ML19290E944

Emergency Operating Procedures Relevant to SEP Topic III-12, Environ Qualification of Safety-Related Equipment

ML19290E944
Person / Time
Site:	Haddam Neck, Millstone  File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	03/31/1980
From:	NORTHEAST UTILITIES
To:
Shared Package
ML19290E933	List: ML19290E932 ML19290E936 ML19290E944
References
TASK-03-12, TASK-3-12, TASK-RR PROC-800331, NUDOCS 8003170358
Download: ML19290E944 (49)

Text

.'

DOCKET NO. 50-245 ATIACliMENT 2 MILLSICIiE IiUCLEAR POWER STATION, U!iIT NO.1 SEP 10PIC III-12 EINIRO MENTAL QUALIFICATI0:I 0F SAFETY-RELATED EQUIPMENT MARCH, 1980 G0031703 8(

MILLS"'ONE NUCLEAR POWER STATION, UNIT !!0. 1 OPERATING PROCEDURES OP 502-B.

. H48GENCY PLANT SHUTDOWN OP 506......... LOSS OF COOLANT OP 516A

. LOSS OF FEEDWATE OP 516B

. NUCLEAR STEAM SYSTE4 RUPWRE OP 516c

. CONTROL RCD DRTIE HYDRAULIC SYSTE4 RUPTURE OP 516D ISOLATION CONDENSE SYSTH4 RUPTURE OP 516E

. REACTOR CLEAN-UP SYSTE4 RUPTURE OP 516F

. LOSS OF FEEDWATE WHEN 0 PIRATING AT < 40% POWER WITH THE ISOLATION CONDENSER OUT OF SEVICE

• ~-

31 -

n 1.upertn cncent

/- -

STATION PP.0CEDUP.E CHAiGE FOPA e.

• IDEllTIFICATIOri j

~.

Procedure Number _

OP 502B Rev.

O Chatige llo.

Procedure Title EMERGENCY PLANT SHUTDOWN i

" Initiated By__

w.D. ROMBERG Date JAriUARY 9, 1980 1

B.

CHAflGE

~

. STEP 5.4 bodfTOR REILCTOR. PRESSURE AND LdVEL "D EVEL TO,

[-

EXCEED ' + 5 0. BY. N. R.

YARWAY

('ISOL'ATION CONDENSER'. WATER 8A j-

. CO,NSIDERATIONS).

^

C'.'

REA50il FOR CHAf!GE

. '. 'v.

TO PhEVENT -WATER HAM'4ER OF THE 'ISOL'ATION CONI)ENSER P PI

's.

.DUE TO FLOdDING, 'OF THE HOT 'fSOLATION CONDENSER.S'!Ehr LIlid.

i..

' i '. D.

!!Of!-IrlTEili CHAtlGE AUTHORIZATIO!! (flA. for Intent Changes) in j

TITLE SJGilATURE

~DATE iv/

l*

chi f t 'Sunervisor(on duty) m e,,2 -,

/[' F

\\.

' %,u,w-., GLt %6 klah>-. L

.i/N4 i

d j

~ ~

e nt Head N#

1:

y le

..Unreviewed Safety Question Evaluation Ddcumentation Reauired:

}

(Significant change in procecure method or scope 4

as described in FSAR)

[ ] YES

.[

!!0 !p (If yes, document in PORC/50RC meeting minutei)

..a.'.

EllVIRO !MEtlTAL 'Il! PACT (Adv.erse environmental impact)

-[ ] YES

[

!!O

.(If yes, document in 'PORC/50:1C meeting minutes)

.l l.

PORC/50RC RECOMMEilDS APPROVAL (or confirmation of ' interim change within T4 PORC/SORC Meeting Number

?# ' #

~-

~

.Q.'AP"f.0VALANDItIPLEliFilTATICE lhe change is hereb', implemented and is effective this date, except for in

~

changes which were implec.ented and effective per the Authorization of D ab f~'y d A& S ne np Plant Superintendent.@ Superintendent S F-s Date

Plant Superintencent STAT 10:1 PRCCEDURE C7!ER Si!EET J t.

Q IDEt:TIFICATIO:1 tiumber OP 50?B

Rey, O

I l

Ti tle EMERGEllCY PLA?;T <HUTDOWN i

)

Prepared By G. Zitka l

B.

REVIE'l I have reviewed the above precedure and have found it to be satisfactory.

{

TITLE SIG:!ATURE DA'i E l

DEPART!;EtT HEAD-p) d /-

M22-77

% YdY

/kSV7Y S (? O

/

/

/

A,/Wln 9 c, n

/2.v'L f

C.

U: REVIE'<!ED SAFETY QUESTIC.' EVALUATIO:! DOCU:.Ei;TATIC 1 REGUIRED:

{

(Significant chance in precedure method or scope as described in FSAR)

YES [ ]

NO [T

}

g (If yes, dccument in PORC/SORC meeting minutes) l EtVIRO:WE?!TAL IMPACT (Adverse environcental impact)

YES [ ]

NO [g (If yes, document in PORC/SORC meeting minutes)

D.

PORC/SORC AFPROVAL PORC/EM Meeting fiumber 7 f-3 /

1 E.

APPROVAL Ar:0 IM?LEME::TATIO:

I l

The attached procedure is hereby approved, and effective on the da tes below-

}

/. nl tl

'/b//7 9

'#IV/79

_ Plant Superintendcnt/ Unit Superintencant Approved Da te Effective Dele S F-301 l

h Rev. 2 i

• s OP 502B Page 1 t

Rev. O Date: 4/14/79 O

EMERGEf'CY PLArlT SHUTDOWil PAGE ti0.

EFFECTIVE REVISIO!i DATF 1

0 4/14/79 2

0 4/14/79 3

0 4/14/79 4

0 4/14/79 I

1 1

a i

a e

O t

4 r

l I

?

I i

1 t

I O

OP 5023 Page 2 Rev.0 Date: 4/14/79 O

OBJECTIVE 1

To provide a procedure for oporator action to be followed upon a I

reactor shutdown due to automatic action of the reactor protection l

system, spurious operation of the Reactor Protection System, or manual action by the Operator.

l 2.

DISCUSSION j

The reactor is protected from the various accidents that can occur f

through the use of the Automatic Scram and the select rod insert.

t It is beyond the scope of this procedure to list all possible f

emergencies.

The operator has the overall responsibility for reactor safety, and for this reason a reactor full scram may be 1

manually initiated at any time the operator deems it necessary for 1

Reactor Protection.

I 1

I If at any time a reacter safety system limitation setpoint is j

g exceeded and the reactor protection system does not initiate an automa.lic full scram, manually scram the reactor by depressing the i

l two scram buttons in the center of reactor CRP 905.

l 1

l The Plant conditions that can automatically initiate a Reactor Scram are as follows:

l Condition Scram Set Point 2.1 Reactor High Pressure Initiated at < 1085 psig 2.2 Low Vessel Level Initiate at > +8" Yarway 2.3 liigh Neutron Flux S =.65W + 55 S = 15% (mode switch not in Run).

3 I

2.4 Main Stea.n Line High-High 7 Times normal Main Steam-I Radiation line Background Radiation 1

2[5 Primary Containment

< 2 psig

{

i High Press 1

O I

1

e OP 502B Page 3 Rev. O Date: 4/14/79 i

h i

Condition Scram Set Point i

2.6 Condenser Low Vacuum

> 23" Ha 2.7 Scram Discharge Volume

< 39 gallons High Level 2.8 Turbine Bypass Steam Bypass valves fail to open Failure on Generator within 260 milliseconds on i

Load Rejection Generator load rejection 2.9 Main Steam Line 3 of 4 MSIV's <10" closed l

1 solation Velve Closure i

l 2.10 Turbine Stop Valve 3 of 4 TSV's 3 10% closed Closure at High Power l

Level 2.11 Manual Scram When the operator deems necessary 2.12 IRM liigh Flux

-< 120/125 of full scale and 15% of Rated Power 3.

SYMPTOMS h

NOTE:

All the following symptoms will be present on any Reactor Emergency Shutdown.

l 3.1 Scram Channel A and Channel B annunciator lights illuminated on annunciator Panel A2 on CRP 905.

8 3.2 Orange accumulator, white scram, and red drift lights illuminated l

on the core display panel.

A White Scram Signal Identification light and 2 red (Scram Channel A/B Scram) annunciator lights f

on annunciator A2 CRP 905.

i 3.3 Reactor power decreasing as indicated by the APRM/IRM recorders located on CRP 905.

i 3.4 Rapidly decreasing generator load as indicated by Generator i

Power Meter on CRP 907.

I 4.

AUTOMATIC ACTIO"S i

4.1 The reactor will scram.

l 0 i

i

s OP 502B Page 4 Rev. O Date:4/14/79 1

5.

IMMEDIATE OPERATOR ACTIONS 5.1 Verify the Reactor has scrammed and reactor power decreasing on the APR!i/IRM Recorders located on CRP 905.

i 5.2 Transfer tSe Reactor Mode Switch to the REFUEL position when l

it is determined the pressure regulating system is operating properly, to prevent 380 psi isolation. The purpose of the 3

{

880 psi isolation is to prevent inventory loss and uncovering the fuel in the case of a pressure regulator malfunction.

5.3 Trip the turbine.

I W.

5.4 Monitor reactor pressure and level, j j g.

i 5.5 Insure that 4160V buses have transferred to the RSS trans-1' formers.

5.6 Manually run recirc. pumps back to minimum speed.

4 i

6.

SUBSEQUENT ACTIONS 6.1 Determine the cause of the scram and clear the scram condition.

Bypass the scram dump tank, reset both RPS buses and reset all annunciators. Normal cooling flow should now be established l

to all rods, and scram accumulators should recharge.

If CU system isolated, clear isolation signals, reset logic and return to service for vessel level control.

t NOTE:

Demand 007 Option 2, new Control Rod Position; if computer is available to identify any rods that did I

I not fully insert.

6.2 Verify that the turbine auxiliary lube oil pump has started.

l 6.3 Insert IRM's maintaining readings between 25-75% on each range I

while following reactor power down.

t 2

6.4 Insert SRM's maintaining readings between 10 - 10 CPS while following reactor power down.

6.5 Notify the Unit Superintendent or his designee of the existing f

conditions.

l 6.6 If the condition causing the scram cannot be eliminated without cooling the plant down, proceed with plant cooldown in accordance with the appropriate general plant operating procedure.

i GZ:amc

l

.S._T_A.T.10;! iTO_.X...UU..M.i.._ _C.O. V.f..R. 5._!.!.!:1,T,.

,s. l n ;

1 I

i

.ls c.

~ _ -.,

I '),

g i j,. m

- D..'..:nT U'l CATION Lll l

',I '

IJ l

!) 1 t

g f,.h, 6j 1l 0'u!'M' ',

t Ihrobe.-.

OP 506 I!b._

0 Ti tl e.

los s o f Cool a_n,.t Prepitred By, _

r % r., y 1

_. s -

p, REVIEU

~

I have reviewed 1.hc above. procedure and have -Tound it to be so TITI.E SIC;!ATURE

• DA'TE DEPARTiia!T llEAD p

n m3 1

/

C..

UsiRE.VID!CD SAFETY OUESTJ0ii EVAi.UATIC'! DOCU;Ei! TAT 10N RED'lIRED:

u 2

h (as described in FSAR) procedure 1;icthod or sco~pa Signi f'icant change in f

(1f 'yes, docuraent in PORC/SOHC meeting. tainutes).YES [-]

110. [vj

~

.El.l.V. ) R.0..;.;.I ;..E.!.!T.A L_..I.i:PA.CT,.

~

(Adverse environmentai impact)

(If yes, document in PDHC/SORC meeting rainutes)

YES'[ ]

,110 [ ' '

D.

'.PORC_/_SORC APPRO_ VAL PORC/SORC liacting flumber 7.9-/A 9 ~

.~

E.

. APP._ROVI: fe;D ylipi.Et;,.;; tar 10l; The cLlached procedure is hereby approved, and effective on the dates balor

-J.:d0*':

Sup._ w_erintendent./Uait Supen g.i. ;)/./.../_..f. ".

3,3 Un t-

/M]

/.i ntendent Approved Dale Effect.ive DaLc s

.i h

[

l

-31.10~1 nuv. M !

[-

,.' '..'[ ( i. k.

T.t:

btD' 'l '}

..;,.a.

0:

.i

',i

.,.. r i n

..it

• r g

e I :// 4 f J.N

{T #3 1 -

.N m

1 0). !,0 T

l;!

.) Uf m) % J jj j

j j

1. : * - i c,:j c

y

....e 3

f.<;eg i

f.

c i'rcc 'tra fi:le

/c,.

. / (

c

./

[.).

/.-

., a n,<..s.., c.;,,. 7 n,. ' a l..7 r,

t

./ _

/. s 3.

I J

i

/

/,

/

1 n,,.

q,,

(!..

. /.<..(..

.a

..i k

(.,,...,.

s. c.,

.2.

e i <

i.

.,,, (,, ', -

/:.[;.,f,,1 < d u.> r. J lc -

l'

/-

_t

! '.. i ij'.'[ (U,1.S.. I n t e n t < '

.; s) 0.

' /: if..

f.

'. {

.e m i iI Ylf.

$l','l'Tl'P.E.

e. ( )*

t jw

-)

/,

I p

.),

.;. /

/

5 s

l9i

.t i

.c...

./,/

f, i

c i

'.:0 s

' ' -...,G

.i!:ir vi c.c..; c fe :.y Qu 2s tic >a Evaluation ::utn ta tion Rccuired:

a

, ii fir a t cis: u in,: o'an.re r:u thed sr sce.;:e r, '

, -' ' a. i '..i : n. - 1)

[ ] YF.S

[]l0

.fi s,

f.

ia,,er, g,:,c,

. t ;;; ;, i,, _.; )

.ti.

..,,... i. ;.

7.. 3 3. f

.r

~

rec tic:. '. n t al ii, c e. t )

[ ] YES

[ ] :;0

,'?.

3, I w.:.u. - ia,

' /" ' 7.C n a ti.lg i:.'It M)

F.

-js

.iv ~ ' '. 3

t. f,3c cci.;r.-L;+: of i d uci a c' c, ' cii:.:,';

'- f

.m e

g e

'I

,y e,

. i s

j

,.l.

' i > ri 1,

. i f.,

j f.,

i,l.

d 1:!<:'~

'j,

) r ' '.,j

,- j, ;i t : ;

,[ 3

./

Tr!t I

5t

• l[

e r

l'e f g4

• l

!~

l *, ',

OP 506 Page 1

{

Rev. 0 Date:

1/1/80 i

e i

l I

I Loss of Coolant j

Page No.

Effective Revision flo.

Date i

1 0

1/1/80 2

0 1/1/80 j

3 0

1/1/80 j

4 0

1/1/80 f

5 0

1/1/80 6

0 1/1/80 7

0 1/1/80 8

0 1/1/80

O i

l i

l l

t 1

I

l OP 506 Page 2 Rev. O Date: 1/1/80 j h 1.

PURPOSE To outline the four basic objectives the operator is to achieve in the event of a pipe break, with respect to the core and containment, i

which are:

a)

Maintain core cooling to prevent excessive cladding heat-up and oxidation.

b)

Limit the release of off-site radiation by maintaining the integrity of the primary and secondary containments.

c)

Place the reactor in a safe, stable condition.

d)

Keep the torus water bulk temperature below 120 F to prevent excessive loads to the pool boundary and structures during safety / relief valve discharges, and maintain peak allowable i

temperatures within cooling equipment and containment structure design limits and to provide amplifying guidance to the operator on the operation of systems designed to mitigate a loss of coolant condition.

O 2.

DISCUSSI0fl 2.1 The Emergency Core Cooling Systems (ECCS) are desicned to provide adequate core cooling over the complete spectrum of possible break sizes in the nuclear system process barriers including a circumferential rupture of the largest pipe connected to the vessel.

l Dering a loss of coolant accident condition, the reector is automatically shutdown by a low vessel water level or a high drywell pressure.

Losses of coolant not large enough to cause these actions are considered leaks and are not covered by this 1

procedure.

Technical Specifications require a reactor shutdown if (a) a total leakage exceeds 25 gpm or (b) unidentified leakage exceeds 2.5 gpm.

I i

O i

}

I.'

OP 506 Page 3 s-Rev. O Date: 1/1/80 h

The first action necessary during a loss of coolant accident is to diagnuse, from the symptoms available, the location of the break.

Initially, this diagnosis must determine whether the break is l

inside or outside the primary containment.

3 A break inside the primary containment will be indicated by a high j

drywell pressure scram accompanied by the resultant isolations and j

ECCS equipment starts.

I 1

A break outside the primary containment is keyed by a group isolation

-1 with no_ concurrent high drywell pressure indication.

In the case of a break outside the containment go to OP 516.

With a high drywell pressure condition, the emergency diesel and l

gas turbine will receive auto start signals and provide power to FWCI and ECCS equipment in the case of a loss of off-site power.

t l

} h 2.2 Cautions 2.2.1 Operators should be prepared to take immediate actions as necessary to protect the core and contain-i ment.

Immediate operator actions include verification of automatic actions and taking manual action to I

initiate an automatic function whenever an automatic j

action did not occur that should have occurred.

j 2.2.2 Continuously monitor vessel level and pressure from j

multiple indications.

2.2.3 On any automatic initiation of a safety function,

}

t assume a true initiating event has occurred, until otherwise confirmed by two or more independent process indications.

1 I

l i

i!e i

i l

1 l

I'-

OP 506 Page 4 l.,

Rev. O Date:

1/1/80 l

l@

2.2.4 Automatic controls should not be placed in " manual" mode, unless (1) misoperation in " automatic" mode is confirmed by at least two independent prccess parameter indications, or (2) core cooling is assured, and i

these guidelines state specifically to do otherwise.

When manual operation is no longer needed, restore the system to " automatic / standby" mode, if possible.

2.2.5 Any emergency core cooling system should not be shut off unless there are multiple confirming process parameter indications (such as level indications from several instruments) that the core aid contain-ment are in a safe, stable condition.

I 2.2.6 If any system is switched from " automatic" to " manual" mode, then frequent checks of the controlled parameter must be made.

2.2.7 The indicated water level, where provide 6 by Yarway l

Instrumentation utilizing reference legs in the lg drywell, is dependent upon drywell temperature.

j Very large increases in drywell temperatire (an 1

4 increase from 135 F to 340 F could result in a level l

inaccuracy (as much as 14 inches on narr:u range instruments and 37 inches on wide range finstruments).

In each case, the actual level is lower than indicated.

1 i

During rapid reactor depressurization (vith APR j

operation for example) and particularly 3elow 500 psig, j

the operator should utilize the cold ref2rence leg i

type of level indicators to give back-up information on vessel water level.

The operator sho11d not turn I

off any ECCS equipment unless there is sifficient J

confirming information from cold referente leg level instruments that vessel water level has.1een restored.

1 4

l0 i

i i

i i

l OP 506 Page 5 1

l*

Rev. O Date: 1/1/80 t

i The operator.should not rely on the Yanvays if erratic behavior, indicative of reference leg flashing, has occurred until the Yaniay readings are on scale and in reasonable agreement with other (cold reference i

leg) types of level instruments.

I The operator should verify that automatic ECCS actuations occur when the levels are at the trip points.

The operator should be prepared to manually actuate ECCS during a suspected LOCA if automatic actuation is not achieved.

3.

SYMPT 0MS I

3.1 Increasing drywell pressure as indicated by pressure recorder and gage on CRP 903 and increase in drywell temperature as f

indicated by temperature recorder on CRP 925.

l 3.2 Decreasing reactor water level as indicated by level recorder (Q

and Yanvay on CRP 905.

1 3.3 Increasing feedwater flow as indicated by flow recorder on CRP 905.

3.4 Decreasing reactor pressure as indicated by pressure recorder 1

on CRP 905.

i 3.5 High drywell pressure alarm and reactor scram on high drywell

)

pressure initiating Group II isolation and start of the standby gas treatment system.

J 3.6 Low reactor water level alarm and scram initiating Group II 1

isolation and start of the standby gas treatment system.

.]

3.7 Reserve station service transformer voltage and power "0" as I

indicated by meters on CRP 903.

3.8 Reserve station service transformer trouble alarm on annunciator 54B CRP 903.

I i

i

O i

i i

6

a OP 506 Page 6 1,

Rev. O Date: 1/1/g0 j

h 4.

AUTOMATIC ACT10js 4.1 The reactor scrams due to low water level or high drywell pressure.

l 4.2 The diesel generator starts (output breaker will close within i

13 seconds if accidents are coincident with an LNP).

l 4.3 The gas turbine generator starts (output breaker closes within j

48 seconds).

I 4.4 Feedwater coolant injection initiates (if the accident is coincident with an LtlP, the FWCI string will initiate after 4160 volt buses 14A and 14C are energized by the GT).

l 4.5 ECCS system pumps start (power must be restored from the j

diesel and gas turbine generators if the accident is coincident withanLilP).

4.6 Initiation of ECCS systems when reactor pressure decreases to 1350 psi (power must be restored from the diesel a:.d gas f

turbine generators if the accident is coincident with an Lf4P).

4.6.1 Core spray initiates 4.6.2 LPCI initiates j

5.

IletEDIATE OPERATOR ACTI0'lS J

5.1 Verify reactor scram has occurred by observing scram Channel A and B annunciator lights illuminate, all control rods fully inserted, and reactor power decreasing on APRI1/IRM recorders on CRP 905.

5.2 g

Trip the turbine by depressing the two turbine trip buttons on i

CRP 907 simultaneously and ensure that house loads transfers l

to the reserve station service transformer.

If the accident is coincident with an Lf4P, ensure that the diesel generator assumes load on Bus 14F within 13 seconds.

The gas turbine generator assumes load on 14A,14C, and 14E within 48 seconds of the LftP.

5.3 Verify the following systems are in operation.

5.3.1 Low pressure coolant injection O

i e

, e V$J 9% Q

~

)T >)

D D

J 'n J m.FLa b.a H

~

'l

)

i

• .. s.

ii., i

.i G ',.,

1 c.

t, i-S. 3. 5 P.s 1 ;i ' t r' e r. <.-

.or

.6 f l ' f. [ tf

- Te: r' [.1:5.p

r.... /

st '?./

..ith !he c'

.t ol

.l l

'l i Li d

1:

,9 il i '. ;

1

's.

c, i

5...1 i

.P 5.4.2 l'

c. ' "/> V. e.

s, (2F.'05 i.'

S.'.3

'.' i '2 4.

,o RCS Y.

ys, O.P '.03 M 4

: de

,s.;i 110 >.j ;., ' Jac, CRP 0);

. iy v.

rati : vf th e -

r.

4

-ic pr.2ssur..elic?

-.c 7

.)

ei ?

.1

i.;il '.,. ?l l

.r'

./

.1 i

.i 1

i,.

s p

i. O4

)

,s.

i

.n, cc all.

. e i., r,.. -.s or 1 ;o

.o

. i c t.,.c

. 'i l,

n

)

i ';. '

'cr :

'.0 i

l <' /

. ! L,'..I

..n l

. c.j

.u.T'.

r,

,g (t p.i ce'.n t to a s..-inch dia :0'er ; >

)

n

r ronju.ction vii th F. 01 failure, it is c

'i.e th c c. ara tc r unually i.litiates all three (3)

.T s a f, F. i1aj s uuuC.0 i n. s C c prs:,5Ul 0 LO *4055. Ji

>cs)

J lo.a ti s fy LFCI ir.1 '. ore spray ci,tist;.n

> s Ic.i

' r. c ; i 0

,ic.

- h I.1 ( i ~ t f s -

I/

n -)i il i

• ).

.I).

l A g Jl/

6

i GZ

(

'I 3

6.1 r-

. E

'2

_ i. c

~

f I

}

l

,3f'

l Il.ill?

j

.i.

. I.",l

. '.2 4,., 1., ) >. f ? sII.

' i '.

• i3 i 'l

t. /

OP 506 Page 8 Rev. O Date: 1/1/80 l h This will be prevented by ensuring that only one feedwater pump (that is, the selected FWCI string) is running.

The SRV's have the water flow capacity of one feedwater string.

6.2 Place the emergency service water system in operation in i

accordance with Operating Procedure 322, Emergency Service t

l Water System, when suppression chamber temperature approaches 90 F and plant load conditions permit.

6.3 Notify the unit superintendent or his designee of the existing l

plant conditions.

l 6.4 LPCI flow should be limited to 5,500 gpm per pump during the f

injection phase into the vessel to prevent pump run out, if necessary throttle the 1-LP-9A(B) valve to reduce flow to this

'j limit.

l 6.5 A'ttempt to maintain reactor level in the normal range (20-40")

j by throttling or cycling ECCS pumps as needed.

If the level I

instruments are in doubt, fill to and overflow via the open APR's l

with the low pressure ECCS pumps.

jO NOTE:

Prior to shuttin9 down any ECCS pumps, it is imperative that operators monitor all available water level 4

I instruments to ensure adequate vessel level.

If l

level indicators disagree, operate by the lower reading indicators until instrument accuracy is I

determined.

f i

6.6 Flooding of the entire containment vessel to a water level f

above the reactor core is the ultimate assurance that core

{

cooling can be maintained, if this becomes necessary.

A cross 1

tie between emergency service water and condensate storage l

i tank supply to ECCS pumps can be affected.

a

)

il 1

' O 1

' api'nu ou.. L.

Plant Superintendent 1

l-(I STATIO:1 PP.0CEDURE COVEP. SilEET

,A 10EfiTIFICATIO!!

thnaber OP 516A Rev.

3 1

Title Loss or renm:ATra Prepared By _

R.

KRAE!!ER B.

REVIEW I have revic,ied the above procedure and have found it to be satisfactory.

1 DATE TITLE SIGt1ATURE DEPARTIE!!T llEAD

/s) 49

/t, ff, y y q

C.

U:lREVIEWEIS?.FETY Q'JESTIC i EVALUAT10tl DGCL"'EtiTATIO?! REC'JIRE_ll:

l

( ' (Significant change in procedure nothod or scopa j

as described in FSAR)

YES [ ]

il0 [ ']

(If yes, document in PORC/S0?.C meeting minutes)

]

EttVIP,0:!:'E s'TAL !!'?ACT 1

(Adverse environmental ir. pact)

YES [ ]

!!0 ((

A 4

(If yes, document in PORC/50RC meeting minutes) i O.

PORC/50RC APPROVAL PORC/SORC i.:ecting fiumber 79-O 9 E.

APPROVAL A!!D Il-:PLEi'E:iTAT!0:1 l

The attached procedure is hereby approved, and effective on the dates below:

i I

//

f

.N/2/!U

/'

? _.__

Plant Superintendent / Unit Superintencent Approved Date Effective Date h..

SF-301 I

Rev. ?

l

I OP 515A Page 1 Rev. 3 Date:

1/1/80 i

I k!h Loss of Feedwater Page No.

Effective Revision No.

Date 1

3 1/1/80 2

3 1/1/80 l

3 3

1/1/80 4

3 1/1/80 5

3 1/1/80 6

3 1/1/80 i

I I

l j

i (l) 1 1

OP 516A Page 2 i

Rev. 3 Date:

1/1/80 i

l $

1.

OBJECTIVE 1

1.1 To provide the operator with an aid to be used to bring the i

reactor to a safe shutdown condition following a loss of i

feedwater transient possibly coincident with additional equip-Ij ment failure compounding the transient.

2.

DISCUSSI0ft 1

2.1 A loss of feedwater transient, whil. in itself not a particularly l

severe condition, can be considerably compounded by failure of additional equipment and/or piping.

The spectrum of combined failure conditions is broad.

This procedure along with the j

attached fault tree analysis (Attachment A) is intended to be utilized by the operator as an aid in determining what steps i

l to take to protect the reactor core should any of these condi-l tions arise.

3.

SYttPTOMS j $

Any one or all of the following may be indication of a loss of J

feedwater condition.

3.1 Indicated feedwater flow decrease on CRP 906.

3.2 Reactor water level decreasing as indicated by reactor water E

level indication on CRP 905.

3.3 Reactor scram, Group II and III isolation on low reactor water level as indicated by alarms on CRP 905.

3.4 Receipt of Group I Isolation from reactor low-low water level t

Alarm CRP 905.

3.5 Reactor feed pump or condensate booster trip on low suction j

pressure.

i 3.6 Low hotwell level and/or condensate pump trip.

3.7 Condensate and condensate booster pump low discharge pressure I

alarms (CRP 906).

3.8 Excessive condensate demineralizer D/P and/or condensate domin i

c trouble alarm observed on CRP 906.

I!O I

1 1

4 l

OP 516A Page 3 l

Rev. 3 Date:

1/1/80

$ 4.

AUTOMATIC ACTI0il 4.1 Condensate booster pump trip on suction pressure less than 20 psi.

4.2 Reactor feedwater pumps trip on suction pressure less than 1

335 psi.

4.3 Main condensate pumps trip on low condenser Hotwell level of 12".

4.4 Reactor scram, Group II and III Isolation at reactor water level of +8" on CRP 905 yarway indication.

4.5 Reactor Group I Isolation, auto sta. ' of L.P.C.I., core spray pumps, emergency diesel and gas turbine generators on low-low reactor water level +79" above fuel.

5.

IMMEDIATE OPERATOR ACTIO:t 5.1 If feedwater flow to reactor has not been totally lost, reduce reactor power to within capacity of the feed and condensate systems.

5.2 Attempt to regain total feedwater system flow.

5.3 If loss of feedwater flow to reactor : 3 total or if reduction in flow is due to an unisolable pipe leak, complete the following actions:

5.3.1 Manually scram the reactor.

5.3.2 Trip the turbine.

5. 3. 3 Isolate steam flow from the reactor by shutting M.S.I.V.'s.

5.3.4 Control reactor pressure by use of isolation condenser as needed.

5.4 If af ter performing Step 5.3 above reactor vessel level is decreasing, assume a coincidental equipment / piping failure exists, refer to Attachment A of this procedure and other individual applicable emergency procedures for further guidance.

' O I

..--.4..

--eu.e--=

e-e e - e-

OP SlCA Page 4 Rev. 3 Date:

1/1/80 h 6.

SUBSEQUEllT ACTIONS l

6.1 Carry out applicable steps of the immediate, and all subsequent actions of Emergency Procedure 502, Emergency Shutdown.

6.2 If li.S.I.V.'s are shat, break condenser vacuum to prevent damage to the turbine shaft from cold air being drawn through the turbine shaft seals.

7.

FIGURES 7.1 Attachment A i

k l

l 1

1 I

l RK:cp

[

LOSS OF PEEDNI.TER

~

@fD)$ N hd-g i

i I

(

in..;is W u uo w -

..n

' RPV LEVEL DECREASE

' V EC' LOW LEVEL ALARM -

- f/ 1 h

/ VERIFY : SCRA::, SBGTS, t:0 i

LOW WATER LEVEL

\\GRP II,III ISOLATION 1

I YES NO

~

LO,LO WATER LEVEL t

./ MANUAL ISO. CO::D. INIT.

1

' \\ TO CONTEOL PRESS.

NO LYES v

1 y 'g LEVEL INCREASI :G

. VERIFY F.W.C.I.

l

' AUTO INITIATIO:

3-No Q"- )

e MANUAL F.W.C.I.

INITIATION

'l VERIFY / MANUAL RECIRC. PP\\ NO NO 4YES h ',

TRIP GRP.I ISOLATION YES LEVEL INCF27.S!NG P

YES

,INO v

lvrg LEVEL INCREASING NOl XANUAL G.T. \\ go 1

LOSS OF l'2 4

g.

START f

I

(

OFFSITE POWER hO YES

),YES

!.NO YE&

v ERIFY G.T.

gg AUTO START

.W l

VERIFY CRD ON "S -- \\

STA2T hO M UAL D.G.

A 4

lYES NO 3

ERIFY D.G.

i v

AUTO START j

u fESSEL LEVEL DECREASINQ:

~

h,4 4.w

'V NO y.ANUAL POLIEF VALVE!

RELIEF VI,LVE g

AUTO OPEN

', ACTL'ATION f 3 VALVES)i NOTE 5

OR RELIEF VALVE YE

• i i

PRESSURE DECREASINS4-1 j

STUCK OPEM NO DEPRESSURI::E TO CS, ygg 7

LPC7 ? -' ? ". I S S T v?g CORE CQOLI::3 ESTABLISHi:D fVERIFY C.S. \\ NO C.S. MA::JAL\\NO 4

{

' \\ AUTO. INIT. j START

/

3t,333gg73;;7 ES A YES 1

v 3PERATOR,AcTIeNS i

1EACTO:i C00LCO'.::

l

,_/ VERIFY LPCI \\ NO./LPCI MA:.UAL\\ '!O '

In p30caggs m

' \\ AUTO. INIT. /

'N STARi' /

4 DS YES j

' 4 9

COLD ShuTDO'.1 1,. 4 -

l l

g', g LEVEL INC3EASI:G

}

PRESSURE OT'C:'. EASING YCN

-l

OP 516A Page 6 Rev. 3 Date:

1/1/80 h

t10TES TO ATTACHMEf1T A 1

ii 1.

Take prompt operator (or maintenance) action as severity of failure or transient warrants; priority of safety actuations must be consid-ered in restoring failed equipment.

Do not underman control room.

I Utilize approved plant operating, maintenance and emergency proce-dures.

2.

If gas turbine fails to start during L.fl.P. condition, the F.W.C.I.

system is inoperable.

Water must be added to vessel using L.P.C.I.

I and/or core spray pumps energized from diesel generator after reduction in reactor pressure.

l l

3.

Additional sources of high pressure water include standby C.R.D.

pump, standby liquid control (from test tank only).

I 4.

Additional. sources of low pressure water include condensate and J

condensate booster pumps, condensate transfer system via makeup connections to shutdown cooling system, ECCS system keep full lines and emergency service water cross tied to ECCS pumps suction header l

from the condensate storage tank.

5.

When performing manual initiation of reactor vessel blowdown with air actuated pressure relief valves, use three (3) valves.

l'lan t dup; rmtennuni D

]9 3 L Vl0U uJ$/) k g.

.S..T...A.T.103 PROCEliUML CO::TR S!!n.T l A.

.I_n._.:U._T 1 f l CAT I ON._.

e j

!!u:nhar OP 516B.

~

e2

[:ey, Ti tl c. -

Jutlcar_ S. team._ Sys tem _ Rupture

/

Prepared liy-E. Berry'.

i }:.

REVI'rli j

-I have reviewed the above procedure and have -found it to be sa.hisfactory

}

TITI.li.

SICMT.TURE

.DNTE_.

DEPART;EIT !! EAU

' p g V-h hy, y -

l 1

O.

3

=-

3

-~

1 i

C..

.UNR_E_V__ID.. E. D SAFETY OUESTION EVAltlATION 110CUl;EliTAT10N REGUIRED:

~

'(Signi ficant change ~ in procedure method or sco'pc

~

I, as descr-ibed in FSAR)

YES [-] - 110. ((.

1' -

(It 'yes, docuraent '-in P0HC/SOHC meetmy' ininutes).

Ell

---.V. I RO M.- ;E.C TA.L.I.M..PA CT s

(Adverse envirolimenta'i impact)

YES'[.]

110 [ '.

(If yes, document in P0"C/SORC meeting rainutes) l D.

' PORC/SORC APPR. OVAL s,

PORC/SORC Meeting Number 7 9 -/d f ~

I7

. A2 PRO.Vl.i.l. A.?;i) li;PLri;EiiT. A. TIOl;

{

The ut.tached procedure is hereby approved, and effective on the dates bel.ow:

r s

.s l

. _ [

--.. f. Q._'.

yj y }. '.

/i yd

,lant. Superintenden t/ Unit Supermtendent' Approzed Dale Eff ective tratc c.

l

{

.i W

1

?

l 3

-s}. 3 01 Huv. 2. !

t,

OP 516B Page 1 Rev. 2 Date: 1/1/80 Nuclear Steam System Rupture Page No.

Effective Revision No.

Date 1

2 1/1/8G 2

1 9/27/78 3

1 9/27/78 4

2 1/1/80 I

l j

I e

1 i

4 i

i OP 516B Page 2 Rev. 1 Date:

9/27/7B j

1.

PURPOSE The purpose of this procedure is to provide the operator with 1

necessary actions to be taken to place the plant in a safe condition in the event of a Nuclear Steam System rupture outside primary containment.

l 2.

DISCUSSION For the purpose of this procedure the Nuclear Steam System will be i

defined as from downstream of the MSIV's to the turbine.

3.

SYMPTOMS i

Any one or all of the following may be observed as indication of Nuclear Steam System rupture.

3.1 tuin steam line Channel A and/or B High Flow Annunciator CRP 905 3.2 Main steam line Channel A and/or B I

Low Pressure Annunciator CRP 905 3.3 Steam tunnel Channel A and/or B 4

High Temperature Annunciator i

CRP 905 3.4 Steam leak areas high temperature Annunciator, CRP 903.

3.5 Increasing activity indicated by ARM alarms.

4.

AUTOMATIC ACTIONS Any or all.of the following actions may occur.

1 4.1 Reactor Scram.

4.2 Group I isolation.

1 4.3 Group II isolation, i

4.4 Group III isolation.

4.5 Initiation of Isolation Condenser System.

khh 1

1

OP 516B Page 3 Rev. 1 Date: 9/27/78 0

4.6 Isolation of Reactor Building ventilation and start of Standby Gas Treatment System on a Group II or III isolation.

5.

IMMEDIATE OPERATOR ACTION 5.1 If a Nuclear Steam System rupture has occurred, and automatic action has taken place, carry out OP 502, ensure the reactor has scramed, trip the turbine, ensure t' ! main steam isolation p

valves and the main steam drain valves have shut, if not close them from CRP 903 and initiate the isolation condenser, 5.2 If the Operator has dcLermined that a Nuclear Steam System rupture has occurred and automatic action has not, manually scram the reactor, carry out OP 502, trip the turbine, close the main steam isolation valves and main steam drain, and initiate tSe isolation condenser from CRP 903.

5.3 Monitor reactor vessel level, pressure and feed water flow on h

CRP 905. Stack activity shall be closely monitored for any signs of an increase due to fission products and gases released into the Reactor or Turbine Building ventilation.

l 5.4 Control Rod Drive System flow or feed water flow will compensate for the reactor low water level.

Control vessel level by securing feed pumps as needed.

When normal vessel level is attained, place the Clean-up System in operation in accordance with OP 303 and control vessel level with use of the clean-up

drain, i

j 6.

SUBSEQUENT OPERATOR ACTION j

6.'

Monitor isolation condenser level and make-up as required.

6.2 Maintain the cooldown rates on the reactor pressure vessel l

below 100 F/hr.

Place the Shutdown Cooling System in service

]

in accordance with OP 305.

I.

i l

}

6 OP 51, B Page 4 Rev. 2 Date: 1/1/80 b

Maintain level with CRD pump flow, and Clean-up System.

6.3 4

6.4 Determine the source of the rupture by monitoring indications i

of different temperature indications located in the steam tunnel, and ARft alarms.

Dispatch personnel with radiation monitoring and respiratory protection to accessible portions of the Reactor and Turbine Buildings to locate the leakage, and try to isolate as soon as possible.

6.5 tiotify the Duty Officer and the Operations Supervisor.

6.6 If the isolation valves fail to isolate the break on either an i

automatic or manual signal, then proceed with Procedure OP 506

" Loss of Coolant".

i

)

I i

d EB:cp i

j h T p;.nt..,;.-- ~ ' -

'-"~ '

w___.

h '.,.

ur,i t. :

e - 8 " ij.,_ _ _._

Plan t. Superini.e.; den !.

i I

\\

I STAT 10:1 PRC :EDURE CO'!FR S!!EET I)

D

.D F g!.

e [a e

l EL..

h i

I o

II:!.'i:fIFIrATIOil,

')

i

!!umb.:r OP 51CC h

Rev.

1 Ti tle Control nod Drive Hydra'.lic System Rupture f

i Prepared By J. IJowell B.

P.EVIEW

~

1 I have revier:ed the above procedure and have found it to be satisfactory.

1 TITLE SIGilATURE DATE l

DEPARTt ENT liEAD g,j' g c sg,

p f 7_ yj n u.

<.f 8', /u b 9 E

5 S-f, t

I I

C.

UI;REVIE':ED SAFETY OUESTIO:1 EVALUATION DOCUMEt TATION REQi! IRED:

[

(Significant change in procedure method or scope

.j as described in FSAR)

YES [-]

?!O.[9 (If yes, document in PORC/50RC meeting minutes)

Ei!VIR0"MEl!TAL It' PACT (Adverse environmantal impact)

YES [ ]

[10 [

(If yes, document in PORC/SORC meeti_ng minutes)

D.

PORC/SORC APPROVAL PORCf50RC eeting Mumber 79 ff E.

APPROVAL AtlD IMPLEf1EllTATI_ON The attached procedure is hereby approved, and effective on the dates below:

0 kL c'. t.!

[k\\Y71 V/.hbhf Plant Superintendent / Unit. Superintendent Approved Date EffecGe Date 9

] Q SF-301 j

Rev. E l 4

J

OP S16C l' age 1 i

Rev. I Date:

0/2/,/70 l

t i

O i

J l

Control Rod Drive ifydraulic System Rupture l

Py e tio.

Effective Revisicn !!o.

Date 1

1 8/24/79 2

1 8/24/79 3

1 8/24/79 l

5 1

e i

i i

l 1

I i

I

t

@ mC N. m P.

~[]

D Rev 1

Da '.e.

f./ 2 ' / P v

UP,JECTIVE 1.1 The purpose of this procedure is to provide the operator te.!th actions to be taken in the event of a rupture of the Control Rod Drive Hydraulic System outside primary containment.

i y,

DISCUSSION i

2.1 for the purpose of this procedure, we will consider the Control Rod Drive Hydraulic System as being the suction side of the CR0 pump to the primary containment penetration.

3.

SYMPTLJiS 3.1 Any one or all of the following may be indications of a control rod drive system rupture.

3.1.1 Charging water low pressure alann at 1400 psig on annunciator Al on CRP 905.

3.1.2 Control rod drive pump trip on low suction pressure at 18" HG.

Vacuum (alarm on annunciator Al on CRP905).

Control rod drive high tc. perature alarm on annunciator m

3.1. 3 Al on CRP 905.

3.1.4 Erratic control rod drive flow indication by meter on CRP 905.

4, AUTO:iATIC ACTIONS N/A IMMEDIATE ACTIONS 5.1 Verify the symptoms of Section 3 of this procedure.

5.2 If the rupture is between the operating pump discharge and f

valve 301-2 (A or B), shift to the standby CT!D pump and isolate the first pump.

1 5.3 If the rupture is an individual CRD hydraulic control unit, insert the red if possible and valve it out and electrically disarm the directional control valves.

I 5

l l

OP SIGC Pa gt. J 1

'D

{

Rev. 1 Date: C/24/79

)

o If the control rod cannot be fully inserted, refer to require-mants of Technical Specification 3.3. A.2.

5.4 If the rupture is in an isolable section which includes discharge i

filters, flow control stations or flow stabilizing sections, isolate the effected area and place the alternate section in j

service.

I 5.5 If the rupture is in a non-isolable section of the main header, proceed as follows:

5.5.1 Stop the running CRD pump.

5.5.2 With recirc. pump control in individual manual, reduce rccirc. pumps speed to minimum.

5.5.3 Scram reactor and carry out provisions of Emergency Procedure 502, Emergency Shutdown.

6.

SUBSE0'JEf:T ACTI0tt 6.1 Carry out Subsequent Actions of Emergency Procedure 502, Emergency Shutdoan.

6.2 flotify llealth Physics for surveying the area to d2termine extent of contamination due to activity of condensate and reactor water spilled from the rupture.

6.3 Check local equipment in the break area for possible damage.

6.4 Continue cooldown to cold shutdown to reduce probable back leakage from reactor through break.

7.

FIGUPES N/A Jti:cp 1

i

ro ()T 9 9'%

m hv3 51 L

r s ini i. a up.a m t im wn i.

o

-w.

n s.

STKi10N PRO ~.DiUl:E CD'!D: S!!El.'l j ng,JJpj,rl!'ICATION lhi:0h';P..-

OR 516D.-_ __..

Ile'v._ '2 Ti tle, Is_olation_ Condenser System Rupture

/

I Prep $ red I;y_

E. Berry s

. -.... /

1

}t.

I!EVIEll-I have reviewed the above. procedure and have found it to be sa.tisfactory

)

_ TITLE

' ~

SIR!AT.U_RE.

.DA'TE.

DEPARTHE!!T llEAD p

'p

-)2-j - )/

i

_1 y

t C.-

UMi!EVID.'ED SAFETY OUESTION EVAllinTION DOCUE!!TATION REC'lIRED:

.,i

'(Signi ficant change'in procedure lanthod or sco.

pe i

as described in FSAR) y.

s.~

(If yes, docuraent in PORC/SOHC meeting, rainutes}

YES [-]

HO.' [g

'D VIRONi;Ei!TAL IMPACT (Adverse environmentai impact)

YES'[ ]

110 [. '

(If yes, document in PORC/SORC meeti,ng minutes) 1

~

' PO!!C/SORC APPROVAL

~

a D.

PORC/SORC Meetin.g Numb'er 7f -/ 2. f ~

.~-

E-S'!'if]'{AL AMil Il;PLD;EliTATION 1

j The at tached procedure is hereby approved 16 effective on the dates belov.:

~

j

~

'. ~.

/ f m... /] f..

/ '/l-

{

-.g'g').i(

• I lunl Superintendent /Cait Superintende,__

Appro'/cd' il.i le Effec ti ve......

n t

.(

9 l

31..,g

-nc;.. :

~

\\

I, 3-DAhE:

~~ % %h,d'.

I

.._ -..'A..-.i 7 '.. ( -_ _.

k Ai n 0Vra:

-w.

..... s. c 5 (t i).o kp e ri n u nd. n t -... _. -

D'P D "3 p[ M p' EiATI_0:J.f yfG p l.R E 5,y,q _G l _f_0 2 1 ebtj d f.d. 3 h a

A.

ICE! TIFICATIO:1 Procedure Nu'mber_ p L.7/ [ O Rev.

.'7, Changerio./

([w.[g._M.k(%,kgyy.k.L6, Procedure Tit!e

' Initiated By_

i

. ~ 3 c. ;,

Date 8 Ti d x 3 g/ g) g,,. ). l B.

CHAi;GE

. %.c..S 'O b,.i L' L. n.: i:1.:i d L. E..'th c G,, 0 ;.. r a,. ~ YL.,

• !< r. ) 4 b e d E

vy e. s ~, (GA cj N u D.<4 d-W h

' Vnhien). % y1_q..at%l o. aY s ff c *.,.. W k a y. /c,3 [.S'c. 'N 'Nl q A

. m._ </ y

-c ~ Z U. W k ~ci.. m p/

U. X-:.,.i. k t,.; ( Y G 1. c~..; (t.._n.Q

.e<< &

.!KAS0:1 FOR CHAf!GE *C b'"^w@ -. a.,

3 Or

~ '

C.

./ OY,-

L%

sl

)

/

/

/:1.W dr. 6.k.;..

^

)

~

.D.

00j',-I lTElli CHAliGE AUTHORIZATI0tl (ilA. for Intent Changes)

_S.IGTI AT_b..R_E.

_DAT.E

~

TITLE eWtlSupe rvisor on dut'd

[.

_,)2fMSS-3 - 7 ';'d r

.__ 0po--

%Lk.

L f-r b? -

?..l$ 90

()'

f d

E.

P EV I E',.'E0

.hepartcent Head

..t!nreviewed Scfety Question Evaluation Documentation Required:

(~Signific?.nt change in procedure me.thod or scope

[]NO as d2 scribed in FSAR)

[ ] YES (If yas, document in PORC/SORC meeting.ninutes)

Ei;'/IRO:!MEi:iAL IMPACT (At/crse environmental impact)

[ ] YES

[]N0 (If yes, document in 70RC/SORC meeting minutes)

F.

. RC/50RC RECOMMEllDS A.: PRO'/AL (or confircation of inMria change within l4 di

' C/ 50?,C l b e t i n g ilc. ". e r.... __._.____ _

~

~

ti.

,l7.L C 3 I;:rl5." '. /. iiC':

N change is hereby a pi. ranted and is ef fective this date, except for inn 9

ch..y:s \\:hich uare i:.ph.: anted ar.d ef fective par G.e f.utharita ti:n af 0 abr. '.

.s

~

l-1.'lant Sci.crintendent/ Unit Superintendcnt

_ _.. _.. _.Date. _... _. _ _

> p ".. '

..e v 3

OP 516D Page 1 Rev. 2 Date:

1/1/80 I

Isolation Condenser System Rupture 1

Page No.

Effective Revision No.

Date i

1 2

1/1/80 2

1 1/13/79 3

2 1/1/80 i

1 i

l i

l l

i 1

I

t 516D Page 2 I

. n.

f.

Rev. 1 Date: 1/13/79 1.

OBJECTIVE The purpose of this procedure is to provide the operator with actions to be taken in the event of an isolation condenser system rupture.

2.

DISCUSSI0tl For the purpose of this procedure the isolation condenser system will start and end at the two drywell penetrations.

1 3.

SYMPT 0f1S l

Any one or all of the following may be indications of an isolation condenser system rupture.

3.1 Isolation condenser steamline break alarm and Group 4 isolation.

l{

3.2 High area temperature alarm.

J 3.3 Decreasing reactor water level as indicated on CRP 905.

3.4 Reactor scram and Group II and III isolations on low reactor water level.

3.5 Reactor building high rc3iation alarm.

t4 j

4.

AUTOMATIC ACTIONS Any one or all of the following actions may be automatically initiated due to an isolation condenser system rupture.

4.1 Group 4 isolation due to high steam or condensate flow through I

the isolation condenser system.

4.2 Reactor scram and Group II, III isolation due to low reactor I

water level.

5.

IMtiEDIATE ACTION j

5.1 Verify that a rupture condition exists.

5.2 If system has not yet isolated, isolate the Isolation Condenser f

System from CRP 903.

5.3 If the reactor has scrammed on low water level, verify reactor power decreasing and carry out the immediate actions of Emergency q

Procedure 502, Emergency Shutdown.

g

OP 5160 Page 3

~'

Rev. 2 Date: 1/1/80

(

6.

SUBSEQUENT ACTION If the reactor has scrammed on low water level due to the 6.1 rupture, carry out the subsequent action of Emergency Procedure 502, Emergency Shutdown.

If the reactor is still at power with the isolation condenser 6.2 system isolatd, complete repairs as soon as possible and restore the system to service.

tt0TE:

Ref. Ltr. IlEE-79-R-182 of June 4, 1979.

If the 3

iso-condensor can not be returned to service in 24

(.f hours plant operation shall be restricted to 40". of rated thermal power for up to the 15 days allowed by Tech. Spec. 3.5.E.2.

Perform surveillance SP 627.6, Functional Test When Isolation 6.3 Condenser System is Inoperable.

If above requirements cannot be met, an orderly shutdown shall 6.4 be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

the isolation valves fail to isolate the break on either an

[

6.5 tomatic or manual signal, proceed to Procedure OP 506 " Loss of Coolant".

7.

FIGURES N/A

-(

rian g dupar nit.entien t:

STNiTO.1 PROCEliURE COVE.P. SilEl.1

[c D

r-cD<.

u Ul} Ud bmju ki-/!gM 1

', A.$,I_D_El.ff..T.r..I.CA.T I O:l!

i

.x Ilu:nber OP 516E.

I;e'y, 3

g e

• fitle Reacto[_ Clean-UpSystqmRupture

~

~'

1

-,,y'.

Prepared By, E. Berry 1

}t.

REVIEW-s s

\\

I have reviewed the above, p.rocedure and have found it to be sa;i:isfactory -

\\c k

TITLE SIGE!KruRE

.DRfE e

.r DEPARTiiE!!T !!EAD 1

,3 1

t C..

UMREVirdD SATETY QUESTIO:i EVA1.UKfl0:! DOCU ;E!!TKfluti RE(pIi1ED:

'(Significant cliange'in procedure idethod or scob j.

as descr-ibed in FSAR)

YES [-]

110.' [VJ

/.,, (If'yes, docua:ent in PORC/SOHC meeting ininutes)

~

.E!!.M.. R.O..:.EENTAL IMPACT.

(Adverse envirorimenta*j impact)

YES'[ ]

Il0 [ j '

(If yes, document in PORC/SORC meeti,ng minutes)

D'.

' PORC/SORC APPROVAL

\\

I PORC/SORC lleeting !!umb'er 79-/Sc

' f-l E.

. APM.:.0..y3..L._ Ar;g 1;;PLEf:E!!TKfiO!!

The ut.tached procedure is hereby approved and er.rective on t.he dates bel.ow:

s s

. &. &...f...

y,i:y;.gf.-"..

) lp h- - -

pUnl Superintendent /dait Superintendent Appr'ovec Da le I.ffective Date

.I l

Sr. 30.'I.

Rev. 2

i

^

I.~

OP 516E Page 1 Rev. 3 Date:

1/2/80

.!O l

1 Reactor Clean-Up System Rupture Page No.

Effective Revision No.

Date i

1 3

1/2/80 j

2 3

1/2/80 i

3 3

1/2/80 l

1 O

OP 516E Page 2

~

Rev. 3 Date: 1/2/80

\\

1.

PURPOSE To provide the operator with actions to be taken in the event of a Reactor Clean-up System Rupture.

2.

DISCUSSION For the purpose of this procedure the Reactor Clean-up System will be defined as starting and ending at the drywell boundary.

3.

SYMPTOMS Any or all-of the following may be indications of a Reactor Clean-up System Rupture.

3.1 Decreasing reactor water level as indicated on CRP 905.

3.2 Reactor Scram, Group II and III isolation on low reactor water level.

3.3 Erratic pressure and flow control of the clean-up system as indicated by flow and pressure recorder on CRP 904.

3.4 High area temperature alarms,160 F.

/

3.5 Clean-up recirc. pump trip on low suction pressure (10 psig).

3.6 Reactor building high area radiation alarm.

3.7 Non-regenerative heat exchanger effluent high temperature alarm at 140 F on annunciator A2 CRP 904.

3.8 Clean-up system low flow, alarm at 300 gpm.

4.

AUTOMATIC ACTIONS The following automatic actions may or may not be initiated depending on severity of the rupture.

4.1 Reactor Scram, and Group II and III isolation due to low reactor water level.

4.2 Clean-up system isolation due to non-regenerative heat exchanger effluent high temperature.

-(

OP 516E Page 3 Rev. 3 Date:

1/2/30 5.

IMfiEDIATE OPEP.ATOR ACTIONS s

5.1 If rupture is discovered and validated before the reactor scrams on low water level, isola.te the clean-up system and restore the reactor water level to normal while at power.

5.2 If the reactor scrams on low water level, verify the scram, Group II and III isolation and carry out the immediate operator actions of Emergency Procedure 502, Energency Shutdown.

6.

SUBSEQUENT ACTIONS 6.1 With the reactor operating and clean-up system isolatad, located and repair the leak.

NOTE:

If at any time while the clean-up system is isolated reactor water conductivity exceeds 2.0 umho/cm or chloride ion concentration reaches.5 PPM, an orderly Plant Shutdown shall be initiated.

6.2 Notify the Unit Superintendent of existing plant conditions and request further instructions.

k 6.3 With reactor scrammed and clean-up system isolated, carry out the subsequent actions of Emergency Procedure 502, Emergency Shutdown.

6.4 Locate and repair the leak.

6.5 Restore the plant to service in accordance with General Plant Operating Procedures following the appropriate repairs and testing.

6.6 If the isolation valves fail to isolate the break on either an automatic or manual signal, proceed to Procedure OP 506,

" Loss of Coolant".

l

kN {[__,,

l

' MIN'i(b-DATE:

hPI'f:0VE0:,..-h:9 5[4t i.n 5.ap ri n tend. r.t STATION PPOCED'L3 C1jijiD J021 D 0

t n.

---

IDEl;l iF ICAT IO 1 Procedure Nu'...bero/ 5 / (., F Rev.

2.

Cnance no.../

4 0 s s, o t feo NA Ter w e4 e~' afasA rwa.4 i 4 4 ci 4 A,tz Proccdure TiLTc M cv r&,. isoarty cma~s <<

our of sn w C *

'InitiatedBy,[

w

g. __

Date _f- - /Idi C,.3 -

S nur rii+ ASt ?D Bo m MP. 9by B'

CliANGC c.'t u.u c e

~ 4 9.704 p Quo CAP 703 l

c

=

C.'

REASOM FOR CHA:'GE Q pja jz( fdhc ESOW ?

,C64' C 4 U?NT:5 J T 1 Y/'.Skh' -

Y 1

~

.D.

I 0."-I:lTEt;T CHESE AUTHCRIZATION (UA. for Intent Changes)

TITLE SIG.'iATUP.E

_D A.T...E

~

.._.Shif_t3unervisor (on du tv)

..,.(( p,,/h

,J

/.l-0Adk'

-p h&A, Ahg3()

s E.

REVla:E0 M# Y'-

2 / v j;q pepartmentHead V

..Unreviewed Safety Ouestion Evaluation Occumentation Recuired:

TSignificant chance in procecure r:ethcc or scc,n

~

as described in FSAR)

[ ] YES

[Tii0.

(If yes, document in FORC/50RC meeting mir.utes)

ENVIR0T Ni!TAL IMPACT (Adverse environmental impact)

[ ] YES

[

H0 (If ycs, document in 'PORC/50RC meeting minutes)

.~

F.

.' ORC /SORC RECOMMEilDS APPROVAL (or confircation of interim change 'aithin K c*u'

(.h'C ceting !; umber _

~

i. ",l. A':0 I!*"LE"il:iAT IC.'l he chan;e is hereby im,iienented and is ef fcctive this date, except for intc' Mng ':hicM.;ere i::plc:ren ted and ef fective per 'de /su thori; a tion o f D a:..' '

/

/

i 6-

/0, '$}hV p-f),f [U olant su,2crintee.a:/ Unit Superinten '.at 7 o, te P.

. ' SPl>R6\\*AL :$ - Q":_i~h Q __

DATE:

7-1-77 Plant Superintendent STATIO:t PROCEDURE COVER SHEET grq E

h.

IDffiTIFICATIO1 I

J

_a

?! umber OP 516F Rev.

2 Title LOSS OF FEEDt!ATER t! Hell OPFRATIf:G AT < 40" RATED P00ER UITH THE ISOLATI0fl I

C0:!DEilSEIOUI OITERVKE

~

l Prepared By L. Crosse B.

REVIEW l

I have reviewed the above procedure and have found it to be satisfactory.

4 i

TITLE S_IG!!ATURE DATE DEPARTilalT HEAD d) op d /9 y/;y 77 f

u h gG Ry n_ 'rfo r

& &onc-S-S-79 l

j C.

UtiREVIEUED SAFETY QUESTI0il EVALUATI0il DOCUMEftTATI0il REQUIRED:

(Significant change in procedure method or scope l

as described in FSAR)

YES [ ]

If 0 [u]'

g (If yes, document in PORC/50RC meeting minutes) l EllVIRO:lME!1TAL Ii4 PACT (Adverse environmental impact)

YES [ ]

t10[*[

(If yes, document in PORC/SORC meeting minutes) l D.

P_0RC/SORC APPROVAL 1

j PORC/50RC Meeting flumber 7f - 9.9 E.

APPROVAL AtlD IMPLEMEt1TATI0il The attached procedure is hereby approved, and effective on the dates below:

4 1

WRbtl Wib9 r//r/?9 Plant Superintendent / Unit Superintendent Approved Date Effectivo Da'te SF-301 i

Rev. 2l i

j

I OP 516F Page 1 Rev. 2 Date: 8/15/79 i 0 PHil31G l$1 l

LOSS OF FEECllATER tillEt! OPERATIt!G AT < 40% POWER ilITil THE ISOLATI0tl C0!iDEftSER OUT OF SERVICE I

l I

PAGE !!0.

EFF. REV.

.DATE i

l 1

2 8/15/79 j

2 2

8/15/79 i

3 2

8/15/79 i

4 2

8/15/79 l

t t

1 i

l i

i 1

1 1

1 I

t b

i

OP SlGF Page 2

~

1 Rev. 2 Date: 8/15/79 g

i O

l 1.

PURPOSE To provide the operator with action to be taken in the event of a loss of feedwater when operating at 140% rated power with the isolation condenser out of service.

1 2.

DISCUSSICri At < 40% reactor power, with the isolation condenser out of service, 1

j plant operating parameters will be modified to assure that the core i

will not be uncovered in the event of a loss of feedwater transient.

2.1 The SJAE minimum flow line will be isolated at power levels greater than 25%.

I 2.2 Operate the feedwater control station on one valve.

The second valve is to be closed and on individual manual control.

i l

2.3 One control rod drive pump will be operated continually.

ii 3.

SYitPT0:1S j

3.1 Reactor water level decreasing as indicated by reactor water level recorder on CRP -905.

1 3.2 Reactor scram, Group II and Group III isolation on low reactor 1

q water level as indicated by alarm on annunciator Al CRP-905.

3.3 Reactor feedwater pump, condensate booster pump or condensate pump trip.

3.4 Indicated feedwater flow decrease.

3.5 Feedwater control valve failed shut.

4.

AUTO:1ATIC ACTI0fl 4.1 Reactor scram, Group II and Group III isolation at reactor water level +8 by Yarway. CRP-905.

t

)

5.

Ilif1EDIATE OPERATOR ACTI0ft Attempt to re-establish feedwater flow to prevent reactor scram and a

group isolation.

If you are unsuccessful and a reactor scram i

j occur 2, carry out the following action:

0 i

OP 516F Page 3 G'{D

]U)

'fD~hff Rev. 2 Date: 8/15/79 J e v' WA\\.M];E U

5.1 Verify reactor scret has occurred by observing scram Channel j

}

"A" and "B" annunciator. lights illuminated,. all control rods

{

fully inserted, and reactor power decreasing on APftf4/IRil recorders on CRP-905.

l 5.2 Trip the turbine by simultaneously depressing the two turbine trip buttons on CRP-907.

1 (pC 5.3 Shut the l',SIV's from CRP-904.

Il 3

5.4 Confim that CRD flow to the reactor vessel is > 60 GPfl.

If there is no CRD flow, carry out the following steps:

5.4.1 Start core spray and low pressure ceclant injection pumps (4 LPCI and 2 CS).

5.4.2 Depressurize the vessel by immediately opening all 3

three APR's, following their operation leave all three A.P.R.'s cpen to provide an adequate vent path to assure reactor pressure remains below the L.P.C.I.

and core spray pump shut off head pressure.

5.4.3 Insure at 300 psi core spray and low pressure coolant injection valves open.

5.4.4 Run core spray and low pressure coolant injection pumps as necessary to maintain normal vessel level.

NOTE:

Prior to shutting down any E.C.C.S. pumps, it is imperative that operators monitor all available water level instruments to ensure adequcte vessel level.

If level indicatore disagree operate by the lower reading indicators until instrument accuracy is determined.

5.4.5 flotify higher supervision.

5.5 If CRD flow is > 60 GPIt to the reactor vessel, attempt to re-establish feedwater flow to the vessel using all means

{

available.

If at the end of eight (8) minutes feedwater flow 1

to the vessel has not been re-established and the vessel low level e

{

alam has not cleared, carry out Steps 5.4.1 thru 5.4.5.

3

(.A.,

OP 516F Page 4

~

i

~

Rev. 2 Date: 8/15/79 I g 6.

SUCSE00ErlT ACTICil 6.1 riotify higher supervision and retuest further instructions.

i 7.

FIGURES fl/A e

LC/llm 4

1 1

\\

\\

i

}

!