Text

Rev 2 to C.13B, Cooldown from Hot Shutdown to Cold Shutdown W/Fire in Control Room. Related Info Encl
	ML20155H654
Person / Time
Site:	Rancho Seco, 05000000
Issue date:	09/12/1985
From:	; SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:	;
Shared Package
ML20155H523	List: ML20155H518; ML20155H562; ML20155H585; ML20155H596; ML20155H625; ML20155H627; ML20155H636; ML20155H645; ML20155H654; ML20155H665; ML20155H686; ML20155H706; ML20155H720; ML20155H726; ML20155H742; ML20155H774; ML20155H798; ML20155H841; ML20155H894; ML20155H911;
References
	RTR-NUREG-1195 C.13B, NUDOCS 8605160320
	Download: ML20155H654 (59)
	v • d • e

- . .

% EFFECTIVE DATE N 09-12-85 Rev. 2 s

C.13B

. CDOIDOWN DCM IDI SHUIDONN TD CDID SHUIDOWN WIDI A FIRE IN THE CCNIRCL ROOM 1.0 SYMPICMS

.1 It is zwwamary to cooldown the Reactor from the hot shutdown condition to the cold shutdown condition when acx:sss to the Ccntrol Roca has been lost due to a fire in the Control Room.

.2 off-Site power may or may not be available.

2.0 RESPCNSE

.1 Initial System Conditions

.1 Procedure C.13A, " Hot Shutdown Frt:n ShutdcWn Penal with a Fire in the Castrol Roca," has been ocupleted.

.2 Reactor N 1arit System is in natural circulation, c .1 #w414=vy Feedwater Pump (P-319) is providing feedwater ,

( flCW-

.2 Heat remewal is threugh the Main Steam Code Safety Valves.

.3 BC system volume is ma4

4med by the HPI system through ,

RCP seal injection and opening HPI valve SIV-23811 as

recluired.

.3 RCS *mmtwrature stable or slowly decreasing.

.4 RCS pressure stable and in allowable range for the RCS rantuvatura per Enclosure 4.1.

.5 E.-- w4 E level above 100" Pted and stable.

(Enclosure 4.2).

.6 Cha HPI/lO pump alternata recirculaticn path to the BWST is in use, per C.13A, Enclosure 4.5, steps 7. and 8.

.7 BC pung seal injection is at 12.0 gpn (3.00 ggn per RCP),

as read at the local f1cu indicator (FI-23606A) .

Rev. 2 C.13B-1 y:. ,

h S

9 RESP WSE (Ca tinued).

2.1 .8 OISG levels between 242 inches and 368 inches on t% wide range level indication. .

Q .

.9 AEW to the "A" OISG is being w iuulled fr a the Shutdown Panel by use of the AEW cross-conrmet valve HV-31827.

.10 AEW to the "B" OISG is being controlled frcza the Shutdown Panel by the use of AFW bypass valve SEV-20578.

.2 Recpired Acticris j .1 Beform initiaticn of cooldown, the Shift Supervisor shall:

.1 Direct I&C technicians to ocrinact the Portable Sourm Neutron Flux Indir star per I.109F. An operator assist, if av=41=hle.

.2 Station a watcts to monitor the Source Range cour:ts.

.3 Direct cmtinuous caumznications to be established between the Shutdown Panel and Scurce Range Flux Mcnitor.

.2 Senior Centrol Rocza Cs .atcr:

.1 Ensure the Ah- , hic Dung Valves (AD7s), have a

positive centinuous air supply as follows:

CAUITCN The he f cDiesel Air Cw-.sicr has s five hours of diesel fuel in the l h tanks. Ioss of the h e fcDiesel Air Cwm for any reason will rencis miaul of the AN- ; h-ic Dung Val'res and cause them to close.

.1 If the he y cDiesel Air Cw-i sor is running, additional fuel m.ist be mela available.

Than go to 2.2.2.2.

.2 If the he f Diesel c Air Cw.esor is not available, valve in nil ,, h the ADV's per C.34, "T .- 9_1y ADV Nit. ogen Systam."

.2 Direct an cim.atcr to gM .o the Turbine Area Grade Inval and operate the ADV Manual Ccntrol Panel in accordance with C.37, "A^ - ,Mic Dump Valve Manual Icading Station OperatiCD."

RBV. 2 C.13B-2

~

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l RESPCalSE (Ccritinued) -

l l

p' 2.2 .2 .3 Likul AN Valves SW-20578 armi HV-31827 fra the Shutdan

_ Panel to regulate feedwater flow.

NCrs: . -

RCS pressure will decrease slowly due to Pressurizar heat losses to the RB envirmaant.

.4 Direct an operator to monitor incore th-; --:e_'ples in acocedanos with Enclosure 4.3, Incore h --:O m1_ a Mcnitoring.

.5 G Lul RCS 'wature by directing makul of the At2nos-pharic Dung Valves, to ma4'*=in RCS *=mparature versus RCS pressure within the limits of Enclosure 4.1.

.6 Maintain 3 --Mzer water level at er above 100 incises emY=nsated (Enclosure 4.2) by wikullinJ HPI valve SW-23811 fra the h*% Panal.

NCTE:

Make up to the RCS is fra the NEST.

Step 6 ansures the required bort:n m' W is maintained.

.7 If the plant is 130 affective full power days or more into tha fuel cycle then:

, I

.1 Instruct an cF ..bu. to line up Boric Acid Pungs (P-705A) and (P-705B) to the alternate power sourca and barata the plant in accordance with the " Boric i

Acid Transfer Pung Repair" g_- --W.

NCTE:

23ere is a Safety Feature Actuation System (SFAS) trip at 1600 psig RCS pressure which has not been defeated f

fra the a:ritrol room. Siis signal will not affect the ocoldown or

T'4==nt positioned by the Hot herh=1 3._-r t 'm.

.8 If dammar1 pernamaty, direct operators to install temporary

~

fans in accordance with C.31, "Ioss of Swier Ventila-ticri. "

.9 Maintain an RCS cooldown rate of 10 degrees F to 50 degrees F per hour for tenperatures greater than 400 ha F.

I Rev. 2

C.13B-3 i

m

s. .-

RESPCNSE (Continued) 2.2 . 2 .10 When the RCS cooldown rate falls balw 10 dog..es F/hr, whl Pressurizer level as follows:

.1 Reduce the RCP seal injection flw rate fra 12.0 M to 8.0 M as read on local fl w indicator (FI-23606A).

m:

Batch feeding the RC pump seals injects water into the seals for 15 mimtes, then allows the seals to sit in a hot sytem for 15 minutes.

.2 Itan mg to limit Pressurizer level increase, batch feed the RC pung seals twice per hour as follows:

.1 Cicae the seal supply fl w m a.wl valve, W-23606, using the local PW-1.

.2 Racpan W-23606 slwly after 15 mimtas to reestablish RCP seal injection at 8.0 6 total flw.

.3 Repeat the above process twice per hour until the Decay Heat system (IES) is p1=M into service at 290 M--jc F.

m:

Nhan rees*=hlimhing RC Pump seal

')>

injectica, use the local RC Pump Seal injecticn flw indication (FI-23606A).

.i

.4 Fra IES initiaticn at 290 degrees F, until the HPI/W Pump is secured at 150 degrees F, use cmtinuous RCP seal injection at a flow rate of 8.0 M , and control Pressurizer level by rejecting to the 5t!rr via HV-26046.

m:

'Iha Fnler= CE serves as the back-up AEW supply.

.11 When the condensata Sh.ge Tank (CST) level reaches

5 feet, direct an operator to positica the follwing l motor operated valves using the local manual handwheel

I

.1 HV-43504 Reservoir Tanlatim Valve Open Rev. 2*

C.138-4 e

--oeMeme e ne ' wm -ee tm e t v s o' e e b -m , ,- ~ --~wwe = w - - - - - - - - - - - - - - -

RESPCNSE (Contirmed)

p. 2.2 . 2 . 11 .2 HV-43603 Reservoir Line Strainer (Y-436B) Open Isolation Valve AND HV-43012 Eservoir Line Strainer (Y-436B) Cpen Isolatim Valve OR HV-43607 -Reservoir Line Strainer (Y-436A) Open

. Isolation Valve AND HV-43606 Reservoir Line Strainer (Y-436A) Open Isolatim Valve

.3 HV-430ll Strainer and Boost Pump Isolation Open Valve

.4 HV-43010 Canal Isolation Valve closed

. 12 If the Folsa Canal source of AEW is reglired then direct an q =.e h to:

.1 Open AEW Pump (P-319) suction r.anual valve PCW-079 to ocuplete the flow path.

.2 Close valve 105-058.

. 13 Before RCS pressure decreases to 600 psig, direct an operator to:

.1 Close Core Flood Tank isolation valves, HV-26513 and

' L HV-26514.

. .2 After all other means to close the valves have been expanded, antar the Reactor m4M4m and close using local handwheels.

. 14 Before RC5 teim (T bot) decreases to 300 degrees F or below, direct an q=;&tcr to s uc.Wed to the 480 Volt West Swit*=- Rom and position the followirq breakers:

Ecrir-nt Name Breaker No. Position m Pump Suction HV-20005 2A134 open m Cooler Telation Valve SEV-26039 2A106 Open m Cooler Bypass Valve SEV-26037 2A107 Open m to HPI HV-26007 2A139 Open IEI Injecticn SEV-26005 2A138 Verify Open Rev. 2 C.13B -5

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yy,e-- w-, ,. - - - - -- -v-- -,,w- r- - - - - - - -

1 i RES1CNSE (Continued) -

1 2.2 .2 .14 .1 P m ed to the 480 Volt East MCC aIxi cpen breaker 2B144. m Pump Suction HV-20006.

.2 once the breakers are open, unnually position the l following valves: ,

l Valve Valve No. Position !

l

E Pung Suction Valve HV-20006 Close m Pung 9v+1c: rt Valve HV-20005 Open I

m Cooler Outlet Valve SIV-26039 Close m Cboler Bypass Valve HV-26037 Open IJI to HPI Valve HV-26007 Close RB Isolation Valve -

SIV-26005 Open

.15 Itsen RCS pressure is 255 psig or below and RCS

wture (T hat) is 290 tsgrees F or below, direct an q - a h to initiata mS operation as follows:

.1 open m Drop Lina valves HV-20001 and HV-20002.

.2 If remote operation is icible, enter the Reactor m41d4m and open by using local valve motor hanchhael. .,

.3 Es*=hl 4ah r==w11caticr2s with the E-pJy Kht*% -

1 Panel.

.4 Start M Pung (P-261A) frun swird-Je 4A05 in the 4160 Volt West SwitM-J =r Roan.

.5 Ctritrol the m Cooler Outlet valve SIV-26039 and m Cooler bypass valve HV-26037 by local ha W aal as directed by the Rht*% Panel Ciw.ater.

.6 Raad m cooler outlet Panparature locally per I.]43,

" Decay Heat System Tenparature Monitoring."

.16 Reduce plant *=nparature below 2(?3 degrees F in accordance i

with B.4, " Plant Shutdown and Cocidown."

i .

t .17 Nhan T (hot) is 150 degrees F or less, deer-vize the HPI cr M7 pung, *4% is running.

l .18 'Iha plant is now in a Cold Safe sht*% condition. Cool-i down is cczplete Mun the limits of Operating Instruction i tion A.8, " Decay Heat System," have been met.

Rev. 2 C;13EH5 l l

I -

3.0 RESIMATICH gg .1 'Iha h*Am Panel (H2SD) will be used to wiel the plant until

',. e s_

the control Rocza is available.

4.0 EtKIDSURES

.1 RCS Pressure Iinits vs. RCS Temperature.

.2 Pressurizar Isvel Cm ction for Temperature Qation.

.3 Incore %--r---:c m1_e Monitoring.

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,.. g Page 1 of 1 INCIOSURE 4.3

.f' INCRE N MNIICRDR3 '

Preceed to Appendix R Shutdown Eqd I -t I.cckar and obtain the Doric 450 Temperature Indicator and the key for the signal Conversian Isolation Cabinet IE (H4SlA).

Davion Name of Device Acticri Doric 450 Portable Tauperature 1. Connect black lead on PIT l Indicator (PII) to red lead on the selected Tauperature Transmitter (TI)

inside panel H4SIA. !

2. Connect red lead en PII to yells (+) lead an the sams TI panel insida panel H4SIA.

3. Turn en PTI.

4. Record *Japeratures for the respective TI en the table belw.

I

! 5. Repeat the above staps for

,all 8 Trs.

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N Care A. = --xgle Temperatures Table Temperature Reading Readhg '. Readirg Reading Raadhg Transmitter #1 #2 #3 #4 #5 TIC 1005 TIO1009

, TT01013 ;

TT01019 TIO1023 TIO1032 TT01039 Tr01047 Rev. 2 END C.13B-11

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a. - . u- u--- - u-^ = - - - - ~ ~ '-

' j F . , . s i, .. .,

b u .s . . r' Y'^ I " '" " " / M fh .s - I H2PSB .

WINDOW NUMBER ACTUATING NAME SETPOINT DEVICE RESPONSE '

i 21 RCP D LO RSVR Level Hi-lo i Up jer Bearing 1. Reduce reactor power and trip the 15" F

L51-21062 RCP. !

11" LSL-21194 13><

Lower Bearing 2. Take subsequent action for RCP i 15" LSH-21066 Casualty Procedure C.8.

8.2" LSL-21188 ,

. L I

22 RCP D Seal Ret Flow HI 1.8 gpm i FSH-24026 1. Check seal return flow on computer ,

pt. F104. r

- 2. If combined seal leakage and seal i return flow for RCP exceeds 3.35 I gpm, reduce reactor power, trip '

. the RCP.

13><

3. Take subsequent action for RCP Casual ty Procedure C.8.

23 ICS or NNI 120 Volt Power Transfer Transfer to Auto Bus Xfer 1. Ensure availability of alternate alternate Device power supply to '

pwr. supply NNI X 1 J08 NNI Y 1 J06 i

ICS 1 J04 s-

2. Determine and correct cause of -

loss of normal power supply to r

NNI X 1D07 4 NNI Y 1001 ICS 1C07

3. Return to normal power supply by ~

depressing " Reset" button on auto bus Xfer device.

Rev. 13 H2PSB-8 !

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I WINDOW ACTUATING NUMBER NAME SETPOINT DEVICE RESPONSE 33 RCP D Seal Cavity Press HI 1250 pst PSH-21266 1. Check seal return flow on computer pt. F104, seal return pressure on TJR-10-11.

2. If limiting conditions for pump operation are exceeded (combined leakage and seal return flow >3.35

! gpm) reduce reactor power and trip the RCP.

i

3. Take subsequent action for RCP I?s< Casualty Procedure C.8.

I 34 ICS Fuse Fail Open/ Closed Any Fuse in 1. Monitor plant parameters closely ,

ICS cabinets to determine if plant operation is !

permissible with existing ;

, conditions. [

2. Check ICS fuse panels for blown fuse indication amber lite lit. I

3. Contact I and C to investigate and correct cause of blown fuse and '

replace fuse.

I f

Rev. 13 * [

4 H2PSB-13 ;

t

__ _ . . . _ . . - - . _ . .. . _ . . . . __ _ . ._._-_.-...1__. . .< - m

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H2PSB

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WINDOW ACTUATING NUMBER NAME SETPOINT DEVICE RESPONSE 63 RCP Reverse Rotation 12.7 gpm FSH-21121 1. Start the oil lift pump and >

Pop A commence a normal plant shutdown 13>4 12.7 gpm FSH-21122 per Casualty Procedure C.8.

Pop A

' 12.7 gpm FSH-21123 Pop C 12.7 gpm FSH-21124

, Pop C 64 ICS or Fan Power Failure Open/Close Power Supply 1. Ensure auto bus transfer device Monitor has transfered from norm. (1C07)

Airflow to alt. -

, Sensing Sw.

2. 24 VDC Pwr. Supply outputs are in parallel and not affected by AC bus power transfer. Thus the. .

l normal DC Pwr. Supply (+24V, -24V) ,

will remain deenergized with the alternate DC Pwr. Supply supplying DC loads until IC07 is restored.

3. When 1C07 is restored, auto bus transfer device can be realigned to the normal power source by depressing " Reset" button on the 4

transfer panel. ,

i

, 4. If the alarm is due to fan failure (check fans to determine if running), open the cabinet doors

, to supply cooling to ICS j

components and contact I and C.

Rev. 13 -

H2PSB-28 i .

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STP 856 )

Procedure No. J

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Title D02CENCY IV COhTROL VALVE FV-20527 I Young /F Burke 0,ge 1/21/80 Dri,inato, Approvai ,

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DUICENCY W CONTROL VA1.VE TV-20527 l y i' y s

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. .1 To verify that cable routing changes are made correctly per fire ,

> protection modifications. . ._

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. 2.0 REFEEENCES

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.1 ECN A-2472 and associated drawings.

Drawing E-205, Sh. 29. Emergency W Control Valve P V -20527. j j .2 .

i .3 EM.14'8, Standard Insulation Test for Cable. ,

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3.0 Pr.EREQUISITES

.1 That installation and inspection has been completed for the circuit to be tested.

l 4.0 TEST EQUIPMENT ,

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$ .1 hitimeter , ,

.2 Megger .

s 5.0 LIMITS AND PRECAUTIONS s

.1 That test and/or clearance tags are placed on equipment to be tested.

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.2 Ensure that all personnel are clear of circuit if meggering is

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h .3 Coordinate with Control Room on valve ' operation prior to running STP.

' I INITIAL l 6.,0 PROCDURE

.~ .1 Check, that construction inspection has inspected and approved circuit.

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.2 , Verify that proper test and/or clasrance authorization has s been obtained. , _$ .

a-Verify viring per ECN A-2472. Attach transmittal sheet and I

.3 indicate drawings used to verify wiring. .

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Megger control circuits', switch D500-11, or verify same.

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CAUTION: Do not megger solid state components.

.5 Notify Control Roces before operating valve.

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.6' Close switch D500-11 on E-205, Sh. 29. .

.7 Verify visually that valve W-20527 is open. Confirm by red light on BLFB2 on HISS. 4

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.1 .8 Operate BLFB1/ Auto to close FV-20527. y 9

J .9 Yarify that latching relay EWA has closed and latched. ConfiraA#LO that amber light appears on BLFBl. .

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.50 Verify visually that valve has closed and that lights have changed from red to green, BLFB(2 & 3).

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Fush BLFB2/Open to open TV-20527. A.744 ll .11 y

.t 9 .12 Verify visually that FV-20527 has opened and that lights have h.#'9ec changed from green to red.

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.13 BolddownBLFB2/OpenandherateBLFB1/ Auto. Verify that h

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lights do not change and that the valve does not operate.

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- .14 Release BLFB1/ Auto and BLFB2/Open, in that order. U

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. .15 open switch D500-11. .

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.16 Release to Operations. - * ' " ' '

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.1 That devices operate per Step 6.7 through 6.13.

2 That conductor insulation resistance meets the requirements of EM.143. l

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For short Time Readings of insulation resistance operate the instrument for a

, .. definite icngth either 30 seconds or one (.1) ninute and read at the end of that time.

Conticue cranking , steadily at slip speed until the reading has been taken. Hake - -

- future tests with the caec length of operating time. ...

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AP.23 EECLOSURE 1 Pag 2 1 of 3 POST TRIP TRANSIENT RIU' ORT NO. 21 :
To be filled out by the On-Shift Operations Crew "<
Occurrence Date: N Ms [, / 9 / 9 Time: /267 V l f / / _ d '. - e
., Description of Occurrence: q ss_ -
Aimf$ n - / s ,*ss C r_$ D e %< (
~
~
S t:'" 2 [ M@ )CV I L D 3 C3 C. D.@kl0N Conditions Prior to Occurrence: .
Reactor Power /M RCS Fressure [/.(( _
Turbine-Gen Load
~~f// [ ff,4 2 RCS T-ave [f~~
. ControlRodPosition(%Withdrawq Preocurizer Level ,/
t Groups 1-5 /M _ RC , Pumps in Service, l Group 6 /6Y Main Feed Pumps in Service Group 7 7I Condensate Pumps' in Service _ b Group 8 /f Main Circ Wat.cr Pucaps in Service A/
ICS Mode [g [6 l -
1 List of Equipment out of service:
rs , J, m
,.n m,- .
/
Yf ,s m, j
.i _ _ _
l ?.,
Details of Occurrence: Q;.
~~1. Type of Trip (circle one or nior or Trip, 1 biric Trip t. [r Dp p 1~~
1 1 :
i ,' l
--m _
~~m. _ . . ~ _s , - m ~~~
! t : q AP.28 ENCLOSURE 1 (Cont.) P;ga 2 of 3
[ Details of Occurrence (Continued):
' High Pressure Injection
'C au 2.
~~a. Was HPI initiated? No (Circle one) l 1. If yes, was HPI started manually by valving in the BWST or by~~
~~Safety Features actuation?~~
~~Manual, ety Features (Circle one)~~
~~b. Was HPI initiated in RCS Loop A? h No (Circle one)~~
~~c. Was HPI initiated in RCS Loop B? No (Circle one)~~
~~d. How long?~~
RCS Loop A - RCS Loop B ,
j Nozzle 1 (SFV-23809)yJ' min. Nozzle 1 (SFV-23810)~s min.
Nozzic 2 (SFV-23811 M min. Nozzle 2 (SFV-23812)~ s min.
t i 3. Atmospheric Dump Valves k
4 a. Did the valves lift? Yes No (Circle one) ,-
~~b. How many lifted? g --~ /[M (If available) / 7 f IO - -'~~
k.
~~c. For how long? (If available) .~~
,.* r
! d. How many valves were in service? - _' __ r 2 2 1 /
! 4. Turbine Bypass Valves
) /~~
~~a. How many valves were in service? _ .. efe W~~
~~b. Did the valves operate~~
~~perly? @ No (circle one)~~
~~1. If no, explain f~~
~~5. Code Safety Relief Valves (Main Steam)~~
~~s. How mny valves were in service? /~~
~~d b. Did the valves 11ft? Yes No (Circle one)~~
~~c. How many lifted? m ,. 4 [ / 8 (If available)~~
't
~~d. For how long? (If available) , ,~~
i .
c.
- - m u - -. - = - a n .-w. .
. . . - .- ,w- .
~~.~a~~
?!
b $? e ,
AP.28 ENCLOSURE 1 (Cont.) Pzgo 3 of 3 Details of Occurrence (Continued):
.G
} 6. Did S eam Generator Startup level decrease to less than 18 inches? t)
}
Ye .Ng (Circle one)
I i a. Record lowest reading observed during the transient:
d -
OTSG-A +
f% OTSG-B t #% 'C $
r
~~7. Record highest and lowest Pressurizer level experienced during the j transient. (LR-21504)~~
~~High .f 7I inches Low inches~~
~~8. Record highest and lowest RCS pressure readings experienced during~~
'the transient.
PR-21037 High 2 N AC psig Low /-- / 7 M puis L PR-21038 High 2376 psig Low 4 //vf paig h
f PR-21092 High 23[6 psig Low ,/ 2 2 I psig k, 9. List equipment damaged during the transie.nt:
U E
I
) 10. Remarks: 31.,,Wh L:?J - ,/! W v / g,r>
h t
u
~~t. .~~
~~Computer Print Outs:~~
~~1. Attach the " Sequence of Events", " Memory Trip Review", and " Alarm Typer" computer printout sheets to,t is,repo c. ?~~
f'
@* '?
cmf Computer Print Outs attached to report.
+ fif*'t-No '(Circio one)
! Completed a ..,
1 i t,) G 1
.j'
&2 r, ,
j ATTACHMENT To E.nclosure 1 -
AP.28 Post Trip Transient Report No. 36 ,
Description of Occurrence:
{
0 A technician performing a modification to the test panel and the ICS allowed i
a wire connected to a terntnal in the ICS to swing free and caused a short circuit which'in turn caused one of the two ICS power supplies to trip.
At this point a number of non-nor:al conditions were imposed upon the
~~ICS which in retrospect are difficult to establish and therefore' analyze.~~
i Suffice to say that feedwater flow was dramatically reduced, resulting in a
' reactor coolant pressure increase, with all four RPS channels tripping on high pressure approximately 0.16 seconds into the transient. The turbine was automatically tripped and both generator 0CB's opened within 1/3 of a second. Approximately 70 seconds af ter the trip on high pressure, low RCS pressure was reached in the RPS. This was due to relatively high feedwater flow continuing as a result of failure of the isolation valves to close.
It is estimated that at least twice the quantity of feedwater necessary for removal of decay heat was being provided at this time.
At 2 minutes 53 seconds into the transient, the Safety Features Analog channels tripped, bringing into service High Pressure Injection, Decay Heat and Reactor Building isplation. Normal feedwater flow continued to increase .tnd was augmented by Auxiliary Feedwater started by the Safety Features. At approxi-mately 5 minutes into the transient, feedwater flou had increased to nearly ,
2.2 million lbs./hr and was, at that pgint, terminated by operator action when the ICS power was restored. From that point on, feedwater supplied was limited ~ ]
to that from the Auxiliary Feedwater System, and both boiler feed pumps were ,
tripped at approximately 7 minutes. As a result of the massive quantity of feedwater supplied, the RCS was not only depressurized to the SFAS actuation level, but was cooled down at a higher than nominal rate.
The "C" Reactor Coolant Pump was tripped at approximately 10 minutes 30 seconds into the transient, while the minimum Reactor Coolant System temperature of approximately 430*F was reached at 15 minutes into the transient. The minimum RCS pressure was reached at approximately 6 minutes into the trans'enti and was increased af ter that point due largely to the large quantity of High Pressure Injection water being injected by the Safety Features actuation.
. The "0TSC-A" level increased during the transient and subsequent to Safety Features, was brought under control and level remained on scale. The "OTSG-B" was lik.ewise being filled but as a result of loss of Safety Features indication to the "A" Safety Features panel, was filled to the top of the
~~operating range and continued at that level for 10 to 15 minutes. The filling of CISG-B was the single most significant cause of the excessive cooldown race.~~
At some time early in the transient, the pressurizer heater circuits were lost due to a ground fault. As a result, RCS pressure was maintained by compressing the residual steam bubble using high pressure injection to fill the pressurizer.
~~These heaters were not raturned to service until approxinatoly 00 minutes into the transient. All safety fescures eqetpment performed as designed during the~~
. g s
f
~~., m ..~~
ATTACHSTNT to Enclosure 1 (Continued) . ,
!.- 4 ._/
Description of Occurrence: (Continued) l transient and subsequent actuation. All control rod assemblies dropped clean and shut down the reactor as desired. Subsequent review of the Reactor Coolant Pump seal performance data shows no abncrmal seal behavior or reason to suspect t
degradation appears.to beof240 the inche Reac/ybnCoolant Pump seals. scale, the uncompensated The minimum pressurizer which occurred level at the i 15-minute point into the transient.
/
/ '- //, n, Written by: D. D. Whitney I
! 1/11/79 Date l
l .
+
?
l i.
k 1
4 a
.Q L - - - - - - - - , - - - - -
7 _
m_ e - wr v i m "
. i 8 '
i AP.28 ENCI.0SUPi 2 I
Review and Approval Sheet O
V 1
Post Trip Transient Report No. 3&
~~CAUSE~~

~~1. Technician inadvertently shorting an ICS power supply caused the trip.~~
~~2. I.oss of ICS feedwater control reduced feedwater flow, allowing RCS pressure i to increase to RPS.Hi Pressure trip limit.~~
l
( 3. Continued operation of feedwater pumps with block valves "0 PEN" cooled
~~RCS anough to reduce RCS pressure to SFAS actuation level.~~
L j 4. SFAS actuation without " blue light" indication allowed filling of one OTSG
, with Auxiliary Feedwater and caused excessive cooldown rate.
i CORRECTIVE ACTION:
1. T'a e present arrange =ent requiring. the Auxiliary F=eowater valves to be opened automatically on Safety Features initiation, needs to be reviewed. Numerous occurrences similar to the above have been caused by the automatic operation of this system and of these valvasi Serious consideration should be given to blocking the Safety Features actuation of these valves.
~~2. Operations, together with I&C and Electrical Maintenance. should revi'ew the controlling systems and cabinets to look for circuit breakers, fuses, links, '~~
etc. which as a result of calibrations and/or main:enance can be inadvertently l 1ef t open, remain unalarmed, and therefore be recored from function or reset capability from the subject equipment. Such poinu once identifie*d should f be added to the check lists and lineups necessary for normal operation of j these systems.
i
3. In transients such as this, which involve excessiw RCS cooling and/or losses of RCS pressure, the operators should be cautioned that only pressurizer level is to be' maintained and not to. attempt to maintain RCS pressure to normal values by use of High Pressure Injection. Dual High Pressure
Injection capability alone provides cooling in excess of the Decay Heat generation rate and is, therefore, a significant factor in reJueing the very pressure l which is trying to be increased. The important par.e eter is to keep water in the pressurizar and thereby prevent shif ting of the Subble. This can be done
, at lower pressures which are mandated by the datur. 'On pressure determinod 1
by the RCS water which enters the prossurizer.
~~SUBSEQUENT HAPPENINGS:~~
~~Immadiately following this trip, and subsoquent recovery of system parameters J S,~~
, to nominal hot shutdo'.a values, a review of the data cont'irned that while the O s
-- ----------------------------------------------b
~
9.; ,
Pcg2 2 of 2 a
i d Enclosure 2 (Continued) Review and Approval Sheet -
Post Trip Transient d36 SUBSEQUENT HAPPENINGS: (Continued) pressure / temperature requirecents regarding heacup and cooldown of the RCS in the Technical Specifications had not been violated. The cooldown rate spect-fication of 100*F/hr. had been exceeded. -
Detailed data regarding the performance of the plant during the transient was transmitted to B&h*, which established a task force of qualified engineering personnel to review the data and rule on the adequacy of items relative to returning the plant to operation. At 1843 hours0.0213 days <br />0.512 hours <br />0.00305 weeks <br />7.012615e-4 months <br /> that evening, B&W contacted f"
t us with the information that they determined the maximum cooldown rate as being that portion below 530'y accomplished within any one-hour period.
Therefore, the cooldown rate for this transient was established at 120*y/hr.
)
Using this information and the detailed parameters provided, they determined that the plant could be safely returned to power and operated as long as the transient was reported to the NRC under conditions of the license. The transient had been identified to the NRC inspectors who were on site
? that afternoon and the usual 14-day formal reporting requirements would suffice.
As a side line to this transient, an NRC inspector on site at the time of the
- transient, had discovered several Decay deat hangers which had been rendered out-of-service due to a water hammer during the recent refueling. Prior to returning the reactor to critical, it was necessary to ef fect the repairs to these hangers. That was done, and the Meactor taken critical approximately 13 j
~~hours subsequent,co the transient.~~
1 Prepared By '/ _* _ /, ' fe__ /-/Y- 7f
. 'Technicai Support Date i Reviewed By ~% b a /~})~
l Plant Review Committee ., Date
. l Approved By i
1. A., .!- / *."#*
PIsht Superintendent
~
Date i . .
I. .
j .
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. '*s
' Q, e
0

ML20155H654

Text

SUMMARY

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