ML20002A747

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Emergency Operating Procedure EOP-1,Revision 1, Safety Injection Actuation.
ML20002A747
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 10/14/1980
From:
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20002A746 List:
References
EOP-1, EOP-1-R1, NUDOCS 8011210466
Download: ML20002A747 (67)
v • d • e


Text

l .

SOUTH CAROLINA ELECTRIC AND GAS COMPANY VIRGIL C. SUMMER NUCLEAR STATION NUCLEAR OPERATIONS NUClEAo 0 FOR INffky)'f f ljT ,

,\;3 EMERGENCY OPERATING PROCEDURE E0P-1 SAFETY INJECTION ACTUATION REVISION 1 OCTOBER 14, 1980 SAFETY RELATED Reviewed by:

ORIGINATOR (of this revision) Date QUALIFIED REVIEWER Date Approved:

OPERATIONS SUPERVISOR Date Date Issued:

FormAP-101-2'?1/80) l l

8011210tG' O

a' , ' .?

E0P-1 o PAGE i

. REVISION

  • 10/14/80 LIST OF EFFECTIVE PAGES PAGE REVISION i 1 11 1 1 1 2 1 3 1 I i 4 1 1  ;

5 1 6' 1 7 1 8 1 9 1 ATTACHMENTS I

Attachment I, Pages 1 through 9 1 Attachment II, Pages 1 through 8 1 Attachment III, Pages 1 through 8 1 ,

Attachment IV,.1 through 3 1 Attachment V, Pages 1 and 2 0 Attachment VI, Pages 1'and 2 - 1

' Attachment VII, Pages'1 and 2 1 Attachment VIII, 1 through 8 1 Attachment IX 1 Attachment.X, Pages 1 through-4 1 j

4 I

]

E0P-1 PAGE 11-REVISION 1 10/14/80 TABLE OF CONTENTS

.. / , . . . . , .

.... . r.' ,. . ,a ,.

PAGE, , , ,

1.0 PURPOSE 1

2.0 REFERENCES

AND GLOSSARY 1 30 SYMPTOMS 3 4.0 AUTOMATIC ACTIONS 4 5 0- IMMEDIATE ACTIONS 5 6.0 FOLLOW-UP ACTIONS 6 70 FINAL CONDITIONS 9 ATTACRMENTS Attachment I- - Loss of Reactor Coolant Attachment II - Loss of Secondary Coolant 1

Attachment III - Steam Generator Tube Rupture

~ Attachment IV - ESF Actuated Equipment (by Train)

I

, Attachment V - ESP Monitor Light Status

.,; , , Attachment VI .r..Pdst AccJden't Monito. ding Instrument,a ' -

Attachment VII - Reactor Coolant System Pressure Temperature Limit Curve Attachment VIII- Long Term Plant Status Evaluation l

Attachment II - Short Term Plant Status Evaluation l l

Attachment X - Partial Safety Inje,ction Reset , ,,

i e

I E0P-1 PAG 2 1 REVISION 1 10/14/80 1.0 PURPOSE The purpose of this'proce' dure is to provide operating guidelines in the event of an actuation of the safety injection system. This procedure provides diagnostic guides to be used in determining the cause of the system actuation and the subsequent actions to be taken.

Subsequent actions are given in the following attachments:

Attachment I -

Loss of Reactor Coolant Attachment II - Loss of Secondary Coolant Attachment III- Steam Generator Tube Rupture The attachments provide instructions to be followed once the operator has determined the cause of the safety injection actuation.

2.0 REFERENCES

AND GLOSSARY 2.1 References 2.2.1 Westinghouse Reference Emergency Operating Instructions.

2.2.2 FSAR Section 15 2.2 3 System Descriptions for:

Safety Injection i . . . .

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C$01.anhl5ge);gn.y.g.. .. . ,.,Q,.,' ., ,  ;.;. ; y,Q ,. . ,;, . ., .

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En'g iheered Safety Features Actuation ~ System '

2.2.4 Virgil C. Summer Precautions, Limitations and Setpoints for NSSS, January 1979 2.2 5 Plant Procedures.

. SOP-211-Emergency Feedwater System

, SOP-11.2-Safety. .Inj e.c. tion ,

Sop-115 : Residual'Hedt Removal- .- .

~~, .

SOP-116-Reactor Building Spray System SOP-117-Service Water System SOP-122-Post Accident Hydrogen Removal System SOP-208-Condensate System SOP-306-Emergency Diesel Generator GOP-6 -Plant Shutdown from Hot Standby to Hot Shutdown GOP-7 -Plant Shutdown from Hot Shutdown to Cold Shutdown GOP-10 -Preparation for Refueling E0P-5 -Reactor Trip E0P-13 -Natural Circulation 2.2.6 Plant Drawings

E0P-1 . .

PAGE 2 .'

REVISION 1

~10/14/80 I

108D837 Series Westinghouse Functional Diagrams

. .. . . 10.8D932, Series Westinghouse Process Control Block., , .. . . ,

' Diagram v *'

r- -

'T 2.2. Glossary BIT - Boron Injection Tank CCW - Component Cooling Water

-CST - Condensate-Storage Tank ESP - Engineered Safety Features 4

ECCS Emergency Core Cooling System ESFLS - Engineered Safety Features Load Sequencer HVAC - Heating, Ventilation,. Air Conditioning System i

FI - Flow Indicator IRB - Inside Reactor Building KV - Kilovo1+,s LI - Level Indicator MDEFP - Motor Driven Emergency Feedwater Pump

.: MS -i .: .' ~.~  : " ; .. - -

..l . . -l:: h .: .c. . ; ; . .[M ' .'; ',t n: St e a m . -' 5)t%:/f){*.: ::? % 'h.,':';i.. = TL.* * * * ' ~ ' , 6;*.

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  • ' ~ ' '

. :' ':3,',4,*f

.L ORB. - Outsids'Reacto.r Bulding- -

i- -

MSIV - Main' Steam Isolation Valve i PA - Public Address PAMS - Post Accident Montoring 3-PI. '

- Pr, essure Indicator

.\- .C .

. , .. . ; . . .  : .  : . -r.,- .. . -

PZR' - Pressuri.ze-r. -

PORY - Power' 0perated Relief Valve PRT~ - Pressurizer Relief Tank RB - Reactor Building RLP: - Relief RC .cReactor Coolant l

l

r l E0P-1 PAGE 3 REVISION 1 10/14/80

, RCP - Reactor Coolant Pump

s. .

RCS Reactor Coolant' System -...

RHR - Residual Heat Removal System RM - Radiation Monitor ,

RWST - Refueling Water Storage Tank S/G - Steam Generator SI - Safety Injection Tavg - Average RCS Temperature TDEPP - Turbine Driven Emergency Peedwater Pump TI - Temperature Indicator T - Differential Temperature 30 SYMPTOMS CAUTION: No single plant parameter should be relied.upon for evaluating plant status under accident conditions.

Redundant channels should be checked for consistency while performing the steps of thie procedure.

3. 1 Initiation o,f,saf'ety',i~njection and reactor trip by one of the. ;, ,

. f01,14 Wing:. .

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7 3 1.1 Low Presdurlzer'Pressu're (2/3')' ' 1770' psig' '~

3 1.2 High Reactor Building Pressure (2/3) 4.0 psig 313 Low Steamline Pressure (2/3) 675 psig 3 1.4 High Steamline Differential Pressure (2/3 on 2/3 S/G',s) 100, psid

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~ P .-  : *6 } j.h 'c,

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3 32 Typical Symptoms (one or more systems may appear in any order) 3 2.1 Decreasing Pressurizer Level 3 2.2 Increasing Pressurizer Level 323 Decreasing Pressurizer Pressure 3 2.4 Increased Charging Plow 3.2 5 Letdown Isolation

E0P-1 -

PAGE 4 ,

REVISION 1 10/14/80 3 2.6 . Rapidly Changing Reactor Coolant System Average Temperature .

327 Increasing Reactor Building' Pressure 3 2.8 Increasing Reactor Building Temperature 329 Increasing Reactor Building Radiation 3 2.10 Increasing Reactor Building Sump Levels 3 2.11 Increasing Reactor Building Humidity (Computer indication only) 3 2.12 Low Steamline Pressure on one or all Steamlines 3 2.13 High Steamline Flow in one or all Steamlines 3 2.14 Steam Flow / Feed Flow Mismatch 3 2.15 Low or High SIG Level 3 2.16 Increasing Steam Generator Blowdown Radiation 3 2.17 Increasing Main Steamline Radiation 3 2.18 Increasing Condenser Exhaust Radiation 3 2.19 High Auxiliary Buiding Radiation

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. . :.' :~, . . . 4 , 63 ' AkITOMIT' ice ACTION ~ e ' . '

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4.1 Reactor / Turbine Trip I 4.2 Generator trip after 30-second tiue delay.

43 Emergency Diesel Generators start.

431 7.2 KV ESP Buses 1DA, 1DB, 1EA and 1Eb are energized

, within 10 seconds if..de-ener.gized.

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,. . . n p : . . ..

.4-Char'ging: and RHR pumps' start.

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4 5 . Safety Injection Flow through BlT is initiated. j 4.6 Feedwater Isolation and Main Feedwater Pumps trip.

4.7 Emergency Feedwater Pumps start and supply E'mergency Feedwater to Steam Generators..

1 4.8 Phase A Containment Isolation is actuated. I

.c 49 Service Water Pumps. start in high speed.

m E0P-1 PAGE'S REVISION 1 10/14/80

. 4.~10 Chilled Water Pumps start.-

4 11 Component Cooling . Pumps start.

4 12 Containment Ventilation Isolation actuated.

4 4.13 Ventilation Isolation for the following areas is actuated.

i 4.13 1 Control Room and Tech Support Center 4.13 2 Eslay Room 4.13 3 Controlled Access Area 4.14 Reactor Building cooling unit switch to two (2) slow speed fans.

4.15 HVAC Chiller units start.

4.16 Service water booster pumps start and supply water to Reactor Building cooling units.

4.17. Main steam isolation-occurs upon:

4.17 1 High-2 Reactor Building Pressure (5 7 psig) 4 17.2 Low Steamline Pressure (675 psig)-

4.17 3 High Steam Flow Coincident with Lo-Lo Tavg (553*F) y,.18 On Hijh-31Reac't.or Building Pressure (11.4 psig)-

r.

4.18.1 Reactor Buiiding Spray actuat.ed.

I 4.18.2 Phase B Containment Isolation 50 IMMEDIATE OPERATOR ACTION 51 Verify reactor Turbine trip by observing all control and

, shutdown' rod.s f.ully inserted.and nuclear-power.is decreasing. r

.* JTr?ansfer NR-45 r.ecdMer'ito.'one source rang'e arid' liitei mediate-h -

range' channel.- i' -

. ]i 5 1.1 If not, manually trip the reactor and turbine.

5 1.2 If still not tripped, place Bus 1B1 and 101 TIE BREAKERS in MANUAL and CPEJ Bus 1B1 and 101 FRD Breakers from the

-main control board.

NOTE: Busses 1B1 and 101 may he-reenergized when rod are inserted. ,.

52 . Verify Turbine Trip

E0P-1

.PAGE 6 .'

REVISION 1 10/14/80 5 2.1 If not TRIP.from Main Control Board or 5~.2.2 Stop'EHC pumps A and'B from main control board or

5. 2 3 . Trip locally from turbine front standard.
5 3 Verify generator trip approximately 30 seconds after turbine trip.

54 If the-plant is in a condition warranting a Safety Injection as per Step 3 1 and automatic actuation has not occurred, MANUALLY initiate Safety Injection.

5 5 -Verify the ESP. Buses 1DA, 1DB, IEA and 1EB are energized and the diesel generators are running.

5.6 Verify the following:

5.6.1 FEEDWATER ISOLATION and FW Pump A/B/C Trip has occured.

5.6.2 Emergency Feedwater Pumps have started and are supplying emergency feedwater flow to the steam generators.

563 Charging Pumps have started and are deliverin6 safety injection flow through the BIT from the RWST (BIT flow on FI-943).

0 5 6.4 RHR pumps have started.

. 5 . 6. -5s, .Phas.e A Is.olation has occur. red. ,

5*.- 6 '. 6 "SeYvice Water Pumps have started in high speed.

Component _ Cooling Water Pumps have started.

~

567 i

5.7 Verify Main Steamline Isolation on: i 5 7.1 High-2 Containment Pressure (5 7 psis) i 5 7.2 Steamline-Low Pressure.(675 psig) 57.'Nl$51hitfam h5%incide$sdish5bdolaVg(N3[P,)') .

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58 VerifyReactorBuildingkrayactuationonHigh-3 Containment Pressure '(11 4 psig) . '

59 Announce over the station PA system " Reactor Trip - Safety Injection".

5 10' Implement the-Emergency Plan.

e

E0P-1 PAGE 7 REVISION 1 10/14/80 6.0 -FOLLOW-UP OPERATOR ACTION -

LNOTE: Initial or check steps as indicated when completed. l 6.1 ' Verify all automatic and immediate actions are completed. If not manually actuate.

6.1.1 Insure at least one complete train of safety injection equipment is operating (Attachment IV).

6.2 Assign personnel to:

6.2.1 Verify ESF valves and equipment are in the proper position and operating by status of the ESF status lights (Attachment V).

6.2.2 Evaluate plant equipment status (Attachment VIII).

6.2 3 Start a log of key plant parameters (Attachment IX).

63 Verify the reactor coolant system is at least 50*F subcooled by the subcooling monitor OR Reactor Coolant System Pressure-Temperature Limits (Attachment VII). If not:

631 Attempt-to cool the RCS by dumping steam from-the steam generacors to the condenser or atmosphere.

A. Steam pressure controller (s) setpoint will have to be reset to a corresponding pressure for the temperature

, , requi. rad.. See example,.with. Attachment VII.. ... .

B. ' Wits condenser available.

1) Reset then block steamline safety injection Train ,

A and Train.B, if necessary j

2) Open MS Line Bypass Iso valves (PVM-2869A, 2869B and 2869C) if necessary.
3) Transfer STEAM DUMP MODE SELECT to the STM PRESS '

,j mo.de.

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4) If Tavg:is below 553*F set STEAM DUMP INTERLOCK (2 Trains) to RESET and BYPS INLK.
5) Set the STEAM DUMP CONTROLLER to the lower required pressure setpoint, or transfer to MANUAL and OPEN to establish steam flow.

C.- With condenser not available.

1) Transfer MS Line SD/PWR RLF (IPV-2000, 2010,

~2020) controls to POWER RELIEF mode.

EGP-1 .

PAGE 8 -

REVISION 1 10/14/80

2) Set'the MS POWER RELIEF controllers to the lower required pressure,setpoint, or transfer to MANUAL~

and OPEN to establish steam flow.

6.4 IF RCS pr, essure is low or decreasing, verify:

6.4.1 Pressurizer Spray control (PCV-444C and D) are closed.

A. If either is stuck open stop RCP A for PCV-444D or RCP C for PCV-4440.

6.4.2 PZR Range Relief valves (PCV-444B, 445A, and 445B) are closed.

A. If any are open close the associated relief isolation valve (MVG-800A, B, or C)

B. If the PZR power relief actuated during the transient verify their closure when pressure drops below the reset pressure (2335 psig). If they do not reset close the associated relief isolation valve.

6.4 3 Pressurizer safety valves are shut by monitoring TI-465, 467, 469 and the accoustic monitoring indication.

65 STOP all RCP's within 5 minutes if Phase B isolation has actuated.

16.6;STOPalIl',R6P',sa'ftdriverif'yingEa'fetyinjec.tionfiowifRCS'.

pressu'r e decreases tb '1550 psig on RCS presure wid'e range PI-402.

  • NOTE: Monitor RCS pressure throughout this procedure for conditions requiring RCP trip. 1 iNOTE: Do not stop seal injection flow.,_ l 6.

."'7 Whenever,all. force'd reactor. coolant. flow'.i'arstopped, implement.

.'~.. .

' ,EOPif 3,j Naldr~al ,Cirdufah' ion ,"in confundtibn . with 't h'i's' "' 2 ' ' " , ~

procedure.

6.8 Identify'the cause of the SI and proceed to the applicable attachment. Monitor PAMS closely since parameters change slowly on a small break.

2

.. . -EOP-1 PAGE 9 REVISION 1 10/14/80 e .

s E~ .s i Dominant. C><3 - % Mu ". 0 f., eo d t 8 M.= 15 il a.c eGJ -%

^88 1***d W 5$$ #50- .5 i $$

.3 $ 0"c j$t$) ogg 5M M $ MM LLow PZR pressure X Y _W "A- -~ ~

~~ Low PZR level =..S e

_High RB pressure XM

_High RB temperature X iEiSES

_High RB radiation X

_High RB sumps X W

_High Aux Bldg radiation W Abnormally low S/G pressure X X High steam flow M oc:pe:.

High steamline ~  ::===-

differential pressure M ~

Steam / feed flow ee & _~

J Lmismatch Condenser exhaust high

_ radiation S/G blowdown high

__ radiation Main steamline

,_high radiation _

^

SIG Level Increasing 69 IF A'LL of the following parameters . appear norms 1, the,SI may bb

  • spuri.ous, BUT MUST BE- ASSUMED REAI, UNTIL PROVEN OTHERWISE. , , , *l 4

6.9 1 RB temper'ature.(TI-9201A, TI-9203A) i 120*F' {

t 692 RB sump level. (LI-1963, LI-1964) Indicate o j I

6.9 3 RB radiation. (RMA2, RMG7, RMG8)

694 RB pressure.(PI-950 thru 951)1 1 5 psig C4 h!9.'5 condens5keb$aust radl'ahi$f." . ($$A5),- I

6 9.'6 Radiation levels in the auxiliary building are normal.

6 9 10 SIG Blowdown radiation (RML-3) 6.10 In addition to Step 6.8, all the following parameters must exist prior to terminating the SI:

6'.10.1 RCS' pressure >2000 psig and increasing.(PI-402,403)

E0P-1 .

- PAGE 10

  • REVISION 1 10/14/80 6.10.2 PZR level >500 (LI 459A, LI 460, LI 461)

.e in at' lea'st'one S/G' . -' . .-" ' :. . '"'

, . .. .. s. .. .

.6.10 3 S/G'l.,....evel .in the nariow range OR.at least 285-gpm total emergency feed water-flow 6.10.4 RCS at least 50*F subcooled.

6.11 When the SI is. proven spurious, with Shift Supervisor permission, reset..the SI per Attachment X.

6.12 Complete the follow-up actions required by E0P-5, Reactor Trip.

7.0 FINAL' CONDITIONS FOR INADVERTENT SI

- 7.1 Recovery from the'SI is in progress per Attachment.X.

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E0P-1 Attachment I

-Page 1 of.9 Revision 1 LOSS OF REACTOR COOLANT

.4-  :..... ..l.0 , PURPOSE . , ,

1.1 LThis attachment provides instructions to:-

1.1 . 1 Verify and/or establish short term cooling to prevent or minimize fuel-damage.

1.1.2 Mt-imize and/or eliminate any radioactive releases to the etc. : "or. ment .

1.1 3 Maintain the plant in a safe condition.

1.1.4 Provide long term shutdown and cooling of the fuel.

2.0 REFERENCES

AND GLOSSARY

- 2.1 See Section 2.0, E0P-1 30 SYMPTOMS CAUTION: No single: plant parameter should be relied upon for evaluating plant status during accident conditions.

Redundant channels should be checked for consistency

_3 pile performing the steps of this attachment.

. 31 '

Decreasing PZR pressure, normally accompanied by; 32 ,

Dec'eas1.ng PZR lbtel.' .

'3 3' Near normal- steam pressdre in all steam generators accompanied -

by one or more of the following:

331 Increasing RB pressure.

332 Increasing RB radiation.

333 Increasing RB sump level.

~3 4 4 'High'RB' Tem'peratu$e '

345 High Auxiliary Building radiation 4.0- AUTOMATIC ACTIONS 4.1 See Section 4.0, E0P-1.

4

- - = - - - . ,

6 E0P-1 Attachment.I .

Page 1! of 9 Revision 1 LOSS OF REACTOR COOLANT

'5.0 IMMEDIATE OPERATOR ACTIONS 5 1- See Section 5 0, E0P-1.

6.0 FOLLOW-UP ACTIONS

- lNOTE: Initial or check steps as indicated when completed. l 6.1 Verify RB sump level (LI-1963, 1964) increases as RWST level (LI-990 thru 993). decreases, or re-evaluate per Section 6.0, E0PL1. ,

6.2 IF RCS pressure decreases to 1550- psig, after verifying SI flow, 570P all RCP's and establish natural circulation per E0P-13, Natural Circulation,. currently with this procedure.

lHOTE: Monitor RCS pressure throughout this procedure for l L conditions reQuireing RCA trip. I 6.2.1 If'RB pressure increases to 11.4 psig verify Phase B Isolation, RB Spray actuation and stop RCP's.

INOTE: Do not stop seal injection flow. l 63 If RCS ' pressure decreases below 600 psig, -verify accumulator -

Tnjection.by decreasing accumelator level. indication on:

- 15,.3 1 A Accumulator,- LI-920,

.~

922., <

B:A'ccumulator .5I J924, 926. .

632 -

633 C' Accumulator - LI-928, 930.

6.4 If RCS pressure decreases below-175 psig, verify RHR flow.

6.4.1 A RHR - FI-605A.

6.4.2 B RHR - FI-605B. )

' ~

. - 615; Regulate.em$rgency feedwhter. flow..to r.essore'and.naintaint.S/Gyg- . . .

levels in'the narrow range.

6.5 1 RESET the EF ISO valves (6 valves) to the respective S/G, then select MANUAL.

6.5 2 Regulate emergency feedwater flow- using IFV 3531, IFV 3541, IFV 3551 for MDEFP and IFV 3536, IFV 3546, IFV 3556 for the TDEFP.

653 IF S/G level increases in an unexplained manner in one 57G,'go to Attachment III, Tube Rupture.

J

l 1

E0P-1 '

. Attachment I Page 3 of 9 Revision 1 LOSS OF REACTOR COOLANT 6.6 ~Close or verify closed'all PZR power relief valves (PCV-445A, 445B, 444B).

6.6.1 If valve (s) will not close, close the associated

' isolation valve-(MVG 8000A, B, or C).

6.7 Verify the' reactor coolant is at least 50*F subcooled by the subcooling monitor OR reactor coolant pressure temperature limits (Attachment VII) If not:

6.7.1 Attempt to cool the RCS by dumping steam from the steam generators to the condensor or atmosphere.

A. . Reset steam pressure controller (s) setpoint to a value corresponding to pressure for the temperature required. -See example with Attachment VII.

B. With the condenser available:

1) Reset then block steamline safety injection Train A and Train B.
2) Open MS line bypass ISO valves (MVG-2869A, 2869B, and 28690) if necessary.
3) Transfer STEAM DUMP MODE SELECT to the STM PRESS mode.
4) If Tav is below 553*F set STEAM DUM -

- INTERLhCKtoRESETandBYPASSINLK,.,f2.Tr'ains). - .

C. With the cohdensor not available:

1) Transfer MS LINE SD/PWR RLF valves (IPV 2000, 2010 and 2020) controls to POYER RELIEF mode.

2)- ' Set MS POWER RELIEF controllers to MANUAL and i 1

modulate OPEN to establish steam relief.

6; . 7. 2 If feedwater. flow is unavailable, implement. E0_P ,14, -

Inadequate core cooling co'ncurrently with this-

  • t '

procedure.-

6.8- IF RWST level is approaching the low-low level alarm (18%) or

-RCS pressure has quickly decreased below S/G pressure, go to s tep. 6.19 4

4

p--

~

E0P-1 .

Attachment I -

Page 4 of 9 Revision 1 LOSS OF REACTOR COOLANT 6.9 Monitor Condensate Storage Tank level: .

691 If svailaole fill the CST from the condensate system: .

NOTE: If condensate pump (s) are running, makeup to the CST May

_ be automatic. (FR 3019)

A. Close XVT-643-C0 (local valve,.436 Turbine Building)

B. Open XVT-668-C0 (local valve, 436 Turbine Building) ,

C. Start or verify Demineralizer Water Pump (s) are running in the water treatment building.

692 If condensate system is unavailable when-CONDENSATE LOW / LOW LEVEL alarm.is received:

i CAUTION: Automatic-transfer to service water supply for emergency feedwater is actuated on low emergency i feedwater_ pump suction pressure. This may not be fast enough to prevent pump damage.

A. Open SW LP A to EMER FW (MVG-1037A) and SW LP A to MDEPP l A (MVG-1001 A)

B. Open SW LP B to EMER FW (MVG-1037B) and SW LP B to MDEPP '

A (MVG-1001B).

C. Open SW LP A to EMER FW. (MVG-1037A) and SW LP A to .

_ . . LTDEPP(MVG-liOO8) 6r SW LP B to EMER.FW (MVG-1037B) and SW

.~LP B to TDEFP (MVT-1002) .-

l 6.1 ressure is slowly decreasing or stabilized above 1176 psig, IF RCSSp/G pressure to 975 psig.

reduce 6.10.1 With the main co:: anser-available:

A. RESET then BLOCK STEAMLINE SAFETY INJECTION Train A and B.

D'.'.'OpenM'S-LINEBYPASiISO'(MVG-2869-),B,C). - -

C. Select STM PRESS mode on STEAM DUMP MODE SELECT.

D.- Open condenser dumps by lowering the SD controller setpoint or by MANUAL operation of controller.

, 1

! 6.10.2 Condenser not~available:  ;

l

-A. Select STM PRESS mode on STEAM DUMP MODE SELECT.

11 B. Open-the S/G PORV's by lowering the setpoint ji potentiometer. ,l l

, .~ . _ . _.

=

t-E0P-1 Attachment I

.Page 5 of 9 Revision 1 LOSS OF REACTOR COOLANT 15.'11,[P RCS pressure has stabilized above 200 psig, reset the SI'and

- STOP the RHR pumps..

i CAUTION: Automatic.re-initiation of SI will not occur due to the reactor trip-breakers being open. SI-must be

_ - manually reinitiated if required. -

6.11.1,The'RHR pumps must be manually restarted, if required due

~

~to RCS pressure decrease below 175 pais.

6.12 SI.may.be reset and normal charging established as per

. Attachment-X-if ALL the following exist:

6.12.1 RCS pressure > 2000 psig and increasing

~ 6.12.2 PZR level > 50%. -

6.12 3.S/G 1evel in narrow range in at least one steam generator OF at least 285 spm total emergency. .

6.12.4 RCS' > 50* F subcooled. .

6.13 Manually reinitiate SI if:

6.13 1 RCS pressure decreases by 200 psi.

6.13 2 PZR level decreases to 20%.

6.13 3 RCS'50.*.F,s,ubcooling cannot be m,aintained.

, 6.'13 4 If SI'is r'eiditiated do not' terminate again u~nt'il'at'

~

~ '

leest 65*F of .subcooling is maintained.

6.14 RB spray, if actuated, may.be reset and the pumps placed in standby.once RB pressure is reduced to nominal operating

~

, pressure-and the RB-spray NA0H storage tank low level.

6.15 Periodically check the auxiliary building for evidence of ECCS leakage by. monitoring area radiation monitors.

~ '

. 6.~1'6' Monitor RB hydrogenc'oncentration.

  • 6.16.-1-Start the hydrogen recombiners, per SOP-122 after 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s-or whenever H2 level reaches 3%, whichever occurs first.

6.17 The' diesel generators should not.be.run at minimum load or idle

- for extended periods.. Once the SI--is reset with-normal power-available, shutdown.the diesels and place.in standby condition for an automatic start per. SOP-306, Section 5 6.

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~EOP-1 ,

Attachment I -

Page 6 of 9 Revision 1 N

LOSS OF REACTOR C00LANTs s

- 6.18 Complete Follow-Up Actions of E0P-5, Section 6.0.

6.19 Prior to .the RWST reaching 18% level, reset the SI .(Train A and

.B).

6.20 Shiftzthe Component Cooling Pump carrying the non-essential-

~

loads to. Fast Speed.

6.20.1 IF fast speed is unavailable, trim unnecessary non-essential loads and thrdttle component cooling to the spent fuel heat exchanger.

6.l21 OPEN the RER HX ~ A .(B) CC Valve (MVG-9503A) (B) in the non-essential loads loop.

6.22 START or verify operation of the Component Conling Pump in the inactive loop in Slow Speed.

6.23 IFLRWST level decreasesEto 6% (empty alarm) before. cold leg recirculation switchover-is complete, stop all pumps taking a e suction from the RWST.

6.24. Establish RHR flow to the charging pumps from the RER sumps (upon receipt of RWST low-low level alarm).

CAUTION: Steps must be performed-in the order listed to prevent isolating RHR . pump . suction or RHR. pump . runout. . , ,

' , ' 8.24.1'OPENo'rverifyopen-RHRSumpto'kHRPumpA(B).valv'es.

A. - MVG-8811 A and MVG-8812A for RHR Pump A. [

B. MVG-8811B and MVG-8812B for RHR Pump B.

NOTE: MVG-8811 A & B and MVG-8812 A and- B automatically open on RWST low-low level. (18%).

( "'

'.' '6.24'.'2 CLbSE RWSf'To RER Pump A'and.'B Valves. -

A. MVG-8809A for RHR Pump A.

B. MVG-8809B for RER Pump B.

6.24 3 START RHR Pump A and B if stopped in stop 6.11.  ;

l l

6;24.4 CLOSE Low Head Hot Leg Recire (MVG-8887 A and B). j l

T W r v M k - -+

W

. ~ EO P

  • Attachment I Page 7 of 9 Revision 1 LOSS OF REACTOR COOLANT 6.24 5 OPEN RHR Loop-A (3) To CHG Pumps valves..

A.- MVG-8706A.from RHR Loop A to charging Loop A.

B.- MVG-8706B _from RF2 Loop B to charging Loop B.

6.25 CLOSE RWST To CHG PUMP SUCTION valves LOV-115B and LCV-115D.

6.26 Establish redundant flow paths for high head injection to the RCS cold legs.

CAUTION: IF only one RHR Pump is operable DO NOT do steps 6.26.

and 6.26.2.

l CAUTION: Steps must be in-the order listed to prevent isolating l L changing pump discharge. I NOTE: These steps align charging pump C to either Loop A and Loop B. IF both charging pump A and B are operating, the loop selected is optional. IF either charging Pump A or B is inoperable align C pump to that loop. I 6.26.1 CLOSE MVG-8131 A and B to align Charging Pump C to Loop A SE

'6'.26.2'CLOSE,MVG-61j0!AindBtoalignCharging,P.umpCtoLoop, B ,

- 3 6.26.3 OPEN CHG LP A ALT To COLD LEGS, MVG-8885 6.26.4 CLOSE MVG-8133 A and B to align charging Pump C to Loop .

SE 6.26 5 CLOSE MVG-8132A and,B to align charging Pump C to Loop.

B. -

6.27 Reactor Building. Spray System Operation. ,

LNOTE: RB Spray may have been stopped in Step 6.14. l 6.27.1 Verify RB_ Spray Sump isolation valves MVG-3004A and MVG-3005A for Spray Pump A and MVG-3004B and MVG-3005B for Spray Pump B automatically open upon receipt of RWST low-low level-alarm.

1 I

i

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E0P-1 ,

Attachment.I

~6.27.2 Close RWST TO SPRAY PP A(B) SUCTION valves.

'A. MVG-3001A for Spray Pump A. J B. MVG-3001B for Spray Pump B.

NOTE: The following steps must be coordinated with the _

l Chemistry Section.

6.27 3 Upon receipt of RB Spray NA0H Storage Tank Low level alarm.

A. Reset RB Spray (Train A and B).

B. Stop RB Spray Pumps A and B.

6.27 4 Sample RB sump water for PH.

A. Verify PH is above 8.0.

6.27.5 If PH is out of limits and require adjustment.

A. Refill NA0H tank.

B. Verify the following conditions exist.

1) RB Sump temperature is less than RB atmosphere temperature. .
2) RB pressure has decreased to nominal (approximately 0.0 psig). .

6.27.6 START RB spray pump A or B. _

6.27.7 Inject the amount of NaOH specified by the Chemistry j Section-then stop the RB spray pump. }

6.28 Periodically check the auxiliary building area radiation monitors for evidence of ECCS leakage.  ;

6.29 Perform an evaluation of plant status per Attachment VIII.

6 30 Hot leg recirculation shall be initiated 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> after SI actuation. Perform the following steps on a train-by-train i basis.

6 30.'1 Turn on. Train A (B) valves Power Lockout Train A Train B 6 30.2 CLOSE RHR Loop A (B) to Cold Legs MVG-8888A MVG-88888

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E0P-1 Attachment I Page 9 of 9 Revision 1 LOSS OF REACTOR COOLANT 6.30 3;0 PEN RHR.LP A & B,. Hot Legs, MVG-8889 .

6 30 4 OPEN LOW HEAD HOT LEG RECIRC valves 8887A and B.

.6.30 5 STOP Chrging Pump C if not required to be operating when

' aligning the first train:

Pump'C or N/A 6 30.6 STOP Charging Pump A (C).

6 30 7 CLOSE CHG LP A ALT To Cold Legs, MVG-8885 6 30.8 OPEN CHG LP A Hot Legs, MVG-8884 6 30 9 START Charging Pump A (C).

6 30.10 STOP Charging Pump B (C) .

6 30.11 CLOSE Boron INJ Tank Inlet valves MVG-8803A and B.

6.30.12 CLOSE Boron INJ Tank Outlet valves MVG-8801 A and B.

6 30.13 START Charging Pump B (C) 6.30.14 Turn Train A and B VALVES POWER LOCK 0UT off.

6 31 Alternate coldleg and hotleg recirculation every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

7.0 FINAL CONDITIONS 7.1 RCS on cold or.hotleg recirculation.

.]

t E0P-1 ATTACHMENT II-PAGE 1 of 8 REVISION 1 LOSS OF SECONDARY COOLANT 1.0 PURPOSE 1.1 This' Attachment provides. instructions to:

A. Stabilize RCS and S/G conditions prior to cooldown.

B. Minimize energy release by isolation of the break where possible.

C. Prevent lifting the PZR PORV's and code safeties by dumping steam from non-faulted S/G's.

D. Isolate emergency-feedwater to the faulted S/G to maximize feedwater to the non-faulted S/G's.

E. Borate the RCS to maintain the required shutdown margin.

2.0 REFERENCES

AND GLOSSARY 2.1 See Section 2.0 of EOP-1.

Caution No single plant parameter should be relied upon for I evaluating the plant status under accident conditions.

Redundant channels should be checked for consistency I while performing the steps of thic attachment.

30 SYMPTOMS 31 The key' symptom is abnormally low pressure in one or all S/G's accompanied by:

32 High steam flow.

33 High steamline differential pressure.

34 Steam flow / feed flow mismatch. i I'

l 1

1 1

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E0P-1 . l ATTACHMENT II -

PAGE 2 of 8 REVISION 1 LOSS OF SECONDARY' COOLANT

  • i 4.0 AUTOMATIC ACTIONS 41 See Section 4.0 of E0P-1.

50 IMMEDIATE ACTIONS 51 See Section 5 0 of E0P-1.

6.0 FOLLOW-UP ACTIONS NOTE: Check or initial steps as indicated when they have been l completed. I 6.1 Verify Main Steam Isolation, if not actuated, manually initiate steamline isolation.

6.2 Verify the PZR POWER RELIEF valves (PCV-444B, 445A, 445B) close when RCS pressure decreases below 2335 psig. IF NOT:

6.2.1 CLOSE the associated RELIEF ISOLATION valve (MVG-8000A,B,C) 6.2.2 IF the PZR power relief valves cannot be closed or-isolated Attachment I must be implemented concurrently with this Attachment.

6.3 STOP all, reactor coolant pump after verifying safety '

injection flow if-i NOTE: Monitor RCS pressure throughout this procedure for conditions requiring RCP trip.

6.3 1 Wide range RCS pressure drops to 1550 psig.

632 Phase B isolation occurs ar.d component cooling water is ,

isolated.

LNOTE: Do not stop seal injection flow. I 633 Implement EOP-13, Natural Circulation, concurrently with this procedure.

.- . .EOP-1 ATTACHMENT II PAGE 3 of 8 REVISION 1 LOSS 0F-SECONDARY COOLANT

. 6.4 :lF RCS pressure'stablizes above 200 psig, reset the SI and stop the RHR pumps. -

16.4 1 SI must be manually initiated, if required, after resetting SI..

6.4.2- The RHR pumps must be' manually started whenever the wide range.RCS pressure decreases below 175 psig.

CAUTION: DO NOT terminate emergency feedwater flow to ANY steam.

generator until the faulted loop is identified. NEVER terminate emergency.feedwater flow to ALL steam generators unless the RHR is in operation and providing cooling water ~to the RCS.

65 Record-the following to aid in identifying the faulted S/G.

6.51 S/G Pressures S/G A PI-474 PI-475 PI-476 S/G B PI-484 PI-485 PI-486 S/G C PI-494 PI-495 PI-496 652 S/G Levels S G A LI-474 LI-475 LI-476

.S G B LI-484 LI-485 LI-486 3 G C LI-494- LI-495 LI-496 653 . Emergency'Feedwater Flow S G A FI-3561 S G B FI-3571 S G C FI-3581 1 NOTE "

r, -Emergency feedwate.r flow may have been automatically ,

L 15 orated from' the faultad' loop due to high' flow.

6.6 Determine the location of the fault.

6.6.1 A low steam generator pressure sa compared to'the others indicates that loop.as faulted.

6.6.2 .If all-steam generators depressurized and are repressurizing after ' main steam and feedwater isolation,

.t'he. fault may bs down's'tr.eam o':the f 'MSLV or[on a' -

feedwater line. This c'an be verified by:

A. Comparing MAIN STM HDR PRESS-(PI-464) with the pressures recorded in 6'.5 OR ,

B. Visual observations by outside operators. ,j e

E0P-1 ,

ATTACHMENT II

  • PAGE 4 of 8 REVISION 1 LOSS OF SECONDARY COOLANT

.6 . 7. If there is no indication of a. break in the secondary pressur.e boundary, go to E0P-1, Section 6.8 and re-evaluate conditions.

6.7.1 If a break is found continue with this procedure. ,

' CAUTION: If all S/G's are depressurized or depressurizir.g DO NOT l isolate emergency feedwater to any S/G until the faulted loop-is identified.

6.8 Isolate the faulted S/G Loop l NOTE: If the break has already been isolated due to automatic l closure of the MSIV's and feedwater isolation valves, L this step may be omitted.

6.8.1 Stop Emergency.Feedwater flow to the faulted S/G.

A. Reset all EF ISO valves (6 valves) to the respective S/G and then select MANUAL.

1) IFV-3531 and IFV-3536 for S/G A.
2) IFV-3541 and IFV-3546 for S/G B.
3) IFV-3551 and IFV-3556 for S/G C.

B. CLOSE (100% demand) the respective IFV to the faulted S/G.

. IF, -3531', and' IFV--%36 for S/G,'i ~ ..,

'2') IFV-3541 and IFV-3546 for S/G B. -

3) IFV-3551 and IFV-3556 for S/G C.

6.8.2 Verify. CLOSED or CLOSE the respective MS LINE ISO VALVE AND MS LINE BYPASS ISO for the faulted S/G.

A. PVM-2801A and PVM-2869A.for S/G A. I 1

B. PVM-28d1'B and P'VM-2869B'for S/G B.

C. PVM-2801C and PVM-2869C for S/G C.

6.8 3 Transfer MS line SD/PWR RLF valve (IPV 2000, IPV 2010 or ..

IPV 2020) for the faulted S/G to Power RELIEF mode, set the controller to MANUAL and CLOSE (0% demand).

CAUTION: If a S/G PORV is stuck open it must be isolated locally.

by closing the manual isolation valve.

- E0P-1 ATTACHMENT II PAGE 5 of 8

' REVISION 1 LOSS OF SECONDARY COOLANT 6.8.4 If S/G B or C.is faulted CLOSE the TURBINE DRIVEN EMERGENCYEFEEDWATER' PUMP STEAM SUPPLY valve:

A. MVG-2802A for MS Loop B to EF TURB OR B. MVB-2802B for MS Loop C to EF TURB 69 Regulate emergency feedwater flow to the non-faulted S/G's to maintain S/G level in the narrow range.

6.10 IF feedwater flow is unavailable implement E0P-14 inadequate care cooling concurrently with this procedure.

6.11 If water level increases unexplainably in one S/G, proceed to Attachment III, Steam Generator Tube Rupture.

6.12 Monitor pressurizer precaure and level.

CAUTION: Do not operate the charging munps at 2485 psig pressurizer pressure (safety. valve setpoint) without minimum flow lines open.

6.12.1 If pressurizer pressure exceeds 2345 psig:

A. RESET SAFETY INJ TRAIN A AND TRAIN B.

B. OPEN MVG-8109A, B and C and MVG-8106 to establish charging pump minimum flow.

C' CLOSE MVG'-8109A,'B'and'C'and MVG-8106 w'enev'er' h .

. pressuri,zer pres'sure drops to 1550 psig.

6.13 If RWST Low-Low -Level Alarm is annunciated (18% level) complete switch over to Cold Leg Recirculation.per Attachment I, Steps 6.24 through 6.27 6.14 Monitor Condensate Storage Tank Level .

6.14 1 If available, fill the CST from the condensate system.

NOTE: If. condensate pump (s') are running, mak7up to'the CST may be automatic.

A. CLOSE XVT 643-C0 (local valve, 436 Turbine Building).

B. Open XVT-668-C0 (local valve, 436 Turbine Building).

C. . START or verify running Demineralized Water Pump in the Water Treatment Building.

6.14 2 If condensate grade water is not available, when condensate storage Low / Low-Iow Level alarm is annunciated.

E0P-1 .

ATTACEMENT II -

PAGE 6 of 8 )

REVISION 1 LOSS OF SECONDARY COOLANT CAUTION: Automatic transfer to Service Water. Supply for-Emergency ~

-Feedwater is actuated'on low emergency feedwater suction pressure. This may not be fast enough to prevent pump damage and should not be depended on.

A. Open MVG-1037A and MVG-1001A for MDEFP'A B. Open MVG-1037B and MVG-1001B for MDEFP B C. Open MVG-1037A and MVG-1008 OR MVG-1037B and MVG-1002 for TDEPP 6.15 SI may be terminated IF:

CAUTION: Do not terminate SI. if all S/G's are depressurized or l pressurea are decreasing until the faulted S/G is identified.

6.15 1 One wide range RCS TH as verif ed by core exit thermocouples is less than 350}F AND:

A. RCS pressure >700 psig and increasing, AND B. PZR level > 20% and increasing, AND C. RCS > 50*F subcooled (per Attachment VII or

_' subcooling monitor), AND D. S/G level is in the narrow ran6e scale (above the . ., '

tubes) in at least.ons.S/G or at'least 285.'gpm' total emergency feedwater flow .* -

SE 6.15 2 All wide range RC3 TH is greater than 350*F AND A. Reactor Building pressure, radiation, and sump levels D.0'NOT exhibit abnormally high or increasing s.l.

. '..._ readiQ6s,'AND,

. Bi'-RC'S'Irecsur.e.>2000

~i psig and stable or increasingW AND. - '6 C. PZR level > 20%, AND D. .RCS >50*F subcooled (per Attachment VII or subcooling monitor), AND E .- S/G level is in the narrow range scale (above the tubes) in at least one S/G at least 285 spm total, emergency feedwater flow 9E

. LEOP-1 ATTACEMENT II PAGE 7 of 8 REVISION 1 LOSS OF SECONDARY COOLANT

~6.15 3--A11 wide range RCS Tg is greater than 350*F, AND A~. HRB pressure, or. radiation, or sump levels are neither abnormally high or increasing, AND-B. RCS pressure >2000 psig, and is stable.or increasing AND C. PZR level >50%, AND D. RCS >50*F subcooled (per Attachment VII or subcooling monit'o r) , AND '

E. S/G level is'in the narrow range scale (above the tubes)in at least'one SIG OR at least 285 spm total emergency feedwater flow.

6.16 Reset the SI per Attachment X, steps 1-12.

6.17 Manually SI (and refer' to E0P-1, Section 6.0); IF 6.17.1 RCS pressure drops 200 psig.

i 6.17.2 PZR level- drops 10%.

6.~17 3-RCS Subcooling < 50*F.

6.17.4 If SI is manually reinitiated do not reterminate unless RCS Subcooling >65*F.

4 6.18 Complete follow up actions required by E0P-5, Reactor Trip.

6.19 Maintain >50*F subcooling of RCS by dumping steam from l

non-faulted S/G's.

6.19 1 Condenser available and no uncontrolled steam release will occur by1 opening MSIV.

A. RESET and BLOCK STEAMLINE SAFETY INJ Train A and Train B. ,

B. Open MSIV for at least one intact S/G'.

I C. Transfer STEAM DUMP MODE SELECT to STM PRESS mode.  !

D. Set SD CONTR0ller at pressure of intact S/G's at termination of SI.

E -6.19 2 Condenser not available or rupture downstream of MSIV's or.cannot open MSIV's.

1 4

E0P-1 ,

ATTACHMENT II PAGE 8 of 8 REVISION 1

,, LOSS OF SECONDARY C00LANT' A. . Transfer MS Line SD/PWR RLF valves (1LPV 2000, 2010 or

'2020) controls to Power' RELIEF mode.

B. Set MS PWR'RLF controllers at pressure intact S/G.at termination of SI.

6.20 IF RCS subcooling cannot be maintained manually SI and go to E0P-1, Follow-Up Actions, Section 6.0 for re-evaluation.

6.21 Borate RCS to maintain required shutdown margin.

6.21.1 Sample RCS pressurizer and VCT for boron concentrations.

6.21.2 At completion of boration set automatic makeup control for the required concentration.

6.22 With offsite power available, restart A_or C RCP for cooldown purposes.

6.23 Isolate S/G if radiation level in th'e S/G' increases and.go to Attachment III.

6.24 Establish the necessary auxiliary systems and cooldown to cold shutdown per GOP-6 and 7 6.25 The diesel generator should not be run at minimum load or idle for extended periods. Once the SI is reset, with normal power available, shutdown the diesels and place in standby condition for automatic start per SOP-306, Section 5 6.

i 7.0 FINAL CONDITIONS 71 RCS is in a controlled configuration with at least 50*F subcooling.

.. . 'EOP-1 ATTACHMENT III-PAGE 1 0F 9 REVISION 1

?

STEAM GENERATOR TUBE RUPTURE

.0 PURPOSE 1.1 This attachment will' provide' instructions to:

A. ' Minimize'the release of radioactive material by:

1) Identifying and' isolating the faulted S/G.
2) Reducing-RCS pressure below S/G safety valve settings.

a 3) ' Diverting the' condenser vacuum exhaust:to the auxiliary building filtration system.

B.- Establish capability to supply feedwater to all S/G's and isolate feedwater to the faulted S/G.

C. to remove residual heat from the reactor Maintain through the theintact ability S/G's via the steam dump valves or power-operated reliefs.

D. Maintain the RCS;in a subcooled state.

E. Prevent overflooding-the faulted S/G.

2.0 REFERENCES

AND GLOSSARY 2.1 See Section 2.0, E0P-1.

30 SYMPTOMS 4 31 Decreasing PZR pressure.

32 Decreasing PZR level.

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33 Main Steam Line high-radiation.

34 . Condenser Vacuum pump exhaust high radiation.

3 5. S/G blowdown hi'gh radiation.

1 36 Increasing water level'in the faulted S/G.

-3 7' Steam /feedwater-flow mismatch.

40 AUTOMATIC ACTIONS

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4.1 :See Section'4.0, E0P-1.

I

EOP-1 ATTACHMEliT III PAGE 2 0F 9 REVISION 1 STEAM GENERATOR TUBE RUPTURE 50 IMMEDIATE OPERATOR ACTIONS 51 See Section 5 0, E0P-1.

6.0 FOLLOW-UP ACTIONS

LNOTE
Check or initial steps as indicated when they have been completed l 6.1 While performing the steps of this attachment, evaluate the following to identify the faulted S/G.

4 6.1.1 Unexplained' increase in one S/G 1evel with emergency feedwater to_that S/G reduced or stopped.

~6.1.2 ~High radiation fr'om:

A. S/G blowdown (RM-L3 and/or -10) .

B. Any one main steam line (RM-G 19 A,B, or C) .

C. Any.one S/G as determined by analysis or sample.

l NOTE: Upon positive identification of the faulted steam generator, l L immediately isolate per step 6.14. - I 6.2 Verify condenser vacuum exhaust to the auxiliary building charcoal exhaust system. (local' action) 6.2.1 OPEN the combined discharge to charcoal exhaust (XVB-110).

6.2.2 CLOSE the combined discharge to atmosphere (XVB-109).

63 Initiate samples of RB atmosphere and S/G's to identify-the presence of any abnormal radioactivity.

631 Reset Containment Phase A-(Train A and B).

632 Maintain Containment Isolation except for required valve manipulations to draw samples.

'6.4' Monitor blowdown' sample recorders (in Secondary' Sample Room) for pH and conductivity. ___

'6 5 Verify closed or close all PZR PORV's.

16.6 Verify PZR PORV isolation valves open and power available.

f6.7 STOP all'RCP'){ after verifying SI flow-if RCS pressare de' creases to 1550 peig ,

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.- E0P-1 '

ATTACHMENT'III

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PAGE 3 0F 9 REVISION 1 STEAM GENERATOR TUBE RUPTURE NOTE: Continue to-monitor RCS pressure while performing this.

attachment.

LCAUTION: Maintain seal injection flow. l' 6.8 -Whenever forced.RCS flow cannot be maint.ained, establish natural i Lcirculation per-EOP-13 in conjunction with this attachment.-

69 Stabilize:RCS temperature ~at 557'F, if not accomplished

-automatically.

691 Condenser and offsite power available.

]

A. Reset ' and Block' Steamline: Safety Injection' Train A and

Train B.

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-B. L0 pen MS. Line by pass ISO (PVM-2869 A.B.C) if necessary.

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C.: Transfer._ Steam. Dump mode select to STM. PRESS mode.

D. OPEN the condenser steam-dumps by decreasing the setpoint

on the ' steam -dump controller or by MANUAL control of controller.

6 9 2--Condenser not available.

A. Transfer MS'Line SD/PWR RLF valves (1PV-2000, 2010, 2020)' controls to' power Relief mode.

B. Set MS.PWR RLF controller. to MANUAL and modulate open to establish steam relief.

6.10 Regulate. emergency feedwater flow -to restore and . maintain S/G levels in the narrow-range.

6 '.' 10 .1 RESET the EF ISO valves -(6 valves) to the respective S/G and then. select MANUAL.

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6.10.2 Regulate. flowL using 'the . respective S/G emergency ' feed valve potentiometer.

A. . IFV-3531 and-IFV-3536 for.S/G.A.

B. IFV-3541:and IFV-3546 for S/G'B.

C. IFV-3551-and IFV-3556 for S/G C.

.6.11 Monitor Condensate Storage Tank leve1~ .

i 6.1.1.1 If'available fill the-CST from the condensate system.

i l

E0P-1 ATTACHMENT III -

PAGE 4 0F 9 REVISION 1 STEAM GENERATOR TUBE RUPTURE NOTE: If condensate pump (s) are running, makeup to the CST may -be automatic.

A. :Close XVT-643-C0 (local valve, 436 Turbine Building).

B. Open XVT-668-C0 (level valve, 436 Turbine Build'ing).

C. Start or verify running demineralized water pump (s) in the water treatment buiding.

6.11.2 If condensate water is not available, when low-low CST alarm is annunicated:

A. Open MVG-1037A and MVG-1001 A for MDEFP A.

L. Open MVG-1037B and MVG-1001B for MDEFP B.

C._ Open MVG-1037A- and MVG-1037B and MVG-1002 for TDEFP.

Caution: Automatic transfer to service water supply for emergency feedwater is actuated on low emergency feedwater suction pressure. This may.not be fast enough to prevent pump L damage.

6.12 IF RCS pressure has.stablized above 200 psig, reset the SI and stop the RHR _ pumps.

LNOTE: The-RHR pumps must be manually restarted if recuired.l 6.13.The diesel generators should not be run at minimum load or idle for extended periods. Once the SI is reset, with normal power available, shutdown the diesels and place in standby condition for an automatic start per 30P-306, Section 5.6.

6.14 Isolate and faulted S/G:

6.14.1 Stop'all feedwater flow to the faulted S/G.

A. RESET ALL the SF ISO valves (6 valves) for the respective S/G then select MANUAL.

1).A S/G.IFV-3531 and 3536.

'2) B S/G IFV-3541 and 3546.

3) C_S/G IFV-3551 and 3556.

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B. CLOSE EF to S/G using the potentiometer (100% demand) to the faulted S/G.

1) A S/G HCV-3531 and 3536.
2) B S/G HCV-3541 and 3546.

^

. . E0P-1 ATTACHMENT III PAGE 5 0F 9 REVISION 1 JSTEAM GENERATOR TUBE RUPTURE
3) C.S/G.HCV-3551 and 3556.

6.14 2 0 LOSE the MS line ISO and.MS line 230 bypass valves for the faulted S/G.

6.14 3 ~ If the MS line ISO Cg MS line ISO . bypass valves for the

~

faulted steam generator will not CLOSE, close the valves for .the non faulted S/G and use step 6.16.2 for cooldown.

1) A-S/G PVM-2801A and 2869A.
2) B S/G PVM-28013. and 2869B.
3) C S/G PVM-28010 and 2869C.

6.14.4 . Transfer'MS Line SD/PWR RLF valva (IPV 2000, IPV 2010 or.

IPV-2020) for the faulted S/G to power relief mode,' set valve controller to MANUAL snd close (0% demand).

6.14 5 IF isolating B or C S/G, CLOSE the steam supply to the Turbine driven emergency feedsator pump from the faulted loop.

S/G MS. Loop B to EF TURB (MVG-2802A).

S/G'MS Loop C to EF TURB (MVG-28U2B).

6.15 IF the faulted S/G was isolated before completing steps 6.3 to 6.15, return.to the applicable step but DO NOT UNISOLATE THE-

FAULTED S/G.

i 6.16 Rapidly reduce- RCS temperature to 507'F by dumping steam from' the non-faulted S/G.-

6.16.1 Condenser and offsite power available.

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'A. Block steam line safety-INJ Train A and Train B.

B. OPEN' MS line ISO valves (PVM-2801 A,- B or C) .

C. Select STM PRESS on Steam Dump mode select switch.

D.= Open. condenser. dumps by decreasing the cetpoint on the steam dump controller (approximately 725 psig) or'by manual' control of-controller.

E. Momentarily; bypass on both. steam dump interlock'

' switches at 553* F.

6'.16.2 l Condenser not;available.

E0P-1 ATTACHMENT III -

PAGE 6 0F 9 REVISION 1 STEAM GENERATOR TUBE RUPTURE A. '2.ransfer MS line' SD/PWR RLF valves (IFV-2000, 2010, or 20.20) controls to power reltaf mode.

B'. Set PWR RLF controllers ~to MANUAL and modulate open or

-C.-Set PWR RLF controllers to AUTO and set at required pressure; (approximately 225 psig).

'f- 6.17-Depressurize the RCS to faulted S/G pressure (approximately 1050 psig)-by one'of-the following methods.

HOTE: .P3R level-will increase, but there may be no indicate.d PZR l level wher initiating this step. l LHOTE: Do not stop RCP's at 1550 psig.l 4

6.17.1. OPEN PZR SPRAY (PCV-444C or 444D) if A or C RCP operating QR 6.17.2 .0 PEN one PRZR power relief (PCV 444B, PCV 445A PCV'445B) if offsite power;and RCP's not available OR 6.'17 3 - OPEN PRZR Spray from _CVCS (PVT-8185) if AT between PZR and charging is < 260*F.

~

6.18 Stop the RCS depressurization when RCS pressure is equal to faulted l S/G pressure.OR 1

6.18.1 At 50% PZR~1evel and increasing.

CAUTION: Maintain a steam bubble in the PZR while performing the l rest of this attachment. l 6.19 IF the'PZR-PORV was used for depressurization, verify PORV closed and 7HT integrity.

6.1_91 .

IF PZR level-is increasing and RCS pressure is decreasing, Teakage from the PZR steam space exists.

A. Verify all PRZR Power Relief' valves are closed.

B. Refer to E0P-1, Attachment I.

~

6.20 Verify RCS pressure is increasing, PZR level'> 20%, and the faulted S/G level is; increasing to determine SI flow greater than leak flow.

6.21 Reset'the J 3I and establish normal charging and letdown per Attachment X when:

6.'21.1 RCS pressure has' increased 200 psig after stopping.the

- d ep r essufi z atio n. -

E0P-1 ATTACHMENT III PAGE 7 0F 9 REVISION 1 STEAM GENERATOR TUBE RUPTURE 6.21.2 PZR level > 20%.

6.21 3 RCS subcooling > 50*F as determined by wide range temperature in the NON-FAULTED loops or core exit thermocouples.

6.22 Maintain PZR level > 20% and RCS at least 50*F subcooled OR 6.22.1 Start additional charging pumps.

6.22.2 IP cannot maintain PZR level, manually SI and return to step 6.16 (Rapid Cooldown).

6.23 Maintain, or establish, flow in only one RCS non-faulted loop.

6.23.1 IP all RCP's kre operating, stop all except A or C (for sprays).

6.23 2 IF the RCP's have been stopped and offsite power is available, start A or C RCP.

A. The criteria for terminating SI must be met.

B. Plant conditions for an RCP start have been evaluated and satisfied.

6.24 Turn on PZR heaters as necessary to maintain RCS pressure.

6.25 Complete followup actions of E0P's, Reactor Trip 6.26 Analyze the results of RCS and S/G sample for radioactove release.

If the limits of 10CFR20 will be exceeded, DO NOT PROCEED.

6.27 The next three steps must be performed simultaneously or a loss of PZR level control will occur.

6.28 Cooldown the RCS at less than 50*F per hour while maintaining S/G 1evels in the narrow range by dumping steam.

6.28.1 Condenser and offsite pwoer available.

A. Open steam dumps by decreasing the setpoint on the steam dump controller.

6.28.2 Condenser not available.

A. Open the non-faulted S/G PORV's by decreasing the setpoint on the steam dump controller.

E0?-1 ATTACHMENT III -

PAGE 8 0F 9 REVISION 1 STEAM GENERATOR TUBE RUPTURE 6.29 Decrease the faulted S/G pressure. __ ,

6.29 1 With cooldown on condenser dumps, slowly open the faulted S/G MSIV bypass valve.

6.29 2 With cooldown on MS line SD/PWR RLF valves, slowly open the faulted S/G Power Relief valve.

6 30 Decrease RCS pressure with faulted S/G pressure to minimise S/G inleadage to the RCS through the use of:

6 30.1 PZR heaters and ONE of the following:

6 30.2 PZR spray.

6303 Brief intermittent use of ONE PZR PORV.

6 30.4 Auxiliary PZR spary if A T < 260*P.

6 31 Manually SI if an uncontrolled decrease in RCS pressure or PZR level occurs.

6 32 IP one PZR PORV was utilized for RCS depressurization, verify PRT integrity and PORV closed.

6 33 Periodically sample the RCS. for boron concentration to verify the ren,uired shutdown margin of 1.77% A K/K.

6 34 When RCS pressure approaches 700 psig.

6 34.1 Unlock and close breakers for accumulator isolation valve's.

6 34.2 Close the accumulator isolation valves.

6.34 3 Open and lock breakers for the accumulator isolation valves.

6.35 Continue RCS cooldown and depressurization to 350*F and 400 psig.

6 36 Initiate cooldown on RHR per SOP-115, Section 4.2.

6 37 Cooldown the RCS to 200*F.

6 38 Reduce RCS pressure using auxiliary PZR spray until RCS and faulted S/G pressures equalice.

6.39 Continue RHR operation to remove decay heat.

6.40 Maintain charging and letdown for PZR level control and a boration path.

- E0P-1 ATTACHMENT III PAGE 9 0F 9 REVISION 1 STEAM GENERATOR TUBE RUPTURE 7.0 FINAL CONDITIONS 7.1 RCS in cold shutdown on RRR.

I

. E0P-1 ATTACHMENT IV PAGE 1 0F 3 REVISION 1

~

ESFLS ACTUATED EQUIPMENT

. . a.:

SI WITH NORMAL POWER l

1. Diesel Generators Start
2. Predesignated equipment motor feeders are tripped from l respective ESP buses IDA, 1DB.

3 Load Block 1 equipment is not tripped from the bus and is l immediately energized if voltage and necessary control signals j are present.

4 The equipment that is tripped from the ESP bus is then sequentially loaded.

! SI WITH A FOLLOWING UV ON ESF BUS l 1. The diesel generators start i

i 2. Once the undervoltage is detected, the SI actuation of the ESFLS is removed and reset.

3 All motor feeders are tripped off the respective bus except for load block 1.

4. Once the diesel is up to speed-it closes onto the bus-and energizes all of Load Block 1 except for the swing SI/ charging pump.

5 The equipment tripped from the bus is then loaded. sequentially onto the bus.-  ;

LOAD BLOCK #1 This equipment is not tripped from the ESP Bus, and therefore, is energized immediately if voltage and the necessary control signals are i present. ,

L-  !

~

TRAIN A TRAIN B 7200 V Switchgear .

1. SI/ Charging Pump XPP-43A-CS XPP-43B-C

( 2. SI/ Charging Pump (Swing Pump) (XPP-43C-CS) i- 3. Reactor Building Spray Pump XPP-38A-SP. XPP-38B-SP 480 V Switchgear

1. No Equipment.

E0 P-1 '

ATTACHMENT IV PAGE 2 0F 3 REVISION 1

-480 V Motor Control Centers -

TRAIN.A TRAIN B "

1. Relay Room Cooling Sys. Fan XFN-36A-AH XFN-36B-AH
2. Traveling Screen XRS-2A-SW IRS-23-SW 3 Traveling Screen (Swing) (XRS-2C-SW) 4 ESP Swgr. Room Cooling Sys. Fan XFN-50-VL XFN-76-VL 5 Service Water Intake Vent. Fan IPN-80A-AH XFN-80B-AH
6. Cdntrol Rm. Emerg. Filter Sys. Fan XFN-30A-AH XFN-30B-AH 1 7 Control Rm. Normal Supply Fan XFN-32A-AH XFN-32A-AH
8. Battery Rm. Supply Fan XFN-38A-AH XFN-38B-AH 9 Battery Rm. Exhaust Fan XFN-39A-AH XFN-39B-AH
10. Speed Switch ~ Room Fan XFN-106A-AH XFN-106B-AH
11. MCC Fans IFN-133-AH XFN-133-AH The following. equipment is tripped from the bus and sequentially  ;

loaded once Load Block 1 is energized. j-l AFTER X SECONDS (APPROX)- LOADED STARTED i 5 -

, COMPONENT TRAIN A TRAIN B 3 IPP-31A-RH _XPP-31B-RH RHR Area Pump Fan (RRR), IPN-49A-VL XFN-49B-VL (Only if an'SI signal is present) 10 Service Wtr Pump XPP-39A-SW XPP-39B-SW (Swing - XPP-390-SW)

XPP-48A-VU Chilled Water Pump (XPP-48A-VUSwing - XPP-48C-VU) 15 . XPP-1B-CC Comp. Cooling Pump (XPP-1A-CCSwing 'XPP-1C-CC) '

20~ Emerg. FW Pump XPP-21A-EF XPP-21B-EF j Area Fan (EFW Pmp)~IFN-83A-VL XFN-83B-VL  ;

i 1

t.

. E0P-1 ATTACHMENT IV

' PAGE 3 0F 3 REVISION 1 AFTER X SECONDS ( APPROI) - T20AD STARTED - -

COMPONENT TRAIN A TRAIN B 25 RB Cooling Units Fan XFN-64A-AH/ Fan XFN-64B-AH. .

(1 per train) Motor MFN-97A-AH Motor MFN-97B-AH Fan XFN-65A-AH/ Fan XFN-65B-AH Motor MFN-970-AH Motor MFN-97D-AH 25 F. H. Bldg. XFN-23A-AH XFN-23B-AH Exhaust' Fan (only if bus.undervoltage is present) 30 HVAC Chiller XHX-1A-VU XHX-1B-VU

(Swing - XHX-IC-VC) 35 Setvice Water Booster Pump Area Fan XPP-45A-SW XFP-45B-SW

. XFN-81A-VL XFN-81B-VL

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'. E0P-1 ATTACHMENT VI PAGE 1 0F 2 REVISION 1

'PAMS INSTRUMENTS TH TC

1. Wide Range TH 0-700*Fi8%fufkRange hf-

- fg T{-jg

2. Pressurizer Level -

LI-459A, 460, 461 (Between Taps) i 25% Span 3 RCS Wide Range Pressure PI-402B, 403 0-3000 psi 1 8% Range

, 4 RB Pressure (Min 2 Channels) PI-950, 951, 952, 953

(-5 to + 65 psig) 4%

5 Steam Line Press. 2/ steam Line A PI-475, 476, 474 0-1300 psig + 4% F.S B PI-485, 486, 484 C PI-495, 496, 494

6. -Steam Gen. Level-(Narrow or Wide Range) 0-100% Sufficient A LI-474, 475, 476 Narrow 3/SG- B LI-484, 485, 486 C LI-494, 495, 496 7 RWST Level 0-100% 1 3% of Span LI-990, 991 Tank A Tank B
8. BA Tanks' Level (2) LI-106 LI-108 0-100% 1 5% FS LI-161 LI-163 ,

9 RB Sump Temperature (2 Channels) TI-1971 50-350*F 1 5% TI-1972

10. RB Spray Pump Flow (2 Channels) A-FI-7368 1 0-3000 gpm i 10% B-FI-7378 )

t

11. RB Temp. 2 Channels. TI-9201A ,.

50-350*F 1 5% TI-9203A

12. RB Sump Level (2 Channels) LI-1963 0-12 Ft i 10% LI-1964
13. RB Sump Level-(2 Ch) LI-1975 0-12 1-10% LI-1976
14. Condensate. Storage-Tank (2-Ch) LI-3621A 0-40 Ft i 3% LI-3631B

. E0P-1 ATTACHMENT VI.

PAGE 2 0F 2 REVISION 1 15.' ' Emergency Feedwater Flow (one/each S/G)* A-FI 's561

~

0-300 gpm + 10% ' ~

B-FI~3571 - -

C 'tI-3581

16. RB Cooling Unit'SW Flow (one/SW Booster Pump) 0-5000 gym + 10%

FI-4466 FI-4496 17 SW Temp in & out of RB Cooling Unit one pair on each of 2 loops In TI-4480 4510 T in 0-150*F T out 0-225*F 1 4% TI-4467 4497

18. Sodium Hydrox. Tank Level LI-7356 0-40 Ft i 5% LI-7358 i

4

- .. ... . . - - . ~ . -

- .. . . - . . - . .- . . - ~ .._

ESP-l',IATTACHMENT VII, PAGE 1 0F 2, Rev. 1 2 scc ,_l l l l l l l l l l l l l l l l l l l l l l l l l jjl__  : soc

_ M ATERI AL 3 B ASIS: -

I _

_ REACTOR VESSEL INTER. MINIMUM TEMPERATURE I _

_ SHELL- FOF: CRITICALifY -

( 551* F ) NI CU- 0.10 ,f 2250 ___ INITI AL RT =30 F 3 ' I 2250

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R T,, AFTER IOE Y f NORMAL OPKRATIN1G j _

I/4 T elO 7' F RANGE LIMITS f __

_ 3/4T 82*F l f _

b l I 2000 e f 2000 l / -_

- I I _

INSER / ICE LEAK TEST l 1 _

MINIMlJM TEMR-h I I l l l 17SC I i 1750

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_ ACCEPTABLE I l -

UNACCEPTABLE / REGION OF l __

'000 REGION OF 1 OPERATION f '

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_ O PE RATl ON j _

1500 _

- I _ $

(1)RCS PRESSURE /

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  • F/HR HEATUP R ATE - NORM AL O PER ATING CONDITIONS ,,,,,,,,,

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, i EOP-1 ATTACRMENT~VZI PAGE 2 0F 2 REVISION 1  !

l i

DETERMINING S/G PRESSURE TO MAINTAIN 50*F SUBCOOLED RCS -

1

1. Determine RCS pressure.and-draw a horizontal line to intersect the RCS. saturation - 50*F.line.

1 2. Draw a vertical line down to intersect the RCS saturation line.

3 Draw a horizontal line to intersect the RCS pressure axis to determine.the required S/G pressure.

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I - E0Pe1 ATTACHMENT VIII PAGE 8 0F 8 REVISION 1

-COMMENTS -

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TIME-

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- ATTACHMENT X' PAGE 1 0F 4

~ REVISION,1

SAFETY INJECTION RESET NOTE This attachment allows the operator-to gain control of critical plant equipment.necessary to regain control of RCS pressure and level and-to protect that-equipment from prolonged operation at
minimum: flow conditions.

1.0 - Resetcthe SI signal (Train A and B).

1.1 . Manually'reinitiate SI and go to Section 6.0 of Attachment 1I,; IF:

NOTE Monitor' parameters throughout-this procedure to. insure SI reset conditions'are satisfied.

~ 1.1.1 ' RCS pressure decreases by 200 psi.

1'.1.2 -PZR leve1' decreases-to 20%.

1.1 3 RCS subcooling of 50*F cannot be maintained.

1.2 RCS subcooling must-be at least 65*F on subsequent SI terminations.

This- can be accomplished - by raising RCS pressure by 200 psi over the pressure at which-SI was initially-terminated.

CAT 7 ION Automatic reinitiation of SI till not occur with the -reactor trip breakers open.

2.0 IF a loss of. power. occurs,.the RHR pumps must be manually restarted.

30 Reset the NON-ESP loads by-placing the ESF. Loading Sequencer Reset Control switch to. RESET NON-ESP LOCK 0UTS (Train A & B).

4.0 Start one Instrument Air-Compressor and place the other'in " Auto Start".

50 Establish normal' charging. Perform in a controlled. manner'such as not requiring a reinitiation of SI.

5.1 Open Charging' Pump combined-mini-flow (MVT-8106). .

^

5 2 -- Open individua1' charging pump mini-flow.-

1)- MVT-8109A 1

2) MVT-8109B -

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.3 ) ~ MVT--8109C d 'w

$ 9 y w p -y a- wwm  % ,w.-.e.- u- 1 y + p- - t

EOP-1 .

ATTACHMENT X PAGE 2 0F 4 '

REVISION 1 c SI RESET:

.5.3.).Stop. charging pumps not. required to maintain PZR level.-

5 4 =0penithe cha'rging line. stops.

.5 4.1. MVT-8107 5 4.21 MVT-8108 ,

6.0 Establish' normal letdown.

6.1 Verify-the letdown orifice block valves are not in local control by

. ensuring the following annunciators are not lit:

6.1.1 EVAC Panel "A" Remote Control Defeated (XCP-622) .

i 6.1.2 EVAC Panel "B"' Remote Control Defeated (XCP-623).

6.2 Reset Containment Phase A Isolation (Train A & B).

6. 3' Establish instrument air to-the. reactor. building by opening:

I

.631 RB Air Service Isolation (PVT-2662A). ,

632 RB Air .Se rvice . Isolation (PVT-2662B) .

633 RB Air Service Isolation (PVT-2660).

. 6.4 -Open RCS Letdown Isolation (PVT-8152).

~

6 5- Open Letdown orifice blocks as necessary:

~

6 . 5 .1. 45 spm orifice-isolation (PVT-8149A).

6.5 2l 60 gpm : orifice isolation- (PVT-8149B) .

6.5 3J 60-gpm; orifice isolation (PVT-8149C).

7.0- Transfer chargingEpump suction to the VCT.

' 7 . -1. Open VCT Outlet Isolation 9

i 7.1.1 .LCV-1150-7.1.2~ LCV-!!5E:

- EOP ATTACHMENT X' PAGE 3 0F 4

, REVISION 1

, SI RESET 17.2 close RWST-to charging pump s'uctions.

4 7.2.1 'LCV-115B.

1 7 . 2 '. 2 .LCV-115D 8.0 Terminate BIT injection:

- . ' 8.1 ' Close the-BIT valves..

8.1.1 BIT' outlet (MVG-8801A)

.8.1.2 7 BIT outletT(MVG-8801B) '

1 8.1 3 BIT inlet-(MVG-8803A)

~

8.1.4 BIT inlet.(MVG-8803B):

8.2 'Make preparation to increase-BIT boron concentration to-20,100 ppm per SOP-112.

i 4

I:

9.0- Establish--seal return by opening the RCP Seal Water Return stops.:

91 .MvT-8100 l 9 .' 2 MVT-8112

10.0 Adjust-~ seal injection' to' 6-13 gpm for. each RCP.

11'.O Tur,nson~the.PZR backup heaters.

12.0 .Stop'any operating RHR oumps.

13 0-.Close the following valves?bo realign the RB Spray System:

13 1~ Na0)I.to Spray Pump Suction.

13 1.-1 Pump?A - MVG-3002A 13 1.2 . Pump B!- MVG-3002B~ i

, -13 2 Spray Header Isolation

.g 1-312'.1- Header AI- MVG-3003A n v- -, . - - ,.m . - ,- ,, ,,-, p . - + rg,--y , g

E0P-1 .

ATTACHMENT X PAGE 4 0F 4 REVISION 1 SI RESE'r 13 2.2 Hender B - MVG-3003B.

14.0 For complete reset of SI instructions, continue per 80P-112, Section 6.6, Ster N, page 31.

4

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