ML20155H562
| ML20155H562 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco, 05000000 |
| Issue date: | 07/12/1985 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| Shared Package | |
| ML20155H523 | List: |
| References | |
| RTR-NUREG-1195 E.02, E.2, NUDOCS 8605160280 | |
| Download: ML20155H562 (10) | |
Text
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j gt, EFFECTIVE DATE e
07-12-85 Rev. 1 i
WP0002F D-0058P l
E.02 VITAL SYSTEM STATUS VERIFICATION c3 Verification Column Action Column, VERIFY THE FOLLOWING:
IF VERIFICATION CANNOT BE MADE. PERFORM THE FOLLOWING:
1.0 ALL SAFETY AND
. Borate to a 1% shutdown margin.
CONTROL RODS AT IN LIMIT
/
2.0 REACTOR POWER a.
Push Rx Trip button on H1RC.
tj DECREASING ON b.
At Panel H2ES deenergize bus 3B
- INTERMEDIATE
" (52.-3B05) and 3C2 (52-3C23) at the,
RANGE same time. T[EE af ter 10 sec delay, reenergize bus 3B and 3C2.
c.
Start HPI Pump taking suction from BNST; stop makeup pump.
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d.
Maximize letdown flow to flash tank.
e.
Manually open CRD breakers in East 480V switchgear room.
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i 8605160280 860306 PDR ADOCK 0500 2
6 Rev. 1 E.02-1 i
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V E.02 A
VITAL SYSTE STATUS VERIFICATION b
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Verification Column
' Action Column a
s VERIFY THE FOLLOWING:
IF VERIFICATION CANNOT BE MADE. PERFORM
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THE FOLLOWING:
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3.0 AT LEAST.ONE RCP a.
Verify Natural Circulation RUNNING 1.
OTSG T,,g approximately the same as T,.
2.
Lovering OTSG pressure causes a corresponding decrease in T, and T #i""*****
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Incore temp within 10*F of T
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b.
Verify AFW flow.
Rule 4 4.0 MAIN FEEDWATER a.
Take manual control and shut main FLOW AND feedwater control valve.
FEEDPUMR SPEED b.
Take manual control of startup i
RUNNING BACK feedwater control. valve and attempt to control feedwater flow.
c.
At 82.5% on OP Range, run feedpumps j
hack to minimum speed and ensure Main J
'i Block Valves are closed.
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.d.
At 90% on OP Range, trip one Main Feed j
Pump.
1 1
1 5.0 BOTH OTSG Trip both runnin'g MFW pumps 8HD. verify 1
i LEVEL < 95%
AFW Starts.
l ON OP RANGE AND Verify AFW valves shut to the affected DECREASING
. OTSG(s) until level returns to normal.
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E.02 l
VITAL SYSTEM STATUS VERIFICATION
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VERIFY'THE FOLLOWING:
IF VERIFICATION CANNOT BE MADE. PERf_QRH THE FOLLOWING:
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6.0 ALL MAIN. TURBINE Push Turbine Trip and Generator Trip button STOP VALVES SRUT on HISS.
If,the turbine does not trip, a.
Run valve position limiter to zero and trip turbine from the front standard.
l b.
Trip EH oil pumps.
[
7.0 OCBs AND GENERA-(QQ H9I open breakers if turbine is not 1-TOR EXCITER tripped.)
Verify Turbine tripped 3232[
BREAKER TRIPPED push Generator Trip button.
IE: breakers do not open, manually open the*generatoc OCBs &EQ generator exciter breaker.
8.0 SITE LOADS a.
Verify auto start.of:the diesel'
. TRANSFERRED TO-generators &HR loading of-the 4A and STARTUP TRANS-4B buses.
3 j
FORMER WITH 4A AND 4B BUSES b.
Verify auto start of AFW &MQ raise SG
]
ENERGIZED level to 50% on the OP Range, with'AFW I
properly throttled.
(See Specific 1
q Rule 3.)
c.
Ensure Seal Supply Isolation Valve.
SFV-23616 is closed.
Restart an HPI
- or Makeup Pump.
Recover RCP Seal 3
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Injection per OP A.2, Section 7.0.
Rev. 1 E.02-3
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r E.02
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VITAL SYSTEM STATUS VERIFICATION
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h Verification Column Action Column VERIFY THE FOLLOWING:
IF VERIFICATION CANNOT BE MADE. PERPORN THE FOLLOWING:
- j d
8.0 (Continued)_
Verify SAS and IAS in service, if not, d.
start diesel air compressor and refer i
to C.23, Loss of Plant Air System as necessary.
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e.
Verify Nuclear Service Raw Water pumps i
j start.
f.
Verify OTSG pressure control with ADVs.
^
9.0 LETDOWN FLOW AT Close letdown bypass and orifice block 40 GPN valves (HV-22010 and HV-220ll) at Panel H1RC.
- i 10.0 PRESSURIZER.
Start HPI Pump lined up to BWST and open i
LEVEL Loop A HPI injection valve (SFV-23811).
100 INCHES i
a l
11.0 RCS PRESSURE
. a)
Verify HPI, LPI, and RB isolation and 4
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GREATER THAN cooling channels (lA and 18 &lE 2A and j
1600 PSIG AHD, 2B) have actuated by noting the colors RB PRESSURE of components' indicating lamps on the LESS THAN H2SF panel.
4 PSIG b)
Close the EMOV block valve (HV-21505).
Rev. 0 7
Rev. 1 E.02-4 y
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3 E.02 VITAL SYSTEM STATUS VERIFICATION f.}.
i u-j Verification Column Action Column i:
VERIFY THE FOLLOWING:
IF VERIFICATION CANNOT BE MADE. PERFORM THE FOLLOWING:
11.0 (Continued) c)
Verify AFW starts M maintain appropriate OTSG level.
(See' Specific Rules 3 and 4.)
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d)
Close AFW Bypass Valves SFV-20577 and SFV-20578.
Verify AFW flow on FI-31802 and FI-31902 on H2PS.
R AFW
. flow is not observed, control flow by
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throttling AFW. Bypass Valves SFV-20577 s
and SFV-20578.
E AFW control valves FV-20527 and FV-20528 operate, M q
close AFW bypass valves SFV-20577 and 20578 83, control AFW flow with the (l
AFW control valves. OTHERWISE throttle rt l1 AFW bypass valves to. control AFW flow.
4
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Verify RCP seal injection flow at ElRC.
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12.0 RB PRESSURE a)
Verify that RB spray pumps M, spray
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LESS THAN 30 PSIG valves-(Channels 3A'and 3B & B,4A and, d
4B) have actuated.
b)
Verify'RB spray flow subsequent to the li 5 min time delay.
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E.02 VITAL SYSTkN STATUS VERIFICATION i
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Verification Column Action Column VERIFY THE FOLLOWING:
IF VERIFICATION CANNOT BE MADE.' PERFORM THE FOLLOWING:
13.0 OTSG "A" AND Verify:
"B" PRESSURE GREATER THAN "A" SIDE LOW PRESSURE 435 PSIG j
.a)
Verify MFW Block Valve,(FV-20529) l closed.
b)
Stop any AFW flow to "A" OT3G.
l c)
Verif.y no MFW flow at H1RI.
f "B"
SIDE LOW PRESSURE i
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a)
Verify MFW Block Valve (FV-20530) i c1'osed:
b)
Stop any AFW flow to "B" OTSG.
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c)
Verify no MFW flow at H1RI.
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14.0 ALL NNI Refer to C Procedures for Loss of NNI
- j POWER ON power.
r 15.0 ADEQUATE Go to Loss of Subcooling E.03.
l.
SUBCOOLING MARGIN' EXISTS REFER GUIDELINE 1
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?b.
Rev. 1 E.02-6 i
j lu E.02 VITAL SYSTEM STATUS VERIFICATION Ds
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Verification Column-Action Column 1
VERIFY THE FOLLOWING:
IF VERIFICATION CANNOT BE MADE. PERFORM l
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THE FOLLOWING:
E 16.0 ADEQUATE PRIMARY Go to Loss of Heat Transf*er E.04.
'TO SECONDARY
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HEAT TRANSFER EXISTS REFER GUIDELINE 2 I
l 17.0 PRIMARY TO Go to Excessive Heat Transfer E.05.
SECONDARY HEAT TRANSFER IS l
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NOT EXCESSIVE
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l REFER GUIDELINE 3 18.0 NO~ INDICATION Go to SGTR E.06.
j OF A SGTR ON MAIN STEAM LINE OR AIR EJECTOR OFF GAS OR GLAND STEAM i
RADIATION j
MONITOR 19.0 THE PLANT IS STABLE IN A, SAFE SUBCOOLED CONDITION WITH $ ROPER PRIMARY TO SECONDARY HEAT TRANSFER AND NO MAJOR PRIMARY
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BOUNDARY FAILURES.
FURTHER ACTION AT THIS POINT WILL BE AT THE' DISCRETION OF STATION MANAG$, MENT.
Rev. 1 E.02-7 i
E.02 4
SUBC00 LING MARGIN J
GUIDELINE No. 1
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1.
Adequate Subcooling Margin exists when the SPDS T hot Incore Thermocouple data point is above and to the left of the i
variable subcoo' ling margin curve.
OR v
a.
If both SPDS displays are not_available and at least one RCP is_. sunning:
Subcooling monitors indicate gre'ater than 50* subcooling.
b.
If both SPDS displays are not available and no RCPs are running:
RCS pressure and incore thermocouple temperature (average of five highest) plot >50* subcooling or above and to the left,of th'e variable subcooling margin curve.
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Rev. 1.
l E.02-8 a
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E.02 INADEQUATE PRIMARY TO SECONDARY HEAT TRANSFER GUIDELINE No. 2 2.
Inadequate Primary to Secondary Heat Transfer a.
Primary Method j
SPDS:
RCS temperature is increasing, not stable f
inside the Post Trip Nindow t
and t
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T, and OTSG T,,g are not coupled.
k T, and CTSG T,,g should be approximately equal and tracking together
>j (coupled).
6 P.
b.
Secondary Method (both SPDS displays are not available)
I i
Use plant instrumentation to determine the following:
j RCS temperature increasing
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and T, and oTSG T,,, are not coupled.
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Rev. 1 E.02-9
b E.02 1
-EXCESSIVE PRIMARY TO SECONDARY HEAT TRANSFER f
GUIDELINE No. 3
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4 3.
Excessive Primary to Secondary Heat Transfer a.
Primary Method SPDS':
RCS temperature and pressure decreasing, not stable in the Post Trip Window I
c j
and l
j.
OTSG pressure decreasing (<960 psig) or
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OTSG T,,g decreasing (<540*F).
f a
f b.
Secondary Method (both SPDS displays are not available) 3 i
i Use' plant indication to determine the following:
'RCS temperature and pressure decreasing
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and' OTSG pressure decreasing (<960 psig).
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Rev. 1 D
E.02-10 J
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