ML20034C785
| ML20034C785 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/25/1990 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20034C092 | List: |
| References | |
| AOP-EP-Q, NUDOCS 9005100051 | |
| Download: ML20034C785 (8) | |
Text
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TITLE:
STEAM LEAK OR INADVERTL4T LIFTING OF STEAM RELIEF VALVE.
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SIEAM LEAK CR INADVERl[M[_(1FTING Of STEAM RELIEF VALVE SYMPTOM-ACTION MATRIX l
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l SYMPTDMS i
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IUnexpected LesslUnusual Moise lBoth " Steam 1" Steam Leak De-l 4
N-ACTIONS Than Normal IOr Visual ILeak Detection itect60n Systes"I Steam Pressure IObservation l System" Alarms IHigh T f=pe ra-l l
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11-05B, 2-6 AND lture Ala rm l
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18-05C, 2-6 I
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location of the leak.
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Isolate.the' leak, XX XX l XX XX l l XX Kr.
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Ensure main turbine l
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.._ t IO RAISE PRESSURE Alt 0/OR TEMPERATURE'INSfDE A N M - THIS EMERGENCY PROCEDURE DEALS Wlill LEAKS L'ARCE ENOUCil BUILDING OR OBSTRUCT VISIBILI TY AROUND,"QUIPMENT OR PASSAGE 'IAYS.'
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I AOP-EP Q Issue 57 - Last Page 3 of as 3
(Q)
STEAM LEAK OR INADVERTINI LIFTING OF STEAM RELIEF VALVE SYMPTOM-ACTION MATRIX 4
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SYMPTOMS 1
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1.1 ll 1.2 l-1.3 1.4
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l Unexpected Less Unusual Noise IBoth " Steam
" Steam Leak De-l ACTIONS lihan Normal Or Visual ILeak Detection tection System"!
Steam Pressure. Observation ISystem" Alarms -lHigh Tempera-1 in Any Steam i
18-05B. 2-6 AND= lture Alarm l
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wi thin one ( 1 ) - hour a f ter l ll
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G' Tills EMERGENCY PROCEDURE DEALS Wlill l EAKS E ARGE ENOUGH 10 RAISE PRESSURE AND/OR ' TEMPERATURE INSIDE A.
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STEAM LEAK OR INADVEfLTEMT LIFTING OF STF.8N REllEF VALVE SYMPTOM-ACilON MATRIX 1-l 1
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ACTIONS IThan Normai Or Visuai I Leak Detection itection System"l ISteam Pressttre 1; Observation System" Ala rms lHigh Tempera-I' I
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If active core cooling i
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NOTE; BUILDING OR.OBS1RUCT VIStBill1Y AROUND EQUIPMENT OR PASSAGE WAYS.
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AOP-EP APP Q
- Issue 57 - Last 0Public FORT ST. VRAIN NUCLEAR GENERATING STATIO@ age l' of ~ 3 E
$0rVIC9' PusuC ssRVICs COMPANY OF COLORADO ~
O INTRODUCTION This emergency procedure deals with leaks which are large enough to raise the temperature of either building up to and including actuation of the Steam Line Rupture Detection / Isolation System (SLRDIS). Emergency Procedure B-1 provides instructions for main steam pressure low (<1500 psig), reheat pressure low (<35 psig),:and reactor building temperature high (>175'F) all of which could be due to a steam leak. This emergency procedure provides immediate and follow-up actions for a SLRDIS trip and directs'to Safe Shutdown.
Cooling Procedures for recovery, if unsuccessful then to EP-G, Loss CP Forced Cooling.
DISCUSSION OF SYMPTOMS 1.1 Unexpected, less Than Normal Steam pressure In Any Steam Header.
1 Lower then-normal steam pressure could indicate a sizeable leak somewhere, i
1 1.2 Unusual Noise Or Visual Observation.
Cortinued unusual noise could be a steam leak or a steam leak could be observed during. regular rounds.
j 1.3 Both " Steam Leak Detection System" Alarms, -I-05C, 2-6 AND-I-05C, 2-6.
j Each of the SLRDIS panels (I-93543 and I-93544) monitors i
temperature and the rate of ~ temperature rise in the turbine Nilding and the reactor building.. Temperature trips an. initiated at a fixed setpoint prior to the analyzed value of 180 F.
Rate of rise trips are initated-l prior to the analyzed value of 55 F per minute.
If-BOTH panels have at.least two of the four fixed temperature i
channels OR two of tha four. rate of rise channels tripped, the reactor will scram on two loop trouble, all four helium circulators trip (steam and water), both secondary i
coolant loops isolate, the main. turbine trips immediately, and forty-four valves shut to isolate the leak.
j 1.4
" Steam Leak Detection System" High Temperature Alarm.
Setpoint of 135'F would indicate area of actual high temperature.
O FORM (D)372 22 3643
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AOP-EP APP Q' f
' Issue 57 - Last OPublic FORT ST VRAIN NUCLEAR CENERATING STATIONPage 2 of 3 Service *
- PUBUC SERWCE COMPhNY OF COLORADO DISCUSSION OF OPERATOR ACTION 2.1 Dispatch an operator to investigate source and location of the leak.
i An investigation is required to locate,the source of the leak for eventual corrective action.-
2.2 Isolate leak including loop isolation-if'necessary.
A steam leak of the size covered by this procedure would create a hazard in adaition to representir.g a sizeable loss of secondary coolant.
2.3 IF leak is not isolatable AND constitutes a hazard, THEN shut down the affected system.
Repair is necessary for a sizable leak.
j 2.4' Verify reactor scran red on Two ' oop Trouble, ensure u
appropriate immediate actions ot'A0P-EP B.
Actuation of both SLRDIS panels scrams the. reactor on two-loop. trouble due to both loops being shutdown.
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2.5 Verify both secondary cooling loops' shutdown and isolated.
Actuation of both SLRDIS panels isolates both secondary
. 1 cooling loops to help isolate rupture. Verify'with.
qualified instruments; SI-2109, SI-2110, 51-2115,:51-2116, FR-2205, and FR-2206.
2.6 Ensure main turbine tripped and appropriate immediate j
actions of A0P-EP F-1.
Actuation of both SLRDIS panels isolates all steam to the main turbine causing immediate turbine trip tnrough Four y
Circulator Trip Circuitry.
4 2.7 Verify leak isolated.
If not, shut off "B" BFP.
If the actuation of the SLRDIS system does not isolate the leak, the most likely source capable of actuating the
~
i system is "B" Boiler Feed Pump. Qualified isolation is by closing HV-3109 and HV-31119.
2,8 Followup action will vary with magnitude and location of leak. The Shift Supervisor will decide the followup action.
Each leak will need to be acted on as conditions dictate.
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FoRMID)J/2 22 3643 e
/
-AOP-EP APP Q
/
!ssue 57 ~Last
./
A Public FORT ST. VRAIN NUCLEAR GENERATING STATIONPage 3 of 3-
7
%F Service
- Pusue senvece COMPANY OF COLORADO 2.9 Proceed to Emergency Operating Procedures-for recovery from 10FC.
The Emergency Operating Procedures (EOP) will identify the steps needed to restore forced cooling within 90 minutes.
2.10 Insert Reserve Shutdown ~ material in all 37 regions within=
one (1) hour af ter reactor building temperature is
- onfirmed to be 150 degrees F or higher.
Insertion of reserve shutdown material is necessary due'to the CRD'In-Limit lights, analog and digital indications not being environmentally' qualified. The'one hour time is-
.]
based on Interim Technical Specification LCO 3.1.4 j
Action B.
This requirement is to be deleted if the CRD indications are qualified in the future.
2.11 Notify the Technical Advisor as soca as possible upon
{
actuation of the SLRDIS system.
Because an LOFC has taken place, and a high energy line break existed, the Technical Advisor shall be contacted to ensure his availability if needed for core ~ heat
=
calculations, j
2.12 If active core cooling cannot be established within 1 1/2 hours, proceed to A0P-EP G.
E The tables of EP G determine how long is allowed for; re-establishing core cooling following'the LOFC.
If.these times are exceeded ( 1 h hours, worst case) the operators-must follow the Loss of Core Cooling Emergency Procedure.
O FORM (D)372 22 3H3 F
Public
' FORT ST. VRAIN NUCLEAR GENERATING STATION
. h
$grylCO' PusuC SERVICE COMPANY OF COLORADO 04/19/90
- x' O
EMERGENCY OPERATING PROCEDURES ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE l
E0P-UG EmergencyOperatingProcedures-User s Guide 1
06-29-89
-l E0P-CSFM
. Critical Safety Function Monitoring i
Procedure 3
08-09-89 l E0P-1 Restoration of Reactivity Critical l
Safety Function 3
04-19-90 E0P-2 Restoration of Secondary Coolant Critical Safety-Function 3
08-09 -i E0P-3 Restoration. of Primary Coolant Critical Safety Function 3
08-09-89 E0P-4 Restoration of PCRV Integrity Critical Safety Function 3
08-09-89 1
I E0P-5 Restoration'of Radioactive Release-
]
Critical Safety Function 3
08-09 !
E0P-6 Restoration of Essential Electric Power
'3 08-09-89 l
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l FORM (D)372 22 3643 t,
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