ML19325F247

Rev 12 to Plant Safety Verification Procedure VP-580

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 FOR. DOCUMENTS TRANSMITTED TO DC DESK (NRC)*

r DATE: 30 OCT 1989 BATCH: 180 I

' DOCUMENT NUMBER SHEET NUMBER REVISION NUMBER COPY NUMBER

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VPi SBO 12 20 -

INSTRUCTIONS TO THE ADDRESSEE .

' COMPLETE EACH OF THE INSTRUCTIONS BELOW WHICH ARE MARKED WITH AN " X" (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_'(3) DESTROY DOCUMENTS OR PORTIONS OF DOCUMENTS SUPERSEDED BY THE ABOVE ',

(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 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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• l- : . PSVP REV 12- DATE 10/27/89 VP-580 i lt f

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PLANT SAFETY VERIFICATION PROCEDURE ti

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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 -

sy j 1.1 12 Rx tripped, o Rx trip pushbutton

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l; IBEN verify Immediate Actions depressed.

of AP-580, Rx Trip,

! are completed.- o CRD Groups 1 thru 7 are ,

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.

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.

l o All MFW is lost 215% FP.

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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.

1.5 Verify 480V Bkrs are closed:  ;

o- Bkr 3305, o Bkr 3312.

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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( , g 1 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

, ~ 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 is being performed .#

ANQ monitor RCS inventory. affected by HPI, LPI, or Natural Circulation flow, o Reactor Coolant Pump Void 1 Trend Monitoring System'-

effective only when RCP(s) are opert. ting. .

/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 o OTSGs at 95%.

o Refer to AP-380, ES Actuation. )

o Refer to AP-360, Loss of -i DHR.

2.4 IE Subcooling Margin is > 100*F, M verify: -

o HPI and LPI Control, o OTSG Feeding Control, o OTSG Steaming Control .

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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 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.

AM STS

> 270*F s 100*F/hr Cooldown Rate limits 270'-171*F s 50*F/hr are exceeded .

s 170*F 1 10*F/hr o RCS is < 500*F, AM HPI flow exists, 6@ RCPs are MI operating, -

IllEH ensure EP-220, PTS, is.being performed.  ;

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.h.0*INERNALCONTROL(CDNT'D)  ;

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, , r'~T ACTIONS DETAILS l

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l _ 2.7 IE RCPs are HQI operating, Indications of Nat Circ:

B Itifj verify Nat Circ. q 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, 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.  ;

l 2.8 1E OTSG Tube Rupture has Refer to EP-390, OTSG Tube i occurred, Leak.

IREli verify proper cooldown .

rate.

8 E9U A)'v Enclosure 2 contains EFW inventory requirements during a -

loss of offsite power cooldown to DHR.

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 ,

• 50

• 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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Hals 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.

IE SPDS is HQI operable, '

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 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,  ;

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, 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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4.0 E0Q1BEHL&M&lL&BIL11Y Li

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.: } ACTIONS DETAILS

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a 4.1 Verify 'availibility of borated o MUT. level between -

water sources for MVPs and DHPs. 30" and.100". .

IE HQI, o BWST level 2 4 ft, ,

IBEN refer to:

o'If in Modes.l. 2 or 3 AP-380, ES Actuation,-

Jo If in Modes 4, 5 or 6, AP-360, Loss of DHR. -

4.2 IE RCS PRESS is < 600 psig, 'l 8HQ adequate subcooling margin .

does 821 exist, i '

IBEN verify CFT level lowers.

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 requirements.

o See Enclosure 3 for other '

sources of water.

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, 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.

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" ,

.,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 4.10 Observe RB conditions, o RB TEMP l.

o RB PRESS 'l 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, -

f neutron flux monitors, may '

i not be reliable under .

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, E

o DW and boric acid. ,

'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. ,

I 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 - 5 1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> /

event Review annunciator  :

'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)

L. ACTIONS DETAILS -l

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.4.15 Verify proper notification are o' Refer to CP-lll, completed.. Documenting, Reporting and .

Reviewing NCORs.

o Refer to Al-500, Conduct of .:

F Operations. '! .

- o. Refer to EM-202, Duties of the Emerger,cy Coordinator, ,

4.16 WHiH VP-580 is stopped,-  :

i 181H notify SSOD. c C

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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

/ // H NDT LIMIT 1800 I H,

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1400

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,7 2.2 RCPeg E 1200 '

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c' ' " ,, / Gr ^Y /

/ SATURATION

/ < 2 RCPs

} Y} f CURVE f j 400 g y ,

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0 100

\\\\WV 300 500 700 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 j

subcooling margin curve.

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e . j, 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

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.

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 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 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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