ML20248D900
| ML20248D900 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/27/1989 |
| From: | FLORIDA POWER CORP. |
| To: | |
| References | |
| VP-580, NUDOCS 8910050003 | |
| Download: ML20248D900 (16) | |
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." DOCUMENT TRANSMITTAL FORM 16174 FOR DOCUMENTS TRANSMITTED TO DC DESK (NRCH DATE: 26 SEP 1989 BATCH: 142 DOCUMENT NUMBER SHEET NUMBER REVISION NUMBER COPY NUMBER VP 560 11 20 INSTRUCTIONS TO THE ADDRESSEE COMPLETE EACH OF THE INSTRUCTIONS BELOW WHICH ARE MARKED WITH AN " X (1) VERIFY THE DOCUMENTS RECEIVED AGREE WITH THE ABOVE DESCRIPTION a (2) INCORPORATE THE TR ANSMITTED DOCUMENTS INTO YOUR FILES (3) DESTROY DOCUMENTS OR PORTIONS OF DOCUMENTS SUPERSEDED BY THE ABOVE (4) SIGN AND DATE IN THE SPACES BELOW INDICATING THAT YOU COMPLETED THESE INSTRUCTIONS.
(S) SIGN BELOW INDICATING THAT YOU HAVE READ AND UNDERSTOOD THE CHANGES AS IDENTIFIED (6) RETURf TO DOCUMENT CONTROL, CR YSTAL R I VER UNIT 3, MAC# NA2C NR2' _ FLA. P OWER COR P. , P, D. BOX 219 CRYSTAL RIVER FLA. 32629 SIGNATURE OF ADDRESSEE DATE
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INDEPENDENT VERIFICATION DATE ( OP S )
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. PSVP REV 11 DATE 09/20/89 VP-580 0 -
PLANT SAFETY VERIFICATION PROCEDURE 4
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This Procedure Addresses Safety Related Components Approved by NOS OJE bb Date 09 -27 P9 g VP-580 REV 11 PAGE 1 of 15 PSVP
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'. l. 0 REACTIVITY CONTROL-
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ACTIONS DETAILS H
1.1 E Rx tripped, . . .
o Rx trip pushbutton THEN verify Immediate Actions depressed, of AP-580,.Rx Trip,:
ar? completed, o.CRD Groups.1 thru 7 are .
L; fully inserted.
o Intermediate range flux -
decreasing.
o Turbine trip pushbutton depressed.
o TVs or GVs closed.
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o " MAIN FW BLOCK"s closed.
o'"LO LOAD FW BLOCK"s' closed.
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o PZR level 2 50".
o Steam Hdr PRESS = 1010 psig.
o' Output Bkrs open.
o Ensure ICS and NNI power is available.
1.2' E Rx is E I tripped, o RPS setpoint exceeded.
-))iG observe plant parameters a@ determine if Rx should be o PZR level 2 290".
tripped.
o 2 or more MSIVs are closed.
1.3' E Rx should NOT be tripped, THEN GO TO Step 2.1 in this procedure.
.VP-580 REV 11 PAGE 2 of 15 PSVP
_ _ _ _ _ _ - _ _ _ = _ _ _ _ _ _ _ - - _ _
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- .~i.0'REhCTIVITYCONTROLfCONT'D1-ACTIONS DETAILS-V ^[~'f; R, 1
y 11.4. Verify IR flux. is decreasing
. to Source' Range.
IE Neutron flux is Refer to EP-140, Emergency EQI decreasing,- .
Reactivity Control. j e JE M verify Emergency Boration.
1.5 Verify 480V Bkrs are closed:
.o 'Bkr 3305,-
o'. 'Bkr 3312. ;
q 1.6 Verify Shutdown Margin is IE in Modes 3, 4, ' or 5, is 11%. THEN refer to SP-421, Reactivity Balance Calculations. -
Li JE in Mode 6, I
,f g THEN verify the requirements of STS 3.9.1 are met.
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-t VP-580 REV 11 PAGE 3 of 15 PSVP
. - 210 THERNAL' CONTROL
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/ ACTIONS- DETAILS
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' 2.1. IE RCS PRESS is > 2300 psig, Refer to SPDS AND abnormal or.
IH M verify PORY emergency operating procedures QR high point vents in use to determine RCS PRESS .
are used to' restore limits.
RCS-PRESS within limits.,
2.2 IE incores indicate superheated Instrumentation for monitor-conditions, ing RCS inventory:
IBM ensure' EP-290, Inadequate Core Cooling, o Reactor Coolant Inventory -
is being performed- Tracking System - will be AND monitor RCS inventory. affected by HPI, LPI, or Natural Circulation flow.
o Reactor Coolant Pump Void Trend Monitoring System.-
effective only when RCP(s) are operating.
p 2.31 1E Adequate subcoolirig margin Adequate Subcooling Margin
'd' does NOT exist, IE W verify: RCS PRESS MARGIN o Full HPI or LPI flow, > 1500 psig i 20*F o No RCPs operating, s 1500 psig 2 50*F o OTSGs at 95%.
o Refer to AP-380,
, ES Actuation.
o Refer to AP-360, Loss of DHR.
C 2.4 JE Subcooling Margin is > 100*F, IBM verify:
o HPI and LPI Control, o.'OTSG Feeding Control, !
1 o OTSG Steaming Control. 1 i
Q VP-580 REV 11 PAGE 4 of 15 PSVP l
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. 2.'O THERMAL CONTROL (CONT'D)
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ACTIONS DETAILS
. (v) l 2.5 Verify HPI flows are balanced.
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2.6 Verify required 0TSG level. Required 0TSG 1evels If EFW and MFW is NOT Condition Level available, THEN verify HPI/PORV cooling. Inadequate 95%
subcooling margin NO RCPs 65%
and adequate subcooling margin RCPs Low and adequate Level subcooling margin Limits
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<- 2.7 If any of the following I conditions exist: RCS TEMP LIMIT .
o RCS is < 500*F. > 270*F 1 100*F/hr AND STS Cooldown Rate limits -
270*-171*F s 50*F/hr are exceeded 1 170*F 1 10*F/hr o RCS is < 500'F, AND HPI flow exists, AND RCPs are NOT operating, THEN ensure EP-220, PTS, is being performed.
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1-2.0 -
THERMAL CONTROL (CONT'D) .
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' ACTIONS DETAILS 2.8 ' E RCPs are NOT operating, Indications of Nat Circ:
THEN verify Nat Circ.
o Verify Tc = Tsat of OTSG. .
E Nat Circ is @I verified a @ adequate subcooling o Verify core AT develops and margin' exists, . stabilizes.
lHfH refer to AP-530, Nat Circ. o Verify incore TEMPS follows Th within 10*F.
o M OTSG PRESS is lowered, IEN verify Tc, incore TEMPS, and Th lower.
2.9 - E OTSG Tube Rupture has Refer to EP-390, OTSG Tube occurred, Leak. -
IEN verify proper cooldoen rate.
O Enclosure 2 contains EFW inventory requirements during a loss of offsite power cooldown to DHR.
2.10 E Nat Cire exists, Nat Circ Cooldown Rates It!EN verify proper Nat Circ L cooldown rate. RCS Tc 'F/hr 1 280*F 10 280 to 150*F 5 5 150'F 2.5
- 50
- Only to be used if RCS PRESS is maintained above Nat Circ cooldown curve.
'v VP-580 REV 11 PAGE 6 of 15 PSVP
2.0 THERMAL CONTROL (CONT'D)
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ACTIONS DETAILS Note
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Due to possible high radiation co'nditions, Th and Tc indications may become unreliable 24 hrs after a LOCA.
2.11 Verify RCS PRESS and TEMP Observe SPDS Post Trip Display are maintained within limits. for RCS PRESS and Incore TEMP.
If SPDS is NOT operable, THEN record RCS PRESS and TEMP on Enclosure 1 until plant is stable for = 30 min.
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--} VP-580 REV 11 PAGE 7 of 15 PSVP
3.0 RADI0 ACTIVE INVENTORY CONTROL-
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.v ACTIONS DETAILS 3.1 Observe radiation monitors IE any monitor is in alarm, for unexplained trends. JHEN refer to AP-250, Radiation Monitor Actuation.
I 3.2 Observe MS radiation monitors. .1E any MS radiation monitor-l for unexplained trends. trend indicates OTSG. leakage,
! IH_fM refer.to EP-390, Steam Generator Tube Leak.
3.3 Observe for increased RCS o Observe:
leakage.
o Refer to STS 3.4.6.2, Operational Leakage.
3.4 Verify fuel integrity. Observe RML-1 Alarms and trends.
.3. 5 Verify MWST level rise is Time MWST Level -
< 1%/hr.
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VP-580 REV 11 PAGE 8 of 15 PSVP j
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4.0 EQUIPMENT AVAILABILITY w ..
(( l' R ' \J ACTIONS DETAILS-
'L ' T4ii Verify availability of borated o MUT level between water sources for MUPs and DHPs. 30" and 100".
- 3. - .
- 1E HQI, o. BWST level 2 4 ft.
IHfH refer to:
o If in Modes 1, 2 or 3, An 380, ES Actuation, o If in Modes 4, 5 or 6,
" AP-360, Loss of DHR.
r .4'2 If RCS PRESS is <'600 psig, o ANQ. adequate subcooling margin-does HQI exist, (
IHEN verify CFT level lowers.- N 4.3 Verify water sources for OTSG o EF Tank 1 15 ft.
js c cooling.
, (,,). o CST 3evel 1 28 ft.
o Hotdelifl evel at 7 to 9' ft.
(84 to 109").
o See Enclosure 2 for EFW requirements.
o See Enclosure 3 for other sources of water.
4.4 Verify SW Cooling. o SW PRESS 2 110 psig.
e if NOT, o Stable SWP Motor Current IEEN ensure AP-330, Loss of SW, is being performed.
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"a i 4'0 EQUIPMENT AVAILABILITY'(CONT'D)
ACTIONS Q[IA11$
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4.5 Verify DC Cooling, if required. o Stable DCP motor current.
)) NOT, o Stable discharge PRESS.
..THEN ensure AP-360, Loss of .
DH, is being performed, o DC Heat Exchanger Outlet TEMP < 105'F.
o RW AT across DH Seawater heat exchanger.-
4.7 Verify Instrumentation power o NNI X available.
o NNI Y o ICS.
4.8 Verify ES busses are energized. o ES 4160V "A" t'~ o ES 4160V "B" (s)} o ES 480V "A" o ES 480V "B" 4.9 Verify Instrument Air pressure o SAP-1A available. o SAP-1B o SAP-1C o SAP-ID o IAP-1A o IAP-1B o SA-4-PI o IA-4-PI i j 4.10 Observe RB conditions. o RB TEMP o RB PRESS o RB H2 concentration, if available from Chemistry.
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p oik.0 EQUIPMENT' AVAILABILITY (CONT'D)-
Is e ACTIONS' DETAILS
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l 4.11 - NI-14-nil and NI-15-NII,-
neutron flux monitors, may not be reliable under 7
accident conditions, due to -
cable assemblies possibly leaking.
l 4.12 lE a OTSG tube leak exists, Makeup water can be obtained MQ BWST level is 135 ft, from:
It!EN notify SSOD to begin makeup to the BWST. o SF pools, o 'DW and boric acid.
. l 4.13 IE EFWPs are on minimum o EFW is required when:
recire, o No RCPs operating, I!iEN determine their o Adequate subcooling need to be running. margin does'not exist, Is o OTSG Heat Removal does 4
+w not exist.
N o ' Time EFWPs are on recirc should be limited to:
1 EFWP running - 1 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> /
event 2 EFWPs~ running - 1 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> /
event
' l 4.14 Review alarm summaries for o Review annunciator unexplained alarms. alarm summary. --
o Review computer alarm summary.
O VP-580 REV 11 PAGE 11 of 15 PSVP
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- 4 h EQUIPMENT-AVAILABILITY (CONT'Di
,%. ACTIONS DETAILS L 4
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, l L4.15/ Verify proper notification are o Refer to CP-111, completed. . ' Documenting, Reporting and Reviewing NCORs.
o Refer to AI-500, Conduct'of Operations.
< o ; Refer to EM-202, Duties of the: Emergency Coordinator.
l 4.16 E!!EN VP-580 is. stopped, I!!1H notify SS00.
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VP-580' REV 11 PAGE 12 of 15 PSVP
, ENCLOSURE 1 RCS Pressure and Temperature Cooldown Limits 2400 '
ADEQUATE SU'J dOOLING MARGIN -
j 2000 -
NDT LIMIT 1800
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1600
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1400 l ,
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E'S 1200 jj 1000 V /
,, OPERATING .
iREGION q t 4r800 I SATURATION j
< 2 RCPs CURVE 1 600 l f P 1 400 g
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0 100
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RC TEMP ( F)
Acceptable region is below and to the right of the NDT curve.
Acceptable region is above and to the left of the applicable Fuel Pin in Compression curve.
Acceptable region is above and to the left of the adequate subcooling margin curve.
VP-580 REV 11 PAGE 13 of 15 PSVP l
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ENCLOSURE 2 1 ;. ;
Cooldown Requirements Vs. Nat Circ Cooldown Rates
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- 1) FW requirements and the time to cooldown are controlled primarily by the characteristics of the ADVs and the cut-in.. conditions for !
the DHR system. j
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- 2) The time to cooldown from Rx trip is about 45' hrs.
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- 3) The FW requirement to cooldown is about 350,000 gal.
~ ~4) The minimum cooldown rate consistent with the above minimum time
-and FW requirements is about 8.5'F/hr.
. 5), Cooldown rates in excess _of 8.5'F/hr do not decrease the FW or time requirements for cooldown.
'6) Cooldown rates less than 8.5*F/hr increase both the FW and the time requirements for cooldown. .
- 7) '.A _ time delay'of 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> from Rx trip will not significantly affect FW or time requirements if a cooldown rate of 50*F/hr is then utilized. For smaller time delays smaller cooldown rates may be utilized.
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- ENCLOSURE 3 )
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Sources of Emergency Feedwater (EFW) at the Crystal River Site N,] j condensate - Grade Sources Source Volume (aal) ]
Dedicated EFW Tank (EFT-2) 150,000 Condensate Storage Tank 139,000 Condenser Hotwells 150,000 l DW Storage Tank, Unit 3 450,000 DW Storage Tank, Unit 1 147,000 DW Storage Tank, Unit 2 147,000 DW Storage Tank, Unit 4/5 500,000 CD Storage Tank, Unit 4 500,000 CD Storage Tank, Unit 5 500,000 AB DW Storage Tank, Unit 3 5,000
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