ML20205C801

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Rev 2 to Emergency Operating Procedure EOP 35 FR-P.1, Response to Imminent PTS Condition
ML20205C801
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 06/15/1988
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-35-FR-P.1, NUDOCS 8810260574
Download: ML20205C801 (13)
v • d • e


Text

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  • 3-31-87 87-12 Iorm Approved by Stat'.on Superintend:nt Effective t, J SORC Mtg. No.

STATION PROCEDURE COVER SHEET A. IDENTIFICATION Number: E0P 35 FR-P.1 Rev. 2 l

Title:

RESPONSE TO IMMINENT PRESSURIZED THERMAL SHOCK CONDITION l Prepared By: A.W. HORTON B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

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TITLE SIGNATURE DATE DEPARTMENT HE 4,[/

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t C. SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED: .

Modifies intent of procedure and changes operation '

/ l of systems as described in design documents. YES [ ] NO D/]

(If yes, perform written USQ determination and Safety Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)  ;

! ENVIRONMENTAL REVIEW REQUIRED l (Adverse environmental impact) YES [ ] NO [ [

> l t D. SPECIFIC SAFETf EVALUATION REQUIRED  ;

i Affects respon.e of safety systems, performance of systems which may have been credited in the  !

safety analysis or non-credited systems which / l may indirectly affect safety system response. YES [ ] NO [i  :

(If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine  !

need for Integrated Safety Evaluation.) ,

E. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] NO [

i F. PROCEDURE REQUIRES M SORC REVIEW l (Tn addition to revfrw it ith a YES response j must be documented *.7 the OR 50RC meeting minutes.) YES [G NO [ ] r l

G. 50RC APPROVAL SORC Heeting Number 3-17-207 H. APPROVAL AND IMPLEMENTATION I 1 The attached raceduse. i s y approved, and effective on the date below: t L,a wa  ;

Station / Service / Unit Superintendent Effective Date

SF 301 Rev. 9 i Page 1 of 1 ,

j 8810260574 00100723 ,

PDR ADOCK 050 P [

$ a E0P 35 Fn 9.1 Page 1 j <. Rev. 2  ;

s RCSPONSE TO IMMINENT PRESSURIZED 4

THERMAL SHOCK CONDITION '

i PAGE NO. EFF. REV.  !

1-10 2 l

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RESPONSETOIMMIN$NTPRESSURIZED E0P 35 FR-P.1 Page 2 TKERMAL SHOCK CONDITION Rev. 2 n

A. PURPOSE This procedure provides actions to avoid, or limit, thermal shock or pressurized thermal shock to the reactor pressure vessel, or overpressure conditions at low temperature.

B. ENTRY CONDITIONS This procedure was written for modes 1, 2, 3, and 4. Using this procedure when not in these modes requires a step by step evaluation to determine if the required action is still applicable to current plant conditions.

This procedure is entered from E0P 35 F-0.4, INTEGRITY Critical Safety Function Status Tree on either a RED or ORANGE condition.

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RESPONSE TO IMMINENT PRESSURIZED THERMAL E0P 35 FR-P.1 Paga 3 l SHOCK CONDITION Rev. 2

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STEP ACTION /SIPSCTED RESPONSE AESPONSE NOT 09TAINED NOTE i A faulted SG is any SG that is depressurizing in an uncontrolled manner or is completely depressurized. [1 i

CAUTION If RCS Temperature is below 350*F arm the cold  ;

Overpressure Protection System i-1 Check RCS Cold Les Try to stop RCS cooldown  ;

Temperatures - STABLE OR ,

INCREASING a. Verity SG atmospheric dump valves and safeties

> closed IF NOT, CLOSE RCS cold les isolation valve for that loop.

< b. Verify condenser steam

,g dump valves closed.

c. IF RHR system in service, ,

THEN stop any cooldown r from RHR system.

d. Control feed flow to  :

I non-faulted SG(s) to stop RCS cooldown. Maintain L total feed. flow > 525 spa  ;

until narrow range level i a > 4% (34% for adverse i containment) in at least  ;

one non-faulted SG. '

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RESPONSE TO IMMINENT PRE;'SURIZED THERMAL EOP 35 FR-P.1 Peso 4 SHOCK CONDITION Rev. 2 G

STEP ACTION /SEPECTED RESPONSE RESPONSE NOT OSTAINEO

e. Minimize cooldown from faulted SO(s):
1) Close the following

- Main Stese Line Isolation and Bypass Valves

- Main Feed Line Isolation

- Chemical Feed Lines

- Blowdown and Sampitas Lines

- Auxiliary Feed Lines

- Steam Supply to TDAFW Pump ,

, 50 Atmospheric Dump Valves

- Main Steam Line Low Point Drains

- TDAW Puey Low Point Drains IF all 50s faulted,

2) EMEN control feed

( flow at 75 spa to each 50.

3) IF any 50 NOT faulted. THEN isolate all feedwater to faulted SO(s) unless necessary for RCS temperature control. IF a faulted SG is necessary for RCS temperature control, THEN control feed flow at 75 spa to that 50.

2 Check PZR PORY Block Valves

a. Block valvea - AT LEAST a. Open one block valve ONE OPEN unless it was closed to isolate an open PORV.

O OP5064-1 H4

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1 RESPONSE TO IMMINENT PRESSURIZED THERMAL EOP 35 FR-P.1 Pago 5 ,

SNOCE CONDITION Rev. 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED CAUTION If any PZR PORY opens because of high pressure. Step 3b should be repeated after pressure decreases to less than the L PORY setpoint.

3 Check If PZR PORVs should Be Closed

a. Check the following a. Verify at least one PZR PORY open. ,
1. PZR prosaura Continue with Step 4. '

< 2350 psia IF WHEN pressure < setpointe  ;

COLD OVERPRESSURE THEN do Step 3b. ,

PROTECTION SYSTEM .

NOT IN SERVICE .

OR

2. RCS pressure  !

< COLD OVERPRESSURE LIMIT IF COLD i OVERPRESSURE PROTECTION  :

O, SYSTEM IN SERVICE  ;

b. PZR PORVs - CLOSED b. Manually CLOSE PORV.

lE any valve can NOT be closed. THEN manually l CLOSE its block valve.

4 Check If ECCS Is In Service Go to Step 12.

a. SI pumps - ANY RUNNING  ;
b. Charging Pumps Cold 7 Less Isolation Valves

- OPEN 5 Check If ECCS Can Be Terminated DO NOT STOP SI PUMPS.

a. RCS subcooling based on Perform the following core exit TCs > SO'F (140'F FOR ADVERSE 1) 1F RCS subcooling based l CONTAINMENT on core exit TCs AND > 80*F (140*F for
b. RVLMS plenum level adverse containment) AND ,

>19%. no RCP running, THEN  ;

start an RCP per t OP 3301D, RCP OPERATION.  !

2) co to Step 23.

({]) I CPK68-1 344

RESPONSE TO INMINENT PRESSURIZED THERMAL E0P 35 1R-P.1 Page 6 SHOCK CONDITION Rev. 2

- sTap ACTION /tXPECTRO RESPONSE RESPONGE NOT OSTAINEO CAUTION If offsite power is lost after SI reset, manual action may be required to restart aafeguards equipment.

6 RESET SI 7 RESET Containment Isolation Phase A And Phase B 8 Instrument Air to Containment Establish Instrument

- LGfABLISHED Air to Containment

a. One instrument air l corpressor - RUNNING
b. OPEN instrument air containment isolation valves 9 STOP ECCS Pumps And Place O In AUTO
a. RHR pumps
b. SI pumps
c. All but one charging Pump 10 Isolate Charging Pump Injection Flow Path
a. IF two charging pump cold les injection valves are open, THEN CLOSE one valve.
b. Establish 60 gpm normal charging path
c. CLOSE the Charging Pump miniflow isolations to the RWST (3CHS*MV8511A/B)
d. CLOSE a Charging Pump Cold Leg Injection valve 11 OPEN the Charging Pump Recire Isolations To Reactor Cold Leg Isolation Valves O

0P5004-1 H4

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RESPONSE TO IMMINENT PRESSURIZED THERMAL E0P 35 FR-P.1 Page 7 f SHOCK CONDITION Rev. 2 i I

O - aTsP ACTION /EIPSCTED RESPONSE ASSPONSE NOT OSTAINEO t

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12 Verify ECCS Flow Not Required Manually operate ECCS

a. RCS subcooling based on pumps as necessary, core exit TCs > 30*F Perform the following (

(90*F FOR ADVi.RSE ,

CONTAINMENT) 1) E RCS subcooling based [

on core exit TCs  ;

> 30*F (90'F for adverse i containment) AM no RCP i running, THEN START an i RCP pre OP 3301D, RCP l OPERATION. j

b. RVLMS plenum level 2) Go to Step 23. l

> 19%

13 Check RCS Hot Les E increasing, THEN control .

Temperatures - STABLE feed flow and steam dump as 7 necessary to establish stable i RCS hot leg temperatures. E  !

decreasing, THEN verify actions  !

of Step I have been performed t before continuing with this r procedure.

O 14 Isolate All SI Accumulators Check the following

[

4. a. Return to Step 12. {
1) RCS subcooling based on l core exit TCs > 30'T (90*F FOR ADVERSE CONTAINMENT)
2) RVLMS plenum level > 19%.
b. Restore power to the SI accumulator isolation valves (32-2R-R5F, 32-2W-R3J, 32-2R-F4M, 32-2W-F4M)
c. CLOSE the SI accumulator c. Vent unisolated isolation valves accumulators
d. Remove power from the SI accumulator isolation valves O

OPS 0641 3-84

d e . i RESPONSE TO IMMINENT PRESSURIZED THERMAL E0P 35 FR-P.1 Page 8 SHOCK CONDITION Rev. 2 1 1

- e7tp Acil0N/expecies neep0Nea esep0 Net NOT 08TA8NEO

,15 Depressurize RCS To Decrease RCS Subcooling '

a. Use normal PZR spray a. E normal spray NOT  !

available, TR use one PZR PORV. E necessary, manually operate ECCS l

pumps to maintain RCS  :

subcooling > 30'F (90'F  !

FOR ADVERSE CONTAINMENT). .

E RCS can NOT be l depressurized using any  !

PZR PORV, THEN use auxiliary spray.

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b. Depressurire RCS until j

either of the following . t conditions satisfied .

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1) RCS subcooling based on core exit TCs

< 40*F (100*F FOR I ADVERSE CONTAINMENT)

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2) PZR level > 82%  !

(54% FOR ADVERSE l CONTAINMENT)

c. Stop RCS depressurization CAUTION I i

An increase in RCS pressure may result in excessive reactor vessel stress. RCS pressure and temperature should be -

maintained stable while performing subsequent steps in this I procedure, i f

16 Check PZR Level > 17% Try to restore level with (50% FOR ADVERSE charging while maintaining CONTAINMENT) stable RCS pressure.

IF level can NOT be restored.

THEN go to Step 22.

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RESPONSE TO IMMINENT PRESSURIZED THERMAL E0P 35 FR-P.1 Page 9 SHOCK CONDITION Rev. 2 t t

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- step ACTIOWSIPSCTED M8:P00008 RESP 08845 NOT 09TA48880 l [

i 17 Check VCT Hakeup Control Adjust controls as necessary.  !

System  !

a. Makeup set for > RCS  !

boron concentration  !

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b. Makeup set for automatic  !

> control  !

18 Establish Letdown Establish excess letdown as per OP 3304 CHARGING AND LETDOWN l

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. 19 Check Charging Pump Suction - Align suction to VCT [

ALIGNED TO VCT  ;

f j 20 Check PZR Level < 82% Control charging and letdown , i t (54% FOR ADVERSE as necessary. If necessary j

. CONTAINMENT) establish excess letdown  !

i 21 Control PZR Pressure t

a. Turn on PZR heaters and a. E normal spray NOT d

operate normal PZR spray l available and letdown  ;

i as necessary to maintain is in service, THEN use l

. pressure stable auxiliary spray. IF, f j NOT, THEN use one PZR  !

PORV.  !

22 Check RCS Subcooling Based On E normal spray NOT l Core Exit TCs - AT 40*F available and letdown i (100*F FOR ADVERSE is in service, THEN use

]; CONTAINMENT) auxiliary spray for any

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further depressurization. [

1 Return to Step 15b. E i NOT, THEN return to Step  ;

15a.

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RESPONSE TO IMMINENT PRESSURIZED THERMAL E0P 35 FR-P.1 Pega 10 SHOCK CONDITION Rev. 2 sist Action /expecten mespoNes Resp 0Nes NOT OefAINs0 23 Determine If RCS Temperature Soak Is Required

a. Cooldown rate in any RCS a. Go to Etep 24, cold leg > 100'F IN ANY 60 MINUTE PERIOD
b. Perform all of the following
1) Do not cooldown RCS until temperature has been stable for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
2) Do not increase RCS ,

pressure during that time .

3) Perform actions of other procedures in effect which do not cooldown or increase RCS pressure until the RCS temperature soak has been completed
4) RCS cooldown is permitted after 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
5) Maintain RCS pressure and cold les temperature within the limits of OPS Form E0P 35 TR.P.1-1 (OPS Form E0P 35 FR.P.1-2 TOR ADVERSE CONTAINMENT)
6) Maintain cooldown rate in RCS cold legs < 50*F in any 60 minute period 24 Return To Procedure And Step In Effect

-FINAL-O OPS 0041 344

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POST SOAK C00LOOWN LIMIT NORMAL ERRORS

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OPS Form E0P 35 FR-P.1-1 Rev, O Page 1 of 1

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POST SOAK C00LOOWN LIMIT ADVERSE ERRORS i

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