ML19325F247
ML19325F247 | |
Person / Time | |
---|---|
Site: | Crystal River ![]() |
Issue date: | 10/27/1989 |
From: | Bandham W FLORIDA POWER CORP. |
To: | |
References | |
VP-580, NUDOCS 8911170217 | |
Download: ML19325F247 (16) | |
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-DOCVENT TRANSMITTAL FORM 18551
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FOR. DOCUMENTS TRANSMITTED TO DC DESK (NRC)*
r DATE: 30 OCT 1989 BATCH: 180 I
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' DOCUMENT NUMBER SHEET NUMBER REVISION NUMBER COPY NUMBER
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VPi SBO 12 20 -
INSTRUCTIONS TO THE ADDRESSEE .
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' COMPLETE EACH OF THE INSTRUCTIONS BELOW WHICH ARE MARKED WITH AN " X"
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(I) VERIFY THE DOCUMENTS RECEIVED AGREE WITH THE ABOVE DESCRIPTION !
(2) INCORPORATE THE TR ANSMITTED DOCUMENTS INTO YOUR FILES ;
_'(3) DESTROY DOCUMENTS OR PORTIONS OF DOCUMENTS SUPERSEDED BY THE ABOVE ',
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(4) SIGN AND DATE IN THE SPACES BELOW INDICATING THAT YOU COMPLETED '
THESE I NSTR UCT I ONS. [
,,___ (5) SIGN BELOW INDICATING THAT YOU HAVE READ AND UNDERSTOOD THE i
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CHANGES AS IDENTIF IED
- )[_ ( 6 ) RETUR,jN TO DDCUMENT CONTROL, CRYSTAL RIVER UNIT 3, MAC# NA1C NR2A X FLA. P OWER CORP. , P. O. BOX 219 CRYSTAL RIVER FLA. 32629 l SIGNATURE OF ADDRESSEE DATE INDEPENDENT VERIFICATION __
DATE (OP S )
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F ADOCK 0s000302 PDC
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- l- : . PSVP REV 12- DATE 10/27/89 VP-580 i lt
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PLANT SAFETY VERIFICATION PROCEDURE
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- Document Section q N F O R M ATIO N OHl.
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O. R. Nuclear f
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3 This Procedure Addresses Safety Related Components Approved by N05 v C Date /o -42_ Af .
/3 VP 580 REV 12 PAGE 1 of 15 PSVP 4
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..'j.0REACTIVITYCONTROL
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ACTIONS DETAILS -
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sy j 1.1 12 Rx tripped, o Rx trip pushbutton
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IBEN verify Immediate Actions depressed.
of AP-580, Rx Trip,
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! are completed.- o CRD Groups 1 thru 7 are ,
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fully inserted, o Intermediate range' flux
, decreasing, o Turbine trip pushbutton- ,
depressed. -
o TVs or GVs closed.
o " MAIN FW BLOCK"s closed. ;
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o "L0 LOAD FW BLOCK"s closed.
a o PZR level 2 50".
o Steam Hdr PRESS = 1010 psig.
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o Output Bkrs open. .
O A-o Ensure ICS .and NNI power is available.
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1.2 1E Rx is HQI tripped, o RPS setpoint exceeded. !
It!EH observe plant parameters ^
l A!!D determine if Rx should be o PZR level 2 290".
tripped, o 2 or more MSIVs are closed.
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1.3 If Rx should NOT be tripped, J11EH GO TO Step 2.1 in '
this procedure.
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- -i 1.0 REACTIVITY C0NTROL (CONT'D) )
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ACTIONS DETAILS y l ,
5 1.4' Verify IR f1'ux is decreasing.
to. Source' Range. ,
, t IE Neutron flux 'is Refer to EP-140, Emergency
HQI decreasing,. Reactivity Control.
IHEN verify Emergency Boration.
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1.5 Verify 480V Bkrs are closed: ;
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o- Bkr 3305,
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o Bkr 3312.
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1.6 Verify Shutdown Margin is IE in Modes 3, 4, or 5, is 1 1%. JH G refer to SP-421,
, Reactivity Balance Calculations.
IE in Mode 6 (q
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, ItiB verify the requirements of STS 3.9.1 are met. ,
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2.0 THERMAL CONTROL l
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) ACTIONS. DETAILS 2.1- IE RCS PRESS is > 2300 psig, Refer to SPDS AND abnormal or M verify PORV emergency operating procedures :
.QB high point vents in use to determine RCS PRESS
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- , ~ are used to restore limits. .
i RCS' PRESS within limits. ;
o 2,2 1E incores indicate superheated Instrumentation for monitor -
conditions, _ ing RCS inventory: :
M ensure EP-290, Inadequate Core Cooling, o Reactor Coolant Inventory i Tracking System - will be
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is being performed .#
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ANQ monitor RCS inventory. affected by HPI, LPI, or Natural Circulation flow, o Reactor Coolant Pump Void 1 Trend Monitoring System'-
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effective only when RCP(s) are opert. ting. .
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/O 23 lE Adequate subcooling margin Adequate Subcooling Margin .
'\_/ . does liQI exist, .
E verify: RCS PRESS MARGIN
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o Full HPI or LPI flow, > 1500 psig- 2 20*F s
o No RCPs operating, ' s 1500 psig 2 50*F
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o OTSGs at 95%.
o Refer to AP-380, ES Actuation. )
o Refer to AP-360, Loss of -i DHR.
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2.4 IE Subcooling Margin is > 100*F, M verify: -
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o OTSG Feeding Control, o OTSG Steaming Control .
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VP-580 REV 12 PSVP l .
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2.0' THERMAL CONTROL (CONT'D1 /
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.[^ ACTIONS DETAILS
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. ] 2.5 Verify required 0TSG level. P.equired OTSG levels
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lE EFW and MFW is MI fondition level available, - -
IllEH. verify HPI/PORV cooling. Inadequate 95% ;
subcooling margin NO RCPs 65%
and adequate subcooling margin RCPs Low
. and adequate Level subcooling margin Limits l
- l 2.6 lE ADI of the following -
conditions exist: RCS TEMP LIMIT 4 rm Q o RCS is < 500*F.
> 270*F s 100*F/hr Cooldown Rate limits 270'-171*F s 50*F/hr are exceeded .
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s 170*F 1 10*F/hr o RCS is < 500*F, AM HPI flow exists, 6@ RCPs are MI operating, -
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is.being performed. ;
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VP-580 REV 12 PAGE 5 of 15 PSVP
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.h.0*INERNALCONTROL(CDNT'D) ;
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l _ 2.7 IE RCPs are HQI operating, Indications of Nat Circ:
B Itifj verify Nat Circ. q
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o Verify Tc = Tsat of OTSG, j 1E Nat Cire is HQI verified
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AtiQ adequate subcooling o Verify core AT develops and margin exists,. stabilizes.
IllEff refer to AP-530,
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Nat Circ. o Verify incore TEMPS follows f Th within 10*F.
o E[ti OTSG PRESS is lowered, IliEtt verify Tc, incore TEMPS, and Th lower. ;
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l 2.8 1E OTSG Tube Rupture has Refer to EP-390, OTSG Tube i
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occurred, Leak.
IREli verify proper cooldown .
rate.
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A)'v Enclosure 2 contains EFW inventory requirements during a -
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loss of offsite power cooldown to DHR.
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l l 2.9 1E Nat Circ exists, Nat Circ Cooldown Rates IHf3 verify proper Nat Circ
- cooldown rate. RCS Tc 'F/hr 2 280*F 10 L
280 to 150*F 5 1 150*F 2.5 ,
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- Only to be used if RCS PRESS is maintained above Nat Circ ..
cooldown curve. ,
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2.0 THERNAL CONTROL (CONT'D) ,
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i ACTIONS DETAILS
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Due to possible high radiation conditions, Th and Tc .,
indications may become unreliable 24 hrs after a LOCA. {
j 2.10 Verify RCS PRESS and TEMP Observe SPDS Post Trip Display are maintained within limits, for RCS PRESS and Incore TEMP.
IBEH record RCS PRESS and TEMP on Enclosure 1 until' plant is. l stable for = 30 min. .
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' 3.0 RADI0 ACTIVE INVENTORY CONTROL i
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} ACTIONS. DETAILS
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3.1 Observe radiation monitors. If any monitor is in alarm,
, for unexplained trends. IHEN refer to AP-250, Radiation Monitor Actuation.
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3.2 Observe MS radiation monitors IE any MS radiation monitor
for unexplained trends, trend indicatos CTSG 1eakage, ;
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IBIN refer to EP-390, Steam Generator Tube Leak, r :
3.3 ~ Observe for increased RCS o Observe: '
leakage.
o RCP seals and dumpsters, o PZR level, o RCDT level, <
o MUT level, r~'; o RB sump level,
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- o Relief valve tailpipe TEMPS, o Refer to STS 3.4.6.2,
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3.4 Verify fuel integrity. Observe RML-1 Alarms and trends. .
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3.5 Verify MWST level rise is Time MWST Level
< 1%/hr.
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4.0 E0Q1BEHL&M&lL&BIL11Y Li
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a 4.1 Verify 'availibility of borated o MUT. level between -
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water sources for MVPs and DHPs. 30" and.100". .
IE HQI, o BWST level 2 4 ft, ,
IBEN refer to:
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o'If in Modes.l. 2 or 3 AP-380, ES Actuation,-
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Jo If in Modes 4, 5 or 6, AP-360, Loss of DHR. -
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4.2 IE RCS PRESS is < 600 psig, 'l 8HQ adequate subcooling margin .
does 821 exist, i '
IBEN verify CFT level lowers.
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14.3 ' Verify water sources for OTSG o EF Tank 2 15 ft. .
cooling.
(/'",y/ o CST level 2 28 ft. ..
r o Hotwell level at 7 to 9 ft.
(84 to 109").
o See Enclosure 2 for EFW
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requirements.
o See Enclosure 3 for other '
sources of water.
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4.4 Verify SW Cooling. o SW PRESS 2 110 psig. .
1E HOI, o Stable SWP Motor Current IHEH ensure AP-330, .
Loss of SW, is being parformed.
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. 4.0 F'0UIPftENT AVAILABILITY (CONT'D)
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' 4.5 . Verify DC Cooling, if required,
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o Stable DCP motor current. l 1E EI, o Stable discharge PRESS.
ItiEN ensure AP-360,. Loss of DH, is being performed, o DC Heat Exchanger Outlet -
TEMP < 105"F.. -:
.4.6 Verify RW available, o Stable RWP motor current.
O RW AT across DH Seawater p heat exchanger.
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4 7 Verify Instrumentation power o NNI X available.
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o NNI Y
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o ICS 4.8 Verify ES busses are energized, o ES 4160V "A" ,
.,s o ES 4160V "B" s s V o ES 480V "A" -
e ES 480V "B" .
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4.9 Verify Instrument Air pressure o SAP-1A available. o SAP-1B o SAP-lC o SAP-ID o IAP-1A o IAP-1B o SA-4-PI o IA-4-P1
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4.10 Observe RB conditions, o RB TEMP l.
o RB PRESS 'l
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o RB H2 concentration, if available from Chemistry. <
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- $ 4.0 EQUIPMENT AVAILABILITY (CONT'DF ,
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.j cs ACTIONS DETAILS .
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r 4.11 NI-14-nil and NI-15-NII, -
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f neutron flux monitors, may '
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accident conditions, due to .
cable assemblies possibly .:
leaking, e
p 4.12 1E a OTSG tube leak exists, Makeup water can be obtained
&MQ BWST level is s 35 ft, from:
> IBEN notify SSOD to begin makeup to the BWST. o SF pools,
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E o DW and boric acid. ,
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'4.13 1E EFWPs are on minimum o EFW is required when:
recirc, o No RCPs operating, IHEN determine their o Adequate subcooling need to be running. margin does not ,
exist, rT o OTSG Heat Removal does .
() not exist. ,
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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 /> /-
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event 2 EFWPs running - 5 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> /
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Review annunciator :
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'4.14 Review alarm summaries for o unexplained alarms. alarm summary.
1 L o Review computer alarm summary.
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.lA4.0' EQUIPMENT AVAILABILITY fCONT'D)
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.4.15 Verify proper notification are o' Refer to CP-lll, completed.. Documenting, Reporting and .
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Reviewing NCORs.
o Refer to Al-500, Conduct of .:
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Operations. '! .
- o. Refer to EM-202, Duties of the Emerger,cy Coordinator, ,
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4.16 WHiH VP-580 is stopped,- :
i 181H notify SSOD. c
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's VP-580 REV 12 PAGE 12 of 15 PSVP ..
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ENCLOSURE 1 l 1
- RCS Pressure and Temperature Cooldown Limits 1 A 2600 I
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2400 ADEQUATESUBCOOLING/ .)
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MARGIN
2200
-2000
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NDT LIMIT 1800 I H,
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,7 2.2 RCPeg
E 1200 '
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/ SATURATION
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/ < 2 RCPs
} Y} f CURVE f j 400 g y ,
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0 100
\\\\WV 300 500
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700
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RC TEMP ( F)
Acceptable region is below and to the right of the NDT curve.
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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 j
subcooling margin curve.
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ENCLOSVRE 2 4
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.( )L Cooldown Requirements Vs. Nat Circ Cooldown Rates -
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1). FW requirements and the' time to cooldown are controlled primarily s
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by the characteristics of the ADVs and the cut in conditions for .
the DHR system.
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- 2) The time to' cooldown from Rx trip is about 45 hrs. .
- 3) .The'FW requirement to cooldown is about 350,000 gal.
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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)1 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 i utilized. For smaller time delays smaller cooldown rates may, be utilized.
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ENCLOSURE 3 h-s Sources of Emergency Feedwater (EFW) at the Crystal River Site .
{k l' Condensate'- Grade Sources
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p l' ' Source- Volunie (oall-L.
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
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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 c
AB DW Storage Tank, Unit 3 5,000
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