ML20042C117

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Plant Shutdown & Cooldown, Revision 19
ML20042C117
Person / Time
Site: Rancho Seco
Issue date: 04/11/1981
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20042C116 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.13, TASK-TM B.4, TAC-45202, NUDOCS 8203300225
Download: ML20042C117 (20)


Text

..

4

.. ~.

Rev. 19 g,4

?LA::T 3F.U-~;C'.C: A:~0 CCCLOC'C'

  • 0.

?t'RPOSE

.1 To outline the s:eps :: which :he nuclear sceam sys:ec is snu:down fro = 15% pcwer and :coled :o :he cold shu:down condi: ion.

4

.1 Plant Shutdown, See: ion 1. 0

.2 Plant Cooldown, See: ion 3.0

.3 Natural Circulation Cooldown, See:1on 6.0

2.0 REFERENCES

.1 SMUD Rancho Seco Uni: 1, FSAR, Sec: ion 13, Technical Specifications

.2 SMUD Rancho Seco Unit 1, Plant Process Standards

.3 SMUD Rancho Seco Unit 1,f4ater Chemistry Manual, A?-306 4

SMUD Rancho Seco Unit 1, Plant Operations Manual 3.0 LIMITATIONS AND PRECAUTIONS

.1 Maintain RCS Pressure, temperature, and cooldown race within the limi:s of Process Standards Curve 101-2a.

.2 The pressurizer cooldown rate shall not exceed 100*F/hr.

.3 Maximum allowable IT between the RCS cold leg temperature and pressurizer temperature is 410*?.

.a The secondary side of the OTSG's shall not be pressurized

>200 psis if secondary side temperature is below 100*F.

.5 The feedwater :emperature :o the OTSG shall be no more than 350*? below OTSG dowr.cumer outlet ce=perature.

.6 Do not open valves connecting the decay heat removal system

o the reactor coolant system until reactor coolant pressure is less than or equal to che naximum pressure shown in process scandards curves 101-3D :hru 1013K, and/or 101-4, and until RCS :emperature is less than 290*?.

3. :.-l Rev.

6 8203300225 820317 PDR ADOCK 05000312 P

ppy

G 3.0 LIMITATIONS AND PRECAUTICMS (Continued) i

.7 At all times during cooldown, the reactor shall be maintained at least 1*. subcritical.

If source range count rate increases

.j~

abnormally, discontinue cooldown until cause is identified and corrected.

removal Maintain makeup and purification system and decay heat

.3 system boron concentrations equal to or greater than the boron concentration of the reactor coolant system such that the reactor coolant system is not diluted luring cooldown.

Observe allowable RCS pressure-temperature curves for si=ultaneous

.9 operation of RC pu=ps and Decay Heat System see OF A.2.

.10 Continue seal injection and component cooling water to RCS pumps until RCS temperature is <150*F.

.11 Before RCS temperature decreases to 520*F, at least one RCS pu=p must be taken out of service.

Close core flood tank isolation valves when RCS pressure decreases

.12 to <700 but >600 psig.

All subcritical boron changes shall be verified every esti=ated lll

.13 30 ppm change or hourly, whichever is more frequent.

.14 Between 0 and 15 reactor power, maintain pressurizer level commensurate with, but not less than, process standards curve 101-16.

.15 Maximum allowable aT between OTSG downcomer inlet temperature and RCS T cold is 25*F.

.16 Maximum allowable RCS temperature change rate between 0 and 15 power is 150*F/hr.

1

.17 Maximum allowable AT between OTSG average shell temperature and RCS temperature is 60*F (see OP A.6, Enclosure 3.6 for calculating OTSG Average Shell Temperature).

inadvertent actuation of the auxiliary feedwater

.18 To prevent system during cooldown, the automatic start controls for the pumps and valves should be placed in manual prior to cooldown.

.19 The auxiliary feedwater system shall be used for filling an empty (< 8 inches level) OTSG vhen RCS temperature is >200*F.

.20 If all RC pumps are lost during cooldown, continue RCS cool-down via natural circulation per Section 6.0.

.)

3.4-2 Rev. l' m

4

n: :,.,;

30 L :::TA!!ONS ASO ?RICAUT:GNS (continued; 15

.21 Ceieted.

.22 The axi=u: allowable ;; between RCS : hot and !_ol, is 100*?.

w

'4 hen cooling the RCS vich one OTSG in a dry tendition, that

.23 be within 100*? of the GTSG's Average Shell Temperature must RC3 te=cerature and =ax1=u= !

to T across that OT3G l

hot cold is 10*?'.

.24 for loss of OTSG feed or decay heat removal system see I ergency Procedure D.14 or D.16, respectively.

.25 Control rod safety group 1 shall be fully withdrawn when-ever positive reactivity is being added to the reactor by either xenon, boron, temperature, or motion of parr length control rods.

t I

The following excepticas say be applied.

.1 The reactor coolant system has been borated to at least the hot, xenon free boron concentration and is being maintained at hot shutdown.

.2 The reactor coolant system has been borated to the cold shutdown boron concentration and the plant is being cooled down.

4.0 PLANT SHUTDOWN Initial Conditions

.1 Unit is %15% power.

.2 Unit T,y, is controlling at 582*y and Reactor Coolant Pressure is controlling at s2155 psis.

.3 Two main feedwater pumps and one condensate pump operating (Preferably one main feedwater pump in auto and the other in manual at minimum speed).

4 At least two circulating water pumps in operation.

.5 An auxiliary boiler is hot and pressurized per 0F A.39, j

l Section 4.0.

1 RCS shutdown boron concentration has been deter =ined for het

.6 '

shutdown and/or cold shutdown per OP 3.6 and calculations made per 3.9 to insure > 1" shutdown margin during all stages of plant shutdown and/or cooldown.

.7 Pressurirar level control in "Anto" and controlling at 200 inches.

3.4-3 Rev. 13

7 : -,._

.0

?LA:3! 3 HUT CWM ;L n:inued)

.3

?lant loads ::ansferred fr:: uni: auxi'iary ::ansferrers di and :'2 :o star:up ::ans farters, per OF A.55.

!! :he RCS is :o be cooltd down, RCS degassification is in

.9

^

progress per 0? A.13 anc/or OF A.3.

3 Procedure NCTI:

Coe=unica:e with SMUD dispatcher prior :o switching such as RC pu=ps or power supplies, large --culp=ent anything : hat would effect power :ransmissions.

.10 Place reactor steam generator, feedwater loops A and 3 and reactor demand in hand and decrease feedwater de=and Establish OTSG blowdown per OF A.6.

to zero.

NOTE:

This insures that OTSG is being controlled at minimum level.

Verify letdown flow is reduced to block orifice flow only.

.11 Place the EHC in " Operator Auto".

.12 Set speed-load reference-aetter at 30 MW.

.13 Set load rate setter to 5% per minute or less.

.14 Depress EHC "Go" pushbutton.

As load decreases, observe turbine by-pass valve maintains secam header pressure at set point (885 psig).

s

.15 At N10% turbine generator load take the reheaters out of service in accordance with OP A.46.

.16 When load decreases to s30 MW, trip :he OC3's and remove main generator excitation per OP A.64, Sec:1on 6.1.

Observe turbine bypass valves are controlling header pressure at 355 psig.

CAUTION:

Prior to accomplishing :he next step, verify that CC3-220. OC3-220 and the Main Generator Field 3reaker (41) are OPEN.

Failure :o have all three (3) open will result in a reactor trip when the turbine is tripped.

CAUTION:

The Turbine Trip pushbutton MUST be used in the next step.

Use of the Generator Trip pushbut:en will result in a REACTOR TRI?.

.17 Trip the turbine and observe that AC bearing oil pump starts on decreasing oil pressure.

Star: :he bearing 3

-/

lif: pump.

.13 Tollew OP A. '6, Section 6.0, for steps :o completely place :he unit on turning gear.

3.1-4 Rev.

!A'_

4.0 FI.A IT S*dCTD0h'N (Continued)

.19 Gradually reduce reactor power to 8" while monitoring and plotting cooldown race (maximum of 150*F per hour between 0 and 15% power).

NOTE:

f Between 0 and 15% reactor power adjust pressurizer level setpoint to decrease pressurizer level to 90-115 inche*.

Maintain pressurizer level decrease commensurate with but not less than process standards curve 101-16.

.20 Between 8 and 5% reactor power, place the CRD panel in manual and gradually reduce power to <2%, by inserting the regulating group.

NOTE:

Makeup to the makeup cank, as re-quired to maintain makeup tank level between 60 and 80 inches.

If going to cold shutdown add concentrated boric acid as calculated per B.9 for boration during cooldown.

.21 The plant is now at hot standby:

.1 Reactor is critical at <2% power.

.2 RCSpressureisbeingcontrolledat%2155psig.

.3 RCS T,y, >525'F.

4 Startup feedwater valves in auto.

.5 Mainsteampressurebeingcontrolledat%885psigby the turbine bypass valves.

.6 One (1) condensate pump and 2 main feedwater pumps in operation (one main feed pump in auto, and the other in manual at minimum speed).

.22 To take the plant to hot shutdown t.omplete the fo11osing:

.1 With the CRD panel in manual, insert the regulating groups to reduce reactor power to 10-8 amps, while monitoring and plotting RCS cooldown rate.

4

.2 At 10-3 amps and steady record reactivity balance information as required below:

B.1-5 Rev. 17

7 - -,,;

?'_A::: 5F.UT:CW5 :C:n:inued)

R:d :: ii;ura:i:n

.1 RC3 3:::n : ntentra 1:n

.3 RC3 Pressure Te:pera:ure

.a Dace /Ti=e.

.3 Turther reduce reac:or power :: 25 x 10~I amps by inserting :he regulating group.

NOTE:

Observe : hat source range instru=en:a-tion is energited at approx 1:acely 5 x 10~13 a=ps.

amps, verify source range instru=enta At 25 x 10-11 4

tion is on scale and indicacig no greater :han 5 x 10:

CPS.

CAUTION:

If the source range instrumentation 3 CPS when does not indicate <5 x 10 the intermediate range is at 5 x 10-11 amps, the required one decade overlap does not exist.

Reactor power shall be maintained 1,5 x 10711 amps until 3W at 11ast i source range channel is operable.

.5 Fully insert the regulating groups.

NOTE:

If the plant is to be cooled down for refueling, group 8 may be inserted at this time, if reactivity addition due to inserting group S will not decrease shuedown margin to 117. shutdown.

.6 Disable the Reac:or Trip From Turbine - Main Feed Pumps as follows:

.1 At ElRI place Reactor /F?T Trip CUTOUT Key in CUTOUT.

.7 When'it has'been confirmed chai 31%~ shutdown margin will exist, per 3.6 calculations all safety groups may be inserted.

NOTE:

For cooldown safety group 1 shall be w1:hdrawn.

3.4-6 Rev.

1-

.-.~s_

IN*~AL

t. 0 PLANT SHLTD0'4i (Continued)

NOTE:

If desired, f or cooldown, the RCS =ay be borated at this ti=e to the cold shutdown boren concentration.

Since it is desirable to batch borate for cooldown, the pressuri:er level =ay be increased to 290 inches during batch boration.

See 3.9 for boration during cooldown.

Open 2fCM-165 and MCM-166, feedwater loop A/S startup recir-

.8 culation valves to the condenser, to establish condensate recirculation flow. Throttle open WS-129 and MS-130 to provide continuous sinimum feedwater flow to each OTSG.

.9 The plant is now at hot shutdown.

i

.1 Reactor >l" shutdown.

.2 RCS T

>525'F.

ave -

.3 RCS pressure being controlled at approxinately 2155 psig.

.4 Main steam pressure being controlled at approximately 885 psig with the turbine bypass valves in automatic.

.5 OTSG's on low level control (30 inches)..

.6 One (1) condensate pump and two (2) main feedwater pumps running (one =ain feed pump in auto and the other in manual).

5.0 PLANT C00LDOWN Initial Conditions

.1 Reactor is in a hot shutdown condition.

.2 Safety Rod Group. 1 fully withdrawn.

.3 RC Makeup aligned per OF A.15, for feed to makeup tank from de=in.

RC Storage Tank and from concentrated boric acid tank.

.4 Boron concentration / addition requirements deter =ined per 3.6 and calculated per OPOP 3.9 for cold shutdown or for refueling concen-tration.

.5 RCS degassing completed per 0F A.15 and/or 0F A.3.

3. !*- 7 Rev. L7 j

3 '. 2

?'_A:: Ci;:.;;a!..::::inue:

?recedure

.6 5:op '

sir. feedva:er ;u ; in a::ordance wi:- !? A.30-7er fy

ne rema ning feedvater pump is in au:: a:i: and ve rif' CM-15 3 anc MCM-166 are Open wi:h c:ncensa:e f.:w :: ::ndenser.

signa's for :he emergency feeewa:er

.')

.7 Place :he au:c a:i: s:ar:

sys:em in manual (pu=ps and valves).

.3 Close :he 1e:down isola:1on valve S?V-22009.

Moni:or MU :ank level and feed at the required boron concentra:1on as necessary during cooldown to maintain :he MU :ank between 50 and 30 inches.

NOTE:

Verify :he RCS boron concentration

~

every estimated 30 ppm change.

Sample the pressurizer water space for boron concentration and periodically increase spray flow as required to keep the pressurizer boron concentration within 18 ppab of the RCS.

.9 Establish a drain path from the OTSG's to che HP condenser in accordance with OP A.6, Section 6.0.

Follow 0F A.6 for steps to control OTSG levels during cooldown.

.10 Establish one RC pump running in each loop (preferably 3 & D).

N0'TE :

O Sequence for stopping RCP's dur-ing cooldown is:

C, A, 3, & D.

.11

. Initiate and control RCS cooldown wi:h the turbine bypass valves.

Monitor and plot RCS c,coldown rate.

Turn pressurizer heaters OF7 and spray the pressurizer as required to stay within Process Standards Figura 101-2a.

NOTE:

Should it be necessary to close ei:her the pressurizer spray isolation valve - (HV-21510) or the EMOV isolation valve (EV-21505) while the plant is hot and the reason for closure would not prevent further valve operation the valve should be cycled every 1000 ? as :he plant is cooled down to prevent valv* wedge seizure due :o contraction of the valve body.

.12 Vent the pressuri:er to the PRT in accordance with 0F A.3.

Follow OP A.,3, Section 6.0 for pressurizer cooldown. Vent the MU cank as necessary.

.13 When RC. System pressure decreases to between 1950 psig and 2000 psig, :erminate depressurization and cooldown.

.14 Drive all safety rod groups :o :he full "In' posi:1on as per 0F A.74 3.a-3 Rev. 17

INITIAL 5.0

?L.4ST CCCLOCTU (Continued)

NOTE:

If cooldown is for refueling and gr up i has not been inserted it may be fully inserted this time (prior to inserting safety at group:-:).

Insertion of group a vill add pos-itive reactivity, therefore, =enitor neutron count race closely and verify >1% shutdown margin.

.15 Trip the reactor and continue to depressurize to 1750 psig, ter-minate depressurization.

NOTE:

?

Adjust turbine bypass valve setpoine as re-quired to maintain RCS temperature steady.

Initiate Reactor Protection System shutdown bypass per OP A.69,

.16 illy Section 5.2.

.17 Notify the I&C Department to reset the high flux crips to 15%

j per OP A.69, Section 5.2.

(In accordance with I-104).

I Fill out a work request form.

I & C Technician to sign off this step wnen completed.

Licensed Operator to sign off this step when comoleted.

.18 Withdraw safety red group 1 to the full out position.

.19 Initiate safety features RC System low. pressure bypaas between 1750 psig and 1650 psig.

CAUTION:

TRIP is at 1600 psig.

.20 Continue with depressurization and cooldown. Monitor and plot temperature-pressure to stay within Process Standards Figure 101-2a.

NOTE:

Establish letdown and purification for RC System as necessary.

.21 When main steam pressure falls to approximately 500 psig, bypass the main steam line failure logic.

Place the main feedwater control and block valves in manual and closed.

Leave the startup feedwater valves in auto.

approximately 500 psig main steam pressure, bypass the

.22 At running main feedwater pump by opening MCM-154 With the main feedwater pump at minimum speed, place it in manual and secure it in accordance with OP A.50.

3.4-9 Rev. 17

- -. ~ -.

~~

.. :: : *..~. u e i

.,... _.....u-u..

reaches 100'? int:ia:e Se :1:n 6.'

.23 When :he RCS :e:pera ure es:aclisa : ndensa:e and feedwa:er sys:e=

of 0F A.a7, ::

u:e ::ndenser che=is:ry f or layup. Change valve ineup ::

l-pi: su=p pu=p cischarge :: :he polisher su=p. :2 pen 2DS-a?.;

Closa CDS-493).

0TE :

Layup che=istry is no required 1,f shutdown is f or shor: dura:icn <43 hours and condenser vacuu= is not :o ha broken.

When the RCS pressure is below 100 psig verify the low

.1; range RCS pressure ::ans=1:ter is in service.

.25 At 675-700 psig RC Syste= pressure, close the core flood isolation valves (EV-26513 and 26514).

Open AC supply sw1:ches at MCC-52D2 and :ag, in accordance wi:h 0F A. A.

When the RCS te=perature decreases :o approx 1=ately 350*?,

.26 adjust pressurizer level controller se: point :o 90-115 inches, per CF A.3, See:1on 6.0.

.27 When =ain stea= pressure has decreased to N200 psig verify that the auxiliary boiler has picked up the lll auxiliary stea= load.

.28 When RC Syste= te=perature is %310*?, stop the RC Su=p in loop A and establish 1 or 2 RC Pu=ps running in loop

'3'.

.29 3efore the RCS pressure /te=perature relationship falls below the =ini=u=, per process standards curve 101-1a ;

verify RCS boron concentration is 1 the cold shutdown boren concentration; and, that 11% shutdown =argin exists ;

hen, insert all safety groups and akeup at RCS boron concentration.

"0TI:

Rack out and clearCRD breakers A i 3. Supervisor, il-Nuclear Operations Division, per=ission required prior to re-enersi:ine, CRD's.

300*F, begin in-

.30 When :he RCS te=perature decreases to sSS:

on the operating range creasing the OTSG Icvels to in accordance with 0F A.6, Section 6.0, or Section 1.3 if for wet layup.

NOTE:

Sn=ple :he RCS and verify :he=istry is vi:htn.4pecifica: ion prior Oc reach-ing 200*? RCS :e=perature.

e.. i _,.

.w,..

5.G

?L/d:~ C00L;0'C: (Continued)

.31 ihen RCS tenperature approaches 1:::::AL in service as per OP A.25 and the NSCU300*F, place the'NS!C 0F A.24 system system in service as per 32 When RCS temperature /pressurc is 120

  • following equipment under clearance wi h0 F/300 psig, place Racked Out:

(Closed), HV-26106 (Closed)STV-29107 (Closed), SFV-29108 t

sed), HV-26105 l3

, HV-20003 (Closed), P-291A, P-2913.

l^9 NOTE:

1 Breakers may be racked in as required f scheduled Surveillance Testing.

or

.33 Establish RCS pressure and temperatu ation of RC pu=ps and decay heat systre for simultaneous oper-heat removal system in service per OF A 8then, place the decay em;

, Section 4.3.

.34 Close HV-23801; open EV-23802 to provid pressurizer.

Observe OP A.3, Section 6.0 for presse HPI spray to the cooldown.

urizer

.35 When the decay heat system is in auxiliary feedwater service, rackout 6.0.

system in accordance with OP A.51and tag the

, Section

.36 Follow OP A.8, Section 4.3 for coold own with the decay heat system.

goTE:

Continued cooldown with simultaneo0 long as the RCS operating pressureof RCP's and s operation e erable as observed.

temp stratification.)(This will reduce RCS hot / cold l curves are eg

.37 uriser cooldown. Follow OP A.3, Section 6.0 to contr l R o

CS pressure and press-

.38 When the RCS be at a85%

temperature decreases to :230*F to secure OTSG feed, maintain weton the operate range.

the OTSG's should Follow OP A.6..Section 6.0 blanket on the-layup OTSG's if condenser vecu,um is brokenand place a nitrogen

.39 Vnen RCS temperature is 1200*F tection as follows:

, establish RCS overpressure pro-1 and SFV-23812.Close and place clearance on HV-23801

, SFV-23809, SFV-23811 _

.2 to remain open when RCS <200*FCaution tag the e ock valve, HV-21505 3

On control room console ElRC switch, for pressurizer 'electromatic r l, place the key lock selector position.

(key will normally be left in the ief, in the Lcw e switch).

3.4-11 Rev.19 A

. _ _ = _

5.0 PLANT C00LOOZ: (C:ntinued)

INITIAL

.39 (C: tinued) 4 Place clearance on breakers for HP! pumps ?-23dA and ?-2383.

CTI:

HV-23801, SFv-23809, SFV-23811 and/or SFV 23812 may be opened as required for maintenance or Surveillance Testing if an in series valve in their respective RFI line is closed and placed under clearance or the RV head is removed.

High pressure injection lines may be lined up as required for.the performance of SP 203.01A I

or 3, SFAS Digital Channel 1A or 13 Refueling Test,

without in line valves tagged or the RV head being removed.

When OTSG feed is terminated close MCM-165 and :"/,M-166, and place 40 the condensate and feedwater system in cleanup.ecirculation to the condenser, per OF A.47, Section 6.0.

41 When the RCS is less chan 200*F, verify RCS boron concentration l.

and chemistry.

^

If condenser vacuum is to be broken, shutdown the condensate and

,42 feedwater system per OP. A.47, Section 6.0.

NOTE:

If condenser vacuum is to be broken for longer than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, place the feedwater heaters and reheaters in layup, per OP A.53, Section 6.0.

Uhen the RCS is cooled down to approximately 150*F, initiate fur-

,43 ther cooldown of the pressuriser in accordance with 0F A.3, Section 6.0.

44 When the RCS temperature is 140' to 150*F, the pressurizer cool-down is completed, and a nitrogen blanket has been established in the pressuri:er; the makeup system may be secured in accordance with OP A.15, Section 6.0.

45 When the decay heat cooler outlet temperature is <135*F and the MU pump stopped, the decay heat purification mode may be placed in service per OP A.8, Section 4.5.

.46 At 140*F the cooldown is considered complete; however, it is recommended co further reduce coolant temperature for personnel

}'

comfort and safety if RC systems are to be opened.

t 3.5-12 Rev. 17 m,a

5.0

? '_A':7 C00L30'C: / Con:inued) s NOTE:

If the RCS is to be opened f or =ain-tenance or refueling, vent the RCS loop high points and the CRD's in accordance with 0F A.1, in preparation for draining.

6.0 NATUP.AL CIRCULATION C00LDOWN

.1 Reactor Coolant Pumps (RCP's) Tripped (Operator or Automatic Function).

Initial Conditions

.1 Reactor tripped.

.2 RCS being maintained 150*F subcooled by:

.1 Pressurizer control, OR

.2 HPI flow, OR

.3 Control of RCP seal flow /RCS =akeup or letdown flow.

.3 Auxiliary Feedwater System (Aux FWS) in service.

F Procedure

.4 Verify Aux FWS auto start on loss of RCP's.

If Aux FWS does cot start, core cooling must be provided by HPI flow in accordance with Emergency Procedure D.2 Reactor / Turbine trip. Aux. FWS must be restored in accordance with 16 Emergency Procedure D.14, Loss of Steam Generator Feed.

.5 Verify both OTSG levels approaching 50% on the Operate Range recorders (%135" Startup Range).

.6 Verify RCS temperature / pressure relation 150*F but

<l50*F subcooled. Take manual control of feedwater flow race and/or RCS pressure control as required to maintain pressurizer level at 150 1 50 inches.

CAUTION:

If RCS AT approaches 100*F or subcooling is

<50F, iactease flow through the core by:

1) increasing Aux FWS flow, 2) raise OTSG level to 95 (slowly) 3)

increase steam flow (T3V's or ADV's)

Monitor RCS subcooled 150*F closely.

Maintain pressuriter level 150 1 50" while raising OTSG levels.

3.4-13 Rev. 16

l 6.0 SATURAL CIRCL*LATION C00LDOWU (Continued)

)

.1

.,7 Verify natural circulation by:

.1 Th rises about 35'? above T and stabilizes in e

15 to 30 minutes (also incore TC's).

.2 RCS iT increases and stabili:es in 15 to 30 minutes.

.3 Te re=ains steady or decreases slightly and is at saturate temperature for secondary pressure.

4 Trend computer " Assign Group A, Group No. 15."

_, Compare trend points 1 and 2 (T, loop A&B) with h

trend points 3 and 4 (incore T 's).

They should be e

of similar value and trend.

.5 With Th off scale high, refer to Casualty Procedure C.47, inadequate Core Cooling, v

With "Tg off scale low, verify RCS subcooling utilizing

.6 "T Sat meters (120*P-920*F) and Incore TC's (0-2000*F).

CAUTION:

4 Monitor pressuri:er level and makeup tank level j

during natural circulation cooldown. A sudden g

1 W

increase in either level while pressure is con-stant or decreasing indicates flashing of water to steam inside the RCS.

If this occurs, rake the following actions:

.1 Increase ".JS t ersure using H. P. Inj ection.

.2 Incr;gt< IT' levels 18

.3 Increase OTSG sceaming races.

4 R'efer to Casualty Procedure C.47, Inadequate. Core Cooling.

.S With all RCP's stopped, if RCS pressutx increases to >2300 psig or indicated T /T i= plies Technical Specification pressure /

h c temperature limits may be' exceeded and natural circulation

-cannot be confirmed:

.1 Open the EMOV by placing key lock selector switch on ElRC in the OPEN position.

Reduce RCS pressure 75-100 psi.

(Time required for valve to be open l

s10-15 seconds.)

l

.2 Close the EMOV by placing key lock-selector switch on l

HlRC console in the HIG'd position.

3e prepared to l l) i= mediately close the EMOV block valve if the IMOV

~does not reseat on command.

3.4-14 Rev. 18 4

6.0 SATl'RAI. CIRCL1ATION C00LDOWN (Continued)

.1

.3

.3 Continue this cycle until RCS pressure decreases to

{

within 100 psi greater than secondary side pressure.

I 4

IF RCS pressure increases to 2300 psig, again repeat steps.1 and.2 above.

Continue this cycle until one of the following occurs:

.1 Natural circulation has been established.

.2 One RCP has been started.

(Section 6, step

.12.)

9 If natural circulation has been established.

Maintain the RCS in hot shutdown condition by using T3V's (condenser l.

vacuum) or ADV's (no vacuum) for RCS temoerature control.

I The above is assuming RCP's will be available within a few hours.

.10 If natural circulation cooldown is desired or necessary, plot cooldown using Process Standards-Figure 101-2a.

NOTE:

Maintaining the RCS between 50*F and 150*F subcooled will ensure RCS pressure / temperature limits are not exceeded until RCS pressure is reduced to 800 psig.

7g Use of the pressurizer spray lined up to the makeup pump is allowed for depressurization to remain on the pressure temperature window.

CAUTION:

Using pressurizer spray requires isolating one HPI Injection valve.

Do not use pressuriser spray when criteria for stopping High Pressure Injection is not met ( Eme rgency Procedure D.5).

Below 1525 psig, minimum desired subcooling is %150*?

to maintain the fuel under co=pression.

.10a Maximum cooldown rate is 100*F/ hour. -(May.imum cooldown rate with Te3280*F is 50*F/ hour).

Depressurize gradually (75-100 psi steps). This will prevent flashing in the Reactor vessel head due to residual =etal heat.

3.4-14a Rev. 18

.....,. _.,,. C,-,. C.,.

o.

...e3.,,

........u..

..:.u.

..J

..n..

.1 (Continued)

oni:or RC5 _

5.

comparing Tg J 3 C-6 2;* ?) ei:.- !:

.11 (30-630*?'. un:11 T. goes off scale lo.

'?i:5 T.

off scale use :he highss: indica:ed incere :her=occuole

?

sith !.

o de:er=ine reac:or

.T.

anc Oc= care -

.__-s Res:ar: c:. RC?,s 7, requires feed :o a:.eas: one v.:v>;

.1 With RCS subcooling verified stable a: >50*?, and natural circulation flow established, star: 1 RC?

IAW normal pu=p star: procecures 0? A.2, RC?

Systa=.

Do not operate more than 1 RCP/ loop.

.2 If natural circulation flow cannot be verified and RCS pressure exceeds secondary pressure by 600 psig, or RCS > 1600 and not decreasing, run one RCP for 10 seconds or un:il motor a=ps decrease to -600 a=ps-(preferred RCP in operable GTSG loop).

Allow RCS pressure / temperature to stabilize.

ggg NOTE:

When an RCP is started,be prepared for RCS pressure swing due to mixing of hot and less hot water.

.3 Subsequent "10 seconds" RC? runs may be repeated at 13-minute intervals until natural circulation flow is established OR until each RCP has been run once.

4 If subcooling can be verified, start original RC?

(first 10 second run) and =aintain forced circulation.

')

3.1-13 Rev. 13

..a. 3..a.................. ~ C...

.,_..e_s

,y_

.1

. '_2

.f

~f su-ccolinz :an not be verified,.ain:ain : re

coling ;AN. 2:erz. ?re. '.; un:11 suhccolin2 of
he RCS can be es ablished.

..u t 1)

An RC Pump res:ar: is all:ved 2n'y if feecuater is available :: a: 'eas: :ce steam zenera:::.

2) 5:andard precau:icns :: be Obserte pri:: ::

l pu=p rescar:.

.1 CCW has been =ain=ained or vill be reinstated p'rior :o s:arting the RC pumps.

.2 Seal inj ection flow has been =ain:ained : all RC pumps.

.3 Seal return is sain:ained or is reins:a:ed prior to starting pu=ps.

4 Pressure >250 ps12.

3)

E=ergency op.eracing lisi:s for continued pu=p operacion.

.l' Shaft runouc ' vibration) shall nec exceed 30 mils.

13 I

l 3.1-16 Rev. 13

6.0

  • ATURAL CIRCULCIO:: COOLDOWN (Continued)

.1

.13 Verify the reactor is >L'. shutdcun.

RCS zust be borated

- )

to the cold shutdown condition.

Refer to OPOP 3.6,

_ 0.

.14 Terminate RCS letdown flew as required.

Maintain RC?

0 seal supply until RCS temperature is 1150 F.

Insure sufficient RCS inflow to maintain pressurizer level 150 t 50 inches.

.15 Establish pressurizer spray flow with the =akeup system

)

in accordance with 0F A.15 as required to control RCS pressure.

.16 Continue RC$ cooldown in accordance with applicable As RCS portions of Section 5.0 of this procedure.

temperature decreases, insure subcooling of the RCS 0 F.

is at least 50

.17 With Aux FWP's supplying the OTSG's, break condenser vacuum when the CST level reaches the Lo-Lo level alarm point (29' 3").

With the Plant Cooling Water and Reservoir System in service in accordance with 0F A.36, shif t Aux FWP's section to site supply system when the CST level reaches the Lo-Lo-Lo level alarm point (3').

l P-318, Open PCW-076 - then close MCM-057 llh P-319, Open PCW-079 - then close MCM-058

.2 RCP's to be stopped by Operator Action with RCS subcooling verified.

Initial Conditions

.1 At least one RCP operating.

.2 Reactor tripped for at least 10 minutes.

Procedure

.3 Verify Aux FWS in operation and RCS parameters stable.

.4 Manually control Aux FWS flow to slowly raise the OTSG 1evel to 50% on the Operate Range recorders.

Control feedwater rate to insure pressurizer level remains at 150 + inches and RCS pressure remains steady.

.5 Verify RCS > 100 F and 1 150 F subcooled (T-SAT meter, Th, 0

Tc and/or incore Tc's).

Slowly adjust OTSG secondary level between 50% and 95% on the Operate Range as necessary to maintain this amount of subcooling BEFORE stopping the last RCP.

3.4-17 Rev. 16

.y..

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

..y...._........3.,.

.,a.....

.2

.6

~7 hen RCS pressure :en; era:ure and pressuri:er 'erel are

he RCP's in ac::rdance wi:h 0F a.2.

s:aole. :-1:

~.*erify !._ and/or in:cre T,'s indi:ste a steacy rise f

^

2.

I saculc retain about 35+? above ;e, :nen 5:a0111:

c steady or decrease slish:ly "erif:. 3C' subccoling does no: decrease :elow 50 7.

Resta-: at leas One RC? (preferably one/lcop) if a:

of subecoling is not naintained, or least :his amount provide core cooling wi:h 'dP! fl0t..

.3 Ref er :o see:1on 6.1. 7 :hrough 6.1.17 for continued RCS cooldown.

Cooldown shall be in accordance wi:h Process Standards, Figure 101-2a.

A3NOR.JJ OPERATIONS 7.0

.1 Solid Plant Operation Initial Conditions

.1 Reactor / Turbine tripped.

Emergency Procedure D.2 in progress.

.2 The following plant conditions are established in accordance wi.ch Emergency Procedure D.5.

.1

'dPI is providing ' core cooling.

.2 All 4 RCP's tripped.

.3 Aux. F'4P(s) supplying feedwater to at least one OTSG in automatic mode.

4 RCS is 1500 F. subccoled.

.3 Pressurizer indicated level is off scale high.

(Verify at all available indicators).

P rocedure 4

Establish a steady cooldown of the RCS of at least 200 F/kr taking manual control of the T3V's (use ADV's if r.o condenser vacuum).

.5 Verify natural circulac oa cooldewn in accordance wit!.

OP 3.4, Section 6.

3. ' -13 Rev.16 f

I

7.0 A3 NORMAL OPERATIONS (Continued)

.6 Adjust =akeup/ gpl flow to con. trol RCS pressure.

Insure subcooling of at least 500 F.

Utilize the Pressure / Temperature curve at the HlRC and "T-S AT" indicators.

.7

. Continue to adjust =akeup/ injection flow as necessary, to of f-set RCS pressure changes due to steaming of the OTSG(s).

NOTE:

Both steaming rates and HPI injection can cause dramatic pressure swing in RCS pressure.

Ideally, the steaming rate should be stabilized (requires frequent operator attention) and the RCS injection rate varied as necessary, to stabilize RCS pressure.

Any changes in flow rate (steam or injection) =us t be done slow 1v and one at a ti=e.

Allow plant conditions to becore steady af ter each adjust =ent.

.8 Determine the pressurizer temperature as indicated at the H1RC.

Using the Pressure / Temperature curve, determine saturation pressure for the pressurizer.

lll

.9 Place all available pressurizer heaters in service in accordance with 0F AP.3, Pressurizer, to support establishing a steam bubble.

.10 Maintaining at le ast 50 F subcooling, permit the RCS' pressure 0

to decrease to saturate condition for the pressurizer.

CAUTION:

Verify natural circulation is not interrupted by this action, i.e.,

Tc rate of decrease and core AT should remain steady.

.11 When saturate conditions have been reached in the pressurizer, RCS pressure will stabilize.as further RCS cooldown takes place.

.12 With RCS pressure stabilized, slowly reduce makeup / injection flow to a minimum.

Ideally, RCP seal supply flow will provide necessary makeup.

1

.13 RCS shrinkage due to cooldown will establish a visable level in the pressurizer (monitor all available pressurizer level indicators),

j 3.4-19 Rev. 16

\\

7.0 A350ttu. OPERATIONS (Continued)

'41th an indicated pressurizer level of 150 - 50", adjust

.14 makeup / injection flow as necessary, to stabilize indicated level.

cooldown in accordance with Section 6 of this

.15 Continue plant Procedure.

?

3.4-20 Rev. 16 r: