ML20205C273

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Rev 2 to Emergency Operating Procedure EOP 35 ECA-2.1, Uncontrolled Depressurization of All Steam Generators
ML20205C273
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-ECA-2.1, NUDOCS 8810260436
Download: ML20205C273 (18)


Text

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.' 4 STATION PROCEDURE COVER SHEE.

A. IDENTIFICATION n

) Number: E0P 35 ECA-2.1 Rev. 2

Title:

UNCONTROLLED DEPRESSURIZATION OF >.LL STEAM GENERATORS Prepared By: D. BR00 SKY t

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

TITLE SIGNATURE DATE DEPARTMENT HEAD , (o &

C. SPECIFIC UNREVIEWE0 SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation of systems as described in design documents. YES [ ] NO [4 (If yes, perform written USQ determination and Safe'y Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

ENVIRONMENTAL REVIEW REQUIRED

(~~} (Adverse environmental impact) YES [ ] NO [6

\'~~/

D. SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safsty analysis or non-credited systems which may indirectly affect safety system response. YES ( ) N0 ((

(If yes, perform written Safety Evaluation and contcet Manager, Safety Analysis Branch tc determine i need for Integrated Safety Evaluation.)

E. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] N0 ( I F. PROCEDURE REQUIRES h f/50RC REVIEW (In addition to review, ite ' with a YES response must be documented in the 03/SORCmeetingminutes.) YES ( I N0 [ ]

C. h SORC APPROVAL PORC SORC Meeting Number 3 - 8[- /O_3 v

H. APPROVAL AND IMPLEMENTATION lhe attached procedure is hereby approved, and ef?ective on the dato below:

- 4 - ,__ /A - /i $5

' Station / Service / Unit Superintendent ;iffective Date

\ SF301/9/s/SES/87-12/lof1 8910260436 801007 3 DR ADOCK 0D00

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! l 4 1 E0P 35 ECA-2.1 . age 1  ;

Rev. 2 i i

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UNCONTROLLED DEPRESSURIZATION OF ALL STEAM CENERATORS l

Page No. Eff. Rev.  ;

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- 1 - is 2 l Attachme'nt A 2  !'

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. UNCONTROLLED DEPRESSURIZATION E0P 35 ECA-2.1 Page 2 0F ALL STEAM GENERATORS Rev. 2

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- A. PURPOSE i This procedure provides actions for a loss of secondary coolant which affects all steam generators.

B. ENTRY CONDITIONS This procedure was written for modes 1, 2, 3 and 4 with RHR system not in service, 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 E-2, FAULTED STEAM GENERATOR ISOLATION, Step 2, when an uncontrolled depressurization of all steam generators occurs.

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E0P 35 ECA-2.1 Page 3

. UNCONTROLLED DEPRESSURIZATION 0F ALL STEAM GENERATORS Rev. 2

\O) v STEP ACTIOpt tXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION

1. If any SG pressure increases at any time during this procedure, E0P 35 E-2, TAULTED STEAM GENERATOR ISOLATION, should be pe r fo rmed ,
2. If the turbine-driven AFV pump is the only available source of feed flow, steam supply to the turbine-driven AFW pump must be maintained from one SG.

NOTE Foldout page should be open.

_____1 Check Secondary Pressure Manually close valves. IF Boundary valves can NOT be closed, 7.

a. Main steamline THEN dispatch operator to

\ isolation and locally close valves, one bypass valves - loop at a time.

CLOSED

b. FW control and bypass valves - CLOSED
c. FW isolation valves

- CLOSED

d. Steam supply valves to turbine-driven ATV pump - CLOSED i f ttDAFW pump running
e. SG atmospheric damp valves - CLOSED
f. SG blowdown isolation valves - CLOSED
g. Main steam line drains upstream MSIVs - CLOSED
h. SG Blowdown Sample Isolation valves - CLOSED (v)

OPRM 1 3 44

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. UNC05 fh0LLED DEPRE55UMIZATION EUF 35 ECA-2.1 Fage 4 0F ALL STEAM GENERATORS Rev. 2 r~N i)

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STEP -

ACTION EXPECTED RESPONSE RESPONSE NOT OBTAINED r

CAUTION A minimum of feed flow of 75 gpm must be maintained to each SG with a narrow range level

< 4% (34% for adverse containment). l 2 Control Feed Flow To Minimize RCS Cooldown

a. Check cooldown rate a. Decrease feed flow to in RCS cold legs 75 gpm to each SG.

< 100*F/HR Go to Step 2c.

b. Check narrow range b. Control feed flow to level in all SGs maintain narrow range

< 50% level ( 50% in all SGs. )

c.. Check RCS hot leg c. Control feed flow or dump temperatures - steam to stabilize RCS STABLE OR DECREASING hot leg temperatures.

NOTE Seal injection flow should be maintained to all RCPs.

3 Check If RCPr Should Be Stopped

a. Charging OR Safety a. Go to Step 4.

Injection Pumps -

AT LEAST ONE RUNNING

b. RCS Pressure < 1435 psia b. Go to Step 4.  !

(1700 PSIA FOR ADVERSE ,

CONTAINMENT)

c. Stop all RCPs 4 Check DWST Level Switch to CST AFW water supply.

> 80,000 gal O

OF%W 1 3-44

. UNCONTROLLED DEPRESSURIZATION E0P 35 ECA-2.1 Page 5 0F ALL STEAM GENERATORS Rev. 2 j

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If any PZR PORV opens because of high PZR pressure, Step Sb shot ' be repeated after pressure decreases to . than PORV setpoint.

5 Check PZR PORVs And Block Valves

a. Power to block valves - a. Restore power to block AVAILABLE valves.
b. PORVs - CLOSED b. IT PZR pressure < 2350 psia, THEN manually close PORVs. IT any valve can NOT be closed.

THEN manually close its block valve,

c. Block valves AT c. OPEN block valve

\ LEAST ONE OPEN 'unless it was closed to isolate an open PORV.

6 Check Secondary Radiation

a. Have Chemistry obtain sample for SG activity,
b. Check unisolated secondary radiation monitors
1) IF the radiation monitoring computer is NOT available, THEN have an HP technician manually determine main steam line radiation -

SORMAL

c. Secondary radiation - c. Go to E0P 35 E-3 NORMAL STEAM GENERATOR TUBE RUPTURE, Step 1.

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CPMa 1 3H

. UNCONTROLLED DEPRESSURIZATION E0P 35 ECA-2.1 Page 6 0F ALL STEAM GENERATORS Rev. 2

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STEP ACTION / EXPECTED RESPONSE .9ESPONSE NOT OSTAINED CAUTION

1. If offsite power is lost after S1 reset, manual action may be required to restart .

safeguards equipment. L

2. RCS pressure should be monitored. If RCS pressure decreases to < 300 psia (450 psia for adverse containment), the RHR pumps must be manually restarted to supply water to the RCS.

i 7 Check If RER Pumps Should Be Stopped

a. Check RCS pressure
1. Pressure > 300 psia 1. Go to E0P 35 E-! l (450 psia FOR LOSS OF REACTOR OR ADVERSE CONTAIN'1EN1) SECONDARY COOLANT, Step 1.
2. Pressure - ST.tPIF. 2. Go to Step 8.

OR INCREASING

b. RESET Si if necessary

, c. RESET RHR pumps and d

place in AUTO i

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CMcu t 3 44

. UNCONTROLLED DEPRESSURIZATION E0P 35 ECA-2.1 Page 7 0F ALL STEAM GENERATORS Rev. 2

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-- STEP ACTION; EXPECTED RESPONSE RESPONSE NOT OSTAINED 8 Check If Containment Spray Should Be Stopped

a. Spray pumps - RUNNING a. Go to Step 9.
b. Containment pressure - b. .inue with Step 9.

< 13 PSIA W.2N containment pressure

< 13 psia THEN do Steps Steps 8c and d.

c. Reset containment depressurization actuation signal
d. STOP containment spray pumps and place in AUTO
1. STOP Quench Spray Pumps, CLOSE Spray Header Valves, and CAT valves.
2. STOP Containment Recire. Spray

()

V Pumps 9 Check RWST Level Go to E0P 35 ES-1.3, TRANSFER

> 520,000 gallons TO COLD LEG' RECIRCULATION, Step 1.

10 Check If Accumulators Should Be Isolated

a. At least two RCS hot a. Go to Step 11.

leg temperatures

<375'T l

b. Restore power to isolation valves (32-2R-R5F, 32-2W-R3J.

32-2R-F4M, 32-2W-F4M).

c. CLOSE all SI accumulator c. Vent any unisolated isolation valves accumulators
d. Remove power from isolation valves.

O z , . . . ..

UNCONIh0LLED DEPRESSURIZATION E0P 35 ECA-2,1 Page 8 0F ALL STEAM GENERATORS Rev. 2 D

(U STEP ACTION. EXPECTED RESPONSE RESPONSE N07 0 STAINED 11 Check If ECCS Should Be Reduced

a. RCS subcooling based a. DO NOT STOP ECCS PUMPS.

on core exit TCs Return to Step 2. i

> 30'F (90*F FOR ADVERSE CONTAINMENT).

b. RCS pressure - STABLE b. DO NOT STOP ECCS PUMPS.

OR INCREASING Return to Step 2.

c. PZR level > 7% (50% FOR c. DO NOT STOP ECCS PUMPS. i ADVERSE CONTAINMENT) Try to stabilize RCS I pressure with normal PZR spray. Return to Step 11a.

CAUTION If offsite, power is lost after SI reset, manual action may be required to restart

[3 safeguards equipment.

s>-

12 RESET SI 13 RESET Containment Isolation Phase A And Phase B 14 Instrument Air To Establish instrument air to Containment - ESTABLISliED containment.

a. START oue a)r compressor l and establish instrument l air to containsient
b. OPEN Instrument Air Containment isolation valves 15 STOP All But One Charging, Pump And Place In AUTO  ;

16 Check RCS Pressure - DO N0T SiOP ADDITIONAL ECCS -

Return to Stap 2 STABLE OR INCREASING PUMPS.

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. LNCvhlkutLtD DEPRESSURIZAl'ON E0P 35 ECA-2.1 Page 9 0F ALL STEAM GENERATORS Rev. 2

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- STEP A TION /EX8tCTED RESPONSE RESPONSE NOT OSTAINID 17 Establish normal Charging Pump Injection Flow Path

a. IF two chstging }. ump

, cold leg injection valves are open, THfN CLOSL 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 18 OPEN the Charging Pump Recirc Isolations 19 Control Charging Flow IF PZR level continues to To Maintain PZR Level decrease, THEN realign charging pump to Reactor

('_,N ) Cold Legs Injection valves.

Return to Step 2.

20 Check If SI Pumps Should Be Stopped

a. Check RCS prersure a. DO NOT STOP ADDITIONAL
1. Pressure > 1635 psia SI PUMPS. Return To (1905 psia FOR Step 2.

ADVERSE CONTAINMENT)

2. Pressure - STABLE OR INCREASING
b. STOP SI pumps and place in AUTO

. 21 STOP RHR Pumps And Place In AUTO e , ..

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. trNCONTROLLED DEPRESStlRIZATION E0P 35 ECA-2.1 Page 10 0F ALL STEAM GEh"ZRATORS Rev. 2 A _

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STEP AC7 ION EXPECTED RESPONSE RESPONSE NOT OSTAINED

,22 Verify ECCS Flow Not Required

a. RCS subcooling based a. Manually operate SI pumps on core exit TCs as necessary. Seturn to

> 30'F (90*F FOR ADVERSE Step 2.

CONTAINMENT).

b. P2R level > 7% (50% FOR b. Control charging flow to ADVERSE CONTAINMENT) maintain PZR level. IF PZ't level can F0T be maintained, THEN manually operate SI pumps as necessary. Return to Step 2.

23 Check RCS Hot Leg Control feed flow or dump Temperatures - STABLE steam to stabilize RCS hot OR DECREASING leg temperatures. i-24 Check Narrow Range Control feed flow to maintain Level In All SGs < 50% narrow range level < 50% in l all SGs.

O _ _2 5 Check If Letdown Can Be Established

4. PZR level > 17% a. Continue with Step 26.

(50% FOR ADVERSE kHEN PZR level increases CONTAINMENT) > 17% (50% FOR ADVERSE CONTAINMENT), THEN do Step 25b.

h. Establish letdown b. Establish excess letdown per OP 3304A, CHARGING AND LETD0kN.

26 Check VCT Makeup Control Adjust controls as necessary.

System

4. Makeup set for greater I than RCS boron i concentratton .

1

b. Makeup set for automatic control  ;
c. BTRS - 0FF 27 Align Charging Pump Suction
To VCT O

OPSR 1 3 44

. UNCONTROLLED DEPRESSURIZATION E0P 35 ECA-2,1 Page 11 0F ALL STEAM GENERATORS Rev. 2 O --

STEP ACTION EXPECTED RESPONSE RESPONSE NOT ORTAINED

_____28 Check RCP Cooling -

NORMAL

a. RCP RPCCW System .s . Establish RCP RPCCW flow flow per OP 3330A RPCCW.
b. RCP seal b. Establish RCP seal injection flow injection flow.

29 Check If RCP Seal Return '

Flow Should Be Established

a. RCS pressure > 115 psia a. Go to Step 30.
b. VCT pressure > 15 psta
c. Open RCP SEAL CTMT ISOLATION valves 30 Control PZR Pressure
a. Turn on heaters a. IF normal spray NOT and operate normal available and letdown spray as necessary is in service, THEN

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to maintain pressure stable use auxiliary spray.

IF NOT, THEN use one PZR PORV. i 31 Verify All AC Busses - Try to restore offsite power.

ENERGIZED BY OFFSITE IF necessary, TREN manually I

POWER load the following equipment on the ac emergency busses

a. Fuel 3uilding Filter System l

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b. Instrument Air

- Compressor B l

. c. Pressurizer Heaters  !

d. RPCCW Pumps ,

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e. Fuel Pool Cooling Pump ,

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f. MCC32-3T and verity Inverter 6 is energized A 68 1 3-44 O P' ,i

i UNCONTROLLED DEPRESSURIZATION E0P 35 ECA-2.1 Page 12 0F ALL STEAM GENERATORS Rev. 2 rh STEP ACTION / EXPECTED RESPONSE a-- RESPONSE NOT OBTAINEO CAUTION

1. If RCP seal cooling had previously been lost, the affected RCP(s) should not be started prior to a status evaluation. 9 NOTE RCPs should be run in order of priority (2, 1, then 3 or 4) to provide normal PZR spray.

32 Check RCP Status - AT Try to start one RCP LEAST ONE RUNNING

a. Establish conditions for starting an RCP. Refer to OP 3301D REACTOR COOLANT PD!P OPERATION
b. Start one RCP. IF an RCP can NOT be started. THEN refer to ATTACHMENT A to verify natural circulation. IF natural circulation NOT verified, THEN increase feed flow or dumping steam.

33 Check If Source Range Detectors Should Be Energized

4. Check intermediate a. Continue with Step 34 range flux < 10E-10 ellen flux < 10E-10 amps, amps TREN do Steps 33 b and c.
b. Verify source b. Manually energize source range detectors - range detectors.

ENERG12ED

c. 1ransfer nuclear recorders to source range scale ONOM-1 3 44

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UNCONTROLLED DEPRESSURIZATION E0P 35 ECA-2.1 Page 13 i 0F ALL STEAM CENERATORS Rev. 2 <

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% ,)$ l STEP ACTION. EXPECTED RESPONSE RESPONSE NOT OBTAINED 34 Check If Diesel Generators Should Be l Stopped

a. Verify ac emergency a. Try to restore of fsite busses - ENERGIZED power to ac emergency BY OFFSITE POWER busses,
b. RESET any LOP, SIS, or CDA signal at MB2
c. Stop any unloaded diesel generator and place in standby
d. RESET Station LOP at both Sequencer panels,
e. RESET, then turn ca each diesel Sequencer Automatic Tester toggle switch.

O f. CLOSE Feeder Breakers

('s) to Emergency Generator Distribution Panels 3EGS*PNLIA at 32-lT-3H and 3EG3*PNLIB at 32-lU-3H.

35 Shutdown Unnecessary Plant Equipment

a. All but one condensate pump
b. All but one cire, water pump per bay
c. Moisture separater drain pumps

- d 4th point heater drain pumps

' ~ ~ ~ ~

36 Maintain Plant Conditions

- S?ABLE

a. PZC pressure
b. PZR level
c. RCS tempe r<.tures oP* M t 3 8e

. UNCONIKOLLZD DEPRESSURIZATION E0P 35 ECA-2.1 Page 14 0F ALL STEAM GENERATORS Rev. 2 (m)wi' STEP ACTION. EXPECTED RESPONSE RESPONSE NOT OSTAINED 37 Verify ECCS Flow Not Required

a. RCS subcooling a. Manually operate ECCS based on core pumps as necessary, exit TCs > 30'F Return to Step 2.

(90'T FOR ADVERSE CONTAINMENT)

b. PZR. level > 7% b. Control charging flow (50% FOR ADVERSE to maintain PZR level.

CONTAINMENT) IF PZR level can NOT be maintained, THEN manually operate ECCS pumps as necessary.

Return to Step 2.

38 Check If SI Accm ulators Should Be Isolated

a. Check the following a. Go to Step 39
1) RCS subcooling based on core exit TCs > 30'F (90'F O FOR ADVERSE CONTAINMENT) l
2) PZR level > 7%

(50% FOR ADVERSE CONTAINMEh"T)

b. Restore power to accumulator isolation valves (32-2R-R5F, 32-2W-R3J.

32-2R-F4M, 32-2W-F4M)

c. CLOSE all Si c. Vent any unisolated accumulator isolation accumulators.

valves I d. Remove power to accumulator isolation valves 39 Check RCS Hot Leg Control feed flow and dump Temperatures < 350'F steam to establish a

cooldown rate < 100*F/RR in RCS cold legs.

l O i OP%X4-1 3-44 i

UNCONTROLLED DEPRESSL'RIZATION E0P 35 ECA-2.1 Page 15 0F ALL STEA'l GENERATORS Rev. 2 V)

STEP ACTHM0 EXPECTED RESPONSE RESPONSE NOT ORTAINED 40 Check RCS Pressure Use normal PZR spray. IF

< 390 psia normal spray NOT available and letdown is in service.

THEN use auxiliary spray.

IF NOT, THEN use one PZR PORV.

41 Check If RHR System Can Be Placed In Cooldown Mode

a. Check the following a. Return to Step 37
1) RCS temperature

< 350*F

2) RCS pressure

< 390 psia

b. Place RHR System in cooldown mode using OP 3208 PLANT C00LDOWh' 42 Continue Cooldown To' Cold Shutdown

[} a. Maintain cooldown

\s / rate in RCS cold legs < 100'F/HR

b. Check narrow range b. Contre feed flow to level in all SGs mainta, narrow range

< 50% level < 50% in all SGs.

43 Check RCS Temperatures AND Return to Step 42.

RVIJtS Head TCs < 200*F 44 Evaluate Long Term Plant Status

a. Maintain cold shutdown condit ions
b. Consult Director of Station Emecgency Organization (DSEO)

-FINAL-O C PK64- 1 3 44

. UNCONTROLLED DEPRESSURIZATIJN OF ALL E0P 35 ECA-2,1 Page 1 of 1 STEAM GENERATORS Rev. 2

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- STEP ACTION EXPECTIO RESPON$t RESPONSE NOT CSTAINED f ATTACHMEh"T A '

The following conditions support or indicate natural circulation flow:

i RCS subcooling based on core exit TCs > 30*F (90*F FOR ADVERSE CONTAINMENT)

SG pressures - STABLE OR DECREASING RCS hot leg temperatures - STABLE OR DECREASING Core exit TCs - STABLE OR DECREASING

  • RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE I

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FOLDOUT FOR E0P 35 ECA-2.I PROCEDURE,

1. SI REINITIATION CRITERIA Manually operate ECCS pumpn es necessary IF_,EITHER condition listed below occurs
a. RCS h,bcooling based on core exit TCs < 30'T (90'T FOR ADVERSE CONTAINMEaT)

-OR-

b. PZR *evel - CAN NOT BE MAINTAINE6 GREATER THAN 7% (50% FOR ADVTRFE CONTAIhMENT)
2. _RE1 PATH

SUMMARY

a. SUBCRITICA11TY - Nuclear power > 5%
b. CORE COOLING - Core exit TCs > 1200*F
c. HEAT SINK - Total AVAILABLE feedwater flow capability < 525 apm
d. INTEGRITY - Cold leg temperature decrease > 100'T in last 60 mintues AR RCS cold leg temperature < 252'T
e. CONTAINMENT - Containment pressure greater than 60 psia
3. E0P 35 E-2 TRANSITION CRITERION Go to E0P 35 E-2 FAULTED STEAM GENERATOR ISOLATION, Step 1. ~IT any SG pressure increases at any time.
4. COLD LEG RECIRCULATION SWITCHOVER CRITERION Co to EOP 35 ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Stc,i 1, IF RWST level decreases to < 520,000 gallons.
5. AIV SUPPLY SWITCHOVER CRITERION Establish the CST alternate UN' water supply IF DWST level detreases to < 80,000 gal.

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