Text

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 i

i 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_'(3) DESTROY DOCUMENTS OR PORTIONS OF DOCUMENTS SUPERSEDED BY THE ABOVE (4) SIGN AND DATE IN THE SPACES BELOW INDICATING THAT YOU COMPLETED THESE I NSTR UCT I ONS.

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(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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ADOCK 0s000302 PDC

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PSVP REV 12-DATE 10/27/89 VP-580 i

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V PLANT SAFETY VERIFICATION PROCEDURE ti

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This Procedure Addresses Safety Related Components Approved by N05 v C Date /o -42_ Af

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'j.0REACTIVITYCONTROL ACTIONS DETAILS

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1.1 12 Rx tripped, o Rx trip pushbutton 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.

9 o "L0 LOAD FW BLOCK"s closed.

a o PZR level 2 50".

o Steam Hdr PRESS = 1010 psig.

c o Output Bkrs open.

O o Ensure ICS.and NNI power A-is available.

1.2 1E Rx is HQI tripped, o

RPS setpoint exceeded.

It!EH observe plant parameters

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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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L 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) f-

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ACTIONS DETAILS y

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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

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ItiB verify the requirements (q

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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

~ 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

is being performed Tracking System - will be 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

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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.

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o Refer to AP-360, Loss of 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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DETAILS ACTIONS

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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

rmQ o RCS is < 500*F.

> 270*F s 100*F/hr AM STS 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) 1

,, 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

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1E Nat Cire is HQI verified 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.

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'v contains EFW inventory requirements during a loss of offsite power cooldown to DHR.

l 2.9 1E Nat Circ exists, Nat Circ Cooldown Rates l

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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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.

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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

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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.

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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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.

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cooling.

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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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ACTIONS DETAILS l

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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" o ES 4160V "B"

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o ES 480V "A" e ES 480V "B" t

I 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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VP-580 REV 12 PAGE 10 of 15 PSVP

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$ 4.0 EQUIPMENT AVAILABILITY (CONT'DF s;

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

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not exist.

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Time EFWPs are on recirc should be limited to:

1 EFWP running - 1 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months /-

event 2 EFWPs running - 5 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months /

event

'4.14 Review alarm summaries for o

Review annunciator unexplained alarms.

alarm summary.

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o Review computer alarm summary.

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.lA4.0' EQUIPMENT AVAILABILITY fCONT'D)

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ACTIONS DETAILS

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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.

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Refer to EM-202, Duties of the Emerger,cy Coordinator, 4.16 WHiH VP-580 is stopped,-

i 181H notify SSOD.

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ENCLOSURE 1 1

RCS Pressure and Temperature Cooldown Limits 1

A 2600

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2400 ADEQUATESUBCOOLING/

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MARGIN

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2200

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-2000 NDT LIMIT 1800 I

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1400

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< 2 RCPs

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100 300 500 700 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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ENCLOSVRE 2 4

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)L Cooldown Requirements Vs. Nat Circ Cooldown Rates -

J 1). FW requirements and the' time to cooldown are controlled primarily by the characteristics of the ADVs and the cut in conditions for s

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 0.00778 hours 4.62963e-5 weeks 1.0654e-5 months 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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c ENCLOSURE 3 h-s Sources of Emergency Feedwater (EFW) at the Crystal River Site

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Condensate'- Grade Sources p

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' 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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ML19325F247

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