ML20205C524
| ML20205C524 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 12/13/1985 |
| From: | CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | |
| Shared Package | |
| ML20204H467 | List:
|
| References | |
| EOP-35-FR-H.1, NUDOCS 8810260520 | |
| Download: ML20205C524 (14) | |
Text
- _ _ - _ _ _ _ _ _ _ _ _ _ _ _
u E. J. Mroc: .
- 2-1-85 Fcre Apprcved by Station Sup;rint:ndent Effective Date
~
STATION PROCEDURE COVER SHEET A. IDENTIFICATION Number E0P 35 FR-H.1 Rev. 1 Title RESPONSE TO LOSS OF SECONDARY HEAT SINK Prepared By R. McGowan B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT HEAD /.2 C. UNREVIEWEDSAFETYQUESTIONEVALUATIONDOCUMENTATIONREQUkRED:
(Significant ch*nge in procedure method or scope YES [ ] NO t>{
as described in FSAR)
(If yes, document in PORC/SORC meeting minutes)
ENVIRONMENTAL IMPACT (Adverse environmental impact) YES [ ] NO(N3 (If yes, document in PORC/SORC meeting minutes)
D. INTEGRATED SAFETY REVIEW REQUIRED 1 (Affects response of Safety Systems, performance YES [ ] NO bd' of safety-related control systems or performance of control systems which may indirectly affect safety system response.)
(If yes, document in PORC/SORC meeting minutes.)
E. PROCEDURE REQUIRES M ORC REVIEW YES.1<] NO [ ]
F. b 60RC)SORCAPPROVAL h 0RC Meeting Number 3 ~ f3 5 ' M Y G. APPROVAL AND IMPLEMENTATION The atsached procedure is hereby approved, and effective on the date below:
^?N Station /Sdvice/UnitSuperinfndent V l1 - l]W Effective Date SF 301 8910260520 001007 Rev. 7 hDR ADOCK o 3 Page 1 of 1
EOP 35 FR-H.1 Page 1
- Rev. 1 RfSPONSE TO LOSS OF SECONDARY HEAT SINK Page No. Eff. Rev.
1-12 1 d
C O
l O
RESPONSE TO LOSS OF SECONDARY HEAT SINK E0P 35 FR-H.1 Pega 2 Rev. 1 Y../
A. PURPOSE This procedure provides actions to respond to a loss of secondary heat sink in all steam generators.
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 evaluation to determine if the required action is still applicable to current plant conditions.
This procedure is entered from:
- 1) E0P 35 E-0, REACTOR TRIP OR SAFETY INJECTION, Step 17, when .
minimum AFW flow is not verified. .
- 2) E0P 35 F-0.3, HEAT SINK Critical Safety Function Status Tree on a RED condition, f~
'N u no, ,, .
RESPONSE TO LOSS OF SECONDARY HEAT SINK E0P 35 FR-H.1 Pest 3 Rev. 1 C. -
STEP ACTION /EEPECTED RESPONet RESPONet NOT OSTAINEO CAUTION
- 1. If E0P 35 ECA-2.1, UNCONTROLLED DEPRESSURIZATION OF ALL STEAM GENERATORS, is in effect and total feed flow is less than 525 spo due to operator action, this procedure should not be performed.
- 2. If WR level in any 3 SG(s) is LESS THAN 39% (54% for l adverse containment) OR PZR pressure is greater than I
or equal to 2350 psia due to loss of secondary heat l sink, RCPs should be tripped and Steps 10 through 16 should be immediately initiated for bleed and feed.
1 Check If Secondary Heat Sink Is Required O a. RCS pressure - GREATER THAN ANY NON-FAULTED SG PRESSURE
- a. Go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.
- b. RCS temperature - b. Try to place RHR System GREATER THAN 350*F in service while (350*F FOR ADVERSE continuing in this CONTAINMENT) procedure. Refer to OP 3310A RESIDUAL HEAT REMOVAL. IF adequate cooling with RHR System established, THEN return to procedure and step in effect.
O OPS 0041 344
O RESPONSE TO LOSS OF SECONDARY HEAT SINK E0P 35 FR-H.1 Page 4 Rev. 1 STEP ACTHWEXPECTED RESPONSE RESPONSE NOT 09TMNED 2 Try To Establish AFW Flow
. To At least One SG
- a. Check control room indications for cause of AFW failure 1
- 1) DWST level
- 2) AFW pump power supply
- 3) AIV valve alignment
- b. Try to restore AFW flow
- c. Check total flow to c. Dispatch .:perator to SGs - GREATER THAN locally restore AIV 525 GPM flow. Go to Step 3.
- d. Return to procedure .
i and step in effect 3 STOP All RCPs 4 Check Charging Pump Status - Go to Step 10.
4 AT LEAST ONE RUNNING WITH FLOW TO RX VESSEL i
CAUTION l
i If offsite power is lost after SI reset, manual
- action say be required to restart safeguards equipment.
l I
i
)
a t
!O opsoes.1 1-44
RESPONSE TO LOSS OF SECONDARY HEAT SINK E0P 35 FR-H.1 Paga 5 Rev. 1
- erap Actiowaxpeciso neaponsa nespoNea NOT oSTAINEO 5 Try To Establish Main W Flow To At least One SG
- a. Check Condensate System - a. Try to place Condensate IN SERVICE System in service. IFF i NOT, THEN go to Step 9.
- b. Check W isolation valves - OPEN
- b. Perform the following:
- 1) IF SI has occurred
{}
TEEN RESET SI and momentarily pull
[
Universal Logic Card A213 from both trains I of the solid state protection system.
- 2) Reset W Isostion ,
- 3) RESET and OPEN W Isolation valves. IF no W isolation vale can be opened, THEN go to Step 9.
- 4) IF SI has occurred, THEN replace Universal Logic Card A213 in both trains of the solid state protection system.
- c. Establish Main W c. Go to Step 7.
flow l 1) CLOSE A(B) SGFP
! Discharge Isolstion 3WS-MOV23C/B
- 2) dTART MDW Pump
- 3) OPEN Steam Generator Feed Isolation valves
- 4) CLOSE Steam Generator Feed Control Isolation Valves
- 5) Maintain Steam Generator levels with Bypass Level Control Valves CP50ss-1 344
e .
RESPONSE TO LOSS OF SECONDARY HEAT SINK E0P 35 Ek-H.1 Pent 6 '
Rev. 1 l
O -
STEP ACTION /EEPECTIO RESPONSE RESPONSE NOT OSTAINEO 6 Check SG Levels
- a. Narrow range level in a. IF feed flow to at least.
at least one SG - one SG verified, THEN l GREATER THAN 4% maintain flow to l (34% FOR ADVERSE restore narrow range CONTAINMENT) level to greater than l
i 4% (34% for adverse containment). IF NOT l verified THEN go to Step 7.
- b. Return to procedure and step in effect 1
CAUTION .
l Following block of automatic SI actuation, manual SI actuation may be required if conditions degrade.
l 7 Try To Establish Feed l Flow From condensate l System
- a. At least one Condensate a. 1) START one l Pump running Condensate Pump.
l IF one Condensate
! Emp can not be '
g started, THEN go to Step 9.
- b. Depressurize RCS to less than 1950 psia
- 1) Check letdown IN 1) Use one PZR PORV.
SERVICE E NOT, THEN use auxiliary spray. Go to Step 7b3.
- 2) Use auxiliary spray 2) Use one PZR PORV.
- 3) Turn off all PZR heaters O
oPSO4441 344
[l * , ,
RESPONSE TO LOSS OF SECONDARY KEAT SINK E0P 35 FR-H.1 Pago 7 -
Rev. 1
,-~
kx -
STEP ACTION /EEPECTED RESPONSE RESPONSE NOT OSTAINEO
- c. Block SI signals
- 1) Low Steamline Pressure SI
- d. Depressurize at least one SG to less than 575 psig
- 1) Dump steam to 1) Manually dump steam :
! condenser at from SGs to t maximum rate atmosphere i IF NOT, THEN go to Step 9. t
- e. Establish condensate e. 1) Locgily OPEN SGFP i flow OP 3319A CONDENSATE Bypass Valve [
SYSTEM '
- 1) OPEN A(B) SGFP Discharge 2) Go to Step 9 Isolation 3FWS-MOV23C/B i
- 2) Maintain Steam Generator O Levels with Bypass Level Control Valves i
8 Check SG Levels !
, a. Narrow range level in a. IF feed flow to at ,
at least one SG - least one SG verified, GREATER THAN 4% THEN maintain flow to (34% FOR ADVERSE restore narrow range CONTAINMENT) level to greater than 1 4% (34% for adverse containment). IF NOT
~
verified, THEN go to Step l
- 9. l
- b. Return to procedure i and step in effect ,
r 9 Check For Loss Of l Secondary Heat Sink '
is LESS THAN 39% (54% [
FOR ADVERSE CONTAINMENT) ;
OR PZR pressure is GREATER
, THAN OR EQUAL to 2350 OSIA l
f f
OPSM&1 144 L
RESPONSE TO LOSS OF SECONDARY HEAT SINK E0P 35 FR-H.1 Peas 8 Rev. 1 O -
STEP ACTWM/EXPECTRO RESPONGE RESPONSE NOT OSTAINED CAUTION Steps 10 through 16 must be performed quickly in order to establish RCS heat removal by RCS bleed and feed.
10 Actuate SI 11 Verify RCS Feed Path Manually start pimps and
- a. Check pump status align valves as necessary 1
- 1) Charging pumps - to establish feed path. IF AT LEAST ONE a feed path can NOT be ,
RUNNING established..TKEN continue attempts to establish feed flow. Return to Step 5.
-OR-
- 2) SI pumps - AT LEAST ONE RUNNING
- b. Check for normal valve alignment for operating pumps at ESF Status Panel - PROPER EMERGENCY ALIGNMENT l
l 12 Reset SI 13 Reset Containment Isolation Phase A And Phase B 14 Instrument Air to Containment Establish instrument air to
- ESTABLISHED containment,
- a. One instrument air compressor - RUNNING.
- b. OPEN instrument air containment isolation valves 15 Establish RCS Bleed Path
- a. Verify PZR PORV a. Open block valves, block valves -
ALL OPEN
() b. Open both PZR PORVs OPS 0ss 1 Fa4
O RESPONSE TO LOSS OF SECONDARY HEAT SINK E0P 35 FR-H.1 Pegs 9 Rev. 1
- etsp Actiowszpecteo neapowea neapowse NOT OSTAINEo 16 Verify Adequate RCS Bleed Path
- a. PZR PORVs - BOTH a. Perform the following OPEN
- 1) OPEN Reactor Vessel Head Vents to the PRT
- 2) Depressurize at least one intact SG to atmospheric pressure using atmospheric dumps.
. 3) Align any available low pressure water source to the
- depgessurized SG(s).
17 Maintain RCS Heat Removal
- a. Maintain SI flow
- b. Maintain PZR PORVs -
BOTH OPEN CAUTION If RWST level decreases to less than 520,000 gal, the ECCS systems should te aligned for cold les recirculation using E0P 35 ES-1.3 TRANSFER TO COLD LEG RECIRCULATION.
18 Continue Attempts To Establish Secondary Heat Sink In At least One SG .
- a. AFW flow
- b. Main FW flow
- c. Condensate flow 19 Check For Adequate Secondary Heat Sink
- a. Narrow range level a. Return to Step 18.
in at least one SG - GREATER THAN O 4% (34% FOR ADVERSE CONTAINMENT) orw.$i 344
RESPONSE TO LOSS OF SECONDARY HEAT SINK E0P 35 FR-H.1 Pega 10 Rev. 1 f )
'd -
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 20 Check RCS Temperatures Return to Step 18.
- a. Core exit TCs -
DECREASING
- b. RCS hot leg temperatures -
DECREASING NOTE
- 1. After stopping any ECCS pump, RCS pressure should be allowed to stabilize before stopping another ECCS pump.
21 Check If One Charging Pump Should Be Stopped
- a. Two charging pumps - a. Go to Step 22.
RUNNING r^' b. Determine required i RCS subcooling from s~
table:
SI PUMP STATUS RCS SUBC00 LING (*F)
NORMAL ADVERSE NONE RUNNING 103*F 195'F ONE RUNNING 59'F 157'F TWO RUNNING 55'F 153'F
GREATER THAN REQUIRED SUBC00 LING
- d. PZR level - GREATER d. DO NOT STOP CHARGING THAN 7% (50% FCR PUMP. Go to Step 24.
ADVERSE CONTAINMENT)
- e. STOP one charging pump p
V CPK6&1 2-44
, . I RESPONSE TO LOSS OF SECONDARY KEAT SINK"' E0P 35 FR-H.1 Pegs 11 !
Rev. 1 '
f
- STEP ACTION /tXPECTED RESPONSE RESPON88 NOT OSTAINSO ;
22 Check If One SI Pump Should Be Stopped
- a. ,Any SI pump - a. Go to Step 23.
RUNNING
- b. Determine required RCS subcooling from table:
I RCS SUBCOOLING (*F)
SI PUMP STATUS ONE CHARGING PUMP RUNNING NO CHARGING PUMP RUNNING ONE NORMAL ADVERSE NORMAL ADVERSE ,
RUNNING 154*F 239'T --------- --------- l TWO
- RUNNING 47'T 136*F 64*F . 160*F i
based on core exit Go to Step 24. '
TCs - GREATER THAN REQUIRED SUBC00 LING
() d. PZR level - GREATER TRAN 7% (50% FOR
- d. DO NOT STOP SI PUdP.
Go to Step 24.
ADVERSE CONTAINMENT)
- e. STOP one additional SI pump
- f. Return to Step 22a 23 Check If Normal Charging Should Be Established
- a. Check the following a. Return to Step 21.
- 1) Both SI pumps -
STOPPED
- 2) Charging pumps -
ALL BUT ONE STOPPED
GREATER TRAN 30*F (94*F FOR ADVERSE C0hTAINMENT O
OPMeG1 >44
i e .
RESPONSE TO LOSS OF SECONDARY HEAT SINK E0P 35 FR-H.1 Pogs 12 Rev. 1 4
O -
STEP ACTNH6/SIPECTRO RESPONSE mesPONSE NOT OSTAH080
- c. PZR level - GREATER c. Go to Step 24 THAN 7% (50% FOR ADVERSE CONTAINMENT)
- d. Go to Step 25 NOTE Af ter closing a PZR PORV, it may be necessary to wait for RCS pressure to increase to permit stopping SI pumps in Steps 21 and 22.
24 Check PZR PORY Status
- b. Close one PZR PORV b. Close its PORV block valve. IF block valve 1 can NOT Ee closed, THEN go to E0P 35 E-1, LOSS OF REACTOR OR SECONDARY d
- c. Return to Step 21 25 Establish Normal Charging
]
Flow a
26 CLOSE Charging Pump
] to Reactor cold less isolation valve.
4 27 Check PZR PORVs - ALL Close PZR PCRVs. IF any l CLOSED valve can NOT be closed, THEN manually close its block
, valve.
5 28 Control Charging Flow To Maintain PZR Level i 29 Go To E0P 35 ES-1.1, SI TERMINATION, Step 11
, -FINAL-t 4
l 0
OPMe&1 344
. . _ _ _ _ _ . _ _ . , . . _ _ . - . _ , - , _ , __ _ _ _ , _ . . _ _ _ _ _ _ , _ _ _ _ _ . . _ , . , , _ _ , _ , _ . . _ ., y ,
l ffk Fora C;/bvio 8f itaph ~5wperintenoint 2 -/ f(
Eftsctive Date STAT!cN #R0tt0V#t C# F08M CHAN06 m - A. 10ENTIFICAT!cN PROCEDURE OR FORM NutastR _ EOP 3 5 FR-H.1 Rtv. O CHAN;t NO. /
(Circle One)
PROCrouet OR FORM TITLE LOSS OF HEAT SINK (Circle One)
INITIAftD By B. CHANat INSERT the following in step 5.b. RESPONSE NOT OBTAINED
- b. Verify TW Isolation valves - CLOSED
- c. Verify SG Blowdown Sample Isolations - CLOSED CHANGE b. to d. and ADD "at MB2 and MB5" to the end of "RESET FWI" RENUMBER remaining steps in 5.b.
C. Atas0N tea twAN0t To ensure FWI Isolation valves are closed prior to restoring from TWI.
D. NON !NTENT CHANOt AUTHOR!!ATION (N/A for Intent Changes)
TITLE 51cNATcet CATE SMf t Sweeeviser (en duty) ,1, O- t, afvitwto
} Oepartment Head .s=
fy (
Unreviewed Safety Question tvalwation Documentation Reouired; (5tgaificant cnange in procecure setnoo or scope as Gescribed in FSAR) ( ) Yt$ (A)NO (If yes, document in PORC/50RC setting sinutes)
. (Nytt0No.tNTAL IMPACT (Acuerse environmental tocact) ( ) Yt1 (ar)NO (If yes, cocument in PORC/50RC meeting sinwtes)
F. INT [ceATfD SArriv etvitw atculato (Affects response of Safety Systees, performance ( ) Yt3 Dd NO i of safety *related control systees or performance of control systees which say indirectly affect 2
safety systee response.)
(If yes, socument in PORC/50RC meeting minutes.)
l G. htC Rtcos*OO5 APPROVAL (or confirmation of interia change within 14 days)
@aC meeting nunnor 3-1P22(
H. APPROVAL AND 1M8(tm(NT AT!0N The change is hereby implemented and is ef fective this date, encept for interim 3
changes whiCh were imple#ented and effecdve per the Awthoritation of 0 above.
- OOg _m -
9-\ s -aco
( 5taucyr ,erintenoenvunit s ,erinten ent cate 5r m tev, 7 i
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