ML20092F813

From kanterella
Jump to navigation Jump to search
Rev 15 to 12006-C, Unit Cooldown to Cold Shutdown
ML20092F813
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 03/08/1990
From: Bockhold S
GEORGIA POWER CO.
To:
Shared Package
ML20092F288 List: ... further results
References
CON-IIT05-002-134-90, CON-IIT05-078-90, CON-IIT5-2-134-90, CON-IIT5-78-90, RTR-NUREG-1410 12006-C, NUDOCS 9202190513
Download: ML20092F813 (45)
v • d • e


Text

_ _. _ _ _ _. _ _

1 Appr:41

'1 p,,c.a,, u,.

yr 4 Y:

Vogtle Electric Generating Plant 12006-C h

NUCLEAR OPERATIONS I

o*t*

15 Unit _ COMMON GeorgiaIbwer e...go. a o g

i UNIT NO.-

DATE

/

/

t l

UNIT COOLDOWN TO COLD SHUTDOWN i

1.0 PURPOSE 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 arovided for maintaining conditions stable at points

3etween, 4

i

\\

- -['

2.0 PRECAUTIONS AND LIMITATIONS

' =*

yn 4t tGp gg (;;; 1 -.

2.1 PRECAUTIONS 2.1.1 If this procedure is terminated prior to completion, the Unit Shift Supervisor (USS) should note the reason for the termination in the comments section.

2.1.2 The Reactor Coolant System (RCS) pressure and temperature shall be maintained within the operating region of RCS Pressure Temperature Limits (Plant Technical Data Book Tab 3.1).

2.1.3 Da 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 ensure best spray capability.

2.1.5 Prior-to opening any portion of the RCS to the atmosphere, the hydrogen concentration in the affected portion must be reduced to less than Sec/kg.

2.1.6 1he boron concentration in the pressurizer should not-be different from the RCS by more than 50 ppm.

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 temperature is greater than or equal to 350'F-or when any CRDM-is energized.

9202190513 920116 POR ADOCK 05000424 S

PDR 7031014 W81JD

. -.,., _ _.,.... - _. - - ~,.., - _ - - -..,. _, -

..m.-,.-_.,..._..

---...-m,.,,.,.-_-,-_.-,--e.--._

__--,..-.~.-,--,m-,

c.. _.,,,

(Wi" liR. No.

s mEvisios EtW ~

t 74GP 12006-C 15 2 of 45 O-2.1.8 During cooldown, all Main Steam Isolation Valves (MSIVs) should be open or atmospheric reliefs balanced to allow uniform.cooldown of all Reactor Coolant System (RCS) 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 in 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.

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 g0'F, notify the USS.

resourizer steam space and the spray fluid exceeding 3t (Technical Specification 5.7.1) 2.1.13 While in Hot Standby, feeding Steam Generators should be continuous to minimize thermal stresses on the Feedwater Nozzle.

O 2.1.14 Vacuum should be maintained on the Main Turbine "711owing unit shutdown until the Turbine coasts down to approximately 661 rated speed (1200 rpm) unless an emergency dictates rapid coastdown of the Turbine Rotor.

2.1.15 If Main Turbine coastdown is in progress, then coastdown parameters should be monitored per 13800,

" Main Turbine Operation" Sub-subsection 4.3.2.

2.1.16 The Main Turbine should be kept on Turning Gear until metal casing temperatures have returned to ambient.

Bearing lube oil circulation must also be maintained.

2.1.17 During periods of operation with the RCS level below the Reactor Vessel Flange elevation (194 fact elevation), ongoing work activities should be closely scrutinized and any work activity limited that has the potential for reducing RHRS capability.

I

PACK.EDURE No.

REVl$loN

' didk'$h' '

'~

VEGP 12006-C 15 3 of 45 2.2 LIMITATIONS'

}

2.2.1 The RCS pressure and temperature shall not exceed 425 psig and 350'F when open to the RHR system.

2.2.2 While in Modes 3 and 4, shutdown margin shall be greater than or equal tci the limit specified in Technical Specification 3.1.1.2, Figure 3.1-1.

2.2.3 While 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.

2.2.4 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) 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.

(Technical Specifications 3.4.1.3) 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 1cvel of at least two steam Jenerators shall be i

greater than 17% wide range.

(Tecinical Specification 3.4.1.4.1) 2.2.7 While in Mode 5 with the RCS loops not filled, at least two RHR trains shall be operable and at least one RHR train shall be in o Valves 1208-U4-175,peration.

Reactor Makeup Water 1208-U4-176, 1208-U4-177, and 1208-U4-183 shall be closed and secured in position (by mechanical atops), except 1208-U4-176 and 1208-U4-177 may be opened for short periods of time for chemistry control provided the Hi 71ux at Shutdown Ai, arm is operable with a setpoint of less than or equal to 2.30 tiues background.

(Technical Specification 3.4.1.4.2) 2.2.8 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 PORVs with lift settings which do not exceed i

the limits established in Figure 1, b.

Two RHR suction Relief Valves each with a setpoint of 450 psig *3%, or Os The RCS depressurized with an RCS vent capable of c.

relieving at least 670 gpm water flow at 470 psig.

(Technical Specification 3.4.9.3) nun

mocEDURE No.

AbstoN "PAEE So.

~ ~ ~ ~ " " '

VEGP 12006-C 15 4 of 45 2.2.9 While in Modes 5 and 6, at least one Charging Pump in O

the required boron injection flow path shall be operable.

(Technical Specification 3.1.2.3) 2.2.10 The primary to secondary pressure differential shall not exceed 1600 psid or a secondary to primary pressure differential of 670 psid during unit operations or leak tests.

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 aressurizer shall be limited to 200*F in any one '1our 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 poig.

(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.B) 2.2.16 While in Modes 3, 4, and 5 at least one channel Source Range Nuclear Instrumentation should be selected to Recorder NR-45 and the CONTROL ROOM HI FLUX LEVEL AT SHUTDOWN alarm operable.

2.2.17 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 (91 of instrument span) of water at a boron concentration between 2400 and 2600 ppm.

3,0 INITIAL CONDITIONS 3.1 The reactor is shut down either following normal shutdown or reactor trip with Shutdown Rods either withdrawn or inserted.

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.

mus

. - - -.. ~,.

_ _- ~

_ ~.

PAoCEDURE No.

REVl5loN FAGE NoI

~

~~

VEGP 12006-C 15 5 of 45

=

3.4 At least one RCP is operating.

[)

3.5 Pressurizer level is at aparoximately or returning to the program level with eitler 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 into sections which permit either cooldown or maintaining stable conditions within a specified mode.

Section E may be performed concurrently with Sections A,B,C,D.

L 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 r

shown in parenthesis, i

l The sections of this procedure are:

A.

Hot Standby Following Reactor Shutdown or Trip.

B.

Cooldown to not less than 350'F.

i C.

Cooldown to not less than 205'F.

D.

Cooldown to Cold Shutdown (less than 200'F).

l E.

Secondary Plant Shutdown.

I O

i r

,e

.-----,--e-+w-----

w~

_m.. _ _ _ _ _ _

PAoCEDURE No REVIGoN PAGE No.

VEGP 12006-C 15 6 of 45

(}

UNIT NO.

~

SECTI0N As Hot Standby.Following Reactor Shutdown or Trip A4.1 OPERATING IN HOT STANDBY FOLLOWING REACTOR SHUTDOWN OR TRIP:

INITIALS A4.1.1 If this procedure has been entered from a reactor trip, then perform the followings a.

INITIATE 10006-C, " Reactor Trip Review",

b.

If entering this procedure from SI termination, tien perform 11886, " Recovery From ESF Actuation",

c.

MONITOR Main Turbine coastdown parameters per 13800, " Main Turbine Operation" and:

(1)

ENSURE that the Turning Gear O

Motor Control Handswitch is in AUT0/ PULL-TO-LOCK position, (2)

When Turbine Rotor reaches zero speed, VERIFY all Li.ft Pumps.

Turning Gear Oil Pumps ON and Turning Gear engagement.

d.

If ap)licable, ENSURE that TDAFW Pump '1as been stopped per 13610,

" Auxiliary Feedwater System" and returned to STANDBY per 13610, Checklist 2, e.

If not performed in the previous 92 days COMPLETE 14423, " Source Range NIS Channel Analog Operational Test" (Technical Specification Table 4.3.1 item 6),

O i

doCEDURE No.

AEVISloN PAGE No-VEGP 12006-C 15 7 of 45

()

UNIT NO.

INITIALS f.

When Source. Range channels indication stabilizo PLACE CONTROL ROOM HI FLUX LEVEL AT SHUTDOWN alarm in operation by performing the followings (1)

NOTIFY I&C and if necessary, RESET the HI FLUX AT SHUTDOWN alarm setpoint per 24695 and

24696, "N.I.

System Source Range Channel Calibration".

(2)

ENABLE THE HI FLUX AT SHUTDOWN alarm by placing the HIGH FLUX AT SHUTDOM4 NORMAL / BLOCK switches to the NORMAL, (3)

VERIFY annunciator SOURCE RNG 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 channels selected, g.

CALCULATE SHUTDOWN MARGIN per 14005, " Shutdown Margin Calculations",

h.

If necessary, BORATE the RCS per 13009, "CVCS Reactor Makeup control System",

i.

SHUT DOWN the CVCS DTRS System by performing the following:

(1)

PLACE che CVCS BTRS SELECTOR Switch HS-10351 in the OFF

position, (2)

CLOSE the BTRS Demineralizer Flow Control HV-0387 to the FULLY CLOSED position.

l O

7c:ao

._________..m hRdCd5 met [d REvlSION PAGE No.

VEGP 12006-C 15 8 of 45 9

UNIT NO.

INITIALS j.

DIRECT Chemistry to sample the RCS hydrogen, gas activity concentrations and PERFORM an RCS Iodine sample analysis per the required frequencies of Technical Specifications Table 4.4-4, Person Contacted Date Time k.

MAXIMIZE CVCS letdown purification flow rate per 13006, " Chemical And Volume Control Sy' stem Startup And Normal Operation,

/

~Date Time 1.

If required, INITIATE STARTUP of the Auxiliary Boiler per 13760-C, " Auxiliary Steam Boiler System",

NOTIFY Chemistry Department, m.

At the Steam Generator Blowdown' Panel, slowly LOWER Steam Generator Cooling Water To The Heater Drain Tank temperature to 200*F by adjusting the setpoints on the Steam Generator Blowdown temperature Control Valves Controllers TIC-1191, 1192, 1193 and

1194, n.

STOP both Heater Drain Pumps, o.

STOP all but one Condensate Pump, p.

REDUCE in-service Condensate Demineralizer Powdex Vessels as applicable per 13616, " Condensate Filter Demineralizer System",

l l

mas

_ _.___. ~.- - --.. - - ~ - -

  • 'Ph0C'EDUkIb

~

REVISloN PAGE No.

VEGP 12006-C 15 9 of 45 4

~

UNIT NO.

INITIALS

~

)

q.

PLACE the Condensate and Feedwater System on Long cycle recirc per 13615, " Condensate And Feedwater Systems", or if a return to power is anticipated, OPEN MFP A & B 3YPASS:

UNIT 1:

1-1305-U4-655 UNIT 2:

2-1305-U4-655 or at least one MFP Discharge MOV and VERIFY condensate /feedwater chemistry is acceatable for feeding Steam Generators by obtaining concurrence from Chemistry Department.

r.

NOTIFY Chemistry to initiate placing condensate and feedwater into proper chemical wet layup, i

s.

If necessary, SHUT DOWN all but one Circulating Water Pump, I

t.

If necessary, SHUT DOWN all but one O

P.iver Makeup Pump and RECORD time in the Unit Control Log Book, u.

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 a.

ENSURE MSR Heating Steam Supply Valves HS-6015 and HS-6030 closed, b.

TRANSEER the Auxiliary Steam System steam suppl to the Auxiliary Boiler per 13761, y' Auxiliary Steam System",

c.

TRANSFER the Turbine Steam Seal supply 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",

O

.~, -

.,.,-_-. _.. _,. ~. -, -... - -

PAQh EDb Ah. NQ.

REVISION PAGE No.

VEGP 12006-C 15 10 of 45 UNIT NO.

INITIALS

()

~

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 57 and TBS 4 and 5 located in Protective Relay Panel Bay 4, per 00306-C, i

" Temporary Jumper and Lifted Wire Control".

This will prevent tripping 'ockout Relays 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 Operation"

()

Sub-subsection 4.3.1.

A4.1.3 At the USS's' discretion, DISABLE the MFPT trip circuitry to AFWAS by removing and tagging the following fuses on the applicable unit:

UNIT 1:

Train A - Aux Relay Panel INCPAR2, Fuse FU-4 IV Train B - Aux Relay Panel INCPAR4, Fuse FU-l IV UNIT 2:

Train A - Aux Relay Panel 2NCPAR2, Fuse FU-4

~~

IV Train B - Aux Relay Panel 2NCPAR4, Fuse FU-l O

1v

_.m

_...___m

..- _. _.. _ _ _ _ __ _ _. _ _ _._ __ _._._.-__._. __.._ _ _ _ _. _ _ _ _ _ _ _. _. - _ ~ _ ~. _ - _ -.. _. _ _ _ _... - -

)

i

~* - >..--

~

pppggy pg=

REVISloN PAGE No.

VEGP 12006-C 15 11 of 45 O

UNIT NO.

INITIALS A4.1.4 Either OPERATE unit systems as necessary to maintain the unit at Hot Standby, or PROCEED to either Section B to initiate unit cooldown or 12003-C, " Reactor Startup" to return to power.

END OF SECTION A

(

O O

1 0

?OJ44%

PRoCEDUAE No.

[E'v'IsidN' ~~

~~

PAGE No.

VEGP 12006-C 15 12 of 45

()

~

UNIT NO.

SECTION B:

Cooldown to not less than 350' F NOTE This section directs cooldown to 375'F or any point between without crossing the boundary 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 vacuun 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 boron equalization by energizing Pressurizer 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 Control System".

If applicable, PERFORM 14835, " Boric Acid Injection Check Valve Cold Shutdown Inservice Test" during the boration.

B4.1.6 DIRECT Chemistry to sample the RCS and Pressurizer boron concentration.

B4.1.7 If withdrawn, INSERT all Shutdown Banks to the fully inserted position.

B4.1.8 OPEN the Reactor Trip breakers.

O

.., ~

,. ~..

i PRoCEDUAE No, R E Vi$10.J PAGE No VEGP l2006-C 15 13 of 45 UNIT NO.

INITIALS

~

[

B4.1.9 If not currently in progress.

INITIATE by perfor.RCS gaseous activity degas ming the following:

a.

ENSURE that the Pressurizer i

Steam Space Sample line is in I

o3eration by verifying that tic PRZR STM SAMPLE IRC/ ORC Valves HV-3513/HV-3514 are

open, b.

NOTIFY Chemistry to adjust the pressurizer steam _ space sample flow rate to maximum, c.

While maintaining hydrogen cover gas, DEGAS the RCS by raisin g VCT gas purge flow rate to the Gaseous Waste Processing System to approximately 1.2 scfm using HIC-1094, as limited by the Hydrogen Recombiners.

B4.1.10 When notified by Chemistry that the O

RCS gaseoua activity has been reduced j

to an acceptable level, TRANSFER VCT' l

cover gas to Nitrogen and INITIATE RCS l

Hydrogen degas per 13007, "VCT Gas Control And RCS Chemical Addition".

NOTE Prior to opening the RCS to containment the hydrogen concentration shall be less than 5 cc/kg.

B4.1.11 START both Containment Pre-access Filter Units using/2621.

CTB PREACCESS FLTR UNIT-1/2 FAN HS-2620 date/ time B4.1.12 If it is planned.to cool down to Cold Shutdown, and if not performed in the grevious three months, COMPLETE 14748, AFW Check Valve Shutdown Inservice Test".

O

PROCEDURE No.

REVISdh

~

'P AGE No VEGP 12006-C 15 14 of 45 l

UNIT NO.

INITIALS B4.2 RCS COOLDOWN TO 375'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, 4.4.9.2)

Data taking and plotting may be suspended during holds in the cooldown if the duration is expected to exceed one hour.

CAUTION To reduce thermal stratification in the Pressurizer Surge Line maintain the Delta-T between the RCS and the Pressurizer Steam Space as low as aractical.

The Delta-T of 320*F s'aould not be exceeded.

NOTE It.. recommended that the RCS temperature be maintained 100*F 25'F below Pressurizer steam space temperature.

(See Figure 1.)

l B4.2.2 COMMENCE the cooldown to 375'F and 540 psig at a recommended rate of approximately 50*F per hour by performing the 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, If necessary, selectively DE-ENERGIZE l

Pressurizer Back-up Heaters by placing

.O-Control Switches to PULL-TO-LOCK,

- -.. ~ _ -. ~. _ - - _.. =.. - - -

PROCEDURE No.

REylSloN PAGE No.

VEGP 12006-C 15 15 of 45 UNIT NO.

INITIALS

~

[)

CAUTION RCS temperature and pressure shall be maintained within the acceptable operating region of Figure 1.

c.

Slowly ADJUST the Steam Duma Controller setpoint or if applicable the Atmospheric Relief Valves to initiate RCS cooldown.

B4.2.3 At approximately 2185 psig, OBSERVE PRZR PORV 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 approximatel 550'F RCS temperature

()

PERFORMthefolfowing a.

VERIFY 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 Suitches to the BYPASS INTERLOCK

position, If ooerating on Steam Dumps, then VERITY Steam Dump Cooldown Valves PV-0507A,B and C are open by observing ZLB-2 on QMCB.

m-,

1 l.-

. __ _.~____

PROCEDURE ND REVISION PAGE NQ VEGP 12006-C 15 16 of 45

()

UNIT NO.

INITIALS

^

~

CAUTION If the RCS is allowed to pressurize above Pil and SG pressurL> is below 085 psig, Anfety Injection and Sceam Line isolation will occur.

B4.2.5 At approximately 1970 psig, manually BLOCK Pressurizer Pressure and Steam Line Pressure Safety Injection and Steam Line Pressure Steam Line Isoletion signals by performing the following:

u.

It is is planned to cool down for refueling, then PERFORM 14710

" Remote Shutdown Panel Transfer Switch And Control Circuit 18 Month Surveillance Test" Data Sheets 3A and 3B in lieu of the following

substeps, b.

VERIFY Elock Permissive Status Light PRZR LO PRESS SI BLOCK PERM Pil illuminates, c.

BLOCK the Low Pressurizer Pressure Safety Injection signal using i

PRZR PRESS SI BLOCK / RESET A and B bandswitches 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 PRESS SI/SLI BLOCK RESET handswitches HS-40068 and 40069, f.

OBSERVE Status Lights STMLINE ISO TRAIN A/B SI BLOCKED illuminated.

B4.2.6 CHECK that Pressurizer level is between 201 and 461.

B4.2.7 As RCS pressure lowers, OPEN additional Letdown Orifice Isolation Valves and ADJUST PIC-131 setpoint to raintain desired letdown flowrate.

O B4.2.8 During RCS depressurization, MAINTAIN all RCP seal injection flow rates between 8 and 13 gpm by adjusting the Charging i

Header Flow Controller HC-0182.

l*

wu.s l

PROCEDURE No Revision PAGE No.

~ " ~ ' ~ ~ ~ ~ " ~

1 VEGP 12006-C 15 17 of 45 i

i UNIT NO.

INITIALS

~

B4.2.9 At approximately 950 psig, ISOLATE ECCS

a.

REMOVE TAG, UNLOCK and CLOSE the Accumulator Discharge Isolation Valve 489V MCC Breakers on the applicable

'ini ? :

1 i

UNIT 1 ACCUM-1 1ABE-19 ACCUM-2 1BBC-19 I

ACCUM-3 1ABC-19 ACCUM-4 1BBE-19 l

UNIT 2 ACCUM-1 2ABE-19 ACCUM-2 2BBC-19 t

ACCUM-3 2ABC-19 ACCUM-4 2BBE-19 b.

CLOSE the Accumulator Isolation Velves, ACCUM-1 HV-8808A, ACCUM-2 HV-8808B, ACCUM-3 HV-8808C, ACCUM-4 HV-8808D.

c.

OPEN, LOCK and TAG the Accumulator Discharge Isolation Valves 480V MCC Breakers on the applicable unit, UNIT 1 ACCUM-1 1ABE-19 IV ACCUM-2 1BBC-19 IV ACCUM-3 1ABC-19 IV O

ACCUM-4 1BBE-19 tv osus

PAoCEDURE No.

REVISloN PAGE No VEGP 12006-C 15 18 of 45

()

UNIT NO.

INITIALS

~

UNIT 2

~

ACCUM-1 2'ABE-19 IV ACCUM-2 2BBC-19 IV ACCUM-3 2ABC-19 IV ACCUM-4 2BBE-19 IV d.

OPEN and TAG MCC Relay K2 Links for the above MCC breakers.

B4.2.10 When steam pressure falls too less-than 550 psig, at the USS's discretion the Steam Generators may be supplied O

by the running Condensate Pump per Section E4.2 of this procedure.

B4.2.11 Either OPERATE unit systems as necessary to maintain RCS within the following parameter values or PROCEED to either Section C to continue the cooldown or 12002-C, " Unit Heatup to Normal Operating Temperature and Pressure" to commence a heatup.

RCS tempe*ature 375'T *10'F RCS pressure 540 psig *25 ps g Pressurizer level at program leve END OF SECTION B O

.., _ _.. _. ~, _,

- - - -. ~ ~. -..

- _. ~ ~

$ oCf DURE No.

REVIStoN PAGE NO, VEGP 12006-C 15 19 of 45 SECTION C:

Cooldown to not lest than 205'F NOTE This section directs cooldown to 225'F or any point between without crossing i.he boundary for Modo 5.

C4.1 PREPARATION FOR CONTINUING UNIT C00LDOWN.

INITIALS C4.1.1 If required to cooldown secondary systems and break condenser vacuum, then INITIATE SECTION E of this procedure.

CAUTION Maintain pressurizer cold calibration level greater than 17%.

C4.1.2 If it is planned to cool down to cold shutdown, then ALLOW pressurizer level to rise to approximately 65%

O during the cooldown but not greater than 80% cold calibrate.

CAUTION To reduce thermal stratification in the Pressurizer Surge Line maintain the Delta-T between the RCS and the Pressurizer Steam Space as low as oractical.

The Delta-T of 320*F should not be exceeded.

C4.1.3 COMMENCE RCS/ Pressurizer pressure and temperature trending at 30 minutes intervals using Data Sheet 1 and ERF computer.

(Technical Specification 4.4.9.1, 4.4.9.2)

Plotting may be suspended during holds in the cooldown if the duration is expected to exceed one hour.

O

PROCEDURE No REVIStoN FAGE No.

VEGP 12006-C 15 20 of 45

(

)

UNIT NO.

INITIALS

~

C4.2 RCS C00LDOWN TO 225'F.

NOTE It is recommended that the RCS tamperature be maintained 100'F i25'F below Pressurizer steam space 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 Spray Valves, If necessary, celectively DE-ENERGIZE Pressurizer Backup Heaters by placing Control Switches to PULL-TO-LOCK, CAUTION O

RCS temperature and pressure shall be maintained within the acceptable operating region of Figure 1.

b.

Slowly ADJUST the Steam Dump Controller Setpoint or if applicable the Atmos 3heric Relief Valves to initiate RCS cooldown.

C4.2.2 If it is planned to cool down for refueling, then prior to reaching 350'F, REQUEST 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, ISOLATE PERMS CVCS Letdown Monitor RE-48000.

O

.m MoCEDUAE No REVISloN PAGE NO.

VEGP 12006-C 15 21 of 45

{}

UNIT NO.

INITIALS C4.2.4 Prior to reaching 350*F, PLACE the Cold Overpressure Protection System (COPS) in operation by performing the following:

a.

If not performed in the previous three months, PERFORM 14860, "PORV Cold Shutdown Inservice Test",

ARM the A and B COPS by/ COLDplacing b.

the PRZR PORV BLOCK VL OVERPRESSURE CNTL handswitches HS-8000G and 8000H to the ARM

position, c.

VERIFY the following annunciators alarmed upon arming COMS:

A COLD OP ACTU VLV HV-8000A NOT FULL OPEN (ALB12 E06),

B COLD OP ACTU VLV HV 8000B NOT FULL OPEN (ALB12 F06),

O d.

ENSURE PRZR PORVs PV-455A and 1-PV-456A are closed and the handswitches in AUTO, e.

ENSURE OPEN PRZR PORV BLOCK Valves HV-8000A and 8000B, NOTE Step f satisfies Technical Specification surveillance 4.4.9.3.1.c f.

VERIFY the following annunciators reset:

A COLD OP ACTU VLV HV-8000A NOT FULL OPEN (ALB12 E06),

B COLD OP ACTU VLV HV-8000B NOT FULL OPEN (ALB12 F06).

C4.2.5 At 350'F, LOG time and date of entry into Mode 4 in the Unit Control Log Book.

{)

date/ time

.. _.. ~.. - -.. -. _ _ _, -. -.

.. _~.- =.~.. _ -. ~.

.. =. -. - -.. - _ ~.. - _..

I FAVC EDV% e4 REVISION PAGE No.

VEGP 12006-C 15 22 of 45 UNIT NO.

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 prior to reaching 325'F PERFORM the following:

a.

RACK OUT and TAG both safety Injection Pump Breakers on the applicable unit, (Technical Specification 4.5.3.2)

UNIT 1:

SI PMP-A 1AA02-16 IV SI PMP-B 1BA03-17 IV UNIT 2:

SI PMP-A 2AA02-16 IV SI PMP-B 2BA03-17 IV O

......-... m

. ~., -.

~

Mo'CtbuNE No

' " h E' INoN

~

PAUE No.

VEGP 12006-C 15 23 of 45 UNIT NO.

INITIALS

[)

NOTE AFWAS should be defeated to the SG Blowdown Valves, Sample Valves and MDAFW 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 on the applicable unit:

UNIT li Train A - Aux Relay Panel 1ACPAR6, Fuse FU-2 IV Train B - Aux Relay Panel 1BCPAR7, Fuse FU-6 O

IV UNIT 2:

Train A - Aux Relay Panel 2ACPAR6, Fuse FU-2 l

IV i

Train B - Aux Relay Panel 2BCPAR7, Fuse FU-6 IV c.

PLACE standby MDAFW Pumps handswitch in PULL-TO-LOCK, d.

If the TDAFW Puma is not being utilized, CLOSE AV-5122, 5125, 5127 and 5120.

O

~ -

~^

enoctount No.

~

nos,ou "--

piog 30 VEGP 12006-C 15 la of 45

()

UNIT NO.

INITIALSL

~

C4.2.7 When the RCS pressure is less than 365 psig, and RCS temperature is less than 340 F. PLACE at least one RHR Train in operation per 13011. " Residual Heat Removal System".

a.

OFERATE RHR RX Outlet Valves HV-0606(0607) and Bypass Valves FV-0618(0619) to control RCS tt_perature as necessary end RHR flow at a minimum total flow of 3000 gpm, b.

If applicable, PERFORM 14896, "ECCS Check Valve Cold Shutdown Inservice Test",

i c.

ENSURE RHR Suction Isolation surveillance is initiated each shift per 14000. " Shift And Daily Surveillance Logs".

CAUTION

()

While in Mode 5 with the Rea,ctor Coolant Loops filled, with 1 RHR Train inoperable, the secondary side water level of at least two Steam Generators shall be greater than 17% WR.

C4.2.8 If desired, REDUCE the number of operating RCPs to one per 13003, " Reactor Coolant Pump Operation".

Pump l' is the preferred running pump to ensure best spray capability.

C4.2.9 When SG pressure falls to 25 psig INITIATE aligning Nitrogen to the SG's per 13601, " Steam Generator And Main Steam System Operation" with regulators set at 2 to 5 psig.

C4.2.10 If it is intended to aerform maintenance on the RAT's during t'Te outage, then NOTIFY Maintenance to initiate work towards backfeeding through the Main Transformer and UAT's per 13417. " Main O

And Unit Auxiliary Transformer Backfeed To The 13.8kV And 4160V Non-1E Busses".

?w s

- - ~

' - ~ ~ " " ' " ' ' ~ ^ ~ ^ ' ~

~

P,RoCEDURE No.

~IEVIEEN

~ ~~

PAGE No.

VEGP 12006-C 15 25 of 45

~

INITIALS C4.2.11 Either OPERATE unit systes as necessary to maintain RCS within the following parameter values or PROCErD to either Section D to continue the cooldown or 12001-C, " Unit Heatup to Hoc Shutdown" to commence a heatup.

CAUTION Ensure running RCP seal differential pressure is maintained greater than 200 psid.

RCS temperature 225 F 10*F RCS pressure 250 psig 25 psig END OF SECTION C O

~

O

~

703445

~

'PAoCEDUREV'.

REVISto E PAGE NI VEGP 12006-C 15 26 of 45

()

UNIT NO.

~

SECTION D:

Cooldown to Cold Shutdown (1'ess than 200'F).

NOTE This section directs cooldown to Mode 5 and maintains temperature between 130'F and 80'F.

D4.1 PREPARATION FOR CONTINUING UNIT C00LDOWN TNITIAlf D4.1.1 If required to cool down secondary systems and break condenser vacuum, then INITIATE Section E of this procedure.

CAUTION To reduce thermal stratification in the Pressurizer Surge Line maintain the Delta-T between the RCS and the Pressurizer Steam Space as low as oractical.

The Delta-T of 320*F should not be exceeded.

D4.1.2 C0KKENCE RCS/ Pressurizer pressure and temperature trending at 30 minute intervals using Data Sheet 1 and ERF Computer.

(Technical Specification.

4.4.9.1, 4.4.9.2)

Plotting may be suspended during holds in the cooldown if the duration is expected to gpceed one hour.

D4.1.3 ENSURE RF.R letdown is in operation with flow rate greater than or equal to 75 gpm.

D4.1.4 If not previously performed, RAISE Fressurizer level to approximatley 65%.

i m-

i PRoCEoVRE No.

REVIS8oN PAGE No.

VEGP 12006-C 15 27 of 45

()

UNIT NO.

INITIALS

~

D4.2 RCS C00LDOWN TO B,ETWEEN 130*F and 80*F

~

D4.2.1 COMMENCE the coo 1down at a recommended rate of approximately 50*F per hour by performing the following:

a.

Slowly ADJUST the RHR Outlet Valves HV-0606(0607) to reduce RCS temperature, CAUTION Ensure running RCP seal differential pressure is mainteined greater than 200 psid, b.

MAINTAIN Pressurizer pressure at 250

psig, 25 psig, by selective use of Pressurizer Backup Heaters.

D4.2.2 At 200*F, LOG time and date of entry into Mode 5 in the Unit Control Log Book.

time /date D4.2.3 RACK OUT and TAG the Containment Spray pump breakers on the applicable unit.

UNIT 1:

CS PMP-A 1AA02-14 CS PMP-B 1BA03-14 UNIT 2:

CS PMP-A 2AA02-14 CS PMP-B 2BA03-14 D4.2.4 As directed by the USS, PLACE the Containment Pre-access Purge System in operation Purge System"per 13125, " Containment D4.2.5 To facilitate personnel ingress and egress, during cold shutdown, NOTIFY Maintenance to bypass the Containment Personnel Lock Interlock System.

If desired the Containment Equipment Hatch Missile Shield may be moved at this time.

D4.2.6 NOTIFY Work Planning Group to schedule and initiate mode dependent Fire Protection Surveillances.

rwn

u-

__---wa.

-.~. ~ ~

a.a.,

..=

PROCEDURE No.

REVISloN

~ ~ ~ ~

IdG"E'Nb"

~~ ~**~~

~ ~ "

VEGP 12006-C 15 28 of 45 UNIT NO.

INITIALS

)

D4.2.7 If it is intended to drain the RCS to below 172 pressurizer level, then REQUEST Engineering to defeat the RHR Suction Valves Autoclosure Interlock per 54840, " Installation And Removal Instructions For The RCS Temporary Level Indication Tygon Tube And The Defeat Of The Residual Heat Removal Suction Valve Auto Closure Interlock".

D4.2.8 When the RCS temperature is between 120'F to 180*F and if it is intended to take the RCS solid and cooldown the Pressurizer, then PERFORM the following:

a.

ENERGIZE all Pressurizer Heaters and maintain RCS pressure at 250 psig 25 psig by use of Pressurizer Spray Valves, b.

ENSURE all CVCS Letdown Orifices are in operation, CAUTION Expect rapid Pressurizer.

pressure rise with charging flow greater than letdown flow at the point of going i

solid.

Be prepared to reduce charging flow or raise letdown flow to prevent extreme pressure fluctuations.

NOTE During the filling process, monitor Pressurizer liquid and steam space temperature.

If liquid temperature lowers toward RCS temperature, then the Pressurizer fill rate should be reduced, c.

RAISE Pressurizer level by raising charging flow rate and/or lowering RHR letdown flow d'e at a maximum filling rate of 30 6Pm, O

h

-n.-

PROCEDURE No.

REVISloN PAGE No. ~

~ ~ * ~ ' ~ ~

VEGP 12006-C 15 29-of 45 UNIT NO.

INITIALS

)

d.

When the pressurizer is solid as indicated by rising RCS pressure or if PIC-131 is in AUTO rising letdown flow rate, then PERFORM the following:

(1)

BALANCE charging and letdown flow rates using HV-0128 and/or PIC-131 to maintain RCS pressure at 250 psig i25 psig, NOTE 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 gpm, CONTINUE the-Pressurizer cooldown by e.

O selectively de-energizing Pressurizer Heaters while maintaining Pressurizer spray.

D4.2.9 When the RCS temperature is less than 140*F, PERFORM the following:

a.

If withdrawn, INSERT all Shutdown Banks to the fully inserted position, b.

OPEN the Reactor Trip Breakers, c.

STOP the CRDM Cooling Fans using the following handswitchess CRDM UNIT FAN 1 HS-12273A, CRDM UN1T - FAN 2 HS-12274A, CRDM UNIT - FAN 3

-HS-12275A, CRDM UNIT - FAN 4 HS-12276A.

d.

If it is intended to remain in cold shutdown for greater than 4 days, then PLACE the SG's in wet layup as specified by Chemistry Department per 13601, " Steam Generator and Main Steam System Operation".

PROCEDURE No.

REVISION

~~

PAGS No.

VEGP 12006-C 15 30 of-45

(

UNIT NO.

INITIALS

~

NOTE The RCP(s) shall be run for one or more hours after reaching the desired RCS temperature plateau to enhance SG and RCS temperature equalization.

D4.2.10 When RCS temperature is less than 110*F, the remaining RCPs may be stopped per 13003, " Reactor Coolant Pump Operation".

D4.2.ll CONTINUE the Pressurizer cooldown by opening Pressurizer Auxiliary Spray Valve HV-8145.

a.

INITIATE AUX SPRAY /PRZR DELTA-T surveillance per 14915, "Special Conditions Surveillance Logs",

(Technical Specification 4.4.9.2),

b.

If pressurizer auxiliary spray water delta-T exceeds 320*F, then LOG the spray valve operation in O

the Unit Control Log and NOTIFY Technical Supp' ort to log the cycle per 83101-C, Com Transient Limits"ponent Cyclic or c.

CLOSE the open Charging Isolation Valve HV-8146 or HV-8147, d.

Continue CHARGING through the Pressurizer cuxiliary spray line until pressurizer steam space temperature is less than 190*F.

D4.2.12 MAINTAIN RCS temperature between 130*F and 80*F using RHR HX Outlet Valves HV-0606(0607).

NOTIFY Technical Support to log the unit cooldown per 83101-C, " Component Cyclic or Transient Limits".

i l O L<

f f

PROCEDURE No.

REVISloN PAGE No.

VEGP 12006-C 15 31 of 45 UNIT NO.

INITIALS CAUTION Ensure all RCP's are shutdown.

D4.2.13 If it is desired to depressurize the RCS, then PERFORM the following:

a.

INITIATE Lowering RCS pressure to 4

atmospheric (50 poig as indicated on PI-408, 418, 428 or 436) using letdown pressure control PIC-131, b.

When RCS pressure reaches 100 psig (150 psig as indicated on PI-408, 418, 428, 438), CLOSE all RCP Seal Leakoff Isolation valves HV-8141A, B,C,D, c.

ENSURE PRT nitrogen pressure is maintained greater than 0.5 psig.

NOTE SI Pmp Cold Leg Isolation O

Valves are closed to preclude inadvertent draining of RWST to the RCS while the RCS is depressurized and partially drained.

D4.2.14 ISOLATE the Safety Injection Cold legs by performing the following:

a.

CLOSE SI PMP-A TO COLD LEG ISO VLV HV-8821A, b.

CLOSE SI PMP-B TO COLD LEG ISO VLV HV-8821B, OPEN and TAG the following SI Cold c.

Leg Isolaticn Valves MCC breakers on the applicable unit:

UNIT 1:

1-HV-8821A 1ABD-15 1-HV-8821B 1BBD-15 UNIT 2:

2-HV-8821A 2ABD-15

{}

2-HV-8821B 2BBD-15 d.

OPEN and TAG MCC Relay K2 Links for the above MCC breakers.

mm3

PRoCEDl3E No.

REVISloN PAGE No.

VEGP 12006-C 15 32 of 45

()

~

UNIT NO.

INITIALS CAUTION Prior to opening any mortion of the RCS to the atmosphere, the hydrogen concentration in the affected oortion must be reduced to less than Sec/kg.

D4.2.15 When required, INITIATF RCS draining by performing the following:

a.

If it is intended to drain down to perform maintenance on Reactor Head, SG's or RCP seals, then the following RCS level controls shall be placed into effect:

(1)

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 x

Vessel Flange (191 ft. el.),

(2)

A review of all Containment penetrations addressed in 14210, " Containment Building Penetrations - Refueling" should be accomplished to determine those which have been opened by manual means and an info LCO generated for those identified.

(3)

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:

(a)

Removing a pressurizer manway, or (b)

Removing a Steam Generator g*

manway on a hot leg that will not be dammed, or (c)

Removing three pressurizer i

code safeties.

^*

mws

' I'hocE0biE'Eii. '

REVISloN PAGE No.

~

VEGP 12006-C 15 33 of 45

(}

UNIT NO.

INITIALS

~

(4)

If SG Nozzle Dams are to be I

opening is to be established, instal %ed and a cold leg a vent path is required from the Reactor Vessel Upper Plenum by removing an SG manway on an HL that will not be dammed.

(5)

If it is intended to operate at one foot above mid-nozzle level, the preferred RHR configuration is one train operating with a flow of 3000

gpm, (6)

If it is intended to operate below 191 ft. el., then:

(a)

A minimum of two incore thermocouples shall be available during periods where the Reactor Head is installed, i

(b)

REQUEST I&C reset the designated ERF incore' l

thermocouples alarm setpoint to alarm at 10*F above desired temperature per 00410-C, " Computer Software Control".

( '/ )

I&C should be notified to install temporary remote RCS level monitoring in the Control Room, (8)

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, (9)

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 l

and the Tygon tube,

. ()

(10) The Control Room Monitors l

should agree within 7 percent i

of scale with the Tygon tube, l.

vano

PRoCE0unE NO.

REVISloN PAGE No.

VEGP 12006-C 15 34 of 45 UNIT NO.

INITIALS

[)

~

(11) Two out of three Level Monitors must agree before draining RCS below the top of the hot leg (188 feet 3 inches),

(12) If neither Control Room RCS Level Monitor is available, then a continuous Tygon tube watch should be established while RCS level is below 171 pressurizer level, (13) While operating with SG Nozzle Dans installed, ENSURE one Safety Injection Pump is capable of being racked in and operated in the hot leg injection mode if

needed, (14) While level is in the region of the hot legs, TREND RHR Pump parameters on ERF for early detection of possible RHR Pump degradation due to vortexing, (15) Minimum RCS level 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, (16) 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.

O m_,

PRoCEDUR5 No.

REVISloN PAGE No.

VEGP 12006-C 15 35 of 45

[}

UNIT NO.

INITIALS Dose Equivalent Iodine should be below 0.1 uCi/gm, Xe-133 and Co-58 below 0.05 uCi/gm prior to opening the RCS to the containment atmosphere.

b.

OBTAIN Chemistry concurrence that RCS chemistry is appropriate for draining the RCS.

c.

INITIATE draining the RCS per 13005,

" Reactor Coolant System Draining".

D4.2.16 If it is intended to drain the RCS to less than-25% cold calibrate pressurizer level, then prior to reaching 25% ISOLATE potential dilution flow paths by performing the following:

a.

CLOSE, LOCK and TAG the following valves on the applicable uniti (1)

UNIT 1:

CVCS ISOLATION RMW TO BA BLEND, O

l-1208-U4-175 CVCS ISOLATION RMW TO CVCS, 1-1208-U4-177 (2)

UNIT 2:

CVCS ISOLATION RMW TO CVCS, 2-1208-U4-177 CVCS ISOLATION RMW TO BA BLEND, 2-1208-U4-175 b.

ENSURE CLOSED, LOCKED and TAGGED the following valves on the applicable unit:

(1)

UNIT 1:

CVCS OUTLET CHEM MIXING TK, 1-1208-U4-181 CVCS SUPPLY RMW TO CHEM MIXING TK, 1-1208-U4-176 CVCS FLUSH RMW TO TRN A EMERG l

BORATION,

()

1-1208-U4-183 RMWST TO BTRS ISO, 1-1208-U6-226 nws

-~.

.... - -..... ~.

- ~.

~

~ '"

PROCEDURE No.

REh5 ION PAGE No.

VEGP 12006-C 15 36 of 45

()

UNIT NO.

INITIALS

~

(2)

UNIT 2.

CVCS SUPPLY RMW TO CHEM MIXING TK, 2-1208-U4-176 CVCS OUTLET CHEM MIXING TK, 2-1208-U4-181 CVCS FLUSH RMW TO TT ' A EMERG

BORATION, 2-1208-U4-183 RMWST TO BTRS ISO, 2-1L98-U6-226 c.

When necessary, makeup to the VCT by performing the following:

(1)

OPEN RWST TO CCP A & B SUCTION Valves LV-Oll2D and LV-0112E, (2)

CLOSE VCT OUTLET ISOLATIONS, LV-0112B and LV-01120, (3)

ENSURE Letdown to VCT or Hold-up Tank Valve LV-0112A is in the VCT position, (4)

When VCT level has been returned to normal, OPEN LV-0112B and LV-0112C then CLOSE LV-0112D and LV-0112E.

D4.2.17 OPERATE unit systems as necessary to maintain the above conditions, a.

If required to break condenser vacuum, then PROCEED to Section-E, b.

If it is intended to proceed to Mode 6, then Go to 12007-C,

" Refueling Entry",

c.

If it is intended to commence unit heat up, then GO to-12001-C, " Unit Heatup to Hot Shutdown".

O l

END OF SECTION D

,wc

PROCEDURE No.

F4EWuO.

~^~

PAGE No.

VEGP 12006-C 15 37 of 45

()

~

UNIT NO.

SECTION E.

Secondary Plant Shutdown NOTE This section directs secondary 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 Relief valves.

E4.2 Feeding Steam Generators With Condensate Pump.

E4.3 Breaking Condenser Vacuum.

E4.4 Secondary Systems activities.

E4.1 TRANSFER FROM STEAM DUMPS TO ATMOSPHERIC RELIEF VALVES INITIALS E4.1.1 TRANSFER to the SG Atmospheric Relief Valves by performing the follcwing:

a.

Slowly OPEN each atmospheric relief while verifying a reduced steam dump demand signal 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 Steam Dump control Valves while opening each atmospheric

relief, c.

When all Steam Dump Control Valves are closed, ENSURE PIC-507 is in MANUAL, d.

BALANCE the positions of each atmospheric relief while

()

maintaining Tavg as desired.

I 73344$.

i

PROCEDURE NO.

REVISloN PAGE No.

VEGP 12006-C 15 38 of 45

(}

UNIT NO.

INITIALS

~

E4.2 FEEDING STEAM GENERATORS WITH CONDENSATE PUMP E4.2.1 At the USS's discretion, INITIATE feeding Steam Generators with the running Condensate Pump by performing the following:

a.

VERIFY SG pressure is less than 550 psig, b

VERIFY that lube oil pressure to the reset MFP and MFP Turbine Fearings is 10 to 12 psig by local indications, c.

OPEN the reset MFP Discharge Valve by placing the Control Switch in OPEN-PULL-TO-LOCK at the Main Control Panel QMCB:

SGFP A HS-5208, SGFP B HS-5209.

d.

If not previously performed, RESET both trains of Feedwater Isolation:

(1)

HS-40049 for Train A, (2)

HS-40050 for Train B.

e.

OPEN all BFIV's, f.

CONTINUE maintaining desired SG 1evel utilizing the BFRV's.

O

._.~

PROCEDURE No.

REVISloN PAGE No.

VEGP 12006-C 15 39 of 45

()

UNIT NO.

INITIAI,4

~

E4.3 BREAKING CONDENSER VACUUM E4.3.1 If necessary,- TRANSFER the Auxiliary Steam System steam supply-to the alternate unit or Auxiliary Boiler per 13761, " Auxiliary Steam System".

E4.3.2 TRANSFER the Turbine Steam Seal supply to the Auxiliary Steam Supgly per 13825,

" Turbine Steam Seal System E4.3.3 TRANSFER the SJAE steam supply to the Auxiliary Steam Supply per-13620,

" Condenser Air. Ejection System".

E4.3.4 CLOSE the MSIVs and-Bypasses.

CAUTION Breaking condenser vacuum will result in a MFPT Low Vac Trip.

If AFWAS has not been defeated, then both MFPs-tripped will result in O.

a AFWAS initiation.

E4.3,5 PLACE the standby MDAFW Pump (s)

Handswitches in PULL-TO-LOCK.

E4.3.6 BREAK condenser vacuum and SHUT DOWN.

the Steam Jet Air Ejectors and the Condenser Vacuum Pumps per 13620,

" Condenser Air Ejection System".

E4.3.7 PERFORM the following to reset the AFWAS signal a.

RESET the AFWAS by resetting one MFPT Low Vacuum Trip by.

momentarily placing the MFPT-A(B)

VAC TRIP BYPASS Handswitch-to RESET position and MFPT A(B)

TRIP RESET HS-3169 (3170) to the RESET position, b.

If running a MDAFW Pump, then THROTTLE the AFW Flow. Control-Valves to the pre-initiation flow rate, O

m_,

PROCEDURE No REVISloN

~ AdE 5o$ '

^ ~ ~

VEGP 12006-C 15 40 of 45 UNIT NO.

, INITIALS

()

~

c.

If applicable, ENSURE the SG Blowdown Isolation Valves HV-7603A(B,C,D) op_en.

E4.3.8 After the condenser pressure reaches atmospheric, SHUT DOWN the Turbine Steam Seal System per 13825, " Turbine Steam Seal System".

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 E4.4.1 If condensate and feedwater cleanup is not anticipated, then when condensate and feedwater metal temocratures are less than 200*F, SHUT DOWN't'te Condensate and Feedwater System per And Feedwater Systems,13615, Condensate E4.4.2 NOTIFY Chemistry and SHUT DOWN the i

Condensate Filter Demineralizer System N-per 13616, " Condensate Filter Demineralizer System".

E4.4.3 If the secondary _ outage is planned to exceed 10 days, then PERFORM the following:

a.

When condensate and feedwater metal temperature 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 />.

mms

PROCEDURE No.

REVISloN PAG E No. ~~ ~

~'

'^

VEGP 12006-C 15 41 of 45

(

)

UNIT NO.

INITIALS E4.4.4 If required, PLACE a steam blanket on the MSRs per -13800, " Main Turbine Operation".

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 INITIATE purging" Generator Gas System".the main generator per

13810, If hydrogen atmosphere is to be maintained, then MINIMIZE usage during the outage by reducing hydrogen pressure to not less than 5 psig.

%)

E4.4.7 SHUT DOWN the Isophase Bus Duct Cooling System by performing the following:

a.

At 480V AC SWGR NB03, OPEN Isophase Bus Duct Heater Breaker on the applicable unit:

UNIT 1:

1NB03-16, UNIT 2:

2NB03-16.

b.

At local Panel PLCB, STOP the running fan using MS-16550 for Fan No. 1 and/or HS-16551 for Fan No. 2.

Completed Signature Date/ Time Reviewed Signature Date/ Time Comments O

~-

PROCEDURE No.

REVISlok PAGE No.

~ ~ ~ ~ ~ ' "

VEGP 12006-0 15 42 of 45

()

5.0 REFERENCES

~

5.1 PROCEDURES 5.1.1 00410-C,

" Computer Software Control" 5.1.2 10006-C,

" Reactor Trip Review" 5.1.3 12001-C,

" Unit Heatup To Hot Shutdown" 5.1.4 12002-C,

" Unit Heatup To Normal Operating Temperature And Pressure" 5.1.5 12003-C,

" Reactor Startup" 5.1.6

13003,

" Reactor Coolant Pump Operation" 5.1.7

13005,

" Reactor Coolant System Draining" 5.1.8

13006,

" Chemical And Volume Control System Startup And Normal Operation" 5.1.9

13007, "VCT Gas Control And RCS Chemical Addition" 5.1.10
13009, "CVCS Reactor Makeup Control System"

()

5.1.11 13010

" Boron Thermal Regeneration System" 5.1.12

13011,

" Residual Heat Removal System" 5.1.13

13120,

" Containment Building Cooling Systems' 5.1.14

13125,

" Containment Purge System" 5.1.15

13601,

" Steam Generator And Main Steam System Operation" 5.1.16

13605,

" Steam Generator Blowdown Processing System" 5.1.17

13610,

" Auxiliary Feedwater System" 5.1.18

13615,

" Condensate And Feedwater Systems" 5.1.19

13616,

" Condensate Filter Demineralizer System" 5.1.20

13617, "Feedwater Heater Extraction, Vent And Drain System" 5.1.21
13620,

" Condenser Air Ejection System"

()

5.1.22

13724,

" Circulating Water System"

- -. ~

PROCEDURE No-REVl51oN PAGE NO.

~~

VEGP 12006-C 15 43 of 45 5.1.23

13760,

" Auxiliary Eteam Boiler System" 5.1.24

13761,

" Auxiliary Steam System" 5.1.25

13800,

" Main Turbine Operation" 5.1.26 13810

" Generator Gas System" s

5.1.27

13825,

" Turbine Steam Seal System" 5.1.28

14000,

" Operations Shift and Daily Surveillance Logs" 5.1.29

14005,

" Shutdown Margin Calculations" 5.1.30

14210,

" Containment Building Penetrations -

Refueling" 5.1.31

14748, "AFW Check Valve Cold Shutdown Inservice Test" 5.1.32
14915, "Special Conditions Surveillance Logs" 5.1.33
24695, "N.I. System Source Range Channel Calibration" 5.1.34
24696, "N.I. System Source Range Channel Calibration" i

END OF PROCEDURE TEXT l

1 l

l O

l

PROCEDURE NO.

REV SiON PAGE NO, VEGP 12006-c 15 44 of 45 V

2400..

22R REC 0WDOED W / CD PATH +- 25 f-- - -sI

__if.

l 20R 9

l d

51800 PSD-U Igy::

/

l i

/

n 0

160E p

t i

I v

l

~.

W NON OPERAMG REGION r

3 1200r"

'4 a

e I

p W

e E

j G

NON OPmmG R82 4 a

9,,"

> ET UP '

1 50 y quemm EE:

~

i 4

p 111llI111llllll1lllI11llllllll11lll1lllllllllllllIl111111lll1llll11ll 0

100 200 300 400 500 000 NO l

OCS10f0NE(F)

FIGURE 1 - RCS PRESSURE TEMPERATURE LIMITS e

10344S i

}'

-. (

VEGP 12006-C 15 45 of 45

.C

)

Sheet 1 of 1 UNIT NO,

~DATE

/

/

RCS/PRZR TEMPERATURE AND PRESSURE DATA SHEET 1 Lowest Channel of TI-0413B TI-0423B TI-0433B PI-438LR or TI-0443B PRZR TEMP PI-405WR PRZR/RCS TIME RCS TEMP TI-0454 TI-0453 PRZR PRESS DELTA T p

Completed Signature Date/ Time Reviewed Signature Date/ Time Comments O

6 l

Retrieved from "https://kanterella.com/w/index.php?title=ML20092F813&oldid=4332764"