ML20155C087
| ML20155C087 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/19/1988 |
| From: | GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20155C011 | List: |
| References | |
| 12006-C, NUDOCS 8810070235 | |
| Download: ML20155C087 (52) | |
Text
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Vogtle Electric Generating Plant *$206-C oat.
fh NUCLEAR OPERATIONS g, , g ,,
9 3/p/ff Unit COMMON Geogia Potver e.s . ~..
1 of 41 UNIT NO. DATE / /
UNIT COOLDOWN TO COLD SHUTDOWN MANUAL SET 1.0 PURPOSE NO. R This procedure provides instructions for maintaining hot standby following reactor trip, maintaining hot standby following reactor shutdown, taking the unit from hot standby to cold shutdown. Instructions are .
provided for maintaining condit4ons stable at points '
between. ;
1 2.0 PRECAUTIONS AND LIMITATIONS, 1
2.1 PRECAUTIONS 2.1.1 If this procedure is terminated prior to completion, the Unit Shift Supervisor (USS) should note the reason i for the termination in the coments section.
2.1.2 The Reactor Coolant System (RCS) pressure and temperature shall be maintained within the operating region of Figure 1, 2.1.3 Do not add positive reactivity by more than one controlled method at a time while the reactor is suberitical.
2.1.4 Whenever RCS temperature is above 160'F, at least one ,
RCP should be in operation. Preferably Pump 4 to l ensure best spray capability.
2.1.5 The hydrogen concentr.ation in the RCS must be reduced to less than Sec/kg prior to opening any RCS component.
2.1.6 The baron concentration in the pressurizar should not ba different from the RCS by more than 50 ppe.
Pressurizer Backup Heaters may be energized as necessary to equalize the boron concentration.
2.1.7 The Control Rod Drive Mechanism (CRDM) Cooling System shall be operating when RCS tammerature is greater than or equal to 350*F or when any CLDM is energized.
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i PmoCEDULE No. T.EVISloN PAGE No ,
VEGP 12006-C 9 2 of 41 l l
2.1.8 During cooldown, all Main Steam Isolation Valves l (MSIVs) should be open or atmospheric reliefs balanced l gallow uniform cooldown of all Reactor Coolant System E 5Y loops and Steam Generators (SGs). Steam dump is the preferred method of heat removal.
2.1.9 The Residual Heat Removal (RHR) Pump Suction Line should not be isolated from the RCS unless there is a steam bubble ip the Pressurizer.
2.1.10 One Reactor Coolant Pump (RCP) should be running ,
anytime RCS temperature is changed by more than 10*F in one hour. l 2.1.11 Spray flow into the Pressurizer should not be initiated if the temperature difference between the Pressurizer steam space and the spray fluid exceeds 125'F.
2.1.12 Before auxiliary spray is initiated with a temperature ,
difference between the pressurizer s team space and the l spray fluid exceeding 320'F, notify rhe USS.
(Technical Specification 5.7.1) r 2.1.13 While in Hot Standby, feeding Steam Generators should be continuous to minimize thermal stresses on the Feedwater Nozzle.
2.1.14 Vacuum should be maintained on the Main Turbine following unit shutdown until the Turbine coasts down to approximately 66% rated speed (1200 rpm) unless an ,
emergency dictates rapid coastdown of the Turbine Rotor.
2.1.15 The Main Turbine should ba kept on Turning Gear until ,
metal casing temp *eratures have returned to ambient.
Bearing lube oi1 circulation must also be maintained.
2.1.16 During periods of operation with the RCS level below the Reactor Vessel Flange elevation (194 feet elevation), ongoing work activities should be closely scrutinised and any work activity lbatted that has the potential for reducing RCS inventory.
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PftoCEDURE No. htVISloN PAGE No. i VEGP 12006-C 9 3 of 41 i i
2.2 LIMITATIONS 2.2.1 CS pressure and temperature shall not exceed 425 g and 350'F when open to the RHR system. .
2.2.2 While in Moder 3 and 4, shutdown margin shall be ;
greater than or equal to the limit specified in Technical Specification 3.1.1.2, Figure 3.1-1, l
2.2.3 While in Mode 5, shutdown margin shall be greater than l or equal to the limit specified in Technical :
Specification 3.1.1.2, Figure 3.1-2. I I
2.2.4 While in Mode 3, at least two RCS loops shall be in !
operation with the Reactor Trip Breakers closed and at least one in operation with the Reactor Trip Breakers open. (Technical Specifications 3.4.1.2) l t
2.2.5 While in Mode 4, at least two RCS loops and/or RHR ;
trains shall be operable and at least one of the RCS !
loops and/or RHR trains shall be in operation, j (Technical Specifications 3.4.1.3) j 2.2.6 While in Mode 5 with the RCS loops filled, at least'one RHR train shall be operable and in operation and either one additional RHR train operable or the secondary side ;
water level of at least two steam generators shall be (
greater than 17% wide range. (Technical Specification j 3.4.1.4.1) j 2.2.7 While in Mode 5 with the RCS loops not filled, at least !
two RNR trains shall be operable and at least one RHR l train * :,..all be in operation. (Technical Specification !
3.4.1.4.2) 2.2.8 While in Modaa 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 PORVs with lift settings which do not exceed the limits established in Figure 1,
- b. Two RHR suction Relief Valves each with a setpoint of 450 psig i31, or
- c. The RCS depressurised with an RCS vent capable of relieving at least 670 spe water flow at 470 psig.
(Technical Specification 3.4.9.3) 2.2.9 While in Modes 5 and 6, at least one Charging Pump in l the required boron injection flow path shall be operable. (Technical Specification 3.1.2.3)
- &ocEDui,E No. KEVISloN FAGE No VEGP 12006-C 9 4 of 41 2.2.10 The primary to secondary pressure differential shall not exceed 1600 psid or a secondary to primary pressure gfrentialof 70 psid during unit operations or leak 2.2.11 The maximum cooldown of the RCS shall be limited to 100*F in any one hour period. (Technical Specification .
3.4.9.1) 2.2.12 The maximum cooldown of the pressurizer shall be limited to 200*F in any one hour period. (Technical Specification 3.4.9.2) 2.2.13 The maximum temperature differential between auxiliary spray water and pressurizer steam space is 625'F.
(Technical Specification 3.4.9.2) 2.2.14 The temperature of both the primary and secondary coolant in the Steam Generators shall be greater than 70*F when the pressure of either coolant in the Steam Generator is greater than 200 psig. (Technical Specification 3.7.2) 2.2.15 While in Modes 3, 4 and 5, both channels of Source Range Nuclear Instrumentation shall be operable.
(Technical Specifications Table 3.3-1, 6.5) 2.2.16 While in Modes 3, 4, and 5 at least one channel Source Range Nuclear Instrurantation should be selected to Recorder NR-45 and the CONTROL ROOM HI TLUX LEVEL AT SHUTDOWN alarm ope'.able.
2.? 17 While in Modes 5 and 6, with the RCS level below Reactor Vesse) Flange elevation (194 feet elevation),
the RWST wil7. be operable with a minimum volume of 70,832 gallens (5% of instrument span) of water at a boron conceatration between 2000 and 2200 ppm.
3.0 INITIAL CO)DITIONS 3.1 The reactor is shut down either following normal shutdown or reactor tri withdrawn or inserted. p with Shutdown Rods either t
3.2 RCS temperature is stabilized at no load Tavg under control of the steam dumps in Steam Pressure mode or by
, operation of the Steam Generator Atmospheric Relief Valves.
3.3 RCS pressure is stable at normal operating pressure.
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PAoCEDU;sE No. i,EVISIO N prAGE NO VEGP 12006-C 9 5 of 41 3.4 At least one RCP is operating.
3.5 Pressurizer level is at approximately or returning to
$5e~ program level with either the Positive Displacement (PD) Pump or a Centrifugal Charging Pump (CCP) operating to supply normal charging and RCP seal injection flow.
3.6 SG levels are at 45% to 55% NR level with Auxiliary Feedwater (AFW) operating.
3.7 The main Turbine is tripped and either coasting down or on the Turning Gear.
4.0 INSTRUCTIONS NOTES
- a. This procedure is divided i into sections which permit i either cooldown or maintaining i stable conditions within a
- specified mode. Section E may be performed concurrently L
! , with Sections A,B,C,D. ,
- b. Asterisk (*) steps beside INITIAL steps indicates steps that generate additional documents,
- c. This procedure is written using Train A designations. Train B component designations are shown in parenthesis.
The sections of this procedure are:
A. Hot Standby Following Reactor l Shutdown or Trip.
. . B. Cooldown to not less than 350*F.
I j C. Cooldown to not less than 205'F.
, D. Cooldown to Cold Shutdown (less i
than 200'F). ;"
i l E. Secondary Plant Shutdown. l 1 4 34.%
PROCEDUCE NO. REVISloN PAGE NO
,VEGP 12006-0 9 6 of 41 SECTION A: Hot Standby Following Reactor Shutdown or Trip A4.1 g TING IN HOT STANDBY FOLLOWING REACTOR SHUTDOWN OR INITIALS A4.1.1 If this procedure has been entered from a reactor trip, then perform the following: ;
- a. INITIATE 10006-C, "Reactor Trip Review",
- i
- b. If entering this procedure from f SI termination, then perform 11886, "Recovery From ESF i Actuation", l
- c. If required, INITIATE STARTUP !
., of the Auxiliary Boiler per l 13760-C, "Auxiliary Steam Boiler System".
NOTIFY Chemistry Department ,
- d. If applicable, ENSURE that TDAFW Pump aas been stopped psr 13610, ;
"Auxiliary Feedwater System" and l returned to STANDBY per 13610, l Checklist 2, *
- e. When Source Range channels indication stabilize PLACE CONTROL ROOM HI FLUX LEVEL AT SHUTDOWN aldrm in operation by performing the following:
(1) NOTIFY IEC and RESET the .
HI FLUX AT SHITIDOWN alarm l
, setpoint per 24695 and 24696, "N.I. System Source Range Channel Calibration", ,
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(2) ENABLE THE HI FLUX AT SHUTDOWN l alarm b lacing the HIGH FLUX i AT SHU NO N L/ BLOCK l l switches to the NORh*.L. _
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PmocEDURE No. GEUIsloN UAGE No VEGP 12006-C 9 7 of 41 INITIALS (3) VERIFY annunciator SOURCE RNG F*.
HI SHUTDOWN FLUX ALARM BLOCKED ALB-10 B01 resets, (4) SELECT both channels of Source .
Range indication on Recorder NR-45, ANNOTATE chart to reflect l channels selected,
- f. CALCULATE SHUTDOWN MARGIN per 14005, "Shutdown Margin Calculations", * .
3 If necessary, BORATE the RCS per i 13009, "CVCS Reactor Makeup control System",
- h. SHUT DOWN the CVCS BTRS System by performing the following: .
(1) PLACE the CVCS BTFS SELECTOR Switch HS-10351 in the OFF ,
position. l (2) CLOSE the BTRS Domineralizer Flow Control MV-0387 to the FULLY CLOSED position,
Iodina sempre analysis per the required frequencies of Technical !
Specifications Table 4.4-4, i l
Person Contacted Date Time J. MAXIMIZE CVCS letdown purification flow rate per 13006, "Chemical And Volume Control System Startup And Normal Operation ',
/
Data TLae l
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i PRoCEDU E No. REVISloN FAGE No VEGP 12006-C 9 8 of 41 INITIALS g._,MONITORMainTurbinocoastdown, (1) ENSURE that the Turning Gear Motor Control Handswitch is in AUT0/ PULL-TO-LOCK position, .
(2) When Turbino Rotor reaches zero speed, VERIFY all Lift Pumps, Turning Gear Oil Pumps ON and Turning Gear engagement.
- 1. STOP both Heater Drain Pumps,
- m. STOP all but one Condensate Pump,
- n. REDUCE in-service Condensate Domineralizer Powdex Vessels as applicable per 13616. "Condensate Filter Domineralizar System",
- o. PLACE the Condensate and Feedwater System on Long cycle recire per 13615, "Condensate And Feedwater Systems",
- p. NOTIFY Chemistry to initiate placing condensate and feedwatsr into proper chemical wet layup,
- q. If necessary, SHUT DOWN all but one C dediating Water Pump,
- r. If necessary SHUT DOWN all but one River Makeup Pump and RECORD time in the Unit Control Log Book,
- s. ENSURE SG Blowdown Isolation Valves 1-HV-7603A(B, C, D) open.
A4.1.2 If No-Load Tavg cannot be maintained due to excessive steam demand, REDUCE steam demand by performing the followings
- b. TRANSFER the Auxiliary Steam System steam suppi j
per 13761, g to the Auxiliary Auxiliary Boiler Steam System",
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PROCEDURE No. REVISloN PAGE No VEGP 13006-C 9 9 of 41 INITIALS
- t. TRANSFER the Turbine Steam Seal Fr. 'aupply to the Auxiliary Steam Supply per 13825 "Turbine Steam Seal System",
- d. TRANSFER the SJAE steam supply to the Auxiliary Steam Supply per 13620, "Condenser Air Ejection System",
- e. If Main Generator is to be shut down ,
for more than two days, then to prevent overheating relay 360A, OPEN links TBR 28, 29 and 30, located in Protective Relay Panel Bay 4, per 00306-C, "Temporary Jumper And -
Lifted Wire Control",
- f. If the Generator Regulator Panel (1328-P5-GRC) is to be de-energized for maintenance, then OPEN links TBR 56 and 5) and TBS 4 and 5 located in Protective Relay Panel Bay 4, per 00306-C, "Temporary Jumper and Lifted Wire Control". This will prevent tripping Lockout Relaye 386 G9 and 386 G10 which trip Generator Output Breakers.
- g. At the Main Transformer Control Cabinets , de-energize the Transformer Oil Pumps and Fans per 13800, "Main Turbine O Sub-subsection 4.3.1. peration" A4.1.3 Either OPERATE unit systems as necessary to maintain the unit at Hot Standby, or l FROCEED to either Section B to initiate i unit: racidown or 12003-C, "Reactor Startup" i i
to .eturn to power.
END OF SECTION A l
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PRocEDUCE No. GEUl$loN PAGE No VEGP A2006-C 9 10 of 61 SECTION B: Cooldown to not less than 350' F NOTE pg . .
This section directs cooldown I to 375'F or any point between without crossing the boundarv '
for Mode 4 at 350'F.
B4.1 PREPARATION FOR UNIT COOLDOWN INITIALS B4.1.1 If required to cooldown secondary systems, then INITIATE Section E of this procedure.
B4.1.2 If Condenser vacuum is being maintained, then INITIATE placing a steam blanket on the MSR's Operation"per 13800, "Main Turbine B4.1.3 INITIATE pressurizer and RCS boren equalization by energizing Prescurizer Backup Heaters.
B4.1.4 MAXIMIZE CVCS letdown purification ,
flowrate, date/ time B4.1.5 INITIATE Borating the RCS to the cold shutdown boron concentration per 13009, "CVCS Reactor Makeup Cone ol System".
If applicable, PERFORM . ' *
, "Boric Acid Injection Check Valv old Shutdown i
Inservice Test" dhring the 'coration.
B4.1.6 DIRECT Chemistry to sample the RCS and ;
Pressuriser boron concentration.
B4.1.7 If withdrawn, INSERT all Shutdown l
. . Banks to the fully inserted position.
B4.1.8 OPEN the Reactor Trip breakers. _
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PRocEDULE No. LEYtSloN P AGE No VEGP 12006-C 9 11 of 41 INITIALS B4.1.9 pot currently in progress, TIATE RCS gaseous activity degas by performing the followings
- a. ENSURE that the Pressurizer ,
Steam Space Sample line is in o peration by verifying that the PRZR STM SAMPLE IRC/ ORC Valves HV-3513/NV-3514 are op '.n ,
- b. NOTIFY Chemistry to adjust the pressurizer steam space sample flow rate to maximum,
- c. tihile maintaining hydrogen cover gas, DEGAS the RCS by raising VCT gas purge flow rate to the Gaseous Waste Processing System to approximately 1.2 sch using HIC-1094, as lheited by the Hydrogen Recombiners.
B4.1.10 When notified by Chemistry that the RCS gaseous activity has been reduced to an acceptable level, TRANSFER VCT cover gas to Nitrogen and INITIATE RCS Hydrogen degas per 13007, "VCT Gas Centrol And RCS Chemical Addition".
NOTE Prior to opening the RCS to containment the hydrogen concentration shall be less than 5 cc/kg.
54.1.11 START both Containment Pre-access Jilter CTB PREACCESS FLTR UNIT-1/2 Units using/2521.
FAN HS-2620 date/ time B4.1.12 If it is Shutdown, and planned to cool if not down to performed inCold the revious three months, COMPLETE 14748, p'AFW Check Valve Shutdown I.nservice Test". __
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VftocEDUCE No. GE 451oN RAGE No VEGP 12006-C 9 12 of 41 l
INITIALS B4.2 pC,00LDOWNTO375'F B4.2.1 COMMENCE RCS/ Pressurizer pressure and !
temperature trending at 30 minute "
intervals using Data Sheet 1 and ERF computer. (Technical Specification 4.4.9.1)
Data taking and plotting may be suspended during holds in the cooldown if the duration is expected to exceed one hour.
NOTE It is recommended that the RCS temperature be maintained L between 75' F and 125' F less than pressurizer temperature.
(See Figure 1.)
B4.2.2 .0MHENCE the cooldown to 375'T and 540 psig at a recommended rate of aaproximately 50*F per hour by performing tae following:
- a. REDUCE the number of operating RCPs to two per 13003, "Reactor Coolant Pump Operation",
Pumps 4 and 1 are the preferred running pumps,
- b. INITIATE Pressurizer cooldown and depressurization by slowly opening the Pressurizer Spray Valves, _
i If necessary, selectively DE-ENERGIZE ,
I Pressurizer Back-up Hertars by placing I Control Switches to PULL-TO-LOCK, CAUTION RCS temperature and pressure j shall be maintained within j the acceptable operating region of Figure 1.
- c. Slowly ADJUST the Steam Dum) Controller setpoint or if applicable the Atmospheric Relief Valves to initiate RCS cooldown.
'Casal
PROCEQUQE NO. CEUl$1CN PAGE No VEGP 12006-C 9 83 of 41 INITIALS B4.2.3 pproximately 2185 psig, OBSERVE PRZR BLOCK VALVES HV-8000A and HV-8000B auto close.
NOTE Depending on the rate of RCS cooldown and depressurization, Step B4.2.5 may occur before Step B4.2.4.
B4.2.4 At aparoximately 550*F RCS temperature PERF0TM the following:
- a. VERITY status light LO LO TAVG TRAIN A STEAM DUMP INTL P12 illuminated,
- b. BYPASS the LO LO TAVG interlock by momentarily placing the Train A and B Steam Dump Interlock Selector Switches to the BYPASS INTERLOCK position, If operating on Steam Dumps, then VERIN Steam Dump Cooldown Valves PV-0507A,B and C are open by observing ZLB-2 on QMCB, CAUTION
'. If the RCS is allowed to pressurize above Pil and SG -
pressure is below 585 psig, Safety Injection and Steam Line Isolation will occur.
B4.2.5 At approximately 1970 pais, manually BLOCK Pressurizer Pressure and Steam Line Pressure
- Safety Injection and Steam Line Pressure ,
Steau Line Isolation signals by performing the following: ,
- a. It is is planned to cool down for ,
refueling, then PERFORM 14710, ,
"Remote Shutdown Panel Transfer Switch And Control Ctreuit 18 Month Surveillance Test" Data Sheets 3A and 3B in lieu of tho followleg substeps,
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PaoCEDU E No i EYlSiON 6 AGE No VEGP 12006-C 9 14 of 41 l i
INITIALS
- c. BLOCK the Low Pressurizer Pressure F ~-Safety Injection signal using PRZR PRESS SI BLOCK / RESET A and B handswitches HS-40012 and 40013, ,
- d. OBSERVE Status Lights PRZR TRAIN A/B SI BLOCKED illuminated, ,
- e. BLOCK the Low Steam Line Pressure Safety Injection signal using LOW ,
STM PRSS SI/SLI BLOCK RESET handswitches HS-40068 and 40069,
B4.2.6 CHECK that Pressurizer level is between 20% and 40%.
B4.2.7 As RCS pressure lower., OPEN additional Letdown Orifice Isolation Valves and ADJUST PIC-131 setpoint to maintain desired letdown flowrate.
4 B4.2.8 During RCS depressurization, MAINTAIN all RCP seal injection flow rates between 8 and 13 p m by adjusting the Charging Header Flow Controller HC-0182, i
B4.2.9 At approximately 950 psig. ISOLATE ECCS 1 Accumtlators by perferming the followings
- a. REMOVE TAG, GNLOCK and CLOSE the i Accumulator Discharge Isolation Valve
! 480V MCC Breakers UNIT 1 UNIT 2 ACCUM-1 1ABE-19 2ABE-19 ACCUM-2 IBBC-19 2BBC-19 .
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PAoCEDUCE No. LFvi$loN PAGE No.
VEGP 18006-C 9 15 of 48
! INITIALS
, CLOSE the Accumulator Isolation Valves, ACCUM-1 HV-8808A, ACCUM-2 HV-88085, .
ACCUM-3 HV-8808C, ACCUM-4 HV-8808D.
j NOT FULLY OPEN in alarm. l l
ALB06-A05,505,C05,D05, 1
OPEN, LOCK and TAG the Accumulator
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i Discharge Isolation Valves 480V MCC i Breakers, UNIT 1 UNIT 2 ACCUM-1 1ABE 19 2ABE-19 IV ACCUM-2 1BBC-19 2BBC-19 I
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a IV ACCUM-4 1BBE-19 2BBE-19 l
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,- IV I 1 I B4.2.10 Vhen steam pressure falls too less than 550 psig, at the USS's diserstion the Steam Generators may be supplied ,. i by the running Condensate Pump per .-
4 Section E4.2 of this procedure.
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PmocEOUCE No. CEUISloN PAGE No. j VEGP 12006-C 9 16 of 61 -
4 INITIALS l B4.2.11 Qgber OPERATE unit systems as necessary
! pumintain RCS within the following parameter values or PROCEED to either !
Section C to continue the cooldown or 12002-C, "Unit Heatup to Ncrmal Operating ,'i Temperature and Pressure" to consnence a
, heacup.
, i, RCS temperature 375'T *10*F '
RCS pressure 540 psig *25 psig Pressurizer level at program level .
j END OF SECTION 8
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PmoCEDUCE No. CEVISloN PAGE No VEGP 13006-C 9 17 of 41 1
SECTION C: Cooldown to not less than 205'F (
NOTE pG. -
This section directs cooldown to 225'T or any point between without crossing the boundary for Mode 5.
- 1 C4.1 PREPARATION FOR CONTINUING UNIT C00LD0k'N.
INITIALS -
C4.1.1 If required to cooldown secondary systems :
- and break condenser vacuum, then INITIATE
- SECTION E of this procedure.
i CAUTION ~;
I Maintain pressurizer cold d
calibration level greater than 17%.
C4.1.2 If it is planned to cool down to cold shutdown, then ALLOW pressurizer t level to rise during the cooldown to not greater than 80% cold calibeate.
j C4.1.3 COMMENCE RCS/ Pressurizer pressure and l temperature trending at 30 minutes
) intervals using Data Sheet 1
) and ERF computer. (Technical Specification 4.4.9.1) i 4
Plotting may be suspended during holds in the cooIdown if the duration is expected to exceed one l
, hour. !
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PRoCEQUCE No CEVISioN P AGE NQ VEGP A2006-C 9 18 of 41 INITIALS C4.2 gC00LDOWNTO225'F.
NOTE It is recommended that the .
RCS temperature be maintained between 75'F and 125'F less than pressurizer temperature. (See Figure 1.)
C4.2.1 COMMENCE the cooldown to 225'F and 250 psig at a recommended rate of approximately 50 F per hour by performing the following:
- a. CONTINUE the pressurizer cooldown and depressurization by slowly opening the Pressurizer SprayTa"Iv,es ,
If necessary, selectively DE-ENERGIZE Pressurizer Backup Heaters by placing Control Switches to PULL-TO-LOCK, CAUTION RCS temperature and pressure shall be maintained within the acceptable operating region of Figure 1.
- b. 5 iwIy ADJUST the Steam Dump controller Setpoint or if applicable the Atmospheric Relief Valves to initiate ES cooldown.
C4.2.2 If it is planned to cool down for refueling, then prior to reaching 350*F, UQUEST confirmation from Engineering / Maintenance that actions have been taken to preclude Reactor Vessel Seismic Tie Rod Binding.
C4.2.3 Prior to reaching 350'F, NOTIFT Chemistry to isolate PERMS CVCS Letdown Monitor RE-48000.
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PmocEQU ENo LEVI $loN PAGE No VEGP 12006-C 9 19 of 41 INITIALS C4.2.4 M or to reaching 350*F, PLACE the Cold m fpressure Protection System (COPS) in operation by performing the followingr
- a. If not performed in the previous ,
three months, PERFORM 14860, "PORV Cold Shutdown Inservice
- Test",
- b. ARM the A and B COPS by placing the PRZR PORV BLOCK VLV COLD OVERPRESSURE CNTL handswitches HS-80000 and 8000H to the ARM position, c.
VERIFY the following annunciators alarmed upon arming COMS:
A COLD OP ACTU VLV HV-4000A NOT FULL OPEN (ALB12 E06),
B COLD OP ACTU VLV HV-80005 NOT FULL OPEN (ALB12 F06),
- d. ENSURE PRZR PORVs PV-455A and 1-PV-456A are closed and the handswitches in AUTO,
- e. ENSURE OPEN PRZR PORV BLOCK i Valves MV-8000A and 80008, '
NOTE Step f satisfies Technical 1 Specification surveillance l 4.4.9.3.1.c
- f. VERIFT the following annunciators reset l A COLD OP ACTU VLV HV-8000A NOT FULL OPEN (ALB12 E06),
B COLD OF ACTU VLV HV-80005 NOT FULL OPEN (ALB12 F06). ,
C4.2.5 At 350*F, LOG time and date of entry into i
- Mode 4 in the Unit Control Log Book. ;
l date/ time i
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pmoctov,,E No. REYlSICN P AGE No.
VEGP 12006-C 9 20 of 41 -
INITIALS C4.2.6 Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entering Mode 4 and gar to reaching 325'T PERFORM the following: I
- a. RACK OUT and TAG both safety ,
Inj ection Pump Breakers ,
UNIT 1 UNIT 2 SI PHP-A 1AA02-16 2AA02-16 l SI PMP-B IBA03-17 2BA03-17 i
NOTE AFWAS should be defeated to the SG Blowdown Valves, Sample Valves and MDATW Pump Discharge Valves to accommodate MFP activities and/or SG draining /
filling operations without
, resulting in impacting those activities. ,
- b. At the USS's discretion, REMOVE and TAG the following fuses:
]
(1) Train A i (a) Auxiliary Rela Panel -
i Fuse Block (A1.ows full use of SG Blowdown valves),
i UNIT 1 UNIT 2 1ACPAR6-FU-2 2ACPAR6-FU-2 1
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. . IV :
(b) Auxiliary Relay Panel -
Fuse Block (Id ibits feed pump trip sipal to initiate W S),, , ;",
- UNIT 1 UNIT 2
- INCPAR-2-FU-4 1NCPAR-2-FU-4 I
- Iv m,
emocicuN$ 12006-C '
INITIALS Train B pG~- - ( 2 )
(a) Auxiliary Relay Panel -
Fuse Block (Allows full use of SG Blowdown valves),
UNIT 1 UNIT 2 IBCPAR7-FU-6 2BCPAR7-FU-6 IV (b) Auxiliary Relay Panel -
Fuse Block (Inhibits feed pump trip si nal to -
initiate S),
UNITJ, UNIT 2 INCPAR-4-MI-l 2NCPAR-4-TU-1 IV
- c. PLACE standby MDAFW Pumps handswitch in PULL-TO-LOCK.
- d. If the TDAFW Ptunp is not being utilized, CLOSE HV-5122, 5125, 5127 and 5120.
e
PRoCEQvCE No. Revision SQGENo UEGP 12006-C 9 22 of 41 INITIALS l C4.2.7 the RCS pressure is lets than 377 i{F.PLACEat.
0 andleast RCS one temperature is less RHR Train in than operation per ,1,3011, "Residual Heat Removal System
- a. OPEAATE RHR RX Outlet Valves HV-0606(0607) and Bypass Valves FV-0618(0619) to control RCS temperature as necessary and RHR flow at a minimum total flow of 3000 gpm,
- b. If applicable, PERF0RM 14896, "ECCS Check Valve Cold Shutdown.
Inservice Test", * -
- c. ENSURE RER Suction Isolation surveillance is initiated each shift per 14000, "Shift And Daily Surveillance Logs".
CAUTION While in Mode 5 with the Reactor
- Coolant Loops filled, with 1 RNR Train inoperable, the secondary side water level of at least two Steam Generators shall be greater than 17% WR.
i C4.2.8 If desired, REDUCE the number of operating 3 RCPs to one per 13003, "Reactor Coolant Pump Operation".' ,
1 Pump 4 is the preferred running pump to l 1
ensure best spray capability. ;
4 C4.2.9 When SC pressure falls to 25 pois INITIATE ali per 13601, "gning Steam Nitrogen Generatorto theMain And SG's Steam System Operation" with regulators set at 2 to 5 pais.
C4.2.10 If it is intended to perform maintenance on the RAT's during the outage, then NOTITY Maintenance to initiate work towards backfeeding through the Main Transformer and UAT's.
j u..s
. = . . _ - - _ . . . _
PaoCECURE No Revision PAGE No l VEGP 12006-C 9 23 of 61 !
INITIALS l C4.2.11 Either OPERATE unit systems as necessary ,
$5Fbaintain RCS within the following parameter values or PROCEED to either !
Section D to continua the cooldown or i 12001-C, "Unic Heacup to Hot Shutdown" to i commence a heatup.
CAUTION !
Ensure running RCP seal differential pressure is maintained greater than 200 paid. ,
RCS temperature 225 F *10'F RCS pressure 250 psis *25 psig .
END OF SECTION C 1
t 9
l f
I i
1 1
1 i
i E
I
PMocECUCE No. CEVisioN # AGE No VEGP 12006-C 9 24 of 41 l
SECTION D: Cooldown to Cold Shutdown (less than 200'F). '
Fr~- NOTE This sect.on directs cooldown i
to Mode 5 and maintains .
< temperature between 130'F and 80'F.
1 I D4.1 PREPARATION FOR CONTINUING UNIT C00LDOWN I INITIALS D4.1.1 If required to cool down secondary systems '
i and break condenser vacuum, then INITIATE 9
Section E of this precedure. ..
i D4.1.2 COMMENCE RCS/ Pressurizer pressure and temperature trending at 30 minute intervals using Data Sheet 1 and EFF .
Computer. (Technical Specification I 4.4.9.1)
(
, Plotting may be suspended during holds I l in the cooldown if the duration is [
expected to exceed one hour. l D4.1.3 ENSURE RHR letdown is in operation with flow rate greater than or equal to 75 spm. !
- f
) D4.2 RCS C00LDOWN TO BETWEEN 130'F and 80*F l I
D4.2.1 COMMENCE the cooldown at a recommended rate I of approximately 50*F per hour by ;
performing the following
) a. Slowly ADJUST the RNR Outlet Valves r a KV-0606(0607) to reduce RCS i temperature ,
CAUTION Ensure running RCP seal .
differential pressure is maintained greater than ;
, 200 paid. ,
- b. MAINTAIN Pressuriser pressure at 250 :
by selective use of l 1
psig, *25 psis,kup Pressurizer Bac Heaters. ;
l l
?
m..
l
- . _ ~
PeoCEDwE No LEYl33o5 PAGE No VEGP 12006-C 9 25 of 41 INITIALS !
D4.2.2 200*F, LOG time and date of entry 1
d
. & Mode 5 in the Unit Control Log Book. __
time /date i
D4.2.3 RACK OUT and TAG the Containment Spray pump breakers.
UNIT 1 UNIT 2 !
D4.2.4 As directed by the USS, PLACE the !
Containment Pre-access Purge System -!
4 in operation ;
Purge System"per 13125, "Containment
- i i D4.2.5 To facilitate personnel ingress and
! egress, during cold shutdown, NOTIFY ;
! Maintenance to bypass the Containment i j
Personnel Lock Interlock Systaa,
' i If desired the Containment Iquipment
} Hatch Missile Shield may be moved at ,
this time. :
D4.2.6 NOTIFY Work Planning Group te schedule j and initiate mode dependent Fire t Protection Surveillances.
j D4.2.7 When the RCS teaperature is less than [
140*F PERFORM tte following: <
l i a. If withdrawn. INSERT all Shutdown !
]
Banks to the fully inserted position, t
, l J b. OPEN the Reactor Trip Breakers, ,
I '
- c. STOP the CRDM Cooling Fans using '
1 the followLng handswitches t i
CRDH UNJT - FAN 1 HS-12273A,
- CRDM UNIT - FAN 2 HS-12274A. .I" ,
, CRDM UNIT - FAN 3 MS-12275A, CEDM UNIT - FAN 4 HS-12276A. ,
I If it is intended to remain in cold
- d. I shutdown PLACE theforSG' I
- s greater in vec layup than 4per days, 13601, then j "Steam Generator and Main Steam System Operation".
4 M3484
.,- - - - --- , - - - - - - -- _-ww
- -- -- ,-ww-,
pmocgDU ENo L.Evi$loN PAGE No VEGP 12006-C 9 26 of 41 l
INITIALS NOTE pg...
The RCP(s) shall be run for l one or more hours after reaching the desired RCS temperature .;
1
- D4.2.8 When RCS temperature is less than 110'F, I the remaining RCPs may be stopped per 13003, "Reactor Coolant Pump Operation". !
D4.2.9 If it is desired to collapse the j pressurizer bubble ano cooldown the
- pressurizer, then PERFORM the following
- a. EN3URE all CVCS Letdown Orifices are i
f,n operation.
l CAUTION Expect rapid pressurizar pressure rise with charging flow greater than letdown i flow at the point of going
, solid. Be prepared to reduce l charging flow or raise letdown 1 flow to prevent extreme l pressure fluctuations,
- b. RAISE pressurizer level by raising char flow rate and/or lowering i RHR ngownflowrate, t
j 1
- c. When the pressurizer is solid as indicated by rising RCS pressure or if PIC-131 is in A MO rising letdown j flew rate, then PERFORM the following: ,
I (1) RALANCE charging and letdown
, flow rates using HV-0128 and/ar PIC-131 to maintain RCS
. pressure at 250 psig *25 psis, l
1 l
i i
Th8l
pmocE0 vet No LtytSicN PAQt No VEGP 12006-C 9 27 of 41 INITIAL 3 NOTE
, Y*.
- Charging flow may remain greater than letdown flow as a result of coolant contraction during the cooldown.
(2) Charging /RHR letdown flow rate should be adjusted so that RHR letdown purification flow is maintained greater than or equal to 75 spm,
- (3) OPEN Pressurizer Auxiliary Spray valve KV-8145.
(a) INITIATE AUX SPRAY /PRZR DELTA-T surveillance per 14915. "Special Conditions Surveillance Logs",
(Technical Specification
- 4.4.9.2),
l (b) If pressurizer auxiliary
, spray water delta-T exceeds 320 F, then LOG the spray i valve operation in the Unit Control Log and NOTIFY Engineering to los the cycle per 50040-C, "Component !
Cyclic or Transient Limits",
(4) CLOSE the open Charging Isolation '
Valve HV-8146 or HV-8147, J
(5) Continue CHARGING through the pressurizar auxiliary spray line until pressurizer steam space temperature is less than 190*F.
D4.2.10 MAINTAIN RCS teaserature between 130'F and 80'F using K4R HX Outlet Valvas HV-0606(0607). __,
- NOTIFY Engineering to log the unit j cooldown per 50040-C, "Component
- Cyclic or Transient LLaits '.
- 4 Nb.6
Joct0V-t No MtV153oN *AGENo VEGP 12006-C 9 28 of 41 i i INITIALS !
CAUTION FG" - ;
Ensure all RCP's are shutdown. t D4.2.11 If it is desired to depressurize the RCS, .'
then PERFORM the followings
- a. INITIATE Lowering RCS pressure to atmospheric (50 psig as indicated on PI-408, 418, 428 or 438) using letdown pressure control PIC-131,
- b. When RCS pressure reaches 100 psig (150 psig as indicated on PI-408, j ,
l 418, 426, 438), CLOSE all RCP Seal Leakoff Isolation valves MV-8141A, u j B, C, D,
i i i NOTE i SI Pmp Cold Leg Isolation Valves are closed to preclude ,
l inadvertent draining of RWST to the RCS while the RCS is depressurized and partially drained.
D4.2.12 ISOLAL she Safety Injection Cold legs by ,
performing the following: :
1 !
) NY-88213, ;
l 4 c. OPEN and TAG the following SI Cold j j Lag Isolation Valves MCC breakers: '
]
UNIT 1 UNIT 2 i (1) SI PMP-A TO
- COLD LEG ISO
]
VLV HV-4421A, 1A3D-15 2A3D-15 (2) SI FMP-3 TO
) COLD LEG ISO j VLV NV-88215. 1BBD-15 2BBD-15 .,
1 d
796 1
J PRQCggy.[NQ htYl$loN P AQ[ NQ VEGP 12006-C 9 29 of 41 INITIALS CAUTION pr,% -
Prior to opening the RCS to the containment atmosphere, the RCS hydrogen concentration shall be less than 5 cc/kg.
- D4.2.13 When required INITIATE RCS draining by performing the following
4
- a. If it is intended to drain down to perform maintenance on Reactor Head, i
SG's or RCP sealm, then the fe', lowing RCS level controls should be placed ir.co offect: ~;
f (1) If it is intended to operate
. at one foot above mid nozzle i level, the preferred RHR l configuration is one train i
! operating with a flow of 3000 l
- spm, (2) If it is intended to operate
- at one foot above mid-nozzle L l
level, a minimum of two incore l thermocouples should be ,
available during periods where the Reactor Head is installed. ___
(3) I&C should be neitifisid to a install temporary remote RCS j level monitoring in the l Control Room, (4) Tyson tube watch is required any time the RCS level is
! beina changed while the RCS level is below 17% (
! (approximately 207 feet ,
elevation) pressurizer level, (5) Periodic comparison checks 4 should be made every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> i between the Control Room T g orary RCS Laval Monitors 4
and the Tyson tube, !
i l
I (6) The Control Room Monitors !
i should agree within 2 percent l i of scale with the Tyson ?ube,
- I l
'CMan I
~
PmoesCwtNo MEvlSICN PAGE No VEGP 12006-C 9 30 of 41 INITIALS (7) Two out of three Level Monitors pr, - muse agree before draining RCS below the top of the hot leg (188 feet 3 inches),
(8) 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.
(9) While operatina with Steam Generator Nozzle Dams installed.
ENSURE one Safety Injection Pump is capable of being racked in -
and operated if needed.
(10) While level is in the region of the hot legs, TREND RHR Pump Parameters on ERF for early detection of possible RHR Pum degradation due to vortexing,p (11) Minimum RCS levs1 is one 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 and MAINTAIN at this level thereafter, (12) INITIATE draining the RCS per 13005, "Raactor Coolant
. System Draining".
l
=. l
P#ocE0VCE No QEylsiCN PAGE NO l VEGP 12006-C 9 31 of 6A !
INITIALS D4.2.14 If it is intended to drain the RCS to less GEsh 25: cold calibrate pressurizer level, ,
then prior to reaching 25% ISOLATE potential dilution flow paths by performing '
{
the following: ,i
- a. CLOSE, LOCK and TAG the following l valves i
(1) UNIT 1: CVCS ISOLATION l KMW TO BA BLEND, '
1-1208-U4-175 ;
UNIT 2: CVCS ISOLATION i RMW TO BA BLEND, 2-1208-U4-175 "l (2) UNIT 1: CVCS ISOLATION !
RMW TO CVCS, 1-1208-U4-177 UNIT 2: CVCS ISOLATION RMW TO CVCS, 2-1208-U4-177
- b. ENSURE CLOSED, LOCKED and TAGGED the following valves (1) UNIT 1: CVCS OUTLET CHEM MIXING TK, 1-1208-U4-181 UNIT 2 :- CVCS OUTLET CNEM MIXING TK 2-1208-U4-181 (2) UNIT 1: CVCS SUPPLY RMW TO CHEM MIXING TK, 1-1208-U4 '.76 l UNIT 2: CVCS SUFFLY RMW i TO CNEM MIXING TK, 2-1208-U4-176
% 4%
PROCEQUnENO. LEYl54CN PAGE NO VEGP 12006-C 9 32 of 41 l
INITIALS UNIT 1: CVCS FLUSH RMW FG~- ( 3 ) TO TRN A EMFRG BORATION 1-1208-Ud-183 UNIT 2: CVCS FLUSH RMW TO TRN A EMERG
! BORATION (
! 2-1208-Ud-183 -
i (4) UNIT 1: RMWST TO BTRS ISO, 1-1208-U6-226
! UNIT 2: RMWST TO BTRS ISO, 2-1208-U6-226 .'
- c. makeup to the VCT by i
When performingnecessary,following:
the l
(1) OPEN RWST TO CCP A & B SUCTION l
Valves LV-0112D and LV-0112E, i (2) CLOSE VCT OUTLET ISOLATIONS, i LV-01125 and LV-0112C, i l
l (3) ENSURE Letdown to VCT or Hold-up Tank Valve LV-0112A is in the VCT position, i (4) When VCT level has been returned !
l to normal, OPEN LV-01125 and ,
LV-0112C then CLOSE LV-0112D
, and LV-0112E.
t ,
! D4.2.15 OPERATE unit systems as necessary to j maintain the above conditions,
- a. If required to break condenser i 4
vacuum, then PROCEED to Section t E,
- b. If it is intended to proceed to l
Mode 6, then GO to 12007 C.
"Refueling Entry",
4
- c. If it is intended to commence unit I heat up, then Go to 12001-C, "Unit j
Heatup to Hot Shutdown".
l 1
END OF SECTION D l
1
- mo I
PROCEDUCENo Alth$loN P?.GE No VEGP 12006-C 9 33 of 41 SECTION E. Se:ondary Plant Shutdown
.,. NOTE This section directs secondary 1 plant activities during unit shutdown and can be used in conjunction with primary system ;
cooldown operations. ,
The subsections of this section are: '
E4.1 Transfer From Steam Dumps to '
Atmospheric Reitef valves.
E4.2 Feeding Steam Generators With Condensate Pump. ,
E4.3 Breaking Condenser Vacuum, j E4.4 Secondary Systema activities.
! E4.1 TRANSFER FROM STEAM DUMPS TO ATMOSPHERIC RELIEF VALVES j INITIALS E4.1.1 TRANSFER to the SG Atmospheric Relief Valves f by performing the following:
- a. Slowly 0 FEN cach atmospheric retter while verif ng a reduced r saa dump demand gnal on
- UI-507,
, b. VERIFY that*the Steam Dump Control Valves close if PIC-507
, is in AUTO or if operating in MANUAL, slowly CLOSE the i i Steam Dump Control Valves while opening each atmospheric :
1 relief, !
1 c. When all Steam Dump Control !
Valves are closed. ENSURE I PIC-507 is in MANUAL, 4
- d. BA1.ANCE the positions of each utmospheric relief whila
- maintaining Tavg as desired.
d i
)
i f
4
.. _ _ - _ - ____ _=_ __- _-_.- _ .
Pecct0V-E No LEYlSION # AGE NO~
34 of 41 4
1 VEGP 12006-C 9
~
- t l
' INITIALS l I
j E4.2 ggINGSTEAMGENERATORSWITHC9',cDENSATE l 1 l E4.2.1 At the USS's discretion, INITIATE !
l
- feeding Steam Generators with the !
running Condensate Pump by performing i i
the following: [
t l a. VERIFY SG pressure is less than l
- 550 pais. ;
t i Fearings is 10 to 12 pais by local
- indications. 7 i c. OPEN the reset MFP Discharge Valve !
i by placing the Control Switch in ?
! OPEN-FULL-To-LOCK at the Main [
] Control Panel QMCB: a i
i I SGFP A HS-5208, l
- l 1 SGFP B HS-5209,
- d. If not previously performed. RESET l
! both trains of Feedwater Isolation: ;
a i
j (1) HS-40049 for Train A, i
j (2) HS-40050 for Train B. l
( i j e. OPEN all RFIV's, i I
i a f. CONTINUE maintaining desired SG l i level utilising the BFRV's, !
l !
l f
{
t l
1 l
l I l i
i I
l
! I i !
j suo :
I !
I e
peoqgovCE No CivillCN 7 AGE NQ VEGP 12006-C 9 35 of 61 INITIALS !
I E4.3 BREAKING CONDENSER VACUUM y; - l E4.3.1 If necessary, TRANSFER the Auxiliary i Steam System steam supply to the Auxiliary Boiler per 13761, "Auxiliary Steam System".
E4.3.2 TRANSFER the Turbine Steau Seal supply to the Auxiliar Steam Supp "Turbine Steam eal System,1y per 13825, E4.3.3 TRANSFER the SJAE steam supply to the '
Auxiliary Staam Supply per 13620, "Condenser Air Ejection System".
E4.3.4 CLOSE the MSIVs and Bypasses.
CAUTION i
Breaking condenser vacuum
, will result in a MFPT Low ,
j Vac Trip. If AWAS has not been defeated, then both I j MFPs tripped will result in 4
a A WAS initiation.
E4.3.5 PLACE the standby MDA W Pump (s)
I Handswitches in PULL-To-LOCK.
E4.3.6 BREAK condenser vacuum and SNUT DOWN j the Steam Jet Air Ejectors and the t
Condenser Vacuum Pumps per 13620, ,
- "Condenser Air Ejection System". '
- E4.3.7 PERFORM the following to reset the l j AWAS signal ,
i a, RESET the A WAS by resetting one .
l MrFT Low Vacuum Trip by '
) , momentarily placing the MFPT-A(B) l t VAC TRIP BYPASS Handsvitch to !
RESET position and MTFT A(5)
TRIP RESET HS-3169 (3170) to the l RESET position. , l
- 1 i b. If running a MDA N Pump, thac, I d
THROITLE the AW Flow ConMol !
Valves to the pre-initiation l l
flow rate. l f
00$
i
I PAoGOURE No. GEVISloN WAGE No, I VEGP 12006-C 9 36 of 41 )
l INITIALS 4 . If applicable, ENSURE the SG P Blowdown Isolation Valves HV-7603A(B,C,D) open.
E4.3.8 After the condenser pressure reaches ,
atmospheric, SHUT DOWN the Turbine Steam Seal System Seal System"per 13825, "Turbine Steam E4.3.9 MAINTAIN the main Turbine and MFPTs on Turning Gear per 13800, "Main Turbine Operation" and 13615, "Condensate and Feedwater Systems".
E4.4 SECONDARY SYSTEM ACTIVITIES v E4.4 ' If condensate and feedwater cleanup is not anticipated, then when condensate and feedwater metal temaeratures are less than 200*F, SHUT DOWN the Condensate and Feedwater System per And Feedwater Systems,1,3615, Condensate E4.4.2 NOTIFY Chemistry and SHUT DOWN the Condensate Filter Demineralizer System per 13616, "Condensate Filter Demineralizer System".
E4.4,3 If the secondary outage is planned to exceed 10 days, then PERFORM the followings
- a. When condensate and feedwater metal temgeratura is between 90'F and 200 F, COORDINATE with Chemistry and PLACE the Feedwater Heaters in wet layup,
- b. When Turbine metal temperatures reach ambient, REMOVE Turbine from Turning Gear per 13800, "Main Turbine Operation",
- c. During the unit outage, once a week, PLACE the Turbine on Turning Gear for 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. ;
I N
PCCCEDUCE No. ,
REVISloN PAGE NO-VEGP 12006-C 9 37 of 41 1
INITIALS E4.4.4 required, PLACE a steam blanket "the MSRs per 13800, "Main Turbine Operation".
l E4.4.5 If required, for Condenser Waterbox or _. ;
Circulating Water System maintenance, SHUT DOWN the Circulating Water System per 13724, "Circulating Water System".
If required for maintenance or inspection, then INITIATE draining of the Condenser Waterboxes per 13724, "Circulating Water System".
E4.4.6 If main generator maintenance or inspection is planned, then INITLATE 'H tho main generator per :
purging"Ge.nerator 13810 Gas System". .
If hydrogen atmosphere is to be maintained, then MINIMIZE usage ,
during the outage by reducing h drogen pressure to not less e an 5 psig.
4 E4.4.7 SHUT DOWN the Isophase Bus Duct Cooling i System by performing the followings
- b. At local Panel PLCB, STOP the running fan using HS-16550 for Fan No. 1 and/or HS-16551 for
- Fan No. 2.
~
signatura Data / Tina l Reviewed i signatura pate/ Time i l
l
- Comments
)
4 I
mus 1 -- - . - - . - - - _ . . . _ _ _ _ , - . , _ _ _ _ , , _ _ , _ . _ _ _ _ _ . _ , _ , , , _ , , _ _ _ _ _ . _ _ , _ _ _ _ . , , , _ _ _ . _ , . _ _ _ _ _ _ , _ _ , . _ _ _ _ _
PQoCEDUCE No. GEVISloN PAGE No.
VEGP 12006-C 9 38 of 41
5.0 REFERENCES
5.1 p.EDURES 5.1.1 10006-C, "Reactor Trip Review" 5.1.2 12001-C, "Unit Heatup To Hot Shutdown" -
5.1.3 12002-C, "Unit Heatup"To Normal Operating Temperature Av4 Pressure 5.1.4 12003-C, "Reactor Startup" 5.1.5 13003, "Reactor Coolant Pump Operation" >
5.1.6 13005, "Reactor Coolant System Draining" d
5.1.7 13006, "Chemical And Volume Control System Startup And Normal Operation" -
5.1 8 13007, "VCT Gas control And RCS Chemical Addition" 5.1.9 13009, "CVCS Reactor Makeup Control System" 5.1.10 13010, "Boron Thermal Regeneration System" 5.1.11 13011, "Residual Heat Removal System" 5.1.12 13120, "Contaienent Building Cooling Systems' f
l 5.1.13 13125, "Containment Purge System" 5.1.14 13601, - -
"Steam Generator And Main Steam System Operation"
~
5.1.15 13605, "Steam Generator Blowdown Processing .
System" 5.1.16 13610, "Auxiliary Feedwater System" l
5.1.17 13615 "Condensate And Feedwater Systems"
- 5.1.18 13616 "Condensate Filter Domineralizar System"
! 5.1.19 13617, "Feedwater Heater Extraction, Vent And Drain System" 5.1.20 13620, "Condanser Air Ejection System" 5.1.21 13724, "Circulating Water System" l
i,
.- r.- - - _ , . , , . . _
,m,_. __,,,,,_ _ , , _ _ . . , _ _ _ _ _ _ _ , _ _ , _ _ , _ _ _ _ _ _ _ , ,_ _ _ , , _ _ _ . _ , . _ _ _ _ _ , , _ _ , , _ , _ _ , _ _ _ _
PACCEDUCE No. EEVISION PAGE No.
VEGF 12006-C 9 39 of 41 5.1.22 13760, "Auxiliary Steam Boiler System" 5.1.23 g741, "Auxiliary Steam System" 5.1.24 13800, "Main Turbine Operation" 5.1.25 13810, "Generator Gas System" .
5.1.26 13825, "Turbine Steam Seal System" 5.1.27 14000, "Operations Shift and Daily Surveillance Logs" 5.1.28 14005, "Shutdown Margin Calculations" 5.1.29 14748, "AFW Check Valve Cold Shutdown Inservice Test" ,,1 5.1.30 14915, "Special Conditions Surveillance Logs" 5.1.31 24695, "N.I. System Source Range Channel Calibration" 5.1.32 24696, "N.I. System Source Range Channel Calibration" END OF PROCEDURE TEXT l
1 l
43HS
, 1 l paccEDURE NO. EEWSION PAGE NO l
VEGP 12006-C 9 40 of 41 I
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FIGURE 1 - RCS PRESSURE TEMPERATURE LIMITS l l
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P;;OCEDUME No. ?!EVISION FAGE No.
VEGP 12006-C 9 41 of 41 Sheet 1 of 1 UNIT NO. DATE / / l RCS/PRZR TEMPERATURE AND PRESSURE p ..
DATA SHEET 1 Lowest Channel of TI-0413B TI-0423B TI-04333 PI-438LR or TI-0443B TI-0454 PI-405WR PRZR/RCS TIME RCS TEMP PRZR TEMP PRZR PRESS DELTA T
(
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Attachment 6 RACF.WAY DRAWINGS COLOR CODED FOR SAFE SHUTDOWN CIRCUIT LOCATIONS P = PINK B = BLUELINE AX3DF300-P 2X3DF35D-P 2X3DF522-B AX3DF302-B 2X3DF35E-P T4X3DF523-D AX3DF399-P 2X3DF35F-B 2X3DF524-B 1X3DF302/1-P 2X3DF361-B 2X3DFS26-B IX3DF304-P 2X3DF362-B 2X3DF529-B 1X3DF300-P 2X3DF363-B 2X3DF52A-B 1X3DF30F-P 2X3DF36A-B 2X3DF52B-B 1X3DF314-P 2X3DF36B-3 2X3DF52C-B 1X3DF31D-P 2X3DF071-B 2X3DF52D-B IX3DF31E-P 2X3DF372-B 2X3DF52E-P 2X3DF160-B 2X3DF373-B 2X3DF52F-P 2X3DF162-B 2X3DF300-B 2X3DF530-B 2X3DF163-D 2X3DF42E-P 2X3DF532-B 2X3DF172-B 2rJDFv10-B 2X3DF532-P 2XSDF173-B 2X3DF431-B 2X3DF533-B 2X3DF340-B 2X3DF43:-P 2X3DF534-B 2X3DF340-P 2X3ur=44-P 2X30F535-B 2X3DF341-B 2X3DF441-P 2X3DF537-B 2X3DF342-B 2X3DF442-P 2X3DF538-B 2X3DF343-B 2X3DF443-P 2X3DF539-B 2X3DF344-B 2X3DF444-P 2X3DF53A-B 2X3DF346-B 2X3DF445-P 2X3DF53A-P 2X3DF347/1-B 2X3DF446-B 2X3DF53B-B 2X3DF347/2-B 2X3DF44A-B 2X3DF53C-P 2X3DF348-B 2X3DF44B-B 2X3DF530-B 2X3DF349-B 2X3DF44D-B 2X3DF53D-B 2X3DF34C-P 2X3DF451-P 2X3DH8C3-P 2X3DF34E-B 2X3DF452-P 2X3DH8C5-P 2X3DF350-B 2X3DF453-P 2X3DH8C7-P 2X3DF351-B 2X3DF454-P 2X3DF8D1-P 2X3DF352-B 2X3DF455-P 2X3DH8D4-P i 2X3DF353-B 2X3DF456-P 2XSDH8D5-P ,
2X3DF354-B 2X3DF45B-P 2X3DH8D7-B l 2X3DF357-B 2X3DF450-P 2X3DH8E3-P '
2X3DF358-B 2X3DF45E-B 2X3DH8E4 P 2X3DF359-B 2X3DF45F-P 2X3DF8F1-P i 2X3DF35A-B 2X3DF522-P 2X3DH8F2-P 2X3DH8F3-P 1 2X3DH8F4-P l
,m-- -.- -- , - - , - - - - - - . _ - - - - - - .
Attachmant 7 1
FIRE AREA DRAWINGS
-e AX4DJ8007 Av. 4IU8024 AX4DJ8008 AX4IAT8025 AX4IU8009 AX4DJ8026 AX4DJ8010 AX4DJ8027 AX4DJ8011 AX4DJ8028 AX4DJ8012 AX4DJ8029 AX4DJ8013 AX4DJ8030 AX4DJ8014 AX4DJ8031 AX4DJ8015 E<4DJ8032 AX4DJu016 AX4DJ8041 AX4DJ8017 AX4DJ8042 AX4IU80* 8 AX4DJ8043 AX4DJ8019 AX4DJ8044 AX4DJ6020 AX4DJ8045 AX4DJ8021 AX4IU8046 AX4DJ8022 AX4DJ6047 AX4DJ8023 AX4DJ8048 i
2 i
- l
Attachment 8 P3DCESS A'O INSTEM2.TATION D:AGRAMS 22:4D3100 2X4DB168-3 2X4D3101 2X403170-1
%E4D3102 2X4D3170-2 2X4D3111 2X4D3203 2X4D3112 AX4D3204-1 2X4DB113 AX4D3204-2 2X4DB114 2X4D3205-1 2X4D3115 2X4D3205-2 2X4DS116-1 AX4DB206-1 2X4D3116-2 AX4D3206-2 2X4DB118 AX4D3206-3 2X4D3119 2X4D3207-2 2X4D3120 2X1DB208 4 2X4D3121 2X4D3208-2 2X4DB122 2X4D3208-3 2X4D3131 2X4D3209 2X4D3133-1 2X4DB210 2X4D3133-2 2X4D3211 2X4DB134 2X4D3212 2X4D3135-1 AX4D3215 2X4DB135-2 AX4DB216 2X4D3136 2X4DB217 2X4D3137 2X4DB221 2X4D3136-1 AX4D3223 2X4DB138-2 AX4DB225 2X4D3139 2X4D3227 2X4D3140 2X4DB228 2X4D3159-1 2X4D3233 2X4DB159-2 2X4DB234 2X4D3159-3 AX4D3241 2X4D3161 I 2X4D3174-1 2X4D3161-2 tnru 2X403161-3 2X4D3174-6 CX4D3173-1 thru CX4D3173-6
. _ . . - . . . _ . _ _ _ , _ _ . , _ - - _ - . _ . _ _ . ~ _ . _ _ _ _ - _ . _ _ _ _ . _ _ _ _ _ _ . _ _ _ . _ . - . _ _ _ . . _ _ _ _ _ _ _ . _ _
l Attachmsnt 9 l
l l
l " M CAL & LINE DRAWINGS 1
1 2X3D-AA-A01A 2X3D-AA-D02A 2X3D-AA-D023 2X3D-AA-D03A 2X3D-AA-D033 2X3D-AA-E01A 2X3D-AA-E04A 2X3D-AA-EOSA 2X3D-AA-E06A 2X3D-AA-E07A 2X3D-AA-E10A 2X3D-AA-E16A 2X3D-AA-E17A (
2X3D-AA-F03A 2X3D-AA-F04A 2X3D-AA-F11A 2X3D-AA-F11B 2X3D-AA F12A 2X33-AA-F123 2X3D-AA-F16A 2X3D-AA-F17A 2X3D-AA-F?8A 2X3D-AA-F1GA 243D-Ah-F24A 2X33-AA F25A 2X3D-AA-F36A 2X3D-AA-F38A 2X3D-AA-G014 2X3D-AA-G02A 2X3D AA-G02C 2X3D-AA-H01A 2X3D-AA-H01B 2X3D-AA-H02A I 2X3D-AA-H023 l 2X3D-AA-H04A l 2X3D-AA-H05A I
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Attachment 10 LOOP DIAGRAW 2X5DV009 2X5DV113 2X5DV010 2X5DV149 2X5DV041 2X5DV150 2X5DV042 2X5DV185 2X5DV043 2X5DV136 2X5DV044 2X5DV191 2X5DV065 2X5DV192 2X5DV066 2X5DV288 2X5DV067 2X5DV289 2X5DV068 2X5DV332 2X5DV069 2X5DV333 !
2X5DV070 2X5DV428 !
2X5DV071 2X5DV429 2X5DV072 2X5DV430 2X5DV079 2X5DV431 2X5DV080 2X5DV489 2X5DV091 2X5DV490 2X5DV092 2X5DV492 2X5DV093 2X5DV495-1 2X5DV112 2X50V495-2 i
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Attachment 11 (sheet 1 of 4)
ELECTRICAL E N '2ARY DP1MINGS 2X3D-BA-D02B 2X3D-BA-E04A 2X3D-BA-D02C 2X3D-BA-E04B 2X3D-BA-D02D 2X3D-BA-E04D 2X3D-BA-D02E 2X3D-BA-E04E 2X3D-BA-D02F 2X3D-BA-E04F 2X3D-BA-D02X 2X3D-BA-H01A 2X3D-BA-D02L 2X3D-BA-H01B 2X3D-BA-D033 2X3D-BA-H01C 2X3D-BA-D030 2X3D-BA-H01D 2X3D-BA-D03D 2X3D-BA-H01E 2X3D-BA-D03E 2X3D-BA-H01F 2X3D-BA-D03G 2X3D-BA- H01G 2X3D-BA-D03H 2X3D-BA-H02A 2X3D-BA-D03J 2X3D-BA-H02B 2X3D-BA-E02A 2X3D-BA-H02C 2X3D-BA-E02B 2X3D-BA-H02D 2X3D-BA-E02C 2X3D-BA-H02E 2X3D-BA-202D 2X3D-BA-H02F 2X3D-BA-E02? 2X3D-BA-H02G 2X3D-BA-E02Q 2X3D-BA-H03A 2X3D-BA-E02R 2X3D-DA-H03B 2X3D-BA-202S 2X3D-BA-H03C 2X3D-BA-E02V 2X3D-BA-H03D 2X3D-BA-E02H 2X3D-BA-H03G 2X3D-BA-E02X 2X3D-BA-H04A 2X3D-BA-E02Y 2X3D-BA-H04B 2X3D-BA-E02Z 2X3D-BA-H04C 2X3D-BA-H04D 2X3D-BA-H04F 2X3D-BA-JO2A 2X3D-BA-J023 2X3D-BA-J02C 2X3D-BA-J02D 2X3D-BA-J02E 2X3D-BA-J02F 2X3D-BA-J04A 2X3D-BA-J043 2X3D-BA-J040 2X3D-BA-J04D 2X3D-BA-J04G 2X3D-BA-J04H 2X3D-BA-M11A !
1 1
l 1
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Attachment 11
( sheet 2 of 4 )
ELECTRICAL ELEMBh ARY DRAWINGS ,
, 2X3D-BC-C06D 2X3D-BD-303F 2X3D-BC-C07C 2X3D-BD-B03H 2X3D-BC-C07D 2X3D-BD-303K 2X3D-BC-C08C 2X3D-BD-303R 2X3D-BC-C08D 2X3D-BD-C01A 2X3D-BC-C09C 2X3D-BD-C01B 2X3D-BC-C09D 2X3D-BD-C01F 2X3D-BC-F02A 2X3D-BD-C01G 2X3D-BC-F02C 2X3D-BD-C01Q 2X3D-BC-F02D 2X3D-BD-C01T 2X3D-BC-F02G 2X3D-BD-C01U 2X3D-BC-F04A 2X3D-BD-C01V 2X3D-BC-F043 2X3D-BD-C01W 2X3D-SC-F05A 2X3D-BD-C02F 2X3D-BC-F05B 2X3D-BD-C02G 2X3D-30-F08A 2X3D-BD-C02H 2X3D-BC-F083 2X3D-BD-C02J 2X3D-BC-F06C 2X3D-BD-C02P 2X3D-BC-F06D 2X3D-BD-C02Q 2X3D-BC-QO1J 2X3D-BD-C03F 2X3D-BC-001K 2X3D-BD-C03G 2X3D-BC-QO1S 2X3D-BD-CO3J 2X3D-BC-Q01T 2X3D-BD-CO3K 2X3D-BC-QO1W 2X3D-BD-C03T 2X3D-BC-001X 2X3D-BD-C03::
2X3D-BC-QO2A 2X3D-BD-C04H 2X3D-SC-0023 2X3D-BD-C04J 2X3D-BC-QO2B 2X3D-BD-C04L 2X3D-BC-QO2F 2X3D-BD-C04U 2X3D-BC-QO2H 2X3D-BD-COSA 2X3D-BC-002J 2X33-BD-C05B 2X3D-BC-QO3P 2X3D-BD-C05C l 2X3D-3C-QO30 2X3D-BD-C05D l 2X3D-DC-QO3R 2X3D-BD-C05E !
2X3D-BC-Q04C 2X3D-BD-C05G 2X3D-BD-CC5H 2X3D-BD-C05L 2X3D-BD-C05P i 2X3D-BD-C05Q l
i I
1 1
Attachment 11
( sheet 3 of 4 )
w ELECTRICAL ELEG.NTARY DRAWINGS (cont'd) 2X3D-BD-DO2E 2X3D-BD-KO4E 2X3D-BD-D02F 2X3D-BD-K04F 2X3D-BD-D02L 2X3D-BD-K04Y 2X3D-BD-D02M 2X3D-BD-K04Z 2X3D-BD-D02V 2X3D-BD-K05U 2X3D-BD-D02W 2X3D-BD-K05V 2X3D-BD-D04H 2X3D-BD-K05W 2X3D-BD-D05H 2X3D-BD-K05X 2X3D-BD-D05J 2X3D-BD-LO1A 2X3D-BD-D05K 2X3D-BD-LO1B 2X3D-BD-E01A 2X3D-BD-LO10 2X3D-BD-E013 2X3D-BD-LOID 2X3D-BD-E020 2X3D-BD-LO1E 2X3D-BD-E02D 2X3D-BD-LO1F 2X3D-BD-E02E 2X3D-BD-LO3A 2X3D-BD-E02F 2X3D-BD-LO3B 2X3D-BD-E02G 2X3D-BD-LO3F 2X3D-BD-E02H 2X3D-BD-LO3G 2X3D-BD-E02J 2X3D-BD-LO3H 2X3D-BD-E02K 2X3D-BD-LO3J 2X3D-BD-E02N 2X3D-BD-UO1C 2X3D-BD-E02F 2X3D-BD-UO1D 2X33-BG-C013 2X3D-BD-E020 2X3D-3G-C01E 2X3D-BD-E03M 2X3D-BG-C01F 2X3D-BD-K03A 2X3D-BG-C01Q 2X3D-BD-K033 2X3D-BG-C01R i
2X3D-BD-K030 2X3D-BG-C01V 2X3D-BD-K03D 2X3D-BG-C01X 2X3D-BD-K03E 2X3D-BG-C01Y 2X3D-BD-K03F 2X3D-BG-C01Z 2X3D-BD-K03G 2X3D-BG-C02J 2X3D-BD-K03H 2X3D-BG-C02Y 2X33-BD-K04A 2X3D-BG-C022 2X3D-BD-K04B 2X3D-BG-C04A 2X3D-BD-K040 2X3.>-EG-C04B 2X3D-BD-K04D 2X3D-BG-C04N 2X3D-BG-C04F 1
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Attachment 11
( sheet 4 of 4 )
ele,CIRICAL ELWINTARY DRAWINGS (cont'd1 l
l 2X3D-BG-C04Q 2X3D-BG-G03A i 2X3D-BG-C04R 2X3D-BG-G03B i 2X3D-BG-C04S 2X3D-BH-G01X l 2X3D-BG-C04T 2X3D-BH-G01Z l 2X3D-BG-C04U 2X3D-BH4023 l 2X3D-BG-C04V 2X3D-BH-G02D 2X3D-BG-C07B 2X3D-BH-G03A 2X3D-BG-C07C 2X3D-BH-GO3B 2X3D-BG-C07M 2X3D-CD-B14A 2X3D-BG-C07N 2X3D-CD-315A 2X3D-BG-C07R 2X3D-CD-002B 2X3D-BG-D05A 2X3D-CD-C020 2X3D-BG-D05B 2X3D-CD-C02F i 2X3D-BG-D05C 2X3D-CD-C02H 2X3D-BG-D05D 2X3D-CD-C02J 2X3D-BG-D05E 2X3D-CD-CO3B 2X3D-BG-D05F 2X3D-CD--CO3D 2X3D-BG-D050 2X3D-CD-C03F 2X3D-BG-D05H 2X3D-C" D0'iH 2X3D-BG-D05N 2X3D-CD-CO3J 2X3D-BG-D05F 2X3D4D-S02E
- 2X3D-BG-F01B 2X3D-CE-B13B 2X3D-BG-F01C 2X3D-CE-D16A 2X3D-BG-F01E 2X3D-CE-D16B 2X3D-BG-F01F 2X3D-CE-D20A 2X3D-BG-F01H 2X3D-CE-D23A 2X3D-BG-F01J 2X3D-BG-F01X 2X3D-BG-F01L 2X3D-B'3-F01M 2X3D-BG-G01M 2X3D- BG-GOIN 2X3D-BG-G02A l 2X3D-BG-G02B 2X3D-BG-G02C 2X3D-BG-G02D l
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Attachment 12 EMERGENCY LIGHTING UNIT LOCATION DRAWING 2X3DG341 2X3DG342 2X3DG343 ;
2X3DG344 2X3DG345 2X3DG351 2X3DG352 2X3DG303 2X3DG354 2X3DG37A 2X3DG355 2X3DG356 2X3DG361 2X3DG362 !
2X3DG363 2X3DG364 2X3DG372 2X3DG372 2X3DG373 2X3DG390 2X3DG441 2X3DG442 2X3DG443 2X3DG444 2X3DG445 2X3DG446 2X3DG451 2X3DG452 2X3DG453 ,
. 2X3DG454
! 2X3DG456 2X3DG460 2X3DH804 2X3DH8D3 l 2X3DH8F4 l
i
1 Attachment 13 i BOUIPMENT LOCATION ORAWINGS 2X4DE312 2X4DE313 2X4DE314 2X4DE315 2X4DE316 2X4DE317 L 2X4DE318 l 2X4DE319 l 2X4DE320 !
2X4DE321 l 2X4DE322 '
2X4DE323 ,
l 2X4DE324 l 1 2X4DE325 2X4DE327 l 4
2X4DE328 ,
2X4DE329
, 2X4DE330 2X4DE331 1
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