator obtains 3IEO-EOP-103-I and refers to Section 3.0.
Operator determines that "Vent Scram Air Header" will insert rods and refers to section 3.6 START TIME: ___ _
SAT/UNSAT SAT/UNSAT PROMPT: IF the operator picks an incorrect section, THEN inform the operator that the section is unsuccessful in inserting rods.
At location 130RAR03, ICII-F095, SCRAM AIR HEADER ISOLATION V ALVE is CLOSED.
At location 130RAR03, cap is REMOVED from end of piping downstream of ICII-R013-TVl.
- 5. Open or verify open ICll-R013-IVl.
At location 130RAR03, ICII-R013-IVI, Pressure Instrumentation Isolation Valve is open.
- 7. Verify decreasing air pressure.
At location 130RAR03, ICII-R013-TVI, PRESSURE INSTRUMENTATION VENT V ALVE, is OPEN.
At location 130RAR03, Scram Air Header pressure is verified decreasing on ICll-PI-R013.
NOTE: The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT END TIME: ___ _
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- 1.
- 2.
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRITICAL STEPS must be completed for Satisfactory Performance.
Obtain the procedure.
Operator obtains 3IEO-EOP-103-I and refers to Section 3.0.
Determine correct flowchart action.
Operator determines that "Vent Scram Air Header" will insert rods and refers to section 3.6 START TIME:. ___ _
SAT/UNSAT SAT/UNSAT PROMPT: IF the operator picks an incorrect section, THEN inform the operator that the section is unsuccessful in inserting rods.
- 3.
- 4.
- 5.
- 6.
- 7.
Close ICII-F09S.
At location 130RAR03, ICll-F09S, SCRAM AIR HEADER ISOLATION VALVE is CLOSED.
Remove cap if installed from end of At location 130RAR03, cap is piping downstream of REMOVED from end of piping ICII-R013-TV!.
downstream of ICll-R013-TV!.
Open or verify open ICII-R013-IV!.
At location 130RAR03, ICII-R013-IVI, Pressure Instrumentation Isolation Valve is open.
Open ICll-R013-TV!.
At location 130RAR03, ICII-R013-TV!, PRESSURE INSTRUMENTATION VENT VALVE, is OPEN.
Verify decreasing air pressure.
At location 130RAR03, Scram Air Header pressure is verified decreasing on ICII-PI-R013.
NOTE:
The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
SAT/UNSAT SAT I UNSAT SAT I UNSAT SAT I UNSAT SAT/UNSAT END TIME: ___ _
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Operator states the task is complete.
TERMINATING CUE: We will stop here.
SOUTHERN NUCLEAR DOCUMENT TYPE:
PAGE 1 OF 22 PLANT E. I. HATCH EMERGENCY OPERATING PROCEDURE DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 EXPIRATION APPROVALS:
EFFECTIVE DATE:
DEPARTMENT MANAGER C. R. Dedrickson DATE 02-04-92 DATE:
NIA NPGM/POAGM/PSAGM D. R. Madison DATE 02-10-92 04/25/02 1.0 OBJECTIVE This procedure provides alternate methods of inserting control rods IF they fail to insert automatically upon receipt of a scram signal.
2.0 ENTRY CONDITIONS This procedure is to be performed as directed by 31 EO-EOP-011-1, RCA RPV Control (ATWS).
TABLE OF CONTENTS Section 3.0 OPERATOR ACTIONS....................................................................................................... 2 3.1 ARI MANUAL INITIATION............................................................................................. 3 3.2 RESETTING ARI.......................................................................................................... 4 3.3 REPEATING MANUAL SCRAM.................................................................................... 5 3.4 DE-ENERGIZING SCRAM SOLENOIDS...................................................................... 7 3.5 INDIVIDUALLY SCRAMMING RODS........................................................................... 8 3.6 VENTING SCRAM AIR HEADER................................................................................ 10 3.7 DRIVING CONTROL RODS....................................................................................... 11 3.8 INCREASING CRD COOLING WATER DP................................................................ 12 3.9 VENTING CRD WITHDRAW PORT............................................................................ 13
4.0 REFERENCES
................................................................................................................. 14 Attachments 1
SYSTEM RESTORATION................................................................................................. 15 2
THAXTON PIPE STOPPER DIAGRAM............................................................................ 22 MGR-0002 Rev 8
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SOUTHERN NUCLEAR DOCUMENT TYPE:
PAGE 1 OF 22 PLANT E. I. HATCH EMERGENCY OPERATING PROCEDURE DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 EXPIRATION APPROVALS:
EFFECTIVE DATE:
DEPARTMENT MANAGER C. R. Dedrickson DATE 02-04-92 DATE:
NIA NPGM/POAGM/PSAGM D. R. Madison DATE 02-10-92 04/25/02 1.0 OBJECTIVE This procedure provides alternate methods of inserting control rods IF they fail to insert automatically upon receipt of a scram signal.
2.0 ENTRY CONDITIONS This procedure is to be performed as directed by 31 EO-EOP-011-1, RCA RPV Control (ATWS).
TABLE OF CONTENTS Section 3.0 OPERATOR ACTIONS....................................................................................................... 2 3.1 ARI MANUAL INITIATION............................................................................................. 3 3.2 RESETTING ARI.......................................................................................................... 4 3.3 REPEATING MANUAL SCRAM.................................................................................... 5 3.4 DE-ENERGIZING SCRAM SOLENOIDS...................................................................... 7 3.5 INDIVIDUALLY SCRAMMING RODS........................................................................... 8 3.6 VENTING SCRAM AIR HEADER................................................................................ 10 3.7 DRIVING CONTROL RODS....................................................................................... 11 3.8 INCREASING CRD COOLING WATER DP................................................................ 12 3.9 VENTING CRD WITHDRAW PORT............................................................................ 13
4.0 REFERENCES
................................................................................................................. 14 Attachments 1
SYSTEM RESTORATION................................................................................................. 15 2
THAXTON PIPE STOPPER DIAGRAM............................................................................ 22 MGR-0002 Rev 8
SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
I CONTROL ROD INSERTION METHODS 3.0 OPERATOR ACTIONS De-energize Scram solenoids per subsection 3.4 MGR-0001 Rev 3 NO WAIT UNTIL ARI inward rod motion has ceased G16.30 DOCUMENT NUMBER:
31 EO-EOP-103-1 PAGE 2 OF 22 VERSION NO:
4.2 Increase CRD Cooling Water A p per subsection 3.8 WAIT UNTIL All other rod insertion methods have failed Vent CRD Withdraw port per subsection 3.9
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SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
I CONTROL ROD INSERTION METHODS 3.0 OPERATOR ACTIONS YES De-energize Scram solenoids per subsection 3.4 YES per subsection 3.5 MGR-0001 Rev 3 NO WAIT UNTIL ARI inward rod motion has ceased per subsection 3.6 G16.30 DOCUMENT NUMBER:
31 EO-EOP-1 03-1 PAGE 2 OF 22 VERSION NO:
4.2 Increase CRD Cooling Water L\\. p per subsection 3.8 WAIT UNTIL All other rod insertion methods have failed Vent CRD Withdraw port per subsection 3.9
SOUTHERN NUCLEAR PLANT E. I. HATCH I
PAGE 3 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER: VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 NOTE:
3.0.1 3.0.2 3.0.3 3.0.4 3.1 3.1.1 3.1.2 3.1.3 Subsections 3.3 through 3.9 of this procedure each describe a different method of inserting control rods. The Shift Supervisor or the plant operator will determine which sections will be most effective and which may be performed concurrently based on current plant conditions. Not all subsections need to be performed, and some subsections may be performed more than once IF desired. Section 3.0 may be referred to for guidance.
IF BLUE Scram Inlet and Outlet Valve lights are ILLUMINATED, THEN perform subsection 3.3.
IF WHITE RPS Scram Group A (B) lights are ILLUMINATED, THEN Perform subsection 3.4.
IE BLUE Scram Inlet and Outlet Valve lights are EXTINGUISHED, THEN perform subsection 3.6.
IF all other rod insertion methods have failed, THEN perform subsection 3.9.
ARI MANUAL INITIATION Arm both ARI Manual Initiation Ch A and Ch B push buttons by rotating the pushbutton collar to the ARMED position at panel 1 H 11-P603.
Depress both ARI Manual Initiation Ch A and Ch B pushbuttons.
Check that the ARIINITIATED (603-304) annunciator has ALARMED.
G16.30 MGR-0001 Rev 3
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PAGE 3 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER: VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 NOTE:
3.0.1 3.0.2 3.0.3 3.0.4 3.1 Subsections 3.3 through 3.9 of this procedure each describe a different method of inserting control rods. The Shift Supervisor or the plant operator will determine which sections will be most effective and which may be performed concurrently based on current plant conditions. Not all subsections need to be performed, and some subsections may be performed more than once IF desired. Section 3.0 may be referred to for guidance.
!.E BLUE Scram Inlet and Outlet Valve lights are ILLUMINATED, THEN perform subsection 3.3.
!.E WHITE RPS Scram Group A (B) lights are ILLUMINATED, THEN Perform subsection 3.4.
!.E BLUE Scram Inlet and Outlet Valve lights are EXTINGUISHED, THEN perform subsection 3.6.
!.E all other rod insertion methods have failed, THEN perform subsection 3.9.
ARI MANUAL INITIATION 3.1.1 Arm both ARI Manual Initiation Ch A and Ch B push buttons by rotating the pushbutton collar to the ARMED position at panel 1 H 11-P603.
3.1.2 Depress both ARI Manual Initiation Ch A and Ch B push buttons.
3.1.3 Check that the ARIINITIATED (603-304) annunciator has ALARMED.
G16.30 MG R-OOO 1 Rev 3
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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 4 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.2 RESETTING ARI 3.2.1
!E ARI initiation signals have cleared, THEN depress ARI Reset pushbutton on panel 1 H11-P603.
AND Check that the annunciator ARI INITIATED on panel 1 H11-P603 is CLEAR.
3.2.2 IF ARI initiation signals have not cleared, THEN place the ARI System Test switch, to TEST, on paneI1C11-P001, at 112TFT12.
Check green lights ILLUMINATED on paneI1C11-P001:
VALVE DESCRIPTION 1C11-F228 ARI Solenoid Valve Exhaust Port.
1C11-F229A ARI Solenoid Valve Exhaust Port.
1 C11-F229B ARI Solenoid Valve Exhaust Port.
1C11-F230 ARI Solenoid Valve Exhaust Port.
3.2.3 Perform SYSTEM RESTORATION per Attachment 1 Section 1 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
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PAGE 4 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 3.2 RESETTING ARI 3.2.1 IE. ARI initiation signals have cleared, THEN depress ARI Reset pushbutton on panel 1 H11-P603.
AND Check that the annunciator ARI INITIATED on panel 1 H11-P603 is CLEAR.
3.2.2 IE. ARI initiation signals have not cleared, THEN place the ARI System Test switch, to TEST, on panel 1 C11-P001, at 112TFT12.
Check green lights ILLUMINATED on paneI1C11-P001:
VALVE DESCRIPTION 1C11-F228 ARI Solenoid Valve Exhaust Port.
1C11-F229A ARI Solenoid Valve Exhaust Port.
1C11-F229B ARI Solenoid Valve Exhaust Port.
1C11-F230 ARI Solenoid Valve Exhaust Port.
3.2.3 Perform SYSTEM RESTORATION per Attachment 1 Section 1 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
SOUTHERN NUCLEAR PLANT E. I. HATCH I
PAGE 5 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER: VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.3 3.3.1 3.3.2 3.3.3 NOTE:
3.3.4 3.3.5 3.3.6 REPEATING MANUAL SCRAM Bypass scram discharge volume high level trip at 1 H11-P603.
Confirm RPS Test Trip Logic switches are in NORMAL SWITCH DESCRIPTION LOCATION 1C71-S2A RPS Test A1 Trip Logic 1 H11-P609 1C71-S2C RPS Test A2 Trip Logic 1 H11-P609 1C71-S2B RPS Test B1 Trip Logic 1H11-P611 1C71-S2D RPS Test B2 Trip Logic 1 H11-P611 IF all other scram signals are clear, THEN go to step 3.3.5.
Pre-staged jumpers will be found in the EOP jumper book located behind the operator desk.
Install jumpers to override all automatic scram signals:
JUMPER PANEL 1C71-K10AContact2 to 1C71-K12EContact4 1 H11-P609C 1C71-K10C Contact 2 to 1C71-K12G Contact 4 1H11-P609A 1C71-K10B Contact 2 to 1C71-K12F Contact 4 1 H11-P611C 1C71-K10D Contact 2 to 1C71-K12H Contact 4 1 H11-P611A Place Disch Vol Isol Test switch to NORM.
Reset ARI, lE necessary, per subsection 3.2.
G16.30 MGR-0001 Rev 3
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PAGE 5 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.3 REPEATING MANUAL SCRAM 3.3.1 Bypass scram discharge volume high level trip at 1 H11-P603.
3.3.2 Confirm RPS Test Trip Logic switches are in NORMAL SWITCH DESCRIPTION LOCATION 1C71-S2A RPS Test A 1 Trip Logic 1 H11-P609 1C71-S2C RPS Test A2 Trip Logic 1 H11-P609 1C71-S2B RPS Test B1 Trip Logic 1H11-P611 1C71-S2D RPS Test B2 Trip Logic 1 H11-P611 3.3.3 IF all other scram signals are clear, THEN go to step 3.3.5.
NOTE:
Pre-staged jumpers will be found in the EOP jumper book located behind the operator desk.
3.3.4 Install jumpers to override all automatic scram signals:
JUMPER PANEL 1C71-K10AContact2 to 1C71-K12EContact4 1 H11-P609C 1C71-K10C Contact 2 to 1C71-K12G Contact 4 1 H11-P609A 1C71-K10B Contact 2 to 1C71-K12F Contact 4 1 H11-P611C 1 C71-K1 00 Contact 2 to 1 C71-K12H Contact 4 1 H11-P611A 3.3.5 Place Disch Voilsol Test switch to NORM.
3.3.6 Reset ARI, I.E necessary, per subsection 3.2.
G16.30 MGR-0001 Rev 3
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PAGE 6 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.3.7 I.E 1 C11-F034, Charging Water Header Isolation Valve, has been CLOSED AND Reactor pressure is below 800 psig, THEN REOPEN 1C11-F034 at 130RAR03.
3.3.8 Reset scram.
3.3.9 Confirm all SDV Vent and Drain Valves are OPEN.
3.3.10 Drain SDV UNTIL SCRAM DISCH VOL HIGH LEVEL TRIP alarm OR SCRAM DISCH VOL NOT DRAINED alarm clears.
3.3.11 Insert manual scram.
3.3.12 Repeat steps 3.3.8 through 3.3.11 UNTIL additional inward rod motion is no longer observed.
3.3.13 I.E rod motion is not observed, THEN perform subsection 3.5.
3.3.14 Perform SYSTEM RESTORATION per Attachment 1 section 2.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
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PAGE 6 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER: VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.3.7 IE 1C11-F034, Charging Water Header Isolation Valve, has been CLOSED AND Reactor pressure is below BOO psig, THEN REOPEN 1 C11-F034 at 130RAR03.
3.3.B Reset scram.
3.3.9 Confirm all SDV Vent and Drain Valves are OPEN.
3.3.10 Drain SDV UNTIL SCRAM DISCH VOL HIGH LEVEL TRIP alarm OR SCRAM DISCH VOL NOT DRAINED alarm clears.
3.3.11 Insert manual scram.
3.3.12 Repeat steps 3.3.B through 3.3.11 UNTIL additional inward rod motion is no longer observed.
3.3.13 IE rod motion is not observed, THEN perform subsection 3.5.
3.3.14 Perform SYSTEM RESTORATION per Attachment 1 section 2.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
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PAGE 7 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 3.4 DE-ENERGIZING SCRAM SOLENOIDS 3.4.1 Place keylock RPS Test Trip Logic switches to TRIP:
SWITCHES DESCRIPTION LOCATION 1C71-S2A RPS Test Ai Trip Logic 1H11-P609.
1C71-S2C RPS Test A2 Trip Logic 1 H11-P609.
1C71-S2B RPS Test B1 Trip Logic 1H11-P611.
1C71-S2D RPS Test B2 Trip Logic 1H11-P611.
NOTE:
Fuse pullers may be found in the Unit 1 and Unit 2 key cabinets located behind the STA desk.
3.4.2 IE scram solenoids are still energized, THEN remove fuses:
LOCATION FUSES Panel CC-F03 1C71-F18A 1 H11-P609B CC-F04 1C71-F18E 1 H11-P609B CC-F05 1C71-F18C 1 H11-P609B CC-F06 1C71-F18G 1 H11-P609B CC-F03 1C71-F18B 1H11-P611B CC-F04 1C71-F18F 1H11-P611B CC-F05 1C71-F18D 1H11-P611B CC-F06 1C71-F18H 1H11-P611B 3.4.3 Perform SYSTEM RESTORATION per Attachment 1 Section 3.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
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PAGE 7 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.4 DE-ENERGIZING SCRAM SOLENOIDS 3.4.1 Place keylock RPS Test Trip Logic switches to TRIP:
NOTE:
3.4.2 3.4.3 SWITCHES DESCRIPTION LOCATION 1C71-S2A RPS Test A1 Trip Logic 1H11-P609.
1C71-S2C RPS Test A2 Trip Logic 1H11-P609.
1C71-S2B RPS Test B1 Trip Logic 1H11-P611.
1C71-S2D RPS Test B2 Trip Logic 1H11-P611.
Fuse pullers may be found in the Unit 1 and Unit 2 key cabinets located behind the STA desk.
lE. scram solenoids are still energized, THEN remove fuses:
LOCATION FUSES Panel CC-F03 1C71-F18A 1 H11-P609B CC-F04 1C71-F18E 1 H11-P609B CC-F05 1C71-F18C 1 H11-P609B CC-F06 1C71-F18G 1 H11-P609B CC-F03 1 C71-F18B 1 H11-P611 B CC-F04 1C71-F18F 1H11-P611B CC-F05 1C71-F18D 1H11-P611B CC-F06 1C71-F18H 1H11-P611B Perform SYSTEM RESTORATION per Attachment 1 Section 3.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
SOUTHERN NUCLEAR PLANT E. I. HATCH I
PAGE 8 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.5 3.5.1 3.5.2 3.5.3 NOTE:
3.5.4 INDIVIDUALLY SCRAMMING RODS Bypass scram discharge volume high level trip at 1 H11-P603.
Confirm RPS Test Trip Logic switches in NORMAL:
SWITCH DESCRIPTION LOCATION 1C71-S2A RPS Test A1 Trip Logic 1 H11-P609.
1C71-S2C RPS Test A2 Trip Logic 1 H11-P609 1C71-S2B RPS Test B1 Trip Logic 1 H11-P611 1C71-S2D RPS Test B2 Trip Logic 1H11-P611 IF all other scram signals are clear, THEN go to step 3.5.5.
Pre-staged jumpers will be found in the EOP jumper book located behind the operator desk.
Override all automatic scram signals by installing the following jumpers:
JUMPER PANEL 1C71-K10A Contact 2 to 1 C71-K12E Contact 4 1 H11-P609C 1 C71-K 1 OC Contact 2 to 1 C71-K 12G Contact 4 1 H11-P609A 1C71-K10B Contact 2 to 1C71-K12F Contact 4 1 H11-P611C 1C71-K10D Contact 2 to 1C71-K12H Contact 4 1H11-P611A 3.5.5 Place Disch Voilsol Test switch to NORM.
3.5.6 Reset ARI, !E necessary, per subsection 3.2.
G16.30 MGR-0001 Rev 3
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PAGE 8 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER: VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.5 INDIVIDUALLY SCRAMMING RODS 3.5.1 Bypass scram discharge volume high level trip at 1 H11-P603.
3.5.2 Confirm RPS Test Trip Logic switches in NORMAL:
SWITCH DESCRIPTION LOCATION 1C71-S2A RPS Test A1 Trip Logic 1H11-P609.
1C71-S2C RPS Test A2 Trip Logic 1 H11-P609 1C71-S2B RPS Test B1 Trip Logic 1 H11-P611 1C71-S2D RPS Test B2 Trip Logic 1 H11-P611 3.5.3
!E all other scram signals are clear, THEN go to step 3.5.5.
NOTE:
Pre-staged jumpers will be found in the EOP jumper book located behind the operator desk.
3.5.4 Override all automatic scram signals by installing the following jumpers:
JUMPER PANEL 1C71-K10A Contact 2 to 1C71-K12E Contact 4 1 H11-P609C 1 C71-K1 OC Contact 2 to 1 C71-K12G Contact 4 1 H11-P609A 1C71-K10B Contact 2 to 1C71-K12F Contact 4 1 H11-P611C 1C71-K10D Contact 2 to 1C71-K12H Contact 4 1H11-P611A 3.5.5 Place Disch Voilsol Test switch to NORM.
3.5.6 Reset ARI, !E necessary, per subsection 3.2.
G16.30 MGR-0001 Rev 3
SOUTHERN NUCLEAR PLANT E. I. HATCH I
PAGE 9 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER: VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.5.7 IE 1 C11-F034, Charging Water Header Isolation Valve, has been CLOSED; 3.5.8 3.5.9 NOTE:
Reactor pressure is below 800 psig, THEN REOPEN 1 C11-F034 at 130RAR03.
Reset scram.
Confirm all SDV Vent and Drain Valves are OPEN.
Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.
3.5.10 Obtain recommendations from the STA as to which rods have the highest worth.
3.5.11 Establish communications between panel 1 H11-P61 0 and 1 H11-P603.
3.5.12 Place the Reactor Mode switch to REFUEL, at panel 1 H11-P603.
3.5.13 Select a high worth rod and monitor it's position, at panel 1 H11-P603.
3.5.14 Place the Rod Scram Switch for the selected rod to the DOWN (scram) position, at panel1H11-P610.
3.5.15 WHEN rod motion has stopped, THEN place the Rod Scram Switch to the UP (normal) position.
3.5.16 Repeat steps 3.5.13 thru 3.5.15 to individually scram other rods as desired 3.5.17 IF rod motion is NOT observed, THEN perform subsection 3.7.
3.5.18 Perform SYSTEM RESTORATION, per Attachment 1 Section 4.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
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PAGE 9 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.5.7 IE 1 C11-F034, Charging Water Header Isolation Valve, has been CLOSED; Reactor pressure is below 800 psig, THEN REOPEN 1 C11-F034 at 130RAR03.
3.5.8 Reset scram.
3.5.9 Confirm all SDV Vent and Drain Valves are OPEN.
NOTE:
Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.
3.5.10 3.5.11 3.5.12 3.5.13 3.5.14 Obtain recommendations from the STA as to which rods have the highest worth.
Establish communications between pane11H11-P610 and 1H11-P603.
Place the Reactor Mode switch to REFUEL, at panel 1 H11-P603.
Select a high worth rod and monitor it's position, at panel 1 H11-P603.
Place the Rod Scram Switch for the selected rod to the DOWN (scram) position, at panel 1 H 11-P61 O.
3.5.15 WHEN rod motion has stopped, THEN place the Rod Scram Switch to the UP (normal) position.
3.5.16 Repeat steps 3.5.13 thru 3.5.15 to individually scram other rods as desired 3.5.17 IF rod motion is NOT observed, THEN perform subsection 3.7.
3.5.18 Perform SYSTEM RESTORATION, per Attachment 1 Section 4.0 WHEN directed by the Shift Supervisor.
G16,30 MGR-0001 Rev 3
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PAGE 10 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER: VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 3.6 3.6.1 NOTE:
3.6.2 VENTING SCRAM AIR HEADER CLOSE 1 C 11-F095, Scram Air Header Isolation Valve, at location 130RAR03.
Pliers may be obtained from the EOP gang box on the 130' elevation to aid in the cap removal.
i.E the line is capped, THEN remove cap down stream of 1C11-R013-TV1, Pressure Instrumentation Vent Valve.
3.6.3 Confirm OPEN/OPEN 1 C11-R013-IV1, Pressure Instrumentation Isolation Valve, at location 130RAR03.
3.6.4 OPEN 1 C11-R013-TV1, Pressure Instrumentation Vent Valve, at location 130RAR03.
3.6.5 Perform SYSTEM RESTORATION per Attachment 1 Section 5.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
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PAGE 10 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.6 3.6.1 NOTE:
3.6.2 VENTING SCRAM AIR HEADER CLOSE 1 C11-F095, Scram Air Header Isolation Valve, at location 130RAR03.
Pliers may be obtained from the EOP gang box on the 130' elevation to aid in the cap removal.
IE the line is capped, THEN remove cap down stream of 1C11-R013-TV1, Pressure Instrumentation Vent Valve.
3.6.3 Confirm OPEN/OPEN 1 C11-R013-IV1, Pressure Instrumentation Isolation Valve, at location 130RAR03.
3.6.4 OPEN 1 C11-R013-TV1, Pressure Instrumentation Vent Valve, at location 130RAR03.
3.6.5 Perform SYSTEM RESTORATION per Attachment 1 Section 5.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
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PAGE 11 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 3.7 DRIVING CONTROL RODS 3.7.1 Place Reactor Mode switch to REFUEL.
3.7.2 Place Rod Worth Minimizer bypass switch to BYPASS.
NOTE:
Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.
3.7.3 3.7.4 3.7.4.1 3.7.4.2 3.7.4.3 Obtain recommendations from STA as to which rods have the highest worth.
Establish adequate CRD drive water pressure for driving rods as follows:
IF scram is reset and a CRD pump is running, THEN adjust 1 C11-F003, Drive Press Cntl Vlv, as required.
IF two CRD pumps can be started, THEN place CRD Flow Control 1 C11-R600 in MANUAL and adjust as required.
IF scram is NOT reset AND only one CRD pump can be started, THEN CLOSE 1 C11-F034, Charging Water Header Isolation Valve, at 130RAR03.
3.7.5 Drive selected rods to at least position 02 using the Emerg In Notch Override switch in the EMER ROD IN position OR Rod Movement Switch in the IN position.
3.7.6 IF rod motion is NOT observed, THEN perform subsection 3.8.
3.7.7 Perform SYSTEM RESTORATION per Attachment 1 Section 6.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
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PAGE 11 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.7 DRIVING CONTROL RODS 3.7.1 Place Reactor Mode switch to REFUEL.
3.7.2 Place Rod Worth Minimizer bypass switch to BYPASS.
NOTE:
Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.
3.7.3 3.7.4 3.7.4.1 3.7.4.2 3.7.4.3 Obtain recommendations from STA as to which rods have the highest worth.
Establish adequate CRD drive water pressure for driving rods as follows:
IF scram is reset and a CRD pump is running, THEN adjust 1 C11-F003, Drive Press Cntl Vlv, as required.
IF two CRD pumps can be started, THEN place CRD Flow Contro11C11-R600 in MANUAL and adjust as required.
IF scram is NOT reset AND only one CRD pump can be started, THEN CLOSE 1 C11-F034, Charging Water Header Isolation Valve, at 130RAR03.
3.7.5 Drive selected rods to at least position 02 using the Emerg In Notch Override switch in the EMER ROD IN position OR Rod Movement Switch in the IN position.
3.7.6 IF rod motion is NOT observed, THEN perform subsection 3.8.
3.7.7 Perform SYSTEM RESTORATION per Attachment 1 Section 6.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
SOUTHERN NUCLEAR PLANT E. I. HATCH I
PAGE 12 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER: VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 3.8 INCREASING CRD COOLING WATER DP CAUTION' INCREASING CRD COOLING WATER DP MAY RESULT IN CRD SEAL
.:.:..:.:..:..:=. DAMAGE.
3.8.1 IF the scram cannot be reset, THEN CLOSE 1C11-F034, Charging Water Header Isolation Valve, at location 130RAR03.
3.8.2 PLACE 1 C11-R607, Press Control Vlv F127 Controller, in MAN and run output to 100%, at 1H11-P603.
3.8.3 Confirm OPEN OR fully OPEN 1C11-F003 at 1 H11-P603.
3.8.4 PLACE 1 C11-R600, CRD Flow Control, in MANUAL and run outputto 100% at 1 H 11-P603.
3.8.5 CLOSE 1 C11-F005, Return To Vessel Flow Control, at panel 1 H11-P603.
3.8.6 Perform SYSTEM RESTORATION per Attachment 1 Section 7.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
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SOUTHERN NUCLEAR PLANT E. I. HATCH I
PAGE 12 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 3.8 INCREASING CRD COOLING WATER DP CAUTION: INCREASING CRD COOLING WATER DP MAY RESULT IN CRD SEAL DAMAGE.
3.8.1 IF the scram cannot be reset, 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 THEN CLOSE 1 C11-F034, Charging Water Header Isolation Valve, at location 130RAR03.
PLACE 1C11-R607, Press Control Vlv F127 Controller, in MAN and run output to 100%, at 1H11-P603.
Confirm OPEN OR fully OPEN 1C11-F003 at 1 H11-P603.
PLACE 1 C11-R600, CRD Flow Control, in MANUAL and run outputto 100% at 1 H 11-P603.
CLOSE 1C11-F005, Return To Vessel Flow Control, at panel 1 H11-P603.
Perform SYSTEM RESTORATION per Attachment 1 Section 7.0 WHEN directed by the Shift Supervisor.
G16.30 MGR-0001 Rev 3
SOUTHERN NUCLEAR PLANT E. I. HATCH I
PAGE 13 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 3.9 NOTE:
VENTING CRD WITHDRAW PORT Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.
-HIGH PRESSURE STEAM AND WATER WILL EXIST IN HOSE ATTACHED TO WITHDRAW VENT VALVE. WHEN MIXTURE EXITS HOSE OR IF ANY CONNECTIONS LEAK IT WILL FLASH TO STEAM. HEALTH PHYSICS PERSONNEL MUST BE NOTIFIED.
CAUTIONS:
-EXIT VELOCITY OF STEAM AND WATER MIXTURE WILL CAUSE HOSE TO WHIP. HOSE MUST BE ANCHORED USING SAFETY GAG.
-IF NEEDLE IN WITHDRAW VENT VALVE IS OPENED TOO FAR IT COULD SHOOT OUT AND CAUSE INJURY.
3.9.1 Obtain recommendations from the STA as to which rods have the highest worth. __
NOTE:
The 1C11-F102 is a block valve located approximately 10 to 15 feet above the HCU.
3.9.2 Confirm 1 C11-F1 02, Withdraw Riser Vent Valve is CLOSED.
NOTE:
A high temperature hose with a quick-connect assembly for connection to 1C11-F102 is located in the EOP gang box on the 130' elevation of the Reactor Building.
3.9.3 For selected control rod, remove plug and attach designated high pressure high temperature hose to 1 C11-F1 02, Withdraw Riser Vent Valve. Obtain hose from the EOP gang box on the 130' elevation of the reactor building.
3.9.4 Route hose to closest equipment drain hub. Place safety gag over standpipe and secure by tightening bolts. (See attach 2) 3.9.5 Fully insert Thaxton Pipe Stopper into Equipment Drain standpipe. Tighten hex nut until grip segments are firmly seated against inside wall of stand pipe.
G16.30 MGR-0001 Rev 3
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SOUTHERN NUCLEAR PLANT E. I. HATCH I
PAGE 13 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 3.9 NOTE:
VENTING CRD WITHDRAW PORT Generally, inserting central rods in a black-and-white pattern will add the most negative reactivity.
-HIGH PRESSURE STEAM AND WATER WILL EXIST IN HOSE ATTACHED TO WITHDRAW VENT VALVE. WHEN MIXTURE EXITS HOSE OR IF ANY CONNECTIONS LEAK IT WILL FLASH TO STEAM. HEALTH PHYSICS PERSONNEL MUST BE NOTIFIED.
CAUTIONS:
-EXIT VELOCITY OF STEAM AND WATER MIXTURE WILL CAUSE HOSE TO WHIP. HOSE MUST BE ANCHORED USING SAFETY GAG.
3.9.1
-IF NEEDLE IN WITHDRAW VENT VALVE IS OPENED TOO FAR IT COULD SHOOT OUT AND CAUSE INJURY.
Obtain recommendations from the STA as to which rods have the highest worth. __
NOTE:
The 1 C11-F1 02 is a block valve located approximately 10 to 15 feet above the HCU.
3.9.2 NOTE:
3.9.3 3.9.4 3.9.5 Confirm 1 C11-F1 02, Withdraw Riser Vent Valve is CLOSED.
A high temperature hose with a quick-connect assembly for connection to 1C11-F102 is located in the EOP gang box on the 130' elevation of the Reactor Building.
For selected control rod, remove plug and attach designated high pressure high temperature hose to 1 C11-F1 02, Withdraw Riser Vent Valve. Obtain hose from the EOP gang box on the 130' elevation of the reactor building.
Route hose to closest equipment drain hUb. Place safety gag over standpipe and secure by tightening bolts. (See attach 2)
Fully insert Thaxton Pipe Stopper into Equipment Drain standpipe. Tighten hex nut until grip segments are firmly seated against inside wall of stand pipe.
G16.30 MGR-0001 Rev 3
SOUTHERN NUCLEAR PLANT E. I. HATCH I
PAGE 14 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER: VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.9.6 SLOWLY OPEN 1 C11-F1 02, Vent Valve, ONE HALF OF ONE TURN using the prestaged CRD Vent Valve Tool found in the EOP Gangbox located on the 130' Elev. of the Reactor Building.
3.9.7 WHEN any of the following conditions occur:
-control rod inserts past position 02.
-control rod inward motion stops.
THEN CLOSE 1 C11-F1 02, Vent Valve.
3.9.8 Repeat steps 3.9.6 and 3.9.7 UNTIL control rod is inserted past position 02 as directed by the Shift Supervisor.
3.9.9 Repeat steps 3.9.2 through 3.9.8 to insert all selected rods past position 02.
3.9.10 Perform SYSTEM RESTORATION per Attachment 1 section 8.0 WHEN directed by Shift Supervisor.
4.0 REFERENCES
4.1 H-17791 and H-17792, Reactor Protection System C71 Elementary Diagram.
4.2 H-16064 and H-16065, Control Rod Drive System P & ID 4.3 H-50412, ATWS-ARI System C11 Elementary Diagram.
G16.30 MGR-0001 Rev 3
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SOUTHERN NUCLEAR PLANT E. I. HATCH I
PAGE 14 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER: VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 3.9.6 SLOWLY OPEN 1C11-F102, Vent Valve, ONE HALF OF ONE TURN using the prestaged CRD Vent Valve Tool found in the EOP Gangbox located on the 130' Elev. of the Reactor Building.
3.9.7 WHEN any of the following conditions occur:
-control rod inserts past position 02.
-control rod inward motion stops.
THEN CLOSE 1C11-F102, Vent Valve.
3.9.8 Repeat steps 3.9.6 and 3.9.7 UNTIL control rod is inserted past position 02 as directed by the Shift Supervisor.
3.9.9 Repeat steps 3.9.2 through 3.9.8 to insert all selected rods past position 02.
3.9.10 Perform SYSTEM RESTORATION per Attachment 1 section 8.0 WHEN directed by Shift Supervisor.
4.0 REFERENCES
4.1 H-17791 and H-17792, Reactor Protection System C71 Elementary Diagram.
4.2 H-16064 and H-16065, Control Rod Drive System P & ID 4.3 H-50412, ATWS-ARI System C11 Elementary Diagram.
G16.30 MGR-0001 Rev 3
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
CONTROL ROD INSERTION METHODS ATTACHMENT..1 TITLE: SYSTEM RESTORATION PAGE 15 OF 22 DOCUMENT NUMBER:
VERSION NO:
31 EO-EOP-1 03-1 4.2 ATTACHMENT PAGE:
1 OF 7 The Shift Supervisor will forward this document with all sign-offs complete to Document Control.
PERSON(S) PERFORMING OR VERIFYING LINEUP (PRINT NAME)
INITIALS LINEUP COMPLETED:
TIME ______
DATE _____
REVIEWED BY: SS ____________ TIME ____
./DATE ___
COMMENTS: ___________________________________________________ _
OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4
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SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
CONTROL ROD INSERTION METHODS ATTACHMENT..1 TITLE: SYSTEM RESTORATION PAGE 15 OF 22 DOCUMENT NUMBER:
VERSION NO:
31 EO-EOP-1 03-1 4.2 ATTACHMENT PAGE:
1 OF 7 The Shift Supervisor will forward this document with all sign-ofts complete to Document Control.
PERSON(S) PERFORMING OR VERIFYING LINEUP (PRINT NAME)
INITIALS LINEUP COMPLETED:
TIME ______
DATE _____
REVIEWED BY: SS _____________ TIME ___
'/DATE. ___
COMMENTS: ____________________________________________________ ___
OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4
SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 16 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS ATTACHMENT..1 TITLE: SYSTEM RESTORATION 31 EO-EOP-103-1 4.2 ATTACHMENT PAGE:
2 OF 7 NOTE:
Each section may be performed in whole OR in part.
1.0 ARI Place ARI System Test switch to NORMAL on panel 1 C11-P001.
Verify 2.0 MANUAL SCRAM 2.1 IF jumpers were installed in 3.3.4, THEN remove the following jumpers:
JUMPER PANEL 1C71-K10A Contact 2 to 1C71-K12E Contact 4 1 H11-P609C Verify 1C71-K10C Contact 2 to 1C71-K12G Contact 4 1H11-P609A Verify 1C71-K10B Contact 2 to 1C71-K12F Contact 4 1H11-P611C Verify 1C71-K10D Contact 2 to 1C71-K12H Contact 4 1H11-P611A Verify OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4
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SOUTHERN NUCLEAR PLANT E.I. HATCH PAGE 16 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS ATTACHMENT..1 TITLE: SYSTEM RESTORATION 31 EO-EOP-103-1 4.2 ATTACHMENT PAGE:
2 OF 7 NOTE:
Each section may be performed in whole OR in part.
1.0 ARI Place ARI System Test switch to NORMAL on panel 1 C11-P001.
Verify 2.0 MANUAL SCRAM 2.1 IF jumpers were installed in 3.3.4, THEN remove the following jumpers:
JUMPER PANEL 1C71-K10A Contact 2 to 1C71-K12E Contact 4 1 H11-P609C Verify 1C71-K10C Contact 2 to 1C71-K12G Contact 4 1H11-P609A Verify 1C71-K10B Contact 2 to 1C71-K12F Contact 4 1H11-P611C Verify 1C71-K10D Contact 2 to 1C71-K12H Contact 4 1H11-P611A Verify OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4
SOUTHERN NUCLEAR PAGE 17 OF 22 PLANT E.I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 ATTACHMENT..1 ATTACHMENT PAGE:
TITLE: SYSTEM RESTORATION 30F7 3.0 SCRAM SOLENOIDS 3.1 Install RPS Scram Solenoid Fuses.
LOCATION FUSES PANEL CC-F03 1C71-F18A 1 H11-P609B Verify CC-F04 1C71-F18E 1H11-P609B Verify CC-F05 1 C71-F18C 1 H11-P609B Verify CC-F06 1C71-F18G 1H11-P609B Verify CC-F03 1C71-F18B 1H11-P611B Verify CC-F04 1C71-F18F 1H11-P611B Verify CC-F05 1 C71-F18D 1H11-P611B Verify CC-F06 1 C71-F18H 1H11-P611B Verify
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OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4 SOUTHERN NUCLEAR PAGE 17 OF 22 PLANT E.!. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 ATTACHMENT..1 ATTACHMENT PAGE:
TITLE: SYSTEM RESTORATION 30F7 3.0 SCRAM SOLENOIDS 3.1 Install RPS Scram Solenoid Fuses.
LOCATION FUSES PANEL CC-F03 1C71-F18A 1 H11-P609B Verify CC-F04 1C71-F18E 1 H11-P609B Verify CC-F05 1 C71-F18C 1 H11-P609B Verify CC-F06 1C71-F18G 1 H11-P609B
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Verify CC-F03 1 C71-F18B 1 H11-P611 B Verify CC-F04 1 C71-F18F 1H11-P611B Verify CC-F05 1 C71-F18D 1H11-P611B Verify CC-F06 1 C71-F18H 1H11-P611B Verify OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4
SOUTHERN NUCLEAR PLANT E.1. HATCH DOCUMENT TITLE:
CONTROL ROD INSERTION METHODS ATTACHMENT..1 TITLE: SYSTEM RESTORATION PAGE 18 OF 22 DOCUMENT NUMBER:
VERSION NO:
31 EO-EOP-1 03-1 4.2 ATTACHMENT PAGE:
40F7 3.2 Confirm keylock RPS Test Trip Logic switches in NORMAL.
SWITCHES LOCATION 1C71-S2A RPS Test A1 Trip Logic 1 H11-P609 Verify 1C71-S2C RPS Test A2 Trip Logic 1 H11-P609 Verify 1C71-S2B RPS Test B1 Trip Logic 1H11-P611 Verify 1C71-S2D RPS Test B2 Trip Logic 1H11-P611 Verify OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4 SOUTHERN NUCLEAR PLANT E.!. HATCH DOCUMENT TITLE:
CONTROL ROD INSERTION METHODS ATTACHMENT..1 TITLE: SYSTEM RESTORATION PAGE 18 OF 22 DOCUMENT NUMBER:
VERSION NO:
31 EO-EOP-103-1 4.2 ATTACHMENT PAGE:
4 OF 7 3.2 Confirm keylock RPS Test Trip Logic switches in NORMAL.
OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4
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SOUTHERN NUCLEAR PLANT E.!. HATCH PAGE 19 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 ATTACHMENT..1 TITLE: SYSTEM RESTORATION 4.0 INDIVIDUAL ROD SCRAM 4.1 IF jumpers were installed in 3.5.4, THEN remove following jumpers:
IF jumpers were installed in 3.3.4, THEN remove the following jumpers:
JUMPER PANEL 1C71-K10A Contact 2 to 1C71-K12E Contact 4 1H11-P609C 1C71-K10C Contact 2 to 1C71-K12G Contact 4 1H11-P609A 1C71-K10BContact2 to 1C71-K12FContact4 1H11-P611C 1C71-K10D Contact 2 to 1C71-K12H Contact 4 1H11-P611A ATTACHMENT PAGE:
50F 7 Verify Verify Verify Verify 4.2 Confirm all Rod Scram Switches are in the UP (normal) position at 1 H11-P61 O.
Verify OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4
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SOUTHERN NUCLEAR PLANT E.1. HATCH PAGE 19 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 ATTACHMENT..1.
TITLE: SYSTEM RESTORATION 4.0 INDIVIDUAL ROD SCRAM 4.1 IF jumpers were installed in 3.5.4, THEN remove following jumpers:
IF jumpers were installed in 3.3.4, THEN remove the following jumpers:
JUMPER PANEL 1 C71-K1 OA Contact 2 to 1 C71-K12E Contact 4 1 H11-P609C 1 C71-K 1 OC Contact 2 to 1 C71-K 12G Contact 4 1 H 11-P609A 1C71-K10B Contact 2 to 1C71-K12F Contact 4 1H11-P611C 1C71-K10D Contact 2 to 1C71-K12H Contact 4 1H11-P611A ATTACHMENT PAGE:
50F 7 Verify Verify Verify Verify 4.2 Confirm all Rod Scram Switches are in the UP (normal) position at 1H11-P610.
Verify OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4
SOUTHERN NUCLEAR PLANT E.!. HATCH PAGE 20 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 ATTACHMENT...1 TITLE: SYSTEM RESTORATION 5.0 SCRAM AIR HEADER ATTACHMENT PAGE:
6 OF 7 5.1 CLOSE 1C11-R013-TV1, Pressure Instrumentation Vent Valve, at 130RAR03 5.2
!E the line was capped, THEN install cap down stream of 1C11-R013-TV1, Pressure Instrumentation Vent Valve.
Verify Verify 5.3 Open Scram Air Header Isolation Valve 1 C11-F095, at location 130RAR03.
Verify 6.0 DRIVING CONTROL RODS 6.1 Stop a CRD pump.
Verify 6.2 Adjust 1C11-R600, CRD Flow Control, as required and place in AUTO.
Verify 6.3 OPEN 1 C11-F005, Return To Vessel Flow Control.
Verify 6.4 Place Reactor Mode switch to SHUTDOWN.
Verify 6.5 Place Rod Worth Minimizer bypass switch to OPERATE Verify OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4
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SOUTHERN NUCLEAR PLANT E.!. HATCH PAGE 20 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-103-1 4.2 ATTACHMENT..1 TITLE: SYSTEM RESTORATION 5.0 SCRAM AIR HEADER ATTACHMENT PAGE:
6 OF 7 5.1 CLOSE 1 C11-R013-TV1, Pressure Instrumentation Vent Valve, at 130RAR03 Verify 5.2 IF the line was capped, THEN install cap down stream of 1 C11-R013-TV1, Pressure Instrumentation Vent Valve.
Verify 5.3 Open Scram Air Header Isolation Valve 1 C11-F095, at location 130RAR03.
Verify 6.0 DRIVING CONTROL RODS 6.1 Stop a CRD pump.
Verify 6.2 Adjust 1C11-R600, CRD Flow Control, as required and place in AUTO.
Verify 6.3 OPEN 1 C11-F005, Return To Vessel Flow Control.
Verify 6.4 Place Reactor Mode switch to SHUTDOWN.
Verify 6.5 Place Rod Worth Minimizer bypass switch to OPERATE Verify OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4
SOUTHERN NUCLEAR PLANT E.1. HATCH PAGE 21 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 ATTACHMENT..1 TITLE: SYSTEM RESTORATION 7.0 CRD COOLING WATER 7.1 Adjust 1C11-R607, Press Control Vlv F127 controller, as required and PLACE in AUTO.
ATTACHMENT PAGE:
70F 7 Verify 7.2 Adjust CRD Flow Contro11C11-R600 as required and PLACE in AUTO.
7.3 OPEN 1 C11-F005, Return To Vessel Flow Control.
7.4 Throttle 1 C11-F003 to obtain CRD Drive Water dp at 260 psig as indicated on 1 C11-R602.
8.0 VENTING WITHDRAW PORT 8.1 Close 1 C11-F1 02 for each control rod that was vented 8.2 Remove all hoses.
8.3 Install all plugs OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4 Verify Verify Verify Verify Verify Verify
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SOUTHERN NUCLEAR PLANT E.1. HATCH PAGE 21 OF 22 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
CONTROL ROD INSERTION METHODS 31 EO-EOP-1 03-1 4.2 ATTACHMENT..1 TITLE: SYSTEM RESTORATION 7.0 CRD COOLING WATER 7.1 Adjust 1 C11-R607, Press Control Vlv F127 controller, as required and PLACE in AUTO.
ATTACHMENT PAGE:
7 OF 7 Verify 7.2 Adjust CRD Flow Control 1 C11-R600 as required and PLACE in AUTO.
7.3 OPEN 1 C11-F005, Return To Vessel Flow Control.
7.4 Throttle 1 C 11-F003 to obtain CRD Drive Water dp at 260 psig as indicated on 1 C11-R602.
8.0 VENTING WITHDRAW PORT 8.1 Close 1 C11-F1 02 for each control rod that was vented 8.2 Remove all hoses.
8.3 Install all plugs OPS-0973 Rev N/A G16.30 MGR-0009 Rev 4 Verify Verify Verify Verify Verify Verify
SOUTHERN NUCLEAR PLANT E.I. HATCH I
DOCUMENT TITLE:
I DOCUMENT NUMBER:
CONTROL ROD INSERTION METHODS 31EO-EOP-103-1 ATTACHMENT..f.
TITLE: THAXTON PIPE STOPPER DIAGRAM SunaN MGR-0009 Rev 4 PAGE 22 OF 22 VERSION NO:
4.2 ATTACHMENT PAGE:
1 OF 1
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SOUTHERN NUCLEAR PLANT E.I. HATCH I
DOCUMENT TITLE:
I DOCUMENT NUMBER:
CONTROL ROD INSERTION METHODS 31EO-EOP-103-1 ATTACHMENT -2.
TITLE: THAXTON PIPE STOPPER DIAGRAM 10 tc.U*F\\O:L SunaN MGR-0009 Rev 4 PAGE 22 OF 22 VERSION NO:
4.2 ATTACHMENT PAGE:
1 OF 1
DRAFT Southern Nuclear E. I. Hatch uclear Plant R. A. BELCHER Operations Training JPM PLA T2 Energy to Serve Your World SM
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DRAFT Southern Nuclear E. I. Hatch Nuclear Plant TITLE Operations Training JPM PLANT 2 Locally Start IB psw Pump Breaker Without Control Power AUTHOR MEDIA NUMBER R. A. BELCHER LR-1P-27.65-13 RECOMMENDED BY APPROVED BY TIME 18.0 Minutes DATE Energy to Serve Your World sM
I SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERA TIONS TRAINING Media Number:
LR-JP-27.65
<~~\\v.;~~.* >k// I******** *******.;i <**.*.... ;ri:..2~ ********.**~~ri... _j __ i.* *. ~*>*.....................>
A.~th()r'$
~llJ.ly'S 1<.
..... li<
~l~'
.....*...~~I'~ **.
.*... *i.....>.*
- "'i:-~*7~*.*** *
.. *.*.*.*;*<x*.. *...........
Witials*
Initials i
Modified so operator attempts to start pump locally with the control switch. The pump fails to start due to loss of control power. The operator then uses of the procedure to manually close in the breaker.
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I SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Page 1 of 1 Program/Course Code:
OPERATIONS TRAINING Media Number:
LR-JP-27.65 Rev. No.
Date Reason for Revision Author's Supv's Initials Initials Modified so operator attempts to start pump locally with the control switch. The pump fails to start due to loss of control power. The operator then uses of the procedure to manually close in the breaker.
LR-JP-27.65-13 Page 1 of 5 UNIT 1 (X)
UNIT 2 0
Locally Start IB PSW Pump Breaker Without Control Power LR-JP-27.65-13 The task is complete when from outside the Control Room, during a Control Room evacuation, a PSW Pump has been started without control power.
027.065
_ -' __." _",,',-_'_ 0,' '-, ',-,-,
--,0
_~
pjJ.JF:@TiV$~E~: 027.065.B PLANT HATCH JTA IMPORTANCE RATING:
RO 3.86 SRO 3.86 KIA CATALOG NUMBER:
KIA CATALOG JTA IMPORTANCE RATING:
RO SRO OPERA TOR APPLICABILITY:
G
.* ** *. E.*.*
.* **.N.*.<E./RA.***.******.'L..... REFEJlE. N~.E.S (current version APPROXIMATE COMPLETION TIME:
18.0 Minutes SIMULATOR SETUP:
N/A
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LR-JP-27.65-13 Page 1 of 5 UNIT t (X)
UNIT 2 0
TASK TITLE:
JPMNUMBER:
TASK STANDARD:
TASK NUMBER:
Locally Start IB PSW Pump Breaker Without Control Power LR-JP-27.65-13 The task is complete when from outside the Control Room, during a Control Room evacuation, a PSW Pump has been started without control power.
027.065 OBJECTIVE NUMBER: 027.065.B PLANT HATCH JTA IMPORTANCE RATING:
RO 3.86 SRO 3.86 KIA CATALOG NUMBER:
KIA CATALOG JTA IMPORTANCE RATING:
RO SRO OPERA TOR APPLICABILITY:
I GENERAL
REFERENCES:
Unit t 31RS-OPS-00l-1 (current version)
I REQUIRED MATERIALS:
Unitt 31RS-OPS-00l-1 (current version)
Breaker Charging/Maintenance Handle APPROXIMA TE COMPLETION TIME:
18.0 Minutes SIMULATOR SETUP:
N/A
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UNITl READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The Control Room has been evacuated.
- 2.
A Plant Shutdown is in progress per 31RS-OPS-OOl-l
- 3.
Off-Site Power is supplying all plant busses.
INITIATING CUES:
Locally start IB PSW pump per 31RS-OPS-OOl-1.
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UNITl READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The Control Room has been evacuated.
- 2.
A Plant Shutdown is in progress per 3IRS-OPS-OOI-I
- 3.
Off-Site Power is supplying all plant busses.
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INITIATING CUES:
Locally start IB PSW pump per 3IRS-OPS-OOl-1.
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- 1.
- 2.
- 3.
- 4.
- 5.
For INITIAL Operator Programs:
LR-JP-27.65-13 Page 3 of5 c,'*SitTll1NSAT*******
i(CO~ENT8*'*
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRmCAL STEPS must be completed for Satisfactory Performance.
Operator obtains the procedure and Operator obtains 31RS-OPS-OO1-selects the proper Attachment.
1 and selects Attachment 9.
Start the 1P41-C001B pump In 4160V switchgear room 1G, at panel1H21-P175, the operator places 1C82-S2B, transfer switch, to the EMER position.
The operator places the 1P41-COOlB pump control switch to START.
START TIME: ___ _
SAT/UNSAT SAT/UNSAT SAT I UNSAT PROMPT:
When the control switch is placed inform the operator that there was no sound heard of a breaker closing in.
PROMPT:
IF the operator checks breaker light indication, THEN inform the operator that both the red and green lights are off.
PROMPT:
IF the operator checks control power breaker, THEN inform the operator that control power breaker is tripped and can not be reset.
Identifies the requirement to perform Operator has determined SAT/UNSAT. is required to start a pump.
OPEN breaker cubicle door.
Operator opens 1B PSW pumps SAT I UNSAT cubicle door at 1R22-S007 Fr. 4.
TRIP the 30A control power breaker Inside the cubicle, the operator SAT I UNSAT in the associated breaker cubicle.
has opened/verified tripped the 30A control power breaker.
PROMPT:
IF addressed by the Operator, as the Shift Supervisor, INFORM the operator that Control Power is NOT AVAILABLE.
PROMPT:
IF the operator looks at spring charge status, INFORM the operator that the springs are DISCHARGED.
(** Indicates critical step)
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(
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~TEP
- 1.
- 2.
- 3.
- 4.
- 5.
PERFO~NCESTEP STANDARD For INITIAL Operator Programs:
LR-IP-27.65-13 Page 3 of 5 SATIUNSAT (COMMENTS For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRmCAL STEPS must be completed for Satisfactory Performance.
Operator obtains the procedure and Operator obtains 31 RS-OPS-OO 1-selects the proper Attachment.
1 and selects Attachment 9.
Start the 1P41-C001B pump In 4160V switchgear room 1G, at panel 1H21-P175, the operator places 1C82-S2B, transfer switch, to the EMER position.
The operator places the 1P41-C001B pump control switch to START.
START TIME: ___ _
SAT/UNSAT SAT/UNSAT SAT/UNSAT PROMPT:
When the control switch is placed inform the operator that there was no sound heard of a breaker closing in.
PROMPT:
IF the operator checks breaker light indication, THEN inform the operator that both the red and green lights are off.
PROMPT:
IF the operator checks control power breaker, THEN inform the operator that control power breaker is tripped and can not be reset.
Identifies the requirement to perform Operator has determined SAT/UNSAT. is required to start a pump.
OPEN breaker cubicle door.
Operator opens 1B PSW pumps SAT/UNSAT cubicle door at 1R22-S007 Fr. 4.
TRIP the 30A control power breaker Inside the cubicle, the operator SAT/UNSAT in the associated breaker cubicle.
has opened/verified tripped the 30A control power breaker.
PROMPT:
IF addressed by the Operator, as the Shift Supervisor, INFORM the operator that Control Power is NOT A V AILABLE.
PROMPT:
IF the operator looks at spring charge status, INFORM the operator that the springs are DISCHARGED.
(** Indicates critical step)
LR-IP-27.65-13 Page 4 of5 NOTE: An indicating window on the bottom left side of the breaker shows whether or not the breaker is charged.
RECLOSE the 30A control power breaker.
CLOSE the breaker cubicle door.
- 12. Re-enter Attachment 9.
At the the operator has PLACED the Spring ChargeIMaintenance IS 111 the slot in the manual ratchet lever located to the left of the "UFr TO TRIP" plunger.
At the cubicle, the operator has CHARGED the breaker closing spring. The handle moves and a "click" is heard.
At the cubicle, operator has REMOVED the Spring Charge/Maintenance Handle.
At the cubicle, the operator has PUSHED UP the plunger marked "LIFT'TO CLOSE."
At the cubicle, the operator has RECLOSED the 30A control power breaker.
At the cubicle, the operator has CLOSED the breaker cubicle door.
Operator returns to Attachment 9.
IUNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT/UNSAT SAT I UNSAT NOTE:
With the 30 amp control power breaker open, the breaker indicating lights and meter will not function.
(** Indicates critical step)
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,TEP PERFO~lANCESTEP STANDARD LR-JP-27.65-13 Page 4 of 5 SATIUNSAT (COMMENTS)
NOTE: An indicating window on the bottom left side of the breaker shows whether or not the breaker is charged.
- 6. Place Spring Charge/Maintenance At the cubicle, the operator has SAT/UNSAT Handle into the slot in the manual PLACED the Spring ratchet lever (located to the left of the ChargelMaintenance Handle is in "LIFT TO TRIP" plunger).
the slot in the manual ratchet lever located to the left of the "LIFT TO TRIP" plunger.
- 7. CHARGE the breaker closing spring At the cubicle, the operator has SAT/UNSAT until the handle moves freely and a CHARGED the breaker closing "click" is heard.
spring. The handle moves freely and a "click" is heard.
- 8. REMOVE the Spring At the cubicle, the operator has SAT I UNSAT Charge/Maintenance Handle.
REMOVED the Spring Charge/Maintenance Handle.
- 9. PUSH UP on the plunger marked At the cubicle, the operator has SAT I UNSAT "LIFT TO CLOSE."
PUSHED UP the plunger marked "LIFT TO CLOSE."
- 10. RECLOSE the 30A control power At the cubicle, the operator has SAT/UNSAT breaker.
RECLOSED the 30A control power breaker.
- 11. CLOSE the breaker cubicle door.
At the cubicle, the operator has SAT I UNSAT CLOSED the breaker cubicle door.
- 12. Re-enter Attachment 9.
Operator returns to Attachment 9.
SAT/UNSAT NOTE:
With the 30 amp control power breaker open, the breaker indicating lights and meter will not function.
(** Indicates critical step)
PROMPT:
PROMPT:
LR-JP-27.65-13 Page 5 of5 WHEN the operator addresses throttling PSW flow, INFORM the operator that another operator has been assigned to throttle flow.
IF the operator addresses system restoration, INFORM the operator that restoration is not required at this time.
END TIME: ___ _
NOTE: The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
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,TEP PROMPT:
PROMPT:
PERFO~NCESTEP STANDARD LR-JP-27.65-13 Page 5 of 5 SATIUNSAT (COMMENTS*
WHEN the operator addresses throttling PSW flow, INFORM the operator that another operator has been assigned to throttle flow.
IF the operator addresses system restoration, INFORM the operator that restoration is not required at this time.
END TIME: ___ _
NOTE: The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
(** Indicates critical step)
UNITl READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The Control Room has been evacuated.
- 2.
A Plant Shutdown is in progress per 3IRS-OPS-OOI-l
- 3.
Off-Site Power is supplying all plant busses.
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INITIATING CUES:
Locally start IB PSW pump per 31RS-OPS-OOl-1.
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UNITl READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The Control Room has been evacuated.
- 2.
A Plant Shutdown is in progress per 31RS-OPS-OOl-l
- 3.
Off-Site Power is supplying all plant busses.
(
INITIATING CUES:
Locally start IB PSW pump per 31RS-OPS-OOl-1.
SOUTHERN NUCLEAR DOCUMENT TYPE:
PAGE PLANT E. I. HATCH REMOTE SHUTDOWN PROCEDURE 1 OF 48 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 5.14 EXPIRATION APPROVALS:
EFFECTIVE DATE:
DEPARTMENT MGR G. L. Johnson DATE 06-05-98 DATE:
N/A SSM / PM N/A DATE N/A 4-27-09 1.0 CONDITIONS Under certain conditions the Control Room may be uninhabitable. This procedure describes actions necessary to bring the reactor to a shutdown condition from a steady state normal operating condition by manipulating plant controls outside of the Main Control Room.
TABLE OF CONTENTS Section 2.0 AUTOMATIC ACTIONS...................................................................................................... 1 3.0 IMMEDIATE OPERATOR ACTIONS................................................................................... 2 4.0 SUBSEQUENT OPERATOR ACTIONS.............................................................................. 3 Attachments 1
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER.............................. 11 2
RCIC CONTINUED OPERATION FROM THE REMOTE SHUTDOWN PANEL............... 18 3
RCIC OPERATION FROM REMOTE SHUTDOWN PANEL............................................. 21 4
RCIC SHUTDOWN FROM REMOTE SHUTDOWN PANEL............................................. 25 5
MAXIMIZING CRD SYSTEM FLOW................................................................................. 27 6
LPCI OPERATION FROM THE REMOTE SHUTDOWN PANEL...................................... 31 7
TORUS COOLING FROM THE REMOTE SHUTDOWN PANEL...................................... 35 8
SHUTDOWN COOLING FROM THE REMOTE SHUTDOWN PANEL.............................. 39 9
PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM...................................... 47 2.0 AUTOMATIC ACTIONS None MGR-0002 Ver. 8.1
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SOUTHERN NUCLEAR DOCUMENT TYPE:
PAGE PLANT E. I. HATCH REMOTE SHUTDOWN PROCEDURE 1 OF 48 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 5.14 EXPIRATION APPROVALS:
EFFECTIVE DATE:
DEPARTMENT MGR G. L. Johnson DATE 06-05-98 DATE:
N/A SSM / PM N/A DATE N/A 4-27-09 1.0 CONDITIONS Under certain conditions the Control Room may be uninhabitable. This procedure describes actions necessary to bring the reactor to a shutdown condition from a steady state normal operating condition by manipulating plant controls outside of the Main Control Room.
TABLE OF CONTENTS Section 2.0 AUTOMATIC ACTIONS...................................................................................................... 1 3.0 IMMEDIATE OPERATOR ACTIONS................................................................................... 2 4.0 SUBSEQUENT OPERATOR ACTIONS.............................................................................. 3 Attachments 1
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER.............................. 11 2
RCIC CONTINUED OPERATION FROM THE REMOTE SHUTDOWN PANEL............... 18 3
RCIC OPERATION FROM REMOTE SHUTDOWN PANEL............................................. 21 4
RCIC SHUTDOWN FROM REMOTE SHUTDOWN PANEL............................................. 25 5
MAXIMIZING CRD SYSTEM FLOW................................................................................. 27 6
LPCI OPERATION FROM THE REMOTE SHUTDOWN PANEL...................................... 31 7
TORUS COOLING FROM THE REMOTE SHUTDOWN PANEL...................................... 35 8
SHUTDOWN COOLING FROM THE REMOTE SHUTDOWN PANEL.............................. 39 9
PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM...................................... 47 2.0 AUTOMATIC ACTIONS None MGR-0002 Ver. 8.1
SNC PLANT E. I. HATCH I Pg 47 of 48 DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:
5.6 ATTACHMENT JL TITLE:
PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM Placing the Remote Shutdown Panel Transfer Switches for PSW in Emergency has the following effects on PSW system operation:
- 1.
Auto start of the 1 B PSW pump on low system header pressure (85 PSIG) is
- 2.
defeated.
The subsequent auto start of the 1 B PSW pump after tripping on receipt of a LOSP OR LOCA signal is defeated.
- 3.
All PSW trips are still valid:
CAUTION 3.1 Overcurrentlground fault 3.2 LOSP Load Shed 3.3 LOCA Load Shed WHEN DG is carrying respective bus following a LOSP AND THEN a LOCA is received.
DIESEL GENERATOR LOADING MUST NOT EXCEED THE FOLLOWING RATINGS FOLLOWING A LOSS OF OFFSITE POWER TO AVOID DIESEL OVERLOAD. AMPERAGE INDICATIONS ARE LOCATED ON PANEL R43-P001 IN EACH DIESEL GENERATOR ROOM.
DIESEL 1A 1B 1C RATINGS (AMPERES)
CONTINUOUS 430 430 430 7 DAY (168 HOURY 490 490 490 5.14 1 of 2
- THE HIGHER 7 DAY RATING IS BASED UPON A YEARLY ACCUMULATION OF ENGINE OPERATING HOURS ABOVE THE CONTINUOUS RATING. A TOTAL OF 168 HOURS PER YEAR WITH A LOAD OF 430 TO 490 AMPERES IS ALLOWED.
MGR-0009 Ver. 4
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SNC PLANT E. I. HATCH I Pg 47 of 48 DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:
5.6 ATTACHMENT JL TITLE:
PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM Placing the Remote Shutdown Panel Transfer Switches for PSW in Emergency has the following effects on PSW system operation:
- 1.
Auto start of the 1 B PSW pump on low system header pressure (85 PSIG) is
- 2.
defeated.
The subsequent auto start of the 1 B PSW pump after tripping on receipt of a LOSP OR LOCA signal is defeated.
- 3.
All PSW trips are still valid:
CAUTION 3.1 Overcurrentlground fault 3.2 LOSP Load Shed 3.3 LOCA Load Shed WHEN DG is carrying respective bus following a LOSP AND THEN a LOCA is received.
DIESEL GENERATOR LOADING MUST NOT EXCEED THE FOLLOWING RATINGS FOLLOWING A LOSS OF OFFSITE POWER TO AVOID DIESEL OVERLOAD. AMPERAGE INDICATIONS ARE LOCATED ON PANEL R43-P001 IN EACH DIESEL GENERATOR ROOM.
DIESEL 1A 1B 1C RATINGS (AMPERES)
CONTINUOUS 430 430 430 7 DAY (168 HOUR)*
490 490 490 5.14 1 of 2
- THE HIGHER 7 DAY RATING IS BASED UPON A YEARLY ACCUMULATION OF ENGINE OPERATING HOURS ABOVE THE CONTINUOUS RATING. A TOTAL OF 168 HOURS PER YEAR WITH A LOAD OF 430 TO 490 AMPERES IS ALLOWED.
MGR-0009 Ver. 4
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SNC PLANT E. I. HATCH I Pg 48 of 48 DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:
5.6 ATTACHMENT JL TITLE:
PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM
.. BEFORE STARTING A PSW PUMP ON THE DIESEL GENERATOR, DIESEL LOAD MUST BE BELOW 390 AMPS. REFER TO 34S0-R43-001-1 TO REDUCE DIESEL LOADS IF REQUIRED.
CAUTIONS
.. THE AMPERE VALUES ARE BASED UPON AN ASSUMED TOTAL POWER FACTOR OF 0.91. LOADING OF THE DIESEL GENERATORS ABOVE 430 AMPERES ON THE LOCAL INDICATORS MUST BE ACCOMPANIED BY CLOSE MONITORING OF OTHER DIESEL PARAMETERS FOR SIGNS OF OVERLOADING.
1.0 Start one PSW pump in a division as follows:
1.1 To start the 1 P41-C001 B pump:
1.1.1 In 4160V switchgear room 1 G, at panel 1 H21-P175, place 1 C82-S2B, transfer switch, to the EMER position.
1.1.2 START the pump by placing the 1P41-C001B control switch to START.
1.2 To start pump 1P41-C001A, 1P41-C001C, OR 1P41-C001D, manually close the applicable breaker per Attachment 1.
CAUTION PSW PUMP 1P41-C001A 1P41-C001C 1P41-C001D BREAKER LOCATION 1 R22-S005 Fr. 3 1 R22-S006 Fr. 4 1 R22-S006 Fr. 2 IF RIVER LEVEL IS GREATER THAN 61.2 FEET, LIMIT EACH PSW PUMP FLOW TO 8500 GPM.
IF RIVER LEVEL IS LESS THAN 61.2 FEET, EACH PSW PUMP FLOW MUST BE LESS THAN 7000 GPM.
2.0 THROTTLE 1P41-F302B (1P41-F302A, 1P41-F302C, 1P41-F302D), PSW pump 1 B (1 A, 1 C, 1 D) Discharge valve, to establish a flow greater than 3000 GPM as indicated on 1 P41-N504 (N503, N505, N506), Discharge Flow Indicator, (intake structure valve pit).
3.0 Start additional PSW pumps as required and as Diesel Generator capacity permits.
MGR-0009 Ver. 4 5.14 2 of 2
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SNC PLANT E. I. HATCHL Pg 48 of 48 DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:
5.6 ATTACHMENT JL TITLE:
PSW PUMP OPERATION FROM OUTSIDE CONTROL ROOM
- BEFORE STARTING A PSW PUMP ON THE DIESEL GENERATOR, DIESEL LOAD MUST BE BELOW 390 AMPS. REFER TO 34S0-R43-001-1 TO REDUCE DIESEL LOADS IF REQUIRED.
CAUTIONS
- THE AMPERE VALUES ARE BASED UPON AN ASSUMED TOTAL POWER FACTOR OF 0.91. LOADING OF THE DIESEL GENERATORS ABOVE 430 AMPERES ON THE LOCAL INDICATORS MUST BE ACCOMPANIED BY CLOSE MONITORING OF OTHER DIESEL PARAMETERS FOR SIGNS OF OVERLOADING.
1.0 Start one PSW pump in a division as follows:
1.1 To start the 1 P41-C001 B pump:
1.1.1 In 4160V switchgear room 1 G, at panel 1 H21-P175, place 1 C82-S2B, transfer switch, to the EMER position.
1.1.2 START the pump by placing the 1 P41-C001 B control switch to START.
1.2 To start pump 1P41-C001A, 1P41-C001C, OR 1P41-C001D, manually close the applicable breaker per Attachment 1.
PSW PUMP 1P41-C001A 1P41-C001C 1 P41-C001 D BREAKER LOCATION 1 R22-S005 Fr. 3 1 R22-S006 Fr. 4 1 R22-S006 Fr. 2 CAUTION IF RIVER LEVEL IS GREATER THAN 61.2 FEET, LIMIT EACH PSW PUMP FLOW TO 8500 GPM.
IF RIVER LEVEL IS LESS THAN 61.2 FEET, EACH PSW PUMP FLOW MUST BE LESS THAN 7000 GPM.
2.0 THROTTLE 1 P41-F302B (1 P41-F302A, 1 P41-F302C, 1 P41-F302D), PSW pump 1 B (1A, 1 C, 1 D) Discharge valve, to establish a flow greater than 3000 GPM as indicated on 1 P41-N504 (N503, N505, N506), Discharge Flow Indicator, (intake structure valve pit).
3.0 Start additional PSW pumps as required and as Diesel Generator capacity permits.
MGR-0009 Ver. 4 5.14 2 of 2
SNC PLANT E. I. HATCH I DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER NOTE The following provides guidance on manually closing various types of air and vacuum circuit breakers without the presence of control power.
Pg 11 of 48 Version No:
5.14 Att. Pg.
1 of 7 WHEN WORKING WITH ENERGIZED ELECTRICAL EQUIPMENT FOLLOW CAUTION THE ELECTRICAL SAFETY PROCEDURE OUTLINED IN SOUTHERN NUCLEAR SAFETY MANUAL.
1.0 I F the breaker is 4160 VAC, THEN take the following applicable action:
1.1 CLOSE a 4160 VAC breaker to energize the load, by performing the following steps:
1.1.1 OPEN Breaker Cubicle Door.
1.1.2 TRIP the 30A control breaker in the associated breaker cubicle AND CLOSE the breaker as follows:
NOTE IF it can be confirmed that the spring is charged, go directly to step 1.1.3.
1.1.2.1 1.1.2.2 1.1.2.3 Place the end of the Spring Charge/Maintenance Handle (stored adjacent to the switchgear) into the slot in the manual ratchet lever, located to the left of the "LIFT TO TRIP" plunger. For the new DHP-VR vacuum breakers this slot is located just to the right of the "Spring Charged/Discharged" indicator.
Charge the spring with several downward pumping movements of the handle UNTIL the handle suddenly moves freely AND a "click" is heard.
Remove the Spring Charge Maintenance handle AND return to storage position.
MGR-0009 Ver. 4
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SNC PLANT E. I. HATCH I DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER NOTE The following provides guidance on manually closing various types of air and vacuum circuit breakers without the presence of control power.
Pg 11 of 48 Version No:
5.14 Att. Pg.
1 of 7 WHEN WORKING WITH ENERGIZED ELECTRICAL EQUIPMENT FOLLOW CAUTION THE ELECTRICAL SAFETY PROCEDURE OUTLINED IN SOUTHERN NUCLEAR SAFETY MANUAL.
1.0 I F the breaker is 4160 VAC, THEN take the following applicable action:
1.1 CLOSE a 4160 VAC breaker to energize the load, by performing the following steps:
1.1.1 OPEN Breaker Cubicle Door.
1.1.2 TRIP the 30A control breaker in the associated breaker cubicle AND CLOSE the breaker as follows:
NOTE IF it can be confirmed that the spring is charged, go directly to step 1.1.3.
1.1.2.1 1.1.2.2 1.1.2.3 Place the end of the Spring Charge/Maintenance Handle (stored adjacent to the switchgear) into the slot in the manual ratchet lever, located to the left of the "LIFT TO TRIP" plunger. For the new DHP-VR vacuum breakers this slot is located just to the right of the "Spring ChargedlDischarged" indicator.
Charge the spring with several downward pumping movements of the handle UNTIL the handle suddenly moves freely AND a "click" is heard.
Remove the Spring Charge Maintenance handle AND return to storage position.
MGR-0009 Ver. 4
SNC PLANT E. I. HATCH I DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER Pg 12 of 48 Version No:
5.14 Att. Pg.
2 of 7 The following breakers in Bus 1 F are equipped with control power undervoltage trip devices:
Frame 2 - Plant Service Water Pump 1 D Frame 3 - RHR Service Water Pump 1 C Frame 4 - Plant Service Water Pump 1C Frame 8 - CRD Pump 1 B Frame 9 - RHR Pump 1C These devices will trip their associated breaker upon loss of 125 VDC control power to the breaker. The trip will be mechanically maintained UNTIL control power is restored.
Step 1.1.3.1 MUST be performed before manually closing these breakers.
Steps 1.1.3.1 AND 1.1.3.2 only apply to the Bus 1 F breakers listed above.
Disabling of the undervoltage trip linkage on Frame 7 (RHR Pump 1 D) is NOT necessary due to its control power transfer scheme.
1.1.3 IF the 4160V breaker is one of bus 1 F breakers listed in the above note, THEN perform the following:
NOTE The top nut on this linkage is factory adjusted AND must NOT be disturbed WHEN removing the bottom nut.
1.1.3.1 MGR-0009 Ver. 4 For the old style Type DHP Air Circuit Breakers DISABLE the control power undervoltage trip device by removing the bottom nut and disengage the tripping linkage as shown on Figure 1.
OR For the new style Type VR Vacuum Breakers disable the control power undervoltage trip device by removing the front cover, removing the screw and nut and removing the linkage as shown on Figure 2.
SNC PLANT E. I. HATCH I Pg 12 of 48 DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:
5.14 ATTACHMENT _1 TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER The following breakers in Bus 1 F are equipped with control power undervoltage trip devices:
Frame 2 - Plant Service Water Pump 1 D Frame 3 - RHR Service Water Pump 1C Frame 4 - Plant Service Water Pump 1C Frame 8 - CRD Pump 1 B Frame 9 - RHR Pump 1 C These devices will trip their associated breaker upon loss of 125 VDC control power to the breaker. The trip will be mechanically maintained UNTIL control power is restored.
Step 1.1.3.1 MUST be performed before manually closing these breakers.
Steps 1.1.3.1 AND 1.1.3.2 only apply to the Bus 1 F breakers listed above.
Disabling of the undervoltage trip linkage on Frame 7 (RHR Pump 1 D) is NOT necessary due to its control power transfer scheme.
1.1.3 IF the 4160V breaker is one of bus 1 F breakers listed in the above note, THEN perform the following:
NOTE The top nut on this linkage is factory adjusted AND must NOT be disturbed WHEN removing the bottom nut.
1.1.3.1 MGR-0009 Ver. 4 For the old style Type DHP Air Circuit Breakers DISABLE the control power undervoltage trip device by removing the bottom nut and disengage the tripping linkage as shown on Figure 1.
OR For the new style Type VR Vacuum Breakers disable the control power undervoltage trip device by removing the front cover, removing the screw and nut and removing the linkage as shown on Figure 2.
Att. Pg.
2 of 7
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SNC PLANT E. I. HATCH I P~ 13 of 48 DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:
5.14 ATTACHMENT J.-
TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER Att. Pg.
3 of 7 DO NOT DISTURB POSITION OF TOP NUT MGR-0009 Ver. 4 FIGURE 1 REMOVE BOTTOM NUT TO DISABLE UNDER VOLTAGE TRIP DEVICE 4160V BREAKER CUBICLE LOSS OF DC BREAKER TRIP DEVICE
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SNC PLANT E. I. HATCH I DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER FIGURE 1 Pg 13 of 48 Version No:
5.14 Att. Pg.
3 of 7 4160V DO NOT DISTURB POSITION OF TOP NUT MGR-0009 Ver. 4 REMOVE BOTTOM NUT TO DISABLE UNDER VOLTAGE TRIP DEVICE BREAKER CUBICLE o
LOSS OF DC BREAKER TRIP DEVICE
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I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT J.-
TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER STEP 2 Slide link up & remove.
STEP 1 Remove screw & nut.
FIGURE 2 Pg 14 of 48 Version No:
5.14 Att. Pg.
4 of 7 LOSS OF DC BREAKER TRIP DEVICE FOR NEW VR VACUUM BREAKER MGR-0009 Ver. 4
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SNC PLANT E. I. HATCH I DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER STEP 2 Slide link up & remove.
STEP 1 Remove screw & nut.
FIGURE 2 Pg 14 of 48 Version No:
5.14 Att. Pg.
40f7 LOSS OF DC BREAKER TRIP DEVICE FOR NEW VR VACUUM BREAKER MGR-0009 Ver. 4
SNC PLANT E. I. HATCH I Pg 15 of 48 DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT...L TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER NOTE Due to the possibility of initiating a trip, the nuts must NOT be re-installed WHILE the breakers are supplying power to their respective loads.
1.1.3.2 Upon restoration of control power, AND IF plant conditions permit, Re-install the nut removed in step 1.1.3.1 OR Re-install the linkage, screw and nut removed in step 1.1.3.1 BEFORE STARTING 4160V LOADS ON THE DIESEL GENERATOR, DIESEL LOAD MUST BE BELOW THE MAXIMUM VALUE INDICATED.
MAX DIESEL CAUTION:
LOAD LOAD FOR STARTING 310 AMPS 310AMPS RHR SERVICE WATER PUMP CORE SPRAY PUMP RHR PUMP PSW PUMP 340 AMPS 390 AMPS 1.1.4 Confirm Diesel Generator AMP reading is BELOW the maximum value in the above CAUTION, PRIOR to closing any listed 4160V breaker.
1.1.5 IF a standard DHP Air Circuit breaker is installed in this cubicle, Manually close the 4 KV pump breaker by pushing up on the plunger marked "LI FT TO CLOSE".
OR IF a new DHP-VR vacuum breaker is installed in this cubicle, DEPRESS the button marked "Push to Close".
1.1.6 RE-CLOSE the 30A control breaker in the associated cubicle.
1.1.6.1 Go to step 1.2, IF the 4160 VAC breaker opens.
1.1.7 CLOSE the breaker cubicle door.
MGR-0009 Ver. 4 Version No:
5.14 Att. Pg.
5 of 7
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I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER NOTE Due to the possibility of initiating a trip, the nuts must NOT be re-installed WHILE the breakers are supplying power to their respective loads.
1.1.3.2 Upon restoration of control power, AND IF plant conditions permit, Re-install the nut removed in step 1.1.3.1 OR Re-install the linkage, screw and nut removed in step 1.1.3.1 BEFORE STARTING 4160V LOADS ON THE DIESEL GENERATOR, DIESEL LOAD MUST BE BELOW THE MAXIMUM VALUE INDICATED.
MAX DIESEL CAUTION:
LOAD LOAD FOR STARTING 310 AMPS RHR SERVICE WATER PUMP CORE SPRAY PUMP RHR PUMP PSW PUMP 310 AMPS 340 AMPS 390 AMPS 1.1.4 Confirm Diesel Generator AMP reading is BELOW the maximum value in the above CAUTION, PRIOR to closing any listed 4160V breaker.
1.1.5 IF a standard DHP Air Circuit breaker is installed in this cubicle, Manually close the 4 KV pump breaker by pushing up on the plunger marked "LIFT TO CLOSE".
OR IF a new DHP-VR vacuum breaker is installed in this cubicle, DEPRESS the button marked "Push to Close".
1.1.6 RE-CLOSE the 30A control breaker in the associated cubicle.
1.1.6.1 Go to step 1.2, IF the 4160 VAC breaker opens.
1.1.7 CLOSE the breaker cubicle door.
MGR-0009 Ver. 4 Version No:
5.14 Att. Pg.
5 of 7
SNC PLANT E. I. HATCH I DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER Pg 16 of 48 Version No:
5.14 Att. Pg.
6 of 7 STEP 1.2 BYPASSES ALL TRIPS AND PROTECTIVE FUNCTIONS OF THE CAUTION BREAKER BY ALLOWING THE CONTROL CIRCUIT TO REMAIN DE-ENERGIZED AFTER THE BREAKER IS CLOSED.
1.2 IF the breaker has tripped AND must be reclosed regardless of possible equipment damage, THEN close the 4160 VAC breaker using the sequence of steps 1.1.2 through 1.1.4.
1.3 Trip 4160 VAC breaker to de-energize a load as follows:
1.3.1 OPEN breaker cubicle door.
1.3.2 IF a standard DHP Air circuit breaker is installed in this cubicle, push up on plunger marked "LIFT TO TRIP".
OR IF a new DHP-VR Vacuum breaker is installed in this cubicle, DEPRESS the button marked "Push to Trip".
MGR-0009 Ver. 4 SNC PLANT E. I. HATCH I DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 ATTACHMENT _1 TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER Pg 16 of 48 Version No:
5.14 Att. Pg.
6 of 7 STEP 1.2 BYPASSES ALL TRIPS AND PROTECTIVE FUNCTIONS OF THE CAUTION BREAKER BY ALLOWING THE CONTROL CIRCUIT TO REMAIN DE-ENERGIZED AFTER THE BREAKER IS CLOSED.
1.2 IF the breaker has tripped AND must be reclosed regardless of possible equipment damage, THEN close the 4160 VAC breaker using the sequence of steps 1.1.2 through 1.1.4.
1.3 Trip 4160 VAC breaker to de-energize a load as follows:
1.3.1 OPEN breaker cubicle door.
1.3.2 IF a standard DHP Air circuit breaker is installed in this cubicle, push up on plunger marked "LIFT TO TRIP".
OR IF a new DHP-VR Vacuum breaker is installed in this cubicle,
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DEPRESS the button marked "Push to Trip".
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MGR-0009 Ver. 4
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SNC PLANT E. I. HATCH I Pg 17 of 48 DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:
5.14 ATTACHMENT J.-
TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER 2.0 IF the breaker is a 600 VAC General Electric breaker, THEN take the following applicable action:
2.1 OPEN the front breaker cabinet door. Note the breaker type indicated on metal plate at left.
2.2 Energize a 600 VAC load by closing contacts in the breaker as follows:
2.2.1 For AK25 breakers (load breakers, no Spring Charge Indicator):
CAUTION DUE TO PERSONNEL SAFETY CONSIDERATIONS, THE AK25 BREAKERS WILL BE CLOSED MANUALLY ONLY WHEN THE FOLLOWING CONDITIONS ARE MET:
(1) AN EXTREME EMERGENCY EXISTS.
(2) THE APPROVAL OF THE SOS HAS BEEN OBTAINED.
(3) IF TIME PERMITS, THE CIRCUIT DOWNSTREAM OF THE BREAKER HAS BEEN MEGGERED TO ENSURE NO FAULT EXISTS, OR IF TIME DOES NOT PERMIT MEGGERING, THERE IS NO REASON TO SUSPECT THAT A FAULT EXISTS.
(4) THE OPERATOR MUST MEET THE REQUIREMENTS OF NMP-SH-003, ELECTRICAL WORK PRACTICES..
2.2.1.1 Confirm the above conditions have been met.
2.2.1.2 Place the two small hooks of the maintenance handle into the two slots located in the lower portion of the front panel.
2.2.1.3 Push the long end of the handle downward, forcing the shorter end of the handle upward against the breaker closing solenoid, thus closing the breaker's contacts.
2.2.2 For AK50 breakers (main feeder breakers, with Spring Charge Indicator):
2.2.2.1 Place the ratchet type maintenance handle onto the shaft that protrudes from the gear reduction unit on the right side of the breaker.
Att. Pg.
70f7 2.2.2.2 Operate the handle UNTIL the Spring Charge Indicator reads "CHARGED". __ _
2.2.2.3 Continue to operate handle UNTIL the closing springs discharge AND close the breaker's contacts.
2.3 De-energize a 600 VAC load, by pushing the TRIP pushbutton on the front of the breaker cabinet.
MGR-0009 Ver. 4 l
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SNC PLANT E. I. HATCH I Pg 17 of 48 DOCUMENT TITLE:
I DOCUMENT NUMBER:
SHUTDOWN FROM OUTSIDE CONTROL ROOM 31 RS-OPS-001-1 Version No:
5.14 ATTACHMENT _1 TITLE:
BREAKER CLOSING PROCEDURE WITHOUT CONTROL POWER 2.0 IF the breaker is a 600 VAC General Electric breaker, THEN take the following applicable action:
2.1 OPEN the front breaker cabinet door. Note the breaker type indicated on metal plate at left.
2.2 Energize a 600 VAC load by closing contacts in the breaker as follows:
2.2.1 For AK25 breakers (load breakers, no Spring Charge Indicator):
CAUTION DUE TO PERSONNEL SAFETY CONSIDERATIONS, THE AK25 BREAKERS WILL BE CLOSED MANUALLY ONLY WHEN THE FOLLOWING CONDITIONS ARE MET:
(1) AN EXTREME EMERGENCY EXISTS.
(2) THE APPROVAL OF THE SOS HAS BEEN OBTAINED.
(3) IF TIME PERMITS, THE CIRCUIT DOWNSTREAM OF THE BREAKER HAS BEEN MEGGERED TO ENSURE NO FAULT EXISTS, OR IF TIME DOES NOT PERMIT MEGGERING, THERE IS NO REASON TO SUSPECT THAT A FAULT EXISTS.
(4) THE OPERATOR MUST MEET THE REQUIREMENTS OF NMP-SH-003, ELECTRICAL WORK PRACTICES..
2.2.1.1 Confirm the above conditions have been met.
2.2.1.2 Place the two small hooks of the maintenance handle into the two slots located in the lower portion of the front panel.
2.2.1.3 Push the long end of the handle downward, forcing the shorter end of the handle upward against the breaker closing solenoid, thus closing the breaker's contacts.
2.2.2 For AK50 breakers (main feeder breakers, with Spring Charge Indicator):
2.2.2.1 Place the ratchet type maintenance handle onto the shaft that protrudes from the gear reduction unit on the right side of the breaker.
Att. Pg.
7 of 7 2.2.2.2 Operate the handle UNTIL the Spring Charge Indicator reads "CHARGED". __ _
2.2.2.3 Continue to operate handle UNTIL the closing springs discharge AND close the breaker's contacts.
2.3 De-energize a 600 VAC load, by pushing the TRIP pushbutton on the front of the breaker cabinet.
MGR-0009 Ver. 4
DRAFT Southern E. I.
atch uclear uclear Plant R. A. BELCHER Operations raining JM PLA -T 3 Energy to Serve Your World sM
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TITLE DRAFT Southern Nuclear E. I. Hatch Nuclear Plant Operations Training JPM PLANT 3 STARTUP THE REACTOR PROTECTION SYSTEM (RPS) 120 v AC SYSTEM AUTHOR MEDIA NUMBER TIME R. A. BELCHER LR-IP-1O.01-19 13.0 Minutes RECOMMENDED BY APPROVED BY DATE Energy to Serve Your World sM
SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Page 1 of2 Media Number:
LR*JP*IO.Ol
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SOUTHERN NUCLEAR OPERATING COMPANY PLANT E. I. HATCH FORM TITLE: TRAINING MATERIAL REVISION SHEET Program/Course Code:
OPERATIONS TRAINING Rev. No.
Date Reason for Revision Page 1 of2 Media Number:
LR-JP-IO.Ol Author's Supv's Initials Initials
LR-IP-1O.01-19 Page 1 of5 UNIT 1 (X)
UNIT 2 0
STARTUP THE REACTOR PROTECTION SYSTEM (RPS) 120 V AC SYSTEM LR-IP-1O.01-19 The task shall be completed when the Reactor Protection System 120 VAC System, RPS MG Set, has been started per 34S0-C71-001.
010.001 01O.001.B PLANT HATCH JTA IMPORTANCE RATING:
RO 3.00 SRO 3.31 KIA CATALOG NUMBER: 212000Al.01 KIA CATALOG JTA IMPORTANCE RATING:
RO 2.8 SRO 2.9 OPERATOR APPLICABILITY:
RO 1-1 (current version)
APPROXIMATE COMPLETION TIME:
13.0 Minutes SIMULATOR SETUP:
N/A LR-1P-10.01-19 Page 1 of 5 UNIT 1 (X)
UNIT 2 0
TASK TITLE:
STARTUP THE REACTOR PROTECTION SYSTEM (RPS) 120 V AC SYSTEM JPMNUMBER:
TASK STANDARD:
TASK NUMBER:
LR-1P-10.01-19 The task shall be completed when the Reactor Protection System 120 VAC System, RPS MG Set, has been started per 34S0-C71-001.
010.001 OBJECTIVE NUMBER: 010.00l.B PLANT HATCH JTA IMPORTANCE RATING:
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KIA CATALOG NUMBER: 212000Al.01 KIA CATALOG JTA IMPORTANCE RATING:
RO 2.8 SRO 2.9 OPERATOR APPLICABILITY:
RO I GENERAL
REFERENCES:
Unit 1 34S0-C71-00 1-1 (current version)
I REQIDRED MATERIALS:
Unit 1 34S0-C71-00 1-1 (current version)
APPROXIMATE COMPLETION TIME:
13.0 Minutes SIMULATOR SETUP:
NI A
UNITl READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The Reactor Protection System Bus A is de-energized and no electrical faults currently exist.
- 2.
The power source select switch on panellHII-P61O is in the Normal position.
- 3.
34AB-C71-002-1 is in progress.
INITIATING CUES:
Energize the "A" RPS Bus by starting the 120 VAC RPS MG Set "A" per 34S0-C71-00 1-1.
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UNITl READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The Reactor Protection System Bus A is de-energized and no electrical faults currently exist.
- 2.
The power source select switch on panellHII-P61O is in the Normal position.
- 3.
34AB-C71-002-1 is in progress.
INITIATING CUES:
Energize the "A" RPS Bus by starting the 120 VAC RPS MG Set "A" per 34S0-C71-00 1-1.
For INITIAL Operator Programs:
For OJT/OJE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
- 1.
- 2.
- 3.
- 4.
For License Examinations; ALL CRmCAL STEPS must be completed for Satisfactory Performance.
Operator obtains the procedure needed Operator has obtains procedure to perform task.
34S0-C71-00 1-1.
Confirm Open RPS Equipment In the RPS MG Set Room, the Protection Circuit Breaker 52-3C.
operator VERIFIES 52-3C in panel1C71-P003C is in the OFF position.
Confirm Open RPS Equipment In the RPS MG Set Room, the Protection Circuit Breaker 52-3A.
operator VERIFIES 52-3A in panel1C71-P003A is in the OFF position.
Confirm fuses are installed in panel In panel 1C71-P003A, the 1C71-P003A operator CONFIRMS fuses C71AF474, C71AF475 are installed.
START TIME: ___ _
SAT/UNSAT SAT I UNSAT SAT/UNSAT SAT I UNSAT PROMPT: When operator indicates he would check the fuses in Panel1C71-P003A(C), provide the operator with the associated attached pictures of the panel.
- 5. Confirm the green Motor Off light is illuminated.
At local RPS MG Set 1C71-S001A Control Panel, operator VERIFIES the green MOTOR OFF light is ILLUMINATED.
At local RPS MG Set 1C71-S001A Control Panel, MOTOR ON pushbutton is DEPRESSED and HELD until generator output voltage is greater than 118 VAC.
SAT/UNSAT SAT/UNSAT PROMPT: IF operator does NOT indicate that he held the pushbutton and asks for voltage, then inform the operator voltage is zero.
PROMPT: IF operator DOES indicate that he held the pushbutton and asks for voltage, then inform the operator voltage is 120 VAC.
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- 1.
- 2.
- 3.
- 4.
For INITIAL Operator Programs:
For O.JT/O.JE; ALL PROCEDURE STEPS must be completed for Satisfactory Performance.
For License Examinations; ALL CRmCAL STEPS must be completed for Satisfactory Performance.
Operator obtains the procedure needed Operator has obtains procedure to perform task.
Confirm Open RPS Equipment In the RPS MG Set Room, the Protection Circuit Breaker 52-3C.
operator VERIFIES 52-3C in panellC7l-P003C is in the OFF position.
Confirm Open RPS Equipment In the RPS MG Set Room, the Protection Circuit Breaker 52-3A.
operator VERIFIES 52-3A in panellC7l-P003A is in the OFF position.
Confirm fuses are installed in panel In panel lC7l-P003A, the lC7l-P003A operator CONFIRMS fuses C7lAF474, C7lAF475 are installed.
START TIME: ___ _
SAT/UNSAT SAT/UNSAT SAT I UNSAT SAT I UNSAT PROMPT: When operator indicates he would check the fuses in PanellC7l-P003A(C), provide the operator with the associated attached pictures of the panel.
lC7l-S00lA Control Panel, operator VERIFIES the green MOTOR OFF light is ILLUMINATED.
MOTOR ON pushbutton is DEPRESSED and HELD until generator output voltage is greater than 118 VAC.
PROMPT: IF operator does NOT indicate that he held the pushbutton and asks for voltage, then inform the operator voltage is zero.
PROMPT: IF operator DOES indicate that he held the pushbutton and asks for voltage, then inform the operator voltage is 120 VAC.
I
1 C71-S00 1 A Control Panel, PROMPT:
NOTE:
PROMPT:
PROMPT:
operator VERIFIES voltage is between 118 and 122 VAC.
WHEN the operator addresses output voltage, INDICATE for the operator that output voltage is 120 VAC.
At panellC71-P003A, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER 52-3A is in the ON position.
At panel 1 C71-P003C, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER 52-3C is in the ON position.
SAT/UNSAT SAT I UNSAT If the operator attempts to close breaker 52-3C prior to closing the protection circuit breaker 52-3A, then breaker 52-3C will not stay closed.
WHEN the operator addresses the GEN A white light on panel IHI1-P61O, as the Control Room operator, INFORM the operator that the light is illuminated.
IF the operator addresses Subsection 7.1.3 (7.3.3), as the Shift Supervisor, INFORM the operator that another operator is performing the appropriate subsection.
END TIME: ___ _
NOTE:
The terminating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
I
1C71-S001A Control Panel, operator VERIFIES voltage is between 118 and 122 VAC.
PROMPT:
WHEN the operator addresses output voltage, INDICATE for the operator that output voltage is 120 V AC.
EQUIPMENT PROTECTION CIRCUIT BREAKER 52-3A is in the ON position.
EQUIPMENT PROTECTION CIRCUIT BREAKER 52-3C is in the ON position.
NOTE:
If the operator attempts to close breaker 52-3C prior to closing the protection circuit breaker 52-3A, then breaker 52-3C will not stay closed.
PROMPT:
PROMPT:
WHEN the operator addresses the GEN A white light on panel 1H11-P61O, as the Control Room operator, INFORM the operator that the light is illuminated.
IF the operator addresses Subsection 7.1.3 (7.3.3), as the Shift Supervisor, INFORM the operator that another operator is performing the appropriate subsection.
END TIME: ___ _
NOTE: The tenninating cue shall be given to the operator when:
With no reasonable progress, the operator exceeds double the allotted time.
Operator states the task is complete.
TERMINATING CUE: We will stop here.
PanellC71-P003A PanellC71-P003A
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Panel 1 C71-P003C PanellC71-P003C
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UNITl READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The Reactor Protection System Bus A is de-energized and no electrical faults currently exist.
- 2.
The power source select switch on panellHII-P61O is in the Normal position.
- 3.
34AB-C71-002-1 is in progress.
INITIATING CUES:
Energize the "A" RPS Bus by starting the 120 VAC RPS MG Set "A" per 34S0-C71-00 1-1.
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UNIT 1 READ TO THE OPERATOR INITIAL CONDITIONS:
- 1.
The Reactor Protection System Bus A is de-energized and no electrical faults currently exist.
- 2.
The power source select switch on panel IHII-P61O is in the Normal position.
- 3.
34AB-C71-002-1 is in progress.
INITIATING CUES:
Energize the "A" RPS Bus by starting the 120 VAC RPS MG Set "A" per 34S0-C71-00 1-1.
SOUTHERN NUCLEAR DOCUMENT TYPE:
PAGE PLANT E. I. HATCH SYSTEM OPERATING PROCEDURE 1 OF 50 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
120 VAC RPS SUPPLY SYSTEM 34S0-C71-001-1 8.12 EXPIRATION APPROVALS:
EFFECTIVE DATE:
DEPARTMENT MGR G. L. Johnson DATE 07-13-98 DATE:
N/A SSM/PM N/A DATE N/A 5-4-09 1.0 OBJECTIVE This procedure provides the instructions for startup, shutdown and power source transfer of the 120 VAC RPS power supply system.
TABLE OF CONTENTS Section 2.0 APPLICABILITY.................................................................................................................. 2
3.0 REFERENCES
................................................................................................................... 2 4.0 REQUIREMENTS............................................................................................................... 4 5.0 PRECAUTIONS/LIMITATION............................................................................................. 4 6.0 PREREQUISITES............................................................................................................... 5 7.0 PROCEDURE..................................................................................................................... 6 7.1 SYSTEM STARTUP...................................................................................................... 6 7.1.1 MOTOR GENERATOR SET STARTUP................................................................ 6 7.1.1.1 Motor Generator Set 1 A Startup..................................................................... 6 7.1.1.2 Motor Generator Set 1 B Startup..................................................................... 8 7.1.2 ALTERNATE POWER SOURCE STARTUP........................................................ 10 7.1.3 SUPPLYING RPS BUS FROM MOTOR GENERATOR SET.............................. 11 7.1.3.1 Supplying RPS Bus A From Motor Generator Set 1 A.................................... 11 7.1.3.2 Supplying RPS Bus B From Motor Generator Set 1 B.................................... 13 7.2 SYSTEM SHUTDOWN............................................................................................... 15 7.2.1 MOTOR GENERATOR SET SHUTDOWN......................................................... 15 7.2.1.1 Motor Generator Set 1 A Shutdown............................................................... 15 7.2.1.2 Motor Generator Set 1 B Shutdown............................................................... 16 7.3 INFREQUENT OPERATIONS..................................................................................... 17 7.3.1 SUPPLYING RPS BUS FROM ALTERNATE POWER SOURCE........................ 17 7.3.1.1 Supplying RPS Bus A From Alternate Power Source.................................... 17 7.3.1.2 Supplying RPS Bus B From Alternate Power Source.................................... 19 7.3.2 TRANSFER RPS BUS FROM MG SET TO ALTERNATE POWER..................... 21 7.3.2.1 Transfer RPS Bus A From MG Set 1A To Alternate Power........................... 21 7.3.2.2 Transfer RPS Bus B From MG Set 1B To Alternate Power........................... 26 7.3.3 TRANSFER RPS BUS FROM ALTERNATE POWER TO MG SET..................... 31 7.3.3.1 Transfer RPS Bus A From Alternate Power To MG Set 1A........................... 31 7.3.3.2 Transfer RPS Bus B From Alternate Power To MG Set 1 B........................... 36 7.3.4 SWAPPING RPS THROWOVER SWITCH 1R26-M021....................................... 40 MGR-0002 Ver. 8.1
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SOUTHERN NUCLEAR DOCUMENT TYPE:
PAGE PLANT E. I. HATCH SYSTEM OPERATING PROCEDURE 1 OF 50 DOCUMENT TITLE:
DOCUMENT NUMBER:
VERSION NO:
120 VAC RPS SUPPLY SYSTEM 34S0-C71-001-1 8.12 EXPIRATION APPROVALS:
EFFECTIVE DATE:
DEPARTMENT MGR G. L. Johnson DATE 07-13-98 DATE:
N/A SSM / PM N/A DATE N/A 5-4-09 1.0 OBJECTIVE This procedure provides the instructions for startup, shutdown and power source transfer of the 120 VAC RPS power supply system.
TABLE OF CONTENTS Section 2.0 APPLiCABILITy.................................................................................................................. 2
3.0 REFERENCES
................................................................................................................... 2 4.0 REQUIREMENTS............................................................................................................... 4 5.0 PRECAUTIONS/LIMITATION............................................................................................. 4 6.0 PREREQUISITES............................................................................................................... 5 7.0 PROCEDURE..................................................................................................................... 6 7.1 SYSTEM STARTUP...................................................................................................... 6 7.1.1 MOTOR GENERATOR SET STARTUP................................................................ 6 7.1.1.1 Motor Generator Set 1 A Startup..................................................................... 6 7.1.1.2 Motor Generator Set 1 B Startup..................................................................... 8 7.1.2 ALTERNATE POWER SOURCE STARTUP........................................................ 10 7.1.3 SUPPLYING RPS BUS FROM MOTOR GENERATOR SET.............................. 11 7.1.3.1 Supplying RPS Bus A From Motor Generator Set 1A.................................... 11 7.1.3.2 Supplying RPS Bus B From Motor Generator Set 1 B.................................... 13 7.2 SYSTEM SHUTDOWN............................................................................................... 15 7.2.1 MOTOR GENERATOR SET SHUTDOWN......................................................... 15 7.2.1.1 Motor Generator Set 1 A Shutdown............................................................... 15 7.2.1.2 Motor Generator Set 1 B Shutdown............................................................... 16 7.3 INFREQUENT OPERATIONS..................................................................................... 17 7.3.1 SUPPLYING RPS BUS FROM ALTERNATE POWER SOURCE........................ 17 7.3.1.1 Supplying RPS Bus A From Alternate Power Source.................................... 17 7.3.1.2 Supplying RPS Bus B From Alternate Power Source.................................... 19 7.3.2 TRANSFER RPS BUS FROM MG SET TO ALTERNATE POWER..................... 21 7.3.2.1 Transfer RPS Bus A From MG Set 1A To Alternate Power........................... 21 7.3.2.2 Transfer RPS Bus B From MG Set 1 B To Alternate Power........................... 26 7.3.3 TRANSFER RPS BUS FROM ALTERNATE POWER TO MG SET..................... 31 7.3.3.1 Transfer RPS Bus A From Alternate Power To MG Set 1A........................... 31 7.3.3.2 Transfer RPS Bus B From Alternate Power To MG Set 1 B........................... 36 7.3.4 SWAPPING RPS THROWOVER SWITCH 1 R26-M021....................................... 40 MGR-0002 Ver. 8.1
SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
120 VAC RPS SUPPLY SYSTEM Attachments DOCUMENT NUMBER:
34S0-C71-001-1 PAGE 2 OF 50 VERSION NO:
8.12 1
RPS ELECTRICAL LINEUP.............................................................................................. 42 2
BREAKER REALIGNMENT.............................................................................................. 45 3
VALVE REALIGNMENT.................................................................................................... 48 4
RPS MG SET CONTROL PANEL BULB REPLACEMENT PLACARD.............................. 50 2.0 APPLICABILITY This procedure applies to 1C71-S001A & B, Unit 1 G.E. supplied high inertia motor-generator sets, AND the associated distribution equipment.
3.0 REFERENCES
3.1 GEK-30486, Motor Generator Package Set (Found in Inst. Component Manual X #S30697) 3.2 H-17155, Reactor Protection System MG Set Control Elementary H-17197 H-17499 3.3 H-17783, Reactor Protection System Elementary thru H-17798 3.4 H-13369, 120/208V Essential AC System Single Line Diagram 3.5 H-13361, 600V Bus 1C & 1D Single Line Diagram 3.6 H-17806, Nuclear Steam Supply Shutoff System Elementary thru H-17819 3.7 H-17801, Primary Containment Isolation System Elementary thru H-17805 3.8 H-17096, Nitrogen Inerting & Makeup System Elementary 3.9 H-16000, Nitrogen Inerting System P&ID 3.10 H-17076 thru H-17078, Off Gas System Elementary 3.11 H-11613, Off Gas System P&ID 3.12 H-13377, Turbine Auxiliary Equipment Elementary 3.13 H-17081 thru H-17083, Primary Containment Purge And Inerting System Elementary 3.14 H-16024, Primary Containment Purge and Inerting P&ID 3.15 H-17052 thru H-17056, Reactor Building Ventilation System Elementary 3.16 H-16005, Reactor Building Ventilation System P&ID MGR-0001 Ver. 3
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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 2 OF 50 DOCUMENT TITLE:
DOCUMENT NUMBER:
34S0-C71-00 1-1 VERSION NO:
8.12 120 VAC RPS SUPPLY SYSTEM Attachments RPS ELECTRICAL LINEUP.............................................................................................. 42 2
BREAKER REALIGNMENT.............................................................................................. 45 3
VALVE REALIGNMENT.................................................................................................... 48 4
RPS MG SET CONTROL PANEL BULB REPLACEMENT PLACARD.............................. 50 2.0 APPLICABILITY This procedure applies to 1 C71-S001A & B, Unit 1 G.E. supplied high inertia motor-generator sets, AND the associated distribution equipment.
3.0 REFERENCES
3.1 GEK-30486, Motor Generator Package Set (Found in Inst. Component Manual X #S30697) 3.2 H-17155, Reactor Protection System MG Set Control Elementary H-17197 H-17499 3.3 H-17783, Reactor Protection System Elementary thru H-17798 3.4 H-13369, 120/208V Essential AC System Single Line Diagram 3.5 H-13361, 600V Bus 1C & 1D Single Line Diagram 3.6 H-17806, Nuclear Steam Supply Shutoff System Elementary thru H-17819 3.7 H-17801, Primary Containment Isolation System Elementary thru H-17805 3.8 H-17096, Nitrogen Inerting & Makeup System Elementary 3.9 H-16000, Nitrogen Inerting System P&ID 3.10 H-17076 thru H-17078, Off Gas System Elementary 3.11 H-11613, Off Gas System P&ID 3.12 H-13377, Turbine Auxiliary Equipment Elementary 3.13 H-17081 thru H-17083, Primary Containment Purge And Inerting System Elementary 3.14 H-16024, Primary Containment Purge and Inerting P&ID 3.15 H-17052 thru H-17056, Reactor Building Ventilation System Elementary 3.16 H-16005, Reactor Building Ventilation System P&ID MGR-0001 Ver. 3
SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
120 VAC RPS SUPPLY SYSTEM DOCUMENT NUMBER:
34S0-C71-001-1 3.17 H-17104 and H-17105, Standby Gas Treatment System Elementary 3.18 H-17068 thru H-17073, Control Building HVAC Elementary 3.19 H-16042, Control Building HVAC P&ID 3.20 H-16020, Standby Gas Treatment System Process Flow and P&ID 3.21 H-17138 thru H-17140, Oxygen, Hydrogen Analyzer System Elementary 3.22 H-16276 thru H-16280, Oxygen, Hydrogen Analyzer System P&ID 3.23 H-17176 and H-17177, Reactor Water Clean-up System Elementary 3.24 H-16188, Reactor Water Clean-up System P&ID 3.25 H-16062, Nuclear Boiler System P&ID 3.26 H-17756 thru H-17757 and H-17800, TIP Calibration System Elementary 3.27 H-17760 thru H-17782, RHR System Elementary 3.28 H-16329, RHR System P&ID H-16330 3.29 H-19501 thru H-19543, Radwaste System Elementary 3.30 H-16066 Reactor Recirc. System P&ID 3.31 H-19801 thru H-19835, ATTS Elementary 3.32 Unit 1 FSAR, Chapter 7, Section 7.2.3.2 PAGE 3 OF 50 VERSION NO:
8.12 3.33 H-19551 thru H-19566 and H-19578, H-19584, H-19596. Process Radiation Monitoring System Elementary 3.34 57CP-C71-001-1, RPS MG Set Monitors Calibration.
3.35 Letter LR-REG-008-0689 3.36 Letter HL-1030 MGR-0001 Ver. 3 i I "
SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
DOCUMENT NUMBER:
34S0-C71-001-1 120 VAC RPS SUPPLY SYSTEM 3.17 H-17104 and H-171 05, Standby Gas Treatment System Elementary 3.18 H-17068 thru H-17073, Control Building HVAC Elementary 3.19 H-16042, Control Building HVAC P&ID 3.20 H-16020, Standby Gas Treatment System Process Flow and P&ID 3.21 H-17138 thru H-17140, Oxygen, Hydrogen Analyzer System Elementary 3.22 H-16276 thru H-16280, Oxygen, Hydrogen Analyzer System P&ID 3.23 H-17176 and H-17177, Reactor Water Clean-up System Elementary 3.24 H-16188, Reactor Water Clean-up System P&ID 3.25 H-16062, Nuclear Boiler System P&ID 3.26 H-17756 thru H-17757 and H-17800, TIP Calibration System Elementary 3.27 H-17760 thru H-17782, RHR System Elementary 3.28 H-16329, RHR System P&ID H-16330 3.29 H-19501 thru H-19543, Radwaste System Elementary 3.30 H-16066 Reactor Recirc. System P&ID 3.31 H-19801 thru H-19835, ATTS Elementary 3.32 Unit 1 FSAR, Chapter 7, Section 7.2.3.2 PAGE 3 OF 50 VERSION NO:
8.12 3.33 H-19551 thru H-19566 and H-19578, H-19584, H-19596. Process Radiation Monitoring System Elementary 3.34 57CP-C71-001-1, RPS MG Set Monitors Calibration.
3.35 Letter LR-REG-008-0689 3.36 Letter HL-1030 MGR-0001 Ver. 3
SOUTHERN NUCLEAR PLANT E.I. HATCH DOCUMENT TITLE:
120 VAC RPS SUPPLY SYSTEM 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS DOCUMENT NUMBER:
34S0-C71-001-1 PAGE 40F 50 VERSION NO:
8.12 The number and qualification level of personnel performing the sections in this procedure will be determined by the Shift Supervisor.
4.2 MATERIAL AND EQUIPMENT Fuse pullers 4.3 SPECIAL REQUIREMENTS Independent verification, as described in 1 OAC-MGR-019-0, Procedure Use and Adherence, will be required during performance of Attachments 1 and 2 of this procedure.
5.0 PRECAUTIONS/LIMITATION 5.1 PRECAUTIONS 5.1.1 Observe safety rules outlined in Southern Nuclear Safety and Health Manual.
5.1.2 The Shift Supervisor must be notified PRIOR to beginning work on any section of this procedure.
5.2 LIMITATIONS 5.2.1 Electrical interlocks prevent supplying both RPS buses from the alternate power source at the same time.
5.2.2 Electrical interlocks prevent supplying the RPS bus from both the MG set AND the alternate power source at the same time.
5.2.3 An overvoltage trip of the MG set must be manually reset at the local control panel by momentarily depressing the Motor On pushbutton.
5.2.4 Transferring RPS bus power is a dead bus transfer. The RPS bus will be deenergized momentarily during the transfer.
5.2.5 After restoring power it takes approximately 5 minutes for the Main Steam Line Radiation Monitors to charge up to operating voltage AND the HV-INOP Alarm to clear automatically.
5.2.6 Ensure steps are taken to monitor reactor water conductivity as required by Technical Requirements Manual 3.4.1.
MGR-0001 Ver. 3
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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 40F 50 DOCUMENT TITLE:
DOCUMENT NUMBER:
34S0-C71-001-1 VERSION NO:
8.12 120 VAC RPS SUPPLY SYSTEM 4.0 REQUIREMENTS 4.1 PERSONNEL REQUIREMENTS The number and qualification level of personnel performing the sections in this procedure will be determined by the Shift Supervisor.
4.2 MATERIAL AND EQUIPMENT Fuse pullers 4.3 SPECIAL REQUIREMENTS Independent verification, as described in 10AC-MGR-019-0, Procedure Use and Adherence, will be required during performance of Attachments 1 and 2 of this procedure.
5.0 PRECAUTIONS/LIMITATION 5.1 5.1.1 5.1.2 5.2 5.2.1 5.2.2 5.2.3 PRECAUTIONS Observe safety rules outlined in Southern Nuclear Safety and Health Manual.
The Shift Supervisor must be notified PRIOR to beginning work on any section of this procedure.
LIMITATIONS Electrical interlocks prevent supplying both RPS buses from the alternate power source at the same time.
Electrical interlocks prevent supplying the RPS bus from both the MG set AND the alternate power source at the same time.
An overvoltage trip of the MG set must be manually reset at the local control panel by momentarily depressing the Motor On pushbutton.
5.2.4 Transferring RPS bus power is a dead bus transfer. The RPS bus will be deenergized momentarily during the transfer.
5.2.5 After restoring power it takes approximately 5 minutes for the Main Steam Line Radiation Monitors to charge up to operating voltage AND the HV-INOP Alarm to clear automatically.
5.2.6 Ensure steps are taken to monitor reactor water conductivity as required by Technical Requirements Manual 3.4.1.
MGR-0001 Ver. 3
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SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
120 VAC RPS SUPPLY SYSTEM 6.0 PREREQUISITES DOCUMENT NUMBER:
34S0-C71-001-1 PAGE 50F50 VERSION NO:
8.12 NOTE:
System electrical lineups provided on the Attachments are to be completed as required by 34GO-OPS-003-1, Startup System Status Checklist.
6.1 AC power is available.
6.2 RPS electrical lineup is complete per Attachment 1.
MGR-0001 Ver. 3
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SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
120 VAC RPS SUPPLY SYSTEM 6.0 PREREQUISITES DOCUMENT NUMBER:
34S0-C71-001-1 PAGE 5 OF 50 VERSION NO:
8.12 NOTE:
System electrical lineups provided on the Attachments are to be completed as required by 34GO-OPS-003-1, Startup System Status Checklist.
6.1 AC power is available.
6.2 RPS electrical lineup is complete per Attachment 1.
MGR-0001 Ver. 3
SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 60F50 DOCUMENT TITLE:
120 VAC RPS SUPPLY SYSTEM DOCUMENT NUMBER:
34S0-C71-001-1 VERSION NO:
8.12 7.0 PROCEDURE 7.1 SYSTEM STARTUP 7.1.1 MOTOR GENERATOR SET STARTUP 7.1.1.1 Motor Generator Set 1 A Startup 7.1.1.1.1 7.1.1.1.2 7.1.1.1.3 7.1.1.1.4 7.1.1.1.5 7.1.1.1.6 7.1.1.1.7 CONTINUOUS I
Confirm open OR open 52-3C, Reactor Protection System (RPS)
EQUIPMENT PROTECTION CIRCUIT BREAKER, in panel1C71-P003C.
Confirm open OR open 52-3A, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, in panel1C71-P003A.
Ensure fuse C71AF474, in pane11C71-P003A is installed.
Ensure fuse C71AF475 in panel1C71-P003A is installed.
Confirm green Motor Off light on the local Motor Generator (MG) set control panel is ILLUMINATED.
Depress AND hold the Motor ON pushbutton at the local MG Set 1A control panel, UNTIL the indicated generator output voltage is > 118 VAC.
Confirm voltage is between 118 VAC and 122 VAC, after the generator output voltage stabilizes.
D D
D D
D D
D NOTE: The breaker is TRIPPED WHEN white line CANNOT be seen.
Posted 1C71-P003A, B, C, D, E, F 7.1.1.1.8 MGR-0001 Ver. 3 Close 52-3A, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, panel 1 C71-P003A.
D
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SOUTHERN NUCLEAR PLANT E. I. HATCH DOCUMENT TITLE:
120 VAC RPS SUPPLY SYSTEM 7.0 PROCEDURE 7.1 SYSTEM STARTUP 7.1.1 MOTOR GENERATOR SET STARTUP 7.1.1.1 Motor Generator Set 1 A Startu p DOCUMENT NUMBER:
34S0-C71-001-1 CONTINUOUS I
PAGE 6 OF 50 VERSION NO:
8.12 7.1.1.1.1 Confirm open OR open 52-3C, Reactor Protection System (RPS)
EQUIPMENT PROTECTION CIRCUIT BREAKER, in paneI1C71-P003C.
0 7.1.1.1.2 7.1.1.1.3 7.1.1.1.4 7.1.1.1.5 7.1.1.1.6 7.1.1.1.7 Confirm open OR open 52-3A, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, in paneI1C71-P003A.
0 Ensure fuse C71AF474, in panel 1 C71-P003A is installed.
0 Ensure fuse C71AF475 in pane11C71-P003A is installed.
0 Confirm green Motor Off light on the local Motor Generator (MG) set control panel is ILLUMINATED.
0 Depress AND hold the Motor ON pushbutton at the local MG Set 1A control panel, UNTIL the indicated generator output voltage is > 118 VAC.
0 Confirm voltage is between 118 VAC and 122 VAC, after the generator output voltage stabilizes.
o NOTE: The breaker is TRIPPED WHEN white line CANNOT be seen.
Posted 1 C71-P003A, B, C, D, E, F 7.1.1.1.8 MGR-0001 Ver. 3 Close 52-3A, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, panel 1 C71-P003A.
o
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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 70F50 DOCUMENT TITLE:
120 VAC RPS SUPPLY SYSTEM DOCUMENT NUMBER:
34S0-C71-001-1 VERSION NO:
8.12
- Due to the undervoltage AND underfrequency condition, Circuit Breaker 52-3C will NOT CLOSE UNLESS Circuit Breaker 52-3A is CLOSED.
NOTES:
- The breaker is TRIPPED WHEN white line CANNOT be seen.
Posted 1C71-P003A, B, C, D, E, F.
7.1.1.1.9 Close 52-3C, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, panel 1 C71-P003C.
D 7.1.1.1.10 Confirm GEN. A white light, located above the Power Source Select switch, paneI1H11-P610, is ILLUMINATED.
D 7.1.1.1.11 Supply power to the RPS bus per subsection 7.1.3 OR 7.3.3 of this procedure, IF desired.
D MGR-0001 Ver. 3
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SOUTHERN NUCLEAR PLANT E. I. HATCH PAGE 7 OF 50 DOCUMENT TITLE:
120 VAC RPS SUPPLY SYSTEM DOCUMENT NUMBER:
34S0-C71-00 1-1 VERSION NO:
8.12
- Due to the undervoltage AND underirequency condition, Circuit Breaker 52-3C will NOT CLOSE UNLESS Circuit Breaker 52-3A is CLOSED.
NOTES:
- The breaker is TRIPPED WHEN white line CANNOT be seen.
Posted 1C71-P003A, B, C, D, E, F.
7.1.1.1.9 Close 52-3C, RPS EQUIPMENT PROTECTION CIRCUIT BREAKER, panel 1 C71-P003C.
D 7.1.1.1.10 Confirm GEN. A white light, located above the Power Source Select switch, paneI1H11-P610, is ILLUMINATED.
D 7.1.1.1.11 Supply power to the RPS bus per subsection 7.1.3 OR 7.3.3 of this procedure, IF desired.
D MGR-0001 Ver. 3