ML20214T486
| ML20214T486 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 02/18/1987 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20214T470 | List: |
| References | |
| E.02, E.2, NUDOCS 8706100289 | |
| Download: ML20214T486 (23) | |
Text
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EFFECTIVE DATE 02-18-87 !
Rev. 3 x0 E. 02 i
VITAL SYSTEM STATUS VERIFICATION .
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.O O-B706100289 G70602 PDR ADOCK 05000312 Rev. 3 g PDR E.02-1 i
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.1 INFORMATION PAGE 1.0 REACTIVITY CONTROL -
t 1.1 If any substep (1.1 - 1.4) results in control rod
- insertion and reactor power decreasing, the remaining steps are not necessary.
O 1.4.3 BWS-040 and 054 are Boric Acid Addition valves to the HPI Pumps - Located in the -20 pump alley near the "B" HPI Pump Room door.
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Rev. 3 !
E.02-2 I O
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- VITAL SYSTEM STATUS VERIFICATION CAUTION IF NNI POWER IS IDST, SPDS AND EFIC INSTRUMENTATION SHOULD BE 4
USED TO MONITOR PARAMETERS NOTED IN THIS PROCEDURE. l
- 1. 0 VERIFY REACTOR POWER DECREASING ON '
INTERMEDIATE RANGE AHH ALL SAFETY AND CONTROL RODS AT IN LIMIT -
IF NOT THEN
.1 Push Rx Trip button.
.2 De-energize bus 3B (52-3B05) and 3C2 (52-3C23) for 10 seconds .THEN re-energize both.
O .S e controi rods are siiii not tripped
.IHEE attempt.to drive _ them to the "fuii in" position
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-=----=--^ -
=:--
AHil Manually open CRD breakers in East 480V Switchgear Room.
.4 Borate to a 1% shutdown margin. :
.1 Preferred Method 1
.1 Start Boric Acid Pumps (P-705AacB) and pump to the Makeup Tank.
.2 Marimise makeup / letdown flow to Flash Tank. l j ,
.2 Preferred Method 2
, .1 Start the HPI Pump lined up from the BWST.
.3 Alternate Method
.1 Start Boric Acid Pumps (P-705AacB).
.2 OPEN BWS-040.
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.3 OPEN BWS-054.
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O 1 Reir. 3 E.02-3
?. - - _ . - -- - . - - -. -- - -- - - -- - - - - - -- . . - .--- -
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1 INFORMATION PAGE 2.0 SECONDARY INVENTORY AND PRESSURE CONTROL O
O Rev. 3 E.02-4
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l O e oa VITAL SYSTEM STATUS VERIFICATION CAUTION 2 TURBINE IS NOT TRIPPED .IHEN RO. HOI OPEN GENERATOR BREAKERS 2.0 VERIFY OCBs AND GENERATOR EXCITER BREAKER TRIPPED AND ALL MAIN TURBINE STOP VALVES CLOSED IF NOT THEN
.1 Push Turbine Trip Button.
.2 2 Turbine does HDI trip THEN
.1 Trip EH oil pumps.
- __h_. .2 Run valve position limiters to zero. _ _ , . _ , -
- -- -_L/1 .3 Trip Turbine from front standard. ~~ -- - -
.3 Push Generator Trip Button. -
.4 E Generator does HQI trip THEN
.1 Open Generator OCBs AND Generator Exciter Breaker.
- 3. 0 VERIFY MFW FLOY DECREASING AND FEEDPUMP SPEED RUNNING BACK IF NOT THEN
.1 Manually runback MFW pumps.
.2 Manually control MFW flow with startup feedwater control valves.
.3 2 both MFW pumps are tripped
.THEN O 2 v ' "c **= t= t d "* "= '= ^ "-
l Rev. 3 E.02-5
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INFORMATION PAGE g
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5.1 ADVs setpoint is 1,020 psig 5.2 Below 975 psig Pzr may empty 5.3 .1 EFIC isolates MFY to either or both OTSGs if < S00 psig.
.2 EFIC only isolates AFY to one (1) OTSG.
.3 EFIC automatically resets and refeeds AFW if the pressure or differential pressure which caused the isolation recovers.
O Rev. 3 E.02-6
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O a02 VITAL SYSTEM STATUS VERIFICATION 4.0
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VERIFY BOTH OTSG LEVEIE CONTROLLING AT HR !
l TRENDING TOYARD DESIRED SETPOINT (RULE 4) .
.1 2 either OTSG level is 80% (380" EFIC) M increasing -
)
.IHEN > \J
.1 Run feedpumps to minimum speed. '
.2 Ensure main FW block valves closed. ;
.2 2 either OTSG 1evel is 90% (374" EFIC) M increasing g s x :
.1 Trip one Main Feed Pump. t !
.3 E either OTSG level is 95% (381" EFIC) M increasing THEN >
.1 Trip both MFW pumps. ., ' ,
.2 Verify EFIC has initiated channels A & 7B. i j
.3 Verify EFIC controls OTSG 1evel at the desired -
3'i setpoint. (RULE 4) 5.0 VERIFY 'O'I'SG "A" AND "B" PRESSURE CONTROLLING AT 1,000 PSIG -
IF NOT '
U THEN -
.1 2 pressure is > 1040 psig *
.IHEN verify TBVs/ADVs controlling pressure. , ,
.4
.2 2 pressure is < 975 psig THEN
.1 Check for leaking code safeties.
.1 E any code safeties failed to resent '
.THEN lower OTSG pressure in a CONTROLLED >
mannar to resent valve. -
.2 Verify Aux Steam pressure controlling at setpoint. '; 4 I
.3 Isolate any steam leaks which may be holding pressure low. X' ,
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.3 E EFIC setpoint (800 psig) is reached ','
THEN Q .1 Verify EFIC has initiated channels A & B.
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Rev. 3 '
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INFORMATION PAGE O
. 8.0 .
PRIMARY INVENTORY AND PRESSURE i
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J 7.0, (RULE 2) i .
t 7.1 HPI MAY be throttisd any time SCM is restored 7.2 .
HPI curve SHOULD be throttled to prevent exceedi if SCM is restored.
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1 8.1 Blue and white indicating lignta energized .
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8.3 (RULES 3 & 4) >
1 8.3 .1LOSS OF SCM 8.3 .2 c
8.5 ' '*H.
Level doesn't decrease before .
o ng.
s i i s monhor properly must within 30be st?.rted right away to b minutes.
e functioning 7 , A.05 " Radiation Detection Gaseous System"
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A.52 " Hydrogen Monitor and Purge System" .
-M Rev. 3 f
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VITAL SYSTEM STATUS VERFICATION l i
6.0 VERIFY LETDOWN FLOW AT ~ 40 GPM IF NOT .
.1 Close letdown isolation valve (SFV-22009).
- 7. 0 VERIFY PRESSURIZER LEVEL ~ 100 INCHES IF NOT
[
[ .1 Start HPI pump lined up from BWST. (RULE 2) ,
.2 ' Open Imop A HPI Injection Valve (SFV-23811).
.3 IE Level still cannot be maintained -
.THD[ -
O .1 Open additional HPI injection valves. .
.2 Open the remaining HPI suction valve from- the BYST.
.3 Start the remaining HPI Pump. -
8.0 VERIFY RCS PRESSURE > 1600 PSIG AND RB PRESSURE < 4 PSIG IF NOT '
THEN
.1 Verify SFAS channels 1A,1B M 2A, 2B have actuated.
.2 Close the EMOV block valve (HV-21505).
.3 Verify EFIC has actuated M is controlling 9.3 trending toward the' desired setpoint. (RULES '3 & 4)
IE SCM has been lost THEN select "ECC SETPOINT" on both OTSG level controls.
.4 Verify RCP seal injection and return flow.
.5 Place RB H. Monitors (AE-53811, AE-53812) M R-15100 in service.
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l Rev. 3 E.02-9
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INFORMATION PAGE g l
9.1 Blue and white indicating lights have energized.
9.2 Blinking white light indicates 5 minute timer has started.
10.0 PLANT ELECTRICAL POWER CONTROL 10.1 C.94 for Loss of All AC Powei, C.95 for Loss of Offsite Power.
h 10.3 .1 Continuous flow until OTSG 1evel 31?" EFIC (50%).
10.3 .2 Level doesn't decrease before reaching 317' EFIC (507.).
10.9 C.23 for Diesel Air Compressor.
O Rev. 3 E.02-10
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O E.02 VITAL SYSTEM STATUS VERIFICATION 9.0 VERIFY RB PRESSURE < 30 PSIG ;
l IF NOT THEN
.1 Verify SFAS channels 3A, 3B AND 4A, 4B have actuated.
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.2 Verify RB spray flow after the 5 minute timer times out.
10.0 VERIFY SITE LOADS TRANSFERRED TO STARTUP TRANSFORMF.R WITH 4A, 4A2 AND 4B, 4B2 BUSES ENERGIZED IF NOT ~
THEN
.1 Verify aut.o start of the- diesel . generators. -
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.2 Verify loading of the 4A, 4A2, 4B, .and 4B2 buses.
.3 Verify auto actuation of EFIC.
.4 Verify EFIC control of OTSG 1evel at 317" EFIC (507.).
(RULES 3 & 4)
.5 Verify OTSG pressure control with ADVs.
.6 Ensure RCP seal supply isolation valve closed (SFV-23616).
.7 Restart makeup pump QR HPI pump.
.8 Recover RCP seal injection per OP A.2 Section 7.0.
.9 Verify diesel air compressor supplying IA*.
.10 Verify Nuclear Service Raw Water Pumps start.
O Rev. 3 E.02-11 4
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INFORMATION PAGE h 11.1 NATURAL CIRCULATION
- 1. Tc and OTSG Tsat approximately equal
- 2. Incore temp within 10*F of Th.
- 3. OTSG pressure decrease causes Th, Tc and Incore T/C
. temp decrease.
11.2 (RULES 3 & 4)
- 2. Level doesn't decrease before reaching 317" EFIC (50%). .
- 3. Oscilations of EFIC controls may be seen.
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.O Rev. 3 E.02-12
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E.02 \
VITAL SYSTEM STATUS VERIFICATION !
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1 11.0 CHECK AT LEAST ONE RCP RUNNING l l
IF NOT THEN
.1 Verify Natural Circulation.
.2 Verify EFIC controls OTSG level at _QE trending toward 317" EFIC (507.). (RULES 3 & 4) ,
12.0 VERIFY ALL NNI POWER ON IF NOT THEN
.1 Verify instrumentation YEW Recorder op)erable on SPDS, EFIC, IDADS and (UJR-10104.
- O .2 -Verify ICS power tripped.-
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.3 IMMEDIATELY implement C.15 "Ioss of NNI-X,Y, and/or Z" i IN CONJUNCTION with this procedure.
13.0 VERIFY ALL ICS POWER ON -
IF NOT THEN
.1 Verify both main feed pumps tripped.
.2 Verify EFIC has initiated channels A & B.
.3 Verify TBV closed.
.4 Verify ADV controlling at ~ 1,020 psig.
.5 Verify Aux Steam header is controlling at ~ 250 psig.
.6 WHEN Plant is stable THEN Implement C.40, " loss of ICS Power".
O Reir. 3 E.02-13 1_ - , _ , _
l Q -] . l INFORMATION PAGE 14.0 HEAT TRANSFER UPSETS Typical Loss of Subcooling Trace.
I POST TRIP WNDOW =
/
SATURATION 4 CURVE Y
SUBC 0 @ SECONDARY
- ~
S TURATION TEMPERATURE .
15.0 Typical loss of Heat Transfer Trace.
POST TRIP WINDOW That SATURATION CURVE S OED SECONDARY -
MARGIN SN p SATURATION g
_ TEMPERATURE w Rev. 3 E.02-14
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. VITAL SYSTEM STATUS VERIFICATION 14.0 VERIFY ADEQUATE SUBC00 LING MARGIN EXISTS (GUIDELINE 1)
IF NOT i THEN
.1 Go to E.03, " Loss of SubcooHng".
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i 15.0 VERIFY ADEQUATE -PRIMARY TO SECONDARY HEAT TRANSFER (GUIDELINE 2) ;
IF NOT THEN
.1 Go to E.04, " Loss of Heat Transfer".
Reir. 3 E.02-15
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INFORMATION PAGE h 18.0 Typical Excessive Heat Transfer Trace.
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POST MP WDfDOW SATURATION CURVE VARIABM SUBC00 LED SECONDARY TURATION
_. TmeERA1VRE G
18.0 Typical Pest Trip Normal Trace.
I Icold Y _
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l SAltIRATION
._ _ CURVE VARIABG SUBC00 LED SECONDARY MARGIN -
SWTEM SATURATION A
_._.1TMPERATURE g l
! Rev. 3 i E.02-18
.O -3' E.02 VITAL SYSTEM STATUS VERIFICATION 16.0 VERIFY PRIMARY TO SECONDARY HEAT TRANSFER XQI EXCESSIVE (GUIDELINE 3) l IF NOT THEN
.1 Go to 'E.05, " Excessive Heat Transfer".
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17.0 vERIrY NO SoTR Ex1STS. (cu1DEt1NE --4)-
IF SGTR does exist '
THEN l .1 Go to E.06; "SGTR".
18.0 THE PLANT IS STABLE IN THE POST TRIP WINDOW WITH NO OTSG TUBE LEAK INDICATED l
.1 Refer to Post Trip Check List in B.4 Enclosure 8.1.
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Rev. 3 E.02-17
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l E.02 h SUBC00llNG MARGIN GUIDELINE NO.1 i
EQ.IE There may be many valid indications, besides those provided here, concerning adequate SCM. Do not delay taking appropriate action (E.03) if other indications make it clear that SCM has been lost.
I
! Adequate Subcooling Margin exists when the SPDS That or
- ' Incore Thermocouple data point is above and to the left of the variable subcooling margin curve.
ALTERNATE METHOD - SPDS NOT AVAILABLE
- 1. With any RCPs runnhag, subcooling monitors Indicate greater O~
than 50* subcooling.
. 2. With no RCPs running, RCS pressure and incore thermocouple temperature (Incore thermocouple temperature read from IDADS Incore Temp Display - Coretemp Screen) plot >50*
subcooling or above and to the left of the variable subcooling margin curve.
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l 6 Rev. 3 E.02-18
_ __ _ . _ _ _ . . _ ___n__._.___.._..__ . . _ ..____ _. __ _ __. _
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l O E.02 INADEQUATE PRDLARY TO SECONDARY HEAT TRANSFER GUIDELINE NO. 2 HQ.IE There may be many valid indications, besides those provided here, concerning the adequacy of primary to secondary -heat transfer. Do HQI delay taking appropriate action (E.04) if other indications make it clear that primary to secondary heat transfer is inadequate. .
PREFERRED METHOD - SPDS Inadequate Primary to Secondary Heat Transfer exists when:
RCS temperature is increasing, not stable inside the Post Trip Window; M
Tc and OTSG Tsat are not coupled.
O ALTERNATE METHOD - SPDS NOT AVAIIABLE RCS temperature (as indicated by plant instrumentation) is not stable, and increasing; M
Tc and OTSG Tsat are not coupled.
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l hr. 3 i E.02-19 .
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, E.02 h EXCESSIVE PRIMARY TO SECONDARY HEAT TRANSFER GUIDELINE NO. 3 HQ.H There may be many valid indications, besides those provided here, confirming excessive primary to secondary heat i
transfer. Do not delay taking appropriate action (E.05) if other indications make it clear that the plant is experiencing an excessive primary to secondary heat transfer condition.
PREFFRprn us" RHOD - SPDS Excessive Primary to Secondary Heat Transfer exists when:
2 SPDS indication of RCS temperature and pressure are decreasing, not stable in the Post Trip Window M
OTSG pressun decreasing < 960 psig; OTSG Tsat. decreasing < 540*F. -
- g-i J ALTERNATE us"fMOD - SPDS NOT AVAH.ARLE l
! RCS temperature and pressure (as indicated by plant instrumentation) is decreasing
! M
- OTSG pressure is decreasing < 960 psig.
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Rev. 3 E.02-20 l -
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O 8 oa STEAM GENERATOR TUBE RUPTURE GUIDELINE NO. 4 i
NOTE There may be many valid indications, besides those provided here, confirming an SGTR. Do not delay taking appropriate action (E.06) if other indications make it clear that an SGTR has occurred.
A steam generator tube rupture is indicated by:
- 1. Unidentified RCS leakage exceeding 1 gpm
.AHQ
- 2. Increasing dose rate on Main Steam Line Radiation Monitors, .
i R-15047 R-15048.
! 2R Increasing count rate on the Air Ejector Off Gas Radiation Monitor, R15004.
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I hv. 3 l E.02-21 I
E.02 INADEQUATE CORE COOIJNG I GUIDEllNE NO. 5 i
j NOTE pecause of the severity of an ICC situation and some of the required action under ICC conditions, Operators must be '
especially alert in comparing instruments to establish the exact state of the RCS as accurately as possible.
PREFERRED METHOD - SPDS Inadequate Core Cooling (RCS Superheated) is indicated by:
The Incore T/Cs right of the saturation line on the SPDS Post-Trip Display.
ALTERNATE MFTHOD - SPDS NOT AVAfflRTR The average of the five preferred or alternate incore T/Ca, O as indicated by IDADS' Incore Temp Display - Coretemp Screen, is right of the saturation curve on figure 1, attached.
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Rev. 3 E 02-22
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FIGURE 1 O REACTOR COOLANT SYSTEM INTERIM FRACTURE LIMIT NO FORCED FLOY AND THERMAL SHOCK OPERATING REGION NOTE: Maintaining the reactor ATURLTION 3000- coolant subcooled takes precedence cuaVe over the Interim Brittle Fracture VSM \
Curve (B&Y 74-1122501 page 6) lNOFORCEDF@W \\
2800 OPERATNG QAND INCORE T(Ts TO MONITOR W/HPI w 2600- PREFERRED ALTERNATE m VE
% T9256
- 1) T9254 T9260 0 2400- 2) T9256 -
- 1. 2'-
y 3) T9263 T9252
- NDT N \ ]hg (4 4) T9272 I:L. 2200- 5) T9266 T9266 \ r j! ] )jf Whh T9270 N
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!"""" ,00 >/J'# "
M
- n. ::-
a _.
0'""" '"" P'#d% M
?l,,0 19d%'/ H 2 1000 THERMAL . SHOCK OPERATING REGION f / .
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f 7 7 ,,,,
800 RESTRICTED //// g. ../ /
- REGION /j/j/ j// j .... fj/j n-77//,9'///- ,7 fhh Yf aES.TR1CrED 2 ffj,/ REGION 200 .. .... .... .. V
/
O O 100 200 a00 400 s00 800 700 l l
INDICATED RC TEMPERATURE F l
. Revi 3 END E.02-23
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