ML20135H812

Rev 33 to Procedure B.4 Re Plant Shutdown & Cooldown

ML20135H812
Person / Time
Site:	Rancho Seco
Issue date:	08/12/1985
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20135H794	List: ML20135H793 ML20135H797 ML20135H800 ML20135H803 ML20135H807 ML20135H809 ML20135H812
References
B.4, TAC-57558, NUDOCS 8509240254
Download: ML20135H812 (22)

Text

_ _ - - - _ . __

. EFFECTIVE'0 ATE-08-12-85 ,

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' Rev. 33 WP0871P D-0035P.

4 4 8.4 PLANT SHUTDOWN AND C00LDOWN .

i 1.0 PURPOSE ,_ r. , y {;

.1 -To outline the steps by which the nuclear steam system is shutcown from [.

15 percent power and cooled to the cold shutdown condition. _ . . ' g j;m.,

a ; g m,, . , .

,, , , [

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.1 P1 ant Shutdown, Section 4.0 , .7, y: 2, ; , .

.2 Plant Cooldown, Section 5.0 ,

,. , 3 .; 2 ,

.3 Natural Circulation Cooldown, .Section 6.0 >

, q.. 9 . c, , - 1 2 l ,.

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2.0 REFERENCES

,c , _ _g a  ;

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, .1 SMUD Rancho Seco Unit 1, FSAR, Section ib," Technical Specifications;. ou Nrm.::cr.n i { .

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.2 SMUD Rancho Seco Unit 1, Plant Process Standards , , ,

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.3 SMUD Rancho Seco Unit 1, Water Chemistry Manual, AP.306 ,; scag'g m ., e ,.

,- .4 SMUD Rancho Seco Unit 1, Plant Operations Mar.ual . h u ; s L'L i

3.0 LIMITATIONS AND PRECAUTIONS >

.1 Maintain RCS Pressure, temperature, and coolcown rate within the limits of g .

, . t Process Standards Curve 101-2a. g .3, ,,,J

.2 The pressurizer cooldown rate shall not exceed 100 F/hr. m. e, ,, ,

.3 Maximum allowable aT between the RCS cold let temperature and pressurizer, , 3 ", . '

temperature is 410*F. .

l .4 The secondary side of the OTSGs shall not be pressurized >200 psig if the temperature of the steam generator shell is < 130*F. .

.S The feedwater-temperature to the OTSG shall be no more than 350*F below

, OTSG downcomer outlet temperature. , 3 i

.6 Do not open valves connecting the decay heat removal system to the reactor coolant system until reactor coolant pressure is less than or equal to the i maximum pressure snown in Process Standaros Curves 101-30 through 101-3K,

and/or 101-4, and until RCS temperature is less than 290*F.

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Rev. 33 b.4-1 8509240254 850919 PDR ADOCK 05000312 PDR <

p s

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LIMITATIONS ANU PRECAUTIUNS (Continued) l 3.7 At all times during Cooldown, the reactor shall be maintained at least one percent subcritical . If suurce range count rate increases abnormally, f discontinue couldown until cause is identified and corrected.

.8 Maintain makeup and purification system ano decay heat removal system boron concentrations equal to or greater than the boron concentration of the reactor coolant system 's ucn that the reactor coolant system is not

- diluted during cooldown. .

.9 Observe allowable RCS pressure-temperature curves for sitaultaneous -

operation of RC pumps and Decay Heat System; see UP A.2.

10 Continue seal injection ano component ccoling water to RCS-puups until RCS ,

temperature is <l50*F.

.11 Before RCS temperature decreases to 500 F, at least one RCS pump must be ,

taken out of service.

.12 Close core flood tank isolation valves when KCS pressure decreases to <700 1

but >600 psig.

.13 All subcritical boron changes snall be verified every estimated 30 ppm j change or hourly,'whichever is more frequent.

.14 Between 0 anc lb percent reactor power, maintain ' pressurizer level ,

commensurate with, but not less than, Process Standards Curve 101-16. , ._ , - ,

.15 Maximum allowable aT betneen OTSG downcomer inlet temperature ana RCS Tcold .( >

is 25 F.

.iti Maximum allowable RCS temperature cnange rate bet'aeen 0 ano 1$ percent power is 150*F/hr.

.17 Maximum allowable aT between OTdG average shell temperature anc RCS temperature is 60*F (see OP A.6, Enclosure 8.6 for calculating UTSG Average Shell Temperatures.

.18 To prevent inadvertent actuation of the auxiliary feedwater system during cooldown, the automatic start controls for the pumps ana valves shoula be placea in manual prior to cooldown.

.19 The auxiliary feedwater system shall be used for filling an empty _

(< 8 inches level) OTSG wnen RCS temperature is >200*F.

.2U If all RC pumps are lost during cooldown, continue KCS cooldown via natural circulation per Section 6.U.

.Z1 The maximum allowable aT between KCS Thot and Tcold is 100'F.

.22 When cooling the RCS with one OTSG in a dry condition, that OTSGs Average Shell Temperature must be within luu'F of tne KCS temperature and maximum Thot and Tcold across that UTSG is 10*F.

Rev. 4 d.4-2

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LD18 TAT 10NS ANU PRECAuTIU'NS -(Co'ntinued) ts > , de f. j 3.23 For loss of OTSG feed or decay heat removal system, see Emergency ; , ,. >

' Prccecure C.10 or C.12, respectively.  ;,.o .,,

.24 Control roa safety group 1 shall be fully withdrawn whenever positive .

reactivity is being acced to the reactor of either xenon, borun, , ,

temperature,: or motion of part lengtn control rods. The following .m,..,,. 3; exceptions may be applied. .;w. ,

~

.l

.1 .The reactor coolant system has been borated to at least the hot, f r., ,,c: ;-r y

. xenon free boron concentration anc is being maintainea at hot, "

, g,. g .

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shutdown.: . t , ..

2,_ .2, ,  ;

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7,,-. 3

.2 The reactor coolant. system has bsen boratea .to the' cola's'nutdownj Mc;y mm e ., :

baron concentration and'the plant is;being:cooleo down., ' . _

g,y, ,y .1,

. 4 2  ; -

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I ..25..lf O gAnalyzer is out of service, notify. Chem-Rad to sample within.;4 4 f, ;,, a . ,, ,

hours of start of plant coolaown.'

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.26 If there exists 'a known primary to secondary--leak, and the Hogging. Air y m = c ,; : [;

Ejector, the Auxiliary Feed Pump Terry Turbine, .or any.of the Atmospheric e;. g.

Dump Valves, the Main Steam Relief Valves,' or.the Auxiliary Steam Relief, gp .m i:

. Valves operates, the information requested in Enclosure' 8.2 must'be. c,mns.n.( [

recorded and given to Chem-Rad as soon as is practical.N Also.fensure: ro,0f g .ggy m.4.[

area is clear of p'ersonnel prior to. hogger operations under ;these - ;. m 3 e g . 7 [

ci rcumstances. . m.y ,-  ;

l.

l(  : 4.0 ' PLANT SHUTDUWN .

a ,, - Iu lT IA L b _ ,[h [

a(

j Initial Conditions , ie p ., .m 4 i

Unit is 15 percent power.

] .1 , -u ,

.2 Unit T ave is controlling at 582*F and Reactor Coolant Pressure . '.y

. is controlling at 2156 psig.- , -4. .

.3 Two main feedwater pumps and one condensate pump operating mx, (Preferaoly one main feedwater pump in auto ano the other in .

..; f ,; n . ; ,

j manual at minimum speed).. _

., i

.4 At'least two circulating water pumps in operation. .

. .5 An auxiliary boiler is -hot.and pressurized per UP _ A.39, Section '4.0. .

3 s

.6 RCS shutdown boron concentration has Deen determined for hot -

shutdown and/or cold. shutdown per UP B.6 and calculations made per f[p i

B.9 to insure > one percent 'shutcown margin during all stages of s ,,,

plant shutdown and/or cooldown.

.7 Pressurizer. level control in " Auto" and controlling at 200 inches. l Rev. 33 1( 8.4-3 ,

h .t L I 1 ,:

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i PLANT SHUTU0dN (Continued) lulTIAL 4.6 Plant loads transferred from unit auxiliary transformers do.1 and 11 0 . 2 to startup transformer, per UP A.bu. . ('

.9 If the RCS is to be cooled down, KCS degassification is in progress per OP A.lb and/or UP A.3.

Procedure i NuTE: ,, .

1 Communicate witn SMUU dispatcher prior to , j switching power supplies, large equipment ,

such as RC pumps or anything that would j affect power transmissions.  ;

6

~

i CAUTION:

If UTSG is isolated due to tube leak, do not j open blowcown or drain to condenser.' j i

.10 Place reactor steam generator, feedwater loops A and d and reactor . .- i demand in hand and decrease feedwater demano to zero. Establish _

,, n ,  ;

, .0TSG blowdown per OP A.e. ,a j

- NOTE: ii

~ This insures that UTSG is being controlled .t at minimum level.  ;

.11 Place tne EHC in " Operator Auto." 7 a

.12 Set speed-load reference setter at Su MW. [ g

.13 Set loaa ' rate setter to five percent per minute or less. a. 3

.14 Depress EHC "Go" pushbutton. As load decreases, observe turbine bypass valve maintains steam heacer pressure at setpoint (Bub psig).  ;

.15 At -10 percent. turbine generator load, taxe the reheaters out of ,

service in accordance with UP A.46. .

.16 When load decreases to ~50 MW, trip the OCBs and remove main

• generator excitation per UP A.64, Section 6.1. Observe turbine ., ,

bypass valves are controlling header pressure at 885 psig. ,

CAUT10s: .

Prior to accomplisning the next step, verify that UCB-220, UCd-230, ano the Main Generator Field Breaker (41) are OPEN. Failure to have ,

all tnree (3) open will result in a reactor trip when the turbine is tripped. -3 CAUTION: ,

The Turbine Trip pushoutton HUST be used in

,the next step. Use of tne Generator Trip pushbutton will result in a REACTUR TRIP.

Rev. 33 8.4-4 ,

t t

?

e s PLAdT SHUTDOWN' '(Continued)

. Jc:; INITIAL CAUTIUd:

Tripping the Turoine at a reactor power level ,

f- greater than 10 percent will result in an RPS

~

Anticipatory Reactor Trip.

4.17 Trip tne turbine and observe that AC bearing oil pump starts on iz . g decreasing oil pressure. Start the bearing lift pump. .

- .18 Follow OP A.46, Section O.u, for steps to completely place the ,i,,g,. ,

F

,< i-unit on turning gear. _ , o. [.

l

.19 Gradually ' reduce reactor. power't'o 8 ' percent wnile monitoring 'and / .w w ;,, 3 l

, plotting cooldown' rate.,(maximum of Ib0*F per hour-between u and f W. ;,m

~^

. [

. - ~ . < 1S percent power). g , ,

.- g- , j NOTE:

Between '0. and .lb percent ' reactor power  ;

, adjust pressurizer level setpoint to

.i

' decrease pressurizer level to 90-115 j inches.'> Maintain pressurizer level u s decrease commensurate with but not less ,

js

than Process Standards Curve lul-lo.  ;,j

- l

.20 Between 8 and 5 percent reactor power,' place the CRU panel ,in manualj. ,3... y , . - .[

and gradually reduce power to <2 percent, by inserting the ;p .- . a i, , , ;

- - - regulating group. ,

._4 n NuTE-(

~ ~

iidakeup to the makeup tank, as required < - 61

-to maintain makeup tank level between , --i 60 and 80 inches. If going to cold shutdown, acd concentrated boric acid as -

calculated per B.9 for boration during ,

cooldown.

.21 Ine plant is now at hot standby: - ,

.1 Reactor .is critical at <2 percent power. ,-

.2 RCS pressure is being controlled at ~Z1bb psig. , ; ,

.3 RCS Tave >S2S*F. ,

.4 Startup feecwater valves in auto. ,

.5' Main steam pressure being controlled at -885 psig by the -

turbine bypass valves. .

.6 One (1) condensate pump and two (2) main feecwater pumps '_

in operation (one main feed pump in auto, and the otner in manual at minimum speed).

Rev. 33

{' B.4-S

i PLANT ShuTUUWN (Continued) . INITIAL , ,

4.22 To take the plant to hot shutdown, complete the following: ,

.1 With the Cdu panel in manual, insert the regulating groups to I

reduce reactor power to lu-D .aups, while monitoring and .y. ,

. plotting RCS cooldown rate. , ,,

.2 At 10-0 amps anu steady, record reactivity balance , , . , ,. a.

information as required below: yy ,

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.1 Rod Ccnfiguration . . .a . {

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, .2 KCS Boron Concentration + W , 4. h ' .

, . , 1- : u ,: : ,j-

.: . ..:=' . ~. -

RCS Pressure Temperature ,- 4js y

- - ~ .3' .

.4' Date/ Time -o j',

.3 Further reduce reactor power to -Sx10-11 amps by inserting .

.'tr  ::r - ,f the regulating group. , -. . ,

, t 1

fl

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NOTE:

Ubserve that source ' range . instrumentation , i -j is energized at approximately bx10-10 amps. ,

.i .

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.4 At -5x10-1I amps, . verify source range instrumentation is on _. - u s , y- }

scale and indicating no greater than Sx10-D CPS. -3,5,.3,,.3:(.

CAUTION :  ;

[.

If the source range instrumentation does not -

'- (J indicate <bxluS CPS when the intermediate L.

range is at bx10-21 amps, the requirea one  ;.

decaue overlap does not ex{pt.. Reactor power i:

shall be maintained >Sx10- amps until at -

least one source range channel is operaale. 7

.5 Fully insert the regulating groups. .

NOTE:

If the plant is to be cooled down for refueling, group 8 may be insertea at tais time, if reactivity addition due to inserting group 8 will not decrease shutdown margin to -

3.

<1 percent shutdown. ,

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Rev. 33 6.4-6 '

f e

h'

+

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PLANT SHUT 00WN (Continueo) , INITIAL ,  ;

4.22 .6 When it has been confimed that >l percent shutdown margin ,

will exist, per B.6 calculations all safety groups may be

C,- inserted.

NOTE:

For cooldown ' safety group 1 shall be witndrawn. .

! - NOTE:

If : desired, ; for cooldown, the ;RCS may be  ;

~ barated at this time to the cola shutoown ,g Doron ' concentration. Since it is desirable [

Jto baten borate for cooloown, the pressuri- ,,

- ' zer level may .De increased to 290' inches ,[

2 :during oaten boration. See b.9 for' boration [.

during cooldown. j

.7 Upen MCet-lb5 and rtCct-166,' feeuwater. loop A/B startup

.,,,., , i.

j recirculation valves to the condenser, to establish condensate j recirculation flow. Throttle open FWS-129 ano FWS-130 to r provide continuous minimum feedwater flow to each OTSG. ,.

l i

.8 The plant is now.at hot shutdown. , ,

t 4

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.1  ;

Reactor y_1 percent shutdown. , .g,

.2 RCS,Ta ve ' 2.525 *F . ,_,

7 i( .3 RCS pressure being controlled at approximately 2155 psig. ,; 3 4

.4 Main steam' pressure being controlle'd at approximately ,

j 885 psig with tne turDine bypass valves in automatic.

j .S OTSGs on low level control (30 inches).

.6 One (1) concensate pump ano two -(2) main feedwater pumps running (one main feed pump in auto and the other in ,

manual).

i S.0 PLANT COOLDUWN Initial Conditions ,.

.1 Reactor is in a hot shutcown condition. ,_

.2 Safety Rod Grup 1 fully withdrawn.  :

.3 RC Hakeup aligned per UP A.10, for feed to makeup tanx from demin. {

RC Storage Tank and from concentrated boric acia tank.  :

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!( Rev. 33 8.4-7

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INITIAL ,

PLANT CUOLUUWN lContinueu) , , f f. ,

5.4 Boren concentration / addition requirements determined per B.b and e_n .j.

calculated per UP b.9 for cold shutdown or for refueling (_

concentration.  %

.5 RCS degassing completeu- per UP A.lb and/or UP A.3. _

.6 Stop one main feedwater pump in accordance with OP. A.bO. Verify the -- .g.

. n .[:

remaining feecwater pump is. in automatic .and verify.MQ1-lob and , .

ae .-c. 2 > rj -

3. . < n , j.

- MCH-lbb are open with condensate' flow to condenser. .

).

.7 Place tne' automatic ' start signals lfor the euergency feedwater. systewi f a l

~

g g }

in manual 1 pumps and valves).- f,;; - i :o- lp i.; 3 j.

m o. .

.8 Close the ' letdown ' isolation valve'SFV-22009.Mionito'r 110 tankIlevel M. g , g.., f.

and feed at the required boron concentration as necessary during. .3;.l; . g q a .s j cooldown to maintain the Mu tank between ~ 60 ano 80 ' inches. ; , _. - -

2 ., )

i

. .9 With OCS-220 and OC8-230 open, have Electrical Tect[nician complete ap ,

. g.3.g ,

4 l-EM.174 with System Dispatcher's authorization.- -

. p - t NOTE

g.

' l Verify the RCS boron concentration every ,

n}p estimated 30 ppm change. Sample the .

'ty pressurizer water space for boron concen- .. g L

- tration and periodically increase spray cm

flow as required to keep the pressurizer ., g g,

boron concentration greater than RCS boron gj

' concentration minus du ppmd. .. (

--7.L I

CAUTION:

If OTSG is isolatea due to tube leak, ao not , ,

open blowdown or drain to concenser.

.10 Establish a drain path from'the UTSGs to the HP condenser in _

,., . , . , 'p.

accordance with UP A.6, Section b.U. Follow UP A.6 for steps to '[ }l;  :

control UTSG levels during cooldown. c

.11 Establish one RC pump running in each loop l(preferaoly B .ano DJ.; ,,

NOTE:

Sequence for' stopping KCPs during i

cooldown is: C, A, B, and D. -

4

.12 Initiate and control RCS cooldown with the turbine bypass valves. . , ,

Monitor and plot RCS _ cooldown rate. Turn pressurizer heaters UFF ,

g and spray the pessurizer as required to staf within Process L Standards Figure 101-2a.

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i Rev. 34 8.4-3 , ,1 i

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PLANT C00LDOWN (Continuedj . aiTiAL' 5.12 (Continued) ,

NOTE:

.f Should it be necessary to close eithe.r the pressurizer spray isolation valve (HV-21610) or the Er10V isolation valve (HV-21606) while

- the plant is hot ano tne reason for closure would not prevent further valve operation, ,

.the valve snould be cycled every 100'F as the l

- plant is cooled down to prevent valve wedge seizure due to contraction or the valye boay. $'

1 Follow; , . .. ,k

.13 Vent UP A.3, the Section:

pressurizer 6.0tofor the PRT in accordance pressurizer cooldown.with OP A.3.. Vent the H0 .tack e.

as , p~

,g ,:; p necessa ry. -

, ~ , i i

.14 When RC system pressure decreases to between 1560 psig and 2000 psigi.c, .

ce  !<

terminate depressurization and cooldown. ,

5

[

3

.15 Drive all safety ' roa' groups to the full "in" position as per

- 4 a, n-U.P A.74.

n0TE: f If,cooldown is for refueling and group 8 {

- has not been insertea, it may be fully. .

f.,;

. - - inserted at this time (prior to inserting p s safety groups). Insertion of group 8 will e

- ada positive reactivity, therefore, monitor g neutron count rate closely ana verify

. f .;

(,

>l percent snutdown margin. t

.16 Trip the reactor and continue to depressurize to 1750 psig, ,

_.; n terminate depressurization. -

NOTE:

Adjust turoine bypass valve setpoint as -

required to maintain RCS temperature steady. p

.17 Initiate Reactor Protection System shutdown bypass per OP A.69, Section 5.2. ,

.18 Notify the I and C Department to reset the high flux trips to ,,

<5 percent per OP A.69, Section S.2, (In accordance with I-104.)

Fill out a Work Request form. .. _ , ,

I and C Technician to sign off this step when completed with _

Step 5.2.8 of A.69.  ;

t Licensed Operator to sign off this step when the Reactor Protection -

I System is in shutdown bypass. .

.19 Withdraw safety rod group 1 to the full "Out" position. 1

( Rev. 33

.A B.4-9 t

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, INITIAL PLANT C00LDOWN (Continued)~ _

~

5.20 Initiate safety features RC System low pressure bypass between ,

~

'1750 psig and 1650 psig.  ;

CAUTION:

TRIP is at 1600 psig.

.21 Continue with depressurization and cooldown. Monitor and plot _,

temperature-pressure to stay within Process Standards Figure 101-2a. . ., . -

NOTE: '

- -' > Establish Lletdown .and purification for RC - ,

{

' . System 'as necessary. . ,

y j

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. 22 When main steam' pressure. falls to approximately 500.psig,; bypass the . c , ,

main steam line failure logic. Place the main feedwater control arid J,2. , ,, ,

block valves in manualland closed. Leave the startup feedwater ., , ., ..

~ valves in auto. , , _

j,

.23 At approximately 500 psig main steam pressure, bypass the running '

3 ,

main feedwater pump by opening MCM-154. i With the main .feedwater

~

i , , . 1

,3 pump at minimum speed, place it in manual and secure it in accordance( ,

a ~ ,'; ,

with OP A.50. .

.24 When the RCS pressure is,below 400 psig,' verify the low range RCS ,., .;. ,

gs ,,

[

pressure transmitter is in service.

l

.25 At 675-700 psig RC System pressure, close the core' flood isolation ' .

.y , , ;g :

valves (HV-26513 and 26514). Open AC supply switches at MCC-5202 ,, ,

and tag, in accordance with OP A.4.  ; .

i.

.26 When the RCS temperature decreases to approximately 350*F, adjust , ,

pressurizer level controller setpoint to 90-115 inches, per OP A.3, Section 6.0.

.27 When RCS temperature reaches 350*F, initiate the UTSG Hot Soak . ,, ,

procedure in Section 7.6 of OP A.6. A temperature hold is  ;

~

needed on the RCS between 350*F and 300"F until the Hot Soak .

is completed.

33> .28 Close HV-23801; open HV-23802 and J0G open SFY-23810 to -

provide HPI spray to the pressurizer. Observe OP A.3, Section 6.0, for pressurizer cooldown. _

.29 When RCS temperature reaches 350*F, establish RCS overpressure ' , ,

< protection as follows:  ;

.1 Caution tag the electrcmatic relief block valve, HV-21505 ._

to remain open when RCS < 350*F. .

Rev. 33

. B.4-10 ,

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. . PLANT C00LDOWN (Continued) J.h.TNITIALj.; ] [

5.29 .Z Place the EMOV key lock selector switch, on Control Room . ,e y  ; ,9,e console H1RC, in the icw position. (Key is normally left 3- g n '

in the switch.) Ensure RCS pressure <470 psig prior to .

performing this step. -

33p .3 Close and place clearance on HV-23801, SFV-23809, SFV-23811 '

., m ,

and SFY-23812. _'~]

.4 Place clearance on breakers for HPI pumps P-238A and P-238B. 3, u , m. . . . ( .

s NOTE: _

j m[

HV-23801, 'SFV-23809, SFY-23811,' and/or ~ <

7 ,

- ;SFV-23812 may be opened as' required for , c.  !.

maintenance or Surveillance Testing if an . N (

'in-series valve -in their respective HPI .

e is . .

line is closed and placed under clearance ,

((

or the RV head is removed. . High pressure ,. .

injection lines may be lined up'as required ,

Ei for the perfomance of SP ZU3.01A or B, SFAS ' -

.}l Digital Channel 1A or 1B Refueling Test, .

witnout in-line valves tagged or the RV head - L h {;

c being removed. yj

'I

.30 When the RCS temperature reaches 300*F and the OTS6 . q ,yHot ,, gSoakproc g y , p, OP A.47, to establish condensate and feedwater system chemistry foryp; ,,g g m ;;

layup. ' Change valve lineup to route condenser pit sump pump 99 ggg, g p discharge to the polisher sump. (0 pen CDS-494; Close CDS-493.) ,-.1 a

.g ; t; g3 jy

{' '

NOTE: f Layup chemistry is not required if shutdown -

,.7, is for short duration <48 hours and condenser vacuum is not to be broken. .

.31 When main steam pressure has decreased to -200 psig, verify that,y g u. . . = .,

the auxiliary boiler has picked up. the auxiliary steam load. --

., e- 3:

.32 Before the RCS pressure / temperature relationship falls below the, je m _, e minimum, per Process Standards Curve 101-14; . verify RCS boron g, , .c y .c. 3 concentration is > the cold shutdown boron concentration; and, that ~, ~ ~ ;.,, "

>l percent shutdown margin exists; then, insert all safety groups. 7'7 , l and makeup at RCS boron concentration. .

NOTE:

Rack out and clear CRD breakers A and B. Supervisor, ..,. ,

Nuclear Operatons Division, permission required prior i

< to re-energizing CRDs. y

{

.33 When the RCS temperature. decreases to -300*F and the OTSG Hot Soak [

procedure has been completed, begin increasing the OTSG levels t.

to -85 percent on the operating range in accordance with OP A.6, ,

Section 6.0.

Rev. 33

( B.4-11 ,

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. PLANT C00LDOWN (Continued) ,

" INITIAL.

5.33 (Continued) ,

NOTE: (

Sample the RCS anc verify chemistry is within specification prior to reaching 200*F RCS temperature.

i l .34 When RCS temperature approaches 300*F, place the NSRW system in _

m p service as per UP. A.25 and the NSCW system.in service as'per. ,

e j i

- . OP A.24. j i

.35 equipment When RCS temperature / pressure is <2'00*F/300 psig,L place the following M jc under clearance; CLOSED 7 with the; applicable breaker 2 ,

Racked Out: SFV-29107/42-2A144 (Closed),iSFY-29108/42-28153 , J.,3, ,  ;

i (Closed), HV-26105/42-2A142 (Closed), HV-26106/42-2B151'(Closed), ec . .

' HV-20003/42-2A179_ (Closed), P-291A/52-3A09,iP- 2913/52-3809.'- .

i .

NOTE:

. Breakers'may be rackea in as required for testing. _

t .

.36 Establish RCS pressure and temperature forf simultaneous operation of, ,

, , . j.

RC pumps and decay heat system;- then, place the decay heat removal m j, Z.? y

.y

, - system in service per OP A.8, Section 4.3. . _.

I 33p< ~

.37 When the decay heat system is in service and RCS <200*F, rEk out > n. u.. ~ y 3 and tag the auxiliary .feedwater system in accordance with OP A.51, Section 6.0. . .

pg g ,7 .g 7..

[

=

.38 Follow OP A.8, Section 4.3, for cooldown with the d'ecay heat system. a, 2 (' , ..

4 Continue the cooldown with simultaneous operation of RCPs and " i .,. . ' .. D decay hgat system in accordance with RCS operating pressure curves ' .

I to <l50 F.

I

.39 Follow UP A.3, Section 6.0 to control RCS pressure and pressurizer . ,3 coolcown. ,

.40 When the RCS temperature decreases to -230*F, the OTSGs should be , e at 85 percent'on the operate range. Follow OP A.6, Section 6.0 to  ;

- secure OTSG feed, maintain wet layup, and place a nitrogen blanket' . , , ,

on the OTSus if condenser vacuum is broken. ,

.41 When OTSG feed is terminated, close MCM-165 and MCM-166, and place the condensate and ~feedwater system in cleanup recirculation to * .

the condenser, per OP A.47, Section 6.0. ,

.42 When the RCS is less than 200*F, verify RCS boron concentration and s  ;

l chemistry.  ;

.43 Secure last RCP when RCS temperature is <150*F as read on wide [

range Tc. (This will prevent RCS hot leg and upper head area .,

j temperature stratification.)

.44 If condenser vacuum is to be broken, shut down the condensate and feedwater system per OP A.47, Section 6.0.

Rev. 33 B.4-12 ,

i 1

2 . _ _ . _ . , _ , . - - _ _ - - , , _ _ _

j

+ .

3 -

o =

.c ,

PLANT C00LDOWN (Continued)

. au ,3 g, jq . p ,, [.

?

5.44 (Continued) 3 ' " , '- '

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. .g

.45 When the RCS is cooled down to approximately 135'F, initiate further.

cooldown of the pressurizer in accordance with OP, A.3,'Section 6.0.

yh[n p

[

.46 When the RCS temperature is 135'F, and the pressurizer,cooldown is,' Jg. :

completed, and a nitrogen blanket has been established in;the.

t

,c. ,.c m,

.g, z y ,j 3 pressurizer; the makeup system may be secured ;in.^accordance with -- , f:g , g4 3 ],[ . p:,, ,

OP A.15,'Section.6.0.' .

, ;.g., ,

q. .g gy,; , f- .g.,a. l

- - >' , ' ' . - .  : c

.47 When the decay heat cooler outlet temperature ,is ;<135*F:and the.HU : , ,3 g , 3 ,, _. ;

pump stopped, the decay heat purification mode D,may be placed.inf . g. , , .7 ~

-U r service per OP A.8, Section 4.o. * - ' .-. , .i 41 - p +

- l

.48 At 140*F the cooldown is considered complete; .however,,it.is . gj recommended to further reduce coolant temperature for personnel g . . q 3 g comfort and safety if RC systems are to be oper.ed.

. . ;c ,7;.m.e77 4;; g . ,, ,f NOTE: , I If the RCS is to be opened for mainten- ', s ,f.

ance or refueling, vent the RCS loop _

,u., _p high points and the CRD's in accordance ,j . chil with OP A.1, in preparation for draining. .n =

,34 4 6

6.0 RCS NATURAL CIRCULATION COOLING , . 7 .

}f

.1 Reactor Coolant- Pumps (RCP's) Tripped ,

r

< Initial Conditions -,.,

.2.:- . -.

.1 Reactor tripped. ,,

s 1

s i Procedure 7 1

.2 Verify conditions required for natural circulation. 4-

. .u.. p

.1 Verify Aux FWS auto start. ,

.2 Verify both OTSG 1evels approaching >50 percent on the Operate j' Range (-135" Startup Range). ,

r Rev. 33

-( B.4-13 ,

i e

{l:

I' i

4

< i NATURAL CIRCULATION COOLING (Continued) 4;g 6.1 .2 .3 Verify RCS >50*F subcooled and RCS aT is <100*F. .

3 4 If the previcus three steps cannot be verified, core cooling must be provided by HPI flow. Perfona EUP Procedure E.02. ,.

[

Verify Natural Circulation ~

.3 .u . j m -. . t ,,

+

k

.' 1 Th and'incore T/C's rise about 35*F above .T c and commence to ,y . .e f track Tc in.15 to 30 mnutes. (These values are indicative ~of 4h, 3 a full power trip with both UTSGs operable.)' 1 e f t

.2 .T c remains steady or decreases slightly and is ~at or slightly  ;, ., .

j greater than saturate temperature for OTSG secondary pressure. G 5

- h

'I

.3 Tctracks OTSG secondary side Tsat- o a i

.4 Th and incore T/C's track ' changes in OTSG secondary side ,

7,, y J pressure. f. , -

.5 Trend computer Group No.15 " Loss of X and/or Y." Compare trend " .

.... I points 1 and 2 (T h, loop A and 8) with trend points 3 and 4 d ~, .J -

-(incore T/C's). They should be of similar value and trend. g,.g .f

( *

.6 :If T h,' loop A or B, is off scale high, refer to E0P ,

l Procedures, Inadequate Core Cooling. ,

.7 If T h, loop A'or B, is off scale low, verify RCS subcooling utilizing the "Tsat meters (120*F - 920*F) and incore T/C's __ y (0-2000*F). t

.4 Maintain the Plant at Hot Snutdown .. ,

.1 If natural circulation has been verified, maintain the.RCS in .

hot shutdown condition by using TBVs (condenser available) or 7

ADVs (condenser unavailable) for RCS temperature conrol, if a -

natural circulation cooldown to cold shutdown conditions is not f ~

immediately necessary. Refer to Step 6.1.7 for cooldown. , i.

CAUTION:

Maintaining >b0 F subcooling takes precedence  ;

over controlling pressurizer level. .

Rev. 33 B.4-14

/

f f

m u

NATURAL CIRCULATION CUOLING (Continuad) 6.1 .4 .2 Control feedwater and/or RCS makeup flow rate as necessary to maintain pressurizer level 150

• 50 inches. Ensure RCS is I maintained >50*F but <100*F subcooled.

6.1 .5 RV Thermal Shock Considerations If RCS temperature dropped below 500*F and exceeded 100*F/hr, i

OR l l

If RCS temperature dropped below 500*F and RCPs are off and flow i exists through any HPI inject valve as indicated on the HPI l flowmeters: l

.1 Stabilize the plant temperature / pressure within the Thermal 7' Shock Operation Region of Enclosure 8.1 (>50*F subcooled but

<100*F subcooled) and prevent any heatup or pressurization above i' the stabilized condition for at least THREE hours.

.2 Notify the station management of the plant condition. (

.6 Restart of RCPs (Recuires Feed To At least One OTSG.)

NOTE:

Prior to RCP restart, it is desirable to ensure the pressurizer is 'in a saturatec condition to minimize the RCS pressure swing that occurs due to mixing of water of dif-ferent temperatures. Also, just prior to starting an RCP, it is advisable to close .

any open TBY's or ADV's to minimize the cool-ing effect. The valves must' be reopenea to continue the cooldown.  :

.1 Observe the following precautions for each RCP that is to be restarted:

.1 CCW flow is established.

.2 Seal injection flow is established. ,

.3 Seal return is established.

.4 RCS pressure is ,> 250 psig.

Rev. 33

{ 8.4-15

NATURAL CIRCULATION COOLING (Continued) 6.1 .6 .2 Start one RCP IAW normal pump start procedure OP A.2, RCP System (preferred RCP in operable OTSG loop, if applicable). Do not ,

operate more than one RCP/ loop.

.3 If an RCP has been successfully restarted, continue RCS cooldown, if desired, IAW applicable portions of Section 5.0 of this procedure.

.7 Monitor Natural Circulation Cooldown

.1 If the RCP's are unavailable and a natural circulation cooldown is desired or necessary, monitor the cooldown using:

.1 Process Standards Figure 101-2A if there is no flow through any HPI loop inject valve OR

.2 Enclosure 8.1 if there is flow through any HPI loop inject valve.

NOTE:

During the natural circulation cooldown, it is advisable to cooldown/depressurize as slowly as plant conditions allow to (

minimize the possibility of void formation in the reactor vessel head region or hot legs. The depressurization should be in steps not to exceed 70-100 psi.

CAUTION:

During the natural circulation cooldown, monitor pressurizer level and makeup tank level. A sudden increase in either level while pressure is constant or decreasing could indicate voiding in the RCS. In addition, .

unexpected pressurizer level changes during makeup or spray operations could also indicate voiding in the RCS. If voiding is suspected, stop any depressurization and repressurize to

- maximum pressure allowed by applicable cooldown curve and raise OTSG levels to 95 percent on the Operate Range. Do not continue cooldown on natural circulation unless required by plant conditions. If continued cooldown is required, cooldown and depressurize as slowly as possible for current plant conditions. Monitor natural circulation l

closely during the cooldown.

Rev. 33 B.4-16 l

NATURAL CIRCULAT!ON COOLING (Continued) 6.1 .7 .2 During the natural circulation cooldown,' monitor incore T/C's to determine RCS subcooling margin. If the subcooling margin

(,

decreases to < 50*F or RCS AT approaches 100*F, refer to E0P Procedurc E.07.

CAUTION:

Using auxiliary pressurizer spray requires isolating one HPI injection valve. Do not use auxiliary pressurizer spray when criteria

, for throttling or stopping HPI is not met.

(EOP Rule 2.2.)

.3 Establish pressurizer spray flow with the makeup system in accordance with 5.36 of procedure B.4 as required to control RCS pressure in relation to RCS temperature. Maintain RCS subcooling. > 50*F 'during cooldown.

.4 Continue plant cooldown with natural circulation until the Decay Heat System can be placed in service IAW OP A.8 or RCP flow can be established..

i .5 With Aux. FAP's _ supplying the OTSG's, break condenser vacuum when the CST reaches the Lo-Lo level alarm point (29'3"). With the Plant Cooling Water and Reservoir System in service IAW OP A.36, shift Aux. FWP's suction to site supply system when the CST level reaches the Lo-Lo-Lo level alarm point (3').

P-318, Open 'PCW-076 - then close MCM-057

. P-319, Open PCW-079 - then close MCM-058 '

1

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

Initial Conditions .

j- .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.

( Rev. 33

.B.4-17 i

NATURAL CIRCULATIUti COOLING (Continued) l 6.2 .4 Manually control Aux FNS ficw to slowly raise the OTSG 1evel to 50 percent on the Operate Range recorders. ( ,

Control feedwater rate to insure pressurizer level remains at 150

• 50 inches ~ and RCS pressure remains steady.

.5 Verify RCS > '100*F and < 150*F subcooled '(T-SAT meter, Th, Tc and/or

~

incore Tc'sT. . Slowly aajust OTSG secondary level between 50 percent

- and 95 percent on the Operate Range as necessary to maintain this amount of subcooling BEFORE stopping the last RCP.

! .6 - When RCS pressure / temperature and pressurizer level are stable, trip

~

the RCP's in accordance with OP A.2.

Yerify Th and/or incore Tc's indicate a-steady rise of about 35'F above T c , then stabilize. T should c remain steady or decrease slightly.

.7 Yerify RCS succooling ~ does not decrease below 50*F. Restart at least one RCP (preferably one/ loop) if at least this amount of subcooling is not maintained, or provide core cooling with HPI flow.

.8 Refer to Section 6.1 through 6.1.4 for continued natural circulation operation.

7.0 ABNORMAL OPERATIONS

.1 Solid Plant Operation Initial Conditions

.1 Reactor / Turbine tripped. E0P's E.02 in progress.

.2 The following plant conditions are established in accordance with E0P CP.105.

.1 HPI is providing core cooling.

.2 All 4 RCP's tripped.

.3 Aux. FWP(s) supplying feedwater to at least one OTSG in automatic mode.

.4 RCS is > 50*F subcooled.

.3 Pressurizer indicated level is off scale high. (Verify at all available. indicators.)

Rev. 33 B.4-18 O

L-

r:

A8.10Rt4AL OPERATIONS (Continued)

Procedure

[ .7.1 .4 Establish a steady cooldown of the RCS of at least 20*F/hr taking manual control of the TtiV's (use A0V's if no condenser vacuum).

.5 Verify natural circulation cooldown in accordance with OP 8.4, Section 6.

.6 Adjust makeup /HPI flow to control RCS pressure. Ensure subcooling of at least 50*F. Utilize the Pressure / Temperature curve at the HlRC and "T-SAT" indicators.

.7 Continue to adjust makeup / injection flow as necessary, to offset RCS pressure changes due to steaming of the OTSG(s).

NOTE:

Both steaming rates and HPI injection can cause dramatic pressure swing in RCS pres-sure. Ideally, the steaming rate should be stabilized (requires frequent operator atten-tion) and the RCS injection rate varied as necessary, to stabilize RCS pressure. Any changes in flow rate (steam or injection) must be done slowly and one at a time. Allow plant conditions to become steady after each adjustment.

.8 Detennine the prassurizer temperature as indicated at the H1RC.

Using the Pressure / Temperature curve, detennine saturation pressure

[. for the pressurizer.

.9 Place all available pressurizer heaters in service in accordance with OP A.3, to support establishing a steam bubble.

.10 Maintaining at least 50*F subcooling, pennit the RCS pressure 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.

i

!( Rev. 33

~

B.4-19

-. - . .- .. .. .. ==

ABNORMAL OPERATIONS (Continued).

7.1 .13 -RCS shrinkage.due to cooldown will establish a visable level in the  ;

pressurizer (monitor all available pressurizer level indicators). (

.14 With an indicated pressurizer level of 150

• 50", adjust makeup / injection flow as necessary, to stabilize indicated level, i .15 Continue plant cooldown in accordance with Section 6 of this l procedure.

i 8.0 ENCLOSURE 4 .

j .1 Reactor Coolant System Interim Fracture Limit--No forced Flow And Thennal Shock Operating Region.

.2 Radiological Release Infonnation 9

f 4

4 e

e a

L i

Rev. 33 B.4-20

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

ENCLOSURE 8.1 _

FIGURE 1 REACTOR COOLANT SYSTEM INTERIM FRACTURE LIMIT

( NO FORCED FLOW AND THERMAL SHOCK OPERATING REGION 3200' . . _ . .

5 NOTE: Maintaining the reactor -

E coolant subcooled takes 3000 - -

5 precedence over the Interim NO FORCED FLOW OPERATING BAND 5 Brittle Fracture Curve E (B&W 74-1122501 page.6) W/HPI - - -

2S00 --

5INTERIMBRTTLEFRACTURE VARIABLEi 2600 5 CURVE BREAX POINTS 5UBC00 LED ;

5 INTERIM BRITTLE "--.E:

TEMPERATURE PRESSURE I .

FRACTURE CURVE m. .

2400 -

= .'x '

E 303 250 ' N - -

E 500 1E00 '

1l L,;

w 2200

'5 '

~

RESTRICTED - -

~

2000 REGION < _

-f'

'~

. . _ . v

.~_

• ~~

. S800 ,.

T. 5. CURVE 3.1.2-2 f '

Z NOT LIMIT '

E 1600 \ -

q x .

-c '

W .

" 'I.

1400 - ... .. -. ..- ....

= ' '

E THERMAL SHOCK -

/

5 1200 OPERATING REGION ___.

x

.c -

~

E INCCRE TC'S TO MONITdR' .'N'

'ef  : .

._f - SATURATION 3:

1000 -E CURVE g

- i, ,

N'x z' J EPREFERRED ALTERNATE _

E T9256

'N . f' 800 -

E1) T9254 '

Nm . ,' '7

2) T9258 T9260 z' .- '

E ) T9263 E3 T9252- , e '

e'3 . . '

1. ' 7 - -/'

600 -E4) T9272 T9266 -

T9270 .-

, r' RESTRICTED REGION E l5) T9286 f

_ ,'. t2 j." ,' j f- /- f.f 400 - ,- , '

5 ' :' ,

-_= == m =m ==w z =m' - _ y ,y

.2CD -

- s.'

x ':-

-s'

!( o , ,

0 100 260 360 460 560 6d0 700 INDICATED RC TEMPERATURE- *F Rev. 33 B.4-21

1 ENCLOSURE 8.2 j RADIOLOGICAL RELEASE INFORMATION

.1 Hogging Air Ejectors

.1 How Many

.2 Condenser Vacuum

.3 Duration ___

.4 Date-

.2 Atmospheric Dumo Valves

.1 How Many

.2 Duration I .3 Date

.3 Main Steam Code Relief Valves

.1 Which Ones

.2 Duration of Each

.3 Date

.4 Auxiliary Steam Relief Valves

.1 Duration

.2 Date

.3 Side Supplying Steam

.5 Auxiliary Feed Pump (Terry Turbine).

.1 Duration

.2 Date END Rev. 33 B.4-22

- , , - - - - - - . ., , , . ,p - , y ,,-,-y ,-.