ML20091L281

Rev 19 to VP-580, Plant Safety Verification Procedure

ML20091L281
Person / Time
Site:	Crystal River
Issue date:	12/16/1991
From:	Marshall W FLORIDA POWER CORP.
To:
References
VP-580, NUDOCS 9201270343
Download: ML20091L281 (18)

Text

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DOCUENT TRANSMITTAL FORM 63752 FOR DOCUENTS TRANSMITTED TO DC DESK (NRC)*

DATE: 17 DEC 1991 DATCH:

100 DOCUMENT NUMBER SHEET NUMDER REVISION NUNDER COPY NUMDER VP SBO 19 20 INSTRUCTIONS TO THE ADDRESSEE

___ ~____ __ ____ __

COMPLETE EACH OF THE ' INSTRUCTIONS DELOW WHICH ARE MARKED WITH AN " X"

,,,X,,,. (1 )~ VERIFY THE DOCUMENTS RECEIVED AGREE WITH THE ADOVE DESCRIPTION

_X,,, ( 2 ) INCORPORATE THE TR ANSMITTED DOCUMENTS INTO YOUR FILES

_X,(3) DESTROY. DOCUMENTS OR PORTIONS OF DOCUMENTS SUPCRSEDED BY THE ADOVE

_X,,,, ( 4 ) SIGN AND DATE' IN THE SPACES.DELOW INDICATING THAT YOU COMPLETED THESE INSTRUCTIONS.

(S) SIGN BELOW INDICATING THAT YOU HAVE READ AND UNDERSTOOD THE CHANGES AS ' IDENTIFIED

_X _ ( 6 ).- R E T N TO DOCUMENT CONTROL, CRYSTAL RIVER UNIT 3, MACtt NA1C,___

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NR2A, S A 10__.,

FLORIDA POWER C(A P., P. D.

DOX 219 CRYSTAL' RIVER Fi 6 '

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SIONATURE OF ADDRESEEE DATE

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VP-580 REV 19 PAGE 1 of 17 PSVP iimeii--

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la_J[ACJJVITY CONTROL

,Q A[TLORS DETAlls 1.1 1[ Rx tripped, o CRD Groups 1 thru 7 are fL'.ly lh[B verify Immediate Actions inserted.

of AP 580, Rx Trip, are completed o Intermediate range flux decreasing.

o TVs or GVs closed, o " MAIN FW BLOCK"s closed.

o "LO LOAD FW BLOCK"s closed, o PZR level 1 50".

o Steah Hdr PRESS = 1010 psig.

o Output Bkrs open.

o Ensure ICS and NNI power is available.

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1.2 1[ Rx is NOT tripped, o RPS setpoint exceeded.

1116 observe plant parameters aHD determine if Rx should be o PZR level 2 290".

tripped, o 2 or more MSIVs are closed.

o All MFW is lost 1 15% fP.

o 2 or more CRDM stator TEMPS 2 160*F o

I < 1 ft. and level cannot be restored, o SW flow is lost and cannot be

restored, o PZR level cannot be maintained

> 100* during SGTR with HPl.

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VP-580 REV 19 PAGE 2 of 17 PSVP

1.'0 REACT 1.VITY CSHIRQL.KONT'01 ACTIONS DETAllS 1.3 E Rx should NOT be tripped, IRUi GO TO Step 2.1 in this procedure.

!!Q1f NI-14 Nil and NI-15-N!!, neutron flux monitors, may not be reliable under accident conditions, due to cable assemblies possibly leaking.

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1.4 Verify IR flux is decreasing to Source Range.

E Neutron flux is Refer to EP-140, Emergency dQI decreasing, Reactivity Control.

IdQi verify Emergency Boration.

1.5 Verify 480V Bkrs are closed:

o Bkr 3305, o Bkr 3312.

1.6 E any s'afety or regulating o H 1 control rod is stuck, control rod is NOT fully THEN refer to OP-103C, turve 18

inserted, IdQi verify boron o E > 1 control rod is stuck, requirements to ensure THEN continue boration until

> 1% thutdown margin.

either of the following:

o Actual boron concentration

> 1925 ppmB On o Actual boron concentration

> value determined by the Reactor Engineer or his designee.

O VP 580 REV 19 PAGE 3 of 17 PSVP m

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LO TilERMAL CONTROL

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ACIIONS RETAlLS 2.1 E RX is tripped P.efer to SPDS eM abnormal or 6M RCS PRESS is > 2400 psig, emergency operating procedures 111Lt{ verify PORV in use to determino RCS PRESS QB high point vents are

limits, used to restore RCS PRESS within limits.

2.2 E inceres indicate swerheated instrumentation for monitoring conditions, RCS inventory:

111E1] verify EP 290, inadequate Core Cooling, o Reactor Coolant Inventory 1:; being performed Tracking System - will be affQ monitor RCS inventory, aff2cted by HPI, LPI, or Natural Circulation flow.

o Reactor Coolant Pump Void Trend Monitoring System -

effective only when RCP(s) are operating.

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2.3 E Adequate subcooling margin Tsat Monitor does M1 exist, Adequate Subcooling Margin Ji[W serify:

o Full HPl or.LPI flow, Reactor Coolant MARGIN o No RCPs operating,

> 1500 psig 30er

.o OTSGs at 95%,

s 1500 to > 250 psig 50*F 5 250 to > 150 psig 70*F s 150 psig SPDS s 200'F N/A o Refer to AP 380, ES Actuation.

t Refer to AP 360, Loss of DHR.

Od VP-580 REV 19 PAGE 4 of 17 PSVP

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ACTIONS DETAILS 2.4 jf Subcooling Margin is > 100'F, THEN verify operation in accordance with abnormal and emergency operating procedure in use:

o HPI o LPI o MFW, EFW, EFIL o OTSG PRESS and level t

E912 1E HPl flow is 2 200 gpm for any nozzle, as indicated on tne narrow range HP1 flow instrument, lHEU use the wide range HPl flow instrument for that nozzle on ES Section of the Main Control Board.

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2.5 Vtrify available HPI flows are A._,

balanced.

2.6 Verify required OTSG level.

Required 0TSG levels if EFW and MFW is NOT Condition Level available, 181U verify HPl/PORV cooling.

Inadequate 95%

subcooling margin NO RCPs 65%

and adequate subcooling margin RCPs Low and adequate level subcooling margin Limits IE OTSG Tube leak exists,

&RQ adequate subcooling margin does HQI exist, 882 2 2 liPI pumps are available,

'(~~N In[8 verify affected OTSG is HQ1 A,)

being fed.

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'VP 580 REN 19 PAGE 5 of 17 PSVP

t 2.'O THERMALCphl@l iCONT!D)

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DETAILS 2.7 1[ Any of the following STS cooldown rate limits:

conditions exist:

o RCPs @l operating,-

RCS TEMP 'F RALE LIM T 6@ HPl flow exists throu:.h any nozzle while

280 1 50'F % hr RCS IEMP is < 500*F.

280 to 151 L 25'F 4 hr o STS cooldown rate limits exceeded while RCS TEMP i 150 s 10*f/hr is < 380'F.

IB[N verify EP-220, PTS, is being performed.

2.8 IE RCPs are MI operating, Indications of Nat Circ:

JJiG verify Nat Circ.

o Verify Tc = Tsat of 0150.

1[ Nat Circ is El verified a[1Q adequate subcooling o Verify core AT develops and (N

margin exists, staSilizes.

V) lilB refer to AP 530, Nat Circ.

o verify incore TEMPS follows Th within 10'F.

o M G OTSG PRESS is lowered, IUW verify Tc, incore TEMPS, and Th lower.

2.9 11 OTSG Tube Rupture has Refer to EP-390, 01SG Tube Leak,

occurred, JEM verify proper cooldown

rate, r

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NJ l-l VP-580 REV 19 PAGE 6 of 17 PSVP e

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ACTIO!iS QLTAILS v

eel 2 contoins EfW inventory requirements during a loss of of fsite powar cooldown to DHR.

2.10 if Nat Cire exists, Nat Circ Cooldown Rates 1H[N verify proper Nat Circ cooldown rate.

RCS Tc

'f/hr 2 290*f 10 280 to 150*f 5

s 150*f 2.5 50 Only to be used if P.CS PRESS is maintained above Nat Circ conidown curve.

Note Due to possible high radiation conditions, Th and Tc indications may become unreliable 24 hrs after a LOCA.

2.11 Verify RCS PRESS and TEMP Observe SPDS Post Trip Display for are maintained within limits.

RCS PRESS and incore TEMP.

1[ SPDS is UQT operable, THEff record RCS PRESS and TEMP on until plant is stable for = 30 min.

1[ unexplain6d and significant RC pressure decrease exists, THEN ensure proper operation cf:

o RCV-10, PORV o RCV-14, PZR Spray Valve o PZR Heaters (3

U VP-580 REV 19 PAGE 7 of 17 PSVP

,, 60 THERMAL CONTROL (CONT!D.1 (a)

ACllE!6 D.UAlll 2,12 If adequate subcooling OP 404, Decay Heat Removal System, margin does not exist, Section 4.13, Long Term Post-

)

A!!Q RCS pressure s 200 psig.

Accident Cooling.

lud verify boron precipitation actions are complete within 1.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of cvent.

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1 VP-580 REV 19 PAGE 8 of 17 PSVP

1.'O RADI0 ACTIVE _ MYIMTORY CONT _ROL i)

ACT10f45 DETAILS-3.1 Observe radiation monitors 1[ any monitor is in alarm, for unexplained trends.

1118 refer to AP-250, Radiation Monitor Actuation.

' 3.2 OL'srve MS radiation monitors IE any MS radiation monitor trend for unexplained trends.

indicates OTSG leakage, IDG refer to EP-390, Steam Generator Tube Leak.

3.3 Observe for increased RCS o Observe:

leakage.

o RCP seals and dumpsters, o PZR level, o RCDT level, o MUT level, b

o RB sump level, 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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Lv VP-580 REV 19 PAGE 9 of 17 PSVP

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DETA!LS 4.1 Verify availability of borated o MUT level between 30" and 100".

.o't water. sources for MVPs and DHPs.

i o BWSi level 2 4 ft.

1E Hal, IUfB refer to:

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o if in Modes 1, 2 or 3.

AP-380. ES Actuation, o If in Hades 4, 5 or 6, AP-360,-Loss of DHR.

4.2 If RCS PRESS-is < 600 psig AND adequate subcooling margin does UQI exist.

In[H verify CTT level lowers.

4.3 Verify water sources for OTSG o Ef Tank 2 15 ft.

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o CST level 2 5 ft.

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.

l 4.4 Verify SW Cooling.

o SW PRESS 1 110 psig, l

l 1[ SQI, o Stable SWP Motor Current L

lulu ensure AP-330, Loss of SW, is being performed.

fLJ VP 580-REV 19 PAGE 10 of 17 PSVP

LO E041PMENT AVAllARILIILICEpJ e

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ACTIONS DETAlls 4.5 Verify DC Cooling, if required.

o Stable DCP motor current.

11 t{QI, o Stable discharge PRESS.

1H[H 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 heat exchanger.

4,7 Verify Instrumentation power o NNI X available, o NNI Y o

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4.8 Verify ES bu ses are energized.

o ES 4160V "A" o ES 4160V "B" s

o ES 480V "A" o ES 480V-"B" 4.9 If offsite power is 80,1 lE within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> offsite power available, has HDI been restored, 6HQ offsite power will UDI be AND 2 EDGs are running restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, JB1H not3fy the S500 to:

IBIN verify EDG operation is within fuel oil consumption o Order additional fuel oil for limits and fuel oil reserves emergency delivery within next are adequate.

10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> o Reduce and maintain combined EDG loads to 1 2330 KW within l

next 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> VP-580 REV 19 PAGE 11 of 17 PSVP l

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s 4l0 EQUIPMENT AVAILABILITY (CDNT'01 f]

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4.10 Verify Instrument Air piissure o SAP-1A available.

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o SAP 1B 1-o SAP lC 7

o SAP 10 o

IAP 1A o

I AP 1B c,

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IA-4 P1 4.11 Observe RB conditions o RB TEMP < 130'f hB notify SS00 of para: eters which have exceeded normal o RB PRESS < 4 psig limits.

/'N o RB H2 concentration, if

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available from Chemistry.

o 4.12 E RCS PRESS > 200 psig BST-1 isolation valves:

SM RB Spray actuation is present, o BSV-ll IHG verify BST-1 is o BSV 12

isolated, i

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4.13~ E a OTSG tube leak exists ~

Makeup water can be obtained from:

Af]0 BWST level is s 35 ft, J118 notify 5500 to begin o SF pools, makeup to the BWST, o DW and boric acid.

VP-580 REV 19 PAGE 12 of 17 PSVP

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4l0 EQUIPMENT A/AILMILITY (CONT'D)

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ACTIONS DETAILS 4.14 if EFWPs are on minimum o EFW is required when:

rec 1re, IBEN determine their o4 ho RCPs operating, need to be running c Adequate subcooling margin ones not exist.

o OTSG Heat Removal does not exist.

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

,i.15 Review alarm summaries for o Review annunciator alarm unexplained alarms, summary.

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1 o Review computer alarm summary.

4.16 Vertfy proper notification are o Refer to CP-lll, Processin

.i completed..

Reportable or Plant /Personnt :

Problem Reports which are Safety Concerns.

o Refer to CP-211, Problem Reporting.

o Refer to Al-500, Conduct of Operations.

Refer to EM 202, Duties of the Emergency Coordinator, o lE Any of the following conditions have occurred:

o loss of RCP SW flow i

o loss of RCP seal return flow l

o Aux Pzr spray from MV

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THEN notify NPSE.

VP-580 REV 19 PAGE 1.3 of 17 PSVP

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4.17 Verify Shutdown Margin is 11%.

IE in Modes 3, 4, or 5.

J11M refer to SP-421, Reactivity Balance Calculations.

11 in Mode 6, 111M verify the requirements of 515 3,9.1 are met.

4.18 WHEN VP-580 is stopped, JJfM notify 5500.

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VP-530 REV 19 PAGE 14 of 17 PSVP

l LElQB!8E I RCS Pressure and Temperature Cooldown Limits I

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2200 2000 1800 l

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600 l

400 200j 0

. l RCS TEMPERATURE

• F' Acceptable region is:

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o. below and to the right of the NOT curve o above and to the left of the Adequate Subcooling Margin curve l

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'VP-580 REV 19 PAGE 15 of 17 PSVP

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4 ENCLOSVRE 2 4

4 Cooldown Requirements Vs.-Nat Circ Cooldown Rates 1)

.FW requirements and the time to cooldown are controlled primarily by the characteristir.s of the ADVs and the cut-in conditions for the DHR system.

l 2)

The time to cooldown from Rx trip is about 150 hrs.

l 3)

The FW requirement to cooldown is about 735.000 gal.

4)

The minimu. 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 t.me 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 sm:11er cooldown rates may be utilized.

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VP-500 REV 19 PAGE'16 of 17 PSVP t

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UfG0tVRE 3 Sources of Emergency feedwater (EfW) at the Crystal River Site

'wJ Condensate - Grade Sources

$2qrst Volume (cal)

Dedicated ETW Tank (EFT-2) 150,000 Condensate Storage Tank 139,000 Condeliser Hotwells 150,000 t

DP Storage Tank, Unit 3 450,000 DW florage 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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VP-580 REV 19 PAGE 17 of 17 PSVP

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