ML20155C083

Rev 4 to Procedure 12005-C, Reactor Shutdown to Hot Standby (Mode 2 to Mode 3)

ML20155C083
Person / Time
Site:	Vogtle
Issue date:	03/02/1988
From:	GEORGIA POWER CO.
To:
Shared Package
ML20155C011	List: ML20155C007 ML20155C035 ML20155C047 ML20155C071 ML20155C075 ML20155C083 ML20155C087
References
12005-C, NUDOCS 8810070232
Download: ML20155C083 (8)

Text

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Vogtle Electric Generating Plant Wocews No.

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NUCLEAR CPERATIONS 12005-C p.,,,,on so.

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I REACTOR SHUTDOWN TO HOT STANDBY d's (Mode 2 to Mode 3) i

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This procedure will direct the shut down of the reactor to enter stable conditions in Mode 3, Hot Standby.

2.0 PRECAUTIONS AND LIMITATIONS 2.1 PRECAUTIONS 2.1.1 Xenon level variations should be anticipated following a load reduction and boron concentration adjustments may be required.

2.1.2 The shutdown banks should remain fully withdrawn unless the RCS has been borated to at least the hot, xenon-free boron concentration and is being maintained at hot standby, 2.1.3 The boron concentration in the pressurizer should not be different from the RCS by more than 50 ppm.

Pressurizar backup heaters may be energized as necessary to equalize the boron concentration.

2.1.4 Vacuum should be maintained on the Main Turbine following unit shdtdown until the turbine coasts down to approximately 66% of rated speed (1200 rpm) unless an emergency dictates rapid coastdown of the turbine rotor.

2.1.5 The Main Turbine should be kept on the turning gear until metal casing temperatures have returned to ambient.

Bearing lube oil circulation must also be maintained.

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cacCE%AE No REVIStoN PAGE No VEGP 12005-C 4

2 of 8 2.2 LIMITATIONS IhifeinModes1an'd2,allreactorcoolant

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2.2.1 loops shall remain in operation. (Technical Specification 3.4.1.1) 2.2.2 While in Mode 3, at least two reactor coolant loops shall be in operation when the reactor trip breakers are closed and at least one reactor coolant loop i d's operation when the reactor trip breakers are open.n 2.2.3 While in Modes 1 and 2, shutdown margin shall be greater than or equal to 1300 pcm (1.3% delta k/k).

(Technical Specification 3.1.1.1) 2.2.4 While in Modes 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.

2.2.5 While in Modes 1 and 2 with the reactor critical a.

All reactor coolant loops temperature shall be greater than or equal to 551'F, (Technical Specification 3.1.1.4) b.

All shutdown rods shall be fully withdrawn, (Technical Specification 3.1.3.5)

The control banks shall be maintained above the c.

rod bank LO-Lo limit.

(Technical Specification 3.1.3.6) 2.2.6 While in Modes 3, 4 and 5, both channels of Source Range Nuclear Instrumentation shall be operable.

(Technical Specifi. cations Table 3.3-1, 6.D) 2.2.7 While in Modes 3, 4 and 5, at least one channel of Source Range Nuclear Instrumentation should be selected to Recorder NR-45 and the SOURCE RANGE HI FLUX LEVEL AT SHVIDOWN alarm operable.

3.0 INITIAL CONDITIONS NOTE Variations in the alignment of systems may be justified by maintenance or operational considerations: but suitability should be determined by the Unit Shift Supervisor (USS).

3.1 Reactor power level is less than 5%.

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3 of 8 i

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3.2 RCS temperature is s tabilized at no load Tavg unos -

l5bhtrol of the steam dumps in Steam Pressure mode or by operation of the Steam Generator Atmospheric Relief i

Valves 3.3 RCS pressare is sectie at normal operating pressure.

3,g4 All RCP's are in operation.

3.5 Pressurizer level is at program level with either the PD pump or a CCP operatin and seal injection flow. g to supply normal charging 3.6 AFW pumps are operating to supply auxiliary feedwater to steam generators.

3.7 The Main Turbine has been tripped and is coasting down to or at turning ge condenser pressure.ar speed with normal or stable 3.8 If required, the Auxiliary Boiler is in hot standby.to provide auxiliary steam.

3.9 One channel of Intermediate Range and the highest reading Power Range channel of nuclear instrumentation

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are selected to indicate on Recorder NR-45.

4.0 INSTRUCTIONS

_ INITIALS i

NOTE Asterisk (*) steps beside INITIALS spaces indicates steps that generate additional documents.

4.1 PREPARATION FOR REACTOR SHUTDOWN 4.1.1 If a cooldown to cold shutdown is necessary following reactor shutdown and the RCS is to ha opened to the Containment atmosphere then INITIATE RCS/ Pressurizer gaseous, activity degasification if not currently in progress by performing the followingr i

DIRECT Chemistry sample the RCS a.

hydrogen and gas activity 4

concentration, t

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1 PACCEDUAE No REVIStoN fI AAGENo VEGP 12005-C 4

4 of 8 s

i INITIALS EEE~ ENSURE that pr'essurizer steam space i

sample line is in operation with pressurizer steam space sample i

i containment isolations RV-3513 and HV-3514 open.

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NOTIFY Chemistry to adjust the c.

i pressurizer steam space sample flow rate to maximum, d.

ENERGIZE the pressurizer back-up heaters to enhance RCS desassing, i

While maintaining hydrogen cover e.

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gas, DZGAS the RCS by raising VCT gas purge flow rate to the Gaseous Waste Processing System to 3

i approximately 1.2 scfm using HIC-1094 as limited b i

hydrogen,recombiners. y the j

4.1.2 MAXIMIZE CVCS letdown purification flowrate.

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Date Time 4.1.3 ENSURE RCS temperature is being controlled at approximately no load Tavs by either steam dumps in Steam Pressure Mode or by the Steam Generator i

Atmospheric Relief Valves.

If Tava lower's to 561'F with a.

i the Tavg-Tref deviation alarm l

not reset while the reactor is i

critical then COMMENCE recording Tava ever,y 30 minutes per 14915, i

l "Special Condition Surveillance Logs",

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b.

l If Tavy lowers to 551*F, whila the reactor is critical, then RAISE Tavs to greater than 551*F within 15 minutes or TAKE the i

reactor suberitical within the i

next 15 minutes.

4.1.4 ENSURE al' Steam Generator levels are stable between 45-35% NR.

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pe0CEOUAE NO AEVISioN PAGE No VEGP 12005-C 4

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g.

INITIALS 4.1.5 MAINTAIN,.one condensate pump running d

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.on recire until condenser vacuum is broken and high pressure feedwater i

header temperature is less than 200'F, i

4)(.6 If requested by Chemistry, PLACE the condensate and Feedwater System on i

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Long cycle recire per 13615, i

"Condensate And Feedwater Operation".

i 4.1.7 If No-Load Tavg can not be maintained due to excessive steam demand, REDUCE 1

steam demand by performing the

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I, following:

i a.

TRANSFER the Auxiliary Steam i

system steam supply to either the alternate unit or to the i

i Auxiliary Boiler per 13761, "Auxiliary Steam System",

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b.

TRANSFER the Turbine Steam Seal supply to the Auxiliary Steam Supply per 13825, j

"Turbine Steam Seal System",

c.

TRANSFER the SJAE steam supply to the Auxiliary Steam Supply i

per 13620, "Con ~ denser Air Ejector System".

t 4.2 REACTOR SHUTDOWN '

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NOTE I

i OBSERVE for expected range overlap on NIs during shutdown.

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During rod insertion CHECK for 1

(1)

Proper group alignment.

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(2)

DEFI and group step counter j

indication agreement.

i (3)

Proper bank overlap.

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4.2.1 INSERT all control banks.

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l RECORD reactor shutdown time and date in the Unit Control Logbook, i

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omoCEDU AE No AEVIStoN PAGE No VEGP 12005-C 4

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p; INITIALS 4.2.3 At approximately 5 x 10'11 amps IR, l

. VERIFY that both channels of Source i

Range 1.;dication automatically energize.

's OBSERVE the following status lights a.

j

,s extinguish:

(1)

IR P6 NC35D (TSLB-4,3.1),

j (2)

IR P6 NC36D (TSLB-4,32),

j (3)

SOURCE RANGE BLOCK PERMISSIVE l

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(4)

SR TRAIN A TRIP BLK'D HI VOLT j

OFF, 4'

(5)

SR TRAIN B TRIP BLK'D HI VOLT L

0FF.

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b.

j VERITY annunciator SOURCE RANGE HI VOLTAGE FAILURE ALB-10 A01 resets, l

VERIFY annunciator SOURCE RNG HI c.

j SHUTDOWN FLUX ALARM BLOCKED ALB-10 a

B01 illuminated, i

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d.

If the Source Range chann toenergizebelow5x10~gsfail j

amps s

then RESET the applicable Source, Range using SR BLOCK RESET -A/B 1

HS-40030 and/or HS-40031.

If manual reset attempt fails to energize

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source range, then NOTIFY I&C to insnediately restore the affected channels i

j to service.

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4.2.4 1

SELECT both channels of Source Range indication on Recorder NR-45.

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ANNOTATE chart to reflect channels selected.

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P'*oCECUAE No P EVIS6CN PAGE No VEGP 12005-C 4

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pG INITIALS 4.2.5 When the Source Range channels

. indication' stabilize, PLACE the SOURCE."ANGE HI FLUX LEVEL AT SHUTDOWN alarm in operation by

,s performing the following:

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a.

RESET the SOURCE RANGE HI FLUX LEVEL AT SHUTDOWN alarm setpoint to 3.16 X normal background, t

b.

1 ENABLE the SOURCE RANGE HI FLUX 1

AT SHUTDOWN alarm by placing the l

HIGH FLUX AT SKUTD M NORMAL / BLOCK switches to the NORMAL position, VERITY annunciator SOURCE RNG HI c.

l SHUTDOWN FLUX ALARM BLOCKED ALB-10 B01 reset.

4.2.6 CALCULATE SHUTDOWN MARGIN per 14005, i

"Shutdown Margin Calculations".

4 4.2.7 If necessary, BORATE the RCS per 13009, "CVCS Reactor Makeup Control System" or 13010. "Boron Thermal Regeneration System".

L 4.2.8 CRECK the following plant conditions:

RCS borated as necessary to maintain a.

shutdown margin greater than the limit 1

specified in Technical Specification i

3.1.1.2, Figure 3.1-1, i

j RCS activity and chemistry samples b.

have been obtained by Chemistry.

4.2.9 If the reactor will be returned to I

4 i

operation, then PROCEED to 12003-C, power t

"Reactor Startup" (Mode 3 to Mode 2).

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4.2.10 Either OPERATE plant systems as necessary to maintain the conditions of this procedures or PROCIED to 12006-C, "Unit Cooldown to Cold Shutdown".

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i Completed:

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signature Date Reviewed:

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signature Date 1

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PaoCEDU AE NO.

REvtSION AAGE NC VEGP 12005-C 4

8 of 8 COMMENTS: 5;~ -

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5.D REFERENCES 5.1 PROCEDURES i

5.1.1

13007, "VCT Gas Control And RCS Chemical Addition" 5.1.2

14005, "Shutdown Margin Calculacions" 5.1.3

13009, "CVCS Reactor Makeup Control System" i

5.1.4

13010, "Boron Thermal Regeneration System" 1

5.1.5 12003-C, "Reactor Startup" i

i 5.1.6 12006-C, "Unit Cooldown To Cold Shutdown" L

5.1.7 14915 "Special Conditions Surveillance Logs" 5.1.8

13615, "Condenvate And Feedwater Operation" I

5.1.9

13761, "Auxiliary Steam System" l

5.1.10

13825, "Turbine Steam Seal System" 5.1.11 13620 "Condenser Air Ejector System" END OF PROCEDURE TEXT l

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