ML20092F682
| ML20092F682 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 03/08/1990 |
| From: | Bockhold G GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20092F288 | List:
|
| References | |
| CON-IIT05-002-139-90, CON-IIT05-077-90, CON-IIT5-2-139-90, CON-IIT5-77-90, RTR-NUREG-1410 12000-C, NUDOCS 9202190466 | |
| Download: ML20092F682 (15) | |
Text
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NUCLEAR OPERATIONS
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oste 16-Unit COMMON Georgia Power 3 g fC.
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UNIT NO.-
DATE
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REFUELING RECOVERY 4
(MODE 6 TO MODE 5) i '
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1.0 PURPOSE
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This procedure provides ins'tructions for taking the
-unit-from a refueling condition-(Mode 6) to cold 2
j shutdown (Mode 5).
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2.0 PRECAUTIONS AND LIMITATIONS
)i 2.1 PRECAUTIONS i
i 2.1.1 If the count rate on either Source Range Channel increases-unexpectedly by a factor.of two or more l
during any operation, the operation must be suspended
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immediatel until a satisfact ory evaluation of the situation as been performed.
2.1.2 Notify Health Physics prior to performing operations evolutions which may significantly alter radiation levels.
i 2.1.3 Notify Chemistry prior to installing or removing the Containment Equipment Hatch that containment ventilation flow will be changed during this-evolution.
4 4
2.1.4 During periods.of o)eration with the Reactor Coolant System (RCS) level below the Reactor Vessel Flange
[
elevation (194 feet elevation),-ongoing work activities should be closely scrutinized and any work activity limited that has-the potential for: reducing RHRS capability.
2.1.5' Inadvertent Containment _ Ventilation Isolation (CVI) may occur during the movement of the Reactor. Vessel' Head i
from the head stand-to the cavity.
Ensure. Health i._
Physics initiates compensatory actions-to prevent l
inadvertent actuations.
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9202190466 920116 PDR ADOCK 05000424 S
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PROCEDURE No.
REvtStoN PAGE No.
VEGP 12000-C 16 2 of 15 2.2 LIMITATIONS'
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2.2.1 In Mode 5, shutdown margin shall be greater than or equal to the limit specified in Technical Specification 3.1.1.2, Figure 3.1-2.-
2,2.2 When in Mode 5, with loops filled, at least one Residual Heat Removal train (RHR) shall be operable and in operation, and either:
a.
One additional RHR train shall be operable, or b.
The secondary side water level of at least two Steam Generators shall be greater than 17% of wide range level.
(Technical Specification 3.4.1.4.1) 2.2.3 While in Mode 5, one RHR train may be inoperable for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing proyided the other RHR train is operable and in operation.
(Technical Specification 3.4.1.4.1) 2.2.4 While in Mode 5 with the RCC '.iops not filled, two RHR trains shall be operab1' e'd at letst one RHR train shall be in operation.
Reactor Makeup Water Valves 1208-U4-175, 1208-U4-176, (2C9-U4+177, and 1208-U4-183 shall-be closed and secur4d in position (by mechanical stops), except 1208-U4-1? ') and 1208-U4-177 may be f-'.)
opened for short periods of time for chemistry control provided the Hi Flux at Shutuown Alarm is operable with a setpoint of less than or equal to 2.30 times background.
'Te inical Specification 3.4.1.4.2) 2.2,5 When in Mode ', with the water level greater than or equal to.23 feet above the Reactor Vessel Flange, at least one RHR train shall be operable and in operation, (Technical Specification 3.9.8.1) 2.2.6 When in Mode 6, with the water level less than 23 feet above the Reactor Vessel Flange -two RHR trains shall be operable and at least one RHR train in operation.
(Technical Specification 3.9.8.2) 2.2.7 While in Modes 4, 5, and 6 with the Reactor Vessel Head on, at least one of the following Cold Overpressure Protection Systems shall be operable:
a.
Two Power. Operated Relief Valves (PORV) with lift settings which do not exceed the limits established in Technical Specification Figure 3.4-4, or b.
Two RHR Suction Relief Valves each with a setpoint of 450 psig 3%, or O
c.
The RCS depressurized with an RCS vent capable of relieving at least 670 gpm water flow at 470 psig.
(Technical Specification 3.4.9.3) mun
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PROCEDURE No.
REVI5loN PAGE No.
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VEGP 12000-0 16 3 of 15 2.2.8 While in Modes 5 and 6, at least on'e of the following Boron Injection Flow Paths shall be operable.
a.
A flow path from the Boric Acid Storage Tank via a Boric Acid Transfer Pump and a Charging Pump to the Reactor Coolant System if the Boric Acid Storage Tank in specification 3.1.2.5a is operable, or b.
The flow path from the Refueling Water Storage Tank (RWST) via a Charging Pump to the RCS if the Refueling Water Storage Tank in Specification 3.1.2.5b is operable.
(Technical Specification 3.1.2.1) 2.2.9 The temperature of both the primary and secondary coolant in the Steam Generators shall be greater than 70 degrees when the pressure of either coolant in the Steam Generator is greater than 200 psig.
(Technical Specification 3.7.2) 2.2.10 While in Mode 5 two channels of Source Range Nuclear Instrumentation shall be operable (Technical Specification 3.3.1).
One channel should be selected to Recorder NR-45 with the SOURCE RANGE HI FLUX LEVEL AT SHUTDOWN alarm operable.
2.2.11 While in Mode 6 both Source Range Neutron Flux Monitors shall be operable with continuous visual indication in the Control Room and one with audible indication in the Containment and Control Room. (Technical Specification 3.9.2) 2.2.12 While in Mode 6 (whenever fuel is in the Reactor Vessel with the Reactor Vessel Head Closure Bolts less than fully tensioned or with the head removed) Keff shall be maintained at 0.95 or less, or the boron concentration shall be maintained greater than or equal to 2000 ppm.
whichever is more restrictive.
Additionally, valves 1208-U4-175, 1208-U4-177, 1208-U4-183 and 1208-U4-176 shall be closed'and secured in position (by mechanical stops), except 1208-U4-176 and 177 may be opened for short periods of time for chemistry control provided the Hi Flux at Shutdown Alarm is operable with a setpoint of less than or equal to 2.30 times-background.
(Technical Specification-3.9.1) 2.2.13 While in Modes 5 and 6, with the RCS level below Reactor Vessel Flange _ elevation (194 feet elevation),
the RWST will be operable with a minimum volume of 99,404 gallons (9% of instrument span) of water at a
)
boron concentration between 2400 and 2600 ppm.
l mw,
PROCEDURE No.
REVISloN PAGE No.
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VEGP 12000-C 16 4 of 15
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3.0 INITIAL CONDITIONS
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3.1 The RHR System is in service aligned to the RCS at a minimum total flow of 3000 gpm.
3.2 The Reactor Coolant Drain Tank (RCDT) is aligned to support RCS and/or Refueling Cavity draining operations.
3.3 The Component Cooling Water (CCW) System is in service.
3.4 At least one Nuclear Service Cooling Water (NSCW) train is in service.
3.5 Two Source Range Channels are in operation and highest channel selected to Recorder NR-45.
a.
SOURCE RANGE HI FLUX LEVEL AT SHUTDOWN alarm
- operable, b.
Audible cour.t rate in Containment and Control Room operable.
3.6 Reactor Vessel Head not installed.
p 3.7 Fuel Pool To Transfer Canal Gate is closed.
V 3.8 Transfer Tube Gate Valve is closed and locked.
INITIALS 4.0 INSTRUCTIONS NOTE Asterick (*) steps beside INITIALS spaces indicates steps that generat,e additional documents.
4.1 POST REFUELING MODE 6 OPERATIONS 4.1.1 As directed by the Outage Area Supervisor and when necessary, ADJUST the Refueling Cavity level to sup? ort the Reactor Vessel and Head assembly per 13011, " Residual Heat Removal System".
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PROCEDURE No.
REVISloN PAGE No.
VEGP 12000-C 16 5 of 15
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UNIT NO.
INITIALS
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4.1,2 OBTAIN from the Control Room Mode Change Binder or'0BTAIN from the Surveillance Tra'cking Coordinator all deferred (not performed) surveillance tests requirad for Mode 5 entry.
SCHEDULE and COMPLETE those applicable test procedures prior to Mode 5 entry.
NOTE As a precaution, Containment Building Penetrations Technical Specification 3.9.4 will be established during periods of Reactor Vessel Hca.d movement.
CAUTION Inadvertent Containment Ventilation Isolation (CVI) may occur during the movement of the Reactor Vessel Head from the head stand to the O
cavity.
Ensure Health Physics initiates compensatory actions to prevent inadvertent actuations.
4.1.3 Prior to setting the Upper Internals Assembly a.
NOTIFY Chemistry that closure of the Containment Equipment Hatch will change containment ventilation flow.
b.
NOTIFY Maintenance to reset the Containment Personnel Lock Interlock
- System, c.
PERFORM 14210, " Containment Building Penetrations Verification-Refueling",
d.
NOTIFY Chemistry to reset the PERMS Containment Low Range Area Monitors RE-0002 and RE-0003 alarm setpoint to 100 mR/ hour.
()
e.
INITIATE RWST cleanup per 13719, "Epent Fuel Pool Cooling And Purification System".
icws
Pd6bEDURE No.
REVISloN PAGE t<o.
VEGP 12000-C 16 6 of 15
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UNIT NO.
INITIALS 4.1.4 Prior to setting.the Reactor Vessel Head, PERFORM the following:
a.
VERIFY at least one of the Cold Overpressure Protection Systemc oaerable by performing one of the following (Technical Specification 4.4.9.3):
(1)
RHR Suction Relief Valves -
VERIFY RHR Suction Valves o')en per 14000, " Operations Shift And Daily Surveillance Logs" and INITIATE shiftly surveillance per 14000, (2)
RCS Vent Path -
VERIFY an RCS Vent Path per 14000, " Operations Shift And Daily Surveillance Logs" and INITIATE shiftly surveillance per 14000, (3)
PLACE the Cold Overpressure Protection System (COPS) in operation by performing the following:
4 (a)
ENSURE PRZR PORV BLOCK VLV COLD OVERPRESSURE CNTL Handswitcher HS-8000G and 8000H are in the BLOCK
- position, (b)
REQUEST I&C to perform an analog channel operational test on-both PORV Actuation Channels per 24518, " Reactor Coolant Pressure (Wide Range)
Protection II P-403 Analog Channel Operational Test And Channel Calibration" and 24519, " Reactor Coolant Pressure (Wide Range)
Protection I P-405 Analog Channel Operational Test And Channel Calibration".
O m._
PAoCEDURE No.
REVISloN PAG $ No.
VEGP 12000-C 16 7 of 15
(
UNIT NO.
INITIALS (c)
VERIFY the following annunciators in alarm.
1 A COLD OP LOW AUCT RCS TEMP, (ALB 12 C04),
2 B COLD OP LOW AUCT RCS TEMP (ALB 12 C05).
(d)
ARM the A and B COPS by placing handswitches HS-8000G and 8000H to ARM
- position, (e)
VERIFY the following annunciators alarmed upon arming COPS:
1 A COLD OP ACTU VLV HV-8000A NOT FULL OPEN (ALB 12 E06),
2 B COLD OP ACTU VLV HV-8000B NOT FULL-OPEN
('S (ALB 12-F06).
U (f)
ENSURE PRZR PORVs PV-455A and 456A are closed and the handswitches in AUTO, (g)
ENSURE OPEN PRZR PORV BLOCK valves HV-8000A and HV-8000B.
NOTE This step satisfies Technical Specification survcillance requirement'4.4.9.3.1.c.
(h)
VERIFY the following annunciators reset:
1 A COLD OP ACTU VLV HV-8000A NOT FULL OPEN (ALB 12 E06),
2 B' COLD OP ACTU VLV HV-8000B NOT FULL OPEN
-(ALB 12 F06).
b.
VERIFY SAFETY INJECTION Pumps C.
A and B breakers are racked out and tagged per 12006, " Unit Cooldown To Cold Shutdown".
nws
PROCEDURE No.
REVISloN PAGE No.
VEGP 12000-0 16 8 of 15
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UNIT NO.
INITIALS 4.1.5 While operating with the RCS level below 17% pressurizer -level (approximately 207-feet elevation) the following controls should be in effect:
a.
Tygon tube watch is required any time the RCS level is being changed while the RCS level is below 17%
(approximately 207 feet elevation) pressurizer level, (1)
Periodic comparison checks should be made every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> between the Control Room Temporary RCS Level Monitors and the Tygon tube, (2)
The Control Room Monitors should agree within 7 percent I
of scale with the Tygon tube, (3)
Two out of three Level Monitore must agree before draining RCS
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below the top of the hot leg (188 feet 3 inches),
(4)
If neither Control Room RCS Level Monitor is available, then a continuous Tygon tube watch should be established while RCS level is below 17%
pressurizer level.
(5)
DETERMINE closure status of Containment Equipment Hatch and ENSURE hatch is capable of being closed within 57 minutes or ENSURE hatch is closed prior to reducing RCS level below three feet below the Reactor Vessel Flange (191 ft. el,),
(6)
A review of all Containment penetrations addressed in 14210, " Containment Building Penetrations - Refueling" should be accomplished to determine those which have
((_3 been opened by manual means
)
and an info LCO generated for those identified, a
703MS l
PRoCEDul4L 940 REylsioN Pact No VEGP 12000-0 16 9 of 15
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UNIT NO. _
INITIALS
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(7)
Except when installing the Reacto'r Vessel Head, a minimum of two incore thermocouples shall be available, (8) kbQUEST IEC reset the designated ERF incore thermocouples alarm setpoint to alarm at 10*F above desired temperature per 00410-C, " Computer Software Control",
(9)
If SG Nozzle Dams are to be installed and no cold leg opening is-to be established, a vent path is required from the Reactor Vessel upper plenum.
This vent path can be satisfied by:
1 O'
(a)
Removing a pressurizer manway, or (b)
Removing a Steam Generator manway on a hot leg that will not be dammed, or (c)
Removing three pressurizer code safeties.
(10) If SG Nozzle Dams are to be installed and a cold leg opening is to be established, a vent path is required from the Reactor Vessel Upper Plenum by removin manway on an HL t$e an SG at will not be dammed.
(11) If it is intended to o at one foot above mid perate nozzle level, the preferred RHR configuration is one train operating with a flow of 3000
- gpm, O
1 70164%
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PROCEDURE No-RE Vi$loN PAGt NO.
VEGP 12000-C 16 10 of 15 4
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UNIT NO.
INITIALS (12) While operating with SG Nozzle Dams installed, ENSURE one Safety Injection Pump is capable of being racked in and operated in the hot leg injection mode if needed, (13) While level is in the region of the hot legs, TREND RHR Pump parameters on ERF for early detection of possible RHR Eum degradation due to vortexing,p (14) Minimum RCS level is ot2 foot above mid-nozzle (188 feet 0 inches elevation) except for Steam Generator burping during initial drain down.
For effective SG tube draining, RCS level should be lowered to 187 feet 6 inches.
Upon completion of SG burping, RAISE RCS level to 188 feet - 0 inches O
and MAINTAIN at this level thereafter.
(15) A minimum of 4 Containment Cooling Units will be operable and capable of being started if required while RCS level is below 191 feet elevation.
b.
COORDINATE with Outage Area Supervisor and INITIATE draining the Refuelin Cavity to 190 feet per 13011. "g'esidual Heat Removal R
System".
DE-ENERGIZE all underwater lights prior to uncovering.
4.1.6 When the Reactor Vessel Head is ready to i
be lowered into place, VERIFY RCS water level is less than or equal to 190 feet.
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~*b7570Tl" ~
enoc [ DURE No.
R PAGE No_
VEGP 12000-0 16 11 of 15
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UNIT NO.
INITIALS
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4.1.7 Prior to lowering Reactor Vessel Head into 11 ace, DRAIN Reactor lavity Seal i,
Area by opening Reactor Cavity Seal t
Support Drain.
UNIT 1:
1-1213-U4-088 IV UNIT 2:
2-1213-U4-088 IV 4.1.8 If it is necessary to perform any head lifts for 0-ring inspections, deconning, etc., then-prior to performing the lift, COMPLETE the applicable steps of 12007-C, " Refueling Entry" Core Alternations Checklist 2 and ATTACH to this procedure.
4.1.9 After the Reactor Vessel Head is O
lowered into place and during Head tensionin.g. MAINTAIN RCS water level at less than or equal to 190 feet.
4.1.10 If necessary, INITIATE reducing level to 1 foot above mid-nozzle (188 feet -
i l
0 inches) or 119 feet with SG Nozzle l
Da s installed.
4.1.11 MAINTAIN RCS temperature utilizing RHR i
Outlet HV-0606 for Train A (HV-0607 for l
Train B) as high as possible but not to i
exceed 130'F, i
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_1:
EOCEDURE No.
REylSloN PAGE No.
VEGP 12000-C 16 12 of 15
--a,
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UNIT NO.
INITIALS 4.1.12
. NOTIFY Health Phy' sics the.t they may release the locked or posted access restrictions on the concrete plugs for the Fuel Transfer Tube bellows in the Fuel Handling Building and containment Building, 4.1.13 Upon completion of refueling cavity decontamination activities:
s.
ENSURE Maintenance rem /tes the 2 Blind Flanges on the 12 inch drain lines in the Refueling
- Cavity, IV b.
ENSURE Maintenance has installed the Transfer Tube Blind Flange.
(Technical Specification 4.6.1.1.a)
\\
c.
ENSURE the FHB HVAC Pre-heating coil Thermostat is reset by verifying local handswitches HS-12470 and 12471 are in the OFF position, d.
CLOSE Reactor Cavity Seal Support Drain.
UNIT 1:
1-1213-U4-088
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IV I
UNIT 2:
2-1213-UA-088 IV m
O i
103445
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J.,... - _ -..,,, - -....-_-----.
__._~.m PHoCLDURE No.
Revision Pang No
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VEGP 12000-C 16 13 of 15
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UNIT NO.
INITIALS 4.2
, MODE 5 ENTRY 4.2.1 Prior to Maintenance completing the last head bolt tensioning (Mode 5 entry) PERFORM the followings a.
COMPLETE the following logs and VERIFY the requirements therein are met for entry into Mode 5:
(1) 14000
" Operations Shift And Daily Surveillance Logs".
OBTAIN the new cycle curves for the Plant Technical Data Book from Reactor Engineering to be used for shutdown margin determinations.
If curves are not available.
OBTAIN a method of performing shutdown margin determinations
[)
from Reactor Engineering.
(2) 14225, " Operations Weekly Surveillance Logs",
(3) 14228, " Operations Monthly l
Surveillance Logs",
l (4) 14915, "Special Condition i
l Surveillance Logs.
b.
REVIEW the following for impact on entering Mode 5:
(1)
Jumper and Lifted Wire Log, (2)
Temporary Modification Log, (3)
Equipment Clearance Log, (4)
LCO Book, (5)
Outstanding Work Orders.
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.2
PHoctDURE No H[ vision PAGE No VEGP 12000-C 16 14 of 15
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UNIT NO.
1]iITI AI S, c.
ENSURE that all surveillance test procedures scheduled per Sub-subsection 4.1.2 required for Mode 5 entry have been completed, REVIEW the control Room Mode i
change Binder or OBTAIN from the Surveillance Tracking Coordinator.
d.
INITIATE Mode 5 log sheet readings per 14000, " Operations Shift And Daily Surveillance Legs",
e.
OBTAIN On-Shift Operations Supervisor's approval to change status from Mode 6 to Mode 5.
/
/
OSOS Signature Date Time 4.2.2 When notified by Maintenance Department that the last Reactor Vessel Head Bolt O
is tensioned, LOG Mode 5 entry into the Unit Control Log Book.
1 4.2.3 This procedure is completes REFER to 12001-C, " Unit Heatup To Hot Shutdown (Mode 5 to Mode 4).
Completed:
l Signature Time / Date l
Reviewed:
Signature Time / Date I
Comments:
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FRoCEDURE No.
Aty:Sloy pAGE No.
VEGP 12000-C 16 15 of 15 O
5.0 REFERENCES
5.1 PROCEDURES 5.1.1 12001-C
" Unit Heatup To Hot Shutdown (Mode 5 To Mode 4) 5.1.2 12006-C
" Unit Cooldown To Cold Shutdown" 5.1.3 13005
" Reactor Coolant System Draining" 5.1.4 13011
" Residual Heat Removal System" 5.1.5 13715
" Component cooling Water System" 5.1.6 13719
" Spent Fuel Pool Cooling And Purification System" 5.1.7 14000
" Operations Shift And Daily Surveillance Logs" 5.1.8 14210 "Containmont Building Penetrations Verification-Refueling" 5.1.9 14225
" Operations Weekly Surveillance O
Logs" 5.1.10 14228
" Operations Monthly Surveillance Logs" 5.1.11 14915 "Special Condition Surveillance l
Logs 5.1.12 24518
" Reactor Coolant Pressure (Wide Range)
Protection II P-403 Analog Channel Operational Test And Channel Calibration" 5.1.13 24519
" Reactor Coolant Pressure (Wide Range)
Protection I P-405 Analog Channel Operational Test And Channel Calibration" l
END OF PROCEDURE TEXT l
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