ML20154J099

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Operating Manual;Emergency Operating Procedures
ML20154J099
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 02/10/1988
From: Grooms J
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20154J106 List:
References
PROC-880210, NUDOCS 8809220245
Download: ML20154J099 (616)
v • d • e


Text

_ _ _ _ _ _ _

E P-0 R;v. 1/ Unit 1 Page 1 of 13 l I e

CALVERT CLIFFS NUCLEAR POWER PLANT FOP-O POST-TRIP IMMED_IATE_hCTION!!

REVISION 1 SIGNATURE DATE PREPARED BY; ' nti 1 Y._qwoJe / / 2. //b 'E T'

, I- N s N.

j l VERIFIED BY; N s

. . - , y

/ l E NE$~'$$

s POSRC; MEET _ LNG # F6'l / 2 so - 7/6 APPROVED BY; _

  • , s cc,# / l' W ' 'C*#>

!%nkge,'r-Nuclear Operations or General Supervisor-bperations if POSRC review is not required

)

1 I

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EOP-0 R'sv. 1/ Unit 1 Pega 2 Of 13 I I krJ_T OF_ EFFECTIVE PAGES M=WEEB

- REVISION 1 1 2 3 3 y 4 3 5 y 6 y 7 3 8 y

' 1 10 y 11 y 12 y 13 y l I i

E'iP- 0 R v. 1/ Unit 1 Page 3 of 13 POST-TRIP Il#UtDIATE ACTIONS I. ERECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safet/ function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments.

D. If a pump or component tails, the'cause of the failure should be determined prior to restarting or starting a standby pump or component to prevent a common failure.

II. EfIRY _ CONDITIONS l h The below listing constitutes the most immediate and reliable indication of a reactor trip:

A. Reactor Trip Bus U/V Reisy Trip alarm.

B. CEA Trip Circuit Breaker (s) Trip alarm (s).

C. Rapidly decreasing Generator output.

D. Protective Channel Trip alarm.

E. RPS Trip Bistable Lights lit.

l I l 1

EOP-O R;v. 1/ Unit 1 Pcga 4 of 13 III. IIOfFDIATE ACTIONS ALTERNATE ACTIONS A. MONITOR REACTIVITY CONTROL:

1. Depress one set of Manual  ;

Reactor Trip Buttens

2. Ensure prompt drop in 2.1 IE reactor MOT tripped, NI power. THEN de-energize C"DM Motor Generator Sets: l i
a. Oper. feeder breaker to 12A l

480V Bus, i

b. Open feeder breaker to 13A l 480V Bus, j 4
c. Open tie breakers to 12A and 13A 480V Buses.
3. Ensure all CEAs fully 3.1 If one CEA fails to fully l inserted. insert, l THEN borate 200 ppm:

l l a. Open Boric Acid Direct l Makeup Valve, 1-CVC-514-MOV.

b. Start a Boric Acid Pump. l
c. Start all available Charging Pumps.

3.2 IE more than one CEA fails to fully insert, THEN borate the RCS to 2300 ppm.

B. MONITOR RCS PRESSURE AND INVENTORY CONTRO*:

1. Ensure pressurizer level 1.1 Operate charging and letdown stabilizes between 8C to restore pressurizer level, and 180 f.nches.

EOP-0 R v. 1/ Unit Pcga 5 of 13 I. IMMEDIATE ACTIONS ALTERNATE ACTIONS

2. Ensure pressurizer 2.1 Operate beaters and sprays pressure stabilizes to restore pressurizer between 1850 and 2275 pressure.

PSIA.

2.2 Verify PORVs open at 2400 PSIA and shut by 2300 PSIA.

2.3 If RCS pressure decreases to 1725 PSIA, THEN verify SIAS actuation.

2.4 Implement RCP trip strategy:

a. II[ RCS pressure decreases to 1725 PSIA, THEN trip 11A and 12B RCPs OB trip 11B and 12A RCPs.
b. If positive LOCA indications exists (1) RCS subgooling less than 30 F.

{ g (2) Steady S/G pressure.

(3) S/G Blowdown RMS alarms clear, OR Main Vent Gaseous RMS (1-RI-5415) alarm clear.

AND RCS pressure decreases to less than 1300 PSIA, TIIEN trip all RCPs.

c. IE RCS temperature and pressure are less than the minimum pump operating limits per the RCP curve on Attachment (1),

TIIEN trip all RCPs.

d. 1E CIS has actuated, DIE!J trip all RCPs.
3. insure RCS subcgoling greator than 30 F.

EOP-0 R;v. 1/ Unit 1 Page 6 of 13 II. IMMEDIATE ACTIONS ALTERNATE ACTIONS C. MONITOR CORE AND RCS HEAT REMOVAL:

1. Ensure both S/G levels 1.1 IF S/G level decreases to above (-)170 inches. (-)170 inches, THEN verify AFAS actuation.

Ensure feed rate is 2.1 IF feed flow is lost OR maintaining a constant level excessive, or controlled increase in THEN perform the following:

S/G 1evel, a- Trip the S/G Feed Pumps,

b. Shut the S/G Feedwater

, Isolation Valves,

c. Initiate AFW when feed flow required.
3. Ensure proper operation 3.1 Operate Turbine Bypass or of Turbine Bypass and Atmospheric Dump Valves to j Atmospheric Dump Valves: restore S/G pressure and

) Tcold,

a. S/G pressures stabilize batween 3.2 IF S/G pressure decreases 850 and 920 PSIA. to 800 PSIA, THEN shut both MSIVs.
b. Tcold stabilizes between 525 and 535 F. 3.3 IF S/G prossure decreases to 685 PSIA, THEN verify SGIS actuation.

1 D. MONITOR VITAL AUXILIARIES. l I

1. Ensure 11 or 14 4KV 1.1 IF both 4KV vital buses are l Bus energized. de-energized,

_TREN start 11 or 12 D/G AND close the associated D/G output breaker.

I I

EOP-0 R$v. 1/ Unit 1 Paga 7 of 13 III. IMMEDIATE ACTIONS ALTERNATE ACTIONS l I 1.2 IF the /G fails to load, THEN perform the following:

a. Verify D/G output breaker open,
b. Place the 4KV Bus LOCI /SD Sequencer Manual Initiate Keyewitch in ON.
c. Close the alternate 4KV feeder breaker.

E. MONITOR NORMAL CONTAINMENT ENVIRONMENT: ,

1. Ensure containment pressure 1.1 IF containment pressure less than 0.7 PSIG. increases to 2.8 PSIG, THEN verify LSFAS actuation:
a. SIAS.
b. CIS AND trip all RCPs.

1.2 IE containment pressure increases to 4.25 PSIG, ,

THEU verify CSAS actuation. l l

2. Ensure containment '

temperature less than 120 F.

3. Ensure containment radiction monitor alarms clear.

F. MONITOR NORMAL RADIATION LEVELS EXTERNAL TO CONTAINMENT: i l

1. Ensure Main Vent Gaseous RMS (1-RI-5415) alarm clear, i
2. Ensure Condenser Off-Gas and 2.1 IF Condenser Off-Gas OR S/G Blowdown RMS alarms clear. S/G Blowdown RMS alarm (s) g g received, THEU secure S/G Blowdown.

EOP-O I Rcv. 1/ Unit 1 Page 8 of 13 G. ARE POST-TRIP IMMEDIATE ACTIONS COMPLETED AND SAFETY FUNCTIONS WITHIN ACCEPTANCE CRITERIA?

YES NO IS DIAGNOSIS _ NO POSSIBLE ~

?

" IS ,

DIAGNOSIS POSSIBLE YES USING BREAK IDENTIFICATIOb CHART?

NO IMPLEMENT IMPLEMENT IMPLEMENT REACTOR APPROPRIATE FUNCTIONAL TRIP EVENT BASED RECOVERY (EOP-1) PROCEDURE PROCEDURE (EOP-8)

AND REFER l ) TO ERPIP END OF SECTION III.

EOP-0 Rov. 1/ Unit 1 Pcgo 9 of 13 BREAK IDENTIFICATION CHART PRESSURIZER LEVEL CHANGING AND PRESSURIZER PRESSUAE RAPIDLY DECREASING YES S/G PRESSURE NO ABNORM *,LLY LOW EXCESS STEAM PRIMARY DEMAND EVENT SIDE BREAK YES dONTAINME! NO YES PRESSURE CONTAINMENT N NO PRESCURE NCREASING NCREAS!?

W 1 ACTIVITY IN YES NO STEAM PLANT EXCESS STEAM EXCESS STEAM DEMAND EVENT DEMAND EVENT STEAM INSIDE SMALL EREAK OUTSIDE LOCA INSIDE GENERATOR LOCA OUTSIDE CO!CAINMENT CONTAINMENT CONTAINMENT TUBE RUPTURE CONTAINMENT l l k

EOP-O R;v. 1/ Unit 1 Page 10 of 13 IV. INITIAL SAFETY FUNCTION STATUS CHECK A. The STA (or person designated by the STA) will perform the safety function statue check on entry into this procedure.

B. Immediately notify Shift Supervisor or Control Room Supervisor if any eafety function criteria is not being satisfied.

C. Notify the Control Room Supervisor and Control Room Operator when initial status check is completed.

D. Review and verify that safety function acceptance criteria are satisfied.

REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL PARAMETERS CRITERIA STATUS CHECK

{ lo. WRNI power less than 5%

b. SUR (DPM) negative
c. CEA status all inserted or or Boration status greater than 40 (GPM)

I 1

I EOP O R;v. 1/ Unit 1 Page 11 of 13 I h RCS PRESSURE AND SAFETY FUNCTION ACCEPTANCE CRITERIA INVENTORY PARAMETERS CRITERIA STATUS CHECK

o. Pressurizer pressure 1850 to 2275 (PSIA)
b. Pressurizer level 80 to 180 (inches)
c. RgS subcooling greater than 30

( F) l l CORE AND RCS HEAT SAFETY FUNCTION ACCEPTANCE CRITERIA REMOVAL PARAMETERS CRITERIA STATUS CHECK l

l

c. Rg5 Teold 525 to 535 l

( F)  !

1

b. TgotminusTcold less than 10 1

( F) l

c. # RCPs operating 1 or 2 por loop
d. S/G pressure 850 to 920 _

(PSIA)

o. S/G level (-)170 to (+)30 _

(inches)

{ ) . . _ -

EOP-O R;v. 1/ Unit 1 Pcga 12 of 13 4

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VITAL SAFETY FUNCTION ACCEPTANCE CRITERIA AUXILIARIES CRITERIA STATUS CHECK

o. 4KV vital buses energized 11 or 14
b. Instrument Air greater than 88 pressure (PSIG)
c. Component Cooling 1 or 2

(# pumps running) l

d. Saltwater 1 or 2 ,

(# pumps running)

o. Service Water 1 or 2

(# pumps running)

f. 125V DC buses energized l 11, 12, 21, 22
g. 120V AC vital buses energized 11, 12, 13, 14 l
h. 208/120V Instrument i Bus 11 or 12 energized NORMAL CONTAINMENT SAFETY FUNCTION ACCEPTANCE CRITERIA ENVIRONMEtrI' PARAMETSitS CRITERIA STATUS CHECK
a. Containment less than 0.7 presouro (PSIG)
b. Contairement less than 120 temperature ( F)
c. Containment less than 4 j ) level (inches)
d. Containment radiation alarms clear

EOP-O Rev. 1/ Unit 1 Pago 13 of 13 I

NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL TO CONTAINMENT CRITERIA STATUS CHECK

a. Noble Gas Monitor alarm clear
b. Condenser Off-Gas alarm clear RMS
c. S/G B/D RMS alarm clear
d. Main Vent Gaseous alarm clear RMS (1-RI-5415)  ;,(

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EOP-0 Rav. 1/ Unit 2 Page 1 of 13 l I ,

CALVERT CLIFFS NUCLEAR POWER PIANT EOP-O POST-TRIP IMMEDIATE ACTIONS REVISION 1

, GNA DATE PREPA k BY; __ \ IM N x ' / k1" -

VERIFIED BY; nt/& d F itf & / /2//8((7 POSRC;

/

__ETING # 3 72 - 7 / 7 '\C 83 APPROVED BY; _h ugua / 2 to.'at _

!$4ndgeY' Nuclear Operations or Oeneral Supervisor-Operations if POSRC review is not required i I

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EOP-0 l R2v. 1/ Unit 2 i Pago 2 of 13 l 1

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.- i LIST OF EFFECTIVE PAGES i PAGE NUMBER REVISION 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1

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11 1 12 1 13 1

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EOP-0 Rov. 1/ Unit 2 Pcgo 3 of 13

< ) POST-TRIP IMMEDIATE ACTIONS I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a m- function is apparent or automatic system operation will not apport the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should,be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments.

D. If a pump or component fails, the'cause of the failure should be determined prior to restarting or starting a standby pump or component to prevent a common failure.

i II. ENTRY CONDITIONS The below listing constitutes the most immediate and reliable indication of a reactor trip:

A. Reactor Trip Bus U/V Relay Trip alarm.

B. CEA Trip Circuit Breaker (s) Trip alarm (s).

C. Rapidly decreasing Gcnerator output.

D. Protective Channel Trip alarm.

E. RPS Trip Bistable Lights lit.

I I

EOP-O RCV. 1/ Unit 2 Pcga 4 of 13 IMMEDIATE ACTIONS ALTERNATE ACTIONS JII.

I > .

A. MONITOR REACTIVITY CONTROL:

1. Depress one set of Manual Reactor Trip Buttons.
2. Ensure prompt drop in 2.1 If reactor NOT tripped, NI power. THEN de-energize CEDM Motor Generator Sets:
a. Open feeder breaker to 22A 480V Bus,
b. Open feeder breaker to 23A 480V Bus.

'c. Open tie breakers to 22A and 23A 480V Buses.

3. Ensure all CEAs fully 3.1 If one CEA fails to fully inserted. insert, THEN horate 200 ppm:

I I a. Open Boric Acid Direct Makeup Valve, 2-CVC-514-MOV.

b. Start a Boric Acid Pump.
c. Start all available Charging Pumps.

3.2 If more than one CEA fails to fully insert, TIIEN borate the RCS to 2300 Ppm.

B. MONITOR RCS PRESSURE AND INVENTORY CONTROL: l

=

l

1. Ensure pressurizer level 1.1 Operate charging and letdown I stabilizes between 80 to restore pressurizer level, and 180 inches.

I l I 1

EOP-O R v. 1/ Unit 2 Pcga 5 of 13

'II. IPMEDIATE ACTIONS ALTERNATE ACTIONS I I

2. Ensure pressurizer 2.1 Operate beaters and sprays pressure stabilizes to restore pressurizer between 1850 and 2275 pressure.

PSIA.

2.2 Verify PORVs open at 2400 PSIA and shut by 2300 PSIA.

2.3 1E RCS pressure decreases to 1725 PSIA, TdEN verify SIAS actuation.

2.4 Implement RCP trip strategy:

a. IE RCS pressure decreases to 1725 PSIA, THEN trip 21A and 22B RCPs OR trip 21B and 22A RCPs.
b. IE positive LOCA indications exists (1) RCS subgooling less than 30 F.

q g (2) Steady S/G pressure.

l (3) S/G Blowdown RMS alarms clear, OR Main Vent Gameous RMS (2-RI-5415) alarm .

clear.

AND RCS pressure decreases to less than 1300 PSIA, TlIEN trip all RCPs.

1

c. IE RCS temperature and I pressure are less than the minimum pump operating ,

limits per the RCP curve I on Attachment (1),

TEEN trip all RCPs.

d. IE CIS has actuated, THEU trip all RCPs.
3. Ensure RCS subcgoling greater than 30 F. l l I 1

E0P-0 R;v. 1/ Unit 2 Page 6 of 13 I. IMMEDIATE ACTIONS ALTERNATE ACTIONS C. MONITOR CORE AND RCS HEAT REMOVAL:

1. Ensure both S/G levels 1.1 IF S/G level decreases to above (-)170 inches. (-)170 inches.

THEN verify AFAS actuation.

2. Ensure feed rate is 2.1 IF feed flow is lost OR maintaining a constant level exceseive, or controlled increase in THEN perforra th' following:

S/G level. a. Trip she S/G Feed Pumps.

b. Shut '.he S/G Feedwater Isolation Valves.
c. Initiate AFW when feed flow required.
3. Ensure proper operation 3.1 Operate Turbine Bypass or of Turbine Bypass and Atmospheric Dump Valves to Atmospheric Dump Valves: restore S/G pressure and

{ g Tcold,

a. S/G pressures stabilize between 3.2 IF S/G pressure decreases 850 and 920 PSIA. to 800 FSIA, TIIEN shut both MSIVs.
b. Tcold stabilizes between 525 and 535 F. 3.3 IF S/G pressure decreases to 685 PSIA, THEN verify SGIS actuation.

~

1 D. MONITOR VITAL AUXILIARIES.

i I

1. Ensure 21 or 24 4KV 1.1 IF both 4KV vital buses are Bus energized. de-energized, THEN start 21 or 12 D/G l AND close the associated l D/G output breaker, j l

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EOP-0 Rcv. 1/ Unit 2 Page 7 of 13

'II . IMMEDIATE ACTIONS ALTERNATE ACTIONS l I 1.2 If the D/G fails to load, THEN perform the following

a. Verify D/G output breaker open.
b. Place the 4KV Bus LOCI /SD Sequencer Manual Initiate Keyswitch in ON.
c. Close the alternate 4KV feeder breaker.

E. MONITOR NORMAL CONTAINMENT ENVIRONMENT: ,

1. Ensure containment pressure 1.1 IF containment pressure less than 0.7 PSIG. increases to 2.8 PSIG, THEN verify ESFAS actuation:
a. SIAS.
b. CIS AND trip all RCPs.

1.2 IF containment pressure increases to 4.25 PSIG, THEN verify CSAS actuation.

2. Ensure containment temperature less than 120 F.
3. Ensure containment radiation monitor alarms clear. ,

I F. MONITOR NORMAL RADIATION LEVELS EXTERNAL TO CONTAINMENT:

)i

1. Ensure Main Vent Gaseous RMS (2-RI-5415) alarm clear.
2. Ensure Condenser Off-Gas and 2.1 If Condenser Off-Gas OR S/G Blowdown RMS alarms clear. S/G Blowdown RMS alarm (s) received, I l l p.!EN oecure S/G Blowdown. l l

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EOP-O Rov. 1/ Unit 2 Pcgo 8 of 13 I > .

G. ARE POST-TRIP IMMEDIATE ACTIONS COMPLETED AND SAFETY FUNCTIONS WITHIN ACCEPTANCE CRITERIA?

YES NO IS DIAGNO3IS NO POSSIBLE ,

?

\

IS IAGNOSIS POSSIBLE j ) YES USING BREAK IDENTIFICATIO1 CHART?

\

NO IMPLEMENT IMPLEMENT IMPLEMENT REACTOR APPROPRIATE FUNCTIONAL TRIP EVENT BASED RECOVERY (EOP-1) PROCEDURE PROCEDURE (EUP-8)

AND REFER TO ERPIP END OF SECTION III.

EOP-0 R0v. 1/ Unit 2 Page 9 of 13 l l RREAK . IDDUIFICATION. CHART PRESSURIZER LEVEL CHANGING A}O PRESSURIZER PRESSURE RAPIDLY DECREASING l

YES S/G PRESSURE NO i ABHORMALLY LOW l

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EXCESS STEAM PRIMARY l DEMA?C EVE!C SIDE BREAK YES CONTA!!W ,, NO YES COtCA!!NEtC NO PRESSUR2 PRESSURE NCREASING NCREASING 1

i YES ACTIVITY IN NO STEAM PLANT I

EXCESS STEAM EXCESS STEAM DEMAND EVENT DEMAND EVENT STEAM SMALL BREAK INSIDE OUTS!DE LOCA INSIDE GENERATOR LOCA OUTSIDE CONTA!! MENT CO!CA!NME!C CO!CA!!NINT TUBE RUPTURE CONTA!!NENT I l

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ECP-O R;v. 1/ Unit 2 P;ga 10 of 13 l I IV. INITI AL SAFETY NfION STATUS CHECK A. The STA (or person designated by the STA) will perform the safety function status check on entry into this procedure.

B. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied.

C. Notify the Control Room Supervisor and Control Room Operator when initial status check is completed.

D. Review and v6rify that safety function acceptance criteria are natisfied.

4 REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL PARAMETERS CRITERIA STATUS CHECK l Ic. WRNI power less than 5%

b. SUR (DPM) negative
c. CEA status all inserted or or Boration status greater than 40 (GPM) l l

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E0P-0 RCv. 1/ Unit 2 Pcga 11 cf 13 RCS PRESSURE AND SAFETY FUNCTION ACCEPTANCE CRITERIA INVENTORY PARAMETERS CRITERIA STATUS CHECK

c. Pressurizer pressure 1850 to 2275 (PSIA)
b. Pressuri'er 4 level 80 to 180 (inches)
c. RgS subcooling greater than 30 _

( F)

I h CORE AND RCS HEAT SAFETY FUNCTION ACCEPTANCE CRITERIA REMOVAL PARAMETERS CRI'A ERI A STATUS CHECK

c. Rgs Teold 525 to 535

( F)

b. Tgot minus Tcold less than 10

( F)

c. # RCPs operating 1 or 2 per loop
d. S/G pressure 850 to 920 (PSIA)
o. S/G level (-)170 to (+)30 __

(inches)

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EOP-0 R;v. 1/ Unit 2 Pcg3 12 of 13 VITAL SAFETY FUNCTION ACCEPTANCE CRITERIA AUXILIARIES CRITERIA STATUS CHECK

0. 4KV vital buses energized 21 or 24
b. Instrument Air greater than 88 pressure (PSIG)
c. Component Cooling 1 or 2

(# pumps running)

d. Saltwater 1 or 2 ,

(# pumps running)

o. Service Water 1 or 2

(# pumps running)

f. 125V DC buses energized 11, 12, 21, 22
g. 120V AC vital buses energized 21, 22, 23, 24
h. '08/120V Instrument Bus 21 or 22 energized NORMAL CONTAINMENT SAFETY FUNCTTofi ACCEPTANCE CRITERIA ENVIRON'iENT PARAMETERS CRITERIA STATUS CllECK
a. Containment less than 0.7 pressure (PSIG)
b. Containment less than 120 l

temperature ( F)

c. Containment less than 4 t

{ g levn1 (inchen)

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d. Containment radiation alarms clear 1

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EOP-0 R v. 1/ Unit 2 Pcg3 13 of 13 l l ,

NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL TO CONTAINMENT CRITERIA STATUS CHECK

o. Noble Gas Monitor alarm clear
b. Condenser Off-Gas alarm clear RMS
c. S/G B/D RMS alarm clear
d. Main Vent Gaseous alarm clear ,

RMS (2-RI-5415) s

< i s

EOP-1 R0v. 1/ Unit 1 Pcg3 1 of 14 I I .

CALVERT CLIFFS NUCLEAR POWER PLANT EOP-1 REACTOR TRIP REVISION 1 SIGNATURE DATE PREPARED BY; 4hy/ .

Mrvj- / /J 8/ ' 7 T' s M l ) VERIFIbnv. . v,6s / l1-b-

,3 A 3

POSRC; MEETING # 9 "d ~l / 7 'O-%%

l APPROVED BY; _IN Aaa# / I' \C ' %

Wadat;ffif-Nucioar Operations or General Supervisor- 1 Operations if POSRC review is not required I

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EOP-1 R v. 1/ Unit 1 Paga 2 of 14 I I t

LIST OF EFFECTIVE PAGES PAGE NUMBER 1 1 2 1 3 1 4 1 5 1 6

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EOP-1 R;v. 1/ Unit 1 Pcg3 3 of 14 l I REACTOR TRIP I. PRECAUTIONE A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments.

D. If a pump or component fails, the'cause of the failure should be determined prior to restarting or starting a standby pump or component to prevent a common failure.

II. ENTRY CONDITIONS A. Post-Trip Immediate Actions are completed.

B. Safety Functions are within Acceptance Criteria of EOP-0.

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EOP-1 RSv. 1/ Unit 1 Pcg3 4 of 14

'II. RECOVERY ACTIONS ALTERNATE ACTIOHC l l A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED.

B. COMMENCE INTERMEDIATE SAFETY FUNCTION STATUS CHECK.

C. LONFIRM TURBINE TRIPS i

1. Check Turbine Stop Valves shut 1.1 ,. Depress Turbine Trip Button. ;

and speed decreasing. i

2. Check Turbine Generator 2.1 IF an output breaker remains output breakers opent closcd AND unable to confirm )

Turbine Stop Valves shut, '

a. 11 Generator Bus THEN shut both MSIVs.

Breaker, 552-22.

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b. 11 Generator Tie Breaker, 552-23. l l
3. Verify 11 Generator Field I I

Breaker open.

4. Verify 11 Exciter Field Breaker open.

D. RESTORE NORMAL PRESSURIZER LEVEL.

1. Verify charging and letdown flow restoring pressurizer level to between 130 and 100 inches.

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EOP 1 R;v. 1/ Unit 1 Pcga 5 of 14

'II . RECOVERY ACTIONS ETERNATE ACTIONS

( l E. RESTORE NORMAT FRfSSURIZER PRESSURE.

1. Verify heaters or sprays restoring pressurizer pressure to between 2225 and 2275 PSIA.

F. MAINTAIg Tcold BE7VEEN 525 AND 535 F:

1. Verify proper operation of 1.1 ..IF Tcold decreases to 525 F, turbine Bypass and THEN perform the following:

Atmospheric Dump Valves.

a. Shut S/G Blowdown Valves:

1-BD-4010-CV 1-B9-4011-CV 1-BD-4012-CV l I 1-BD-4013-CV .

b. Shut upstream drains by placing handswitch 1-HS-6622 in CLOSE.
1. 2.

IF fcold 518 decreason F (800 PSIA S/G to pressure),

TIIEN perform the following

a. Shut both MSIVs.

- CAUTIOff -

D/G nupplying pcuer to 13 AFW Pump flow limit in 300 GPM; othorwine, flow limit in 576 GPM.

b. Stact 13 AFW Pump.
c. Shift Gland Seal to Auxiliary Steam by performing the following: >

(1) Vorifi> Auxiliary Steam available.

{l }

EOP-1 R v. 1/ Unit 1 Pcgo 6 of 14 "II. _RECO @RY ACTI.ONS ALTERNATE ACTIONS l I (2) Open Aux Steam To Gland Seal Valve, 1-TGS-4678-MOV.

(3) Shut Main Steam To Gland Seal Valve, 1-TGS-4659-MOV.

2. Verify MSR Second Stage Steam Source Valves shut:

1-MS-4025-MOV 1-MS-4026-MOV

3. Verify Main Feed Regulating Valves shut and S/G feed rate allowing proper temperature control. ,

G. RESTORE NORMAL S/G WATER LEVEL:

- CAUTION -

Severe waterhammer may occur if Main Yeed Ring is allowed to drain then subsequently refilled.

1. Establish a shutdown feed system lineup:
a. One operating S/G 1.a.1. IF S/G Feed Pump NOT Feed Pump, available, IIIEN perform the following:

- CAUTION -

D/G supplying power to 13 AFW Pump flow limit is 300 GPM; otherwise, flow limit is 573 GPM.

a. Start an AFW Pump,
b. Shut S/G Esedwater Isolation Valves:

1-FW-4516-MOV 1-FW-4517-MOV l I

EOP-1 R;v. 1/ Unit 1 ,

PCga 7 of 14 II. RECOVERY ACTIONS ALTERNATE ACTIONS

b. One operating Condensate Booster Pump,
c. One operating condensate Pump.
d. Both Heater Drain Pumps secured.
2. Ensure Main Feed rate: 2.1 Operate AEW tot
a. Slowly increasing S/G a. Slowly raise S/G level level. to between 0 tr.d (+)30 inches.
b. Maintaining,Tcold between 525 and 535 F. b. Maintain Tcgid between 525 and 535 F.

2.2 WHEN S/G level is between 0 and (+)30 inches AND Main Feed is available, THEN initiate Main Feed.

3. WHEN manual control of feed I h flow rate desired OR S/G levels between (-)24 and (+)30 inches, THEN perform the following
a. Depress Feed Regulating Bypass Valve Roset Buttons.
b. Adjust Feed Regulating Bypass Valves to raise S/G levels to approximately 0 inches.
4. WIIZH S/G 1evels are 0 inches, TIIEN shif t Feed Regulating Bypass Controllers to AUTO.
5. 1F S/G level exceeds (+)30 5.1 IF operating AFW AND S/G inches during the recovery, level exceeds (+) 30 inches, THEN je-late appropriate THEN shut appropriate AFW feed win: Flow Control Valves:
a. Le:t appropriate Feed _1_1 S/G 12 S/G <

1egulating Bypass Valve. l 1-AFW-4511-CV 1-AFW-4512-CV

b. Shut appropriate Main Feed 1-AFW-4525-CV 1-AEW-4535-CV

{ }

Regulating Valve,

c. Shut appropriate S/G Feedwater Isolation Valve.

EOP-1

' rov. 1/ Unit 1 Pcg3 8 of 14 I. RECOVERY _ ACTIONS ALTERNATE ACTIONS

6. 6.1 H opera $ing AFW AND S/G H S/G level n.*.ceeds _

level exceeds (+)50 inches,

(+)50 inches _AND increasing, 2]IEH trip both S/G Feed THEN shut appropriate A*W Pumps. Block valves:

11 S/G 12 S/G 1-AFW-4520 CV 1-AFW-4530-CV 1-AFW-4521-CV 1-AFW-4531-CV 1-AFW-4522-CV 1-AFW-4532-CV 1-AFW-4523-CV 1-AFW-4533-CV

7. H S/G level exceeds

(+)63.5 inches, LIEN shut appropriate MSIV.

8. WHEN recovery from high ,

level condition accomplirhed, THEN es:ablish Main Feed OR AFW flow.

g.

ENSURE SAFE TURBINE COASTDOWN:

1. Start Turning Gear Oil Pump.
2. Start Motor Suction Pump.

3 Start Turbine Oil Lift Pumps.

4. Start computer typed trend blocks 1 and 2 (turbine bearing temperatures) on a 1 minute update frequency.
5. Continue Main Turbine shutdown per OI-43A.

I. VERIFY FINAL SAFETY FUNCTION STATUS CHECK SATISFACTORY AND COMPLETE ADMINISTRATIVE POST-TRIP ACTIONS.

EOP-1 R;v. 1/ Unit 1 Pcg3 9 cf 14 l I 1 J. ADMINISTRATIVE POST-TRIP ACTIONS:

- NOTE -

The following actions may be accomplished whenever feasible. They may be done in any order.

1. Perform notifications per CCI-118.
2. Notify ESO of trip.
3. Request RCS boron sample.

__ 4. Perform shutdown margin calcylation per NEOG 2 and 7.

5. Document trip in transient log.
6. Recall post-trip review (preferably within 30 minutes of trip).
7. .erform post-trip review per CCI-111
8. Implement Reactor Trip Recovery (AOP-8) or appropriate operating procedures.

END OF SECTION III.

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EOP-1 Rov. 1/ Unit 1 PCgo 10 of 14 I >

IV. SAFETY FUNCTIO _H STATUS CHEC_K A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to exiting from this procedure.

B. Perform intermediate safety function status checks at 10 minute intervals until plant conditione stabilize.

C. Immediately notify Shift Supervisor or Control Room Supurvisor if any safety function criteria in not being satisfied.

I D. Review data and verify that safety function acceptance criteria are l satisfied.

E. When EOP completed, then perform final safety function check.

REACTIVITY CONTROL SAFETY FUNCTION ACCEPTANCE CRITERIA PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK l I

c. WRNI power less than 3% ___________ less than 1%
b. SUR (DPM) negative ___________

0 j

c. CEA status all inserted ,,,________

all inserted or l l

Boration status: )

appropriate l ccncontration increasing _____,_____

S/D margin __ l l

BAST level decreasing ___________ N/A N/A i

EOP-1 R;v. 1/ Unit 1 Pcg3 11 of 14 I I RCS PRESSURE AND SAFETY FUNCTION ACCEPTANCE CRITERIA INVENTORY PARAMETEPS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

c. Pressurizer pressure (PSIA) 1850 to 2275 ___________

2225 to 2275

b. Pressurizer trending pressure trend towards 2250 .. ________

N/A (PSIA)

c. Pressurizer level (inches) 101 to 180 _____,_____ 130 to 180
d. Pressurizer level trending trend (inches) towards 160 ___________ N/A
o. RgS subcooling 30 to 140 ___________

30 to 140

( F)

~

i I CORE AND RCS HEAT SAFETY FUNCTION ACCEPTANCE CRITERIA REMOVAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL i CHECK CHECK l 1

c. RCS Tcold ( F) 525 to 535 _______,____

530 to 535

b. TgotminusTeold

( F) less than 5 ____________

less than 5

c. # RCPs operating per loop 1 or 2 ___________,

1 or 2 l d. S/G pressure j (PSIA) 850 to 920 ____________

885 to 920 l

l o. S/G level (inches) (-)170 to (+)30____________ (-)24 to (+)30

f. S/G level trend trending trending (inches) towards 0 __________,_

towards 0 l I

EOP-1 R;v. 1/ Unit 1 Pcga 12 ef 14 l I VITAL AUXILIARIES SAFETY EUNCTION ACCEPTANCE CRITERIA j CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

o. 4KV vital buses 11 or 14 energized ___,,,,,,,__

energized l

b. Instrument Air greater greater preosure (PSIG) than 88 ,__________,

than 88

c. Component Cooling

(# pumps running) 1 oi 2 ,,,_,,______

1 or 2

d. Saltwater

(# pumps running) 1 or 2 ,___________

1 or 2

c. Service Water

(# pumps running) 1 or 2 ,_________,,

1 or 2

{ g f. 125V DC buses energized energized 11, 12, 21, 22 ,,__________

1

q. 120V AC vital buses energized ~~~~~~~-~~~'

energized 3, 14

h. Condenser vacuum greater greater (IN Hg) than 20 __________,,

than 20

EOP-1 R v. 1/ Unit 1 Pcg3 13 of 14 l I NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT ENVIRONMENT CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK

o. Containment pressure (PSIG) lecs than 0.7 ,___,,______

less than 0.7

b. Containment temperature ( F) less than 120 ____________

less than 120

c. Containment Gaseous Radiation alarm clear ____________

alarm clear

d. Containment level (inches) less than 4 _____,,______

less than 4 r

EOP-1 R v. 1/ Unit 1 Page 14 ef 14 l l NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL CRITERIA INTERMEDIATE CRITERIA FINAL TO CONTAINMENT CHECK CHECK

o. Noble Gau.

Monitor alarm clear _________,__

alarm clear

b. Cundenser Off-Gas RMS alarm clear ___________,

alarm clear

c. S/G B/D RMS alarm clear ____________

alarm clear

d. Main Vent Gaseous .

RMS (1-RI-5415) alarm clear ____________

alarm clear STATUS CHECK COMPLETE AT NUMBER TIME l I 1

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EOP-1 R'av . 1/ Unit 2 Page 1 of 14 l I CALVERT CLIFFS NUCLEAR POWER PLANT EOP-1 REACTOR TRIP REVISION 1 PREPARED A- /

I VERIFIED BY; /Lutl> d- / /1 /6 7 POSRC;

/

MEETING # Y6~l / DC' W

, APPROVED BY; ses / 2O-4%

. nager-Nuclear Operations or General Supervisor-Operations if POSRC review is not required I I

EOP-1 R:v. 1/ Unit 2 Pcg3 2 of 14 i > ,

LIST OF EFFECTIVE PAGES PAGE NUMBER _R_EVISION 1 1 9 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 l l 11 1 12 1 13 1 14 1 i

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EOP-1 R;v. 1/ Unit 2 Page 3 of 14 l I

, REACTOR TRIP I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inJonsistencies between instruments.

D. If a pump or component fails, the'cause of the failurc should be determined prior to restarting or starting a standby pump or component to prevent a common failure.

l l II. _ ENTRY CONDITIONS A. Post-Trip Immediate Actions are completed.

B. Safety Functions are within Acceptance Criteria of EOP-0, 1

EOP-1 R v. 1/ Unit 2 PCg3 4 Cf 14 II. _RE90VERY ACTIONS ALTERNATE _ ACTIONS l I o

A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED.

B. COMMENCE INTERMEDIATE SAFETY FUNCTION STATUS CHECK.

C. CONFIRM TURBINE TRIP

1. Check Turbine Throttle Valves 1.1 , Depress Turbine Trip Button, shut snd speed decreasing.
2. Check Turbine Generator 2.1 IF an output breaker remains output breakers opent closed AND unable to confirm Turbine Throttle Valves shut,
a. 21 Generator Bus THEN shut both MSIVs.

Breaker, 552-61.

q g

b. 21 Generator Tie Breaker, 552-63.
3. Verify 21 Exciter Field Breaker open.

D. RESTORE NORMAL PRESSURIZER LEVEL.

1. Verify charging and letdown flow restoring pressurizer level to between 130 and 180 inches.

I

EOP-1 R v. 1/ Unit 2 P g] 5 cf 14 III. .R_ECOVERY ACTIONS ALTERNATE ACTIONS

( l ._.

E. RESTORE NORMAL PRESSURIZER PRESSURE.

1. Vorify heaters or sprays restoring pressurizer pressure to between 2225 and 2275 PSIA.

F. MAINTAIgTeoldBETWEEN525 AND 535 F

1. Verify proper operation of 1.1 ,1F Teold decrosses to 525 F, Turbine Bypass and THEN perform the following:

Atmospheric Dump Valves.

a. Shut S/G Blowdown Valves:

2-BD-4010-CV 2-BD-4011-CV 2-BD-4012-CV 2-BD-4013-CV l

D

b. Shut upstream drains by placing handswitch 2-HS-6622 in CLOSE.

1.2 Iffcolddecreasesto 518 F (800 PSIA S/G pressure),

TIIEN perform the following

a. Shut both MSIVs.

- CAUTION -

D/G supplying power to 23 AFW Pump flow limit is 300 GPM; otherwise, flow limit is 575 GPM.

b. Start 23 AFW Pump,
c. Shift Gland Seal to Auxiliary Steam by performing the following:

(1) Verify Auxiliary Steam available.

( )

EOP-1 R3v. 1/ Unit 2 Pcg3 0 of 14 1II. RECOVERY ACTIONS AL_TE_RNATE ACTIONS i I (2) 'Open Aux Steam To Gland Se11 Valve, 2-TGS-4684-MOV.

(3) Shut Main Steam To Gland Seal Valve, 2-TGS-4659-MOV.

2. Deprenc Reset Button on MSR Control Panel and verify Second Stege Steam Source Valves shuta 2-MS-4017-CV 2-MS-4018-CV 2-MS-4019-CV 2-MS-4020-CV
3. Verify Main Feed Regulating Valves shut and S/G feed rate allowing proper temperature control.

l I. RESTORE NORMAL S/G WATER LEVEL:

- CAUTION -

Severe daterhemmer may occur if Main Feed Ring is allowed to drain then subsequently refilled.

1. Establish a shutdown feed system lineup:
a. One operating S/G 1.a.l. 1E S/G Feed Pump NOT Feed Pump. available, T)_1EU perform the following:

- guTLOg -

D/G r.upplying power to 23 AEW Pump flow limit is 300 GPM; otherwise, flow limit is 575 GPM.

a. Start an AFW Pump,
b. Shut S/G Feedwater Isolation Valves:

j )

2-ES-4516-MOV 2-rW-4517-MOV

, s

EOP-1 R;v. 1/ Unit 2 Pc.g3 7 of 14

'II. _ RECOVERY ACTIONS bLTERNATE ACTIONS i > .

b. One operating Condensate Booster Pump.
c. One operating Condensate Pump. 3,
d. Both Heater Drain Pumps secured.
2. Ensure Main Feed rate: 2.1 Operate AFW toi
a. Slowly increasing S/G a. Slowly raise S/G level level, to between 0 and (+)30 inches.
b. Maintaining,Tcold between 525 and 535 F. b. Maintain Tcgid between 525 and 535 F.

2.2 WHEN S/G 1evel is between 0 and (+)30 inches AND Main Feed is available, THEN initiate Main Feed.

3. hHEN manual control of feed I flow rate desired OR S/G levels between (-)24 and (+)30 inches, THEN perform the following
a. Depress Feed Regulating Bypass Valve Reset Buttons.
b. Adjust Feed Regulating Bypass Valves to raise S/G 1evels to approxitantely 0 inches.
4. WHEN S/G levels are O inches, THEN shift Feed Regulating Bypass Oontrollers to AUTO.
5. 1F S/G level exceeds (+)30 5.1 IF operating AFW SND S/G inches during the recovery, level exceeds (+) 30 inches, THEN isolate appropriate THEN shut appropriate AFW feed train: Flow Control Valves:
a. Shut appropriate Feed 21 S/G 22 S/G Regulating Bypass Valve.

2-AFW-4511-CV 2-AEW-4512-CV

b. Shut appropriate Main Feed 2-AFW-4525-CV 2-AEW-4535-CV l } Regulating Valve.
c. Shut appropriate S/G Feedwater Isolation Valve.

EOP-1 R v. 1/ Unit 2 Pcgo 0 of 14 I. BECOVERY_ ACTIONS ALTERNATE _ ACTIONS

6. If S/G level exceeds 6.1 1{ operating AFW 6HD S/G

(+)SO inches AND increasing, level exceeds (+)50 inches, THEN trip both S/G Feed THEN shut appropriate AFW Pumps. Block valves:

21 S/G 22 S/G 2-AFW-4520-CV 2-AFW-4530-CV 2-AFW-4521-CV 2-AFW-4531-CV 2-AFW-4522-CV 2-AFW-4532-CV 2-AFH-4523-CV 2-ADH-4533-CV

7. IE S/G 1evel exceeds

(+)63.5 inches, IDEU shut appropriate MSIV.

G. WHEN recovery from high .

level condition accomplin. d, JJUQ! establish Main Feed OR AFW flow, q g ENSURE SAFE TURBINE COASTDOWN:

1. Start Bearing Oil Pump.
2. Start Turbine Oil Lift Pump.
3. Start computer group display
  1. 1 (turbine bearing temperatures) on a 1 minute update frequency.
4. Continue Main Turbine shutdown per OI-43A.

J l

I. VERIFY FINAL SAFETY FUNCTION I STATUS CHECK SATISFACTORY AND COMPLETE ADMINISTRATIVE POST-TRIP ACTIONS.

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EOP-1 R v. 1/ Unit 2 Pcg3 9 cf 14 I I J. ADMINISTRATIVE POST-TRIP ACTIONS:

- NOTE -

The following actions may be accomplisbud whenever feasible. They may be done in any order.

1. Perform notifications per CCI-318.
2. Notify ESO of trip.
3. Request RCS boron sample.
4. Perform shutdown margin calculation per NEOt, 9 and 11.
5. Document trip in transient log.
6. Recall post-trip review (prei ably within 30 minutes cf l

trip).

1 q

7. Perform post-trip review per CC7-111.

l 8. Implement Reactor Trip Recovery (AOP-8) or appropriate i

operating procedures.

l END OF SECTION I!I.

< i

EOP-1 R;v. 1/ Unit 2 Page 10 of 14

( I IV. SAIXIT_ FUNCTION STATUS CITECK A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to exiting from this procedure.

B. Perform intermediate safety function status checks at 10 minute intervals until plant conditions stabilize.

C. Immediately notify Shift Supervisor or control Room Supervisor if any safety function criteria is not being satisfied.

D. Review data and verify that rafety function acceptance criteria are satisfied.

E. When EOP completed, then perform final safety function check.

REACTIVITY CONTROL SAFETY FUNCTION ACCEPTANCE CRITERIA PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK l I

c. WRNI power less than 3% ,,,,,,,,,,, less than 1%
b. SUR (DPM) negative ,,,,,,,,,,,

O

c. CEA status all inserted ,,,,,,,,,,,

all inserted or Boration status:

appropriate concentration increasing ,,,,,,,,,,,

S/D margin BAST level decreasing ,,,,,,,,,,, N/A N/A I I ,

i

E0P-1 RCv. 1/ Unit 2 Pcg] 11 cf 14 l I ,

RCS PRESSURE AND SAFETY FUNCTION ACCEPTANCE CRITERIA INVENTORY FINAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA CHECK CHECK

o. Pressurizer pressure (PSIA) 1850 to 2275 ,,,,,,,,,,,

2225 to 22'I5

b. Pressurizer trending pressure trend towards 2250 ,,,,,,,,,,,

N/A l

l i

(PSIA) l c. Pressurizer level (inches) 101 to 180 ,,,,,,,,,,,

130 to 180

d. Pressurizer level trending trend (inches) towards 160 ,,,,,,,,,,,

N/A 30 to 140 30 to 140

o. RgS subcooling ,,,,,,,,,,,

l

( F) l l I I

l l CORE AND RCS HEAT SAFETY FUNCTION ACCEPTANCE CRITERIA REMOVAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK o RCS Teold (*F) 525 to 535 ,,,,,,,,,,,,

530 to 535 b.TgotminusTeold less than 5

( F) less than 5 ----,,,,,,,,

l c. # RCPs operating per loop 1 or 2 ,,,,,,,,,,,,

1 or 2 i

l

[

d. S/G pressure j

(PSIA) 850 to 930 ,,,,,,,,,,,,

885 to 920 l

e. S/G level

( (inches) (-)170 to (+)30,,,,,,,,,,,, (-)24 to (+)30 l

trending trending i f. S/G level trend towards 0 (inches) towards 0 ,,,,,,,,,,,,

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EOP-1 Rcv. 1/ Unit 2 Page 12 of 14 l k VITAL AUXILIARIES SAFETY FUNCTION ACCEPTANCE CRITERIA CRITERIA INTERMEDIATE CRITERIA FINAL""

CHECK CHECK

c. 4KV vital buses 21 or 24 energized ,,,,,,,,,,,,

energized

b. Instrument Air greater greater pressure (PSIG) than 88 ___,,,,,,,,,

than 88

c. Component Cooling

(# pumps running) 1 or 2 ,,,_________

1 or 2

d. Saltwater

(# pumps running) 1 or 2 ,,,,,,______

1 or 2

o. Service Water

(# pumps running) 1 or 2 ,,,,,,,_____

1 or 2 f . 125V DC buses I I 11, 12, 21, 22 energized __,,,,,____,

energized

g. 120V AC vital buses energized ~~~~~~~~~~~~

energized 22, 23, 24

h. Condenser vacuum greater greater (IN Hg) than 20 , _,,,,,,,,,

than 20 l I i

EOP-1 R v. 1/ Unit 2 Page 13 of 14 l I t

NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT '

E!NIRONMENT CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK Q. Containment pressure (PSIG) less than 0.7 ,,___,,,,,__

less than 0.7

b. Containment temperature ( F) less than 120 .,,,,,,,,,,,

less than 120

c. Containment caseous Radiation alarm clear ,,______,,__

alarm clear RMS ,

d. Containment level (inches) less than 4 ,_,___,,,___

less than 4 l I I l

EOP-1 R;v. 1/ Unit 2 PCg3 14 Cf 14 I

NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL CRITERIA INTERMEDIATE CRITERIA FINAL __

TO CONTAINMENT CHECK CHECK C. Noble Gas Monitor alarm clear ____________

alarm clear

b. Condenser of f-Gas MS alarm clear . _ _ _ _ _ _ _ , , _ _

alarm clear

c. S/G B/D RMS alarm clear _______,,....

alarm clear

d. Main Vent Gaseous .

RMS (2-RI-5415) alarm clear ... ________

alarm clear STATUS CHECK COMPLETE AT NUMBER TIME I I 1

2 3

4 ,

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! EOP-2 R;v. 1/ Unit 1 P;go 1 cf 27 l l s

CALVERT CLIFFS NUCLEAR POWER PLANI 1

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l EOP-2 LOSS OF OFFSITE POWER l

l REVISION 1 l

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SIGNATURE DATE PREPARED BY; N4Mn / / 7 !///8 ;P -

, dbp'*.

n 1 ~ b,

  • VERIFIED y; N /

Am _

Iv dl\ LM . /

POSRC; MEFZGNG #

b8~7 / b t c'- C6 APPROVED BY; h7Y 6 gen- / 1' ' ' N l f%nigeY-Nuclear Operations or General Supervisor-Operations if POSRC review is not required I

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l EOP-2 R;v. 1/ Unit 1 Pcg3 2 of 27 I h ,,

LIST OF EFFECTIVE _PAGES PAGE NUMBER REVISION 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 , 1 13 1 14 1 15 1 16 1 17 1 18 1 19 1 l l 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 i

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EOP-2 R;v. 1/ Unit 1 Pcg] 3 Cf 27 l l LOSS OF OFFSITE POWER I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation vill not support the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies Detween instruments.

D. In Natural Circulation, increased loop trancport time causes a 5 to 10 minute delay in temperature responses to a plant change. Pressurizer level and pressure responses typically provide better indication of RCS response during this period.

I I E. If cooling down with a S/G isolated, an inverted delta T (Teold higher than Thot) may be observed in the idle loop. This is due to a small amount of reverse heat transfer in the isolated S/G. The inverted delta T is not expected to have any significant effect on natural circulation flow in the operating S/G loop.

F. The concentration of boron in RCS makeup water should be consistent with maintaining the required shutdown margin.

G. Minimize the number of cycles of pressurizer auxiliary spray whgn the temperature differential is greater than 400 F.

H. Excessive Diesel Generator loading can result if a SIAS is received and the LOCI sequencer actuates.

Non-vital loads should be manually shed immediately upon receiving a SIAS.

I. If a pump or component fails, the cause of the failure should be determined prior to restarting or starting a standby pump or component to prevent a common failure.

I I

EOP-2 R v. 1/ Unit 1 Pcg3 4 of 27 l I II. JtNTRLeggnEloyJ The presence of one or more of the following conditions indicates that a Loss Of Offsite Power may have occurred:

A. Momentary loss of Control Room lighting on both Units.

B. 500KV Red and Black Bus power avai?able lights de-energized.

C. Diesel Generators running.

D. 12 and 22 Service Bus 13KV power available lights de-energized.

E. No RCPs running on either Unit.

F. Reactor Trip due to RCS low diow.

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["' EOP-2 R v. 1/ Unit 1 Pcga 5 cf 27 II. .RECOVE_RY ACTIOMS &L_TJRNATE ACTIONS l (P .

A. VERIFY POST-TRIP IMMED3 ATE ACTIONS COMPLETED.

-- m e _

B. COMMENCE TNTERMEDIATE SAFETY FUNCTION DTATUC CHECK.

1 .

!C. DETERMINE APPROPRIATE EMERGENCY RESF ONSE AC'A IONS PER ' IRE ERPIP.

.s___.

l D. PROTECT RCS FROM EXCET,SIVE COOLDOWN AND CONDENSER FROM OVERPRESSURE:

I I 1. Shut both MS!Vs.

2 Shut S/G Blowdown Valves:

1-BD-4010-CV 1-BD-4011-CV 1-BD *,012-CV 1-BD-4013-CV E. ESTABLISH S/G llEAT SINK

1. Establish S/G heat removal -HOTS-a- Shift Atmo pheric Dump Atmospheric Dump Valves are reverse Controller to itANUAL. acting, i.e., clockwise to open, counterclockwise to shut. l
b. Operate Atmospheric Dump 1.b.1 LF Atmospheric Dump Valycs Valves to return Tcold will NOT operate from to between 520 and 530 F. Control Room,

_TIWH locally operate Atmospheric Dump Volves on b

45 ft Aux Building.

f

EOP-2 R;v. 1/ Unit 1 P0ga 6 of 27 II. ALTERNATE , ACTIONS

_ RECOVERY ACTIONS l

-hAUTION-

2. Establish feedwater flow to 13 AFM Pump flow limit is 300 GPM S/Gs: when powered from D/C.
a. Start 11 or 12 AEW Pump 2.a.1 IF steam driven pumps oy opening AFW Steau NOT available,  ;

Supply Valves: THEN start 33 AEW Pump. l 1-MS-4070-CV 1-MS-4071-CV

b. Adjust AFW Flow Control Valves to restore and maintain S/G levels between (-)170 and (+)

30 inches and trending .

towards 0 inches.

F. RESTORE COMPONENT COOLING FLOW:

I h 1. IF RUP lower geal temperature 1.1 IF geal temperature above less than 280 F, 230 F, THEN start a Compenent Cocling THEL { perform the following:

Pump.

a. Shut Component Cooling Supply Containmott Isolation Valve, 1-CC-3832-CV.
b. Start a Component Cooling Pump.
2. Verify Component Cooling Heat Exchanger on service is being supplied from an operating Sa2twater Header.

l I

EOP-2 R0v. 1/ Unit 1 Pcg3 7 of 27 III. RECOVERY _ ACTIONS ALTERNATE ACTION _S I h ,

G. ALIGN OTIIER AVAILABLE POWER SOURCES TO ELECTRICAL SYSTEM:

- CAUTION -

If only one D/G ir available.

starting additional loads may cause an overload condition.

Alternate operation of equipment may be rnquired to prevent this condition.

1. Align 12 D/G to Unit with largest power requirement or with redundant aafety related ,

equipment out of service.

2. Consider use of SMECO Tie for supplying loads per OI-27E.

I I. VERIFY SHU7DOWN SEQUENCER LOADS ,

l OPERATING: l i

1. Service Water Pump (s*f.
2. Saltwater Pump (s).
3. Instrument Air Compressor.
4. 11 or 12 Control Room Ventilation.

I

5. Switchgear Room Ventilation.

)

l I. IF STEAM DRIVEN AEW PUMP A?AILABLE, ,

I RIE_}j SECURE 13 AEM PUMP.

I l k u

3 - - - --

EOP-2 Rov. 1/ Unit 1 PGga 8 of 27 III. RECOVERY ACTIONS ALTERNATE ACTIONS I > .

J. 3ECURE MAIN FEED SYSTEM:

1. Verify S/G Feed Pumps tripped.
2. Place Condensate Booster Pumps in PULL-TO-LOCK.
3. Place Condensate Pumps in PULL-TO-LOCK.
4. Place Heater Drain Pumps in PULL-TO-LOCK.
5. Shut S/G Feedwater Isolation Valves: ,

1-FW-4516-MOV 1-FW-4517-MOV

. CONFIRM NATURAL CIRCULATION l l IN AT LEAST ONE LOOP:

- NOTE -

Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10).

1. Thot minug Teold between 10 and 50 F.
2. Tcold constant or decreasing.
3. Thot constant or decreasing.
4. CET temperatures consistent with Thot.
5. Steaming rate affects primary temperature.

Gl>

EOP-2 R;v. 1/ Unit 1 Pcgo 9 of 27

'II . RECOVERY ACTIONS ALTERNATE ACTIONS l I L. RESTORE REACTOR MCCs AND INSTRUMEi4T BUSES:

1. II 11 4KV Bus is energized

_A_N_D 14 4KV Bus is NOT energized, THEN tie MCC-104 to MCC-114:

a. Open MCC-104 Main Feeder Breaker, 52-10401.
b. Close MCC-104 Tie Bres*er, 52-10420,
c. Close MCC-114 Tie .

Breaker, 52-11430.

2. If 14 4KV Bus is energized AND 11 4KV B11s is NOT energized,

) THEN tie MCC-114 to MCC-104:

I k a. Open MCC-13.4 Main Feeder Breaker, 52-11401.

b. Close MCC-114 Tie Breaker, 52-11420,
c. Close MCC-104 Tie Breaker, 52-10420. ,

)

M. MAINTAIN PRESSURIZER LEVEL BETWEEN 101 AMD 180 INCHES:

1. Open Loop Charging Valves:

I 1-CVC-518-CV l 1-CVC-519-C'l l l

2. Shut Auxiliary Spray Valve, 1-CVC-517-CV.

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EOP-2 R0v. 1/ Unit 1 Pago 10 of 27

'II. RECOVERY ACTIONS ALTERNATE ACTIONS l I

3. Verify at least one Charging Pump operating.
4. Shift Letdown Control Valve Controller, 1-HIC-110, to MANUAL.
5. Adjust controller to shut Letdown Control Valves.
6. Open Letdown Isolation Valves:

1-CVC-513-CV 1-0VC-516-CV

- NOTE -

Degasifier Pumps are powered from non-vital power supply. Excessive diversion may cause Degasifier to overfill.

7. Slowly open the Letdown Control Valve noting the l I increase in letdown pressure as read on 1-PIC-201, until 1-PIC-201 takes control of the Letdown Backpressure Regulating Valve.
8. Allow temperatures to stabilize, then shift 1-HIC-110 to AUTO.

N. RE. STORE RCS PRESSURE TO BETWEEN 2225 AND 2300 PSIA: l

1. Operate 11 or 13 Backup Heaters as necessary to raise RCS pressures
a. Charge closing spring using manual lever at 480V breakers 52-1127 and 52-1427.

{ ) b. Push the PUSH-TO-CLOSE button on breaker fronts.

EOP-2 Rcv. 1/ Unit 1 Page 11 of 27

'II. RECOVERY ACTIONS ALTERNATE ACTIONS l I

2. IF pressure exceeds 2300 PSIA, THEN initiate Auxiliary Spray:
a. Record temperature differential between Pressurizer and Regenerative Heat Exchanger Outlet.
b. Open Auxiliary Spray Valve, 1-CVC-517-CV.
c. Shut Loop Charging Valves:

1-CVC-518-CV 1-CVC-519-CV

d. Shift 1-HIC-100 to MANUAL and shut Pressurizer Spray Valves:

1-RC-100E-CV 1-RC-100F-CV l I O. MAINTAIN RCS SUBCOgLING BETWEEN 30 AND 140 F:

1. Raise subcooling by any of the following:
a. Securing Auxiliary Spray. )
b. Energizing Pressurizer Heaters.
2. Lower subcooling by any of the following:
a. Securing Pressurizer Heaters,
b. Initiating Auxiliary Spray.

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EOP-2 R;v. 1/ Unit 1 Page 12 of 27

'I. RECOVFLY ACTIONS ALTERNATE ACTIONS P. VERIFY EMERGENCY DC PUMP OPERATION:

1. Turbine Emergency Oil Pump.
2. Emergency H 2 Seal Oil Pump.
3. S/G Feed Pump Emergency Oil Pump s .

Q. IF RCS COOLDOWN IS EXPECTED, THEN COMMENCE RCS BORATION:

1. Shut VCT Makeup Valve, 1-CVC-512-CV.
2. Open Boric Acid Direct Makeup Valve, 1-CVC-514-MOV.
3. Start a Boric Acid Pump. 3.1 I_F Boric Acid Pumps NOT

( ) available, THEN establish gravity feeds

a. Open BAST Gravity Feed Vr,1ve s :

1-CVC-508-MOV 1-CVC-509-MOV

b. Shut VCT Outlet Valve, i 1-CVC-501-MOV.  !

I

4. Start all available Charging Pumps.
5. WHEN shutdown margin j requirement of NEOG-7  !

is achieved,  !

THEN secure boration

a. Open VCT Outlet Valve, 1-CVC-501-MOV.
b. Stop Boric Acid Pump (s).

EOP-2 rov. 1/ Unit 1 Pcco 13 of 27

'II. RECOVERY ACTIONS ALTERNATE ACTIONS

c. Shut Boric Acid Direct Makeup Valve, 1-CVC-514-MOV.
d. Shut BAST Gravity Feed Valves:

1-CVC-508-MOV 1-CVC-509-MOV R. ENERGIZE SUPPORT EQUIPMENT AS NECESSARY TO FACILITATE SHUTDOWN AND VERIFY LOAD REMAINS WITHIN RATINGS:

- dAUTION -

If the following load limits can be maintained, actuation of the LOCI Sequencer will not cause a D/G overload conditions without 13 AMf Pump - 1400 KW l with 13 ADf Pump - 1800 KW )

l These limita may be exceeded if additional power is required to safely, officiently shut down the plant. The D/G nhould not be operated above 3250 KW.

- CAUTION -

SMECO load limit in 260 AMPS.

1. Start a Main Exhaust Fan.
2. Start a cavity Cooling Fan ,

as needed to maintain cavity coogingtemperaturebelow 200 F.

3. Start Containment Air Cooler (s) in LOW as necesrary to maintain containment 0 temperature below 120 F.

d I

EOP-2 Rov. 1/ Unit 1 Pcga 14 of 27

'II . RECOVERY ACTIONS ALTERNATE ACTIONS

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4. IF "SFP LEVEL TEMP HI" alarm received,

_THEN start Spent Fuel Pool Cooling Pump (s).

5. Strip MCC-101AT and MCC-101BT cf all loads, by opening individual MCC breakers.
6. IF 11 4KV Bus is energized N 14 4KV Bus is NOT

_A_D_

energized, THEN tie MCC-101BT to MCC-101AT:

a. Close MCC-101AT Feeder .

Breaker, 52-1109.

b. Open MCC-101BT Main T eeder Breaker, 52-10141.
c. Close Tie Breakers:

I 52-10120 52-10160

d. Energize loads per stop R.9, page 15,
7. IF 14 4KV Bus is energized AND 11 4KV Bus is NOT energized,

_THEN tie MCC-101AT to MCC-101BT:

a. Close MCC-101BT Feeder Breaker, 52-1419. ]
b. Open MCC-101AT Main Feeder Breaker, S2-10101.
c. Close Tie Breakers:

52-10120 52-10160

d. Energize loads per step R.9, page 15. l l

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EOP-2 Rav. 1/ Unit 1 Pega 15 of 27 II. RECOVERY ACTIONS ALTERNAT _E ACTIONS l ~

8. IF both 11 AND 14 4KV Buses are energized, THEN energize MCC-101AT and MCC-101BT:
a. Close MCC-101AT Feeder Breaker, 52-1109.
b. Close MCC-101BT Feeder Breaker, 52-1419.
c. Energize loads per step R.9, page 15.
9. Energize MCC-1. OAT and MCC-101BT loads:
a. Turbine Building Lighting Transformer Breaker, 52-10103.
b. Turning Gear Oil Pump Breaker, 52-10102.

l l c. Turbine Oil Lift Pump Breakers:

52-10106 52-10107 '

52-10108 52-10109 5?.-10110

d. Turbine Turning Gear Piggyback Motor and Turning Gear Motor Breaker, 52-10105.
e. Technical Support Center HVAC Breaker, 52-10111.
f. Distribution Penel 11 Breaker, 52-10116.
g. Telephone Transforr.ar Breaker, 52-10118.

y-

h. SRW Pump Room Vent Fan, uq g 52-10124 (Restart SRW g- Pump Room Ventilation, ijg per 01-15).

EOP-2 Rcv. 1/ Unit 1 Pcga 16 of 27

'II . RECOVERY ACTIONS M _ TERNATE ACTIONS

( I .

1. 11 S/G Feed Pump Turning Gear Breaker, 52-10121.
j. Technical Support Center Computer Breaker, 52-10122.
k. Turbine Oil Lift Pump Breakers:

52-10146 52-10147 52-10148 52-10149

1. AFW Pump Room Air Conditioner Breaker, .

52-10150.

m. 12 S/G Feed Pump Turning Gear Breaker, 52-10161.
n. Distribution Panel 111 Breaker, 52-10162.
10. IF emergency power requested by Security, THEN place disconnect switch 2Y211, located on the North wall of Unit 2 27 ft Switchgear Room, in the EMERGENCY position.
5. MINIMIZE 250V DC BATTERY DISCHARGE: 1
1. Energize 15 or 25 Battery Charger on 13 250V DC Bus.
2. Ensure Main Turbine has stopped rotating or is on .

Turning Gear.

i

3. Verify Turning Gear Oil Pump running.
4. Stop Turbine Emergency Oil Pump and place handswitch in

{ ) AUTO.

EOP-2 Rov. 1/ Unit 1 Pcg3 17 of 27

'II. RECOVERY ACTIONS AIiLERNATE ACTIONS I >

5. IF bearing oil header pressure less than 25 PSIG, THEN etart Turbine Emergency Oil Pump.

T. LOWER MAIN GENERATOR HYDROGEN PRESSURE TO 2 PSIG:

1. Align Two-Position Valve, 1-G-01, to VENT position.
2. Throttle open Generator Vent Line Isolation Valve, 1-G-03.
3. WHEN Main Generator hydrogen pressure is vented to 2 PSIG, THEN perform the followings
a. Shut 1-G-03.
b. Secure Emergency H 2 8'"1 Oil Pump.

U. IF LOCI SEQUENCER IS ACTUATED AND TURBINE MCCs ARE BEING SUPPLIED BY D/G, THEN DE-ENERG1ZE MCC-101AT AND MCC-101BT.

1. IF rap' 'G load reduction 1.1 If rapid D/G Joad needed reduction NOT needed, THFN gettorm the following: TIIEN perform the following locally:
a. Open 11A 480V Bus Feeder Breaker, 52-1112. a. Open MCC-101AT Main Feeder Breaker,
b. Open 14B 480V Bus Feeder 52-10101.

Breaker, 52-1413.

b. Open MCC-101BT hain
c. Locally open MCC-101AT Feeder Breaker, Main Feeder Breaker, 52-10141.

52-10101, j ) d. Locally open MCC-101BT Main Feeder Breaker, 52-10141.

EOP-2 rov. 1/ Unit 1 Pcga 18 of 27 lII. RECOVERY ACTIONS ALTERNATE ACTIONS I I .

e. Close 11A 480V Bus Feeder Breaker, 52-1112.
f. Close 14B 480V Bus Feeder Breaker, 52-1413.

V. MAINTAIN VCT LEVEL BETWEEN 60 AND 100 INCHES:

1. WHEN VCT makeup required, THEN shift Charging Pump suction to RWT:
a. Open RWT To Charging Pump i Suction Valve, 1-CVC-504-MOV.
b. Observe VOT level 1.b.1 IF VCT level NOT increasing, increasing. THEN shut VCT outlet Valve, 1-CVC-501-MOV.

{ ) c. Ensure Charging Pump (s)

AMPS steady.

2. WHEU VCT increases to 100 incheo, THEN shift Charging Pump suction to VCT:
a. Open VCT Outlet Valve, 1-CVC-501-MOV.
b. Shut RWT To Charging Pump Suction Valve, 1-CVC-504-MOV.

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EOP-2 R;v. 1/ Unit 1 Pcg3 19 of 27 I. RECOVERY ACTIONS ALTERNATE ACTIONS W. IF FORCED CIRCULATION DESIRED

_A @ PUMP RESTART CRITERIA MET, THEN RESTART RCPs WHEN POWER AVAILABLE:

- CAUTION -

Uncontrollod restoration of cooling to hot RCP seals may cause degradation of the metallic seating surfaces by thermal shock.

2. IF Component Cooling is isolated to RCP seals, THEN reduce RCP lowerg udal ,

tempr>rature below 280 F prior to initiating full cooling flow to the RCPs:

a. Shut Component Cooling 2 Supply Containment Manual j g Isolation Valve, 1-CC-284, located in 5 ft East Penetration Room. .
b. Open Component Cooling Containment Isolation Valves:

1-CC-3832-CV l CC-3833-CV

c. Slowly open 1-CC-284 to throttle component cooling flow until lower seal temperatgres are less than 280 F.
d. WHEN lower seal temperatgres are less than 280 F, T[IEN fully open 1-CC-284,
2. IF an RCP lower seal temperature exceeded 280 F, T[IEN an engineering evaluation is required prior to l l restarting that RCP.

EOP-2 Rcv. 1/ Unit 1 i Pcga 20 of 27 l

'II . RECOVERY ACTIONS ALTERNATE ACTIONS l I

3. Raise pressurizer level to at least 155 inches.
4. Lower Tcold to lous than 525 F.
5. Verify RCP restart criteria:
a. RLS subgooling griater than 30 F.
b. At least one S/G available for heat removal,
c. Pressurizer level greater than 155 inches and stable.
d. Tcold less than 525 F. ,
e. RCS temperature and pressure greater than the minimum operating limits per RCP curve on l Attachment (1).

I h _m_

Starting an RCP may cause a pressurizer level transient.

6. WHEN RCP restart criteria are met, THEN start one RCP in a loop with an operable 5/G:
a. Verify "COMPT CLG FLOW LO" alarm clear.
b. Start Oil Lift Pump.
c. Insert RCP sync stick.
d. Start one RCP.

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EOP-2 RSv. 1/ Unit 1 Pcg3 21 of 27

't II . RECOVERY ACTIONS ALTERNATE ACTIONS

( ) i

e. Monitor RCP running current:

Tava Current 525 to 572 F 238 to 210 AMPS and steady 210 to 525 F 264 to 238 AMPS and steady

7. Monitor RCP seal parameters following pump restart.
8. Allow backflow to equalize temperatures in opposite loop.
9. Start second RCP in opposite loop per steps W.6 and W.7, pages 20 and 21.
10. Secure Auxiliary Sprays
a. Open Loop Charging Valves:

1-CVC-518-CV 1-CVC-519-CV

b. Shut Auxiliary Spray Valvo, 1-CVC-517-CV.
c. Shift Pressurizer Spray Controller, 1-HIC-100, to AUTO.
11. WIIEN RCPs restarted, THEN implement appropriate operating procedure AND complete administrative post-trip actions of this procedure.

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1 EOP-2 I R;v. 1/ Unit 1 l Page 22 of 27

'II. RECOVERY ACTIONS ALTERNATE ACTIONS I I X. DETERMINE TIME UNTIL COOLDOWN REQUIRED:

1. Determine total CST water available for use as makeup.
2. Determine time until commencement of required cooldown per Attachment (11).
3. IF RCS cooldown required, 3.1 IF RCS cooldown NOT required, THEN implement Natural THEN implement Loss Of Circulation Cooldown (AOP-3F) Flow / Natural Circulation AND complete administrative (AOP-3E) AND complete post-trip actions of this ., administrative post-trip procedure. actions of this procedure.

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EOP-2 Rav. 1/ Unit 1 Pcg2 23 of 27 l k Y. ADMINISTRATIVE POST-TRIP ACTIONS:

- NOTE -

The following actions may be acccmplished whenever feasible.

They may be done in any order.

1. Refer to ERPIP to determino appropriate emergency response actions.
2. Perform notifications per CCI-118.
3. Notify ESO of trip.
4. Request RCS Boron and Iodine skmple.
5. Perform shutdown margin calculation per NEOG 2 and 7.
6. Complete transient log entries per CCI-301.
7. Recall poet-trip re'.iew (preferably within 30 minutes of l l trip).
8. Perform post-trip review per CCI-111.
9. Monitor turbine bearing temperaturen.
10. Continue Main 'lurbine Shatdown per applicable step of OI-43A.

END OF SECTION III.

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EOP-2 rov. 1/ Unit 1 Pega 24 of 27 IV. S_AFETY FUNCTION STATUS CHECK A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to exiting from this procedure.

B. Perform intermediate safety function status checks at 10 minute intervals until plant conditions stabilize.

C. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied.

D. Review data and verify that safety function acceptance criteria are satisfied.

E. When EOP completed, then perform final safety function check.

REACTIVITY CONTROL SAFETY FUNCTION ACCEPTANCE CRITERIA PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK l I

a. WRNI power less than 3% ___________

less than 1%

b. SUR (DPM) negative ___________

0

c. CEA status all inserted , _ _ _ _ _ _ _ , , _ _

all inserted or Boration status:

appropriate concentration increasing ________,_,

S/D margin BAST level decreasing ___________ N/A _NZA__

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EOP-2 R v. 1/ Unit 1 Pcga 25 ef 27 RCS PRESSURE AND SAFETY FUNCTION ACCEPTANCE

  • CRITERIA INVENTORY PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK O. Pressurizer pressure (PSIA) 1850 to 2300 __,________

2225 to 2300

b. Pressurizer 130 to 180 level (inches) 101 to 250 ___________
e. RgS subcooling 30 to 140

( F) 30 to 140 ___________

CORE AND RCS HEAT SAFETY FUNCTION ACCEPTANCE CRITERIA REMOVAL PARAMETERS .

FINAL CRITERIA INTERMEDIATE CRITERIA CHECK CHECK

o. RCS Teold (#F) 515 to 535 ____________

520 to 535 (1) less than 560 ________ less than 560

b. CET ( F) _
c. TgotminusTcold

( F):

Natural 10 to 50 Circulation 10 to 50 ____________

Forced N Circulation M/A ,___(A ,___,

less than 5

d. S/G pressure 785 to 920 850 to 920 (PSIA) ____________
c. 3/G level (-)170 to (-)24 to (inches) (+)30 ____________

(+)30 trending

f. S/G level trending towards O towards O trend (inches) ____________
g. Condensate Storage Tank greater than 5 ____________ greater than 5 level (ft)

(1) CET temperatures may be greater than 560 F while Natural Circulation is being established.

l )

EOP-2 R v. 1/ Unit 1 Pcga 26 of 27 I I .

VITAL AUXILIARIES SAFETY EUNCTION ACCEPTANCE CRITERIA CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

c. 4KV vital buses 11 or 14 energized _ _ _ _ _ ,.,_ _ _ _ _ _

energized

b. Instrument Air greater greater pressurt (PSIG) than 88 ____________

than 88

c. Component Cooling

(# Pumps running) 1 or 2 ____________

1 or 0

d. Component Cooling Head Tank level greater greater (2) than 20 than 20 (inches) ____________
c. Saltwater

(# Pumps running) 1 or 2 ____________

1 or 2 I f. Service Water 1 or 2

(# Pumps running) 1 or 2 ,,__________

g. Service Water Head Tank level greater greater (inches) (2) than 30 ____________

than 30

h. 125V DC buses 11, 12, 21, 22 energized ____________

energized

i. 120V AC vital buses 11, 12, 13, 14 energized ____________

energized l

(2) Refer to 01-15 and 01-16 for filling head tanks.

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EOP-2 Rcv. 1/ Unit 1 Page 27 of 27 NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT ENVIRONMENT CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK

c. Containment pressure (PSIG) less than 0.7 _______, ,_

less than 0.7

b. Containment tgmperature less than 120 ____________ less than 120

( F)

c. Containment less than 4 ____________

less than 4 __

level (inches) ,

NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL j CRITERIA INTERMEDIATE CRITERIA FINAL fTOCONTAINMENT CHECK CHECK

c. Noble Gas Monitor alarm clear ____________

alarm clear STATUS CHECK COMPLETE AT NUMBER TIME 1

2 3

4 _

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EOP-2 R;v. 1/ Unit 2 Pago 1 of 27 l I ,

CALVERT CLIFFS NUCLEAR POWER PLANT EOP-2 LOSS OF OFFSITE POWER REVISION 1 SI DATE

~

PREPARED BY; . ~ (lW M /

VERIFIED BY; AM; f jQ t.4 /Jbff$lh POSRC;

/

MEETING # YS-

~

' / 7 9 3 APPROVED BY; kN .tw,,# / I'W-%6 fla6ag66-Nuclear Operations or General Supervisor-Cperations if POSRC review is not required i

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EOP-2 rov. 1/ Unit 2 Paga 2 of 27 L]ST OF EFFECTIVF, PAGES PAGE NUMBER REVISION 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 .

1 13 1 e

14 1 16 1 16 1 17 1 18 1 19 1 I 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 l

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EOP-2 R;v. 1/ Unit 2 Pcga 3 of 27 LOSS OF OFFSITE POWER I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments.

D. In Natural Circulation, increased loop transport time causes a 5 to 10 minute delay in temperature responses to a plant change. Pressurizer level and pressure responses typically provide better indication of RCS response during this period.

E. If cooling down with a S/G isolated, an inverted delta T (Tcold higher than Thot) may be observed in the idle loop. This is due to a small amount of reverse heat transfer in the isolated S/G. The inverted delta T as not expected to have any significant effect on natural circulation flow in the operating S/G loop.

F. The concentration of boron in RCS makeup water should be consistent with maintaining the required shutdown margin.

G. Minimize the number of cycles of pressurizer auxiliary '

spray whgn the temperature differential is greater l than 400 F. J H. Excessive Diesel Generator loading can rssult if a SIAS is received and the LOCI sequencer actuates.

Non-vital loads should be manually shed immediately upon receiving a SIAS.

I I. If a pump or component fails, the cause of the failure )

should be determined prior to restarting or starting a i' standby pump or component to prevent a common failure.

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EOP-2 Rcv. 1/ Unit 2 Pcgo 4 of 27 l I 8

II. ENTRY CONDITIONS The presence of one or more of the following conditions indicates that a Loss Of Offsite Power may have occurred:

A. Momentary losc of Control Room lighting on both Units.

B. 500KV Red and Black Bus power available lights de-energized.

C. Diesel Generators running.

D. 12 and 22 Service Bus 13KV power available lights de-energized.

E. No RCPs running on either Unit.

F. Reactor Trip due to RCS low flow.

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EOP-2 R:v. 1/ Unit 2 Pcga 5 of 27 "II. _RE_C_OVERY ACTICNS ALTEPNATE ACTIONS

( l .

A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED.

B. COMMENCE INTCPMEDIATE SAFETY FUNCTION STATUS CHECK.

C. DETERMINE APPROPRIATE EMERGENCY RESPONSE ACTIONS PER THE ERPIP.

e D. PROTECT RCS FROM EXCESSIVE COOLDOWN AND CONDENSER FROM OVERPRESSURE:

l I 1. Shut both MSIVs.

2. Shut S/G Blowdowr. Valvese 2-BD-4010-CV 2-BD-4011-CV 2-BD-4012-CV 2-ED-4013-CV E. ESTABLISH S/G HEAT SINK:
1. Establish S/G heat removal: -NOTE-
n. Shift Atmospheric Dump Atmospheric Dump Valves are reverso Controller to MANUAL. acting, i.e., clockwise to open, counterclockwise to chut,
b. Operate Atmospheric Dump 1.b.1 J_F Atmospheric Dump Valves Valves to return Tcold will HOT operate from Control Room, to between 5't0 and 530 F.

TTiEN locally operate Atmospheric Dump Valves on 45 ft Aux Building.

EOP-2 R v. 1/ Unit 2 Paga 6 of 27

'II . RECOVERY ACTIONS ALTERNATE ACTIONS l I bAUTION -

2. Establish feedwater flow to 23 AFW Pump flow limit la 300 GPM S/Gs: when powered from D/G.
a. Start 21 or 22 AEW Pump 2.a.1 IF steam driven pumps by opening AFW Steam NOT available, Supply Valves: TIJEH start 23 AFW Pump, 2-MS-4070-CV 2-MS-4071-CV
b. Adjust AFW Flow Control Valves to restore and maintain S/G 1evels between (-)170 and (+)

30 inches and trending ,

towards 0 inches.

> F. RESTORE COMPONENT COOLING FLOW I I 1. IF RCP lower geal temperature 1.1 If goal temperature above ,

less than 280 F, 280 F,  !

THEU start a Component Cooling T!IEN perform the following Pump.

a. Shut Component Cooling Supply Containment Isolation Valve, 2-CC-3832-CV.
b. Start a Component Cooling Pump.
2. Verify Component Cooling Heat Exchanger on service is being supplied from an operating Saltwater Hender.

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EOE-2 Rcv. 1/ Unit 2 Pcgo 7 of 27

' I '. . . RECOVERY ACTIONS ALTERNATE ACTIONS I I .

G. ALIGN OTHER AVAILABLE POWER SOURCES TO ET.ECTRICAL SYSTEM:

- CAUTION -

If only one D/G is available, starting additional loads may

  • cause an overload condition.

Alternate operation of equipment ma' be required to prevent this con ition.

1. Align 12 D/G to Unit with largest power requirement or with redundant safety related ,

equipment out of service.

2. Consider use of SMECO Tie for supplying loads per OI-27E.

I. VERIFY SFUTDOWN SEQUEliCER LOADS OPERATING:

1. Service Water Pump (s).
2. Saltwster Pump (s).
3. Instrument Air Compressor.
4. 11 or 12 Control Room Ventilation.
5. Switchaear Roon. Ventilation.

I. H S'f2AM DRIVEN AFW PUMF AVAILABLE, TIIEN SECURE 23 AFW PUMP.

EOP-2 RCv. 1/ Unit 2 Pcga 8 ef 27

'II. _ RECOVERY ACTIONS ALTERNATE ACTIONS l I J. SECURE MAIN FEED SYSTEM:

1. Verify S/G Feed Pumps tripped.
2. Place Condensate Booster Pumps in PULL-TO-LOCK.
3. Place Condensate Putape in PULL-TO-LOCK.
4. Place Heater Drain Pumps in PULL-TO-LOCK.
5. Shuc S/G Feedwater Isolation Valves: s 2-FW-4516-MOV 2-FW-4517-MOV j . CONFIRM NATURAL CIRCULATION IN AT LEAST ?1E LOOPi

- NOTE -

Wide range Thot may be obtained from Eubcooled Margin Monitor per Attachment (10).

1. Thot minug Tcold between

and 50 F.

2. Tcold constant or decreasing.
3. Thot constant or decreasing.
4. CET temperatures consistent with *lhot.
5. Steaming rate affects primary temperature.

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EOP-2 Rav. 1/ Unit 2 PCg3 9 cf 27

'II. RECOVERY ACTIONF ALTERNATE ACTIONS l I ,

L. RESTORE REACTOR MCCs AND INSTRUMENT BUSFS:

1. IF 24 4KV Bus is energized MQ 21 4KV Bus is NOT energized,

'? HEN tie MCC-214 to MCC-204:

a. Open MCC-214 Main Feeder Breaker, 52-21401.
b. Close MCC-214 Tie Bresker, 52-21420.
c. Close MCC-204 Tic ,

Brenker, 52-20420.

2. IF 21 4KV Bus is energized L.ND 24 4KV Bus is NOT caergized, THEN tie MCC-204 to MCC-214:

l I a. Open MCC-204 Main Feeder Breaker, 52-20401.

b. Close MCC-204 Tie Breaker, 52-20420,
c. Close MCC-214 Tie Breaker, 52-21420.

M. MAINTAIN PRESSURIZER LEVEL BETWEEN 101 AND 180 INCHES:

1. Open Loop Charging Valves: i l

2-CvC-51a-Cv  ;

2-CVC-519-CV

2. Shut Auxiliary Spray Valve, 2-CVC-517-CV.

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l EOP-2 R;v. 1/ Unit 2 Pcg3 10 of 27 III. _ RECOVERY ACTION _S ALTERNATE ACTIONS l I

3. Verify at least one Charging Pump operating.
4. Shift Letdown Control Valve controller, 2-HIC-110, to MANUAL.
5. Adjust controller to shut Letdown Control Valves,
6. Open Letdown Isolation Valves:

2-CVC-515-CV 2-CVC-516-CV

- NOTE -

Degasifier Pumps are powered from non-vital power supply. Excessive diversion may cause Degasifier to overfill.

7. Slowly open the Letdown Control Valve noting the l I increase in letdown pressure as road on 2-PIC-201, until 2-PIC-201 takes control of the Letdown Backpressure Regulating Valve.
8. Allow temperatures to stabilize, then shift 2-HIC-110 to AUTO.

N. RESTORE RCS PRESSURE TO BETWEEN 2225 AND 2300 PSIA:

1. Operate 21 or 23 Backup Heaters as necessary to raise RCS pressures
a. Charge closing spring using manual lever at 480V breakers 52-2127 and 52-2427.
b. Push the PUSH-TO-CLOSE button on breaker fronts.

f

- ~_

EOP-2 R0v. 1/ Unit 2 Pcg3 11 of 27

'II . EECOVERY ACTIONS ALTERNATE ACTIONS I I .

2. IF prr: auro exceeds 2300 PSIA, THEN initiate Auxiliary Spray:
a. Record temperature differential between Pressurize and Regenerative Heat Exchanger Outlet.
b. Open Auxiliary Spray Valve, 2-CVC-517-CV.
c. Shut Loop Charging Valves:

2-CVC-518 CV 2-CVC-519-CV

d. Shift 2-HIC-100 to MANUAL and shut Pressurizer Spray Valves:

2-RC-100E-CV 2-RC-100F-CV O. MAINTAIN RL'S SUBCOgLING BETWEEN 30 AND 140 F:

1. itaise subcooling by any of the following:
a. Securing Auxiliary Spray,
b. Energizing Pressurizer Heaters.
2. Lower subcooling by any of the followings
a. Securing Pressurizer Heaterr.
b. Initiating Auxiliaty Spray.

EOP-2 R;v. 1/ Unit 2 Pcg3 12 of 27

'II . RECOVERY ACTIONS ALTERNATE ACTIONS I l P. VERIFY EMERGENCY DC PUMP OPERATION:

1. Turbine Emergency oil Pump.
2. Emergency Air Side Seal 011 Pump.
3. S/G Feed Pump Emergency 011 Pumps.

Q. IF RCS COOLDOWN IS EXPECTED, 21IElj COMMENCE RCS BORATION:

1. Shut VCT Makeup Valve, 2-CVC-512-CV.
2. Open Boric Acid Direct Makeup Valve, 7-CVC-514-MOV.

I I 3. Start a Boric Acid Pump. 3.1 IE Boric Acid Pumps NQT available, THEN establish gravity feeds

a. Open BAST Gravity Feed Valves:

2-CVC-508-MOV 2-CVC-509-MOV

b. Shut VCT Outlet Valve, 2-CVC-501-MOV.
4. Start a'.1 available Charging Pumps.
5. IfHEN shutdown margin rec,uirement of NEOG-11  ;

de achieved, T'I_Eli secure boration: I Open VOT Outlet Valve, 1

a.

2-CVC-501-MOV.

b. Stop Boric Acid Pump (s).

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EOP-2 R v. 1/ Unit 2 Pcg3 13 of 27

'II . RECOVERY ACTIONS ALTERNATE ACTIONS

c. Shut Boric Acid Direct Makeup Valve, 2-CVC-514-MOV, l
d. Shut BAST Gravity Feed Valves:

2-CVC-508-MOV 2-CVC-509-MOV I

R. ENERGIZE SUPPORT EQUIPMENT AS NECESGARY TO FACILITATE SHUTDOWN '

i AND VERIFY LOAD REMAINS WITHIN RATINGS:

1 I

- CAUTION -

l If the following load limits can i be maintained, actuation of the LOCI Sequencer will not cause a ,

D/G overload condition: )

without 23 AFW Pump - 1400 KW with 23 ADi Pump - 1800 KW These limits may be exceeded if ]

additional power is required to ,

safely, efficiently shut down I the plant. The D/G should not be operated above 3250 KW.

- CAUTION - l SMECO load limit is 260 AMPS.

1. Scart a Main Exhaust Fan. l
2. Start a Cavity Cooling Fan as needed to maintain cavity coofingtemperaturebelow 200 F.
3. Start Containment Air Cooler (s) in LOW as necessary to maintain containment temperature below 120 F.

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ECP-2 Rav. 1/ Unit 2 Pcg3 14 of 27 "II. RECOVERY ACTIONS ALTERNATE ACTIONS l I

4. II "SFP LEVEL TEMP HI" alarm received, THEN cuart Spent Fuel Pool Cooling Pump (s).
5. Strip MCC-201AT and MCC-201BT of all loads, by opening individual MCC breakers.
6. IF 24 4KV Bus is energized AND 21 4KV Bus is NOT energized, THEN tie MCC-201AT to MCC-201BT:
a. Close MCC-201BT Feeder .,

Bruaker, 52 ~.419.

b. Open MCC *.01AT Main Feeder Breaker, 52-20101.
c. Close Tie Breakers:

I I 52-20120 52-20160

d. Energize loads per step R.9, page 15.
7. II 21 4KV Bus is energized AND 24 4KV Bus is NOT energized, THFN tie MCC-?C1BT to MCC-201AT:
a. Close MCC-201AT F9eder Breaker, 52-2109.
b. Open MCC-201BT Main Feeder Breaker, 52-20141.
c. Close Tie Breakers:

52-20140 J 52-2C160

d. Energize loads por l step R.9, page IE.

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I EOP-2 Rov. 1/ Unit 2 Pcg3 15 of 27 III. ALTERNATE _A M OjiS

_ RECOVERY ACTIONS C. IF both 21 AND 24 4KV Buses are energized,

'IIIEE energize MCC-201 AT and MCC-201BT:

a. Clote MCC-201AT Feeder Breaker, 52-2109.
b. Cicae MCC-201BT Feeder Breaker, 52-2419,
c. Energize loads per step R.9, page 15.
9. Energize MCC-201AT and MCC-201BT loads:
a. Turbine Building Light.'no Transformer Breaker, 52-20103.
b. Turbine Oit Lift Pump Breaker, 52-20106.

j ) c. Turbine Turning Gear Motor Breaker, 52-20105,

d. Distribution Panel 21 Breaker, 52-20116.
e. 21 S/G Feed Pump Turning Gear Breaker, 52-20121.
f. AFW Punp Room Air Conditioner Breaker, 52-20150.
g. 22 S/G Feed Pump Turning Gear Breaker, 52-20161.
h. Distribution Panel 211 Breaker, 52-20162.

c 1. SRii Pump Room Vent Fan,

'; 52-20149 (Pistart SRW

.7 Pump Room Ventilation,

$ per 01-15).

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> EOP-2 R0v. 1/ Unit 2 Pega 16 of 27 III. RECOVERY _ ACTIONS AL_TERNAN ACTIONS I I UE i

E 4

10. IF emergency power requented by Security, THEN place disconnect switch 2Y211, located on the North wall of Unit 2 27 ft '

Switchgear Room, in the EMERGENCY position.

S. MINIMIZE 250V DC BATTERY DISCHARGE:

I I

1. Energize 15 or 25 Sattery Charger on 13 250V DC Bus.
2. Ensure Main Turbine has stopped rotating or is on Turning Gear.
3. Verify Bearing 011 Pump running,
4. Stop Turbine Emergency Oil Pump and pisce handswitch in AUTO.
5. JF bearing oil header pressure less than 15 PSIG,

'IIIEN start Turbine Emergency Oil Pump.

5

EOP-2 R;v. 1/ Unit 2 Pcgo 17 of 27 I. RECOVERY ACTIONS ALTERNATE ACTIONS T. LOWER MAIN GENERATOR HYDROGEN PRESSURE TO 2 PSIG:

1. Throttle open Generator Bottom Vent To Atmosphere Valve, 2-G-06.
2. WHEH Main Generator hydrogen pressure is vented to 2 PSIG, THEN perform the followings
a. Shut 2-G-06,
b. Secure Emergency Air Side Seal Oil Pump. .

U. IF LOCI SEQJENCER IS ACTUATED bHD TURBINE MCCs ARE BEING SUPPLIED BY D/G,

{ ) THEN DE-ENERGIZE MCC-201AT AND MCC-201BT.

1. IF rapid D/G load reduction 1.1 IF rapid D/G load reduction NOT needed, needed, THEN perform the following: THEN perform the following locally:
a. Open 21A 480V Bus Feeder Braaker, 52-2112. a. Open MCC-201AT Main Feeder Breaker,
b. Open 24B 480V Bus Feeder 52-20101.

Breaker, 52-2413.

b. Open MCC-201BT Main
c. Locally open MCC-201AT Feeder Breakor, Main Feeder Breaker, 52-20141.

52-20101,

d. Locally open MCC-201BT Main Feeder Breaker, 52-20141,
e. Close 21A 480V Bus Feeder j Breaker, 52-2112.

i

f. Close 24B 480V Bus Feeder l Breaker, 52-2413. l I

EOP-2 Rov. 1/ Unit 2 Pcg; 18 cf 27 R ALTERNATE ACTIONS

'II . _ECOVERY ACTIONS I I .

V. MAINTAIN VCT LEVEL BETHEEN 60 AND 100 INCHES:

1. MTEN VCT makeup required, THEN shift Charging Pump suction to RJT:
a. Open RWT To Charging Pump Suction Valve, 2-CVC-504-MOV, IF VCT level NOT increasing,
b. Observe VCT level 1.b.:

THEN shut VCT outlet Valve, increasing.

2-CVC-501-MOV.

c. Ensure Chargir.g Pump (s)

AMPS steady.

2. WHEN VCT increases to 100 inches, TEIEN shif t Charging Pump suction to VCT:
a. Open VCT Outlet Valve, 2-CVC-501-MOV.
b. Stut RWT To Charging Pump Suction Valve, 2-CVC-504-MOV.

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EOP-2 R;v. 1/ Unit 2 Page 19 of 27

'II. RECOVERY ACTIONS ALTERNATE ACTIONS I I W. IF FORCED CIRCULATION DESIRED AND PUMP RESTART CRITERIA MET, THEN RESTART RCPs WHEN POWER AVAILABLE:

- CAUTION -

Uncontrolled restoration of cooling to hot RCP seals may cause degradation of the metallic seating surfaces by thermal shock.

1. If Component Cooling is isolated to RCP seals, TUEE reduce RCP lowerg seal ,

temperature below 280 F prior to initiating full cooli.ng flow to the RCPs:

a. Shut Component Cooling Supply Containment Manual Isolation Valve, 2-CC-284, I I located in 5 ft East Penetration Room.
b. Open Component Cooling Containment Isolation Valves:

2-CC-3832-CV l

2-CC-3833-CV

c. Slowly open 2-CC-284 to throttle component cooling flow until lower )

seal temperatgres are l I

less than 280 F. 1

d. WHEN lower seal l temperatgres are less i I

than 280 F, THEN fully open 2-CC-284. (

2. IF an RCP lower seal temperature exceeded 280 F, l 17DM an engineering evaluation is required prior to

{ l restarting that RCP.

EOP-2 Rav. 1/ Unit 2 Page 20 of 27

'II. RECOVERY _ ACTIONS ALTERNATE ACTIONS l I .

3. Raise pressurizer level to at least 155 inches.
4. Lower Teold to less than 525 F.
5. Verify RCP restart criteria
a. RCS subgooling greater than 30 F.
b. At least one S/G available for heat removal.
c. Pressurizer level greater than 155 inches and stable,
d. 'iccid less than 525 F. ,
e. RCS temperature and pressure greater than the minimum operating limits per RCP curve on Attachment (1).

I > _ NOTS -

Starting an RCP may cause a pressurizer level transient.

6. WEEE RCP restart critoria are met, THEN start one RCP in a loop l with an operable S/G:
a. Verify "COMPT CLG FLOW LO" alarm clear.
b. Start 011 Lift Pump.

l l c. Insert RCP sync stick.

l 1

d. Start one RCP.

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EOP-2 RCv 1/ Unit 2 Pcg2 21 cf 27 lII. RECOVERY ACTIONS A_LTERNATE ACTIONS I

I Monitor RCP running e.

current:

Tavo Current 525 to 572 F 238 to 210 AMPS and steady 210 to 525 F 264 to 238 AMPS and steady

7. Monitor RCP seal parameters following pump restart.
8. Allow backflow to equalize temperatures in opposite loop.
9. Start second RCP in opposite loop per steps W.6 and W.7, pages 20 and 21.
10. Secure Auxiliary Spray:
a. Open Loop Charging Valves:

2-CVC-518-CV 2-CVC-519-CV

b. Shut Auxiliary Spray Valve, 2-CVC-51"-CV.
c. Shift Pressurizer Spray Controller, 2-HIC-100, i to AUTO.
11. WIIEN RCPs restarted, THEN implement appropriate oparating procedure hND complete administrative post-trip actions of this  ;

procedure.  !

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i ioPa2 R;v. 1/ Unit 2 Page 22 of 27 I. }tECOVERY ACTIONS ALTERNATE ACTIONS X. DETERMINE TIME UNTIL COOLDOWN REQUIRED:

1. Determine total CST water available for use as makeup.
2. Determine time until commencement of required cooldown per Attachment (11).
3. If RCS cooldown required, 3.1 IE RCS cooldown NOT required, THEN implement Natural THEN implement Loss Of Circulation Cooldown (AOP-3F) Flow / Natural Circulation SND complete administrative (AOP-3E) AND complete post-trip actions of this ,

administrative post-trip procedure.

actions of this procedure.

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EOP-2 R v. 1/ Unit 2 Pcg3 23 of 27 l I .

Y. ADMINISTRATIVE POST-TRIP ACTIONS:

- NOTE -

The following actions may be accomplished whenever feasible.

They may be done in any order.

1. Rofer to ERPIP to determine appropriate emergency response actions.
2. Perform notifications per CCI-118.
3. Notify ESO of trip.
4. Request RCS Boron and Iodine sample.
5. Perform shutdown margin calculation per NEOG 9 and 11.
6. Complete transient log entries per CCI-301,
7. Recall post-trip review (preferably within 30 minutes of trip).

{ }

8. Perform post-trip review per CCI-lll.
9. Monitor turbine bearing temperatures.
10. Continue Main Turbine Shutdown per applicable step of OI-43A.

END OF SECTION III.

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EOP-2 R;v. 1/ Unit 2 Pega 24 of 27 l I IV. SAFETY FUt.pTIO!L STATUS CHECK A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to exiting from this procedure.

B. Perform intermediate safety function status checks at 10 minute intervals until plant conditions stabilize.

C. Immedictely notify Shif t Supervisor or Control Room Supervisor if r:ny safety funccfon criteria is not being satisfied.

D. R6 vies dsta and verify that safety function acceptance criteria aro satisfied.

E. When EOP completed, then perform final safety function check.

REACTIVITY CONT.'.0L SAFETY FUNCTION ACCEPTAFCC CRITERIA PARAMETERS

-CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK l I

a. WRNI power less than 3% ,,,,,,,,,,,

less than 1%

b. SUR (DFM) negative ,,_,,,,,,,,

O

c. CEA status all inserted ,,,,,,,,,,,

all inserted or Boration utatus:

appropriate concer.tratio- increasing ,,,,,,,,,,,

S/D margin BAST 19 vel decreasing ,,,,,,,,,,,

N/A N/A l

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E0P-2 R;v. 1/ Unit 2 Page 25 of 27 l )

RCS PRESSURE AND SAFETY EUNCTION ACCEPTANCE CRITERIA INVENTORY PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

c. Pressurizer pressure (PSIA) 1850 to 2300 __,,,,,,___

2225 to 2300

b. Pressurizer level (inches) 101 to 250 _,,___,,,_,

130 to 180

c. RgS subcooling 30 to 140

( F) 30 to 140 ___________

CORE AND RCS HEAT SAFETY FUNCTION ACCEPTANCE CRITERIA REMOVAL PARAMETERS .

CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. RCS Tcold ( F) 515 to 535 ,,,,________

520 to 535

b. CET ( F) (1) less than 560 ,,,,,_______ less than 560 q g
c. Tgot minus Tcold

( F):

Natural Circulation 10 to 50 ____________

10 to 50 Forced I#

circulation N/A ___,_(^____, less than 5

d. S/G pressure (PSIA) 785 to 920 ,,_,,___,,,,

850 to 920

e. S/G level (-)l70 to (-)24 to (inches) (+)30 ____________ (+)30
f. S/G level trending trending trend (inches) towards O ____________

towards O

g. Condensate Storage Tank greater than 5 ____________ greater than 5 j level (ft)

(1) CET temperatures may be greater than 560 F while Natural Circulation

{ } is being established, i

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E0P-2 R;v. 1/ Unit 2 l Pcg3 26 of 27 l l

l l I VITAL AUXILIARIES SAFETY FUNCTION ACCEPTANCE CRITERIA CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

c. 4KV vital buses 21 or 24 energized __,,,,,,,,,,

enargized

b. Instrument Air greater greater pressure (PSIG) than 88 ,,,,,,,,,,,,

than 88

c. Component Cooling

(# Pumps running) 1 or 2 ,,,,,,,,____

1 or 2

d. Component Cooling Head Tank level greater greater (inches) (2) than 20 ,____,,,,,,,

than 20

c. Saltwater

(# Pumps running) 1 or 2 ,,_,,,___,,,

1 or 2 I f. Service Water 1 or 2

(# Pumps running) 1 or 2 ,,,,_,,,,,,,

g. Service Water Head Tank level greater greater (inches) (2) than 30 ,,,,,,,,,___

than 30

h. 125V DC buses 11, 12, 21, 27 energized ,,__,,______

energized

i. 120V AC vital buses 21, 22, 23, 24 energized ,,_,,__,,,,,

energized (2) Refer to 0I-15 and OI-16 for filling head tanko.

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EOP-2 ROV. 1/ Unit 2 Page 27 of 27 l l NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT _

ENVIRONMENT CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK

c. Containment pressure (PSIG) less than 0.7 ,__,,,,_____ less than 0.7
b. Containment less than 120 ___________, less than 120 tgmperature

( F)

c. Containment less than 4 less than 4 level (inches) ~~~~~~~~~7~~

HORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL CRITERI?. INTERMEDIATE CRITERIA FINAL

{ }TO CONTAINMENT CHECK CHECK

c. Noble Gas Monitor alarm clear ___,,,,,,,,,

alarm clear STATUS CHECK COMPLETE AT NUMBER TIME 1 l 2

3 4

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EOP-3 R;v. 1/ Unit 1 Pcga 1 cf 40 l l CALVERT CLIFFS HUCLEAR POWE2t PLANT EOP-3 TOTAL LOSS OF ALL FEEDWATER REVISION 1 SIGNATURE DATE PREPARED BY; bew/;k 9 wto- / /2[/F M 7 ,

Y$ M l l VERIFIED BY; _b '

s

' N, L

y

\ /

\ l POSRC; l(EFLIING tt M / E'W-E3 AP"ROVED BY; 7 N, 4, co u u / 2 - C - W6 Mdndger'-Nuclear Operations or General Supervisor- {

Operations if POSRC review is not required l I

EOP-3 R;v. 1/ Unit 1 Page 2 of 40 l l L_IST OF EFFECTIVE PAGES PAGE NUMBER REVISIOJ 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 1

12 1

, 13 1 14 1 15 1 16 1 17 1 18 1 l l 19 1 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 28

  • 29 1 30 1 31 1 32 1 33 1 34 1 35 1 36 1 37 1 38 1 39 1 40 1 l I l 1

N

EOP-3 R v. 1/ Unit 1 Page 3 of 40 l I TOTAL __ LOSS OF ALL FEEDWATER I. PRECAUTIQHS A. Dn not adopt manual operation of automatically controllsd systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments.

D. Solid operation of the RCS should only be gttempted in order to maintain a subcooled margin of 30 F.

E. If solid operation of the RCS is undertaken, any functions or actions directly affecting maxeup,

{ }

letdown, system heatup or cooldown thould be closely monitored to avoid rapid pressure excursions.

F. Feedwater should not be added to a dry S/G if the other S/G still contains water. If both S/Go become dry, refill only one S/G to reinitiate Natural Circulation.

G. Minimize the number of cycles of pressurizer auxiliary spray whgn the temperature differential is greater than 400 F.

H. In Natural Circulation, increased loop transport time causes a 5 to 10 minute delay in temperature responses to a plant change. Pressurizer level and pressure responses, if available, typically provide better indication of RCS response during this period.

I. S/G pressure, pressurizer pressure, and containment temperature affect the level indication for the S/Gs and Pressurizer. Attachments (8) and (9) contain the corrected S/G and pressurizer levels for various S/G pressures, pressurizer pressures, and containment temperatures.

J. If a pump or component fails, the cause of the failure I I should be determined prior to restarting or starting a standby pump or conponent to prevent a common failure.

EOP-3 R;v. 1/ Unit 1 PCga 4 of 40 l l II. FRERY CONDITIONS The presence of one or more of the following conditions indicates that a Total Loss of All Feedwater may have occurred:

A. Loss of Condensate Storage Tank inventory.

B. Loss of Condenser Hotwell level.

C. Low suction or discharge pressure for either the Condensate, Condensate Booctor, or S/G Feed Pumps.

D. S/G Turbine Tripped alarm on both S/G Feed Pumps.

E. Low suction or discharge pressure for the AFW Pumps.

F. Motor System No Flow alarm for AFW.

G. Turbine System No Flow alarm for AFW.

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EOP-3 R;v. 1/ Unit 1 Pcg3 5 cf 40

I. RECOVKRY ACTIONS ALTERNATE ACTIOt'S l l A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETFD.

B. COMMENCE INTEPREDI ATE SAFETY FUNCTION STATUS CHECK.

C. ERPIP REQUIRES THAT A SITE EMERGENCY BE DECLARED 1F TOTAL LOSS OF MAIN AND AUXILIARY FEEDWATER EXISTS FOR LONGER '

THAN TEN MINUTES.

3. TRIP ALL RCPs.

I I E. MINIMIZE S/G ItNENTORY LOSS.

1. Shut S/G Blowdown Valves:

1-BD-4010-CV 1-BD-4011-CV 1-BD-4012-CV 1-BD-4013-CV F. COMMENCE RCS BORATION:

1. Shut VCT Makeup Valve, 1-CVC-512-CV.
2. Open Boric Acid Direct Makaup Valve, 1-CVC-514-MOV.

I I

EOP-3 R v. 1/ Unit 1 Page 6 of 40 II. RECOVERY ACTIONS N M RNATE_ ACTION 3

3. Start a Boric Acid Pump. 3.1 if Boric'A-id Pumps NOT available, THEU establish gravity feeds
a. Open BAST Gravity Feed Valves:

1-CVC-508 MOV 1-CVC-509-MOV

b. Shut VCT outlet Valv a, 1-CVC-501-MOV.

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4. Start all available Charging Pumps.
5. Continue boration ulttil a total 65 inch decrea.se in BAST 1evel(s) is achievec , or shutdown margin requirement of NEOG-7 is achieved.

ESTABLISH NATURAL CIRCULATION AND COOL DOWN RCSi

1. Block ESFAS actuation:
a. WHEN "SGIS A(B) BLOCK 1.a.1 .(I SGIS actuates, PERMITTED" alarm (s) THEN reset SGIS:

received, TIIEN block SGIS A(B) . a. Place Condensate Booster Pumps in PULL-TO-LOCK.

b. Match handswitches per SGIS Verification Checklist, Attachment (7),
c. Block SGIS.
d. Reset SGIS signal.

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{

EOP-3 R;v. 1/ Unit 1 Pcg] 7 of 40 7II. ]G.COVERY ACTIORS SM3BNATE,_b_CT_LONS l l  !

e. Open S/G Feedwater I

Isolation Valves:

1-rW-4516-MOV l-LH-4517-MOV

f. Start a Condensate I Booster Pump. l
b. MU;H "PRSR PRESS BLOCK A(B) PERMITTED" alarm (s) received, D_lEN bloch SIAS A(B).
2. Commence cooldown by throttling Turbine Bypass or Atmospheric Dump Valves ,

while maintaining:

a. Less than 100 F/h RCS cooldown rate.
b. Pressurizar level between 50 and 180 inches. g l )
3. Shut Letdown Isolation Valves:

1-CVC-515-CV l-CVC-516-CV

4. Maintain RCS subcogling between 30 and 14C F:
a. Raise cubcooling by: 4 (1) Energizing Pressurizer Heaters.

(2) Increasing cooldown rate.

(

b. Lower subcooling by initiating Aaxiliary Spray (1) Record temperature differential between Pressurizer and Regenerative Heat Exchanger Outlet.

1 EOP-3 R;v. 1/ Unit 1 Pega 8 of 40 III. RECOVERY _. ACTION _S ALTERNATE ACTIONS (2) Open Auxiliary Sp..

Valve, 1-CVC-517-CV (3) Shut Loop Charging Valves:

1-CVC-518-CV 1-CVC-519-CV (4) Shift 1-HIC-100 to MA! MAL and shut Pressurizer Spray Valves:

1-RC-100E-GV l-RC-100F-CV

5. Confirm Natural Circulation in at least one loop:

- ! E LE -

Wide range Thot may be obtained from Subcooled Margin Monitor per q g Attachment (10).

a. Thot minug Tcold between 10 and 50 F.
b. Tcold constant or decreasing.
c. Thot constant or decreasing.
d. CET temperatures consistent with Thot.
e. Steaming rate affects primary temperature.
6. IF either S/G level decreases to (-)350 Anches before Main Feed or AFW can be restored, TIIEN proceed to step J, page 13 AND continue efforts to restore Main Feed or AFW.

I I

EOP-3 R0v. 1/ Unit 1 Page 9 of 40 ALTERNATE ACTIONS

{ [I. _ RECOVERY ACTIONS H. ATTEMPT TO ESTABLISH AEW FLOW TO S/Gs:

-CAUTION-Before transferring AEW Pump suction to an alternate supply the possibility of suction line or CST rupture should be considered.

1. Confirm 12 CST operable: 1.1 IF 12 CST NOT operable, THEN line up 11 CST as
a. Ensurn 12 CST level alternate suction supply:

greater than 5 ft.

,a.

Locally open 11 CST AEW

b. Open 12 CST Unit 1 AFW Pump Suction Valves:

Pump Suction Valve, 1-AFW-161. 1-AEW-131 1-AEW-167

b. Locally chut 12 CST Unit 1 AFW Pump Suction l ) Valve, 1-AFW-161.
c. Confirm normal CST level response.

-NOTE-The following step will cause CST levels to equalize.

1.2 IF 11 CST NOT avai;able, THEr1 line up 21 CST as alternate auction aupply:

a. ally open 21 CST AFW

' action Valves:

c-Arw-131 2-AEW-167

b. Loc 111y open 12 CST AEW Pump Suction Valves:

1-AFW-161 2-AFW-161

c. Confirm normal CST level response.

EOP-3 Re. v . 1/ Unit 1 Page 10 of 40

'II . RECC,VERY ACTIONS ALTERNATE ACTIONS I k

2. Ensure normal AFW flowpath available:
a. Open all motor and steam 2.a.1 IF AFW Block Valve (s) will driven train AFW Block NOT open from Control Room, Valves: THEN locally open valve (s) using Hand Transfer 11 S/G 12 S/G Station (s) on North wall of SRW Room. l 1-AFW-4520-CV 1-\FW-4530-CV i 1-AFW-4521-CV l-AFW-4531-CV 1-AFW-4522-CV 1-AFW-4532-CV 1-AFF-4523-CV 1-AFW-4533-CV
b. Open AEW Flow Control 2.b.1 If AFW Flow Control Valves: Valve (s) will NOT open, THEN locally throttle 11 S/G 12_S/G open bypacs valve (s):

1-AFW-4511-CV 1-AFW-4512-CV a. 1511-CV 11 S/G Bypass 1-AFW-4525-CV 1-AEW-4535-CV Valve, 1-AFW-163, located in 27 ft East Penetration Room.

b. 4525-CV 11 S/G Bypass
  • Valve, 1-AFW-195, located in ShW Roem.
c. 4512-CV 12 S/G Bypass Valve, 1-AFW-165, located in 27 ft East Penetration 3.oom,
d. 4535-CV 12 S/G Bypass Valvo, 1-AEW-196, located in SRW Room.
3. Start Unit 1 AFW Pumps: 3.1 IF unable to feed S/Go with Unit 1 AFW Pumps,

- CAUTION - 'HD21 establish Unit 2 to Unit 1 cross connect operation:

D/G supplying power to 13 AFW '

Pump flow limit is 300 GPM; a. Shut Unit 2 motor train otherwise, flow limit is 575 GPM. AFW Block Valves:

a. Start 13 AEW Pump: 2-AFW-4522-CV 2-AFW-4523 CV 7 (1) Place 13 AFW Pump 2-AFW-4532-CV Handawitch in START. 2-AFW-4533-CV

)

L EOP-3 Tcv. 1/ Unit 1 Pcg:J 11 cf 40 l

/

'II . RECOVERY ACTIONS ALTERNATE ACTIOriS l I (2) 2nsure normal pump running current of b. Open Unit 2 To Unit 1 60 to 70 AMPS. AFW Cross Connect Valve, 2-AFW-4550-CV.

(3) Verify 13 AFW Pump flow of 150 GPM per CAUTION -

5/G.

D/G Supplying power to 23 AFW

b. Start 11 or 12 AFW Pump: Pump flow limit is 300 GM, otherwise, flow 11 tait is S75 GPM (1) Open 11 and 12 AFW Puenp Turbine Throttle / c. Start 23 AFW Pump Stop Valves:

(1) Place 23 AFW Pump 1-MS-3986 Handswitch in START. '

1-MS-3988 (2) Ensure normal pump (2) Open 11 and 12 AFW running current of Pump Main Steam 60 to 70 AMPS.

Supply Valves:

(3) Maintain 150 GPM 1-MS-109 flow to each S/G ,

1-MS-107 using Unit 1 AFW (3) Open 11 or 12 S/G AFW Steam Supply Valvest 1-AFW-4525-CV 1-AFW-4535-CV 1-MS-4070-CV 1-MS-4071-CV

'4) Verify 11 er 12 AFW Pump discharge j pressure approximately 100 PSI greater than S/G pressure.

(5) Verify 11 or 12 AFW Pump flow of 150 GPM per S/G

': . Ensure normal or energency AFW Room Ventilation oparable.

.s . 3_F AFW restored, 4.1 H AFW NOT restored, T11EN proceed *o appropriate TilEN proceed to step 1, step: page 12,

4. Once Through Core Cocling ff in ptogress, proceed to step N, pago 20.
b. Once Through Core Cooling i NOT in progress, procned to step V, page 30.

EOP-3 RCv. 1/ Unit 1 Pcgo 12 of 40 III. RECOVERY ACTIONS ALTERFL'E ACTIONS b ..

I. PREPARE TO FEED S/G WITH CONDENSATE BOOSTER PUMP:

1. Open S/G Feedwater Isolation Valves.
2. Shut Main Feed Regulating Valves.
3. Depress Feed Regulating Bypass Valve Reset Buttons.
4. Manually adjust Feed Regulating Bypass Valve Controllers to 30% output. ,
5. Open Condensate Precoat Filter and Condensate Domin Bypass Valves.
6. Verify one Condensate Pump running.
7. Verify one Condensate Booster Pump running.
8. Place Heater Drain Pump Handswitches in PULL-TO-LOCK.

- NOTE -

Feedwater flow to S/Gs should start when S/G pressure decreases to approximately 500 PSIA.

9. Monitor feedwater flow to S/G:
a. Main Feed Regulating Valve Differential Pressure Controller indicates greater than O.
b. S/G 1evel constant or increasing.

l l

EOP-3 Rcv. 1/ Unit 1 Pego 13 of 40 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I ,

10. IF Condensate Booster Pump 10.1 JF Condensate Booster flow restored, Pump will NOT feed S/G, THEN proceed to appropriate THEN proceed to step J, step page 13.
a. Once Through Core Cooling in progress, proceed to step N, page 20.
b. Once Through Core Cooling NOT in progress, proceed to step V, page 30.

4 J. ISOLATE S/Gs IN PREPARATION FOR ONCE THROUGH CORE COOLING: ,

1. WHEN the first S/G decreases to (-)350 inches, THEN isolate that S/G:
a. For S/G to be isolated, A } shut the motor and steam driven train AEW Block Valves:

11 S/G or 12 S/G 1-AFW-4520-CV 1-AFW-4530-CV 1-AEW-4521-CV 1-AEW-4531-CV 1-AFH-4522-CV 1-AFW-4532-CV 1-AFW-4523-CV 1-AFW-4533-CV

b. For S/G remaining to be steamed, place the motor i

and steam driven train AFW Biock Valve Handswitches in OPEN.

c. For S/G to be isolated, shut the AEW Steam Supply Valve.

11 S/_G - or _12 S/G 1-MS-4070-CV 1-MS-4071-CV I

i l . .

EOP-3 R v. 1/ Unit 1 Pcgo 14 of 40 III. PECOVERY ACTIONS ALTERNATE ACTIONS l I

d. For S/G to be isolated, 1.d.1 IF Atmonpheric Dump Valve shut the Atmospheric Dump will NOT shut from 1C43, Valve using the Hand THEN shut Atmospheric Dump Transfer Valves on the Manual Isolation Valve.

West wall of the Unit 1 45 ft Switchgear Room: 11 S/G or 12 S/G (1) Verify 1C43 Atmospheric 1-MS-101 1-MS-104 Dump Controllers at 0%

output.

(2) Align Hand Transfer Valves to 1C43 position:

11 S/G or 12 S/G

~

1-HV-3938A 1-HV-3939A 1-HV-3938B 1-HV-3939B

e. For S/G to be isolated, shut the MSIV.
f. Shut upstream drains by

{ } placing handswitch 1-HS-6622 in CLOSE.

2. Continue to steam uniso?.ated 2.1 IF Turbine Bypass Valves S/G, attempting to maintain unevailable, CET temperatures constant or THEN ;)ntinue to steam decreasing using Turbine unisolated S/G using Bypass Valve (s). Atmospheric Dump Valve.
3. WHEN the remaining S/C level decreares to (-)375 inches OR CET temperatures begin to j increase, THEN isolate botn S/Gs:
a. Shut the motor and steam driven train AFW Block Valves:

11 S/G 12 S/G i 1-AFW-4520-CV 1-AEW-4530-CV 1-AFW-4521-CV 1-AEW-4531-CV 1-AFW-4522-CV 1-AFW-4532-CV 1-AEW-4523-CV 1-AEW-4533-CV l l l

EOP-1

, Rov. 1/ Unit 1 l Pego 15 of 40 l III. RECOVERY ACTIONS ETERNATE ACTIOWS

b. Shut the AFW Steam Supply Valves

11 S/G 12 S/U 1-MS-4070-CV 1-MS-4071-CV

c. Shut Atmospheric Dump Valves,
d. Shut Turbine Bypass Valven.
e. Shut both MSIVs K. COMMENCE ONCE THROUGH CORE COOLING:

1

- CAUTION -

After S/G beccmes ineffective for heat removal, Once Through Core

{ l Cooling must be initiated prior to gET temperatures reaching 560 F to ensure adequate heat removal.

1. WHEN sither of the following conditions exist:
a. Steaming S/G becomes ineffective and CET temperatures begin to increase.
b. Both S/Gs isolated due to low level.

HIEN commence Once Through Core Cooling.

2. Shift Letdown Control Valve Controller, 1-HIC-110, to MANUAL and shut Letdown Control Valves:

1-CVC-110P-CV g g 1-CVC-110Q-CV

EOP-3 R;v. 1/ Unit 1 Page 16 of 40 U. RECOVERY ACTIONS ALTERNATE ACTIONS l I

3. Start all available Charging Pumps. l l

J l 4. Open Main and Aux HPSI

) Hender Valves:

1-SI-616-MOV 1-SI-617-MOV l 1-SI-626-MOV 1-SI-627-MOV l 1-SI-636-MOV 1-SI-637-MOV l 1-SI-646-MOV 1-SI-647-MOV

5. Starc 11 and 13 HPSI Fumps.
6. De-energize the Pressurizer Heaters by placing all handswitches in OFF. i 1
7. Start all available Containment A.: Coolers in IIIGH with maximum SRW flow.
8. Open both PGRVr:

g a. vEH2{ "PRSR PRESS BLOCK )

{

A(9) PERMITTF." alarm (s) received, THEN block SIAS A(B).  !

b. Verify both PORV Block Valves open.
c. Pull two High PressQrizer Pressure Trip Uraits,
d. Verify PORVs open.

EOP-3 R;v. 1/ Unit 1 Pcgg 17 of 43

'II . RECcVERY ACTIONS ALTERNATE ACTIONS l I ,

9. IF containment pressure increases to 2.8 PSIG, THEN verify ESFAS actuation AND commeace Verification Checklists:
a. SIAS per Attachment (2).
b. CIS per Attachment (4).
10. IF containment pressure increasee to 4.25 PSIG, THEN verify CSAS actuation AND commence Verification Checklist, Attachment (3).
11. Confirm initiation of Once ..

Through Core Cooling.

a. WHEN RCS pressure is less than 1270 PSIA, TBEN ensure HPSI flow AND CET temperatures constant or decreasing.
12. Using CET temperatures, i maintain sgbcooling between l 30 and 140 F per Attachment (1) by throttling HPSI flow: l 1
a. Lower subcooling by )

lowering HPSI flow.

b. Raise subcooling by ]

raising HPSI flow.

1

13. Continue cooldown using Once Through Core Cooling until l feedwater restored or shutdown cooling entry conditions are established.

- HOTE -

Additional guidance for feeding S/Gs is given in the CcJe and RCS Heat Removal section of EOP-8.

14. Continue efforts to restore

{ } Main Feed or AfW.

EOP-3 R;v. 1/ Unit 1 Page 18 of 40

'II. RECOVERY ACTIONS -ALTERNATE ACTIONS

( l L. WBEN RCS BORATION COMPLETE, THEN SHIFT CHARGING PUMP SUCTION SUPPLY TO MAKEUP SUPPLY WITH A LOWER BORIC ACID CONCENTRATION.

1. If SIAS actuated, 1.1 IE SIAS NOT actuated, THEN perform the following: THEN line up Charging Pump suction to VCT:
a. Open RWT To Charging Pump Suction Valve, a. Determine blend required 1-CVC-504-MOV. to maintain shutdown boron concentration per
b. Shut VCT Outlet Valve, NEOG-7.

1-CVC-501-MOV.

b. Open VCT Outlet Valve,
c. Place Boric Acid Pumps 1-CVC-501-M0V.

in PULL-TO-LOCK.

c. Secure Boric Acid Pump (s).
d. Ensure Charging Pump AMPS steady. d. Shut Boric Acid Direct Makeup Valve, 1-CVC-514-MOV.

g g

e. Shut BAST Gravity Feed Valves:

1-CVC-508-MOV 1-CVC-509-MOV OR line up Charging Pump .

cuction to RWT: j

a. Open RWT To Charging l Pump Suction Valve, 1-CVC-504-MOV.
b. 4 hut VCT Outlet Valve, '

1 1-CVC-501-MOV.

1

c. Shut Boric Acid Direct l

!!akeup Valvo, ,

1-CVC-514-MOV.

d. Secure Doric Acid Pump (s). l

EOP-3 R^v. 1/ Unit 1 Page 19 of 40 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I M. IF RWT LEVEL DECREASES TO BETWEEN O.5 AND 1.0 FT OR "ACTUATION SYS RAS TRIPPED" ALARM RECEIVED, 1 THEN VERIFY RAS ACTUATION: i i

1. Place SI Pump Recirc Lockout Switches in ON. l
2. Commence RAS Verification l Checklist, Attachment (6).

l

3. Shut RWT Outlet Valves:

1-ST.-4142-MOV l 1-SI-4143-MOV ,

l

4. IF HPSI flow greater than 1000 GPM with two HPSI Pumps operating, THEN equally throttle HPSI flow to 1000 GPM.

I I 5. If HPSI flow greater than 600 GPM with one HPSI Pump operating,

_THEN equally throttle HPSI flow to 600 GPM.

- CAUTION -

To prevent pump damage, minimum flow per operating HPSI Pump is 30 GPM.

6. IF HPSI Pump cavition occurs 6.1 IF Attachment (12) does NOT in recirculation mode, allow throttling HPSI flow, THEN throttle HPSI flow per THEN align Containment Spray Attachment (12). Pump (s) to HPSI Pump suction
a. IF 11 HPSI Pump cavitating,

.THEN open 11 SDC HX To HPSI Suction Valve, 1-SI-663-MOV AND start 11 Containment Spray Pump.

l I

EOP-3 R;v. 1/ Unit 1 Page 20 of 40

'II . RECOVERY ACTIONS ALTERNATE _A,CT_I_ONS l l

b. IF 13 HPSI Pump cavitating, THEN open 12 SDC HX To HPSI Suction Valve, 1-SI-662-MOV AND start 12 Contain.'ent Spray Pump.
7. Commence ECCS Pump Room cooling:
a. Open ECCS Pump Room Air Cooler Saltwater Valves:

1-SW-5170-CV 1-SW-5171-CV 1-SW-5173-CV

b. Start 11 and 12 ECCS Pump Room Cooling Fans,
8. Adjust saltwater Llow to maintain SRW and component cooling temperatures.

l l IF Charging Pumps are aligned 9.

with suction from RWT AND HPSI Pumps maintaining RCS inventory, THEN place Charging Pumps in PULL-TO-LOCK.

N. .IF FEEDWATER AVAILABLE AND CNCE THROUGH CORE COOLING IN PROGRESS, THEN EVALUATE FEEDING S/G:

1. IF decision made to feed S/G, 1.1 IF decision made NOT to T1IEN establish secondary heat feed S/G, sink in S/G with highest level. THEN continue Once Through Core Cooling until Shutdown Cooling can be used.

- CAUTION -

If voids exist in the S/O tuben, a rapid RCS pronoure reduction will occur when the voids collapne.

I I

EOP-3 Rsv. 1/ Unit 1 Page 21 of 40 III. RECOVERY ACTIONS ALTERNATE ACTIONS G

,CCOM CR 2. Throttle Auxiliary Feedwater

)88-1214 flow to less than 150 GPM OR throttle Main Feedwater flow to minimum by cracking the j Feed Regulating Bypass Valve i off its shut seat.

3. WHEN S/G level increases OR continuous feed has been maintained for 5 minutes, THEN slowly raise feed rate to raisc 3/G level to greater than (-)250 inches and trending toward O inches.
4. Align Atmospheric Dump Valve for S/G with highest level .

to 1CO3 and Atmospheric Dump Valve for S/G with lowest level to 1C43.

l 5. Adjust Atmoepheric Dump Valve to establish hatural O Circulation.

- CAUTION -

The RCS may be solid. Any action involving RCF cooldown or heatup l should be closely monitored to l prevent rapid pressure excursions. l

6. WHEN secondary heat sink I established, I THEN secure Once Through Core Cooling:
a. Operate HPSI and Charging Pumps as necessary to maintain RCS subcogling between 30 and 140 F.
b. Shut both PORVs:

(1) Insert High Pressurizor Pressure Trip Units that were previously pulled.

() (2) Ensure "PORV ENERGIZED" alarm clear.

EOP-3 R v. 1/ Unit 1 Paga 12 of 40 III. RECOVERY ACTIONS ALTERNATE _ ACTIONS i I ..

7. Confirm Natural Circulation:

- NOTE -

Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10),

a. Thot n.inug Teold between 10 and 50 F.
b. Tcold constant or decreasing.
c. Thot constant or decreasing,
d. CET temperatures consistent with Thot.
e. Steaming rate affects primary temperature.
8. Monitor for Core and RCS

}

voiding:

{

- CAUTION -

Potential for void formation increases rapidly when pressure decreases below 1500 PSIA.

a. Letdown flow greater than charging flow,
b. Rapid unexplained increase in pressurizer level during an RCS pressure reduction,
c. Loss of subcooled margin as determined using CET temperatures.
d. "REACTOR VESSEL WATER LEVEL LOW" alarm.

EOP-3 Rov. 1/ Unit 1 Pcga 23 of 40 ALTERNATE ACTIONS III, RECOVERY ACTIONS l I "

9. IF voiding inhibits heat removal, THEN reduce or eliminate voided areas
a. Shut Letdown Isolation Valve, 1-CVC-515-CV.

-CAUTION-The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

9.b.1 IF pressurizing the RCS does

b. Pressurize RCS to NOT restore heat removal, maintain g subcooling as
  • THEN operate Reactor Vessel near 140 F as practical. Vent Valves per OI-1G.
c. IF voiding occurs in the S/G Tubes (saturation pressure of S/G greater than saturation pressure l ) of RCS),

'1TIEN cool the S/G by raising any of the following:

(1) Steaming rate.

(2) Feed rate.

(3) S/G Blowdown rate.

AND o maintaining less than 100 F/h cooldown rate.

J

- CAUTION -

I Technical Specifications require  !

MPT protgction when Tcold less

)

I than 275 F.

10. Continue RCS cosidown until l able to initiate Shutdown Cooling.

1 4

l 9

EOP-3 R;v. 1/ Unit 1 Page 24 of 40 III. _ RECOVERY ACTIONS ALTERNATE ACT10NS I >

O. RESTORE CONTAINMENT ENVIRONMENT:

1. Direct Chemistry to place Hydrogen Monitors in service.
2. IF hydrogen concentration 1 increases to 1%, i THEN start Hydrogen Rocombiners per OI-41A. i
3. Maintain Iodine Filter Fans running.
4. WHEN containment pressura less than 4.0 PSIG, ,

I THEN perform the following:

a. Roset CSAS signal.
b. Secure one Containment Spray Pump.

1

{ I c. Verify all Containment Air Coolers operating to maintain containment temperature less than 120 E l

d. Restore equipment per CSAS Verification Checklist, Attachment (3), to desired condition.
5. WHEN containment pressure less than 2.8 PSIG, 3'l_IEE perform the following:
a. Block pressurizer pressure signals and reset SIAS signal.
b. Roset CIS signal,
c. Secure remaining Containment Spray Pump.
d. Restore equipment per SIAS and CIS Verification g

Checklists, Attachments (2) 4 and (4), to desired condition.

EOP-3 Rav. 1/ Unit 1 Pcga 25 of 40 lII. RECOVERY ACTIONS ALTERNATE ACTIONS l P. CET TEMPERATURES LESS THAN l g'F 300 AND RADIATION LEVELS PERMIT, THEN INITIATE SHUTDOWN COOLING:

1. WHEN RCS pressure less than 300 PSIA, THEN shut SI Tank Outlet Valves:

1-SI-614-MOV 1-SI-624-MOV 1-SI-634-MOV 1-SI-644-MOV

2. Lower hCS pressure to less 2.1 ,IF voiding prevents than 250 PSIA by throttling depressurization to 250 PSIA, HPSI flow while maintaining: THEN attempt to eliminate
a. Greater than 30 F subcooling using CET a. Alternately pressurize temperatures. and depressurize RCS by

. throttling HPSI flow.

{ p b. Greater than 30 GPM flow per operating HPSI Pump. b. Operate Reactor Veasel Vent Valves per 01-10.

3. WHEN RCS pressure less 3.1 f/ unable to initiate than 250 PSIA AND Shutdown Cooling, containmenh pressure THEN continue Once Through less than 4.0 PSIG, Core Cooling until able to THEN initiate Shutdown initiate Shutdown Cooling OR Cooling per OI-3. Feedwater available.

l l l

l

EOP-3 Rev. 1/ Unit 1 Pcg2 26 of 40 III. RECOVERY ACTIONS ALTERNATE ACTIONS

- CAUTION -

The RCS may be solid. Any action involving RCS cooldown or heatup should be closely monitored to prevent rapid pressure excursions. ,

4. WHEN Shutdown Cooling flow is established, THEN secure Once Through Core Cooling:
a. Operate HPSI or Charging Punips as necessary to maintain RCS pressure between 150 and 250 PSIA until CVCS letdown ~

available.

- CAUTION -

Technical specifications require MPT protgction when Tcold less than 275 F.

l I

b. Shur both PORVs:

(1) Insert High Pressurizer Pressurt Trip Units that were previously pulled.

(2) Ensure "PORV ENERGIZED" )

alarm clear.

I l

l l

Q. RESTORE SERVICE WATER TO TURBINE BUILDING: I

1. Verify 21 Plant Air Compressor operating.
2. Shut Plant Air To Plant Air Header Valve, 1-PA-2059-CV.

EOP-3 R;v. 1/ Unit 1 Pcgo 27 of 40 III. RECOVERY ACTIONS ALTERNATE ACTIONS I I .

3. Open Plant Air To Instrument Air Cross Connect Valve, 1-PA-2061-CV.
4. Open SRW Turbine Building Header Isolation Valves:

1-SRW-1600-CV 1-SRW-1637-CV 1-SRW-1638-CV 1-SRW-1639-CV R. RESTORE INSTRUMENT AIR COMPRESSORS TO SERVICE:

1. IF high temperature alarm exists on the Instrument Air Comprassors, THEN open the service water isolation valves by placing their handswitches in OPEN

( I until temperature alarm clears.

11 or 12 1-HS-2063 1-HS-2065

2. Start at least one Instrument Air Compressor.

S. RESTORE INSTRUMENT AIR TO CONTAINMEIC:

1. Open Cntmt Instruraent Air Isolation MOV, 1-IA-2080-MOV.

- NOTE -

1-HS-2085 located on West wall of 27 ft Switchgear Room; Key #85 in Control Room Key Locker.

q g 2. Open Cntmt Instrument Air Supply CV, 1-IA-2085-CV, by momentarily placing 1-HS-2005 in OPEN.

EOP-3 RCv. 1/ Unit 1 Page 28 of 40 III. RECOVERY ACTIONS ALTERNATE ACTIONS i I T. RESTORE LETDOWN FLOW:

1. Verify charging flowpath (

through Loop Charging Valves or Auxiliary Spray Valve.

2. Verify at least one Charging Pump operating.
3. Shift Letdown Control Valve Controller, 1-HIC-110, to MANUAL.
4. Adjust controller to shut Letdown Control Valves. .
5. Open Letdown Isolation Valves:

1-CVC-515-CV 1-CVC-516-CV

-CAUTION-

~

l I Thn setpoint of 1-PIC-201 must be above the saturatAon pressure for the letdown outlet temperature of the Regenerative Heat Exchanger.

6. Adjust the setpoint on 1-P2C-201 and adjust 1-HIC-110 to maintain desired RCS pressure.

U. DRAW PRESSURIZER BUBBLE IF DESIRED:

1. Adjust steaming rate or Shutdown Cooling to stabilize Tcold.
2. Heat up Pressurizer by energizing Backup and Proportional Heaters.
3. Adjust letdown flow ar.d Tcold

( l to maintain RCS sugeooling between 30 and 140 F.

L

EOP-3 R3v. 1/ Unit 1 Pcga 29 of 40 III. RECOVERY ACTIONS ALTERNATE ACTIONS I k ,,

4. WHEM pressurizer temperature exgeods CET temperatures by, 50 F, THEN maximize letdown:
a. Lower the netpoint on Letdown Backpressure Regulator Controller to obtain letdown flow of 100 GPM.
b. Secure Charging Pump (s) as needed to increase effective letdown.
5. WBEN saturstion pressure for the existing pressuriz<sr ,

temperature is reached,

_THrl confirm bubble formation by observing steady pressurizer pressure.

6. Using CET temperatures, maintain sgbcooling between 4 g 30 and 140 F rer Attachment (1) by operating:
a. Backup and Proportional Heater (s).
b. Auxiliary Spray.
7. Maintain pressurizer level between 101 and 180 inches by operating:
a. Charging flow.
b. Letdown flow.

l k I

EOP-3 Rev. 1/ Unit 1 Pcgo 30 of 40 I. RECOVERY ACTIONS ALTERNATE ACTIONS V. IF FEEDWATER AVAILABLE AND SHUTDOWN COOLING NOT OPERATING, THEN EVALUATE NEED FOR FORCED OR NATURAL CIRCULATION:

1. MREN RCPs available AND 1.1 IF RCPs NOT available OR Forced Circulation desired Natural Circulation desired, THEN start RCPs por steps THEN implement Natural 2-12. Circulation (AOP-3E) AND complete administrative post-trip actions.
2. IF RCPs exposed to excessive moisture, THEN consider meggering RCP ,

motor.

- CAUTION -

Uncontrolled restoration of cooling to hot RCP seals may cause j g degradation of the metallic seating surfaced by thermal shock.

3. IF Component Cooling is isolated to RCP seals, TBEN reduce RCP lowero seal temperature below 280 F prior to initiating full cooling flow to the RCPs:
a. Shut Component Cooling Supply Containment Manual Isolation Valve, 1-CC-284, j located in 5 ft East Penetration Room,
b. Verify CIS reset.
c. Open Componefit Cooling j Containment Isolation l l

Valves:

1 l

1-CC-3832-CV 1-CC-3833-CV i I

EOP-3 Rcv. 1/ Unit 1 Pcg2 31 of 40 III. RECOVERY ACTIONS ALTERNATE ACTIONS l l

d. Slowly cpen 1-CC-284 to throttle component cooling flow until lower seal temgeratures are less than 280 F.
e. WHEN lower seal temperatgres are less than 280 F, THEN fully open 1-CC-284.
4. IF an RCP lower seal temperature exceeded 280 F, THEN an engineering evaluation tu required prior to restarting that RCP.
5. Raise pressurizer level to at least 155 inches.
6. Verify RCP restart criteria:
a. RCS subgooling greater than 30 F.

l } l

b. At least one S/G available  !

for heat removal. l l

c. Pressurizer level greater 1 than 155 inches and stable,
d. Tcold less than 525 F.
e. RCS temperature and pressure greater than the ,

minimum operating limits '

per the RCP curve on l Attachment (1). l l

l

I EOP-3 Rev. 1/ Unit 1 Page 32 of 40 III. RECOVERY ACTIONS ALTERNATE ACTIONS NOTE --

Starting an RCP may cause a pressurizer level tranaient.

7. WHEN RCP restart criteria are met,

/ THEN start one RCP in a loop with an operable S/G:

a. Verify "COMPT CLG FLOW LO" alarm clear.
b. Start Oil Lift Pump.
c. Insert RCP sync stick.
d. Start one RCP.
e. Monitor RCP running current:

Tavo Current

( 525 to 572 F 238 to 210 AMPS and steady 210 to 525 F 264 to 238 AMPS and steady

8. JF pressurizer level decreases, THEN start Charging or HPSI Pump (s) as necessary to restore AND maintain level greater than 155 inches.
9. Monitor RCP seal parameters following pump restart.
10. Allow backflow to equalize temperatures in opposito loop.
11. Start second RCP in opposite loop por Stop V.7 and V.9, page 32.

EOP-3 Rev. 1/ Unit 1 Page 33 of 40 III. RECOVERY ACTIONS _A L_ _T_E R N A T E A C T I O N S i >

12. Secure Auxiliary Sprays
a. O.en Loop Charging Valves:

1-CVC-518-CV 1-CVC-519-CV

b. Shut Auxiliary Spray Valve, 1-CVC-517-CV.
c. Shift Pressurizer Spray Controller, 1-HIC-100, to AUTO.

W. COMPLETE ADMINISTRATIVE POST-TRIP ,

ACTIONS AND IMPLEMENT APPROPRIATE OPERATING PROCEDURE.

l (:)

EOP-3 R;v. 1/Un3t 1 Page 34 o6 40 l .

X. ADMINISTRATIVE POST-TRIP ACTIONS:

- ND7E -

The following actions may be accomplished whenever feasible.

They may be done in any order.

1. Refer to ERPIP to determitte appropriate emergency responsa actions.
2. Perform notifications per CCI-118.
3. Notify ESO of trip.
4. Request RCS Boron and Iodine sample. '
5. Perform shutdown margin calculation per NEOG 2 and 7.
6. Complete transient log entries per CCI-301.

l l 7. Recall post-trip review (preferably within 30 minutes of trip).

8. Perform post-trip review per CCI-111.
9. Monitor turbine bearing temperatures.
10. Continue Main Turbine shutdown per applicable step of CI-43A.

END OF SE(' f . A i .

l I

EOP-3 Rev. 1/ Unit 1 ,

Page 35 of 40 l I IV. SAFETY FUNCTION STATUS CHECK A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respecticeJy on entry and prior to exiting from this procedura.

B. Perform intermediate safety function status check at 10 minute intervals until plant conditions stabilize. '" '

C. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied.

D. Review data and verify that safety function acceptance criteria are s j satisfied.

gg E. When EOP completed, then perform final safety function check.

REACTIVITY SAFETY EUNCTION ACCEPTANCE CRITERIA CONTROL ~

PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL ,

CHECK CHECK O a. WRHI power less than 3% __________ less than 2% __ __

b. SUR (DPM) negativa O
c. CEA status all inserted __________

all inserted or

  • oration status: ,',E i

l appropriate "

concentration increasing __________

S/D margin 3 BAST level decreasing __________ N/A N/A e .

W e

O ,

(%

b

EOP-3 Rav. 1/ Unit 1 Page 36 of 40 0

RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND INVENTORY . , _ , , , , ,

PARAMETE.".S CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. Pressurizer 1000 to 2350 ,,_,____,_ less than 2300 pressure (PSIA)
b. Nessurizer 50 to 350 ' ' - - ' - - "

101 to 180 level (inches)

c. EgS subcooling 30 te 140 ,_________

30 to 140

( F)

If PORVs wer's opened, once an hour m.nitor the following:

d. Quench Tank parameters:

6 level (inches(j temperature pressure (PSIG)

F) constant or decreasing constant or decreasing

e. 20RV discharge piping temperature (,F)

CCOM CR (c mputer points 88-1173 T107, T108) decreasing __,,______

decreasing 9 ,

,f b p, , -

% ~ .ry. -

EOP-3 R;v. 1/ Unit 1 Pcg3 37 of 40 til> .

CORE AND RCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

c. RCS Tcold ( F) less than 540 ________

less than 535

b. CET ( F) less than 560 ___,_,,,

less than 540

c. TgotminusTcold

( F)

Natural Circulation 10 to 50 __,__,__ 10 to 50 Forced Circulation less than 10 ,_______

less than 5

d. S/G pressure less chan 960 ,,,_,___

less than 920 S/G ltvel (-)400 to (-)24 to l lC. (inches) (+)30 ___,,,,_ (+)30 _

f. Condener.ta greater Storage Tank than 5 and level (ft) greater than 5 ________

increasing 1

i l

i l

l l

l

EOP-3 R;v. 1/ Unit 1 Page 38 of 40 SAFETY FUNCTION ACCEPTANCE CRITERIA VITAL CRITERIA INTERMEDIATE CRITERIA FINAL AUXILIARIES CHECK CHECK

a. 4KV vital buses 11 or 14 energized __________

energized

b. Instrument Air greater greater pressure (PSIG) than 88 __________

than 88

c. Component Cooling

(# Pumps running) 1 or 2 __,___,,___ 1 or 2 _

d. Galtwater

(# pumps running) 1 or 2 __________

1 or 2 ,

e. Service Water

(# pumpa running) 1 or 2 __________

1 er 2 C

125V DC buses

) 11, 12, 21, 22 energized _ _ _ , _ _ _ _ _ , ,

energized

g. 120V AC vital buses 11, 12, 13, 14 energi4ed cnergized l

l 1

l i

i l i

l

EOP-3 R v. 1/ Unit 1 Page 39 of 40 l I

\ '

NORMAL SAFETY FUNCTION ACCEPTAPCE CRITERIA l CONTAINMENT _

l ENVIRONMENT CRITERIA INTERMEDIATA CRITERIA FINAL PARAMETERS CHECK CHEC'(

l a. Containment

pressure l (PSIG) less than 50 ,,,,,,,,, 31ss than 2.8
b. Containment tgmperature

( F) less than 276 ,,,,,,,,

less than 220 l c. Containment .

High Range Radiation alarm alarm Monitor clear ,,,,,,,,

clear

d. Hydrogen concentrat4.cn N/A --- IYb-- test than 2% _

l l 1

I I

i l >

EOP-3 )

Rcv, 1/ Unit 1 Paga 40 of 40 l I NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL TO CONTAINMENT CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. Noble cas alarm alarta Monitor clear __________

clear __

b. Condenser alarm alarm Off-Gas RMS clear ____,,,___

clear

> c. S/G B/D RMS alarm alarm clear ,,___,_____

clenr

d. Main Vent Gaseous alarm alarm RMS (1-RI-5415) ulear _ _ _ _ , , _ , , _ _ clear STATUS CHECK COMPLETE AT NUMBER TIME 1

2 _ _ _ ,

3 4

at aum l

I k l

l I

EOP-3 R.v. 1/ Unit 2 Page 1 of 40 l I l

CALVERT CLIFFS NUCLEAR POWER PLANT 1

l EOP-3 TOTAL _ LOSS OF ALL FEEDWATER REVISION 1 l s F ~ "ImR_ DATE f f PREP BY; -

SW # [ t. A/N ~ / k 1- b-I ) y T ' Q' VERIFIED BY; gA4d" 4f-hWJ- / /7 N/ 7 POSRC; l/EETIHG # D 'l / 2.- \ o 'AS APPROVED BY; kN tu eg/

farfagsSt}uclear Operations or General Supervisor-

/ 2- to S M 1

Operations if POSRC review is not required j l

1 I

I l

(

t >

EOP-3 R;v. 1/ Unit 2 Page 2 of 40 LIST OF EFFECTIVE _PAGES PAGE NUMBER REVISIOH 1 1 2 1 3 1 l

! 4 1 5 1 f 6 1 l 1 7

l 1 8

9 1 l 10 1 11 . 1 12 1 13 1 14 1 15 1 1 16 1 17 1 18 1

{ ) 1 19 20 1 ,

1 21 1 22 1 l 23 1 1 I

24 1 25 1 26 1 i 27 1 l 28 1 )

29 1 30 1 31 1 32 1 33 1 34 1 35 1 36 1 37 1 38 1 39 1 40 1 1

- 1

EOP-3 R;v. 1/ Unit 2 PCg3 3 of 40 l l TOTAL LOSS OF ALL FEEDWATER I. PKECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function.

B. Systems shifted to munua) operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could f.nduce inconsistencies between instruments.

D. Solid operation of the RCS should only be gttempted in order to maintain a subcooled margin of 30 F.

E. If solid operation of the RCS is undertaken, any functions or actions directly affecting makeup, letdown, system heatup or cooldown should be closely I I monitored to avoid rapid pressure excursions.

F. Feedwater should not be added to a dry S/G if the other S/G still contains water. If both S/Gs 5ecome dry, refill only one S/G to reinitiate Natural Circulation.

G. Minimir.e the number of cycles of pressurizer auxiliary spray whgn the temperature different$al is greater than 400 F.

H. In Natural Circulation, increased loop transport time causes a 5 to 10 minute delay in temperature responses to a plant change. Pressurizer level and pressure responses, if available, typically provide better indication of RCS response 'aring this period.

I. S/G prescure, pressuricer pressure, and containment temperature affect the level indication for the S/Gs and Pressurizer. Attachments (8) and (9) contain the corrected S/G and pressurizer levels for various S/G pressures, pressurizer pressures, and containment temporatures.

J. If a pump or component fails, the cause of the failure should be determined prior to restarting or starting a

{ ) standby pump or component to prevent a common failure. .

I I 1

l

ECP-J R v. 1/ Unit 2 Pcga 4 of 40 4 > .

II. Kl;TRY CONDITIONS The presence of one or more of the following conditions indicates that a Total Loss of All Feedwater may have occurred:

A. Loss of Condensate Storage Tank inventory.

B. Loss of Condenser Hotwell level.

C. Low suction or discharge pressure for either the Condensate, Condensate Booster, or S/G Feed Pumps.

D. S/G Turbine Tripped alarm on both S/G Feed Pumps.

E. Low suction or discharge pressure for the AFW Pumps.

F. Motor System No Flow alarm fdr AEW.

G. Turbine System No Flow alarm for AFW.

I I r

EOP-3 R;v. 1/ Unit 2 Pega 5 cf 40 II. RECOVFRY ACTIONS ALTERNATE ACTIONS A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED.

B. COMMENCE INTERMEDIATE SAF3TY FUNCTION STATUS CHECK.

C. ERPIP REQUIRES THAT A SITE EMERGENCY EE DECLARED IF totis',

LOSS OF MAIN AND AUXILIARY FEEDWATER EXISTS FOR LONGER ,

THAN TEN MINUTES.

D. TRIP ALL RCPs.

l I E. MINIMIZE S/G INVENTORY LOSS.

1. Shut S/G Blowdown Valves:

2-BD-4010-CV 2-BD-4011-CV 2-BC-4012-CV 2-BD-4013-CV

2. Depress Reset Button on MSR Control Panel to shut Second Stage Steam Source Valves:

2-MS-4017-CV 2-MS-4018-CV 2-MS-4019-CV 2-MS-4020-CV

. COMMENCE RCS BORATION:

1. Shut VCT Makeup V01vc, 2-CVC-512-CV.

EOP-3 R:v. 1/ Unit 2 Pag] 6 of 40 1II. RECOVERY ACTIONS ALTERNATh. ACTIONS l I

2. Open Boric Acid Direct ,

Makeup Valve, 2-CVC-514-MOV.

3. Start a Boric Acid Pump. 3.1 IF Boric Acid Pumps NOT available, THEN establish gravity feeds
a. Open BAST Cravity Feed Valves:

2-CVC-508-MOV 2-CVC-509-MOV

b. Shut VCT Outlet Valve, 2-CVC-501-MOV.

l 4. Start all tvailable Charging Pumps. ,

5. Continue boration until a total 65 inch decrease in BAST level (s) is achieved, or  ;

shutdown margin requirement of NEOG-ll is achieved.  !

AI i ,

G. ESTABLISH NATURAL CIRCULATION AND i COOL DOWN RCS: l I

1. Block ESFAS actuation:

i

a. WHEN "SGIS A(B) BLOCK 1.a.1 If SGIS actuates, I PERMITTED" alarm (s) THEN reset SGIS: I received, I THEN block SGIS A(B). a. Place Condensate I l Booster Pumps in PULL-TO-LOCK.

I b. Match handswitches per SGIS Verification l Checklist, Attachment (7).

1

' c. Block SGIS.

d. Reset SGIS signal.

l l

, l l

\ 1 l

EOP-3 Rov. 1/ Unit 2 Pcg3 7 cf 40 TII. RECOV_ERY ACTIONS ALTERNATE ACT_ IONS I I '

e. Open S/G Feedwater Isolation Valves:

2-FW-4516-MOV 2-FW-4517-MOV

f. Start a Condensate Booster Pump.
b. W HEN "PRSR PRESS BLOCK A(B) PERMITTED" alarm (s) received, THDi block SIAS A(B).
2. Commence cooldown by throttling Turbine Bypass or Atmospheric Dump Valves l

while maintaining:

a. Less than 100 F/h RCS cooldown rate.
b. Pressurizcr level between l 50 and 180 inches.
3. Shut Letdown Isolation Valv.s l

2-CVC-515-CV l 2-CVC-516-CV

4. Maintain RCS subcogling between 30 and 140 F:

l l a. Raise subcooling by:

(1) Energizing Pressurizer l Heaters.

1 l

! (2) Increasing cooldown I

rate, l

I b. Lower subcooling by I

initiating Auxiliary l

Spray:

l (1) Record temperature l differential between 1

( Pressurizer and t

Regenerative Heat 1 Exchanger Outlet.

{ }

I l

l l

EOP-3 R;v. 1/ Unit 2 Pcg3 8 of 40 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I ,

(2) Open Auxiliary Spray Valve, 2-CVC-517-CV.

(3) Shut Loop Charging Valves:

2-CVC-518-CV 2-CVC-519-CV (4) Shift 2-HIC-100 to MANUAL and shut Pressurizer Spray Valves:

2-RC-100E-CV 2-RC-100F-CV

5. Confirm Natural Circulation in at least one loop

- NOTE -

Wide : ange Thot may be obtained from Subcooled Margin Monitor per

) Attachment (10),

(

a. Thot minug Tcold between 10 and 50 F.
b. Teold constant or decreasing,
c. Thot constant or decreasing,
d. CET temperatures consistent with Thot,
e. Steaming rate affects primary temperature.
6. IF either S/G level decreases to (-)350 inchen before Main Feed or AFW can be restored, THEN proceed to step J, page 13 SSD continue efforts to restore Main Feed or AFW.

l l

EOP-3 R;v. 1/ Unit 2 Page 9 of 40 I. RECOVERY ACTIONS ALTERNATE ACTIONS H. ATTEMPT TO ESTABLISH AFW ELOW TO S/Gs:

-CAUT1oN-Before transferring AEW Pump suction to an alternate supply the possibility of suction line or CST rupture should be considered.

1

! 1. Confirm 12 CST opetable: 1.1 IF 12 CST NOT operable, THEN line up 21 CST as

a. Ensure 12 CST level alternate auction supply:

l greater than 5 ft.

l

,a. Locally open 21 CST AEW I b. Open 12 CST 7 nit 2 AFW Pump Suction Valves:

1 Pump Suction Valve, 2-AFW-161. 2-AFW-131 2-AFW-167

b. Locally shut 12 CST Unit 2 AFW Pump Suction q g Valve, 2-AFW-161,
c. Confirm normal CST level response.

-HOTE-The following etep will cause CST levels to equalize.

1.2 IF 21 CST NOT available, 21IEH line up 11 CST as alternate suction supply:

a. Locally open 11 CST AFW

[

Pump Suction Valves:

1-AFW-131 1-AFW-167

b. Locally open 12 CST AFW Pump Suction ValveJ:

1-AEW-161 2 - AFF 'l 61

c. Confirm normal CST level response.

g EOP-3 Rcv. 1/ Unit 2 Pago 10 cf 40 III. REC;OVERY ACTIONS  % TERNATE _ ACTIONS i ) '

2. Ensure normal AFW flowpath available:
a. Open all motor and steam 2.a.1 II AFW Block Valve (s) will driven train AFW Block HOT open from Control Room, Valves: THEN locally 'ipen valve (s) using Hand Transfer 21 S/G 22 S/G Station (s) on South wall of SRW Room.

2-AFW-4520-CV 2-AFW-4530-CV 2-AFW-4521-CV 2-AFW-4531-CV l 2-AFW-4522-CV 2-AFW-4532-CV 2-AFW-4523-CV 2-AFW-4533-CV

b. Open AFW Flow Control 2.b.1 If AFW Flow Control Valves: Valve (s) will NOT open, THEN locally throttle l 21 S/G 22 S/G open bypass valve (s):

1 2-AFW-4511-CV 2-AFW-4512-CV a. 4511-CV 21 S/G Bypass 2-AFW-4525-CV 2-AFW-4535-Ct! Valve, 2-AFW-163, located in 27 ft East Penetration Room.

l l l b. 4525-CV 21 S/G Bypass Valve, 2-AFW-195, located in SRW P.com.

c. 4512-C1 22 S/G Bypass Valve, 2 AhW-165,
located in 27 ft East Penetration Room,
d. 4535-CV 22 S/G Bypass l Ykive, 2-aFW-196,
located in SRW Room.

l

3. Start Unit 2 AFW Pumps: 3.1 If unable to feed S/Gs with Unit 2 AFW Pumps,

_CA.UILOB - TFEN establish Unit 1 to Unit 2 cross connect operation:

D/G supplying power to 23 AFW l Pump flow limit is 300 GPM; a. Shut Unit 1 motor train othe rwise, flow limit is 575 GPM. AFW Block Valves l

l a. Start 23 AEW Pump: 1-AFW-4522-CV 1-AFW-4523-CV (1) Place 23 AEW Pump 1-AFW-4532-CV Handswitch in START. 1-/.FW-4533-CV l l l

l l

l 1

EOP-3 Rcy. 1/ Unit 2 Pcg] 11 cf 40

'II. _ RECOVERY ACTIONS ALTERNATE A W OliS l I (2) Ensuro normal pump running current of b. Open Unit 1 To Unit 2 60 to 70 AMPS. AEW Cross Connect Valve, 1-AEW-4550-CV.

(3) Verify 23 AFW Pump flow of 150 GPM per - CAUTlON -

S/G.

D/G Supplying power to 13 AFW

b. Start 21 or 22 AFW Pump Pump flow limit in 300 GPM, otherwise, flow limit in 575 GPM (1) Open 21 and 22 A'id Start 13 AFW Pump:

Pump Turbino Throttle / c.

Stop Valves: Place 13 AEW Pump (1) 2-MS-3986 Hhndewitch in START.

2-MS-3988

. (?) Ensure norcal pump (2) Open 21 and 22 AFd running current of Pump Main Steam 60 to 70 AMPS.

Supply Valves (3) Maintain 150 GPM 2-MS-109 flow to each S/G 2-MS-107 using Unit 2 AEW (3) Open 21 or 22 S/G AEW Steam Supply Valves: 2-AFW-4525-CV 2-AFW-4535-CV 2-MS-4070-CV 2-MS-4071-CV (4) Verify 21 or 22 ATH Pump discharge pressure approximately 100 PSI greater than S/G pressure.

(5) Verify 21 or 22 AFW Pump flow of 150 GPM per S/G.

c. Ensure normal or emergency AFW Room Ventilatior.

operable.

4. JF AFW restored, 4.1 JF AEW HOT restored, THEN proceed to appropriate TMEU proceed to step I, step page 12.

i a. Once Through Core Cooling

( ) in progress, proceed to stop N, page 20,

b. Once Through Core Cooling NOT in progress, proceed to step V, page 30.

EOP-3 R v. 1/ Unit 2 Pcg3 12 cf 40

'II . RECOVERY ACTIONS ALTERNATE ACTIONS I. PREPARE TO FEED S/G WITH CONDENSATE BOOSTER PUMP:

1. Open S/G Feedwater Isolation Valves.
2. Shut Main Feed Regulating Valves.
3. Depress Feed Regulating Bypasu Valve Reset Buttons.
4. Manually adjust Feed Regulating Bypass Valve Controllers to 30% output. .,
5. Open Condensate Precoat Filter and Cordensate Demin Bypass Valves.
6. Verify one Condensate Pump running.
7. Verii'y one Condensate Boostsr Pump running.
8. Place Heater Drain Pump Handswitches in PULL-TO-LOCK.

NOTE -

Feedwater flow to S/Gs should start when G/G pressure decreases to approxiitately 500 PSIA.

l

9. Monitor t'eedwater flow to S/G:
a. Main Feed Regulating Valve Differential Pressure Controller indicates l l greater than O.  :

' l

b. S/G level constant or j increasing.  ;

l 1 1 1

l

80P-3 ROV. 2/ Unit 2 Paga 13 of 40

'II . RECOVERY ACTIONS AL_ TERNATE ACTIO4S

10. IF Condensate Booster Pump 10.1 IF Condensate Booste" flow restored, Pump will N9T feed L/G, THEN proceed to appropriate THEN proceed to step J, steps page 13.
a. Once Through Core Cooling in progress, proceed to step N, page 20.
b. Once Through Core Cooling HQT in progress, proceed to step V, page 30.

J. ISOLATE S/Gs IN PREPARATION FOR ONCE THROUGH CORE COOLING: ,

1. WHEN the first S/G decreases to (-)350 inches, THEN isolate that S/G:
a. For S/G to be isolated, I I shut the motor and steam driven train AFW Block Valves:

21 S/G or 22 S/G 2-AEW-4520-CV 2-AFW-4530-CV 2-AFW-4521-CV 2-AEW-4531-CV 2-AFW-4522-CV 2-AFW-4532-CV 2-AEW-4523-CV 2-AEW-4533-CV

b. For S/G remaining to be etcamed, place the motor and steam driven train AFP Block Valve Handswitches in OPEN.
c. For S/G to be isolated, shut the AFW Steam Supply Valve.

21 S/G or 22 S/G 2-MS-4070-CV 2-MS-4071-CV I I w

EOP-3 R;v. 1/ Unit 2 Pcg3 14 of 40 III. RECOVERY ACTIOPLS ALTERNATE ACTIONS

.i > ,

d. For S/G to be isolated, 1.d.1 If Atmospheric Dump Valve i shut the Atmospheric Dump will NOT shut from 2C43, Valve using the Hand THEN shut Atmospheric Dump I Transfer Valves on the Manual Isolation Valve.

West wall of the Unit 2 45 ft Switchgear Room: 2_1 S/G or 22 S/G l

l (1) Verify 2C43 Atmospheric S-MS-101 2-MS-104 l Dump Controllers at 0%

l output.

I I

l (2) Align Hand Transfer Valves to 2C43 position:

l 21 S/G or 22 S/G 2-HV-3939A 2-HV-3930A 2-HV-3939B 2-HV-3938B 1

e. For S/G to be isolated, shut the MSIV.
f. Shut upstream drains by

( I placing handsw!tch 2-US-6622 in CLOSE.

l

2. Continue to steam unisolated 2.1 1E Turbine Bypass Valves S/G, attempting to maintain unavailable, CET temperatures constant or THEN continue to steam decreasing using Turbine unisolated S/G using Bypass Valve ( s) . Atmospheric Dump Valve.
3. WHEN the remaining S/G level decreases to (-)375 inches OR CET temperatures begin to increase, THEN isolate both S/Gs:
a. Shut the motor and steam driven train AEW Block Valves:  ;

1

?) S/G 22 S/G  ;

l l 2-AEW-4520-CV 2-AFW-4530-CV i 2-AFW-4521-CV 2-AFW-4531-CV l l

2-AFW-4522-CV 2-AFW-4532-CV l l 2-AFW-4523-CV 2-AEW-4533-CV l l l l

EOP-3 Rav. 1/ Unit 2 Page 15 of 40 RECOVERY ACTIONS ALTERNATE ACTIONS

]I.

b. Shut the AFW Steam Supply Valves:

21 S/G 22 S/G 2-MS-4070-CV 2-MS-4071-CV

c. Shut Atmospheric Dump Valves,
d. Shut Turbine Bypass Valves,
e. Shut both MSIVs.

~

K. COMMENCE ONCE THROUGH CORE COOLING:

- CAUTION -

After S/G becomes ineffective for heat recoval, once Through Core

{ }

Cooling must be initiated prior to gET temperatures reaching 560 F to ensure adequate heat removal.

1. WHEN either of the following conditions exist:
a. Steaming S/G becorr.es ineffective and CET temperatures begin to increase.
b. Both S/Gs isolated due to low level.

_TPDj commence Once Through Core Cooling.

2. Shrft Letdown Control Valve Controller, 2-HIC-110, to MANUAL and shut Letdown Control Valves:

2-CVC-110P-CV I  ! 2-0VC-110Q-CV

EOP-3 R v. 1/ Unit 2 Pcgo 16 cf 40

11. RECOVERY ACTIGNS ALTERNATE ACTIONS I I
3. Start all available Charging Pumps.
4. Open Main and Aux HPSI Header Valves:

2-SZ-616 MOV 2-SI-617-MOV 2-SI-626 MOV 2-SI-627-MOV 2-SI-636-MOV 2-SI-637-MOV 2-SI-646-MOV 3-SI-647-MOV

5. Start 21 and 23 HPSI Pumps,
6. De-energize the Pressurizer Heaters by placing all handswitches in OFF.
7. Start all ave.ilable Containment Air Coolers in HIGH with maxinum SRW flow.
8. Open both PORVis i 6 a. LG_IEN "PRSR PRESS BLOCK P

A(D) PERMI "TED" alarm ( s) received,

_THEN block SIAS A(B).

b. Verify both PORV Block Valves open,
c. Pull two High Pressurizer Pressure Trip Units,
d. Verify PORVs open.

l I y

EOP-3 R;v. 1/ Unit 2 Page 17 of 40 ALTERNATE ACTIONS q {I. BECOVERY ACTIONS

9. IF containment pressure increases to 2.8 PSIG, THEN verify ESFAS actuation AND commence Verification Checklists:
a. SIAS per Attachment (2).
b. CIS per Attachment (4).
10. IF containment pressure increases to 4.25 PSIG, THEN verify CSAS actuation OND commence Verification Checklist, Attachment (3).
11. Confirm initiation of Once ,

Through Core Cooling.

a. WHEN RCS pressure is less taan 1270 PSIA, T_IIEN ensure HPSI flo" AND CET temperature 0

{ l constant or docreabing.

12. Using CET temperatures, maintain ogbcooling between 30 and 140 F per Attachment (1) by throttling HPSI flows
n. Lower subcooling by lowering HPSI flow.
b. Raise subcooling by raising HPSI flow.
13. Continue cooldown using Once Through Core Cooling until feedwater restored or shutdown cooling entry conditions are established.

- NOTE -

Additional guidance for feeding S/Gs is given in the Core and RCS Heat Removal section of EOP-8,

14. Continue efforts to restore I Main Feed or AFW. I

EOP-3 R v. 1/ Unit 2 Page 18 of 40 RECOVERY ACTIONS ALTERNATE ACTIONS

{ )I.

j L. MHEN RCS BORATION COMPLETE,

_THEN SHIFT CPARGING PUMP SUCTION SUPPLY TO MAKEUP SUPPLY WITH A .

I LOWER BORIC ACID CONCENTRATION.

1. IF SIAS actuated, 1.1 IF SIAS NOT actuated, THEN perform the following: THEN line up Charging Pump suction to VCT:
a. Open RWT To Charging Pump Suction Valve, a. Determine blend required 2-CVC-504-MOV, to maintain ehutdown boron concentration per
b. Shut VCT Outlet Valve, NEOG-11, 2-CVC-501-MOV.

.. b . Open VCT Outlet Valve,

c. Place Boric Acid Pumps 2-CVC-501-MOV.

in PULL-TO-LOCK.

c. Secure Boric Acid Pump (s),
d. Ensure Charging Pump AMPS steady, d. Shut Boric Acid Direct Makeup Valve, l I 2-CVC-514-MOV.
e. Shut BAST Gravity Feed Valves:

2-CVC-508-MOV 2-CVC-509-MOV OB line up Charging Pump BitCtiCn to RWT:

a. Open RWT To Charging Pump Suction Valve, 2-CVC-504-MOV.
b. Shut VCT outlet Valve, 2-CVC-501-MOV.
c. Shut Boric Acid Direct Makeup Valve, 2-CVC-514-MOV.
d. Secure Boric Acid Pump (s),

i i

' _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ __ . _ _ _ _ _]

EOP-3 R' v . 1/ Unit 2 Pou c 19 cf 40

'II. RECOVERY ACTIONS ALTERNATP, ACTIONS l I M. JI RWT LEVEL DECREASES TO BETWEEN 0.5 AND 1.0 FT OB "ACTUATION SYS RAS TRIPPED" ALARM RECEIVED, THEN VERIFY RAS ACTUATION:

1. Place SI Pump Recir Lockout l Switches in ON. l
2. Commence RAS Verification Checklist, Attachment (6).
3. Shut RWT Outlet Valves:

l 2-SI-4142-MOV 2-SI-4143-MOV .. {

t

4. IF HPSI flow greater than 1000 GPM with two HPSI Pumps operating, THEN equally throttle HPSI flow to 1000 GPM.
5. 1F HPSI flow greater than 600 GPM with one HPSI Pump I operating, l THEN equally throttle HPSI flow to 600 GPM.

- CAttrLOg -

To prevent pump damage, minimum flow per operatine HPSI Pump is 30 GPM.

6. IE HPS1 Pump cavition occurs 6.1 IF Attachment (12) does HQT in recirculation mode, allow throttling HPSI flow,

,T_ITEN throttle HPSI flow per HIEN align Containment Spray Attachm0nt (12). Pump (s) to HPSI Pump suction:

l

a. If 21 HPS1 Pump l

cavitating, THEN open 21 SDC HX To l HPSI Suction Valve, 2-SI-663-MOV SNQ st rt 21 Containment Spray Pump.

l I

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A+ b '

/ l Q &@^%s ,

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EOP-3 Rcv. 1/ Unit 2 Pcge 20 of 40 I. RECOVERY _ ACTIONS ALTERNATE ACTI.ONS

b. IF 23 HPSI Pump cavitating,

_THEN open 22 SDC IOC To HPSI Suction Valve, 2-SI-662-MOV SND start 22 Containment Spray Pump.

7. Commence ECCS Pump Room I cooling:
a. Open ECCS Pump Room Air Cooler Saltwater Valves:

2-SW-5170-CV 2-SW-5171-CV 2-SW 5173-CV

b. Start 21 and 22 ECCS Pump Room Cooling Fans.
8. Adjust saltwater flow to maintain SRW and component cooling temperatures.

l I

9. IF Charging Pumps are aligned with suction from RWT AND HPSI Pumps maintaining RCS inventory, THEN place Charging Pumps in PULL-TO-LOCK.

N. IF FEEDWATER AVAILABLE AND ONCE THROUGH CORE COOLING IN PROGRESS, 71534 EVALUATE FEEDING S/G:

i

1. IF decision made to feed S/G, 1.1 IF decision made NOT to THEN establish secondary heat feed S/G, sink in S/G with highest level. THEN continue Once Through ,

Core Cooling until Shutdown Cooling can be used. i

- CAUTION -

If voids exist in the S/G tubes, a rapid RCS pressure reduction will occur when the voids collapse.

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._m._ _ _ _ _ _ _ _ _ __ _ _ _ __ _ . _ __ _ _ . _ _ .

EOP-3 h Rev. 1/ Unit 2

,' Page 21 of 40 III. RECOVERY ACTIOMS M.T_EttNA.TE ACTIONS

2. Throttle Auxiliary Feedwater lCCOMCR flow to less than 150 GPM g .

I j88-1214 throttle hain Feedwater flow to minimum by cracking the l

i Feed Regulating Bypass Valve  ;

off its shut seat.

{

3. WEEN S/G 1evel increases 3 continuous feed has been maintained for 5 minutes, j THEN slowly raise feed rate i to raise S/G level to greater l than (-)250 inches and l
trending toward 0 inches. i Align Atmospheric Dump Valve I
4. '

i for S/G with highest level ,

j to 2CO3 and Atmospheric Dump j

Valve for S/G with lowest ,

j level to 2C43.  !

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5. Adjust Atmospheric Dump Valve  ;

j to establish Natural Circulation.

4 - CAUTION - f The RCS may be solid. Any action involving RCS cooldown or heatup l should be closely monitored to i l prevent rapid pressure excursions. j j

' l j 6. WREtt secondary heat sink J established, i j THEN secure once Through l

{ Core Cooling:

a. Operate NPSI and Charging  ;

. Pumps as necessary to ~

j maintain RCS subcogling l

between 30 and 140 F.

b. Shut both PORVs (1) Insert High i Pressutizer Pressure Trip Units that were l; previously pulled.

(2) Ensure "PORV ENERGIZED" alarm clear.

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EOP-3 Rov. 1/ Unit 2 Page 22 of 40 1I. RECOVERY ACTIONS ALTERNATE ACTIONS

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7. Confirm Natural Circulation:

- NOTE -

Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10).

a. Thot minug Tcold between 10 and 50 F.
b. Tcold constant or decreasing,
c. Thot constant or decreasing.
d. CET temperatures consistent with Thot,
e. Steaming rate affects primary temperature.

l )

8. Monitor for Core and RCS voiding:

- CAUTION -

Potential for void formation increases rapidly when pressure decreases below 1500 PSIA.

a. Letdown flow greater than charging flow,
b. Rapid unexplained increase in pressurizer level during an RCS pressure reduction,
c. Loss of subcooled margin as determined using CET temperatures.
d. "REACTOR VESSEL WATER LEVEL LOW" alarm.

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EOP-3 R;v. 1/ Unit 2 Page 23 of 40 RECOV5RY ACTIONS ALTERNATE ACTIONS l )I .

9. IF voiding inhibits heat removal, THEN reduce or eliminate voided area:
a. Shut Letdown Isolation Valve, 2-CVC-515-CV.

-CAUTION-The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

Pressurize RCS to 9 b.1 If pressurizing the RCS does b.

subcooling as .

NOT restore heat removal, maintain,F as practical.

THEN operate Reactor Vessel near 140 Vent Valves per 01-1G.

c. If voiding occurs in the S/G Tubes (saturation pressure of S/G greater l k than saturation pressure of RCS),

THEN cool the S/G by raising any of the following:

(1) Steaming rate.

(2) Feed rate.

(3) S/G Blowdown rate.

AND maintaining less thtn 100 F/h cooldown rate.

- CAUTION -

Technical Specifications require MPT protgction when Tcold less than 275 F.

10. Continue RCS cooldown until able to initiate Shutdown Cooling.

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EOP-3 R v. 1/ Unit 2 Page 24 of 40

'I. RECOVERY ACTIONS ALTERNATE ACTIONS I i O. RESTORE CONTAINMENT ENVIRONMENT:

1. Direct Chemistry to place Hydrogen Monitors in service.
2. If hydrogen concentration

'ncreases to 1%,

'IBEN start Hydrogen Recombiners per OI-41A.

3. Maintain Iodine Filter Fans running.
4. MHEN containment pressure less than 4.0 PSIG, .

THEN perform the following:

a. Reset CSAS signal,
b. Secure one Containment Spray Pump.

l I Verify all Containment Air c.

Coolers operating to maintain containment temperature less than 120 F,

d. Restore equipment per CSAS Verification Checklist, Attachment (3), to desired condition.
5. MIEN containment pressure less than 2.8 PSIG, THEN perform the following
a. Block pressurizer pressure signals and reset SIAS signal,
b. Reset CIS signal. )

l

c. Secure remaining Containment Spray Pump.
d. Restore equipment per SIAS l l

and CIS Verification l I Checklists, Attachments (2) i and (4), to desired condition.

EOP-3 R v. 1/ Unit 2 Page 25 of 40 I. RECOVERY ACTIONS ALTERNATE ACTIONS P. _q CET TEMPERATURES LESS T1W1 300 F bHD RADIATION LEVELS PERMIT, THKH INITIATE SHUTDOWN COOLING:

1. MHEN RCS pressure less than 300 PSIA, THEN shut SI Tank Outlet Valves:

2-SI-614-MOV 2-SI-624-MOV 2-SI-634-MOV 2-SI-644-MOV

2. Lower RCS pressure to less 2.1 ,.IF voiding prevents than 250 PSIA by throttling depressurization to 250 PSIA, HPSI flow while maintaining: THEN attempt to eliminate
a. Greater than 30 F subcooling using CET a. Alternately pressurize temperatures, and depressurize RCS by
b. Greater than 30 GPM flow per operating HPSI Pump. b. Operate Reactor Vessel Vent Valves per OI-lG.
3. MUEN RCS pressure less 3.1 IF unable to initiate than 250 PSIA OND Shutdown Cooling, containment pressure THEN continue Once Through less than 4.0 PSIG, Core Cooling until able to THEN initiate Shutdown initiate Shutdown Cooling OR Cooling per 01-3. Feedwater available.

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EOP-3 R v. 1/ Unit 2 Pego 26 of 40

'II. RECOVERY ACTIONS ALTERNATE ACTIONS I .

- CAUTION -

The RCS may be solid. Any action involving RCS cooldown or heatup should be closely monitored to prevent rapid pressure excursions.

4. WHEN Shutdown Cooling flow is established, THEN secure Once Through Core Cooling
a. Operate HPSI or Charging Pumps as necessary to maintain RCS pressure between 150 and 250 PSIA until CVCS letdown ,

available.

- CAUTION -

Technical specifications require MPT protgetion when Tcold less than 275 F.

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b. Shut both PORVs:

(1) Insert High Pressurizer Pressure Trip Units that were previously pulled.

(2) Ensure "PORV ENERGIZED" alarm clear.

Q. RESTORE SERVICE WATER TO TURBINE BUILDING:

1. Verify 11 Plant Air Compressor operating.
2. Shut Plant Air To Plant Air Header Valve, 2-PA-2059-CV.

EOP-3 R3v. 1/ Unit 2 Pago 27 of 40 C II . RECOVERY ACTIONS ALTERNATE ACTIOfiS

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3. Open Plant Air To Instrument Air Cross Connect Valve, 2-PA-2061-CV.
4. Open SRW Turbine Building Header Isolation Valves:

2-SRW-1600-CV 2-SRW-1637-CV 2-SRW-1638-CV 2-SRW-1639-CV R. RESTORE INSTRUMENT AIR COMPRESSORS TO SERVICE:

1. IF high temperature alarm exists on the Instrument Air Compressors, THEN open the service water isolation valves by placing j g their handswitches in OPEN until temperature alarm clears.

21 or 22 2-HS-2063 2-HS-2065

2. Start at least one Instrument Air Compressor.

S. RESTORE INSTRUMENT AIR TO CONTAINMENT-

1. Open Cntmt Instrument Air Isolation MOV, 2-IA-2080-MOV.

- NOTE -

2-HS-2085 located on West wall of 27 ft Switchgear Room; Key #80 in Control Room Key Locker.

l l 2. Open Cntmt Instrument Air Supply CV, 2-IA-2085-CV, by momentarily placing 2-HS-2085 in OPEN.

EOP-3 R;v. 1/ Unit 2 Page 28 of 40 RECOVERY ACTIQN_S ALTERNATE ACTIONS

{ JI.

T. RESTORE LETDOWN FLOW:

1. Verify charging flovpath through Loop Charging Valves or Auxiliary Spray Valve.
2. Verify at least one Charging Pump operating.
3. Shift Letdown Control Valve Controller, 2-HIC-110, to MANUAL.
4. Adjust controller to shut Letdown Control Valves. ,
5. Open Letdown Isolation Valves:

2-CVC-515-CV 2-CVC-516-CV l I -CAUTION-The setpoint of 2-PIC-201 must be above the saturation pressure for the letdown outlet temperature of the Regenerative Heat Exchanger.

6. Adjust the setpoint on 2-PIC-201 and adjust 2-HIC-110 to maintain desired RCS pressure.

U. DRAW PRESSURIZER BUBBLE IF DESIRED:

1. Adjust steaming rate or Shutdown Cooling to stabilize "cold.
2. Heat up Pressurizer by energizing Backup and Proportional Heaters.

{ ) 3. Adjust letdown flow and Tcold to maintain RCS sugcooling between 30 and 140 F.

EOP-3 R;v. 1/ Unit 2 Pcg3 29 of 40

'II . RECOVERY ACTIONS ALTERNATE ACTIONS I I

4. WHEN pressurizer temperature exgeedr CET tempbratures by 50 F, THEN maximize letdown:
a. Lower the setpoint on Letdown Backpressure Regulator Controller to obtain letdown flow of 100 GPM.
b. Secure Charging Pump (s) er needed to increase effective letdown.
5. WIIEN saturation pressure for the existing pressurizer ,

temperature is reached, TIIEN confirm bubble formation by observing steady pressurizer pressure.

6. Using CET temperatures, q g maintain agbcooling between 30 and 140 F per Attachment (1) by operating:
a. Backup and Proportional Heater (s),
b. Auxiliary Spray.
7. Maintain pressurizer level between 101 and 180 inches by operating
a. Charging flow,
b. Letdown flow.

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I EOP-3 Rcv. 1/ Unit 2 Pcgo 30 of 40

'II. RECOVERY ACTIONS ALTERNATE ACTIONS l l V. IF FEEDWATER AVAILABLE AND SHUTDOWN COOLING NOT OPERATING, TTEN EVALUATE NEED FOR FORCED OR NATURAL CIRCULATION:

1. WBEN RCPs available AND 1.1 IF RCPs NOT available OR Natural Circulation desired, Forced Circulation desired THEM implement Natural THEN start RCPs per steps 2-12. Circulation (AOP-3E) bHD complete administrative post-trip actions.
2. 1F RCPs exposed to excessive moisture, THEN consider msggering RCP ,

motor.

- CAUTION -

Uncontrolled restoration of cooling to hot RCP seals may cause degradation of the metallic I I seating surfaces by thermal shock.

3. IF Component Cooling is isolated to RCP seals, seal THEN reducebelow temperature RCP 280 lower,F prior to initiating full cooling flow to the RCPs:
a. Shut Component Cooling Supply Containment Manual Isolation Valve, 2-CC-234, located in 5 ft East Penetratie- Room,
b. Verify CIS reset,
c. Open Component Cooling Containment Isolation Valves:

2-CC-3832-CV 2-CC-3833-CV l

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EOP-3 R0v. 1/ Unit 2 Page 31 of 40 ALTERNATE ACTIONS q fl. RECOVERY ACTIONS I

d. Slowly open 2-CC-284 to throttle component cooling flow until lower seal temgeratures are less than 280 F.
e. )DIEN lower seal temperatgres are less than 280 F, THEN fully open 2-CC-284.
4. IF an RCP lower seal temperature exceeded 280 F, THEN an engineering evaluation is required prior to restarting that RCP.
5. Raise pressurizer level to rt least 155 itiches.
6. Verify RCP restart criteria
a. RCS subgooling greater

{ } than 30 F.

b. At least one S/G available for heat removal,
c. Pressurizer level greater than 155 inches and stable.
d. Tcold less than 525 F.
e. RCS temperature and j pressure greater than the minimum operating limits per the RCP curve on Attachment (1). 1 I

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EOP-3 R;v. 1/ Unit 2 Page 32 of 43 I. RECOVERY ACTIONS OLTERNATE ACTIONS s

- NOTE -

Starting an RCP may cause a pressurizer level transient.

7. vnH24 RCP restart criteria are met, THEN start one RCP in a loop with an operable S/G:
a. Verify "COMPT CLG FLOW LO" alarm clear.
b. Start Oil Lift Pump,
c. Insert RCP tjav stick,
d. Start one RCP.
e. Monitor RCP running current:

Tave Current l I 525 to 572 F "J8 to 210 AMPS and steady 210 to 525 a 264 to 238 AMPS and steady

8. IF pressurizer level decreases, TIIEN start Charging or HPSI Pump (s) as necessary to restoro SND maintain level greater than 155 inches.
9. Monitor RCP seal parameters following pump restart.
10. Allow backflow to equalize temneratures in opposite loop.
11. Start second RCP in opposite loop per Step V.7 and V.9, page 32.

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EOP-3 R;v. 1/ Unit 2 Page 33 of 40 I. RECOVERY ACTIONS ALTERNA_TE ACTIONS

12. Secure Auxiliary Sprays
a. Open Loop Charging Valves:

2-CVC-518-CV 2-CVC-519-CV

b. Shut Auxiliary Spray Valve, 2-CVC-517-CV.
c. Shift Pressurizer Spray Controller, 2-HIC-100, to AUTO.

W. COMPLETE ADMINISTRATIVE POST-TRIT .

ACTIONS AND IMPLEMENT APPROPRIATE OPERATING PROCEDURE.

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EOP-3 RCv. 1/ Unit 2 Paga 34 cf 40 X. ADMINISTRATIVE POST-TRIP ACTIONS:

- NOTE -

The following actions may be accomplished whenever feasible.

They may be done in any order.

1. Refer to ERPIP to determine appropriate emergency response ac' ions.
2. Perform notifications per CCI-118,
3. Notify ESO of trip.
4. Request RCS Boron and Iodine sample.
5. Perform shutdown margin calculation per NEOG 9 and 11
6. Complete transient log entries per CCI-301,
7. Recall post-trip review (preferably within 30 minutes of trip).
8. Perform post-trip review per CCI-111,
9. Monitor turbine bearing temperaturer;.
10. Centinue Main Turbine shutdown per applicable step of OI-43A.

END OF SECTION III, l I

t EOP-3 R;v. 1/ Unit 2 Page 35 of 40 l l IV. SAFETY FUNCTION STATUS CIIECK A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to exiting from this procedure.

B. Perform intermediate safety function status check at 10 minute intervals until plant conditions stabilize.

C. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied.

D. Review data and verify that safety function acceptance criteria are satisfied.

E. When E0P completed, then perform final safety function check, o

REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS C.tECK CHECK i I

c. WRNI power less than 3% ,,,,,__,,,

less than 2%

b. SUR (DFM) negative , , , _ _ _ , , , , _

O

c. CEA status all inserted _,,,,,,,__

all inserted or Boration status:

appropriate concentration increasing ___,,____,

S/D margin BAST level decreasing ___,,___,, N/A N/A__

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EOP-3 R;v. 1/ Unit 2 Pcg3 36 of 40 l l RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND INVENTORY __

FINAL PARAMETERS CRITERIA INTERMEDI2TE CRITEF4A CHECK CHECK

c. Pressurizer 1000 to 2350 ~~~"~""

less than 2300 pressure (PSIA)

b. Pressurizer 50 to 350 ~"~~~""

101 to 180 level (inches) 30 to 140 30 to 140

c. RgS subcooling ,,,,,,,,,,

( F)

If PORVs i.ere opened, once an hour monitor the following:

d. Quench Tank parameters constant g level (inchesj constant or or temperature ( F) pressure (PSIO) decreasing ,,,,,,,,,,

decreasing

o. PORV discharge piping temperature (OF)

(computer points T107, T108) decreasing ,,,,,,,,,,

decreasing

EOP-3 R;v. 1/ Unit 2 Pcg 37 cf 40 l I CORE AND RCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL CRITERIA FINAL PARAMETERS CRITERIA INTERMEDIATE CHECK CHECK

c. RCS Tcold ( F) less than 540 _,..,_,

less than 535 less than 560 less than 540

b. CET ( F) __,,,,,,,

c.TgotminusTcold

( F)

Natural 10 to 50 Circulation 10 to 50 ,_,_____

Forced less than 5 Circulation less than 10 ,_______

d. S/G pressure less than 960 ________

less than 920

(-)400 to (-)24 to

{ )o. S/G level (inches) (+)30 ________

(+)30 _

greater

f. Condensate than 5 and Storage Tank greater than 5 increasing level (ft) ...,____

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EOP-3 R;v. 1/ Unit 2 P ga 38 of 40 SAFETi FUNCTION ACCEPTANCE CRITERIA CRITERIA INTERMEDIATE CRITERIA FINAL VITAL CHECK AUXILIARIES CHECK

o. 4KV vital buses energized 21 or 24 energized ,,________

greater greater

b. Instrument Air pressure (PSIG) than 88 ,,,,,,__,,

than 88 l c. Component Cooling 1 or 2

! (# Pumps running) 1 or 2 ,,,__,,,,_

d. Saltwater

(# pumps running) 1 or 2 ,,,,,,__,,

1 or 2 i o. Service Water

(# pumps running) 1 or 2 ____,,,,,,

1 or 2

{ )f 12SV DC buses 11, 12, 21, 22 energized ,,,,,,,,,_

energized l

g. 120V AC vital j buses 21, 22, 23, 24 energized ,,,,,,,,,,

energized l

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EOP-3 R;v. 1/ Unit 2 Pcq 39 of 40 l l NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT FINAL ENVIRONMENT CRITERIA INTERMEDIATE CRITERIA CHECK CHECK PARAMETERS O. Containment pressure less than 50 less than 2.8 (PSIG) ........

b. Containment less than 276 ,,,,___.

less than 220

c. Containment '

High Range Radiation alarm alarm Monitor clear ,,____,,

clear

d. Hydrogen concentration N/A --- ll/A--- less than 2.e.

EOP-3 R;v. 1/ Unit 2 Pcg3 40 cf 40 NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL FINAL TO CONTAINMENT CRITERIA INTERMEDIATE CRITERIA CHECK CHECK alarm

c. Hoble Gas alarm clear Monitor clear ,,,,,,____

alarm

b. Condenser alarm . '

clear Off-Gas RMS clear ___,,,,,,_

alarm alarm

c. S/G B/D RMS clear clear ,___, ....

alarm

d. Main Vent Gaseous alarm clear RMS (2-RI-5415) clear _____,,___

STATUS CHECK COMPLETE AT NUMBER TIME 4

1 2

3 4

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E^P-4 R v. 1/ Unit 1 Pcg3 1 Cf 31 i I CALVERT CLIFFS NUCLEAR POWER PIANT EOP-4 EX_ CESS S* GAM DfMAND REVIS!011 1 SIGNATURE DATE i

PREPARED DY: @tr/ j 14- / /2 //8 d 7

+ m "A VERIFIED B _

\f '[ Y%\ / '!

3J / D \ C * %"6 POSRC; MEEJJMG # }'3 7 APPROVED BY; h~ In0mtF / 'Z'\S'A

__6ager41;uclear Ma Operations or General Supervisor-Operations if POSRC review is not required i I

EOP-4 R v. 1/ Unit 1 Pcg] 2 of 31 l I -

MsT_or_Ettserivs_ moss EAct W.M..n_E.n_. FEvrs103 1 1 2 1 3 1 4 1 ,

5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 1 13 1 14 1 15 1 16 1 17 1

le 1

19

( ) 20 1

1 23 1

22 1

23 1

24 1

25 1

26 1

27 1

28 1

29 J

30 1

31 1

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E!P-4 R;v. 1/ Unit 1 Pcg3 3 of 31 I I .

KXCESS STFJ.M DEMAND

1. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition cince an incident could induce inconsistencies between instruments.

D. High energy line break may cause erratic instrumentation response depending on the magnitude and location of the break.

E. Minimize "he number of cycles of pressurizer auxiliarg spray when the temperature differential is greater than 400 F.

F. In Natural Circulation, increased loop transport time causes a 5 q g to 10 minut0 delay in temperature responses to a plant change.

Pressurizer level and pressure responses, if available, typically provide better indication of PCS response during this period.

G. S/G pressure, pressurizer pressure, and contain2nent temperature affect the level indication for the S/Gs and Pressurizer.

Attachments (8) and (9) contain the corrected S/G and pressurizer levels for various S/G pressures, pressurizer pressures, and containment temperaturer.

H. If a pump or component fails, the cause of the failure should be determined prior to restarting or starting a standby pump or component to prevent a common failure.

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EOP-4 RCv. 1/ Unit 1 PCgo 4 of 31 l I II . AfrRY CONDITIONS The presence of one or more of the following conditions indicates that an Excess Steam Demand may have occurred:

A. Decrease in S/G pressure in one or both S/Gs.

B. Reactor Trip on low S/G pressure.

C. Reactor Trip on high containment pressure.

D. Possible actuation of:

1. SIAS
2. CIS
3. CSAS
4. SGIS ,.

E. Decrease in Teold.

F. Loud noise and poor visibility in plant (location dependent).

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EOP-4 R';v . 1/ Unit 1 Pago 5 of 31 II. EEpOlERJ_hC11ONS MTE ACTIONS I I A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED.

B. COMMENCE INTERMEDIATE SAFETY FUNCTIOli STATUS CHECK.

C. DETERMINE APPROFAIATE EMERGENCY RESPCNSE ACTIONS PER THE ERPIP.

D. ISOLATE BOTH S/Gs:

1. Shut both MSIVs.

I I 2. Shut S/G Feedwater Isolation Valves:

1-FW-4516-MOV 1-FW-4517-MOV

3. Shut MSIV Bypass Valves:

1-MS-4045-MOV 1-MS-4052-MOV

4. Shuc S/G Blowdown Valves:

1-BD-4010-CV 1-BD-4011-CV 1-BD-4012-CV 1-BD-4013-CV I

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E P-4 R v. 1/ Unit 1 PCga 6 cf 31

'II. RECOVERY ACTIONS Af! TERN &TE AC"f!ON!}

l l S. Shut AFW Steam Supply Valves by piccing handswitches in CLOSE:

1-MS-4070-CV 1-MS-4071-CV

6. Shut AFW Block Valves by placing handswitches in CLOSE :

1 11 S/G 12 S/0 1-AFW-4520-CV 1-AFW-4530-CV 1-AFW-4521-CV 1-AFW-4531-CV l

1-AFW-4522-CV 1-AFW-4532-CV 1-AFW-4523-CV 1-AFW-4533-CV

7. Shut Atmospheric Dump Valves.
8. Shut upstream drains by placing handswitch 1-HS-6622 in CLOSE.

l l E. MONITOR RCS DEPRESSURIZATION.

1. II rapid depressurization 1.1. If RCS pressure is greater to 1725 PSIA, than 1725 PSIA AND SIAS HOT THEN verify SIAS actuation actuated,

( AND the following actions: IDEN block SIAS:

a. All available Charging a. Open Main and Aux HPSI Pumps running. Header valves:
b. 11 and 13 HPSI Pumps 1-SI-616-MOV 1-SI-617-MOV running. 1-SI-626-MOV 1-SI-627-MOV 1-SI-636-MOV 1-SI-637-MOV

! c. Main and Aux HPSI Header 1-SI-646-MOV 1-SI-647-MOV l Valves open:

I b. Start 11 and 13 HPSI 1-SI-616-MOV 1-SI-617-MOV Pumps. l 1-SI-626-MOV 1-SI-627-MOV 1 1-SI-636-MOV 1-SI-637-MOV c. WHEN "PRSR PRESS BLOCK

! 1-SI-646-MOV 1-SI-647-MOV A(B) PERMITTED" I alarms (s) received, l IMEH block SIAS A(B).

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EOP-4 R v. 1/ Unit 1 Pcg3 7 of 31

'II. RECOVE.RY ACTION _S ALTERNATE _4CTIQHS i I F. IMPLEMENT RCP TRIP STRATEGY:

1. II RCS pressure decreases to 1725 PSIA, IIIEN trip 11A and 12B RCPs OR trip 11B and 12A RCPs.
2. If positive LOCA in h ations exists
a. RT'g subcooling iese than 30 F.
b. Steady S/G pressure,
c. S/G Blowdown RMS alarms clear OR Main Vent Gaseous RMS (1-RI-5415) alarm clear.

AND RCS pressure decreases to less than 1300 PSIA, I TITEN trip all RCPs.

3. IE RCS tempet..ture and pressure are less than the minimum pump operating limite per the RCP curve on Attachment (1),

T1IEN trip k4, 7 cps.

4. JF CIS has actuated, THEN trip all RCPs.

G. MONITOR CONTAINMENT PRESSURE:

1. JF CSAS HQT actuated, THEN start all available containment Air Coolers in HIGli with maximum SRW flow.

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COP-4 Ray. 1/ Unit 1 Pega 8 of 31 I. RECOVERY ACTIONS A_L_ U R N A T E_ .A C T I O N S

2. IF containment pressure

' increases to 2.8 PSIG, THEN verify ESFAS actuation:

a. SIAS.
b. CIS AND trip all RCPs.

en ! 3. Verify SRW Pump Room

$2 Ventilation in service,

$7 per 01-15.

$$ I

4. IF containment pressure increases to 4.25 PSIG, TTEM verify CSAS actuation AND spray flow approximately 1350 GPM. .

H. VERIFY BORATION IN PROGRESS:

1.1 IF SIAS NOT actuated,

1. IF SIAc w - actuated, 1 Fh THEN verify boration in THEN commence boration:

progress:

a. Shut VCT Makeup Valve,
a. Shut VCT Makeup Valve, 1-CVC-512-CV.

1-CVC-512-CV.

b. Open Boric Acid Direct
b. Open Boric Acid Direct Makaup Valve, Makeup Valve, 1-CVC-514-MOV.

1-CVC-514-MOV.

c. Start a Boric Acid Pump.
c. Boric Acid Pumps running.
d. Start all availablo
d. Open BAST Gravity Feed Charging Pumps.

Valves:

1-CVC-508-MOV 1-CVC-509-MOV I k

EOP-4 R;v. 1/ Unit 1 Page 9 of 31 III. RECOVERY ACTIONS ALTERNATE ACTIONS

e. Shut VCT Outlet 1.2 IF Boric Acid Pumps NOT Valve, 1-CVC-501-MOV. available, THEN establish gravity feed:
f. All available Charging Pumps running. a. Open BAST Gravity Feed Valves:

1-CVC-508-MOV 1-CVC-509-MOV

b. Shut VCT Outlet Valve, 1-CVC-501-MOV.
c. Start all available Charging Pumps.
2. Continue boration until ,

a total 65 inch decrease in BAST level (s) is achieved, or shutdown margin requirement of NEOG-7 is achieved.

I. IDENTIFY AFFECTED S/G.

1. Compare the following parameters:
a. S/G pressures.
b. Teold on both loops.
c. S/G levels.

I I I l

EOP-4 R;v. 1/ Unit 1 Pcgo 10 of 31 III. RECOVERY ACTIONS ALTERNATE ACTIONS J. MAINTAIN HEAT SINK OPERABILITY OF UNAFFECTED S/G DURING BLOWDOWN PHASE:

1. For the affected S/G, shut 1.1 IF Atmospheric Dump Valve the Atmospheric Dump Valve will NOT shut from 1C43, using the Hand Transfer THEN shut Atmospheric Dump Valvss on the West wall Manual Isolation Valve, of the Unit 1 45 ft Switchgear Room: 11 S/G or 12 S/G
a. Verify 1C43 Atmospheric 1-MS-101 1-MS-104 Dump Controllers at 0%

output.

b. Align Hand Transfer Valves to 1C43 position:

11 S/G or 12 S/G 1-HV-3938A 1-HV-3939A 1-HV-3938B 1-HV-3939B l l

- NOTE - - NOTE -

Unaffected S/G temperature may be For steam breaks in Containment, obtained by using the saturation resulting in small cooldown rates, temperature for the existing S/G the energy released to Containment pressure. may be reduced by use of S/G Blowdown on affected S/G.

2. IF RCS cooldown rate 2.1 IF RCS cgoldown . Tate less j gregter than or equal to than 100 F/h,  !

100 F/h AND CET THEN establish Natural l temperatures less than Circulation using i unaffected S/G temperature, unaffected S/G: l 11HQ! cool ungffected S/G to within 25 F of CET a. Open motor driven train temperatures: AFW Block Valves on unaffected S/G:  !

a. Open motor driven train l AFW Block Valves on 11 S/G or 12 S/G I unaffected S/G:

1-AEW-4522-CV 1-AFW-4532-CV 11 S/G or 12 S/G 1-AFW-4523-CV 1-AFW-4533-CV 1-AEW-4522-CV 1-AFW-4532-CV

{ g 1-AEW-4523-CV l-AFW-4533-CV

=

l EOP-4 l Rsv. 1/ Unit 1 Pago 11 of 31

'II. RECOVERY ACTIONS ALTERNATE ACTIONS I l

- CAUTION - - CAhTION -

D/G supplying power to 13 ADf D/G supplying power to 13 ADf Pump Pump flow limit is 300 G.?M; flow limit is 300 GPM; otherwise otherwise, flow limit is 575 GPM. flow limit is 575 GPM.

b Start 13 AFW Pump. b. Start 13 AFW Pump.

c. Adjust AFW Flow Control c. Manually throttle open Valves to feed unaffected AFW Flow Control Valve.

S/G. or 12 S/G 11 S/G 11 S/G or 12 S/G 1-AFW-4525-CV 1-AFW-4535-CV 1-AFW-4525-CV 1-AFW-4535-CV

d. Open Atmospheric Dump

- CAUTION - ,

Valve as necessary to cool unaffected S/G, while CET temperatures must always be maintaining RCS cogidown less than unaffected S/G rate less than 100 F/h.

temperature while affected S/G blowdown is in progress. e. Stabilize unaffected S/G level between (-)170 and g

d. Open Atmospheric Dump (+)30 inches.

4 Valve as necessary to cool unaffected S/G to within 25 F of CET temperatures.

e. Stabilize unaffected S/G 1evel between (-)170 and

(+)30 inches.

K. RESTORE PRESSURIZER LEVEL TO BETWEEN 50 AND 110 INCHES DURING S/G BLONDONN:

1. Verify letdown isolated.
2. If RCS pressure less than 1270 PSIA,

_THEN verify HPSI flow to RCS per Attachment (12).

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l EOP-4 R;v. 1/ Unit 1 l Page 12 of 31 II. RECOVERY ACTIONS ALTERNATE ACTIONS

3. IF additional HPSI flow required to control pressurizer level, THEN lower RCS pressure using Auxiliary Spray per step M, page 13.
4. WHEN pressurizer level greater than 50 inches, THEN secure all but one Charging Pump.
5. IF the following conditions exist:
a. At least 30 F subcooling.

~

b. Pressurizer level greater than 50 inches.
c. At least one S/G available for heat removal,
d. RVLMS indicates that the l I Core is covered.

THEN throttle HPSI flow to maintain pressurizer level between 50 and 110 inches.

L. W HEN STEADY Tcold INDIC*TES S/G BLOWDOWN COMPLETE OR COOLDOWN RATE LESS THAN 100 F/h,

_THEN ESTABLISH UNAFFECTED S/G AS A HEAT SINK:

1. Restore S/G wide range level to between (-)24 and (+)30 inches using 13 AFW Pump.
2. Open Atmospheric Dump Valve as necessary to cool unaffected S/G, while maintaining RCS cogidown rate less than 100 F/h.

) 3. Stabilize pressurizer level between 101 and 155 inches.

l EOP-4 l R3v. 1/ Unit 1 l Pcga 13 of 31 d 1II. RECOVERY ACTIONS .% TERNATE ACTIONS k l M. MAINTAIN RgS SUBCOOLING BETWEEN 30 AND 140 F:

- CAUTION -

The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

1. Operate Pressurizer Heaters as necessary to maintain RgS subcooling greater than 30 F.
2. IF necessary to lower 2.1 ,IF pressurizer level RCS subcooling AND greater than 350 inches pressurizer level less than AND RCS gubcooling is greater 350 inches, than 140 F, THEN verify heaters secured THEN open PORV:

AND initiate Auxiliary Spray:

a. Verify primary makeup
a. Place Instrument Air CIS path operable.

l ) Override Switch, 1-HS-2080A, in OVERRIDE. b. Place both PORV Override Control Switches in

b. Open Cntmt Instrument Air OVERRIDE SHUT.

Isolation MOV, 1-IA-2080-MOV. -

NOTE -

c. Record temperature The "PORV ENERGIZED" alarm will differential between annunciato when two RPS trip Pressurizer and units are pulled. The FORVs Regonerative Heat will not open.

Exchanger Outlet.

c. Pull two High Pressurizer
d. Open Auxiliary Spray Pressure Trip Units out on Valve, 1-CVC-517-CV. RPS.
d. Place one PORV Override Control Switch in AUTO.
e. If second PORV needed to lower subcooling, THEN place the other PORV Override Control Switch in AUTO.

l k f. WHEg subcooling less than 140 F, TUEU perform the following:

EOP-4 R0v. 1/ Unit 1 Page 14 of 31 I. RECOVERY ACTIONS ALTERNATE ACTIONS

e. Shut Loop Charging Valves: (1) Place the PORV Override Centrol Switches in 1-CVC-518-CV OVERRIDE SHUT.

1-CVC-519-CV (2) Insert High Pressurizer

- NOTE - Pressure Trip Units that were previously 1-HS-2085 located on West wall pulled, of 27 ft Switchgear Room; Key #85 in Control Room Key Locker. (3) Ensure "PORV ENERGIZED" alarm clear.

f. Open Cntmt Instrument Air (4) IE Acoustic Monitor indicates flow through Supply CV, 1-IA-2085-CV, the PORV, by momentarily placing 1-HS-2085 in OPEN. THEN shut the PORV

. Block Valve.

g. Shift 1-HIC-100 to MANUAL and shut Pressurizer Spray Valves:

1-RC-100E-CV 1-RC-100F-CV l I

h. Maintain pressurizer coegdown rate less than 200 F/h.

N. If RCPs SECURED, TIIEN CONFIRM NATURAL CIRCULATION IN UNAFFECTED S/G LOOP:

- HOTE -

Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10).

1. ThotmgnusTeoldbetween10 and 50 F.
2. Tcold constant or decreasing.
3. Thot constant or decreasing.
4. CET temperatures consistent l I with Thot.
5. Steaming rate affects primary ,

temperature.

EOP-4 Rcv. 1/ Unit 1 Pcga 15 of 31

'II . RECOVERY ACTIONS ALTERNATE ACTIONS l l O. MONITOR FOR CORE AND RCS VOIDING:

- CAUTION -

Potential for void formation increases rapidly when pressure decreases below 1500 PSIA.

1. Letdown flow greater than charging flow.
2. Rapid unexplained increase in pressurizer level during an RCS pressure reduction.

~

3. Loss of subcooled margin as determined using CET temperatures.
4. "REACTOR VESSEL WATER LEVEL LOW" alarm.

I P. IF VOIDING INHIBITS HEAT REMOVAL, T_IIEN REDUCE OR ELIMINATE VOIDED AREA:

1. Shut Letdown Isolation Valve, 1-CVC-515-CV.

- CAUTION -

The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

2. Pressurize the RCS to 2.1 IF pressurizing the RCS maigtain subcooling as near does NOT restore heat removal, 140 F as practical, by any IMEN operate Reactor Vessel of the following: Vent Valves por 01-10.

- HOTE -

Pressurizer Backup Heater Banks l l 11 and 13 trip on U,1 and SIAS.

EOP-4 RCv. 1/ Unit 1 Pcgo 16 of 31 III. RECOVERY ACTIONS ALTERNATE ACTIONS

a. Operate Pressurizer Heater (s).
b. Operate Turbine Bypass or Atmospheric Dump Valves to maximize RCS cooldown, while maintaining coofdown rate less than 100 F/h.
c. Raise HPSI flow to RCS.

- CAUTION -

If voids exist in the S/G tubes, a rapid RCS pressure reduction will occur when the voids ,

collapse.

3. IF voiding occurs in the S/G tubes (saturation pressure of S/G greater than saturation pressure of RCS),

THEN cool the S/G by raising l I any of the following:

a. Steaming rate.
b. Feed rate.
c. S/G Blowdown rate.

AND, maintaining less than 100 F/h cooldown rate.

Q. SECURE THE FOLLOWING SECONDARY PUMPS:

1. Trip S/G Feed Pumps.
2. Place Condensate Booster Pumps in PULL-TO-LOCK.
3. Place 2 of the 3 Condensate Pumps in PULL-TO-LOCK.
4. Secure Heater Drain Pumps.

l )

EOP-4 R;v. 1/ Unit 1 Pcga 17 of 31 i

'II. RECOVERY ACTIONS ALTERNATE ACTIONS i > _  ;

l R. WHEN RCS BORATION COMPLETE, THEN SHIFT CHARGING PUMP SUCTION SUPPLY TO MAKEUP SUPPLY WITH A LOWER BORIC ACID CONCENTRATION.

1. If SIAS actuated, 1.1 If SIAS NOT actuated, THEN perform the following: THEN line up charging Pump suction to VCT:
a. Open RWT To Charging Pump Suction Valve, a. Determine blend 1-CVC-504-MOV. requirements to maintain shutdown boron
b. Shut VCT Outlet concentration per NEOG-7.

Valve, 1-CVC-501-MOV.

.b. Open VCT Outlet Valve,

c. Place Boric Acid Pumps 1-CVC-501-MOV, in PULL-TO-LOCK.
c. Secure Boric Acid Pump (s).
d. Ensure Charging Pump AMPS steady. d. Shut Boric Acid Direct Makeup Valve, 1-CVC-514-MOV.

4 g

e. Shut BAST Gravity Feed Valves:

1-CVC-508-MOV 1-CVC-509-MOV OB line up Charging Pump suction to RWT:

a. Open RWT To Charging Pump Suction Valve, 1-CVC-504-MOV,
b. Shut VCT Outlet Valve, 1-CVC-501-MOV.
c. Shut Boric Acid Direct Makeup Valve, 1-CVC-514-MOV.
d. Secure Doric Acid Pumps (s).

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EOP-4 RCv. 1/ Unit 1 Fage 18 of 31 III. RECOVERY ACTIONS ALTERNATE ACTIONS l k S, COMMENCE ESFAS VERIFICATION CHECKLISTS:

1. SIAS Attachment (2).
2. CSAS Attachment (3).
3. CIS Attachment (4).
4. SGIS Attachment (7).

T. RESTORE CONTAINMENT ENVIRONMENT:

1. Direct Chemistry to place Hydrogen Monitors in service.
2. IF hydrogen concentration increaseo to 1%,

THEN start Hydrogen I Recombiners per OI-43A.

3. vnDOI containment pressure less than 4.0 PSIG, THEN perform the following
a. Roset CSAS signal.
b. Secure one Containment Spray Pump.
c. Verify all Containment Air Coolers operating to maintain containment temgerature less than 120 F.
d. Restore equipment per CSAS 1 Verification Checklist, 1 Attachment (3), to desired condition, j l

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EOP-4 R;v. 1/ Unit 1 Page 19 of 31 III. RECOVERY ACTIONS ALTERNATE ACTIONS ,

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4. WHEN containment pressure less than 2.8 PSIG, THEN perform the following:
a. Block pressurizer pressure signals and reset SIAS signal,
b. Roset CIS signal.
c. Secure remaining Containment Spray Pump,
d. Restore equipment por SIAS and CIS Verification Checklists, Attachments (2) and (4), to desired ,

condition.

U. RESTORE SERVICE WATER TO TURBINE BUILDING:

~

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1. Verify 21 Plant Air Compressor operating.
2. Shut Plant Air To Plant Air Header Va',ve, 1-PA-2059-CV.
3. Open Plant Air To Instrument Air Cross Connect Valve, 1-PA-2061-CV.
4. Op.en SRW Turbine Building lieader Isolation Valves:

1-SRW-1600-CV 1-SRW-1637-CV 1-SRW-1638-CV 1-SRW-1639-CV l I

EOP-4 R;v. 1/ Unit 1 Page 20 of 31

'II . RECOVERY ACTIONS ~ ALTERNATE ACTIONS l l V. RESTORE INSTRUMENT AIR COMPRESSCRS TO SERVICE:

1. IF high temperature alarm exists on the Instrument Air Compressors, THEN open the service water isolation valves by placing their handswitches in OPEN until temperature alarm clearo.

11 or 12 1-HS-2063 1-HS-2065 .

2. Start at least one Instrument Air Compressor.

PF. STORE INSTRUMENT AIR TO I CONTAINMENT:

1. Open Cntmt Instrument Air Isolation MOV, 1-IA-2080-MOV.

1 1

- NOTE -

1-HS-2085 located on West wall of 27 ft Switchgear Room; Key #85 j in Control Room Key Locker.

2. Open Cntmt Instrument Air Supply CV, 1-IA-2005-CV, by momentarily placing 1-HS-2085 in OPEN.

l X. RESTORE I.ETDOWN FLOW:

1. Verify charging flowpath through Loop Charging

{ } Valves or Auxiliary Spray Valve.

EOP-4 R v. 1/ Unit 1 Pcga 21 of 31

'II . RECOVERY ACTIONS ALTERNATE ACTIONS l I s

2. Verify at least one Charging Pump operating.
3. Shift Letdown Control Valve Controller, 1-HIC-110, to MANUAL.
4. Adjust controller to shut Letdown Control Valves.
5. Open Letdown Isolation Valves:

1-CVC-515-CV 1-CVC-516-CV

-CAUTION-The setpoint of 1-PIC-201 must be above the saturation pressure for the letdown outlet temperature of the Regenerative Boat Exchanger.

6. Adjust the setpoint on 1-PIC-201 and adjust I I 1-HIC-110 to maintain desired pressurizer level.

Y. IF RCPs AVAILABLE, p_IEU EVALUATE NEED FOR FORCED OR NATURAL CIRCULATION:

1. WHEN RCPs available AND 1.1 IF RCPs NOT available OR Forced Circulation desired, Natural Circulation desired,

_T!IEH start RCPs per steps 2-12. THEN implement Natural Circulation (AOP-3E) AND complete administrative post-trip actions.

2. IF RCPs exposed to excessive moisture, THEN consider meggering RCP l motor.

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EOP-4 Rov. 1/ Unit 1 Pcg3 22 of 31 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I

- CAUTION -

Uncontrolled restoration of cooling to hot RCP seals may cause degradation of the metallic seating surfaces by thermal shock.

3. IF Component Cooling is isolated to RCP seals, THEN reduce RCP lower seal '

temperature below 280'F prior to initiating full cooling flow to the RCPs:

a. Shut Component Cooling Supply Containment Manual s Isolation Valve, 1-CC-284, located in 5 ft East Penetration Room. ,
b. Verify CIS reset,
c. Open Component Cooling l I Containment Isolation Valves:

1-CC-3832-CV 1-CC-3833-CV

d. Slowly open 1-CC-284 to throttle component ecoling flow until lower seal temgeratures are less than 280 F.
e. WHEN lower seal temgeratures are less tnan 280 F, TTIEN fully open 1-CC-204.
4. IF an RCP lower seal t2mperature exceeded 280 F, THEN an engineering i evaluation is required prior to restarting that RCP.
f. Raise pressurizer level to l at least 155 inches.

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EOP-4 rov. 1/ Unit 1 Page 23 of 31 III. RECOVERY ACTIONS ALTERNATE ACTIONS

6. Verify RCP restart criteria:
a. RCS subgooling greater than 30 F.
b. At least one S/G available for heat removal.
c. Pressurizer level greater than 155 inches and stable,
d. Tcold less tlaan 525 F.
e. RCS temperature and pressure greater than the minimum operating limits per the RCP curve on Attachment (1).

- NOTF -

Starting an RCP may cause a pressurjzer level transient.

I I 7. WHEN RCP restart criteria met, TIIEN start one RCP in a loop with an operable S/G:

a. Verify "COMPT CLG ' LOW J LO" alarm clear.
b. Start Oil Lift Pump.
c. Insert RCP sync ntick,
d. Start one RCP.
e. Monitor RCP running current:

Isvg Current 525 to 572 F 238 to 210 AMPS and steady 210 's> 525 F 264 to 238 AMPS and steady l l

EOP-4 R v. 1/ Unit 1 Page 24 of 31 q fl. RECOVERY ACTIONS ALTERNATE ACTIONS

8. IF pressurizer level decreases, THEN start Charging or HPSI Pump (s) as necessary to restore AND maintain level greater than 155 inches.
9. Monitor RCP seal parameters following pump restart.
10. Allow backflow to equalize temperatures in opposite loop.
11. StaJt second RCP in opposite loop per step Y.7 and Y.9, pages 23 and 24,
12. Secure Auxiliary Spray: ,
a. Open Loop Charging Valves:

1-CVC-518-CV 1-CVC-519-CV

b. Shut Auxiliary Spray Valve, 1-CVC-517-CV.
c. Shift Pressurizer Spray Controller, 1-HIC-100, to AUTO.

Z. COMPLETE ADMINISTRATIVE POST-TRIP ACTIONS AND IMPLEMENT APPROPRIATE OPERATING PROCEDURE.

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EOP-4 R v. 1/ Unit 1 Pcga 25 of 31 I l AA. ADMINISTRATIVE POST-TRIP ACTIONS:

- NOTE -

The following actions may be accomplished whenever feasible.

They may be done in any order.

1. Refer to ERPIP to determine appropriate emergency response actions.
2. Perform notifications per CCI-ll8.
3. Notify ESO of trip.
4. Request RCS Boron and Iohine sample.
5. Perform shutdown margin calculation per NEOG 2 and 7.
6. Complete transient log entries per CCI-301.

j l 7. Recall post-trip review (preferably within 30 minutes of trip).

8. Perform post-trip review per CCI-lil.
9. Monitor turbine bearing temperatures.
10. Continue Main Turbine shutdown per applicable step of OI-43A.

END OF SECTION III.

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EOP-4 R:v. 1/ Unit 1 Page 26 of 31 l l IV. SAFETY FUNCTION _ STATUS CHECK A. The STA (or percon designated by STA) will perform the intermediate and final safety functions checks respectively on entry and prior to exiting from this procedure.

B. Perform intermediate safety function status check at 10 minute intervals until plant condicions stabilize.

C. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied.

D. Review data and verify that safety function acceptance criteria are satisfied.

E. When EOP completed, then perform final safety function check.

REACTIVITY SAFETY EUNCTION ACCEPTANCE CRITERIA CONTROL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK I I

a. WRNI power less than 8% ,,,,,,,,,, less than 2%
b. SUR (DPM) negative ,,,,,,,,,,

O

c. CEA status all inserted all inserted or Boration status:

appropriate concentation increasing ,,,,,,,,,,

S/D margin BAST level decreasing ,,,,,,,,,, N/A N/A l l

EOP-4 rov. 1/ Unit 1 Page 27 of 31 f .

(.

kJS PRESEURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND IF TITOAY ,__

CRITERIA FINAL I' ARME's "R S ,h_kITERIA INTERMEDIATE CHECK CHECK

r. Pressurizer 300 to 1900 .

pressu. (PSAA) 300 to 1900 ,,,,,,,,,,,

b. Pressurir.er level (inchen) O to 350 , , , , , , , , , , , ,

101 to 160

c. RCS subcooling ( F) 30 to 140 _,,,,,,,,,

30 to 140 it PORVs were opened, once an hour monitor the following:

d. Quench Tank para.ne te rs : ,

cont

  • ant constant l level (inches (j) temperature O pressure (PSIO)

F or decreasing ,___,,,,,,

or decreasing l

e. PORV discharge Piping temperature ( F)

$COM CR (computer points T107, T108) decreasing decreasing

).8 1174 ,,,,,,,,,,,

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. j O  !

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EOP-4 R3v. 1/Uait 1 Page 28 of 31 l I I

CORE AND RCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

=

a. RCS Tcold ( F) less than 515 ________

less than 500

b. CET ( F) less than 565 ,,,,____

less than 550 c.TgotminusTcold

( F)

Natural Circulation 10 to 50 .

.,,_____ 10 to 50 Forced Circulation less than 10 ________

less than 5

d. Unaffected S/G greater pressure (PSIA) 150 to 900 ________

than 50 I e. Unaffected S/G (-)250 to (-)24 to level (inches) (+)30 ,,_,,,,, (+)30

f. Condensate Storage Tank greater level (ft) greater than 5 ____,,,,

than 5 l I

EOP-4 Rcv. 1/ Unit 1 Page 29 of 31 l I VITAL SAFETY FUNCTION ACCEPTANCE CRITERIA AUXILIARIES CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

c. 4KV vital buses 11 or 14 energized __________

energized

b. Instrument Air greater greater pressure (PSIG) than 88 __________

than 88

c. Component Cooling

(# pumps running) 1 or 2 __________

1 or 2

d. Saltwater

(# pumps running) 1 or 2 __________

1 or 2

c. Service Water

(# pumps running) 1 or 2 __._______

1 or 2 f

I I . 125V 11, DC 12, buses 21, 22 energized __________

energized

g. 120V AC vital buses 11, 12, 13, 14 energized __________

energized l

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EOP-4 R;v. 1/ Unit 1 Page 30 of 31 NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT ENVIRONMENT CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK C. Containment pressure (PSIG) less than 50 ________

less than 2.8

b. Containmen',

tgmperature

( F) less than 276 ,,,,_____

less than 220

c. Containment High Range .

Radiation alarm alarm Monitor clear ________

clear

d. Hydrogen N

concentration N/A _ _ _ h_ _ less than 2%

< i

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EOP-4 R;v. 1/ Unit 1 Page 31 of 31 l l r

NORMAL RADIATION SAFETY IUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL TO CONTAINMENT CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. Noble Gas Monitor alarm alarm clear __________

clear

b. Condenser Off-Gas (1) a' arm alarm RMS claar __________

clear

c. S/G B/D RMS (1) alarm alarm clear ,,___,,,,_

clear

d. Main Vent Gaseous alarm alarm RMS (1-RI-5415) clear ___,,,____

clear

' 1) Wjth MSIVs shut and S/G Blowdown isolate 1, request Chemistry to sample S/Gs for activity.

i l STATUS CHECK COMPLETE AT NUMBER TIME 1

2 3

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EOP-4 R:';v . 1/ Unit 2 Paga 1 of 31 l k CALVERT CLIFFS NUCLEAR POWER PLANT EOP-4 EXC_ESS STEAM DEMAND REVISION 1 "IGNATimR DATE PREPARED BY; v

t W /b~ ~

') 3 VERIFIED BY; f[v:h- a/#771P

~

/ / 7 [r # 87

/

POSRC; MEETING # %7 / 2.- l C - W3 APPROVED BY; hd Argmw / t ' ' C ' C'

,Pfa6at;f6r-Nuclear Operations or General Supervisor-Operations if POSRC review is not required I

EOP-4 R;v. 1/ Unit 2 Page 2 of 31 I I LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 1 13 1 14 1 15 1 16 1 17 1 I 18 1 1

19 1 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 28 1 29 1 30 1 31 1 l I l

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EOP-4 R:v. 1/ Unit 2 Pcga 3 of 31 I I EXCESS STEAM DEMAND I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently te ensure correct operation.

C. At least two independent indications should be used, wher available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments.

D. High energy line break may cause erratic instrumentation response depending on the magnitude nd location of the break.

E. Minimize the number of cycles of pressurizer auxiliarg spray when the temperature differential is greater than 400 F.

F. In Natural Circulation, increased loop transport time causes a 5 I I to 10 minute delay in temperature responses to a plant change.

Pressurizer level and pressure responses, if available, typically provide better indication of RCS response during this period.

G. S/G pressure, pressurizer pressure, and containment temperature affect the level indication for the S/Gs and Pressurizer.

Attachments (8) and (9) contain the corrected S/G and pressurizer levels for various S/7 pressures, pressuriser pressures, and containment temperatures.

H. If a pump or component fails, the cause of the failure should be determined prior to restarting or starting a standby pump or component to prevent a common failure.

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EOP-4 R v. 1/ Unit 2 Pcga 4 of 31 l l II. ENTRY CONDITIONS The presence of one or more of the following conditions indicates that an Excess Steam Demand may have occurred:

A. Decrease in S/G pressure in one or both S/Gs.

B. Reactor Trip on low S/G pressure.

C. Reacter Trip on high containment pressure.

D. Possible actuation of:

1. SIAS
2. CIS
3. CSAS
4. SGIS ,

E. Decrease in Tcold.

F. Loud noise and poor visibility in plant (location dependent).

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EOP-4 R0v. 1/ Unit 2 Pcga 5 of 31 III. RECOVERY ACTIONS ALTERNATE ACTIONS I I ,

A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED.

B. COMMENCE INTERMEDIATE SAFETY FUNCTION STATUS CHECK.

C. DETERMINE APPROPRIATE EMERGENCY RESPONSE ACTIONS PER THE ERPIP.

D. ISOLATE BOTH S/Gs:

1. Shut both MSIVs.

l l 2. Shut S/G Feedwater Isolation Valves:

2-FW-4516-MOV 2-FW-4517-MOV

3. Shut MSIV Bypass Valves:

2-MS-4045-MOV 2-MS-4052-MOV

4. Shut S/G Blowdown Valves:

2-BD-4010-CV 2-BD-4011-CV 2-BD-4012-CV 2-BD-4013-CV I

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EOP-4 l R v. 1/ Unit 2 Pcg3 6 cf 31

'I. RECOVERY ACTIONS ALTERNATE ACTIONS

5. Shut AFW Steam Supply Valves by placing handswitches in CLOSE:

2-MS-4070-CV 2-MS-4071-CV

6. Shut AFW Block Valves by placing handswitches in CLOSE:

21 S/G 22 S/G 2-AFW-4520-CV 2-AFW-4530-CV 2-AEW-4521-CV 2-AFW-4531-CV 2-AFW-4522-CV 2-AFW-4532-CV 2-AFW-4523-CV 2-AFW-4533-CV .

7. Shut Atmosphoric Dump Valves.
8. Shut upstream drains by placing handswitch 2-HS-6622 in CLOSE.

l I E. MONITOR RCS DEPRESSURIZATION.

1. 1F rapid depressurization 1.1. IF RCS pressure is greater to 1725 PSIA, than 1725 PSIA AND SIAS NOT THEN verify SIAS actuation actuated, AND the following actions: THEN block SIAS:
a. All available Charging a. Open Main and Aux HPSI Pumps running. Header velves:
b. 21 and 23 HPSI Pumps 2-SI-616-MOV 2-SI-617-MOV running. 2-SI-626-MOV 2-SI-627-MOV 2-SI-636-MOV 2-SI-637-MOV
c. Main and Aux HPSI Header 2-SI-646-MOV 2-SI-647-MOV i

Valves open:

b. Start 21 and 23 HPSI '

2-SI-616-MOV 2-SI-617-MOV Pumps. l 2-SI-626-MOV 2-SI-627-MOV i 2-SI-637-MOV I 2-SI-636-MOV c. WHEN "PRSR PRESS BLOCK 2-SI-646-MOV 2-SI-647-MOV A(B) PERMITTED" alarms (s) received, THEN block SIAS A(B). I l l l l

j l

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EOP-4 R v. 1/ Unit 2 Page 7 of 31 l II. RECOVERY ACTION _S ALTERNATE ACTIONS F. IMPLEMENT RCP TRIP STRATEGY:

1. If RCS pressure decreases to 1725 PSIA, 71521 trip 21A and 22B RCPs QB trip 21B and 22A RCPs.
2. IE positive LOCA indications exists
a. RCgsubcoolinglessthan 30 F.
b. Steady S/G pressure.
c. S/G Blowdown RMS alarms clear 9B Main Vent Gaseous RMS (2-RI-5415) alarm clear.

AND RCS pressure decreases j to less than 1300 PSIA,

)

THEN trip all RCPa.

3. If RCS temperature and pressure are less than the minimum pump operating limits per the RCP curve on Attachment (1),

THEN trip all RCPs.

4. If CIS has actuated, THEN trip all RCPs.

G. MONITOR CONTAINMENT PRESSURE:

1. If CSAS NOT actuated, THEN start all available Containment Air Coolers in HIGH with maximum SRW flow.

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EOP-4 R;v. 1/ Unit 2 Pega 8 of 31

'II . -RECOVERY _ ACTIONS AL. TE.R. NATE ACTIONS

2. IF containment pressure increases to 2.8 PSIG, THEN verify ESFAS actuation
a. SIAS.
b. CIS 6HD trip all RCPs.

60 2. Verify SRW Pump Room 30 Ventilation in service per gf 01-15.

4. 1F containment pressure increases to 4.25 PSIG, TIIEN verify CSAS actuation AND spray flow approximately 1350 GPM. .

H. VERIFY BORATION IN PROGRESS:

1. IF SIAS has actuated, 1.1 IF SIAS NOT actuated, q g THEN verify boration in _THEN commence borationi progress:
a. Shut VCT Makeup Valve,
a. Shut VCT Makeup Valve, 2-CVC-512-CV.

2-CVC-512-CV.

b. Open Boric Acid Direct
b. Open Boric Acid Direct Makeup Valve, Makeup Valve, 2-CVC-514-MOV.

2-CVC-514-MOV.

c. Start a Boric Acid Pump,
c. Boric Acid Pumps running.
d. Start all available
d. Open BAST Gravity Feed Charging Pumps.

Valves:

2-CVC-508-MOV 2-CVC-509-MOV l I

EOP-4 Rcv. 1/ Unit 2 PCg3 9 of 31 AL_TE_RfjMTE ACTIONS III. RECOVERY ACTIONS I )

1.2 IF Boric Acid Pumps NOT

e. Shut VCT Outlet available, Valve, 2-CVC-501-MOV. THEN establish gravity feeds
f. All available Charging Pumps running, a. Open BAST Gravity Feed Valves:

2-CVC-508-MOV 2-CVC-509-MOV

b. Shut VCT Outlet Valve, 2-CVC-501-MOV.
c. Start all available Charging Pumps.
2. Continue boration until
  • a total 65 inch decrease in BAST level (s) is achieved, or shutdown margin requirement of NEOG-11 is achieved.

,. IDE!!TIFY AFFECTED S/G.

1. Compare the following parameters:
a. S/G pressures.
b. Teold on both loops. ,
c. S/G levels.

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EOP-4 R;v. 1/ Unit 2 Pcga 10 of 31

'II. RECOVERY ACTIONS ALTERNATE ACTIONS I I ,

J. MAINTAIN HEAT SINK OPERABILITY OF UNAFFECTED S/G DURING BLOWDOWN PHASE:

1. For the affected S/G, shut 1.1 IF Atmospheric Dump Valve the Atmospheric Dump Valve will NOT shut from 2C43, using the Hand Transfer I1!EU shut Atmospheric Dump Manual Isolation Valve, Valves on the West wall of the Unit 2 45 ft Switchgear Room: 21 S/G or 22 S/G
a. Verify 2C43 Atmospheric 2-MS-101 2-MS-104 Dump Controllers at 0%

output.

b. Align Hand Transfer Valves to 2C43 position:

21 S/G or 22 S/G 1-HV-3939A 1-HV-3938A 1-HV-3939B 1-HV-3938B

- NOTE - - NOTE -

Unaffected S/G temperature may be For steam breaks in Containment, obtained by using tha saturation resulting in small cooldown rates, temperature for the existing S/G the energy released to Containment pressure, may be reduced by use of S/G Blowdown on affected S/G.

2. IF RCS cooldown rate 2.1 IF RCS cgoldown rate less than 100 F/h, gregter than or equal to 100 F/h hND CET 210R{ establish Natural temperatures less than Circulation using unaffected S/G temperature, unaffected S/G:

THEN cool ungffected S/G a. Open motor driven train to within 25 F of CET temperatures: AEW Block Valves on unaffected S/G:

a. Open motor drivan train AEW Block Valves on 2_1 S/G or 22 S/G unaffected S/G: 2-AEW-4532-CV 2-AFW-4522-CV 21 S/G or 22 S/G 2-AEW-4523-CV 2-AFW-4533-CV 2-AFW-4522-CV 2-AFW-4532-CV <

{ } 2-AEW-4523-CV 2-AFW-4533-CV f 1

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EOP-4 R;v. 1/ Unit 2 Pcga 11 cf 31 I. RECOVERY _ACTJONS ALTERNATE ACTIONS

- CAUTION - - CAUTION -

D/G supplying power to 23 AFW D/G supplying power to 23 AFW Pump Pump flow limit is 300 GPM; flow limit is 300 GPM; otherwise otherwise, flow limit is 575 GPM. flow limit is 575 GPM.

b Start 23 AEW Pump, b. Start 23 AEW Pump.

c. Adjust AFW Flow Concrol c. Manually throttle open Valves to feed unaffected AFW Flow Control Valve.

S/G. 22 S/G 21 S/G or 21 S/G or 22 S/G 2-AFW-4525-CV 2-AFW-4535-CV 2-AFW-4525-CV 2-AFW-4535-CV

d. Open Atmospheric Dump

- CAUTION - Valve as necessary to cool unaffected S/G, while CET temperatures must always be maintaining RCS cogidown less than unaffected S/G rate less than 100 F/h.

temperature while affected S/G blowdown is in progress. e. Stabilize unaffected S/G level between (-)170 and

d. Open Atmospheric Dump (+)30 inches.

{ ) Valve as necessary to cool unaffected S/G to within 25 F of CET temperatures,

e. Stabilize unaffected S/G level between (-)170 and

(+)30 inches.

K. RESTORE PRESSURIZER LEVEL TO BETWEEN 50 AND 110 INCHES DURING S/G BLOWDOWN:

1. Verify letdown isolated.
2. IF RCS pressure less than 1270 PSIA, THEN verify HPSI flow to RCS per Attachment (12).

1 l

EOP-4 R v. 1/ Unit 2 Page 12 of 31 I. RECOVERY ACTIONS ALTERNATE ACTIONS

3. lE additional HPSI flow required to control pressurizer level, THEN lower RCS pressure using Auxiliary Spray per step M, page 13.
4. WHEN pressurizer level greater than 50 inches,

_THEN secure all but one Charging Pump.

5. If the following conditions exists
a. At least 30 F subcooling.
b. Pressurizer level greater than 50 inches.
c. At least one S/G available for heat removal.

RVLMS indicates that the

{ d.

Core is covered.

THEN throttle HPSI flow to maintain pressurizer level between 50 and 110 inches.

L. WitEN STEADY Teold INDICATES S/G BLOWDOWN COMPLETE O_R COOLDOWN RATE LESS THAN 100 F/h, TIIEN ESTABLISH UNAFFECTED S/G AS A HEAT SINK:

1. Restore S/G wide range level to between (-)24 and (+)30 3 inches using 23 AFW Pump,
2. Open Atmospheric Dump Valve as necassary to cool unaffected S/G, while maintaining RCS cogidown rate less than 100 F/h.

l I 3. Stabilize pressurizer level between 101 and 155 inches.

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EOP-4 R;v. 1/ Unit 2 Pcg3 13 cf 31

I. EECOVERY ACTIONS ALTERNATE ACTIONS

( l M. MAINTAIN RgS SUBCOOLING BETWEEN 30 AND 140 F

- CAUTION -

The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

1. Operate Pressurizer Heaters as necessary to maintain RgS subcooling greater than 30 F.
2. 1F necessary to lower 2.1 ,1Y pressurizer level RCS subcooling bHD greater than 3SO inches pressurizer level less than SND RCS gubcooling is greater 350 inches, than 140 F, THEU verify heaters secured _TI_IEN open PORV:

AND initiate Auxiliary Sprays

a. Verify primary makeup
a. Place Instrument Air CIS path operable.

{ } Override Switch, 2-HS-2080A, in OVERRIDE. b. Place both PORV Override Control Switches in

b. Open Cntmt Instrument Air OVERRIDE SHUT.

Isolation MOV, 2-IA-2080-MOV. - NOTE -

c. Record temperature The "PORV ENERGIZED" alarm *1111 differential between annunciate when two RPS trip Pressurizer and units are pulled. The PORVs Regenerative Heat will not open.

Exchanger Outlet,

c. Pull two High Pressurizer
d. Open Auxiliary Spray Pressure Trip Units out on Valve, 2-CVC-517-CV. RPS.
d. Place one PORV Override Control 9 witch in AUTO.
e. lE second PORV needed to lower subcooling, T_g;H placs the other PORV Override Control Switch in AUTO.

I I f. WHEg subcooling less than 140 F, THEN perform the following:

EOP-4 I rov. 1/ Unit 2 i Pcy? 14 of 31

'II. _ RECOVERY ACTIONS ALTERNATE _ ACTIONS l l

e. Shut Loop Charging Valves: (1) Pl' ace the PORV Override Control Switches in 2-CVC-518-CV OVERRIDE SHUT.

2-CVC-519-CV

'2) Insert High Pressurizer

- NOTE - Pressure Trip Units that were previously pulled.

2-HS-2085 located on West wall of 27 ft Switchgear Room; Key #80 (3) Ensure "PORV ENERGIZED" in Control Room Key Locker, alarm clear.

(4) IF Acoustic Monitor

f. Open Cntmt Instrument Air indicates flow through Supply CV, 2-IA-2085-CV, the PORV, by mcmentarily placing DIEN shut the PORV Block 2-HS-2085 in OPEN. Valve,
g. Shift 2-HIC-100 to MANUAL and shut Pressurizer Spray Valves:

2-RC-100E-CV 2-RC-100F-CV I I h. Maintain preseurizer coofdownrate 200 F/h less thsn N. IF RCPs SECURED, FIEN CONFIRM NATURAL CIRCULATION IN UNAFFECTED S/G LOOP:

- HOTE -

Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10).

1. ThotmgnusTcoldbetween10 and 50 F.
2. Teold constant or decreasing.
3. Thot constant or decreasing.
4. CET temperatures consistent vith Thot.

{ }

5. Steaming rate affects primary temperature.

EOP-4 R v. 1/ Unit 2 Pcgo 15 cf 31 lI. ALTERNATE ACTIONS

_R_ECOVERY ACTIONS

( l O. MONITOR FOR CORE AND RCS VOIDING:

- CAUTION -

Potential for void formation increases rapidly when pressure decreases below 1500 PSIA.

1. Letdown flow greater than charging flow.
2. Rapid unexplained increase in pressurizer level during an RCS pressure reduction.
3. Loss of subcooled margin as determined using CET temperatures.
4. "REACTOR VESSEL WATER LEVEL LOW" alarm.

l l P. IF VOIDING INHIBITS HEAT REMOVAL, RIEN REDUCE OR ELIMINATE VOIDED AREA:

1. Shut Litdown Isolation Valve, 2-CVC-515-CV.

- CAUTION -

The potential exists for pressurized thermal sheck from an excessive cooldown rate followed by a repressurization.

If pressurizing the RCS  !

2. Pressurize the RCS to 2.1 does NOT restore heat removal, i maigtain subcooling as near THEN operate Reactor Vessel 140 F as practical, by any of the following: Vent Valves per 01-10.

- HOTE -

Pressurizer Backup Heater Banks (

l l 21 and 23 trip on U/V and SIAS. t l

l l

E2P-4 R;v. 1/ Unit 2 Pcq316 cf 31 ALTERNATE ACTIONS

'II . _ RECOVERY ACTIONS l I

a. Operate Pressurizer Heater (s),
b. Operate Turbine Bypass or Atmospheric Dump Valves to maximize RCS cooldown, while maintaining coogdownratelessthan 100 F/h,
c. Raise HPSI flow to RCS.

- CAUTIOE -

If voids exict in the S/G tubes, a rapid RCS pressure reduction vill occur when the voids ,

collapse.

3. II voiding occurs in the S/G tubes (saturation pressure of S/G greater than saturation pressure of RCS),

g THEN cool the S/G by raising

{ any of the following:

a. Steaming rate.
b. Feed rate.
c. S/G Blowdown rate.

AND, maintaining less than 100 F/h cooldown rate.

Q. SECURE THE FOLLOWING SECONDARY PUMPS:

1. Trip S/G Feed Pumps.
2. Place Condensate Booster Pumps 1r LULL-TO-LOCK.
3. Place 0 of the 3 Condeneate Pumps in PULL-TO-LOCK.

( l 4. Secure Heater Drain Pumps.

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EOP-4 R;v. 1/ Unit 2 PCg3 17 cf 31 RECOVERY ACTIONS bLTERNATE ACTIONS tl >I I .

R. LffiK!j RCS BORATION COMPLETE,

_THEN SHIFT CHARGING PUMP SUCTION SUPPLY TO MAKEUP SUPPLY WITH A LOWER BORIC ACID CONCENTRATION.

1. II SIAS actuated, 1.1 II SIAS HQT actuated, THEN perform the following: TIIEN line up Charging Pump suction to VCT:
a. Open RWT To Charging Pump Suction Valve, n. Determine blend 2-CVC-504-MOV. requirements to maintain shutdown boron
b. Shut VCT Outlet concentration per NEOG-11.

Valve, 2 - CVC-- 501- MOV .

.b. Open VCT Outlet Valvo,

c. Place Boric Acid Pumps 2-CVC-501-MOV.

in PULL-TO-LOCK.

c. Secure Boric Acid Pump (s).
d. Ensure Charging Pump AMPS steady, d. Shut Borie Acid Direct

!!akeup ';alve, 2-CVC-514-MOV.

q g

o. Shut BAST Gravity Feed Valves:

2-CVC-508-MOV 2-CVC-509-MOV QB line up Charging Pump suction to RWT:

a. Open RWT To Charging Pump Suction Valve, 2-CVC-504-MOV.
b. Shut VCT Outlet Valve, 2-CVC-501-MOV.
c. Shut Boric Acid Direct Makeup Valve, 2-CVC-514-MOV.
d. Secure Boric Acid Pumpe(s).

l I

EOP-4 R;v. 1/ Unit 2 Dage 18 of 31 I. RECOVERY ACTIONS ALTERNATE ACTIONS S. COMMENCE ESFAS VERIFICATION CHECKLISTS:

1. SIAS Attachment (2).
2. CSAS Attachment (3).
3. CIS Attachment (4).
4. SGIS Attachment (7). .

T RESTORE CONTAINMENT ENVIRONMENT:

1. Direct Chemistry to place Hydrogen Monitors in service.
2. IF hydrogen concentration increases to 1%,

j ) THEN start Hydrogen Recombiners per OI-41A.

3. MHEN containment pressure less than 4.0 PSIG, TIJEH perform the following
a. Reset CSAS signal,
b. Secure one Containment Spray Pump,
c. Verify all Containment Air Coolers operating to maintain containment temgerature less than 120 F.
d. Restore equipment per CSAS Verification Checklist, Attachment (3), to desired condition.

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EOP-4 R;v. 1/ Unit 2 Page 19 of 31

'II. RECOVERY ACTIONS ALTE_RN&TE ACTIONS I >

4. }fSEN containment pressure less than 2.8 PSIG, TEEN perform the followings
a. Block pressurizer pressure signals and reset SIAS signal,
b. Reset CIS signal.
c. Secure remaining Containment Spray Pump,
d. Restore equipment per SIAS and CIE Verification Checklists, Attachments (2) and (4), to desired condition.

U. RESTORE SERVICE WATER TO TURBINE BUILDING:

I

1. Verify 11 Plant Air Cempressor operating.
2. Shut Plant Air To Plant Air Header Valve, 2-PA-2059-CV.
3. Open Plant Air To Instrument Air Crosc Connect Valve, 2-PA-2061-CV.
4. Open SRW Turbine Building Header Isolation Valves:

2-SRW-1600-CV 2-SRW-1637-CV 2-SRW-1638-CV 2-SRW-1639-CV i I

EOP-4 R;v. 1/ Unit 2 Pcga 20 of 31 II. RECOVERY _ ACTIONS ALTERNATE t _ ACTIONS V. RESTORE INSTRUMENT AIR COMPRESSORS TO SERVICE:

1. IE high temperature alarm exists on the Instrument Air Compressors, T1]EN open the service water isolation valves by placing their handswitches in OPEN until temperature alarm clears.

2.1 or R_2 2-HS-2063 2-HS-2065 .

2. Start at least one Instrument Air Compressor.

I '

RESTORE INSTRUMENT AIR TO l l. CONTAINMENT:

1 1, Open Cntmt Instrument I Air Isolation MOV, 2-IA-2000-MOV.

- NOTE -

2-HS 2085 located on West wall of l 27 ft Switchgear Room; Key #80 l in Control Room Key Locker, l
2. Open Cntmt Instrument Air Supply CV, 2-IA-2005-CV, by l momentarily placing 2-HS-2085 j l in OPEN.

l X. PISTORE LETDOWN FLOW:

l 1. Verify charging flowpath I through Loop Charging ij Valves or Auxiliary Spray

)

Valve.

I

E'i P- 4 R;v. 1/ Unit 2 Page 21 cf 31 I. RECOVERY _ACTIOES ALTERNATE I.CTIONS

2. Verify at least one Charging Pump operating.
3. Shift Letdown Control Valve Controller, 2-HIC-110, to MANUAL.
4. Adjust controller to shut Letdown Control Valves.
5. Open Letdown Isolation Valves:

2-CVC-515-CV 2-CVC-516-CV

-CAUTIOB-The setpoint of 2-PIC-201 must be above the saturation pressure for the letdown outlet temperature of the Regenterb.tive Heat Exchanger.

6. Adjust the setpoint on 2-PIC-201 and adjust

{ }

2-HIC-110 to maintain desired pressurizer level.

Y. If RCPs AVAILABLE, 230W EVALUATE NEED FOR FOPOED OR NATURAL CIRCULATION:

1. MIIEN RCPs available AND 1.1 If RCPn HOT available OR Forced Circulation desired, Natural Circulation desired, THEN start RCPa per steps 2-12. THEN implement Natural Circulation (AOP-3E) AND complete administrative post-trip actions.
2. IE RCPn exposed to excessi"e moisture,

, IDEN consider meggering RCP motor.

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E0P-4 R;v. 1/ Unit 2 Page 22 of 31

'II, RF&OM RY ACTIONS AILERNATE ACTI_0_N_S

( l

- G E LOE -

Uncontrolled restoration of cooling to hot RCP seals may caune degradation of the metallic centing surfaces by thermal shock.

3. IE Component Cooling is isolated to RCP seals, seal IJIEN reducebelow temperature RCP lower,F 280 prior to initiating full cooling flow to the RCPs:
a. Shut Component Cooling Supply Containment Manual ,

Isolation Valve, 2-CC-284, located in 5 ft East Penetration Room,

b. Verify CIS reset.

{ ) c. Open Component Cooling Containment Isolation Valves:

2-CC-3832-CV 2-CC-3833-CV

d. Slowly open 2-CC-284 to throttle component cooling flow antil lower seal tengeratures are less than 280 F.
e. MIEN lower seal temgeratures are less than 280 F,

'nIEN fully open 2-CC-284.

4. 14 an P i lower seal

' temp?tature exceeded 280 F.

'DIEN an engineering evaluation is required prior to restarting that RCP.

5. Raise pressurizer level to l at least 155 inches, i

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E0P-4 R;v. 1/ Unit 2 Pcg3 23 of 31 II. BEQO_yERY ACTIONS AL_TE R TE ACTIONS s

6. Verify RCP restart criteria
a. 9CS subgooling greater than 30 F.
b. At least one S/G available for heat removal.

~

c. Pressurizer level greater than 155 inches and stable,
d. Tcold less than 525 F.
e. RCS temperature and pressure greater than the minimum operating limits per the RCP curve on s Attachment (1).

- HOTE -

Starting an RCP may cause a pressurizer level transient.

l l

7. MUM RCP restart criteria met, TIIEN start one RCP in a loop with an operable S/G:

- a. Verify "COMPT CLG FLOW LO" alarm clear.

b. Start 011 Lift Pump.
c. Insert RCP sync stick,
d. Start one RCP.
e. Monitor RCP running current:

Iarg Curren_t 525 to 572 F 238 to 210 AMPS and steady 210 to 525 F 264 to 238 AMPS and steady I I

E0P-4 R;v. 1/ Unit 2 Pcg3 24 of 31 1I. RECOVERMCTIONJ ALTERNAFuACTIOMS

( l

8. IF pressurizer level decreases, THEN start Charging or HPSI Pump (s) as necessary to restore SND maintain level greater than 155 inches.
9. Monitor RCP seal parameters following pump restart.
10. Allow backflow to equalize temperatures in opposite loop.
11. Start second RCP in opposite loop per step Y.7 and Y.9, pages 23 and 24.
12. Secure Auxiliary Spray: ,
a. Open Loop Charging Valves:

2-CVC-518-CV 2-CVC-519-CV

b. Shut Auxiliary Spre;'

Valve, 2 CVC-517-CV.

c. Shift Pressuriter Spray Controller, 2-HIC-100, to AUTO.

Z. COMPLETE ADM!!!!STRATIVE POST-TRIP ACTIO!1S AND IMPLEMENT APPROPRIATE OPERATIl1G PROCEDURE.

1

EOP-4 R;v. 1/ Unit 2 Pcg3 25 of 31 l I AA. ADMINISTRATIVE POST-TRIP ACTIONS:

- HOIE -

The following actions may be accomplished whenever feasible.

They may be done in any order.

1. Refer to ERPIP to determine appropriate emergency response actions.
2. Perform notifications per CCI-118,
3. Notify ESO of trip.
4. Request RCS Boron and Iodine sample.
5. Perform shutdown margin calculation per NEOG 9 and 11.
6. Complete transient log entries per CCI-301.

I I 7. Recall post-trip review (preferably within 30 minutes of trip).

8. Perform post-trip review per CCI-ill.
9. Monitor turbine bearing temperatures.
10. Continue Main Turbine shutdown per applicable step of OI-43A.

END OF SECTION III.

l I

l EOP-4 R:v. 1/ Unit 2 Pcg3 26 cf 31 l I IV. EAEETY FUNCTIOR JTATUS CIIEC)$

A. The STA (or person designated by STA) will perform the intermediate and final safety functions checks respectively on entry and prior to exiting from this procedure.

B. Perform intermediate safety function status check at 10 minuto intervals until plant conditions stabilize.

C. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied.

D. Review data and verify that safety function acceptance criteria are satisfied.

E. When EOP completed, then perform final safety function check.

REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK

( h--

c. WsNI powee less than 8% ,,,,,,,,,,

less than .1% ,

b. 3YR (DI'M) negative ,,,,,,,,,,

0 0, CCA status all inserted ,,,,,,,,,,

all inserted or Boration status:

appropriate concentation increasing ,,,,,,,,,,

S/D margin BAST level decreasing ,,,,,,,,,, N/A N/A i i cx wu

EOP-4 R;v. 1/ Unit 2 Pcg3 27 of 31 I I RCS PRESSURE SAFETY FUNCTIO!1 ACCEPTA!1CE CRITERIA AND ItNENTORY FINAL PARAMETERS CRITERIA  !!iTERMEDIATE CRITERIA CHECK CHECX

c. Pressurizer pressure (PSIA) 300 to 1900 ,,,,,,,,,,

300 to 1900

b. Pressurizer 101 to 160 level (inches) O to 350 ,,,,,,,,,,
c. RCS subcooling ( F) 30 to 140 ,,,,,,,,,,

30 to 140 If PORVs were opened, ,

once an hour monitor the following:

d Quench Tank parameters:

constant constant

{ )

level (inchesj temperature ( F) or or pressure (PSIG) decreasing ,,,,,,,,,,

decreasing

o. PORV discharge piping temperature (OF)

(computer points T107 T108) decreasing ,,,,,,,,,,

decreasing l I

EOP-4 R;v. 1/ Unit 2 PCg3 28 of 31 i I '

CORE AND RCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL FINAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA CHECK CHECK less than 515 less than 500

o. RCS Teold ( F) ,,,,,,,,
b. CET ( F) less than 565 ,,,,,,,,

less than 550

c. Tgot minus Tcold

( F)

Natural Circulation 10 to 50 ,,4,,,,,

10 to 50 Forced Circulation less than 10 ,,,,,,,,

less than 5

d. Unaffected S/G greater pressure (PSIA) 150 to 900 ,,,,,,,,

than 50

c. Unaffected S/G (-)250 to (-)24 to level (inches) (+)30 ,,,,,,,,

(+)30

f. Condensate greater Storage Tank level (ft) greater than 5 ,,,,,,,,

than 5 l I

EOP-4 RCv. 1/ Unit 2 PCg3 29 of 31 l I ,

VITAL SAFETY EUNCTION ACCEPTANCE CRITERIA AUXILIARIES __

CRITERIA FINAL CRITERIA INTERMEDIATE CHECK CHECK

o. 4KV vital buses energized 21 or 24 energized ,,,,,,,,,,

greater

b. Instrument Air greater than 88 pressure (PSIG) than 88 ,,,,,,,,,,
c. Component Cooling 1 or 2

(# pumps runnir.g) 1 or 2 ,,, ,,,,,,

d. Saltwater 1 or 2

(# Pumps running) 1 or 2 ,,,,,,,,,,

c. Service Water 1 or 2

(# pumps running) 1 or 2 ,,,,,,,,,,

f q I . 125V 11, DC 12, buses 21, 22 energized ,,,,,,,,,,

energized

g. 120V AC vital buses energized 21, 22, 23, 24 amergized ,,,,,,,,,,,

4

EOP-4 R v. 1/ Unit 2 Pcga 30 of 31 I I ,

NORMAL SAFETY FUllCTION ACCEPTANCE CRITERIA CONTAINMENT FINAL ENVIRONMENT CRITERIA INTERMEDIATE CRITERIA CHECK CliECK PARAMETERS o Containment less than 2.8 pressure (PSIG) less than 50 ,,,,,,,,,

b. Containment tgmperature less tnan 276 less than 220

( F) ,,,,,,,,

c. Containment High Range .

alarm alarm Radiation clear Monitor clear ,,,,,,,,

d. Hydrogen gjg concentration N/A ,,,,,,,,

less than 2%

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EOP-4 R;v. 1/ Unit 2 PCga 31 cf 31 I I NORMAL RADIAIION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL TO CONTAINMENT CRITERI$ INTERMEDIATE CRITERIA ~ FINAL CIIECK CilECK

o. Noble Gas Monitor alarm alarm clear ,,,,,,,,,,

clear

b. Condenser off-Gas (1) alarm alarm RMS clear ,,,,,,,,,,

clear (1) alarm alarm

c. S/G B/D RMS clear clear ,,,,,,,,,,
d. Main Vent Gaseous alarm alarm RMS (2-RI-5415) clear ,,,,,,,,,,

clear (1) With MSIVs shut and S/G Blowdown isolated, request Chemistry to sample S/Gs for activity.

STATUS CHECK COMPLETE AT NUMBER TIME 1

2 3

4 i

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EOP-5 Rov. 1/ Unit 1 PCgo 1 cf 41 l l CALVERT CLIFFS NUCLEAR PJWER PIANT E9P . L tass _o, COOIANT_ACCIDEgf REVISION 1 i

SIGNATURE DATE I PREPARED BY; _ st/L j t m s4- //2[/8[87 VERIFIED BY; _,_

/ "M Ars 2Q

( , /

!t.g POSRC; M!ETJNG_# 9?'l X_ N\T / ?-\o 7/6

/ 2 'C - T'*3 AP? ROVED BY; p niorei-Mariager-fluclear Operations or General Supervisor-Operations if POSRC review is not required I I l

l E0P-5 i R;v. 1/ Unit 1 !

Page 2 of 41 l

LIST OF EFFECTIVE PAGES I PAGE NUMBER REVISIAT 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 , 1 13 1 14 1 15 1 16 1 17 3 18 1 19 1 I 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 28 1 29 1 30 1 31 1 32 1 33 1 34 1 35 1 36 1 37 1 38 1 39 1 40 1 41 1 I

EOP-5 i R3v. 1/ Unit 1 (

Pcgo 3 of 41 j l

I l I LOSS OF C_OOLANT ACCIDENT I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments.

D. High energy line break may cause erratic instrumentation response depending on the magnitude and location of the break.

E. ESFAS actuated safety features should only be overridden to support a threatened safety function or when directed by the procedure.

I h F. During a LOCA, pressurizer level may not provide an accurste indication of RCS inventory due to the formation of voids.

Pressurizr level "hen combined with RCS subcooling will indicate s.at the core is covered.

G. For small breaks in the RCS where the S/Gs are important for heat removal, one S/G must be used for this purpose even if primary to secondary leaks are detected.

H. Minimize the number of cycles of pressurizer auxiliarg spray when the temperature differential is greater than 400 F.

I. In Natural Circulation, increased loop transport time causes a 5 to 10 minute delay in temperature responses to a plant change.

Pressurizer level and pressure responses, if available, typically provide better indication of RCS response during this period.

J. S/G pressure, pressurizer pressure, and containment temperature affect the level indication for the S/Gs and Pressurizer.

Attachments (8) and (9) contain the corrected S/G and pressurizer levels for various S/G pressures, pressurizer pressures, and containment temperatures.

K. If a pump or component fails, the cause of the failure should be l ) determined pr >r to restarting or starting a standby pump or component to prevent a common failure.

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EOP-5 l Rcy. 1/ Unit 1 l Page 4 of 41 l l

l l I II. ENTRY CONDITIONS The presence of one or more of the following conditions indicates that a Loss Of Coolant Accident may have occurred:

1 A. Unexplained decreasing pressurizer level.

B. Unexplained decreasing pror- ' '* pressure.

C. Loss of RCS subcooled margir.

D. High containment radiation alarm.

E. Increase in containment sump level.

F. Increase in coneainment sump clarm frequency.

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EOP-5 R v. 1/ Unit 1 Page 5 of 41

1. RECOVERY ACTIONS ALTERNATE ACTIONS l

A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED.

B. COMMENCE INTERMEDIATE SAFETY FUNCTION STATUS CHECK.

C. DETERMINE APPROPRIATE EMERGENCY P.ESPONSE ACTIONS PER THE ERPIP.

D. MONITOR RCS DEPRESSURIZATION.

1. If rapid depressurization 1.1 If RCS pressure is greater l l to 1725 PSIA, than 1725 PSIA AND SIAS NOT THEN verify SIAS actuation actuated, AND the following actions: THEN attempt leak isolation:
a. All available Charging a. Shut Letdown Isolation Pumps running. Valves:
b. 11 and 13 HPSI Pumps 1-CVC-515-CV running. 1-CVC-516-CV
c. Main and Aux HPSI Header b. Shut RCS Sample Isolation Valves open: Valve, 1-PS-5464-CV.

1-SI-616-MOV 1-SI-617-MOV c. Shut Reactor Vessel Vent 1-SI-626-MOV 1-SI-627-MOV Valves:

1-SI-636-MOV 1-SI-637-MOV 1-SI-646-MOV 1-SI-647-MOV 1-RC-103-SV 1-RC-104-SV

d. Shut Pressurizer Vent Valves:

1-RC-105-SV l 1-RC-106-SV j 1

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EOP-5 Rev. 1/ Unit 1 Page 6 of 41 4 jI. RECOVERY ACTIONS A L_T_E _R N A_T E A C T I O N S

e. IE PohV leakage is indicated by:

(1) High Quench Tank parameters.

(2) High PORV discharge piping temperature, computer points CCOM CR T107 and T108. .

88-1175 I

(3) Abnormal Acoustic Monitor indication.

THEN shut PORV Block Valves:

1-RC-403-MOV 1-RC-405-MOV

f. If leak is isolated AND SIAS NOT actuated, THEN implement Reactor l l Trip (EOP-1) AND complete administrative post-trip actions step AO, page 35.

1.2 If leak is NOT isolated AND RCS pressure still greater than 1725 PSIA, THEN block SIAS:

a. Open Main and Aux HPSI Header Valves:

1-SI-616-MOV 1-SI-617-MOV 1-SI-626-MOV 1-SI-G27-MOV 1-SI-636-MOV 1-SI-637-MOV 1-SI-646-MOV 1-SI-647-MOV

b. Start 11 and 13 HPSI Pilmp s .
c. )fHEN "PRSR PRESS BLOCK A(B) PERMITTED" alarm (s) received, THEN block SIAS A(B).

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EOP-5 l R';v . 1/ Unit 1 Page 7 of 41 l II. RECOVERY ACTIONS ALTERNATE ACTIONS E. IMPLEMENT RCP TRIP STRATEGY:

1. II RCS pressure decreases to 1725 PSIA, THEN trip 11A and 12B RCPa gB trip 11B and 12A RCPs.
2. IE positive LOCA indications exists
a. RCg subcooling less than f

30 F.

b. Steady S/G pressure.
c. S/G Blowdown RMS alarms clear 9B Main '!ent Gaseous RMS (1-RI-5415) alarm clear.

AND RCS pressure decreases g

to less than 1300 PSIA, q

THEN trip all RCPs.

3. IE RCS temperature and pressure are less than the minimum pump operating limits per the RCP curve on Attachment (1),

BLElj trip all RCPs.

4- IE CIS has actuated,

_ TIM trip all RCPs.

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EOP-5 R;v. 1/ Unit 1 Page 8 of 41

'II. RECOVERY ACTIONS ALTERNATE ACTIONS l I s

F. VERIFY BORATION IN PROGRESS:

1. IF SIAS has actuated, 1.1 IF SIAS NOT actuated, TIIEN verify boration in THEN conmence boration progress:
a. Shut VCT Makeup Valve,
a. Shut VCT Makeup Valve, 1-CVC-512-CV.

1-CVC-512-CV.

b. Open Boric Acid Direct
b. Open Boric Acid Direct Makeup Valve, Makeup Valvo, 1-CVC-514-MOV.

1-CVC-514-MOV.

c. Start a Boric Acid Pump.
c. Boric Acid Pumps running.

,d. Start all available

d. Open BAST Gravity Feed Charging Pumps.

Valves:

1.2 IF Boric Acid Pumps NOT 1-CVC-500-MOV available, 1-CVC-509-MOV TggN establish gravity feed:

e. Shut VCT Outlet Valve, a. Open BAST Gravity Feed I I 1-CVC-501-MOV. Valves
f. All available Charging 1-CVC-508-MOV Pumps running. 1-CVC-509-MOV
b. Shut VCT Outlet Valve, 1-CVC-501-MOV.
c. Start all available Charging Pumps.
2. Continue boration until a total 65 inch decrease in BAST level (s) is achieved, or shutdown margin requirements of NEOG-7 is achieved.

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EOP-5 R v. 1/ Unit 1 Page 9 of 41 I. RECOVERY ACTIONS ALTERNATE ACTIONS G. IF RCS PRESSURE DECREASES TO LESS THAN 225 PSIA, THEN VERIFY SAFETY INJECTION SYSTEM OPERATION:

1. Verify HPSI and LPSI flow to 1.1 IF 11 or 13 HPSI Pump fails, RCS per Attachments (12) and THEN start 12 HPSI Pump AND (13). align to appropriate header.
2. Verify SI Tanks discharging to RCS cold legs.
3. Monitor containment pressure per step K, page 13.

H. RESTORE NORMAL S/G WATER LEVEL:

- CAUTION -

l l Severe water hammer may occur if Main Feed Ring is allowed to drain then subsequently refilled.

1. IF Main Feed available, 1.1 IF Main Feed NOT available, THEN establish a shutdown THEN establish AFW as follows:

feed system lineup:

- CAUTION -

a. One operating S/G Feed Pump. D/G supplying power to 13 AFW Pump flow limit is 300 GPM;
b. One operating Condensate othe rwise, flow limit is 575 GPM.

Booster Pump,

a. Start an AEW Pump.
c. One operating Condensate Pump. b. Adjust AEW Flow Control Valves to maintain S/G
d. Both Heater Drain Pumps levels between (-)l70 and secured. (+)30 inches.

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EOP-5 ROV. 1/ Unit 1 Page 10 of 41 I. RECOVERY ACTIONS ALTERNATE ACTIONS

2. WHEN manual control of feed flow rate desired OR S/G levels between (-)24 and

(+)30 inches, THEN perform the followings

a. Depress Feed Regulating Bypass Valve Reset Buttons.
b. Adjust Feed Regulating Bypass Valves to raise S/G levels to approximately 0 inches.
3. WHEN S/G lovels are 0 inches, THEU shift Feed Regulating ,.

Bypass Controllers to AUTO.

I. IF RCG PRESSURE GREATER THAN 225 PSIA, j ) THEN ESTABLISH COOLDOWN IN AT LEAST ONE LOOP:

1. W HEN "SGIS A(B) BLOCK PERMITTED" alarm (s) received, THEN block SGIS A(B).
2. Open Turbine Bypass or Atmospheric Dump Valves as necessary to maximize RCS cooldown, while maintaining coogdown rate less than 100 F/h.

I I

EOP-5 Rsv. 1/ Unit 1 Page 11 of 41 II. RECOVERY ACTIONS ALTERNATE ACTIONS

3. IF RCPs are secured, THEN verify Natural Circulation:

- NOTE -

Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10),

a. Thot minug Tcold between 10 and 50 F.
b. Tcold constant or decreasing.
c. Thot constant or ,

decreasing.

d. CET temperatures consistent with Thot.
e. Steaming rate affects q g primary temperature.
4. Monitor for Core and RCS voiding:

- CAUTION -

Potential for void formation increases rapidly when pressure decreases below 1500 PSIA.

a. Letdown flow greater than charging flow.
b. Rapid unexplained increase in pressurizer level during an RCS pressure reduction.
c. Loss of subcooled margin as determined using CET temperatures.
d. "REACTOR VESSEL WATER LEVEL LOW" alarm.

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E0P-5 R;v. 1/ Unit 1 Pcg2 12 of 41

'II . RECOVERY ACTIONS _AL_ TERNATE ACTIONS l l l

5. IF voiding inhibits heat removal, THEN reduce or eliminate voided nreas
a. Shut Letdown Isolation Valve, 1-CVC-515-CV.

- CAUTION -

The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

b. Pressurize the RCS to 5.b.1 IF pressurizing the RCS does maintainsugcooling . NOT restore heat removal as near 140 F as THEN operate Reactor Vessel practical. Vent Valves per OI-1G.

- CAUTION -

If voids exist in the S/G Tubes, g g a rapid RCS pressurn reduction will occur when the voids collapse,

c. IF voiding occurs in the S/G tubes (saturation l pressure of S/G greater than saturation pressure l i

of RCS),

THEN cool the S/G by raising any of the following:

(1) Steaming ratu.

(2) Feed rate.

S/G Blowdown rate. f (3)

AND maintaining less than 100 F/h cooldown rate.

6. Continue cooldown to 300 F.

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EOP-5 R;v. 1/ Unit 1 Pcga 13 of 41

't I . RECOVERY ACTIONS ALTERNATE ACTIONS I I J. If RCS PRESSURE LESS THAN 1270 PSIA, THEN VERIFY HPSI FLOW TO RCS PER ATTACHMENT (12).

J.1 IF 11 or 13 HPSI Pump fails, THEN start 12 HPSI Pump AND align to appropriate header.

K. MONITOR CONTAINMENT PRESSURE:

1. IF CSAS NOT actuated, ,

THEN start all available Containment Air Coolers in HIGH with maximum SRW flow.

2. IF containment pressure increases to 2.0 PSIG AND still increasing, THEN start 11 and 12 Containment Spray Pumps and open both Cntmt Spray Header CVs.

11 12 1-SI-4150-CV 1-SI-4151-CV

3. IF contaiment pressure increases to 2.8 PSIG, THEN verify ESFAS actuation:
a. SIAS.
b. CIS AND trip all RCPs.

$$ 4. Verify SRW Pump Room gy Ventilation in service, gg per 01-15. ,

l

5. IF containment pressure increases to 4.25 PSIC, l TIIEN verify CSAS actuation j AND spray flow approximately  !

{ } 1350 GPM.

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EOP-5 R v. 1/ Unit 1 Page 14 of 41 lII. RECOVERY ACTIONS ALTERNATE ACTIONS I I L. COMMENCE ESFAS VERIFICATION CHECKLISTS:

1. SIAS Attachment (2).
2. CSAS Attachment (3).
3. CIS Attachment (4).

M. MAINTAIN RCS SUBCOOLING AND PRESSURIZER LEVEL:

1. Maintain sgbcooling between 30 and 140 F using CET temperatures.

- CAUTION -

The potential exists for l l pressurized thermal abock from an excessive cooldown rate followed by a repressurization.

2. Raise subcooling by any of the following:

.. NOTE -

Pressurizer Backup Heater Banks 11 and 13 trip on U/V and SIAS.

a. Operate Pressurizer Heater (s),
b. Operate Turbine Bypass or 2.b.1 IF unable to obtain desired Atmospheric Dump Valves cooldown rate with Turbine to maximize RCS cooldown, Bypass and Atmospheric Dump while maintaining Valves, coogdown rate less than THEN use steam driven AEW 100 F/h. Pump (s) to increase cooldown rate.
c. Raise HPSI flow to RCS. i k

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EOP-5 R:v. 1/ Unit 1 Page 15 of 41 ALTERNATE ACTIONS

[I. RECOVERY ACTIONS

3. Lower sube~ooling by any of 3.1 IE unable to lower the following: subcooling, T HEN initiate Auxiliary
a. De-energize Pressurizer Spray:

Heater (s). a. Place Instrument Air CIS Override Switch,

b. Lower RCS cooldown rate. 1-HS-2080A, in OVERRIDE.
c. If the following conditions can be b. Open Cntmt Instrument Ait Isolation MOV, maintained: 1-IA-2080-MOV.

(1) At least 30 F

c. Record temperature subcooling.

differential between (2) Pressurizer level Pressurizer and greater than 155 ,

Regenerative Heat inches. Exchanger Outlet.

d. Open Auxiliary Spray (3) At least one S/G Valve, 1-CVC-517-CV.

available for heat removal,

e. Shut Loop Charging l (4) RVLMS indicates that Valves:

the Core is covered.

1-CVC-518-CV THEN throttle HPSI flow 1-CVC-519-CV or operate Charging Pumps as necessary to maintain - NOTE -

subgooling between 30 and 1-HS-2085 located on West wall 140 F.

of 27 ft Switchgear Room; Key

  1. 85 in Control Room Key Locker,
f. Open Cntmt Instrument Air Supply CV, 1-IA-2085-CV, by momentarily placing 1-HS-2085 in OPEN.
g. Shift 1-HIC-100 to MANUAL l and shut Pressurizer l Spray Valves:

1-RC-100E-CV 1-RC-100F-CV

h. Maintain pressurizer cooldowng rate less f q g than 200 F/h. j l

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EOP-5 Rcv. 1/ Unit 1 Page 16 of 41

'II. RECOVERY ACTIONS ALTERhATE ACTIONS I I

- NOTE -

A break on top of Pressurizer will result in an uncontrollable increase in pressurizer level until Pressurizer is solid.

4. Maintain pressurizer level between 101 and 160 inches.

- CAUTION -

Doo not throttle HPSI flow unless 30 F subcooling can be maintained,

a. IF the following .

conditions can be maintained:

(1) At least 30 F subcooling.

q g (2) Pressurizer level greater than 101 inches.

(3) At least one S/G available for heat removal.

(4) RVLMS indicates that the Core is covered.

THEN throttle HPSI flow or operate Charging Pumps as necessary to maintain pressurizer level between 101 and 160 inches.

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EOP-5 Rcv. 1/ Unit 1 Page 17 of 41

'II. RECOVERY ACTIONS ALTERNATE ACTIONS l l N. }fHEN RCS BORATION COMPLETE,

_THEN SHIFT CHARGING PUMP SUCTION SUPPLY TO MAKEUP SUPPLY WITH A LOWER BORIC ACID CONCENTRATION.

1. IF SIAS actuated, 1.1 IF SIAS NOT actuated, THEN perform the following: THEN lineup Charging Pump suction to VCT:
a. Open RWT To Charging Pump Suction Valve, a. Determine blend 1-CVC-504-MOV. required to maintain shutdown boron
b. Shut VCT Outlet Valve, concentration per 1-CVC-501-MOV. NEOG-7.
c. Place Boric Acid Pumps 'b. Open VCT Outlet Valve, in PULL-TO-LOCK. 1-CVC-501-MOV.
d. Ensure Charging Pump c. Secure Boric Acid Pump (s).

AMPS steady,

d. Shut Boric Acid Direct
e. Ensure BAST levels Makeup Valve, I I steady. 1-CVC-514-MOV.
e. Shut BAST Gravity Feed Valves:

1-CVC-508-MOV 1-CVC-509-MOV OR lineup Charging Pump suction to RWT:

a. Open RWT To Charging Pump Suction Valve, 1-CVC-504-MOV.
b. Shut VCT outlet Valve, 1-CVC-501-MOV.
c. Shut Boric Acid Direct Makeup Valve, 1-CVC-514-MOV.
d. Secure Boric Acid Pump (s). l l I

l EOP-5 R;v. 1/ Unit 1 Page 18 of 41 RECOVERY ACTIONS ALTERNATE ACTIONS

{ JI.

O. If RWT LEVEL DECREASES TO BETWEEN O.5 AND 1.0 FT QR "ACTUATION SYS RAS TRIPPED" ALARM RECEIVED, TLIEN VERIFY RAS ACTUATION:

1. Place SI Pump Recire Lockout Switches in ON.
2. Commence RAS Verification Checklist, Attachment (6).
3. Shut RWT Outlet Valves:

1-SI-4142-MOV 1-SI-4143-MOV .

4. IF HPSI flow greater than 1000 GPM with two HPSI Pumps operating, THEN equally throttle HPSI flow to 1000 GPM.
5. IE HPSI flow greater than 600 GPM with one HPSI Pump operating,

_THEN equally throttle HPSI flow to 600 GPM.

- CAUTION -

To prevent pump damage, minimum flow por operating HPSI Pump is 30 GPM.

6. IE HPSI Pump cavitation 6.1 IE Attachment (12) does HgT occurs in recirculation modo, allow throttling HPSI flow, THEN throttle HPSI flow per THEN align Containment Spray Attachment (12). Pump (s) to HPSI Pump suction
a. IE 11(12) HPSI Pump cavitating, THEN open 11 SDC HX To HPSI Suction Valvo, 1-SI-663-MOV AND start 11 Containment Spray Pump.

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EOP-5 Rcv. 1/ Unit 1 Page 19 of 41

II . RECOVERY ACTIONS ALTERNATE ACTIONS l I
b. IF 15 HPSI Pump cavitating, THEN open 12 SDC HX To HPSI Suction Valve, 1-SI-662-MOV AND start 12 Containment Spray Pump.
7. Commence ECCS Pump Room cooling:
a. Open ECCS Pump Room Air Cooler Saltwater Valver:

1-SW-5170-CV 1-SW-5171-CV 1-SW-5173-CV ,

b. Start 11 and 12 ECCS Pump Room Cooling Fans.
8. Adjust saltwater flow to maintain SRW and component cooling temperatures.
9. If Charging Pumps are aligned with suction from RWT AND HPSI Pumps maintaining RCS inventory, THEN place Charging Pumps in PULL-TO-LOCK.

P. RESTORE CONTAINMENT ENVIRONMENT:

1. Direct Chemistry to place Hydroger. Monitors in service.
2. IF hydrogen concentration increases to 1%,

_TIIEN start Hydrogen Recombiners per OI-41A.

3. Maintain Iodine Filter Fans running, i I

EOP-5 RCv. 1/ Unit 1 Page 20 of 41

'II . RECOVERY ACTIONS ALTERNATE ACTIONS l l

4. WBEN containment pressure less than 4.0 PSIG, THEN perform the following
a. Reset CSAS signal.
b. Secure one Containment Spray Pump.
c. Verify all Containment Air Coolers operating to maintain containment temgerature less than 120 F.
d. Restore equipment per CSAS Verification ,

checklist, Attachment (3), to desired condition.

5. WHEN containment pressure less than 2.8 PSIG, THEN perform the following:
a. Block pressurizer pressure signals and reset SIAS signal.
b. Reset CIS signal.
c. Secure remaining Containment Spray Pump.
d. Rostore equipment per SIAS and CIS Verification Checklists, Attachments (2) and (4), to desired condition.

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E0P-5 R;v. 1/ Unit 1 Page 21 of 41 II. RECOVERY ACTIONS ALTERNATE ACTIONS Q. EVALUATE NEED FOR HPSI TERMINATION:

1. WHEN HPSI termination criteria mets
a. At least 30 0F subcooling.
b. Pressurizer level greater than 155 inches and stable.
c. At least one S/G available for heat removal,
d. RVLMS indicates that the Core is covered.

THEN HPSI Pump (s) may be secured.

{ l

2. IF HPSI termination criteria can NOT be maintained, THEN start 11 and 13 HPSI Pumps.

R. RESTORE SERVICE WATER TO TURBINE BUILDING:

1. Verify 21 Plant Air Compressor operating.
2. Shut Plant Air To Plant Air Header Valve, 1-PA-2059-CV.
3. Open Plant Air To Instrument Air Cross Connect Valve, 1-PA-2061-CV.
4. Open SRW Turbine Building Header Isolation Valves:

1-SRW-1600-CV I I 1-SRW-1637-CV 1-SRW-1638-CV 1-SRW-1639-CV

EOP-5 R3v. 1/ Unit 1 Page 22 of 41 I. RECOVERY ACTIONS ALTERNATE ACTIONS S. RESTORE INSTRUMENT AIR COMPRESSORS TO SERVICE:

1. 1F high temperature alarm exists on the Instrument Air Compressors, THEN open the service water isolation valves by placing their handswitches in OPEN until temperature alarm clears.

11 or 12 1-HS-2063 1-HS-2065 .

2. Start at leart one Instrument Air Compressor.

{ ) RESTORE INSTRUMENT AIR TO CONTAINMENT:

1. Open Cntmt Instrument Air Isolation MOV, 1-IA-2080-MOV.

- NOTE -

1-HS-2085 located on West wall of 27 ft Switchgear Room; Key #85 in Control Room Key Locker.

2. Open Cntmt Instrument Air Supply CV, 1-IA-2085-CV, by momentarily placing 1-HS-2085 in OPEN.

U. RESTORE LETDObH FLOW:

1. Verify charging flow path through Loop Charging Valves I I or Auxiliary Spray Valve.

EOP-5 RCv. 1/ Unit 1 Page 23 of 41

'I. RECOVERY ACTIONS ALTERNATE ACTIONS

2. Verify at least one Charging Pump operating.
3. Shift Letdown Control Valve Controller, 1-HIC-110, t'o MANUAL.
4. Adjust controller to shut Letdown control Valves.
5. Open Letdown Isolation Valves:

1-CVC-515-CV 1-CVC-516-CV

- CAUTION -

~

The setpoint of 1-PIC-201 must be above the saturation pressure for the letdown outlet temperature of the Regenerative Heat Exchanger.

6. Adjust the setpoint on 1-PIC-201 and adjust 1-HIC-110

( ) to maintain desired pressurizer level.

V. If FORCED CIRCULATION DESIRED 24Q PUMP RESTART CRITERIA MET, THEU START RCPs:

1. IE RCPs exposed to excessive moisture,

))pq{ consider meggering RCP j motor.

- CAUTION -

Uncontrolled restoration of cooling to hot RCP seals may cause degradation of the I metallic seating surfaces by thermal shock.

1 4 > 1

EOP-5 R v. 1/ Unit 1 Pcgo 24 of 41

'II. RECOVERY ACTIOM ALTERNATE ACTIONS I l

2. IF Component Cooling is isolated to RCP seals, THEN reduce RCP lowerg seal temperature below 280 F prior to initiating full cooling flow to the RCPc:
a. Shut Component Cooling Supply containment Manual Isolation Valvo, 1-CC-284, located in 5 ft East Penetration Room.
b. Verify CIS reset.
c. Open Component Cooling '

Containment Isolation Valves:

1-CC-3832-CV l-CC-3833-CV

d. Slowly open 1-CC-284 l I to throttle component cooling flow until lower soal tempergtures are less than 280 F.
e. W

_ HEN lower seal temgeratures are less than 280 F, THEN fully open 1-CC-284.

3. IP an RCP lower seal 0 temperature exceeded 200 F,

.JIEN an engineering T

evaluation is required prior to restarting that RCP.

4. Raise pressurizer level to at least 155 inches.
5. Verify RCP restart criteria
a. RCS subgooling greater than 30 F.
b. At least one S/G i

{ ) available for heat '

removal.

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I EOP-5 R;v. 1/ Unit 1 Pcg3 25 of 41

11. RECOVERY ACTIONS ALTERNATE ACTIONS l l
c. Pressurizer level greater than 155 inches and stable.
d. Tcold less than 525 F.
e. RCS temperature and pressure greater than the minimum operating limits per the RCP Curve on Attachment (1).

- NOTE -

Starting an RCP may cause a pressurizer level transient.

6. hgD2] RCP restart criteria are met, THFN start one RCP in a loop with an operable S/G:
a. Verify "COMPT CLG FLOW LO" alarm clear.

( )

b. Start Oil Lift Pump.
c. Insert RCP sync stick.
d. Start one RCP.
e. Monitor RCP running current:

Tava Current 525 to 572 F 230 to 210 AMPS and steady 210 to 525 F 264 to 230 AMPS and steady

7. IF pressurizer level decreases, THEN start Charging or HPSI Pump (s) as necessary to restore bND maintain level greater than 155 inches.
8. Monitor RCP seal parameters l I following pump restart.

EOP-5 R v. 1/ Unit 1 Pcg3 26 cf 41 TI. RECOVERY ACTIONS ALTERNATE ACTIONS l l

9. Allow backflow to equalize temperatures in opposite loop.
10. Start second RCP in opposite lo" - step V.6 and V.8, pv "1.

. Ser - tiary Spray:

Loop Charging 4, 9:

NC-518-CV JC-519-CV Snut Auxiliary Spray ,

Valve, 1-CVC-517-CV.

c. Shift Pressurizer Spray controller, 1-HIC-100, to AUTO.

l l W. M RCS, TEMPERATURE IS LESS THAN 330 F MJD RCS PRESSURE IS LESS THAN 380 PSIA, T_IIEU ESTABLISH MPT PROTECTION:

- CAUTION -

PORVs must be in MPT ENABLE before Tcold indication gn T115 ,

or T125 is loss than 325 F.

I

1. Manually reset 1-PY-103 and 1-PY-103-1 bistables by prensing the reset buttons located on 1C25A behind 1C06.
2. Place both PORVs in the MPT f ENABLE mode.

1

3. Place both PORV Override l Switches in OVERRIDE CLOSED i position. l l I i

i 1

1

EOP-5 R;v. 1/ Unit 1 Page 27 of 41 III. RECOVERY _ ACTION _S ALTERNATE _ ACTIONS l l X. )flM RCS, TEMPERATURE IS LESS THAN 300 F AND RCS PRESSURE IS LESS THAN 300 PSIA, THEN PERFORM THE FOLLOWING:

- NOTE -

Cavity Cooling and CEDM Cooling aid in cooling Reactor Vessel Head if a void exists.

1. If Cavity Cooling and CEDM Cooling Fans available,

_T_IIEU maintain Cavity Cooling and CEDM Cooling

  • Fans running.
2. Shut SI Tank outlet Valves:

1-SI-614-MOV 1-SI-624-MOV 1-SI-634-MOV l ) 1-SI-644-MOV

3. .If AFW NOT being used to feed S/Gs, THEN perform the following
a. Shut the motor and steam driven train AFW Block Valves:

11_S/_O 12 S/G 1-AFW-4520-CV 1-AFW-4530-CV 1-AFW-4521-CV 1-AFW-4531-CV 1-AFW-4522-CV 1-AFW-4532-CV 1-AFW-4523-CV 1-AFW-4533-CV

b. Place 13 AFW Pump in PULL-TO-LOCK.
c. Shut AEW Steam Supply Valves:

11 Szg 1;LSE q g 1-MS-4070-CV 1-MS-4071-CV

EOP-5 R;v. 1/ Unit 1 Pcg3 28 of 41

I. RECOVERY AC"fIONS ALTERNATE ACTIONS i I Y. IF CET SUBCOOLING LESS THAN 30 F,

_THEN COMMENCE CORE FLUSH WITHIN 24 HOURS AFTER THE SIAS ACTUATION:

1. Line up for Pressurizer 1.1 IF Pressurizer Injection Injection: NOT available AND the following conditions are
a. Open SI Discharge To met:

Charging Header Core Flush Valve, a. RCS pressure lean than 1-CVC-269-MOV. 270 PSIA.

b. Shut Loop Charging b. RCS pressure minus Valves: ,

containment pressure less than 160 PSID.

1-CVC-518-CV 1-CVC-519-CV TIIEN line up for Hot Leg Injection

c. Shut Pressurizer Spray Valves: a. Place 11 or 12 LPSI Pump RAS Override g g Switch in OVERRIDE.

1-RC-100E-CV 1-RC-100F-CV

b. Cpen Cntmt Sump
d. Open HPSI Aux Header Discharge Valves:

Isolation Valve, 1-SI-656-MOV. 1-SI-4144-MOV 1-SI-4145-MOV l

e. Open Auxiliary Spray Valve, 1-CVC-517-CV. c. Open Shutdown Cooling l I

Heat Exchanger Recirc

f. Shut HPSI Main Header Isolation Valve, Cross Connect Valve, 1-SI-399-MOV.

I 1-SI-653-MOV.

d. Shut LPSI Header Valves ;
g. Shut Aux HPSI Header l Valves: 1-SI-615-MOV 1-SI-625-MOV 1-SI-617-MOV 1-SI-635-MOV 1-SI-627-MOV 1-SI-645-MOV 1-SI-637-MOV 1-SI-647-MOV
h. Start 11 or 12 HPSI Pump and maintain a minimum flow of 40 GPM.

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EOP-5 R v. 1/ Unit 1 Pcg3 29 of 41 III. RECOVERY ACTIONS ALTERNATE ACTIONS l l

1. IF minimum flow can e. Verify RCS pressure NOT be determined, less than 270 PSIA.

THEN initiate Hot Leg Injection. f. Open Shutdown Cooling Suction Header Isolation Valves:

1-SI-651-MOV 1-SI-652-MOV

g. Start selected LPSI Pump,
h. Maintain a minimum flow of 40 GPM.
2. WHEN Pressurizer Injectd.en OB Hot Leg Injection in ,

progress, balance flow by throttling Main HPSI Header Valves:

1-SI-616-MOV 1-SI-626-MOV 1-SI-636-MOV l l 1-SI-646-MOV

_ tin 2J maintain required flow to remove decay heat per Attachment (12).

3. Ensure CET temperatures remain constant or decreasing.

1 1

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EOP-5 R v. 1/ Unit 1 PCg3 30 of 41 I. RECOVERY ACTIONS ALTERNATE ACTIONS Z. q CET TEMPERATURES LESS THAN 300 F AND RADIATION LEVELS PERMIT, THEN COMMENCE SHUTDOWN COOLING.

1. If all the following 1.1 II pressurizer level greater conditions exists than 101 inches AND RCS subcooling greater than 30 F, THEN initiate Shutdown Cooling
a. Pressurizer levol less per OI-3.

than 101 inches.

b. RCg subcooling lers than 1.2 Operate HPSI and Charging 30 F. Fumps as necessary to maintain pressurizer level and
c. RCS pressure minus pressure.

containme't pressure less .

than 160 PSID. t THEN commence Shutdown Cooling as follows:

s. Shut 11 Containment Spray

{ ) Pun.r Discharge Valve, 1-SI-314.

b. Shut 12 Containment Spray Pump Discharge Valve, 1-SI-324.
c. Shut 11 Shutdown Cooling Heat Exchanger Outlet To Spray Header Valve, 1-SI-319.
d. Shut 12 Shutdown Cooling Heat Exchanger Outlet To Spray Header Valve, 1-SI-329.
e. Open 11 Shutdown Cooling Heat Exchanger Inlet Cross Connect Valve, 1-SI-452.
f. Open 11 Shutdown Cooling Heat Exchanger Outlet To l RCS Valve, 1-SI-456.

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E0P-5 R;v. 1/ Unit 1 Page 31 of 41 II. RECOVERY ACTIONS ALTERNATE ACTIONS

g. Open 12 Shutdown Cooling .

Heat Exchanger Inlot Cross connect Valve, 1-SI-453.

h. Open 12 Shutdown Cooling Heat Exchanger Outlet to RCS Valve, 1-SI-457.
1. Place second Component Cooling Heat Exchanger in service by opening appropriate Component Cooling Heat Exchanger Outlet Valve:

1-CC-3824-CV 1-CC-3826-CV

j. Start second Component Cooling Pump.
k. Open 11 Shutdown Cooling Heat Exchanger Component Cooling outlet Valve, j g 1-CC-3828-CV.
1. Open 12 Shutdown Cooling Heat Exchanger Component Cooling Outlet Valve, 1-CC-3830-CV.
m. Open Shutdown Cooling Heat Exchanger Inlet Isolation, 1-SI-658-MOV.
n. IF Hot Leg Injection 1.n.1 IF Hot Leg Injection NOT being used for core flush, being us,d for core flush, THEN shut 12A LPSI J open 12A LPSI Header TIEM Header Valve, 1-SI-635-MOV. Valve, 1-SI-635-MOV.
c. Open LPSI Header Valves:

1-SI-615-MOV 1-SI-625-MOV l-SI-645-MOV

p. Place keyswitch for 1-SI-30'a-CV in AUTO.
q. Shift 1-FIC-306 to MANUAL l with 5% open signal.

EOP-5 rov. 1/ Unit 1 Pcgo 32 of 41 III. RECOVERY ACTIONS ALTERNATE ACTIONS I I

r. Open Cntmt Sump Discharge '

Valves 1-SI-4144-MOV 1-SI-4145-MOV

s. Shut SI Pump Mini Flow Isolations:

1-SI-659-MOV 1-SI-660-MOV

t. Ensure level indication exists on wide range containment level indicator 1-LI-4146.

- CAUTION -

The possibility of cavitation increases when taking suction from containment sump.

u. JF LPSI Pump NOT

{ l operating, THEN clear RAS from one operable LPSI Pump by placing LPSI Pump RAS Override Switch in OVERRIDE AND start selected pump.

- CAUTION -

changes from Coofdownlimig/hgtRCS 100 F/h to 20 F temperature of 250 F.

v. Adjust the ?ignal on  !

1-FIC-306 to raise flow  !

to 3000 GPM, while '

maintaining cooldown rate within limits.

v. Place keyswitch for 1-SI-657-CV in AUTO.

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EOP-5 RCv. 1/ Unit 1 Page 33 of 41

'II . _ RECOVERY ACTIONS ALTERNATE ACTIONS l I

- CAUTION -

Do not exceed 12 F/m heatup rate or greater than 5000 GPM through one heat exchanger.

x. Adjust Shutdown Cooling Temperature Control Valve, 1-gI-657-CV, to obtain 12 F/m heatup rate at Shutdown Cooling Heat Exchanger Outlet (1-TI-303X and 1-TI-303Y).
y. IF desired RCS cooldown rate can NOT be maintained with one LPSI Pump, ,

THEN start second LPSI Pump AND adjust 1-FIC-306 to 6000 GPM.

z. Adjust Shutdown Cooling Temperature Control Valve, 1-SI-657-CV, to obtain I I desired cooldowr rate.

AA. _WHEN CET, TEMPERATURES LESS THAN 200 F, JJUR! SECURE CORE FLUSH FLOWPATH:

1. IF HPSI Pump (s) NOT required for RCS presture or level control, THEN secure HPSI Punip( s) .
2. Shut SI Discharge To Charging Header Core Flush Valve, 1-CVC-269-MOV. ,

I

3. Open Loop Charging Valves:  !

1-CVC-518-CV 1-CVC-519-CV

4. Shut Auxiliary Spray Valve, 1-CVC-517-CV. 4 I I 1

EOP-5 R;v. 1/ Unit 1 Page 34 of 41

'II . RECOVERY ACTIONS ALTERNnTE ACTIONS i l

5. Shut Shutdown Cooling Heat Exchanger Recirc Isolation, 1-SI-399-MOV.
6. Oper 12A LPSI Header Valve, 1-SI-635-MOV.

AB. COMPLETE ADMINISTRATIVE POST-TRIP ACTIONS AND IMPLEMENT APPROPRIATE OPERATING PROCEDURE.

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EOP-5 R v. 1/ Unit 1 Page 35 of 41 i I AC. ADMINISTRATIVE POST-TRIP ACTIONS:

- NOTE -

The following actions may be accomplished whenever feasible. They may be done in any order.

1. Refer to ERPIP to determine appropriate emercency response actiona.
2. Perforn. notifications per CCI-118.
3. Notify ESO of trip.
4. Request RCS Boron and Iodine sample,
5. Perform shutdown margin calculation per NEOG 2 and 7.

6 Complete trknsient log entries per CCI-301.

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7. Recall post-trip review (prefers %1y within 30 minutes of trip).
8. Perform post-trip review per CCI-111.
9. Monitor turbine bearing temperatures.
10. Continue Main Turbine shutdown per applicable step of OI-43A.

END OF SECTION III.

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EOP-5 R v. 1/ Unit 1 Page 36 of 41 l I IV. SAFETY FUNCTION STATUS CHECK A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to exiting from this procedure.

B. Perform intermediate safety function status check at 10 minute intervals until plant conditions stabilize.

C. Immediately notify Shift .9upervisor or Control Room Supervisor if any safety function criteria is not being satisfied.

D. Review data and verify that safety function acceptance criteria are satisfied.

E. When EOP completed, then perform final safety function check.

REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. WRNI power less than 3% __________ less than 1%
b. SUR (DPM) negative ___,,,,,__

O

c. CEA status all inserted _________,

all inserted or Boration status:

appropriate concentation increasing ________,_

S/D margin BAST level decreasing __________ N/A N/A l I

EOP-5 R v. 1/ Unit 1 Page 37 of 41 l I RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND IMVENTORY PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. Pressurizer pressure (PSIA) less than 1900 __________

less than 1900

b. Pressurizer level (inches) (1) O to 160 __________

O to 160

c. RgS subcooling greater than

( F) O to 140 __________

30 (1) A break at top of Pressurizer will result in solid pressurizer indication. This is an acceptaale value provided the other parameters still indicate a LOCA.

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EOP-5 R;v. 1/ Unit 1 Page 38 of 41 I I CORE AND RCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. CET ( F) less than 700 ___,,___

less than 500

b. Tgot minus Tcold

( F) (2) 10 to 50 _____,,_

10 to 50

c. S/G pressure (PSIA) 150 to 900 ________ N/A N/A
d. S/G level (-)170 to , (-)24 to

'(inches) (+)30 _______, (+)30 _

e. Cold Leg greater greater Injection (GPM) than 40 ________

than 40

f. Condensate Storage Tank greater greater I I level (ft) than 5 ___,,,,,

than 5

g. Core flush established within 24 greater greater hours (GPM) than 40 _,,,____

than 40 (2) Thot and Teold indication may be influenced by charging or SI temperatures during a large break LOCA. If this occurs Thot minus Tcold may be deleted from the check provided CET temperatures meet their acceptance criteria, I >

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EOP-5 R;v. 1/ Unit 1 Page 39 of 41 I I VITAL SAFETY FUNCTION ACCEPTANCE CRITERIA AUXILIARIES CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

c. 4KV vital buses 11 or 14 energized __________

energized

b. Instrument Air greater greater preasure (PS?G) than 88 __________

than 88

c. Component Cooling

(# pumps running) 1 or 2 __________

1 or 2

d. Saltwater

(# Pumps running) 1 or 2 __________

1 or 2

c. Service Water

(# Pumps running) 1 or 2 _________,

1 or 2 f

I I . 125V 11, DC 12, buses 21, 22 energized __________

energized

g. 120V AC vital buses 11, 12, 13, 14 energized __________

energized __

EOP-5 R v. 1/ Unit 1 Pcg3 40 of 41 l h NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT ENVIRONMENT CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK

c. Containment pressure (PSIG) less than 50 ________

less than 2.8

b. Containment tgmperature

( F) less than 276 ________

less than 220

c. Containment High Range ,

Radiation alarm alarm Monitor clear ________

clear

d. Hydrogen concentration N/A ___ N(A__ less than 2%

i >

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EOP-5 R;v. 1/ Unit 1 PCga 41 Of 41 l l I NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL TO CONTAINMENT CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. Noble Gas Monitor alarm alarm clear __________

clear

b. Condenser Off-Gas alarm alarm RMS clear ,_________

clear

c. S/G B/D RMS alarm alarm clear __,,_,,,,_

clear

d. Main Vent Gaseous alarm alarm RMS (1-RI-5415) clear __________

clear STATUS CHECK COMPLETE AT NUMBER TIME 1

2 3

4 J

F EOP-5 R;v. 1/ Unit 2 Pcgo 1 cf 41 l I CALVERT CLIFFS NUCLEAR POWER PLANT EOP-5 LOSS OF COOLANT ACCIDENT REVISION 1

' ~

Tu DATE p

PREPAREDBY; , % Av L C/V y x x~

/ k1- '

VERIFIED BY; 4.3t/g [ / /7 6f ~/

POSRC; T

M ETING 46 .

"oG-7 / 2. \C - %%

/ 1' ' O ~ W APPROVED BY; ;4 ww Man &ghf-Nuclear Operations or General Supervisor-Operations if POSRC review is not required

EOP-5 Rcv. 1/ Unit 2 Page 2 of 41 LIST OF EFFECTIVE PAGES PAGE NUMBER REVISIog 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 -

1 13 1 14 1 15 1 16 1 17 1 18 1

( ) 19 1 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 28 1 29 1 30 1 31 1 32 1 33 1 34 1 35 1 i 36 1 37 1 I 38 1 l

39 1 40 1 i 41 1  !

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EOP-5 RCV. 1/ Unit 2 PCgo 3 of 41 l l LOSS OF COOLANT ACCIDENT I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation.

C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments.

l D. High energy line break may cause Arratic instrumentation response depending on the magnitude and location of the break.

l E. ESFAS actuated safety features should only be overridden to I support a threatened safety function or when directed by the procedure.

ll } F. During a LOCA, pressurizer level may not provide an accurate i indication of RCS inventory due to the formation of voids.

Pressurizer level when combined with RCS subcooling will indicate that the core is covered.

G. For small breaks in the RCS where the S/Gs are important for heat removal, one S/G must be used for this purpose even if primary to secondary leaks are detected.

H. Minimize the number of cycles of pressurizer auxiliarg spray i when the temperature differential is greater than 400 F. I l

I. In Natural Circulation, increased loop transport time causes a 5 to 10 minute delay in temperature responses to a plant change.

Pressurizer level and pressure responses, if available, typically provide better indication of RCS response during this period.

J. S/G pressure, pressurizer pressure, and containment temperature affect the level indication for the S/Gs and Pressurizer.

Attachments (8) and (9) contain the corrected S/G and pressurizer levels for various S/G pressures, pressurizer pressures, and containment temperatures.

K. If a pump or component fails, the cause of the failure should be determined prior to restarting or starting a standby pump or

{ } component to prevent a common failure.

EOP-5 R;v. 1/ Unit 2 Page 4 of 41 I I II. KNTRY CONDITIONS The presence of one or more of the following conditions indicates that a Loss of Coolant Accident may have occurred:

A. Unexplained decreasing pressurizer level.

B. Unexplained decreasing pressurizer pressure.

C. Loss of RCS subcooled margin.

D. High containment radiation alarm.

E. Increase in containment sump level.

F. Increase in containment sump alarm frequency.

EOP-5 R;v. 1/ Unit 2 Page 5 of 41 ALTERNATE ACTIONS

{ [I. BECOVERY ACTIONS A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED.

B. COMMENCE INTERMEDIATE SAFETY FUNCTION STATUS CHECK.

C. DETERMINE APPROPRIATE EMERGENCY RESPONSE ACTIONS PER THE ERPIP.

D. MONITOR RCS DEPRESSURIZATION.

1. 1F rapid depressurization 1.1 IF RCS pressure is grunter l I to 1725 PSIA, than 1725 PSIA AND SIAS NOT THEN verify SIAS actuation actuated, AND the following actions: THEN attempt leak isolation
a. All available Charging a. Shut Letdown Isolation Pumps running. Valves:
b. 21 and 23 HPSI Pumps 2-CVC-515-CV running. 2-CVC-516-CV
c. Main and Aux HPSI Header b. Shut RCS Sample Isolation Valves open: Valve, 2-PS-5464-CV.

2-SI-616-MOV 2-SI-617-MOV c. Shut Reactor Vessel Vent 2-SI-626-MOV 2-SI-627-MOV Valves:

2-SI-636-MOV 2-SI-637-MOV 2-SI-646-MOV 2-SI-647-MOV 2-RC-103-SV 2-RC-104-SV

d. Shut Pressurizer Vent Valves:

2-RC-105-SV 2-RC-106-SV l l

EOP-5 Rcy. 1/ Unit 2 Pcg2 6 cf 41

'I RECOVERY ACTION!! ALTERNATE ACTIONS

( i.

e. If PORV leakage is indicated by:

(1) High Quench Tank parameters.

(2) High PORV discharge piping temperature, computer points T107 and T108.

(3) Abnormal Acoustic Monitor indication.

THEN shut PORV Block Valves:

2-RC-403-MOV 2-RC-405-MOV

f. If leak is isolated AND SIAS NOT actuated, T M implement Reactor Trip (EOP-1) SND complete

( ) administrative post-trip actions step AC, page 35, 1.2 IE leak is NOT isolated AND RCS pressure still greater than 1725 PSIA, THEN block SIAS:

a. Open Main and Aux HPSI Header Valves:

2-SI-616-MOV 2-SI-617-MOV 2-SI-626-MOV 2-SI-627-MOV 2-SI-636-MOV 2-SI-637-MOV 2-SI-646-MOV 2-SI-647-MOV

b. Start 21 and 23 HPSI Pumps,
c. MIEN "PRSR PRESS BLOCK A(B) PERMITTED" alarm (s) received, THEN block SIAS A(B).

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EOP-5 R;v. 1/ Unit 2 Page 7 of 41 II. RECOVERY ACTIONS ALTERNATE ACTIONS E. IMPLEMENT RCP TRIP STRATEGY:

1. IF RCS pressure decreases to 1725 PSIA, THEN trip 21A and 22B RCPs QB trip 21B and 22A RCPs.
2. If positive LOCA indications exists
a. RCg subcooling less than 30 F.
b. Steady S/G pressure.
c. S/G Blowdown RMS alarms clear QB Main Vent Gaseous RMS (2-RI-5415) alarm clear.

AND RCS pressure decreases

{ ) to less than 1300 PSIA, THEN trip all RCPs.

3. IF RCS temperature and pressure are less than the minimum pump operating limits per the RCP curve on Attachment (1),

THEN trip all RCPs.

4. IF CIS has actuated, THEN trip all RCPs.

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EOP-5 R0v. 1/ Unit 2 Pcg3 8 of 41 III. RECOVERY ACTIONS ALTERNATE ACTIONS l l .

F. VERIFY BORATION IN PROGRESS:

1. 1E SIAS has actuated, 1.1 IE SIAS NOT actuated, THEN verify boration in THEN commence boration progrese:
a. Shut VCT Makeup Valve,
a. Shut VCT Makeup Valve, 2-CVC-512-CV.

2-CVC-512-CV.

b. Open Boric Acid Direct
b. Open Boric Acid Direct Makeup Valve, Makeup Valve, 2-CVC-514-MOV.

2-CVC-514-MOV. Start a Boric Acid Pump, c.

c. Boric Acid Pumps running.

,d. Start all available

d. Open BAST Gravity Feed Charging Pumps.

Valves:

1.2 IE Boric Acid Pumps NOT 2-CVC-508-MOV available, 2-CVC-509-MOV THEN establish gravity feeds

e. Shut VCT Outlet Valve, a. Open BAST Gravity Feed 2-CVC-501-MOV. Valves:

l l

f. All available Charging 2-CVC-508-MOV Pumps running. 2-CVC-509-MOV
b. Shut VCT Outlet Valve, 2-CVC-501-MOV.
c. Start all available Charging Pumps.
2. Continue boration until a total 65 inch decrease in J BAST level (s) is achieved, or shutdown margin requirements of NEOG-11 is ,

achieved.  :

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EOP-5 R;v. 1/ Unit 2 Pcq3 9 of 41 RECOVERY _ ACTIONS ALTERNATE ACT_I.OJS I.

3. IF RCS PRESSURE DECREASE 3 TO LESS THAN 225 PSIA, THEN VERIFY SAFETY INJECTION SYSTEM OPERATION:

Verify HPSI and LPSI flow to 1.1 1E 21 or 23 HPSI Pump fails,

1. THKH start 22 HP31 Pump $ND RCS per Attachments (12) and align to appropriate header.

(13).

2. Verify SI Tanks discharging to RCS cold legs.
3. Monitor contair. ment pressure per step K, page 13.
  • H. RESTORE NORMAL S/G WATER LEVEL:

- CAUTION -

Severe water hammer may occur if Main Feed Ring is allowed to drain then subsequently refilled.

IF Main Feed available, 1.1 JF Main Feed NOT available,

1. TUEN establish AFW as follows:

33pW establish a shutdown feed system lineup: - CAUTION -

a. One operating S/G Feed D/G supplying power to 23 AFW Pump. Pump flow limit is 300 GPM; One operating Condensate o the rwise , flow limit is 575 GPM.

b.

Booster Pump, Start an AFW Pump, a.

c. One operating Condensate b. Adjust AEW Flow Control Pump. Valves to maintain S/G Both Heater Drain Pumps levels between (-)170 and d.

secured. (+)30 inches.

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EOP-5 R;v. 1/ Unit 2 Pcga 10 cf 41

'II. O

}tEC_O_YERY ACTIONS bLTERNATE ACTIONS

( I

2. WHEN manual control of feed flow rate desired OR S/G 1evels between (-)24 and

(+)30 inches, THEN perform the followings

a. Depress Feed Regulating Bypass Valve Reset Buttons,
b. Adjust Feed Regulating Bypass Valves to raise S/O levels to approximately 0 inches.
3. WHEN S/G levels are 0 inches, THEN shift Feed Regulating ,

Bypass Controllers to AUTO.

I. J.F RCS PRESSURE GREATER THAN q g I kBLISH COOLDOWN IN AT LEAST ONE LOOP:

1. WITEN "SCIS A(B) BLOCK PERMITTED" alarm (s) received,

_TIG2{ block SGIS A(B) .

2. Open Turbine Bypass or Atmospheric Dump Valves as necessary to maximize RCS cooldown, while maintaining coofdownratelessthan 100 F/h.

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EOP-5 ,

R v. 1/ Unit 2 PCga 11 cf 41

'I1. BECOVERY ACTIONS bLTERNATE ACTJCMS l I

3. _Il RCPs are secured, THEN verify Natural Circulation:

- NOTE -

Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10),

a. Thot minug Tcold between 10 and 50 F.
b. Teold constant or decreasing.
c. Thot constant or ,

decreasing,

d. CET temperttures consistent with Thot.
e. Steaming rate affects primary temperature.
4. Monitor for Core and RCS voiding:

- CAR Log -

Potential for void formation increases rapidly when pressure decreases below 1500 PSIA,

a. Letdown flow greater than charging flow,
b. Rapid unexplained increase in pressurizer level during an RCS pressure reduction,
c. Loss of subcooled .nargin as determined using CET temperatures,
d. "REACTOR VE*1EL WATER LEVEL LOW" alarm.

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EOP-5 R;v. 1/ Unit 2 Pcgo 12 of 41 "II. RECOVERY ACTIONS ALTERN&TE ACTIONS I l ,

5. 1F voiding inhibits heat removal, ITDM reduce or eliminate voided area
a. Shut Letdown Isolation Valve, 2-CVC-515-CV.

- CAUTION -

The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

b. Pressurize the RCS to 5.b.1 If pressurizing the RCS does maintainsugeooling ,

NOT restore heat removal, as near 140 F as IEEE operate Reactor Vessel practical. Vent Valves per 01-1G.

- CAUTION -

If voids exist in the S/G Tubes, a rapid RCS pressure reduction I I will occur when the voids collapse,

c. IF voiding occurs in tne S/G tubes (saturation pressure of S/G greater than saturation presnure of RCS),

IIIEN cool the S/G by raising any of the follnwing:

I (1) Steaming rate.

(2) Feed rate.

(3) S/G Blowdown rate.

AND maingaining less than 100 F/h cooldown rate.

6. Continue cooldown to 300 F.

I

EOP-5 rov. 1/ Unit 2 Page 13 of 41

~TI. BECO_V_EP.Y ACTIONS ALTERNATE _ACTI_ ORS l l J. 1F RCS PRESSURE LESS THAN 1270 PSIA,

))IE VERIFY HPSI FLOW TO RCS PER ATTACHMENT (12). J.1 If 21 or 23 HPSI Pump fails, TIIEN start 22 HPSI Pump AND align to appropriate header. K. MONITOR CONTAINMENT PRESSURE:

1. JF CSAS NOT actuated, ,

THEN start all available Containment Air Coolers in HIGH with ma::imum SRW flow.

2. if containment pressure increases to 2.0 PSIG AND still increasing, q g
               'I1D'N s t a r t 21 and 22 Containment Spray Pumps and open both Catmt Spray Header CVs.

El 22 2-SI-4150-CV 2-SI-4151-CV

3. If contaiment pressure increases to 2.8 PSIG,

_TilEN verify ESFAS actuation

a. SIAS.
b. CIS AND trip all RCFs.

5O' 4. Verify SRW Pump Room E: Ventilation in service, per gf 01-15. 5. If containment pressure I increases to 4.25 PSIG, 2]DO! verif y CSAS actuation , AN9 spray flow approximately j l l 1350 GPM. l l

EOP-5 R:v. 1/ Unit 2 Pcg3 14 Cf 41 "II. KECOVERY ACTIONS ALTERNATE ACTIONS I > . L. COMMENCE ESFAS VERIFICATION CHECKLISTS:

1. SIAS Attachment (2).
2. CSAS Attachment (3).
3. CIS Attachment (4).

M. MAINTAIN RCS SUBCOOLING AND PRESSURlZER LEVEL:

1. Maintain agbcooling between 30 and 140 F using CET temperatures.
                 - CAUTION -

The potential exists for I I pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

2. Raise subcooling by any of the following:
                   - HOTE -

Pressurizer Backup Heater Banks 21 and 23 trip on U/V and SIAS.

a. Operate Pressurizer Heater (s),
b. Operate Turbine Bypass 2.b.1 IF unable to obtain desired or Atmospheric Dump cooldown rate with Turbine ,

Valves to maximize RCS Bypass and Atmospheric Dump l cooldown while Valves,  ! maintaining cooldogn THEN use steam driven AFW rate less than 100 F/h. Pump (s) to increase cooldown rate,

c. Raise HPSI flow to RCS. l l I ,

1 1 1 }

EOP-5 R;v. 1/ Unit 2 Pago 15 of 41 II. }tEQO_VERY._ACTI04S bLTERNATR_ACTIOHS

3. Lower subcooling by any of 3.1 IF unable to lower the following: subcooling, DIEN initiate Auxiliary
a. De-energize Pressurizer Spray:

lienter(s),

a. Place Instrument Air CIS
b. Lower RCS cooldown rate. Override Switch, 2-HS-2080A, in OVERRIDE.
c. IF the following conditions can be b. Open Cntmt Instrument Air maintained: Isolation MOV, 2-IA-2080-MOV.

(1) At least 30 F Record temperature subcooling, c. differential between (2) .cessurizer level Pressurizer and greater than 155 . Regenerative Heat ' inches. Exchanger Outlet. (3) At least one S/G d. Open Auxiliary Spray available for heat Valve, 2-CVC-517-CV. removal,

e. Shut Loop Charging

{ } (4) RVLMS indicates that Valves: the Core is covered. 2-CVC-518-CV THEN throttle HPSI flow 2-CVC-519-CV or operate Charging Pumps as nacessary to maintain - NOTE - subgooling between 30 and 140 F. 2-HS-2085 located on West wall of 27 ft Switchgear Room; Key 

                                                   #80 in Control Room Key Locker,
f. Open Cntmt Instrument Air Supply CV, 2-IA-2085-CV, by momentarily placing 2-IIS-2085 in OPEN.
g. Shift 2-HIC-100 to MANUAL and shut Pressurizer Spray Valves:

2-RC-100E-CV 2-RC-100F-CV

h. Maintain pressurizer cooldown rate less l I than 200 F/h.

EOP-5 R:v. 1/ Unit 2 Page 16 of 41 ALTERNA'LK ACTIONS { [I. BECOVERY ACTIONS 

                 - HOTE -

A break on top of Pressurizer will result in an uncontrollable increase in pressurizer level until Pressurizer is solid.

4. Maintain pressurizer level between 101 and 160 inches.
               - CAUTION -

Do,not throttle HPSI flow unless 30 F subcooling can be maintained.

a. If the following ,

conditions can be maintained: (1) At least 30 F subcooling. l ) (2) Pressurizer level greater than 101 - inches. (3) At least one S/G available for heat removal. (() RVLMS indicates that the core is covered. TIIEN throttle HPSI flow or operate Charving Pumps as necessary to maintain pressurizer level between 101 and 160 inches. l I

EOP-5 Rev. 1/ Unit 2 Pago 17 of 41 4 II. TECOVERY ACTIONS ALTERNATE ACTIONS

l. WHEN RCE BORATION COMPLETE, THEN SHIFT CHARGING PUMP SUCTION SUPPLY TO MAKEUP SUPPLY WITH A LOWER BORIC ACID CONCENTRATION.
1. .If SIAS actur.ted, 1.1 IF SIAS NOT actuated, TBEN perform the following: THEN lineup Charging Pump suction to VCT:
a. Open RWT To Charging Pump Suction Valve, a. Determine blend 2-CVC-504-MOV. required to maintain shutdown boron
b. Shut VCT Outlet Valve, concentration per 2-CVC-501-MOV. NEOG-11.
c. Place Boric Acid Pumps 'b. Open VCT Outlet Valve, in PULL-TO-LOCK. 2-CVC-501-MOV.
d. Ensure Charging Pump c. Secure Boric Acid Pump (s).

AMPS steady.

d. Shut Boric Acid Direct
e. Ensure BAST levels Makeup Valve, (1/'} steady. 2-CVC-514-MOV.
e. Shut BAST Gravity Feed Valves:

2-CVC-508-MOV 2-CVC-509-MOV OR lineup Charging Pump suction to RWT:

a. Open RWT To Charging Pump Suction Valve, 2-CVC-504-MOV.
b. Shut VCT Outlet Valve, 2-CVC-501-MOV.
c. Shut Boric Acid Direct Makeup Valve, 2-CVC-514-MOV. ,
d. Secure Boric Acid Pump (s),

i

EOP-5 R;v. 1/ Unit 2 Pcg3 18 of 41

II. RECOVERY ACTIONS ALTERNATE ACTIONS O. IF RWT LEVEL DECREASES TO BETWEEN O.5 AND 1.0 FT OR "ACTUATION SYS RAS TRIPPED" ALARM RECEIVED, THEN VERIFY RAS ACTUATION:
1. Place SI Pump Recirc Lockout Switches in ON.
2. Commence RAS Vorification Checklist, Attachment (6).
3. Shut RWT outlet Valves:

2-SI-4142-MOV 2-SI-4143-MOV ,

4. IF HPSI flow greater than 1000 GPM with two HPSI Pumps operating, THEN equally throttle HPSI flow to 1000 GPM.

I k 5. IF HPSI flow greater than 600 GPM with one HPSI Pump operating, 2TIEH equally throttle HPSI flow to 600 GPM. 

                  - CAUTION -

To prevent pump damage, minimum flow per operating HPSI Pump is 30 GPM.

5. 1E HPSI Pump cavitation 6.1 IF Attachment (12) does NOT occurs in recirculation mode, allow throttling HPSI flow, THEN throttle HPSI flow por THEN align Containment Spray Attachment (12). Pump (s) to HPSI Pump suction:
a. IE 23(22) HPSI Pump cavitating, 21_ LEU open 21 SDC HX To HPSI Suction Valve, 2-SI-663-MOV SND start 21 Containment Spray Pump.

l l 

                                                         . ,$P

EOP-5 Rsv. 1/ Unit 2 Pcge 19 of 41 

 'II . RECOVERY _ ACTIONS ALTERNATE ACTIONS I   I
b. IF 28 HPSI Pump cavitating, THEN open 22 SDC HX To HPSI Suction Valve, 2-SI-662-MOV AND start 22 Containment Spray Pump.
7. Cemnionce ECCS Pump Room cooling
a. Open ECCS Pump Room Air Cooler Saltwater Valves:

2-SW-5170-CV 2-SW-5171-CV 2-SW-5173-CV ,

b. Start 21 and 22 ECCS Pump Room Cooling Fans.
8. Adjust saltwater flow to maintain 3RW and component cooling temperatures.

g

9. IF Charging Pumps are aligned with suction from RWT AND HPSI Pumps maintaining RCS in<intory, THEN place Charging Pumps in PULL-TO-LOCK.

P. RESTORE CONTAINMENT ENVIRONMENT:

1. Direct Chemistry to place Hydrogen Monitors in service.
2. IF hydrogen concentration increases to 1%,

TIIEN start Hydrogen Recombiners per OI-41A.

3. Maintain Iodine Filter Fans running.

I

EOP-5 rov. 1/ Unit 2 Pcg2 20 of 41 

 'II . RECOVERY ACTIONS               ALTERNATE ACTIONS l l
4. WHEN containment pressure less than 4.0 PSIG, THEN perform the following:
a. Reset CSAS signal.
b. Secure one Containment Spray Pump.
c. Verify all Containment Air Coolers operating to maintain containment temgerature less than 120 F.
d. Restore equipment per CSAS Verification ,

Checklist, Attachment (3), to desired condition.

5. WHEN containment pressure less than 2.8 PSIG, THEN perform the following:
a. Block pressurizer pressure signals and reset SIAS signal,
b. Reset CIS signal.
c. Secure remaining Containment Spray Pump.
d. Restore equipment per SIAS and CIS Verification Checklists, Attachments (2) and (4), to desired condition.

1 1 1

EOP-5 Rov. 1/ Unit 2 Page 21 of 41 

  'I.      RECOVERY ACTIONS               ALTERNATE ACTIONS Q. EVALUATE NEED FOR HPSI TERMINATION:
1. WHEN HPSI termination criteria mets
a. At least 30 F subcooling.
b. Pressurizer level greater than 155 inches and stable.
c. At least one S/G available for heat removal. ,
d. RVLMS indicates that the Core is covered.

THEN HPSI Pump (s) may be secured. l l

2. IF HPSI termination criteria can NOT be maintair.ed, THEN start 21 and 23 HPSI Pumps.

I R. RESTORE SERVICE 5/ATER TO TURBINE BUILDING:

1. Verify 11 Plant Air Compressor operating.
2. Shut Plant Air To Plant Air Header Valve, 2-PA-2059-CV. l
3. Open Plant Air To Instrument Air Cr:ss Connect Valve, l

2-PA-2061-CV.

4. Open SRW Turbine Building Header Isolation Valves l l 2-SRW-1600-CV 2-SRW-1637-CV 2-SRW-1638-CV 2-SRW-1639-CV

EOP-5 R;v. 1/ Unit 2 POga 22 of 41

II. RECOVERY ACTIONS ALTERNATE ACTIONS I > .

S. RESTORE INSTRUMENT AIR COMPRESSORS TO SERVICE:

1. IF high temperature alarm exists on the Instrument Air Compressors, THEN open the service water isolation valves by placing their handswitches in OPEN until temperature alarm clears.

21 or 22 2-HS-2063 2-HS-2065 ,

2. Start at least one Instrument Air Compressor.

RESTORE INSTRUMENT AIR TO l I. CONTAINMENT:

1. Open Cntmt Instrument Air Isolation MOV, 2-IA-2080-MOV.
                          - NOTE -

2-HS-2085 located on West wall of 1 27 ft Switchgear Room; Key #80 in Control Room Key Locker, l

2. Open Cntmt Instrument Air  ;

Supply CV, 2-IA-2085-CV, ' by momentarily placing ) 2-HS-2085 in OPEN.  ; 1 1 1 l U. RESTORE LETDOWN FLOWS 1

1. Verify charging flow path through Loop Charging Valves or Auxiliary Spray Valve.

{ }

EOP-5 Roy- 1/ Unit 2 Pcga 23 of 41 

 'II .       RECOVERY ACTIONS               ALTERNATE ACTIONS I  k
2. Verify at least one Charging Pump operating.
3. Shift Letdown Control Valve Controller, 2-HIC-110, to MANUAL.
4. Adjust controller to shut Letdown Control Valves.
5. Open Letdown Isolation Valves:

2-CVC-515-CV 2-CVC-516-CV 

                  - CAUTION -

The setpoint of 2-PIC-2Ol must be above the saturation pressure for the letdown outlet temperature of the Regenerative Heat Exchanger.

6. Adjust the setpoint on 2-PIC-201 and adjust 2-HIC-110 I I to maintain desired pressurizer level.

V. If FORCED CIRCULATION DESIRED AND PUMP RESTART CRITERIA MET, TTH21 START RCPs:

1. IF RCPs exposed to excessive moi sture ,

THEN consider meggering RCP motor. 

                   - CAUTION -

Uncontrolled restoration of cooling to hot RCP seals may cause degradation of the metallic seating surfaces by thermal shock. l l

l l EOP-5 Rcv. 1/ Unit 2 Page 24 of 41 I ALTERNATE ACTIONS { fI. RECOVERY ACTIONS

2. IF Component Coolirg is isolated to RCP ss.ls, THEN reduce RCP lower seal temperature below 280 F prior to initiating full cooling flow to the RCPs:
a. Shut Component Cooling Supply Containment Manual Isolation Valve, 2-CC-284, located in 5 ft East Penetration Room,
b. Verify CIS reset.
c. Open Component Cooling
  • Containment Isolation Valves:

2-CC-3832-CV 2-CC-3833-CV l I d. Slowly open 2-CC-284 to throttle component cooling flow until lower seal tempergtures are less than 280 F.

e. WHEN lower seal temgeratures are less than 280 F, THEN fully open 2-CC-284.
3. IF an RCP lower seal temperature exceeded 280'F,
          'lTIEN an engineering evaluation is required prior to restarting that RCP.
4. Raise pressurizer level to at least 155 inches.
5. Verify RCP restart criteria
a. RCS subgooling greater than 30 F.
 )
b. At least one S/G

{ available for heat removal.

EOP-5 R0v. 1/ Unit 2 Paga 25 of 41 

 'I. RECOVERY ACTIONS                 ALTERNATE ACTIONS
c. Pressurizer level greater than 155 inches and stable.
d. Tcold less than 525 F.
e. RCS temperature and pressure greater than the minimum operating limits per the RCP Curve on Attachment (1).
              - NOTE -

Starting an RCP may cause a pressurizer level transient.

6. WHEN RCP restart criteria are met, THEN start one RCP in a loop with an operable S/G:
a. Verify "COMPT CLG FLOW LO" q alarm clear.
  )
b. Start Oil Lift Pump.
c. Insert RCP sync stick.

1

d. Start one RCP.

i

e. Monitor RCP running current:

Tavq Current 525 to 572 F 238 to 210 AMPS and steady 210 to 525 F 264 to 238 AMPS and steady

7. IF pressurizer level decreases, THEN start Charging or HPSI ,

Pump (s) as necessary to i restore AND maintain level greater than 155 inches.

8. Monitor RCP seal parameters l l following pump restart.

EOP-5 Rov. 1/ Unit 2 Page 26 of 41 I. RECOVERY ACTIONS ALTEPNATE ACTIONS

9. Allow backflow to equalize temperatures in opposite loop.
10. Start second RCP in opposite loop per step V.6 and V.8, page 25.
11. Secure Auxiliary Sprays
a. Open Loop Charging Valves:

2-CVC-518-CV 2-CVC-519-CV

b. Shut Auxiliary Spray ,

Valve, 2-CVC-517-CV.

c. Shift Pressurizer Spray Controller, 2-HIC-100, to AUTO.

W. WHEN RCS TEMPERATURE IS LESS THAN 300 F _A_N_D RCS PRESSUP.E IS LESS THAN 300 PSIA, THEN PERFORM THE FOLLOWING: 

                  - NOTE -

Cavity Cooling and CEDM Cooling aid in cooling Reactor Vessel Head if a void exists.

1. IF Cavity Cooling and CEDM Cooling Fans available, THEN maintain Cavity Cooling and CEDM Cooling Fans running.
2. Shut SI Tank Outlet Valves:

2-SI-614-MOV 2-SI-624-MOV 2-SI-634-MOV 2-SI-644-MOV

EOP-5 l R0v. 1/ Unit 2 Page 27 of 41 

                     'II.                          RECOVERY ACTIONS                    ALTERNATE ACTIONS l                       I
3. IF AFW NOT being used to feed S/Gs, THEN perform the following:
a. Shut the motor and steam driven train AFW Block Valves:

21 S/G 22 S/G 2-AFW-4520-CV 2-AFW-4530-CV 2-AFW-4521-CV 2-AFW-4531-CV 2-AFW-4522-CV 2-AFW-4532-CV 2-AEW-4523-CV 2-AFW-4533-CV

b. Place 23 AFW Pump in PULL-TO-LOCK. ,
c. Shut AFW Steam Supply Valves:

21 S/G 22 S/G q g 2-MS-4070-CV 2-MS-4071-CV X. vnHal RCSgTEMPERATURE IS LESS THAN 280 F _A_N_D_ RCS PRESSURE IS LESS THAN 300 PSIA, THEN ESTABLISH MPT PROTECTION: CAUTION - PORVo must be in MPT ENABLE before Tcold indication gn T115 or T125 is loan than 275 F.

1. Place both PORVs in the MPT ENABLE mode.
2. Place both PORV Override Switches in OVERRIDE CLOSED position.

l I

EOP-5 R;v. 1/ Unit 2 Pcga 28 of 41 

  'II .      RECOVERY ACTIONS                  ALTERNATE ACTIONS l   l                                                        .

0 Y. I_F CE1 SUBCOOLING LESS THAN 30 F, THEN COMMENCE CORE FLU 3H WIUiIN 24 HOURS AFTER THE SIAS ACTUATION:

1. Line up for Pressurizer 1.1 IF Pressurizer Injection Injection: HOT available AND the following conditions are
a. Open SI Discharge To met:

Charging Header Core Flush Valve, a. RCS pressura less than 2-CVC-269-MOV. 270 PSIA.

b. Shut Loop Charging b. RCS pressure minus Valves: , containment pressure less than 160 PSID.

2-CVC-518-CV 2-CVC-519-CV THEU line up for Hot Leg Injection

c. Shut Pressurizer Spray Valves: a. Place 21 or 22 LPSI Pump RAS Override I I 2-RC-100E-CV Switch in OVERRIDE.

2-RC-100F-CV

b. Open Cntmt Sump
d. Open HPSI Aux Header Discharge Valves:

Isolation Valve, 2-SI-656-MOV. 2-SI-4144-MOV 2-SI-4145-MOV

e. Open Auxiliary Spray Valve, 2-CVC-517-CV. c. Open Shutdown Cooling Heat Exchanger Recirc
f. Shut HPSI Main Header Isolation Valve, Cross Connect Vsive, 2-SI-399-MOV.

2-SI-653-MOV.

d. Shut LPSI Header Valves:
g. Shut Aux HPSI Header Valves: 2-SI-615-MOV 2-SI-625-MOV 2-SI-617-MOV 2-SI-635-MOV 2-SI-627-MOV 2-SI-645-MOV 2-SI-637-MOV 2-SI-647-MOV
h. Start 21 or 22 HPSI Pump and maintain a minimum flow of 40 GPM. 1

EOP-5 R;v. 1/ Unit 2 Page 29 of 41 ALTERNATE ACTIONS { fl. RECOVERY ACTIONS

1. IF minimum flow can e. Verify RCS pressure NOT be determined, less than 270 PSIA.

THEN initiate Hot Leg Injection. f. Open Shutdown Cooling Suction Header Isolation Valves: 2-SI-651-MOV 2-SI-652-MOV

g. Start selected LPSI Pump,
h. Maintain a minimum flow of 40 GPM.
2. WHEN Pressurizer Injection OR Hot Leg Injection in ,

progress, balance flow by throttling Main HPSI Header Valves: 2-SI-616-MOV 2-SI-626-MOV I I 2-SI-636-MOV 2-SI-646-MOV THEN maintain required flow to remove decay heat per Attachment (12).

3. Ensure CET temperatures remain constant or decreasing.

l I

EOP-5 R;v. 1/ Unit 2 Page 30 of 41 ALTERNATE ACTIONS { [I. RECOVERY ACTIONS Z. q CET TEMPERATURES LESS THAN 300 F _AN__D RADIATION LEVELS PERMIT, THEN COMMENCE SHUTDOWN COOLING.

1. IF all the following 1.1 IF pressurizer level greater conditions exist: than 101 inches AND RCS subcooling greater than 30 F,
a. Pressurizer level less THEN initiate Shutdown Cooling than 101 inches. per OI-3.
b. RCg subcooling less than 1.2 Operate HPSI and Charging 30 F. Pumps se necessary to maintain pressurizer level and
c. RCS pressure minus pressure.

containment pressure less , than 160 PSID. THEN commence Shutdown Cooling as follows:

a. Shut 21 Containment Spray I I Pump Discharge Valvo, 2-SI-314.
b. Shut 22 Containment Spray Pump Discharge Valve, 2-SI-324.
c. Shut 21 Shutdown Cooling Heat Exchanger Outlet To Spray Header Valve, 2-SI-319.
d. Shut 22 Shutdown Cooling Heat Exchanger Outlet To Spray Header Valve, 2-SI-329.
e. Open 21 Shutdown Cooling Heat Exchanger Inlet Cross Connect Valve, 2-51-452.
f. Open 21 Shutdown Cooling l Heat Exchanger Outlet To l RCS Valve, 2-SI-456. l l I l

i

EOP-5 Rav. 1/ Unit 2 Pcgo 31 of 41 II. RECOVERY ACTIONS ALTERNATE ACTIONS

g. Open 22 Shutdown Cooling ,.

Heat Exchanger Inlet Cross Connect Valve, 2-SI-453.

h. Open 22 Shutdown Cooling Heat Exchanger Outlet to RCS Valve, 2-SI-457.
1. Place second Component Cooling Heat Exchanger in service by opening appropriate Component Cooling Heat Exchanger Outlet Valves 2-CC-3824-CV 2-CC-3826-CV
j. Start second Component Cooling Pump.
k. Open 21 Shutdown Cooling Heat Exchanger Component Cooling Outlet Valve, 2-CC-3828-CV.

l

1. Open 22 Shutdown Cooling Heat Exchanger Component Cooling outlet Valve, 2-CC-3830-CV.
m. Open Shutdown Cooling Heat Exchanger Inlet Isolation, 2-SI-658-MOV.
n. If Hot Leg Injection 1.n.1 IE Hot Leg Injection NOT being used for core flush, being used for core flush, THEN shut 22B LPSI THEN open 22B LPSI Header Header Valve, 2-SI-635-MOV. Valvo, 2-SI-635-MOV.
o. Open LPSI Header Valves:

2-SI-615-MOV 2-SI-625-MOV 2-SI-645-MOV

p. Place keyewitch for l

2-SI-306-CV in AUTO.

q. Shift 2-FIC-306 to MANUAL l l I with 5% open signal.

l 1 l 

                                                                        -- j r

EOP-5 Rov. 1/ Unit 2 Page 32 of 41 

 'II . RECOVERY ACTIONS              ALTERNATE ACTIONS l  l
r. Open Cntmt Sump Discharge Valve:

2-SI-4144-MOV 2-SI-4145-MOV

s. Shut SI Pump Mini Flow Isolations:

2-SI-659-MOV 2-SI-660-MOV

t. Ensure level indication exists on wide range containment level indicator 2-LI-4146.
               - CAUTION -

The possibility of cavitation increases when taking suction from containment sump. g g u. IF LPSI Pump NOT operating, TIIEN clear RAS f rom one operable LPSI Pump by placing LPSI Pump RAS Override Switch in OVERRIDE AND start selected pump. 

                - CAUTION -

Coofdown limig changes from 100 F/h to 20 F/h gt RCS temperature of 250 F.

v. Adjust the signal on 2-FIC-306 to raise flow to 3000 GPM, while maintaining cooldown rate within limits,
w. Place keyswitch for 2-SI-657-CV in AUTO. l l

l I

EOP-5 R;v. 1/ Unit 2 Page 33 of 41 ALTERNATE ACTIONS 4 jI. RECOVERY ACTIONS 

                - CAUTION -

Do not exceed 12 F/m heatup rate or greater than 5000 GPM through one heat exchanger.

x. Adjust Shutdown Cooling Temperature Control Valve, 2-gI-657-CV, to obtain 12 F/m heatup rate at Shutdown Cooling Heat Exchanger Outlet (2-TI-303X and 2-TI-303Y).
y. IF desired RCS cooldown rate can NOT be maintained with one LPSI Pump, ,.

_THEN start second LPSI Pump AND adjust 2-FIC-306 to 6000 GPM.

z. Adjust Shutdown Cooling Temperature Control Valve, j ) 2-SI-657-CV, to obtain desired cooldown rate.

AA. WIIEN CET, TEMPERATURES LESS THAN 200 F, THEN SECURE CORE FLUSH FLOWPATH:

1. IF HPSI Pump (s) NOT required for RCS pressure ,

or level control, l THEU secure HPSI Pump (s).

2. Shut SI Discharge To Charging l

Header Core Flush Valve, 2-CVC-269-MOV. , i

3. Open Loop Charging Valves: ,

1 2-CVC-518-CV 2-CVC-519-CV l

4. Shut Auxiliary Spray Valve, g

2-CVC-517-CV. { 1

EOP-5 rov. 1/ Unit 2 Page 34 of 41 II. RECOVERY ACTIONS ALTERNATE ACTIONS

5. Shut Shutdown Cooling Heat Exchanger Recirc Isolation, 2-SI-399-MOV.
6. Open 22B LPSI Header Valve, 2-SI-635-MOV.

AB. COMPLETE ADMINISTRATIVE POST-TRIP ACTIONS AND IMPLEMENT APPROPRIATE OPERATING PROCEDURE. l l l i 1

EOP-5 RCV. 1/ Unit 2 Page 35 of 41 l l AC. ADMINISTRATIVE POST-TRIP ACTIONS: 

                                       - NOTE -

The following actions may be accomplished whenever feasible. They may be done in any order.

1. Refer to ERPIP to determine appropriate emergency response actions.
2. Perform notifications per CCI-118.
3. Notify ESO of trip.
4. Request RCS Boron and Iodine sample, i
5. Perform shutdown margin calculation per NEOG 9 and 11.

l 6. Complete transient log entries por CCI-301. , l l l } l

7. Recall post-trip review (preferably within 30 i

minutes of trip). , 1

8. Perform post-trip review per CCI-111. f
9. Monitor turbine bearing temperatures.
10. Continue Main Turbine shutdown por applicable step of OI-43A. )

END OF SECTION III. 1 e l

EOP-5 Rcv. 1/ Unit 2 Page 36 of 41 l I IV. SAFETY FUNCTION STATUS CHECK A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to exiting from this procedure. B. Perform intermediate safety function status check at 10 minute intervals until plant conditions stabilize. C. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied. D. Review data and verify that safety function acceptance criteria are satisfied. E. When EOP completed, then perform final safety function check. i REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK I l

c. WRNI power less than 3% __________

less than 1% negative O

b. SUR (DPM) _,___,____
c. CEA status all inserted __________

all inserted or Boration status: appropriate concentation increasing __________ S/D margin BAST level decreasing __________ N/A N/A l I

EOP-5 RCv. 1/ Unit 2 Paga 37 of 41 I I RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND INVENTORY FINAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA CHECK CHECK

c. Prosaurizer pressure (PSIA) less than 1900 __________

less than 1900

b. Pressurizer 0 to 160 level (inches) (1) O to 160 __________

greater than

c. RgS subcooling O to 140 30

( F) ,_________ (1) A break at top of Pressurizer will result in solid pressurizer indication. This is an acceptable value provided the other parameters still indicate a LOCA. I I i l l l l l l l l

EOP-5 R v. 1/ Unit 2 Page 38 of 41 l I CORE AND RCS SAFETY EUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK 

 =
0. CET ( F) less than 700 ________

less than 500 b.TgotminusTcold 10 to 50 ( F) (2) 10 to 50 ________

c. S/G pressure N/A (FSIA) 150 to 900 ____,___

N/A

d. S/G level (-)170 to ,

(-)24 to (inches) (+)30 ________ (+)30

o. Cold Leg greater greater Injection (GPM) than 40 ___,,,,_

than 40

f. Condensate Storage Tank greater greater

{ g than 5 level (ft) than 5 ________

g. Core flush established within 24 greater greater hours (GPM) than 40 ________

than 40 (2) Thot and Tcold indication may be influenced by charging or SI temperatures during a large break LOCA. If this occurs Thot minus Tcold may be deleted from the check provided CET temperatures meet their acceptance criteria. l l

EOP-5 R;v. 1/ Unit 2 Pega 39 of 41 l I VITAL SAFETY FUNCTION ACCEPTANCE CRITERIA AUXILIARIES CRITERIA FINAL CRITERIA INTERMEDIATE CHECK CHECK

c. 4KV vital buses energized 21 or 24 energized ________,,

greater greater

b. Instrument Air than 88 pressure (PSIG) than 88 __________
c. Component Cooling

(# Pumps running) 1 or 2 __________ 1 or 2

d. Saltwater

(# Pumps running) 1 or 2 __________ 1 or 2

o. Service Water

(# pumps running) 1 or 2 ________,, 1 or 2 g g f. 125V DC buses 11, 12, 21, 22 energized ______,,,_ energized

g. 120V AC vital buses 21, 22, 23, 24 energized __________

energized

EOP-5 R3v. 1/ Unit 2 Page 40 cf 41 l I NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT CRITERIA INTERMEDIATE CRI'lERI A FINAL ENVIRONMENT CHECK PARAMETERS CHECK

c. Containment pressure (PSIG) less than 50 ________

less than 2.8 _

b. Containment tgmperature less than 220

( F) less than 276 ________

c. Containment High Range ,

Radiation alarm alarm Monitor clear clear

d. Hydrogen concentration N/A ___ N[^ __

less than 2% I I I I >

EOP-5 Rcv. 1/ Unit 2 Page 41 of 41 l I NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL FINAL TO CONTAINMENT CRITERIA INTERMEDIATE CRITERIA CHECK CHECK

a. Noble Gas Monitor alarm alarm clear __________

clear

b. Condenser Off-Gas alarm alarm RMS clear _,________

clear alarm alarm

c. S/G B/D RMS clear clear _______,__
d. Main Vent Gaseous alarm alarm clear clear RMS (2-RI-5415) __________

STATUS CHECK COMPLETE AT NUMBER TIME ( ) 1 2 3 4 . l I

EOP-6 RCv. 1/ Unit 1 Pcga 1 of 37 l k CALVERT CLIFFS HUCLEAR POWER PIANT EOP-6 STEAM GENERATOR TUBE RUPTURE REVISION 1 SIGNATURE DATE { l PREPARED BY; g- j g / / L [rS [8 7 y m  %

A

md 1-VERIFI Q 

                                                       /
                                         )Q POSRC;       MEETING #    SG ~\                   /7-\O 92 APPROVED BY;    hd        A m.w_                  / 2.-\o - 9 #3 Ma.rfagerYNuclear Operations or General Supervisor-Operatione if POSRC review is not required

EOP-6 P.cv. 1/ Unit 1 Tcga 2 of 37 l I , LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 , 1 13 1 14 1 15 3 16 1 17 1 18 1 19 1 { l 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 28 1 29 1 30 1 31 1 32 1 33 1 34 1 35 1 36 1 37 1 l I

EOP-6 R3v. 1/ Unit 1 Page 3 of 37 l l STEAM GENERATOR TUBE RUPTURE I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function. B. Systems shifted to manual must be monitored frequently to insure correct operation. C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments. l l D. If the damaged S/G has been isolEted and the cooldown is i proceeding via Natural Circulation, an inverted temperature l differential may be observed in the idle loop. This condition I will have no effect on natural circulation flow in the intact 1 S/G. l !{ g E. Minimize the number of cycles of pressurizer auxiliarg spray ' I when the temperature differential is greater than 400 F. l l F. If a pump or component fails, the cause of the failure should be j j determined prior to restarting or starting a standby pump or j component to prevent a common failure. l l II. ElmtY CONDITIONS The presence of one or more of the following co.2ditions indicates that a Steam Generator Tube Rupture may have occurred: l A. Unexplained decrease in VCT level er pressurizer level. B. Condenser Off-Gas RMS alarm. C. S/G Blowdown RMS alarm. D. Main Stoann Line RMS alarm. E. Main Vent RMS alarm. F. Decreasing pressurizer pressure. l I

EOP-6 R;v. 1/ Unit 1 Pega 4 et 37 

     'II . RECOV8RY ACTIONS                                                                  ALTERNATE ACTIONS I

A. VERIFY POST-TRIP IMMEDI ATE ACTIONS COMPLETED. l B. COMMENCE IN'I'ERMEDI ATE SAFETY FUNCTION STATUS CHECK. C. DETERMINE APPROPRIATE EMERGENCY REGPONSE ACTIONS PER THE ERPIP. j ._ 1 . 4 D. MONITOR RCS DEPRESSURIZATION. I 1. IF rapid depressurization 1.1 IF RCS pressure is greater l to 1725 PSIA, than 1725 PSIA AND SIAS NOT 4 g actuated, THEN verify SIAS actuation AND the following actions: THEN block SIAS:

a. All available Charging a. Open Main and Aux Pumps running. HPSI Header Valves:
b. 11 and 13 HP3I Pumps 1-SI-616-MOV 1-SI-617-MOV running. 1-SI-626-MOV 1-SI-627-MOV 1-SI-636-MOV 1-SI-637-MOV
c. Main and Aux HPSI Header 1-SI-646-MOV 1-SI-647-MOV Valves open:
b. Start 11 and 13 1-SI-616-MOV 1-SI-617-MOV HPSI Pumps.

1-SI-626-MOV 1-SI-627-MOV 1-SI-636-MOV 1-SI-637-MOV c. WUEN "PRSR PRESS 1-SI-646-MOV 1-SI-647-MOV BLOCK A(B) PERMITTED" alarm (s) received, THEU block SIAS A(B). Il i A- - - - _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ . _

EOP-6 RCV. 1/ Unit 1 PCg3 5 of 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS I I . E. IMPLEMENT RCP TRIP STRATEGY:

1. 1F RCS pressure decreases to 1725 PSIA, THEN trip 11A and 12B RCPs 9B trip 11B and 12A RCPs.
2. 1[ positive LOCA indications exi.< t s
a. RCg subcooling less than 30 F.
b. Steady S/G prossure.
c. S/G Blowdown RMS alarms clear 9R Main Vent Gaseous RMS (1-RI-5415) alarm clear.

AND RCS pressure decreases to less than 1300 PSIA, I I THEN trip all RCPs.

3. IF RCS temperature and pressure are less than the minimum pump operating limits per the RCP curve on Attachment (1),

THEN trip all RCPs.

4. 1F CIS has actuated, THEN trip all RCPs.

l I

EOP-6 R;v. 1/ Unit 1 Paga 6 of 37 

  'II. RECOVERY ACTIONS                       ALTERNATE ACTIONS l  I                                                     s F. DEPRESSURIZE RCS TO MAINTAIN SUBCOOLINO BETWEEN 25 AND 35 F AND PRESSURIZER LEVEL BETWEEN 101 AND 160 INCHES:
1. Shift 1-HIC-100 to MANUAL 1.1 IF Pressurizer Spray and open Pressurizer Spray Velves NOT effective, Valve, on leg with THEN 1.11tiate Auxiliary operating RCP, as Spray:

necessary to maintain sugeooling between 25 and a. Record temperature 35 F. differential between Pressurizer and Regenerative Heat s Exchanger Outlet.

b. Open Auxiliary Spray Valve, 1-CVC-517-CV.
c. Shut Loop Charging Valves:

I I 1-CVC-518-CV 1-CVC-519-CV

d. Shift 1-HIC-100 to MANUAL and shut Pressurizer Spray Valves:

1-RC-100E-CV 1-RC-100F-CV

2. HIIEN RCS pressure less than 1270 PSIA, THEN verify HPSI flow per Attachment (12). l 1

l I l l l l l l

EOP-6 Rcv. 1/ Unit 1 Page 7 of 37

II. _ RECOVERY ACTIONS ALTERNATE ACTIONS l I
3. IF the following conditions exists
a. At least 25 F subcooling,
b. Pressurizer level greater than 101 inches.
c. At least one S/G available for heat removal.
d. RVLMS indicates that the Core is covered.

THEN throttle HPSI flow to maintain pressurizer level between 101 and 160 inches. ,

4. IF RCS subcooling less than 25 F in an operating S/G loop, THEN raise RCS subcooling using one or more of the following actions:

l I a. Shut Pressurizer Spray Valves. 

                - NOTE -

Pressurizer Backup Heater Banks 11 and 13 trip on U/V and SIAS.

b. Energize Pressurizer Heaters,
c. Raise RCS cooldown rate.
5. IF 35,RCS F in subcooling greater an operating than S/G loop, THEN lower RCS subcooling using one or more of the following actions:
a. De-energize Pressurizer Heaters,
b. Operate Pressurizer Spray 5.b.1 Initiate Auxiliary Spray Valve on leg with per step F.1.1, page 6.

operating RCP.

c. Lower RCS cooldown rate.

EOP-6 R v. 1/ Unit 1 Pcg] 8 of 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I G. COMMENCE RCg COOLDOWN TO LOWER Thot TO 515 F:

1. MHEN "SGIS A(B) BLOCK 1.1 If SGIS actuates, PERMITTED" alarm (s) received, THEN reset SGIS:

THEN block SGIS A(B).

a. Place Condensate Booster Pumps in PULL-TO-LOCK.
b. Match handswitches per SGIS Verification Checklist, Attachment (7).
c. Block SGIS.
                                             'd. Roset SGIS signal.
e. Open MSIVs.
2. Commence cooldown to 515 F 2.1 If Turbine Bypass Valves by throttling Turbine Bypass NOT available, Valves, while g maintaining THEN throttle Atmospheric Dump l I less than 100 F/h RCS Valves to commence cooldown.

cooldown rate. 2.2 Record total time Atmospheric Dump Valve open, for dose calculations, prior to identifying and isolating affected S/G.

3. if Turbine Bypass Valves available, THEN ensure Atmospheric Dump Valves are shut.

l I

EOP-6 R;v. 1/ Unit 1 Page 9 of 37 

  'II. _ RECOVERY ACTIONS                     _ ALTERNATE ACTIONS H. VERIFY BORATION IN PROGRESS:
1. IF SIAS has actuated, 1.1 IF SIAS NOT actuated, RIEN verify boration in RIEN commence borations progress:
a. Shut VCT Makeup Valve,
a. Shut VCT Makeup Valve, 1-CVC-512-CV.

1 - N'C - 512 - u v' .

b. Open Boric Acid
b. Open Boric Acid Direct Direct Makeup Valve, Makeup Valve, 1-CVC-514-MOV.

1-CVC-514-MOV.

c. Start a Boric Acid Pump.
c. Boric Acid Pumps running.
                                              ,d. Start all available
d. Open BAST Gravity Feed Charging Pumps.

Valves: 1.2 IF Boric Acid Pumps 1-CVC-508-MOV HOT available, 1-CVC-509-MOV TIIEN establish gravity feeds

e. Shut VCT Outlet Valve, a. Open BAST Gravity Feed I I 1 - CVC - 5 0,1. - MOV . Valves
f. All available Charging 1-CVC-508-MOV Pumps running. 1-CVC-509-MOV
b. Shut VCT Outlet Valve, 1-CVC-501-MOV.
c. Start all available Charging Pumps.
2. Continue boration until a total 65 inch decrease in BAST level (s) is achieved, or shutdown margin requirement of NEOG-7 is achieved.

l l l > 1 1 l

EOP-6 ) R;v. 1/ Unit 1 1 Page 10 of 37  ! 

   'II. RECOVERY _ ACTIONS                ALTERNATE _ ACTIONS l    l s

I. IDENTIFY AND CONFIRM AFFECTED S/G:

1. Attempt to identify affected S/G by comparing the following trends:
a. Mismatch in feed flow prior to trip.
b. Unexplained increase in S/G level prior to trip.
c. Main Steam Line RMS.
d. Post-trip S/G level .,

changes,

e. S/G samples.
2. Shut S/G Blowdown Valves:

1-BD-4010-CV I I 1-BD-4011-CV 1-BD-4012-CV 1-BD-4013-CV

3. Shut AEW Steam Supply Valves by placing handswitches in CLOSE:

1-MS-4070-CV 1-MS-4071-CV

4. Secure Main Feed eyetem:
a. Trip S/G Feed Pumps,
n. Place Condannate Booster Pumps in PULL-TO-LOCK.
c. Place 2 of the 3 Condensate Pumps in PULL-TO-LOCK.
d. Secure Heater Drain Pumps.

l I

EOP-6 l Rcv. 1/ Unit 1 ! Pcga 11 cf 37 l l ALTERNATE ACTIONS I II. RECOVERY SCTIONS l

e. Shut S/G Feedwater Isolation Valves:

1-FW-4516-MOV 1-FW-4517-MOV

f. Shut Hotwell To CST Dump CV by shifting 1-LIC-4405 to tiANUAL with 50% output.
5. IF affected S/G HQT identified,

_TgEN perform the followings

a. Shut motor driven train AFW Block Valves on both S/Gs:

11 S/G 12 S/G 1-AFW-4522-CV 1-AFW-4532-CV 1-AFW-4523-CV 1-AEW-4533-CV

b. Monitor S/G levels to q g determine affected S/G.
c. Direct Chemistry to sample S/Gs.
d. Direct Rad Con to perform a radiological survey of main steam lines.
6. NUEH affected S/G identified QR if it is determined that both S/Gs are affected, QR if either S/G level decreases to -170 inches, THEN feed unaffected or least affected S/G per step J, page 12.

l I

EOP-6 R;v. 1/ Unit 1 Page 12 of 37 ( I. RECOVERY ACTIONS ALTERNATE ACTIONS l J. FEED UNAFFECTED S/G.

1. Establish AFW flow to 1.1 IF 13 AFW Pump HOT available, unaffected S/G using THEN establish AFW flow 13 AFW Pumps to unaffected S/G using 11 or 12 AFW Pumps
a. For the affected S/G, shut the motor driven train a. For the affected S/G, shut AFW Block Valves: the steam driven train AFW Block Valves:

11 S/G or 12 S/G 11 S/G or 12 S/G 1-AFW-4522-CV 1-AFW-4532-CV 1-AFW-4523-CV 1-AFW-4533-CV 1-AFW-4520-CV 1-AFW-4530-CV 

                                                 ,1-AFW-4521-CV       1-AFW-4531-CV
b. For the unaffected S/G, place the motor driven b. For the unaffected S/G, train AFW Block Valve place the steam driven Handswitches in OPEN. train AFW Block Valve Handswitches in OPEN.
                - CAUTION -

D/G aupplying power to 13 AFW Pump flow limit is 300 GPM; The following step could result otherwise, flow limit is 575 GPM. in an unmonitored radiation release if performed improperly,

c. Start 13 AFW Pump,
c. For the unaffected S/G,
d. Adjust AFW Flow Control open the AFW Steam Supply Valve on unaf; acted S/G Valve.

to maintain S/G level or 12 S/G between (-)24 and 11 S/G (+)30 inches. 1-MS-4070-CV 1-MS-4071-CV 11 S/G or 12 S/G

d. Verify 11 or 12 AFW Pump 1-AFW-4525-CV 1-AFW-4535-CV discharge pressure approximately 100 PSI greater than unaffected S/G pressure,
e. Adjust AFW Flow Control Valve on unaffected S/G to maintain S/G level between (-)24 and (+)30 inches.

I I 11 S/G or 12 S/G 1-AFW-4511-CV 1-AFW-4512-CV

EOP-6 R;v. 1/ Unit 1 Page 13 of 37 lII. RECOVERY ACTIONS ALTERNATE ACTIONS l l K. WHEN Thot DECREASES TO 515 F, THEN ISOLATE AFFECTED S/G:

1. For the affected S/G, shut the MSIV.
2. For the affected S/G, shut S/G Feedwater Isolation Valve.

11 S/G or 12 S/G 1-FW-4516-MOV 1-FW-4517-MOV

3. For the affected S/G, shut the AEW Flow Control Valves: ,

11 S/G or 12 S/G 1-AFW-4511-CV 1-AFW-4512-CV 1-AFW-4525-CV 1-AFW-4535-CV 4 For the affected S/G, shut l l the motor and steam driven train AFW Block Valvos: 11 S/G or 12 S/G 1-AFW-4520-CV 1-AEW-4530-CV 1-AFW-4521-CV 1-AFW-4531-CV 1-AFW-4522-CV 1-AFW-4532-CV 1-AFW-4523-CV 1-AFW-4533-CV

5. For the affected S/G, shut the AEW Steam Supply Valve.

11 S/G or 12 S/G 1-MS-4070-CV 1-MS-4071-CV

6. For the affected S/G, shut the 6.1 IF Atmospheric Dump Valve Atmospheric Dump Valve using will NOT shut from IC43, the Hand Transfer Valves on THEN shut Atmospheric Dump the West wall of the Unit 1 Manual Isolation Valve. l 45 ft Switchgear Room:

11 S/G or 12 S/G

a. Verify IC43 Atmospheric Dump controllers at 0% 1-MS-101 1-MS-104 >

q ) output. l I l

EoP-6 R3v. 1/ Unit 1 Page 14 of 37 q fl. RECOVERY ACTIONS ALTERNATE ACTIONS

b. Align Hand Transfer Valves to IC43 position:

11 S/G or 12 S/G 1-HV-3938A 1-HV-3939A 1-HV-39383 1-HV-3939B

7. Shut MSIV Bypass Valves:

1-MS-4045-MOV 1-MS-4052-MOV

8. Shut S/G Blowdown Valves:

1-BD-4010-CV 1-BD-4011-CV , 1-BD-4012-CV 1-BD-4013-CV

9. Shut upstream drains by placing handswitch 1-HS-6622 in CLOSE.

{ I

10. Verify locally, from the Auxiliary Building Roof, that S/G Safety Valves are shut.
11. If wrong S/G was isolated, 21n2!unicolate that S/G AND isolate proper S/G.
12. Maintain affected S/G level less than (+)30 inches and S/G pressure less than 900 PSIA per step W, page 25.

I I

EOP-6 RCv. 1/ Unit 1 Page 15 of 37

II. RECOVERY ACTIONS ALTERNATE ACTIONS I I L. IF RCPs SECURED, THEN CONFIRM NATURAL CIRCULATION IN UNAFFECTED S/G LOOP:
                     - HOTE -

Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10).

1. ThotmgnusTcoldbetween10 and 50 F.
2. Teold constant or decreasing.
3. Thot constant or decreasing.
4. CET temperatures consistent with Thot.
5. Steaming rate affects primary temperature.

M. MONITOR FOR CORE AND RCS VOIDING: 

                  - CAUTION -

Potential for void formation increases rapidly when pressure decreases below 1500 PSIA.

1. Letdown flow greater than charging flow.
2. Rapid unexplained increase in pressurizer level during an RCS pressure reduction.
3. Loss of subcooled margin as determined using CET temperatures, i
4. "REACTOR VESSEL WATER LEVEL LOW" alarm, i I

l l

EOP-6 R;v. 1/ Unit 1 PCg3 16 of 37 

  'II .      RECOVE'tY ACTIONS                      Af, TERNATE ACTIONS I   >                                                       ,

N. II VOIDING INHIBITS HEAT REMOVAL, TIIEN REDUCE OR ELIMINATE VOIDED AREA:

1. Shut Letdown Isolation Valve, 1-CVC-515-CV.
                  - CAUTION -

The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

2. Pressurize the RCS to 2.1 ,IF pressurizing the RCS does NOT restore heat removal, maigtain subcooling as near THEN operate Reactor Vessel 140 F as practical.

Vent Valves per 01-1G. 

                  - CAUTION -

If voids exist in the S/G tubes, a rapid RCS pressure reduction I k will occur when the voids collapse.

3. II voiding occurs in the S/G tubes (saturation pressure of S/G greater than saturation pressure of RCS),

DIEN cool the S/G by raising any of the following

a. Steaming rate,
b. Feed rate.
c. S/G Blowdown rate.

6ND maintaining less than l I 100 F/h cooldown rate. I I I I , 1

EOP-6 R v. 1/ Unit 1 Page 17 of 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS i I O. WHEN AFFECTED S/G IS ISOLATED, THEN CONTINUE RCS COOLDOWN A?O DEPRESSURIZATION:

1. Continue cooldown by 1.1 If Turbine Bypass Valves throttling Turbine Bypass NOT available, Valves, whileg maintaining IHEN throttle Atmospheric less than 100 F/h RCS Dump Valve on unaffected S/G cooldown rate, to continue RCS cooldown.

1.2 IF unable to obtain desired cooldown rate, TIIEN start 11 or 12 AFW Pump per step J.1.1, page 12.

2. Depressurice RCS to maintain RCS pressure approximately equal to affected S/G pressure.
               - CAUTION -

l l An RCS prennure decreases below 900 PSIA, NPSH requirements for the RCPs may require RCS sugcoolingtobegreaterthan 35 F.

3. hDUQ! RCS pressure decreases belov 900 PSIA, TlIEN perform the following:
a. Ensure RCP NPSH requirements are maintained per Attachment (1).
b. Maintain subcooling as ,

low as the RCP operating curve will allow. l1

c. Evaluate starting a l second RCP, in desired loop per step V., page 22; secure RCP in opposite loop to allow a lower j

minimum RCS pressure. ,

EOP-6 RCv. 1/ Unit 1 Paga 18 of 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS l l

4. Maintain affected S/G pressure and level per step W, page 25.
5. Direct Chemistry and Rad con to perform periodic samples for the following
a. RCS boron and activity.
b. Both S/Gs for activity and boron,
c. Turbine Building Sumps for setivity,
d. Condensate and CSTs for .

activity,

e. Air samples and radiation surveys throughout plant to determine the spread of contamination.

P. WJ1EN RCS BORATION COMPLETE, TIIEN SHIFT CilARGING PUMP SUCTION SUPPLY TO MAKEUP SUPPLY WITH A LOWER BORIC ACID CONCENTRATION.

1. IF SIAS actuated, 1.1 IF SIAS NOT actuated, THEN perform the following: THEN line up Charging Pump nuction to VCT:
a. Open RWT To Charging Pump Suction Valve, n. Determine blend 1-CVC-504-MOV. required to maintain shutdown boron
b. Shut VCT Outlet Valve, concentration per 1-CVC-501-MOV. NEOG-7.
c. Place Boric Acid Pumps in b. Open VCT Outlet Valve, PULL-TO-LOCK. 1-CVC-501-MOV.
d. Ensure Charging Pump AMPS c. Secure Boric Acid steady. Pump (s),
e. Ensure BAST levels d. Shut Bo'ric Acid Direct steady. Makeup Valse,

( ) 1-CVC-514-MOV. 1

EOP-6 R;v. 1/ Unit 1 Pcg3 19 cf 37 

 'II . RECOVERY ACTIONS                 AI, TERNATE ACTIONS l  l
e. Shut BAST Gravity Feed Valves:

1-CVC-508-MOV 1-CVC-509-MOV OB line up Charging Pump cuction to RWT:

a. Open RWT To Charging Pump Suction Valve, 1-CVC-504-MOV.
b. Shut VCT Outlet Valve, 1-CVC-501-MOV.
                                        ,c. Shut Boric Acid Direct Makeup Valve, 1-CVC-514-MOV.
d. Secure Boric Acid Pump (s).
  ,. IF SIAS ACTUATED, TIIEN RESET SI AS:
1. Perform SIAS Verification Checklist, Attachment (2).
2. Block pressuricer pressure signals and reset SIAS signal.
3. Restore equipment per SIAS Verification Checklist, Attachment (2), to desired condition.

l l R. RESTORE SERVICE WATER TO TURBINE BUILDING:

1. Verify 21 Plant Air Compressor operating.

i j ) 2. Shut Plant Air To Plant Air Header Valve, 1-PA-2059-CV. f l l

EOP-6 ROV. 1/ Unit 1 Pcg3 20 cf 37 II. RECOVERY ACTIONS ALTERNATE ACTIONS l l

3. Open Plant Air To Instrument Air Cross Connect Valve, 1-PA-2061-CV.
4. Open SRW Turbine Building Header Isolation Valves:

1-SRW-1600-CV 1-SRW-1637-CV 1-SRW-1638-CV 1-SRW-1639-CV l l l S. RESTORE INSTRUMENT AIR COMPRESSORS TO SERVICE: i

1. If high temperature alarm exists on the Instrument Air Compressors, THDj open the service water isolation valves by placing g g their handswitches in OPEN until temperature alarm clears.

l 11 or 12 i 1-HS-2063 1-HS-2065

2. Start at least one Instrument Air Compressor.

l l T. *0,40RE INSTRUMENT AIR TO l CONTAINMENT: l l 1. Open Cntmt Instrument i Air Isolation MOV, l l 1-IA-2080-MOV. 1 1 l b \ l l I l_ _ _ _ _ _ _ _ .

EOP-6 R';v. 1/ Unit 1 i Page 21 of 37 i II. RECOVERY ACTIONS bLE RNATE_ ACTIONS \< - t -m-1-HS-2085 located on West wall of 27 ft Switchgear Room; Key 

        #85 in Control Room Key Locker.
2. Open Cntmt Instrument Air Supply CV, 1-IA-2085-CV, by momentarily placing 1-HS-2085 in OPEN.

U. RESTORE LETDOWN FLOW

1. Verify charging flowpath through Loop charging Valves ,

or Auxiliary Spray Valve.

2. Verify at least one Charging Pump operating.
3. Shift Letdown Control Valve Controller, 1-HIC-110, to I MANUAL.
4. Adjust controller to shut Letdown Control Valves.
5. Open Letdown Isolation Valves:

1-CVC-515-CV 1-CVC-516-CV 

                    - CAUTION -

The setpoint of 1-PIC-201 must be above the saturation pressure for the letdown outlet temperature of the Regenerative Heat Exchanger.

6. Adjust the setpoint on 1-PIC-201 and adjust 1-HIC-110 to maintain desired pressurizer level.

1 l l . I

EOP-6 R;v. 1/ Unit 1 Page 22 of 37 

    'II .       _ RECOVERY ACTIONS                             ALTERNATE ACTIONS l    I V. IF P. cps WERE SECURED AND RCP RESTART CRITERIA MET, THEN RESTORE Rv5 FORCED CIRCULATION:
                      - CAUTION -

Uncontrolled restoration of cooling to hot RCP seals may cause degradation of the metallic seating surfaces by thermal shock,

1. IF Component Cooling is isolated to RCP seals, .

THEN reduce RCP lower seal

  • temperature below 280 F prior to initiating full cooling flow to the RCPs:
a. Shut Component Cooling Supply Containment I I Manual Isolation Valve, 1-CC-284, located in 5 ft East Penetration Room.
b. Verify CIS reset,
c. Open Component Cooling Containment Isolation valves:

1-CC-3832-CV l-CC-3833-CV

d. Slowly open 1-CC-284 to throttle component cooling flow until lower seal temperatgree are less than 280 F.
e. W

_IJEN lower seal temperatgres are less than 280 F, THEN fully open 1-CC-284. l I

EOP-6 R;v. 1/ Unit 1 Page 23 of 37 

 'II. RECOVERY ACTIONS                              ALTK_RNA_TE ACTIONS l I s
2. IF an RCP lower seal temperature exceeded 280 F, THEN an engineering evaluation is required prior to restarting that RCP.
3. Raise pressurizer level to at least 155 inches.
4. Verify RCP restart criteria:
a. RCS subgooling greater than 30 F.
b. At least one S/G available for heat removal.
c. Pressurizer level greater than 155 inches and stable,
d. Tcold less than 525 F.

j g e. RCS temperature and pressure greater than the minimum operating limite per the RCP curve on Attachment (1). 

              - H9TE -

Starting an RCP may cause a pressurizer level transient.

5. Wi!EN RCP restart criteria met, IDEN start one RCP in a loop with an operable S/G:
a. Verify "COMPT CLG FLOW LO" alarm clear,
b. Start Oil Lift Pump.
c. Insert RCP sync ctick,
d. Start one RC 1

3 8 i i l l 1 _ L . .. . . . l 

                                           -_ ~

1

EOP-6 R;v. 1/ Unit 1 Page 24 of 37 III. RECOVERY ACTIONS 6LTERNATE_ ACTIONS l I

e. Verify RCP running current:

Tava Qurrellt 525 to 572 F 238 to 210 AMPS and steady 210 to 525 F 264 to 238 AMPS and steady

6. If pressurizer level decreases, THEN start Charging or HPS!

Pump (s) as necessary to restore AND maintain level greater than 155 inches.

7. Monitor RCP seal parameters following pump restart.
8. Allow backflow to equalize temperatures in opposite loop.
9. Start second RCP in opposite l I loop per steps V.5 and V.7, pages 23 and 24.
10. Secure Auxiliary Spray:
a. Open Loop Charging Valves:

1-CVC-518-CV l-CVC-519-CV

b. Shut Auxiliary Spray Valve, 1-CVC-517-CV.
c. Shift Pressurizer Spray controller, 1-HIC-100, to AUTO.

i i l i l i 1 1

EOP-6 R;v. 1/ Unit 1 Page 25 of 37 II. RECOVERLAC. T IONS ALTERNATE A(TIONS W. PRESSURE AND LEVEL CONTROL OF AFFECTED S/G: 

                 - HOIE -

The following methode for controlling affected S/G pressure and level are listed in preferred order and should be attenipted in that order.

1. Maintain affected S/G pressure approximately equal to RCS pressure and S/G level between (-)24 and (+)30 ,

inches by:

a. Steaming S/G to Condenser per step W.2, page 2!.
b. S/G Blowdown to Condenser

{ por step W.3, page 27. 

   }
c. S/G Blowdown to MWS per step W.4, page 29.
d. Steaming S/G to atmosphere per step W.5, page 31.
e. Filling S/G to MSIV per step W 6, page 32,
2. Pressure and level control of affected S/G by steaming to Condenser:
a. Ensure condenser vacuum greater than 20 IN Hg.
b. Ennure at least one Condensate Domin in service,
c. Open Condensate Precoat Filter Bypass Valve, 1-CD-5818-CV.

1 I d. Shut Condensate Demin Bypass Valve, 1-CD-4439-MOV.

EOP-6 R;v. 1/ Unit 1 Page 26 of 37 II. BECOVERY ACTIONS ALTERNA_TE ACTIONS

e. Throttle open Feedwater Dump To Condenser Hotwell Valves, 1-FW-134 and 1-FW-135, to obtain maximum condensate flow through Condensate Domin,
f. Shut Condenser High Level Dump CV Inlet Valve, 1-CD-232.
                   - NOTE -

Maintaining S/G 1evel above top of tube bundle provides a large decontamination factor due to the water covering the break. ,

g. Maintain affected S/G 1evel between (-)24 and

(+)30 inches by operating AEW. j g h. Operate upstream drains using 1-HS-6622 as necessary to control affected S/G pressure. 

                 - CAUTION -

Do not operate MSIV Bypass Valve on a S/G whose level exceeded (+)63.5 inches.

1. JF additional steam flow desired, TIIEN operate MSIV Bypass Valve on affected S/G.

11 S/G or 12 S/G 1-MS-4045-MOV 1-MS-4052-MOV l l

EOP-6 R v. 1/ Unit 1 Page 27 of 37 III. BECOVERY__ ACTIONS 2.LJEldnTE ACTIONS l I

3. Pressure and level control of affected S/G by blowdown to Condenser
a. Ensure at least one Condensate Demin in service,
b. Open Condensate Precoat Filter Bypass Valve, 1-CD-5818-CV.
c. Shut Condensate Domin Bypass Valve, 1-CD-4439-MOV.
d. Throttle open Feedwater .

Dump To Condenser Hotwell Valves, 1-FW-134 and 1-FW-135, to obtain maximum condensate flow through Condensate Demin,

e. Shut Condenser High Level l l Dump CV Inlet Valve, 1-CD-232.
f. Place S/G Blowdown Recovery System Radiation Monitor, 1-RE-4095, in RESET.
g. Shut B/D Recovery Discharge To MWS, 1-BD-4097-CV.
h. Shut B/D Recovery Discharge To Cire Water, 1-BD-4015-C"
i. Open B/D Recovery To Condenser, 1-BD-4096-CV.
j. Shut S/G Combined B/D Header Throttle Valves:

1-BD-102 1-BD-104 i > i l i 

                                                                           )

EOP-6 R^v. 1/ Unit 1 PC;3 28 cf 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS I I 

                                                /
k. Open the affected S/G Bottom Blowdown Valve by placing handswitch in RAD TRIP OVERRIDE.

11 S/G or 12 S/G 1-BD-4011-CV 1-BD-4013-CV

1. Throttle open S/G Combined B/D Header Throttle Valve on affected S/G to obtain a blowdown flow of approximately 100 GPM.

11_SE or 12__SE , 1-BD-102 1-BD-104

m. Throttle SRW flow to 12 Blowdown Heat Exchanger to maintain a blowdown discharge temperatuge

{ l between 105 and 115 F using 12 B/D Heat Exchanger Discharge Valve, 1-SRW-522. 

                  - MOTE -

Maintaining S/G 1evel above top of tube bundle provides a large decontamination factor due to the water covering the break.

n. Alternately lower and i raise affected S/G  ;

level by: (1) S/G Blowdown to  ! Condenser to (-)24 l inches. (2) Operating AFW to (+)30 inches. l 1 I

E0P-6 R;v. 1/ Unit 1 Page 29 of 37 II. RECOVERY ACTIONS ALTERNATE ACTIOMS i

4. Pressure and level control of sffected S/G by blowdown to MWS
a. Place S/G Blowdown Recovery System Radiation Monitor, 1-RE-4095, in PULSE CAL and bypass its alarm.
b. Open B/D Recovery Discharge To MWS, 1-BD-4097-CV.
c. Shut B/D Recovery Discharge To Cire .

Water, 1-BD-4015-CV.

d. Shut B/D Recovery To Condenser, 1-BD-4096-CV.
e. Shut S/G Combined B/D

{ } Header Throttle Valves 1-BD-102 1-BD-104

f. Open the affected S/G Bottom Blowdown Valve by placing handswitch in RAD TRIP OVERRIDE.

11 SZG or 12 S/G l 1-BD-4011-CV 1-BD-4013-CV

g. Throttle open S/d Combined B/D Headar Throttle Valve on affected S/G to obtain a blowdown flow of approximately 100 GPM, 11 S/G or 12 S/G 1-BD-102 1-BD-104 i I

EOP-6 R:v. 1/ Unit 1 Page 30 of 37 

 't II . EECOVER_Y ACTIONS               bLTERt/LTE_ ACTION!!

I I

h. Throttle SRW flow to 12 Blowdown Heat Exchanger to maintain a blowdown discharge temperatuge between 105 and 115 F using 12 B/D Heat Exchanger Discharge Valve, 1-SRW-522,
i. Pump MWRT to RCWMT per OI-17D.
j. Monitor MWRT level at IC33.
k. Throttle S/0 blowdown rate to maintain a
  • constant level in MWRT while pumping to RCWMT.
                  - HOTE -

Maintaining S/0 level above top of tube bundle provides a large l I decontamination factor due to the water covering the break.

1. Alternately lower and raise affected S/G 1evel by:

(1) S/0 Blowdown to MWS to (-)24 inches. (2) Operating AFW to (+)30 inches. 1 I i

EOP-6 R;v. 1/ Unit 1 Page 31 of 37 II. RECOVERY _ ACTIONS bhTERNATE ACTIONS 

                                 - CAUTION -

Do not operate Atmospheric Dump Valve on a S/G whose level exceeded (+)63.5 inches.

5. Pressure and level control of  !.1 1E Atmospheric Dump was affected S/G by steaming to previously isolated, atmosphere from IC43: THEN throttle open Atmospherte Dump Manual
a. Establish communications Isolation Valve as at 1C43. directed by Control Room Personnel to control affected
b. Verify IC43 Atmospher' S/G pressure.

Dump Controllers at r output. _11 S/G or 12_R49

c. Verify Hand Transfer 'l-MS-101 1-MS-104 Valves for affected S/G are selected to 1C43 5.2 Maintain affected S/G level position between (-)24 and (+)30 inches by operating ArW.

11 S.ZG or 12 S/G { } 5.3 Record total time Atmospheric 1-HV-3938A 1-HV-3939A Dump Valve open, for dose 1-HV-3938B 1-HV-3939B calculations. 

                                   - NOTE -

Maintaining S/G level above top of tube bundle provides a large decontamination factor due to the water covering the break,

d. Maintain affected S/G 1evel betvien (-)24 and (+)30 inches by operating AFW.
e. Adjust Atmospheric Dump from IC43 as directed by Control Room Personnel to control affected S/G pressure,
f. Record total time Atmospheric Dump Valve open, for dose calculations.
                                                                                ~

r EOP-6 R;v. 1/ Unit 1 Page 32 of 37 II. RECOVERY ACTIONS ALTERNATE ACTIONS

6. Affected S/G may be allowed to fill to MSIV provided the following conditions are maintained:
a. RCS pressure below 900 PSIA.
b. MSIVs, Atmospheric Dump Valves and MSIV Bypass Valves remain shut.

X. CO../LETE ADMINISTRATIVE POST-TRIP ACTIONS AND IMPLEMENT APPROPRIATE OPERATING PROCEDURE. . 1 l l 4 I L _ _ _ _ - - _ - - - - -

EOP-6 Rav. 1/ Unit 1 Page 33 of 37 I I I Y. ADMINISTRATIVE POST-TRIP ACTIONS: ( - NOTE - The following actions may be accomplished whenever feasible. They may be done in any order.

1. Refer to ERPIP to determine appropriate emergency response actions.
2. Perform notifications per CCI-118.
3. Notify ESO of trip.
4. Request RCS Boron and Iodine sample.
5. Perform shutdown margin calculation per NEOG 2 and 7.
6. Complete transient log entries per CCI-301.

{ l 7. Recall post-trip review (preferably within 30 minutes of trip).

8. Perform post-trip review per CCI-111.
9. Monitor turbine bearing temperatures.
10. Continue Main Turbine shutdown per applicable step of OI-43A.

END OF SECTION III. i I l l t ---

EOP-6 Rcv. 1/ Unit 1 Pcga 34 of 37 k l IV. SAFETY FUNCTION STATUS CHECK A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to exiting from this procedure. B. Perform intermediate safety function status check at 10 minute intervals until plant conditions stabilize. C. Immediately notifv Chift Supervisor or Control Room Supervisor if any safety funct.+. ' ariteria is not being satisfied. D. Review data and verify that safety function acceptance critoria are satisfied. .. E. When EOP completed, then perform final safety function check. REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL PARAMETERS CRITERIA INTERMEDIATE CRITERIA EINAL CHECK CHECK l I

a. WRNI power less than 3% less than 1%
b. SUR (DPM) negative 0
c. CEA status all inserted all inserted or Boration status:

appropriate , concentation increasing ________,_ S/D margin BAST level decreasing __________ N/A N/A l I l t

EOP-6 R v. 1/ Unit 1 Page 35 of 37 l I RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND INVENTORY PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. Pressurizer greater pressure (PSIA) 300 to 1900 __________

than 300

b. Pressurizer level (inches) O to 200 __________

101 to 160

c. RCS subcooling ( F) 25 to 140 __________ 25 to 140 CORE AND RCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK l I
a. RCS Tcold ( F) less than 535 ________ 300 to 515 b.TgotminusTcold

( F) Natural Circulation 10 to 50 ________ 10 to 50 Forced Circulation less than 10 ________ less than 10

c. Affected S/G less than less than pressure (PSIA) 920 ________ 900
d. Affected S/G less than less than level (Jnches) (+)30 ________ (+)30
e. Unaffected S/G pressure (PSIA) 70 to 920 ________ 70 to 730
f. Unaffected S/G (-)l70 to (-)24 to l

level (inches) (+)30 ____,,,, (+)30

g. Condensato Storage Tank greater greater level (ft) than 5 ________ than 5 l I l

L

EOP-6 R;v. 1/ Unit 1 Pcg3 36 of 37 A > \ 

                                                              .                                           4 VITAL                        SAFETY FUNCTION ACCEPTANCE CRITERIA AUXILIARIES CRITERIA       INTERMEDIATE         CRITERIA                           FINAL CHECK                                      CHECK
c. 4KV vital buses 11 or 14 energized __________

energized

b. Instrument Air creater greater pressure (PSIG) chsn 88 ______,___

than 88

c. Component Cooling

(# pumpa running) 1 or 2 __________ 1 or 2 _

d. Saltwater

(# Pumps running) 1 or 2 __________ 1 or 2

c. Service Water

(# Pumps running) 1 or 2 ,,_________ 1 or 2

f. 125V DC buses

{ ) 11, 12, 21, 22 energized energized

g. 120V AC vital buses 11, 12, 13, 14 energized energized NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT ENVIRONMENT CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK
c. Containment pressure (PSIG) less than 0.7 less than 0.7
b. Containment tgmperature

( F) less than 120 ________ less than 120

c. Containment High Range Radiation alarm alarm Monitor clear clear

EOP-6 R;v. 1/ Unit 1 Page 37 of 37 I I NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL TO CONTAINMENT CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK alarm

c. Noble Gas Monitor (1) alarming __________

clear

b. Condenser off-Gas (1) alarm RMS alarming __________

clear alarm

c. S/G B/D RMS (1) alarming __________

clear

d. Main Vent Gaseous (1) alarm RMS (1-RI-5415) alarming __________

clear (1) RMS alarms are break size and RCS activity dependent. d I STATUS CHECK COMPLETE AT NUMBER TIME 1 2 3 4 I i 1 l l l l l 1 l

EOP-6 Rcv. 1/ Unit 2 Pcg2 1 of 37 I I . CALVERT CLIFFS NUCLEAR POWER PLANT EOP-6 STEAM GENERATOR TUBE RUPTURE REVISION 1 

                                                                  "^"
                      . vN%               C l l PREP        ,       -A ~ '
                                                        / l1-        -

lD ) / / L //65 /F > VERIFIED BY; Mht4L JA#W 

                   >                                                                1 POSRC;        MEETING # 99 -l                        / 1'LC-93                   i l

APPROVED BY; hN Lww / 2- t o-9% M/ndge"r-Nuclear Operations or General Supervisor-Operations if POSRC review is not required O

EOP-6 RCv. 1, Unit 2 Pcga 2 of 37 l l ~ LIST OF EFFECTIVE PAGES ' PAGE NUMBER REVISION 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 , 1 13 - 1 14 1 15 1 16 1 17 1 18 1 19 1 { } 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 28 1 29 1 30 1 31 1 32 1 33 1 34 1 35 1 36 1 37 1 i I

EOP-6 Rov. 1/ Unit 2 Pcga 3 of 37 I I STEAM GENERATOR TUBE RUPTURE I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems uninss a malfunction is apparent or automatic system operation will not support the maintenance of a safety function. B. Systems shifted to manual must be monitored frequently to ensure correct operation. C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition eince an incident could induce inconsistencies between instruments. 

                                                ~

D. If the damaged S/G has been isolated and the cooldown is proceeding via Natural Circulation, an inverted temperature differential may be observed in the idle loop. This condition will have no effect on natural circulation flow in the intact S/G.

  • E. Minimize the number of cycles of pressurizer auxiliarg spray I l when the temperature differential is greater than 400 F.

F. If a pump or component fails, the cause of the failure should be determined prior to restarting or starting a standby pump or component to prevent a common failure. II. ENTRY CONDITIONS The presence of one or more of the following conditions indicates that a Steam Generator Tube Rupture may have occurred: A. Unexplained decrease in VCT level or pressurizer level. B. Condenser Off-Gaa RMS alarm. C. S/G Blowdown RMS alerm. D. Main Steam Line PMS alcrm. E. Main Vent RMS alarm. E. Decreasing pressurizer pressure. I I

EOP-6 Rcv. 1/ Unit 2 Pcga 4 of 37 III. RECOVERY ACTIO'A' ALTERNATE ACTIONS ( ) . A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED. B. COMMENCE INTERMEDIATE SAFETY FUNCTION STATUS CHECK. C. DETERMINE APPROPRIATE EMERGENCY RESPONSE ACTIONS PER THE ERPIP. D. MONITOR RCS DEPRESSURIZATION.

1. IF rapid depressurization 1.1 IF RCS pressure is greater to 1725 PSIA, than 1725 PSIA AND SIAS NOT THEN verify SIAS actuation actuated, l f AND the following actions: THEN block SIAS:
a. All available Charging a. Open Main and Aux Pumps running. HPSI Header Valves:
b. 21 and 23 HPSI Pumps 2-SI-616-MOV 2-SI-617-MOV running. 2-SI-626-MOV 2-SI-627-MOV 2-SI-636-MOV 2-SI-637-MOV
c. Main and Aux HPSI Header 2-SI-646-MOV 2-SI-647-MOV Valves open:
b. Start 21 and 23 2-SI-616-MOV 2-SI-617-MOV HPSI Pumps.

2-SI-626-MOV 2-SI-627-MOV 2-SI-637-MOV H[IEN "PRSR PRESS l 2-SI-636-MOV c. 2-SI-646-MOV 2-SI-647-MOV BLOCK A(B) PERMITTED" alarm (s) received, i TIIEN block SI AS A(B) . l l 1 l I l l l l

EOP-6 Rav. 1/ Unit 2 Pcg2 5 of 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I E. IMPLEMENT RCP TRIP STRATEGY:

1. If RCS pressure decreases to 1725 PSIA, THEN trip 21A and 22B RCPs 9R trip 21B and 22A RCPs.
2. IF positive LOCA indications exists
a. RCg subcooling less than 30 F.
b. Steady S/G pressure,
c. S/G Blowdown RMS alarms clear 9R Main Vent Gaseous RMS (2-RI-5415) alarm clear.

r AND RCS pressure decreases to less than 1300 PSIA, h THEN trip all RCPs.

3. If RCS temperature and pressure are less than the minimum pump operating limits per the RCP curve on Attachment (1),

TIIEN trip all RCPs.

4. If CIS has actuated, THEN trip all RCPs.

I I

EOP-6 Rov. 1/ Unit 2 Pcg3 6 of 37

II. RECOVERY ACTIONS ALTERNATE ACTIONS i I F. DEPRESSURIZE RCS TO MAINTAIN#

SUBCOOLING BETWEEN 25 AND 35 F AND PRESSURIZER LEVEL BETWEEN 101 AND 160 INCHES:

1. Shift 2-HIC-100 to MANUAL 1.1 IF Pressurizer Spray and open Pressurizer Spray Valves NOT effective, Valve, on leg with THEN initiate Auxiliary operating RCP, as Spray:

necessary to maintain sugcooling between 25 and a. Record temperature 35 F. differential between Pressurizer and Regenerative Heat Exchanger Outlet.

b. Open Auxiliary Spray Valve, 2-CVC-517-CV.
c. Shut Loop Charging Valves:

l l 2-CVC-518-CV 2-CVC-519-CV

d. Shift 2-HIC-100 to MANUAL and shut Pressurizer Spray Valves:

2-RC-100E-CV 2-RC-100F-CV

2. WIIEN RCS pressure less than 1270 PSIA,

_THEN verify HPSI flow per Attachment (12). ( I >

EOP-6 R;v. 1/ Unit 2 Pcg3 7 of 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS l l I ..

3. IF the following conditions exists
a. At least 25 F subcooling.
b. Pressurizer level greater than 101 inches.
c. At least one S/G available for heat removal,
d. RVLMS indicates that the Core is covered.

THEN throttle HPSI flow to maintain pressurizer level between 101 and 160 inches. .,

4. IF RCS subcooling less than 25o F in an operating S/G loop, THEN raise RCS subcooling using one or more of the following actions:

l l a. Shut Pressurizer Spray Valves. 

                   - NOTE -

Pressurizer Backup Heater Banks 21 and 23 trip on U/V and SIAS.

b. Energize Pressurizer Heaters.
c. Raise RCS cooldown rate.
5. IFg RCS subcooling greater than 35 F in an operating S/G loop, THEN lower RCS subcooling using one or more of the following actions:
a. De-energize Pressurizer Heaters.
b. Operate Pressurizer Spray 5.b.1 Initiate Auxiliary Spray Valve on leg with por stop F.1.1, page 6.

operating RCP. l I

c. Lower RCS cooldown rate.

EOP-6 Rov. 1/ Unit 2 Page 8 of 37 I. RECOVERY ACTIONS ALTERNATE ACTIONS G. COMMENCE RCg COOLDOWN TO LOWER Thot TO 515 F: 1.1 IF SGIS actuates, 

 ;       1. WHEN "SGIS A(B) BLOCK PERMITTED" alarm (s) received,      THEN reset SGIS:

THEN block SGIS A(B).

a. Place Condensate Booster Pumps in PULL-TO-LOCK.
b. Match handswitches per SGIS Verification Checklist, Attachment (7).
c. Block SGIS.
                                                'd. Reset SGIS signal,
e. Open MSIVs.
2. Commence cooldown to 515 F 2.1 IF Turbine Bypass Valves by throttling Turbine Bypass NOT available, Valves, while THEN throttle Atmospheric Dump

{ } less than 100, F/h maintaining RCS Valves to commence cooldown. cooldown rate. 2.2 Record total time Atmospheric Dump Valve open, for dose calculations, prior to identifying and isolating affected S/G.

3. IF Turbine Bypass Valves available, THEN ensure Atmospheric Dump Valves are shut.

l I

EOP-6 R v. 1/ Unit 2 PCga 9 of 37 

  'II . RECOVERY ACTIONS                         ALTERNATE ACTIONS l   I H. VERIFY BORATION IN PROGRESS:
1. IF SIAS has actuated, 1.1 IF SIAS NOT actuated, THEN verify boration in THEN commence boration:  !

progress:

a. Shut VCT Makeup Valve,
a. Shut VCT Makeup Valve, 2-CVC-512-CV.

2-CVC-512-CV.

b. Open Boric Acid ,
b. Open Boric Acid Direct Direct Makeup Valve, 1 Makeup Valve, 2-CVC-514-MOV.

2-CVC-514-MOV.

c. Start a Boric Acid Pump. l
c. Boric Acid Pumps running.
d. Start all available
d. Open BAST Gravity Feed Charging Pumps.

Valves: 1.2 IF Boric Acid Pumps i 2-CVC-508-MOV NOT available, l 2-CVC-509-MOV THEN establish gravity feeds

e. Shut VCT Outlet Valve, a. Open BAST Gravity Feed j I

l I 2-CVC-501-NOV. Valvas:

f. All avaia.able Charging 2-CVC-508-MOV Pumps running. 2-CVC-509-MOV
b. Shut VCT Outlet Valve.

2-CVC-501-MOV.

c. Start all available Charging Pumps.

1

2. Continue boration until a l total 65 inch decrease in BAST level (s) is achieved, or shutdown margin requirement of NEOG-11 is achieved.

l I

EOP-6 Rcv. 1/ Unit 2 Pcga 10 of 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS l k - I. IDENTIFY AND CONFIRM AFFECTED S/G:

1. Attempt to identify affected S/G by comparing the following trends:
a. Mismatch in feed flow prior to trip.
b. Unexplained increase in S/G level prior to trip.
c. Main Steam Line RMF.
d. Post-trip S/G 1evel ,

changes.

e. S/G samples.
2. Shut S/G Blowdown Valves:

2-BD-4010-CV l l 2-BD-4011-CV 2-BD-4012-CV 2-BD-4013-CV

3. Shut AFW Steam Supply Valves by placing handswitches in CLOSE:

2-MS-4070-CV 2-MS-4071-CV

4. Secure Main Feed systems
a. Trip S/G Feed Pumps.
b. Place Condensate Booster Pumps in PULL-TO-LOCK.
c. Place 2 of the 3 Condensate Pumps in PULL-TO-LOCK.
d. Secure Heater Drain Pumps.

l I

EOP-6 Rav. 1/ Unit 2 Pcgo 11 of 37 

 'II. RECOVERY ACTIONS                 ALTERNATE ACTIONS l  I
e. Shut S/G Feedwater Isolation Valves:

2-FW-4516-MOV 2-FW-4517-MOV

f. Shut Hotwell To CST Dump CV by shifting 2-LIC-4405 to MANUAL with 50% output.
5. IF affected S/G NOT identified, THEN perform the following:
a. Shut motor driven train AFW Block Valves on both S/Gs 21 S/G 22 S/G 2-AFW-4522-CV 2-AFW-4532-CV 2-AFW-4523-CV 2-AFW-4533-CV
b. Monitor S/G levels to determine affected S/G.
c. Direct Chemistry to sample S/Gs.
d. Direct Rad Con to perform a radiological survey of main steam lines.

1

6. M!EN affected S/G identified QR if it is determined that both S/Gs are at'fected, QR if either S/G level decreases to -170 inches, THEN feed unaffected or least affected S/G per step J, page 12.

l I

EOP-6 R v. 1/ Unit 2 Pcg3 12 of 37 

    'I. RECOVERY ACTIONS                           ALTERNATE ACTIONS l    I J. FEED UNAFFECTED S/G.
1. Establish AFW flow to 1.1 IF 23 AEW Pump NOT available, unaffected S/G using THEN establish AFW flow 23 AFW Pumps to unaffected S/G using 21 or 22 AFW Pumps
a. For the affected S/G, shut the motor driven train a. For the affected S/G, shut AFW Block Valves: the steam driven train AEW Block Valves:

21 S/G or 22 S/G 21 S/G or 22 S/G 2-AFW-4522-CV 2-AEW-4532-CV 2-AFW-4523-CV 2-AFW-4533-CV 2-AFW-4520-CV 2-AFW-4530-CV 

                                                  ,2-AFW-4521-CV       2-AFW-4531-CV
b. For the unaffected S/G, place the motor driven b. For the unaffected S/G, train AFW Block Valve place the steam driven Handswitches in OPEN, train AEW Block Valve Handswitches in OPEN.
                 - CAUTION -

D/G supplying power to 23 AFW Pump flow limit in 300 GPM; The following step could result o the rwi se , flow limit is 575 GPM. in an unmonitored radiation release if performed improperly.

c. Start 23 AFW Pump,
c. For the unaffected S/G,
d. Adjust AFW Flow Control open the AFW Steam Supply Valve on unaffected S/G Valve, to maintain S/G level 22 S/G between (-)24 and 21_S/G or

(+)30 inches. 2-MS-4070-CV 2-MS-4071-CV 21 S/G or 22 S/G <

d. Verify 21 or 22 AFW Pump l 2-AFW-4525-CV 2-AFW-4535-CV discharge pressure approximately 100 PSI I

greater than unaffected S/G pressure. l

e. Adjust AFW Flow Control l Valve on unaffected S/G I to maintain S/G level l between (-)24 and (+)30 l inches, k l 21 S/G or 22 S/G 2-AFW-4511-CV 2-AFW-4512-CV

{ l l m

EOP-6 Rcv. 1/ Unit 2 Pcg] 13 of 37 III. RECOVERY ACTIONS A_LTERNATE ACTIONS ( l . K. WIIEN Thot DECREASES TO 515 F, THEN ISOLATE AFFECTED S/G:

1. For the affected S/G, shut the MSIV.
2. For the affected S/G, shut S/G Feedwater Isolation Valve.

21 S/G or 22 S/G 2-FW-4516-MOV 2-FW-4517-MOV

3. For the affected S/G, shut the AFW Flow Control Valves: .,

21 S/G or 22 S/G 2-AFW-4511-CV 2-AFW-4512-CV l 2-AFW-4525-CV 2-AFW-4535-CV l

4. For the affected S/G, shut l I the motor and steam driven 1 train AFW Block Valves:

I 21 S/G or 22 S/G 2-AFW-4520-CV 2-AFW-4530-CV 2-AFW-4521-CV 2-AEW-4531-CV l 2-AFW-4522-CV 2-AFW-4532-CV 2-AEW-4523-CV 2-AFW-4533-CV

5. For the affected S/G, shut the AFW Steam Supply Valvo.

21 S/g or 22_S/G 2-MS-4070-CV 2-MS-4071-CV

6. For the affected S/G, shut the 6.1 IF Atmospheric Dump Valve Atmospheric Dump Valve using will NQI shut from 2C43, the Hand Transfer Valves on TIIEU shut Atmospheric Dump the West wall of the Unit 2 Manual Isolation Valve.

45 ft Switchgear Room: 21_S/G or 12 S/Q

a. Verify 2C43 Atmospheric Dump controllers at 0% 2-MS 101 2-MS-104 output.

{ }

EOP-6 R;v. 1/ Unit 2 Pcga 14 of 37 

 'II . RECOVERY ACTIONS                   ALTERNATE ACTIONS l  l
b. Align Hand Transfer Valves to 2C43 position:

21 S/G or 22_S/G 2-HV-3939A 2-HV-3938A 2-lW-3939B 2 -lW-3 93 8B

7. Shut MSIV Bypass Valves:

2-MS-4045-MOV 2-MS-4052-MOV

8. Shut S/G Blowdown Valves:

2-BD-4010-CV 2-BD-4011-CV ., 2-BD-4012-CV 2-BD-4013-CV

9. Shut upstream drains by placing handswitch 2-HS-6622 in CLOSE.

I I 10. Verify locally, from the Auxiliary Building Roof, that S/G Safety Valves are shut.

11. IF wrong S/G was isolated, J]pRJ unisolate that S/G mfd isolate proper S/G.
12. Maintain affected S/G 1evel less than (+)30 inches and S/G pressure less than 900 PSIA per step W, page 25.

l I

EOP-6 RCv. 1/ Unit 2 Pcga 15 of 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS I k .. L. IF RCPs SECURED, THEN CONFIRM NATURAL CIRCULATION IN UNAFFECTED S/G LOOP: 

                                                  - NOTE -

Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10).

1. Thot mfnus Tcold between 10 and 50 F.
2. Tcold constant or decreasing.
3. Thot constant or decreasing.
4. CET temperatures consistent with Thot.
5. Steaming rate affects primary
 ,           temperature.

1 I M. MONITOR FOR CORE AND RCS VOIDING: 

                                               - CAUTION -
        ?otential for void forration increason rapidly when pressure decreanen below 1500 PSIA.
1. Letdown flow greater than charging flow.
2. Rapid unexplained increase in pressurizer level during an RCS pressure reduction.
3. Loss of subcooled margin as determined using CET temperatures.
4. "REACTOR VESSEL WATER LEVEL LOW" alarm.

l I

EOP-6 RCv. 1/ Unit 2 Pcg3 16 cf 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS i > . N. IF VOIDING INHIBITS HEAT REMOVAL, THEN REDUCE OR ELIMINATE VOIDED AREA:

1. Shut Letdown Isolation Valve, 2-CVC-515-CV.
                - CAUTION -

The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

2. Pressurize the RCS to 2.1 .IE pressurizing the RCS does NOT restore heat removal, maigtain iubcooling as near THEU operate Reactor Vessel 140 F as practical.

Vent Valves per 01-10. 

                - CAUTION -

If voids exist in the S/G tubes, a rapid RCS pressuro reduction l I will occur when the voids collapse.

3. If voiding occurs in the S/G tubes (saturation pressure of S/G greater than saturation pressure of RCS),

T LIEN cool the S/G by raising any of the following:

a. Steaming rate.
b. Feed rate,
c. S/G Blowdown rate.

AND maintaining less than 100 F/h cooldown rate.

EOP-6 Rcv. 1/ Unit 2 Pcg3 17 of 37 I. RECOVERY ACTIONS ALTERNATE ACTIONS O. WHEN AFFECTED S/G IS ISOLATED, THEN CONTINUE RCS COOLDOWN AND DEPRESSURIZATION:

1. Continue cooldown by 1.1 IF Turbine Bypass Valves throttling Turbine Bypass NOT available, Valves, while maintaining THEN throttle Atmospheric n Dump Valve on unaffected S/G less than 100 F/h RCS cooldown rate. to continue RCS cooldown.

1.2 IF unable to obtain desired cooldown rate, TIIEN start 21 or 22 AFW Pump per step J.1.1, page 12.

2. Depressurize RCS to maintain RCS pressure approximately equal to affected S/G pressure.
                 - CAUTION -

I I As RCS preneure decreason below 900 PSIA, NPSH requirements for the RCPo may require RCS nugcooling to be greater than 35 F.

3. WHEN RCS pressure decreases below 900 PSIA, THEN perform the following:
a. Ensure RCP NPSH requirements are maintained per Attachment (1),
b. Maintain subcooling as low as the RCP operating curve will allow,
c. Evaluate starting a second RCP, in desired loop per step V., page 22; secure RCP in opposite loop to allow a lower minimum RCS pressure.

l EOP-6 R v. 1/ Unit 2 Page 18 of 37 t I. RECOVERY ACTIONS ALTERNATE ACTIONS

4. Maintain affected S/G pressure and level per step W, page 25.
5. Direct Chemistry and Rad Con to perform periodic samples for the following:
a. RCS boron and activity,
b. Both S/Gs for activity and boron.
c. Turbine Building Sumps for activity.
d. Condensate and CSTs for ,

activity.

e. Air samples and radiation surveys throughout plant to determine the spread of contamination.

l I P. HIIEN RCS BORATION COMPLETE, TIIEU SHIFT CHARGING PUMP SUCTION SUPPLY TO MAKEUP SUPPLY WITH A LOWER BORIC ACID CONCENTRATION.

1. IF SIAS actuated, 1.1 I_F SIAS NOT actuated, T!IEN perform the following: DUni line up Charging Pump suction to VCT:
a. Open RWT To Charging Pump Suction Valvo, a. Determine blend 2-CVC-504-MOV. required to maintain shutdown boron
b. Shut VCT Outlet Valve, concentration per 2-CVC-501-MOV. NEOG-il.
c. Place Boric Acid Pumps in b. Open VCT Outlet Valvo, PULL-TO-LOCK. 2-CVC-501-MOV.
d. Ensure Charging Pump AMPS c. Secure Boric Acid steady. Pump (s),
c. Ensure BAST levels d. Shut Boric Acid Direct '

I I steady. Makeup Valve, 2-CVC-514-MOV.

EOP-6 R:v. 1/ Unit 2 Pcg] 19 cf 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I l

e. Shut BAST Gravity Feed l I

Valves: 2-CVC-508-MOV 2-CVC-509-MOV OR line up Charging Pump suction to RWT:

a. Open RWT To Charging Pump Suction Valve, 2-CVC-504-MOV.
b. Shut VCT outlet Valve, 2-CVC-501-MOV.
                                        .c. Shut Boric Acid Direct Makeup Valve, 2-CVC-514-MOV.
d. Secure Boric Acid Pump (s).

I  !. IF SIAS ACTUATED, TIIEN RESET SI AS:

1. Perform SIAS Vorification Checklist, Attachment (2).
2. Block pressurizer pressure signals and reset SIAS signal.
3. Restore equipment per SIAS Verification Checklist, Attachment (2), to desired condition.

R. RESTORE SERVICE WATER TO TURBINE BUILDING:

1. Verify 11 Plant Air Compressor operating.

{ }

2. Shut Plant Air To Plant Air Header Valvo, 2-PA-2059-CV.

EOP-6 . R;v. 1/ Unit 2 P g3 20 of 37 

             'II .      RECOVERY ACTIONS              ALTERNATE ACTIONS I    I
3. Open Plant Air To Instrument Air Cross Connect Valve, 2-PA-2061-CV.
4. Open SRW Turbine Building Header Isolation Valves:

2-SRW-1600-CV 2-SRW-1637-CV 2-SRW-1638-CV 2-SRW-1639-CV S. RESTORE INSTRUMENT AIR COMPRESSORS TO SERVICE:

1. IF high temperature alarm exists on the Instrument Air Compressors, THEN open the service water isolation valves by placing their handswitches in OPEN I I until temperature alarm clears.

21 or 22 2-HS-2063 2-HS-2065

2. Start at least one Instrument Air Compressor.

T. RESTORE INSTRUMENT AIR TO CONTAINMENT:

1. Open Cntmt Instrument Air Isolation MOV, 2-IA-2080-MOV.

I I

EOP-6 RCv. 1/ Unit 2 Page 21 of 37 I. RECOVERY ACTIONS ALTERNATE ACTIONS _ NOTE _ 2-HS-2085 located on West wall of 27 ft Switchgear Room; Key 

              #80 in Control Room Key Locker.
2. Open Cntmt Instrument Air Supply CV, 2-IA-2085-CV, by momentarily placing 2-HS-2085 in OPEN.

U. RESTORE LETDOWN FLOW:

l. Verify charging flowpsth through Loop Charging Valves ,

or Auxiliary Spray Valve.

2. Verify at least one Charging Pump operating.
3. Shift Letdown Control Valve Controller, 2-HIC-110, to

{ } , MANUAL.

4. Adjust controller to shut Letdown Control Valves.
5. Open Letdown Isolation Valves:

2-CVC-515-CV 2-CVC-516-CV 

                        - CAUTION -

The notpoint of 2-PIC-2Ol munt be above the naturation pronouro for the letdown outlet temperature of the Regenerative Ileat Exchanger.

6. Adjust the setpoint on 2-PIC-201 and adjust 2-HIC-110 to maintain

desired pressurizer level. i I

i EOP-6 Rcv. 1/ Unit 2 Pcg3 22 of 37 II. RECOVERY ACTIONS ALTERNATE ACTIONS 

   /. IF RCPs WERE SECURED AND RCP RESTART CRITERIA MET, THEN RESTORE RCS FORCED CIRCULATION:
                 - CAUTION -

Uncontrolled restoration of cooling to hot RCP seals may cause degradation of the metalle seating surfaces by thermal shock.

1. IF Component Cooling is isolated to RCP seals, ,

TIIEN reduce RCP Ic,wer seal n temperature below 280 F prior to initiating full cooling flow to the RCPs:

a. Shut Component Cooling Supply Containment I I Manual Isolation Valve, 2-CC-284, located in 5 ft East Penetration Room.
b. Verify CIC reset.
c. Open Component Cooling Containment Isolation Valves:

2-CC-3832-CV 2-CC-3833-CV

d. Slowly open 2-CC-284 to throttle component cooling flow until lower seal temperatgres are less than 280 F.
e. tillEN lower seal temperatgres are less than 280 F, JJDOJ fully open 2-CC-284.

l I

R;v. 1/ Unit 2 Pcgr

  • 1 of 37
    'II .      RECOVERY A7FIONS                   ALTERNATE ACTIONS I  h                                                 ..
2. IF an RCP lower seal temperature exceeded 280 F,

_TIIEU an engineering evaluation is required prior to restarting that RCP.

3. Raise pressurizer level to at least 155 inchos.
4. Verify RCP restart criteria:
a. RCS subgooling greater than 30 E.
b. At least one S/G available for heat removal.
c. Pressurizer level greater than 155 inches and stable.

5

d. Teold less than 525 F.
e. RCS temperature and l I pressure greater than the minimum operating limits per the RCP curve on Attachment (1).
                    - NOTE -

Starting an RCP may cause a pressurizer level transient.

5. hgD23 RCP restart criteria met,

_TIIEN start ene RCP in a loop with an operable S/G:

a. Verify "COMPT CLG ELOW LO" alarm elesr.
b. Start Oil Lift Pump.
c. Insert RCP sync stick.
d. Start one RCP.
                                                                 ---_____________a

EOP-6 RCv. 1/ Unit 2 Page 24 of 37 I. RECOVERY ACTIONS ALTERNATE ACTIONS

e. Verify RCP running current:

Tavo Current 525 to 572 F 238 to 210 AMPS and steady 210 to 525 F 264 to 238 AMPS and steady

6. IF pressurizer level decreases, THEN start Charging or HPSI Pump (s) as necessary to restore AND maintain level greater than 155 inches.
7. Monitor RCP seal parameters following pump restart.
8. Allow backflow to equalize temperatures in opposite loop.
 )    9. Start second RCP in opposite loop per steps V.5 and V.7, pages 23 and 24,
10. Secure Auxiliary Spray:
a. Open Loop Charging Valves:

2-CVC-518-CV 2-CVC-519-CV f b. Shut Auxiliary Spray Valve, 2-CVC-517-CV.

c. Shift Pressurizer Spray Controller, 2-HIC-100, to AUTO.

e l i 1 l

EOP-6 Rcv. 1/ Unit 2 j Pago 25 cf 37 III. MCOVERY ACTIONS ALTERNATE ACTIONS l l W. PRESSURE AND LEVEL CONTROL OF AFFECTED S/G: 

               - NOTE -

The following methods for controlling affected S/G pressure and level are listed in preferred order and should be attempted in that order.

1. Maintain affected S/G pressure approximately equal to RCS pressure and S/G 1evel between (-)24 and (+)30 ,

inches by:

a. Steaming S/G to Condenser per step W.2, page 25.
b. S/G Blowdown to Condenser g per step W.3, page 27.

5

c. S/G Blowdown to MWS per step W.4, page 29.
d. Steaming S/G to atmosphere per step W.5, page 31.
e. Filling S/G to MSIV per step W.6, page 32.
2. Pressure and level control of affected S/G by steaming to Condenser:
a. Ensure condenser vacuum greater than 20 IN Hg.
b. Ensure at least one Condensate Demin in service.
c. Open Condensate Precoat Filter Bypass Valve, 2-CD-5818-CV.

( ) d. Shut Condensate Demin Bypass Valve, 2-CD-4439-MOV.

EOP-6 R;v. 1/ Unit 2 Page 26 of 37 

     'II. EECOVERY 3_CTIONS                   ALTERNATE ACTIONS l    I
e. Throttle open Feedwater Dump To Condenser Hotwell Valves, 2-FW-134 and 2-FW-135, to obtain maximum condensate flow through condensate Demin.
f. Shut Condenser High Level Dump CV Inlet Valve, 2-CD-232.
                     - NOTE -

Maintaining S/G level above top of tube bundle providec a large decontamination factor due to the water covering the break. ,.

g. Maintain affected S/G level between (-)24 and

(+)30 inches by operating AFW. g?rh h. operate upstream drains 4p using 2-HS-6622 as necessary to control affected S/G pressure. 

                    - CAUTION -

Do not operate MSIV Bypass Valve on a S/G whose level excaeded (+)63.5 inches.

i. IF additional steam flow desired, l THEN operate MSIV Bypace I

valve on affected S/G. 21 S/G or 22 S/G 2-MS-4045-MOV 2-MS-4052-MOV l I

EOP-6 R v. 1/ Unit 2 Pcg3 27 cf 37 

    'II. RECOVERY _ ACTIONS                  ALTERNATE ACTIONS I   I
3. Pressure and level control of affected S/G by blowdown to Condenser:
a. Ensure at least one Condencate Domin in service,
b. Open Condensate Precoat Filter Bypass Valve, 2-CD-5818-CV. ]
c. Shut Jondensate Demin Bypass Valve,.

2-CD-4439-MOV.

d. Throttle open Feedwater .*

Dump To Condenser Hotwell Valves, 2-FW-134 and 2-FW-135, to obtain maximum condensate flow through Condensate Demin.

e. Shut Condenser High Level l I Dump CV Inlet Valve, 2-CD-232.
f. Place S/G Blowdown Recovery System Radiation Monitor, 2-RE-4095, in RESET.
g. Shut B/D Recovery Discharge To MWS, 2-BD-4097-CV.
h. Shut B/D Recovery Discharge To Circ Water, 2-BD-4015-CV.
1. Open B/D Recovery To Condenser, 2-BD-4096-CV.
j. Shut S/G Combined B/D Eeader Throttle Valves:

2 5D-102 2-BD-104 I I ,

EOP-6 R:v. 1/ Unit 2 Pcg] 28 cf 37 AI, TERNATE ACTIONS 

 'II. _ RECOVERY ACTIONS l  I
k. Open the affected S/G Bottom Blowdown Valve by placing handewitch in RAD TRIP OVERRIDE.

21 S/G or 22 S/G gg 2-BD-4011-CV 2-BD-4013-CV

1. Throttle open S/G Combined B/D Header Throttle Valve on affected S/G to obtain a blowdown flow of approximately 100 GPM.

21 S/G or 22 S/G , 2-BD-102 2-BD-104

m. Throttle SRW flo, to 22 Blowdown Heat Exchanger to maintain a blowdown discharge temperatuge I I between 105 and 115 F using 22 B/D Heat Exchanger Discharge Valve, 2-SRW-635.
                    - NOTE -

Maintaining S/G level above top of ^,ube bundle provides a large decontamination factor due to the water covering the break,

n. Alternately lower ar.d raise affected S/G 1evel by:

(1) S/G Blowdown to l Condenser to (-)24 l inches. l l (2) Operating AFW to (+)30 inches. 1 I I 1 1 1 1

EOP-6 R;v. 1/ Unit 2 Pcg3 29 of 37 II. RECOVERY ACTIONS ALTERNATE ACTIONS l

4. Pressure and level control of affected S/G by blowdown to MWS:
a. Place S/G Blowdown Recovery System Radiation Monitor, 2-RE-4095, in PULSE CAL and bypass its alarm.
b. Open B/D Recovery Discharge To MWS, 2-BD-4097-CV.
c. Shut B/D Recovery Discharge To Cire ,

Water, 2-BD-4015-CV.

d. Shut B/D Recovery To Condenser, 2-BD-4096-CV.
e. Shut S/G Combined B/D Header Throttle Valves:

2-BD-102 2-BD-lO4

f. Open the affected S/G Bottom Blowdown Valve by placing handswitch in RAD TRIP OVERRIDE.

21 S/G or 22 S/G 2-BD-40ll-CV 2-BD-4013-CV

g. Throt.le open S/G Combined B/D Header Throttle Valve on affected S/G to obtain a blowdown flow l of approximately 100 GPM.

21 S/G or 22 S/G l 2-BD-102 2-BD-104 I I l 1

EOP-6 R;v. 1/ Unit 2 Pcg3 30 cf 37 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I ,,

h. Throttle SRW flow to 22 Blowdown Heat Exchanger to maintain a blowdown discharge temperatuge between 105 and 115 F using 22 B/D Heat Exchanger Discharge Valve, 2-SRW-635.
1. Pump MWRT to RCWMT per OI-17D.
j. Monitor MWRT level at IC33.
k. Throttle S/G blowdown rate to maintain a .

constant level in MWRT while pumping to RCWMT. I 

                   - NOTE -

Maintaining S/G level above top i of tube bundle provides a large j ( ) decontamination factor due to the water covering the break.

1. Alternately lower and l raise affected S/G level by:

(1) S/G Blowdown to MWS to (-)24 inches. (2) Operating AFW to (+)30 inches. l l

EOP-6 R0v. 1/ Unit 2 Pcg3 31 of 37 

 'II. RECOVERY ACTIONS                          ALTERNATE ACTIONS I  I
                - CAUTION -

Do not operate Atmospheric Dump Valve on a S/G whose level exceeded (+)63.5 inches.

5. Pressure and level control of 5.1 If Atmospheric Dump was affected S/G by steaming to previously isolated, atmosphere from 2C43: THEN throttle open Atmospheric Dump Manual
a. Establish communications Isolation Valve as at 2C43. directed by Control Room Personnel to control affected
b. Verify 2C43 Atmospheric S/G pressure.

Dump Controllers at 0% output. 21 S/G or 22 S/G

c. Verify Hand Transfer '2-MS-101 2-MS-104 Valves for affected S/G are selected to 2C43 5.2 Maintain affected S/G level position between (-)24 and (+)30 inches by operating AEW.

21 S/G or 22 S/G 5.3 Record total time Atmospheric I I 2-HV-3939A 2-HV-3938A Dump Valve open, for dose 2-HV-3939B 2-HV-3938B calculations. 

                   - NOTE -

Maintaining S/G level above top of tube bundle provides a large decontamination factor due to the water covering the break,

d. Maintain affected S/G level between (-)24 and (+)30 inches by operating AFW,
e. Adjust Atmospheric Dump from 2C43 as directed by Control Room Personnel to control affected S/G pressure,
f. Record total time Atmospheric Dump Valve open, for dose calculations.

l I l l

EOP-6 R;v. 1/ Unit 2 Pcgo 32 of 37 

   'II.                         RECOVERY ACTIONS                 ALTERNATE ACTIONS I  l
                                                                      ~
6. Affected S/G may be allowed to fill to MSIV provided the following conditions are maintained:
a. RCS pressure below 900 PSIA.
b. MSIVs, Atmosp.heric Dump Valves and MSIV Bypass Valves remain shut.

X. COMPLETE ADMINISTRATIVE POST-TRIP ACTIONS AND IMPLEMENT APPROPR7 ATE OPERATING PROCEDURE. , l I l

EOP-6 RCv. 1/ Unit 2 Pcg3 33 cf 37 I Y. ADMINISTRATIVE POST-TRIP ACTIONS: 

                                                - NOTE -

The follot.'ing a;tions may bo accomplished whenever feasible. They may be done in any order.

1. Refer to ERPIP to determine appropriate emergency response actions.
2. Pecform notifications por CCI-118.
3. Notify ESO of trip.
4. Request RCS Boron and Iodine sample.
5. Perform shutdown margin calculation per NEOG 9 and 11.
6. Complete transient log entries per CCI-301.

I I 7. Recall post-trip review (preferably within 30 minutes of trip).

8. Perform post-trip review per CCI-111.
9. Monitor turbine bearing temperatares.
10. Continue Ma'in Turbine shutdown per applicable  !

step of OI-43A. END OF SECTION III. 1

EOP-6 l Rcv. 1/ Unit 2 1 Pcga 34 of 37 l I IV. SAFETY FUNCTION STATUS CHECK A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to exiting from this procedure. B. Perform intermediate safety function status check at 10 minute intervals until plant conditions stabilize. C. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied. D. Review data and verify that safety function acceptance criteria are satisfied. E. When EOP completed, then perform final safety function check. REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL PARAMETERS CRITERIA INTERMEDIATE CRITSRIA FINAL CHECK CHECK l l

c. WRNI power less than 3% ,,,,,,,,,, less than 1%
b. SUR (DPM) negative ,,,,,,,,,,

O

c. CEA status all inserted ,,,,,,,,,,

all inserted or Boration status appropriate concentation increasing ,,,,,,,,,, S/D margin BAST level decreasing , , , , , , , , , , , N/A N/A

EOP-6 R v. 1/ Unit 2 Pcga 35 of 37 I I . RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND IINENTORY , PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECX

o. Pressurizer greater pressure (PSIA) 300 to 1900 ,,,,_,,,__

than 300 __

b. Pressurizer level (inches) O to 200 ____,,,,,,

101 tc 160

c. RCS subcooling ( F) 25 to 140 ,_____,,,,

25 to 140 CORE AND RCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK l l

o. RCS Tcold ( F) less than 535 ,,,,,,,,

300 to 515

b. Tgot minus Teold

( F) Natural Circulation 10 to 50 ________ 10 to 50 Forced Circulation less than 10 ,_____,, less than 10

c. Affected S/G less than less than pressure (PSIA) 920 ,,,__,,,

900

d. Affected S/G less than less than level (inches) (+)30 ,,,____. (+)30
o. Unaffected S/G pressure (PSIA) 70 to 920 ,,____,,

70 to 730

f. Unaffected S/G (-)170 to (-)24 to level (inches) (+)30 _,,__,,, (+)30
g. Condeneate Storage Tank greater greater level (ft) than 5 ___,,,,,

than 5

EOP-6 RCV. 1/ Unit 2 Pcq] 36 of 37 I I . VITAL SAFETY FUNCTION ACCEPTANCE CRITERIA AUXILIARIES FINAL __ CRITERIA INTERMEDIATE CRITERIA CHECK CHECK

o. 4KV vital buses energized 21 or 24 energized ______,,__
b. Instrument Air greater greater pressure (PSIG) than 88 ___,,,,,,,

than 88

c. Component Cooling

(# pumps running) 1 or 2 ,__,,,____ 1 or 2

d. Saltwater

(# pumps running) 1 or 2 ,,,,,,___, 1 or 2

c. Service Water

(# pumps running) 1 or 2 ,,,,,,,___ 1 or 2

f. 125V DC buses

( I 11, 12, 21, 22 energized ,________, energized

g. 120V AC vital buses 21, 22, 23, 24 energized _,,,,,,,,,

energized NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT ENVIRONMENT CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK

a. Contair. ment pressure (PSIG) less than 0.7 ,,,,,,,,

less than 0.7

b. Containment tgmperature less than 120

( F) less than 120 ,,,,,__,

c. Containment High Range Radiation -

alarm alarm Monitor clear clear q g ,,,,,,,,

EOP-6 R v. 1/ Unit 2 Page 37 of 37 k l NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA , LEVELS EXTERNAL TO CONTAINMENT CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK alarm

c. Noble Gas Monitor (1) alarming __________

clear

b. Condenser Off-Gas (1) alarm RMS alarming ,_________

clear alarm (1) alarming clear

c. S/G B/D RMS , , , _ _ _ , , , _ _
d. Main Vent Gaseous (1) alarm alarming clear RMS (2-RI-5415) ,,,_______

(1) RMS alarms are break size and RCS activity dependent. I I STATUS CHECK COMPLETE AT NUMBER TIME 1 2 3 4 l l l l

EOP-7 Rev. 1/ Unit 1 Page 1 of 36 l I CALVERT CLIFFS NUCLEAR POWER PLANT _EOP-7 STATION BLACKOUT REVISION 1 SIGNATURE DATE T l l PREPARED BY; y-I I' - [/ </- / /.2 /? . c 7 VERI m , i [5 3 o[ / 4% v \ POSRC; ,MCETING # 93-7 / 2 3 9 APPROVED BY; hYf z.utew / 2 ~ \O~9 8 Manatierkfiticlear Operations or General Supervisor-Operations if POSRC review is not required l I

EOP-7 R;v. 1/ Unit 1 Pcga 2 of 36 l I I,IST OF EFFECTIVE PAGES ,

f. AGE NUMBF8 1 REVISI6B 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 . I 13 1 14 1 25 1 16 1 17 1
           .8                                     1 19                                     1

{ } 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 28 1 29 1 30 1 31 1 32 1 33 1 34 1 35 1 36 1 l i l l J

EOP-7 R;v. 1/ Unit 1 Pcg3 3 of 36 l I STATION BLACKOUT I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function. B. Systems shifted to manual must be monitored frequently to ensure correct operation. C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments. D. In Natural Circulation, increased' loop transport time causes a 5 to 10 minute delay in temperature responses to a plant change. Pressurizer level and pressure responses typically provide better indication of RCS response during this period. E. If cooling down with a S/G isolated, an inverted delta T(Tcold Ligher than Thot) may be observed in the idle loop. This is due I I to a small amount of reverse heat transfer in the isolated S/G. The inverted delta T is not expected to have any significant effect on natural circulation flow in the operating S/G loop. F. The concentration of boron in RCS makeup water should be consistant with maintaining the required shutdown margin. G. Personnel should be prepared for the possibility of inadequate lighting in access areas and equipment rooms. H. Excessive Diesel Generator loading can result if a SIAS is received and the LOCI sequencer actuates. Non-vital loads should be manually shed immediately upon receiving a SIAS. - I. If a pump or component fails, the cause of the failure should be determined prior to restarting or starting c standby pump or component to prevent a common failure. l l l l l l l l

EOP-7 R;v. 1/ Unit 1 Pcgo 4 of 36 I I II. ENTRY CONDITIONS The presence of one or more of the following conditions indicates that a Station Blackout may have occurred: A. Lohs of Control Room lighting on both Units. B, 500KV Red and Black Bus power available lights de-energized. C. Diesel Generators not loaded. D. No RCPs running on either Unit. E. All 4KV Unit bus power available lights de-energized. l I

E0P-7 R;v. 1/ Unit 1 PCg] 5 cf 36 III. _ RECOVERY ACTIQNS ALTERNATE _ ACTIONS I I . A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED. B. COMMENCE INTERMEDIATE SAFETY FUNCTION STATUS CHECK. C. DETERMINE APPROPRIATE EMERGENCY RESPONSE ACTIONS PER THE ERPIP. D. PROTECT RCS FROM EXCESSIVE COOLDOWN AND CONDENSER FROM OVERPRESSURE:

1. Shut both MSIVs.
2. Shut S/G Blowdown Valves:

1-BD-4010-CV 1-BD-4011-CV 1-BD-4012-CV I 1-BD-4013-CV l l E. ESTABLISH S/G HEAT SINK:

1. Establish S/G heat removal:
a. Establish communications l with an operator stationed to manually operate Atmospheric Dump Valves at the 45 ft level of the l Auxiliary Building.

l l 1 >

EOP-7 R;v. 1/ Unit 1 Pago 6 of 36 

      'II. R

_ECOVERY ACTIONS MTERNATE ACTIONS I h 

                      - NOTE -

Atmospheric Dump Valves are reverse acting, i.e., clockwise to open, counterclockwise to shut,

b. Adjust Atmospheric Dump Valves to maintain S/G pressures between 850 and 920 PSIA.

11 S/G 12 S/G 1-MS-3938-CV 1-MS-3939-CV

2. Establish AFW flow to the .

S/Gs:

a. Start 11 or 12 AFW Pump 2.a.1 Start 11 or 12 AFW Pump by by opening AEW Steam opening AFW Steam Supply Supply Valves: Bypass Valves:

1-MS-4070-CV 1-MS-102 I I 1-MS-4071-CV 1-MS-105

b. Adjust AFW Flow Control Valves to restore and maintain S/G 1evels between (-)170 and

(+)30 inches and trending towards 0 inches. 

                          - HOIE -

Turbine Building N Storage Tanks may be used if Li@7id N2 System unavailable.

c. Align nitrogen to supply AFW Flow Control Valves by opening the following valves located in SRW Rooms (1) N, Supply To AFW M.iplifier Air System, H -105.

2 { l (2) AFW Amplifier Air System N 2 Backup Supply, 1-IA-182.

EOP-7 R;v. 1/ Unit 1 Pcg3 7 of 30 III. EECOVERY ACTIONS ALTEPNATE ACTIONS ( l . d, Assign an operator to control AFW discharge pressure locally (1) Open AFW Pump Room double doors. (2) Establish communications. (3) Adjust turbino governor control knob to maintain AFW Pump discharge pressure 100 PSI greater than S/G pressure. i F. CONFIRM NATURAL CIRCULATION IN AT LEAST ONE LOOP: ( ) - nors - Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10).

1. Thot minug Tcold between 10 and 50 F.
2. Tcold constant or decreasing.
3. Thot constant or decreasing.
                     - uOTs -

CET temperature may be read locally per AOP-7H.

4. CET tempiratures consistent with Thot.
5. Steaming rate affects primary temperature.

I I

EOP-7 R;v. 1/ Unit 1 Pcg] 8 cf 36 III. BECOVERY ACTIONS ALTERNATE ACTIONS I I G. MINIMIZE RCS INVENTORY LOSS:

1. Shut Letdown Isolation Valves:

1-CVC-515-CV 1-CVC-516-CV

2. Maintain an RCP Bleedoff flowpath
a. Shut RCP Bleedoff Isolation Valves:

1-CVC-505-CV 1-CVC-506-CV ,

b. Open RCP Bleedoff RV Isolation, 1-CVC-507-CV.
c. Open RC Drain Tank Drain To Cntmt Floor Valve, 1-RCW-4258-SV.
3. Shut RCS Sample Isolation Valve, 1-PS-5464-CV.
4. Shut Reactor Vessel and Pressurizer Vent Valves:

1-RC-103-SV 1-RC-104-SV 1-RC-105-SV 1-RC-106-SV H. VERIFY EMERGENCY DC PUMP OPERATION:

1. Turbine Imergency 011 Pump.

5

2. Emergency H 2 Seal Oil Pump.
3. S/O Feed Pump Emergency 011 Pumps.

l I

EOP-7 R;v. 1/ Unit 1 Pcg3 9 ef 36 III. RECOVERY ACTIOtLS ELTERNATE ACTIONS i I I. ALIGN ELECTRICAL SYSTEMS FOR POWER RESTORATION:

1. Open the following 13KV breakers:
a. U-4000-13 Feeder, 252-1101,
b. U-4000-11 Feeder, 252-1102.
c. U-4000-12 Feeder, 252-1103.
d. Service Bus 11 Feeder, 252-1104.
e. Tie Breaker Service Bus 11, 252-1105. ^
2. Open the following 4KV

{ l breakers:

e. . 11 4KV Bus Normal Feeder, 152-1115.
b. 11 4KV Bus Alternate Feeder, 152-1101.
c. Switchyard Feeder, 152-1113.
d. 12 4KV Bus Normal Feeder, 152-1201.
e. 12 4KV Bus Alternate Feeder, 152-1209,
f. 13 4KV Bus Normal Feeder, 152-1311.
g. 13 4KV Bus Alternate Feeder, 152-1301,
h. 14 4KV Bus Normal Feeder, 152-1414,
1. 14 4KV Bus Alternate Feeder, 152-1401.

EOP-7 R v. 1/ Unit 1 Pego 10 of 36 III. RECOVERY AC*rIONS ALTERNATE ACTIONS ( l

j. 15 4KV Bus Feeder, 152-1501.
k. 16 4KV Bus Feeder, 152-1604.
3. Place 4KV Bus LOCI /SD Sequencer Manual Initiate Keyswitches for 11 and 14 4KV Buses in ON.

J. ALIGN FEED SYSTEMS FOR POWER RESTORATION: s

1. Place 13 AFW Pump in PULL-TO-LOCK.
2. Verify S/G Feed Pumps tripped.
3. Place Condensate Booster Pumps in PULL-TO-LOCK.
4. Place Condensate Pumps in PULL-TO-LOCK.
5. Place Heater Drain Pumps in PULL-TO-LOCK.

K. MONITOR RCS DEPRESSURIZATION.

1. IF "PRSR PRESS BLOCK A(B)

PERMITTED" alarm (s) received, 1TIEN block SI AS A(B) . I l

E:P-7 R;v. 1/ Unit 1 P;g3 11 Cf 36 III. EECOVERY ACTIONS ALTERNATE ACTIONS l l , L. IF RCS SJBCOOLIgG DECREASES TO LESS THAN 30 F, THENCOOgDOWNTOMAINTAIN 30 TO 50 F SUBCOOLING, USING CET TEMPERATURES:

1. Operate AFW to maintain S/G 1evels between (-)170 and

(+)30 inches. 

                     - HQTE -

If two phase naturgl circulation is in progress, 30 F subcooling cannot be achieved. CET . temperatures constant or decreasing indicates adequate core cooling.

2. Operate Atmospheric Dump Vagvestomaintain30to 50 F subcooling.

l I M. ALIGN BACKUP WATER SUPPLIES FOR AFW AS NECESSARY: 

                                                        - H9IE -

The following step will cause CST levels to equalize.

1. IF 12 CST level decreases 1.1 IF 11 CST HQT available, to 5 ft, TIIEN line up 21 CST as THEN line up 11 CST as alternate auction supply:

alternate auction supply:

a. Locally open 21 CST AFW
a. Locally open 11 CST AEW Pump Suction Valves:

Pump Suction Valves: 2-AFW-131 1-AFW-131 2-AFW-167 1-AFW-167 l l

EOP-7 Rov. 1/ Unit 1 Pcgo 12 cf 36 III. RECOVERY ACTIONS b_LTERNATE ACTIONS l >

b. Locally shut 12 CST b. Locaily open 12 CST AFW '

Unit 1 AFW Pump Suction Pump Suction Valves: Valve, 1-AFW-161. 1-AFW-161

c. Confirm normal CST level 2-AEW-161 response,
c. Confi:n normal CST level response.
2. II DI Water Storage Tank 2.1 II gravity fill of CST NOT level is greater than 10 ft, effective, THEN gravity fill 12 CST IgEN connect fire hoses to by opening 12 CST Fill fill CSTs.

Valve, 0-DW-284. N. ENSURE CONTAINMENT INTEGRITY,

1. II unable to ensure the Containment Normal Sump Drain Icolation Valves shut from the control Room:

I I 1-EAD-5462-MOV 1-EAD-5463-MOV ITHW locally check valves shut. O. RESTORE POWER TO AT LEAST ONE 4KV BUS.

1. Start 11 or 12 D/G per 01-21 1.1 Restore power from the 500KV and close the associated D/G Switchyard per the applicable output breaker, procedures ,
a. OI-28, 500KV Switchyard.
b. OI-27B, 13KV System,
c. OI-27C, 4KV System.

1.2 Restore power to 11 or 14 4KV , Bus using SMECO feeder per OI-27E.

E P-7 R;v. 1/ Unit 1 Pcgo 13 cf 36 III. BECOVER_Y ACTIONS AL_ TERNATE ACTIONS P. )fHKH AT LEAST ONE VITAL 4KV BUS IS ENERGIZED, DIEN VERIFY SliUTDOWN SEQUENCER LOADS OPERATING:

1. Service Water Pump (s).
2. Saltwater Puup(;).
3. Instrument Air Compreslor.
4. 11 or 12 Control Room Ventilation.
5. Switchgear Room Ventilation. ..

1 . Q. RESTORE REACTOR MCCs AND l INSTRUMENT BUSES: { 1. 1F 11 4KV Bus is energized bHD 14 4KV Bus ia NOT energized, IIIEN tie MCC-104 to MCC-114:

a. Open MCC-104 Main Feeder l Breaker, 52-10401.

l l b. Close MCC-104 Tie Breaker, 52-10420.

c. Close MCC-114 Tie Breaker, 52-11420.

l l 2. JF 14 4KV Bus is energized l AND 11 4KV Bus in NOT l energized, l I)IEN tie MCC-114 to MCC-104:

a. Open MCC-114 Main Feeder Breaker, 52-114J1.

i b. Close MCC-114 Tie l Breaker, 52-11420.

c. Close MCC-104 Tie l I Breaker, 52-10420.

f

l I EOP-7 Rcv. 1/ Unit 1 Page 14 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS k > R. RESTORE COMPONENT COOLING FLOW: E

1. IF RCP lower seal 1.1 IF seal gemperature less temperature above 280 F, thar. 280 F, THEN shut Component Cooling THEN start a Component Supply Containment Isolation Cooling Pump.

Valve, 1-CC-3832-CV AND start a Component Cooling Pump,

2. Verify Component Cool.ng Heat Exchanger un service is being supplied from an operating Saltwater Header.

S. COMMENCE RCS BORATION:

1. Open Loop Charging Valves:

q g 1-CVC-518-CV 1-CVC-519-CV

2. Shut Auxiliary Spray Valve, 1-CVC-517-CV.
3. Start all available ChatJing Pumps.
4. Shut VCT Makeup Valve, 1-CVC-512-CV.
5. Open Boric Acid Direct Makeup Valve, 1-CVC-514-MOV.
6. Start a Boric Acid Pump. 6.1 IF Boric Acid Pumps NOT available, THEN establish gravity ~ad:
a. Open BAST Gravity Feed Valves:

1-CVC-508-MOV 1-CVC-509-MOV

b. Shut VCT Outlet Valve,

{ l 1-CVC-501-MOV.

E02-7 Rcv. 1/ Unit 1 Pcga 15 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I -

7. WHEN shutdown margin requirement of NEOG-7 is achieved, THEN secure boration:
a. Open VCT Outlet Valve, 1-CVC-501-MOV.
b. Stop Boric Acid Pump (s).

T. RESTORE RCS INVENTORY.

1. Operate Charging or HPSI Pump (s) as necessary to ,

restore and maintain pressurizer level between 101 and 160 inches. IF INSTRUMENT AIR LOST, l k. THEN RESTORE INSTRUMENT AIR:

1. Align fire main to supply cooling water to air compressors per 01-19.
2. Start at least one Instrument Air Comprensor per OI-19.

l 3. WHEN service water cooling restored to Turbine Building, l THEN return air compressor service water lineup to i ne mal. l l l l 1

EOP-7 R;v. 1/ Unit 1 Pego 16 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS l h V. RESTORE INSTRUMENT AIR TO CONTAINMENT:

1. Open Cntmt Instrument Air Isolation MOV, 1-IA-2080-MOV.
                     - NOTE -

1-HS-2085 located on West wall of 27 ft Switchgear Room; Key #85 in Control Room Key Locker.

2. Open Cntmt Instrument Air Supply CV, 1-IA-2085-CV, by momentarily placing .

1-HS-2085 in OPEN. W. RESTORE LETDOWs llD BLEEDOFF FLOW: { l 1. Open Loap Charging Valven: 1-CVC-518-CV 1-CVC-519-CV

2. Shut Auxiliary Spray Valve, 1-CVC-517-CV.
3. Verify at least one Charging Pump operating.
4. Shift Letdown Control Valve Controller, 1-HIC-110, to MANUAL.
5. Adjust controller to shut Letdown Control Valves.
6. Open Letdown Isolation Valves:

1-CVC-515-CV 1-CVC-516-CV I I i

EOP-7 R0v. 1/ Unit 1 Pcgo 17 of 36 I 1 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I 

                -mm-Degasifier Pumps are powered from non-vital power supply. Excessive diversion may cause Degasifier to overfill.
7. Slowly open the Letdown i Control Valve noting the  ;

l increase in letdown pressure as read on 1-PIC-201, until 1-PIC-201 takes control of the Letdown Backpressure Regulating Valve.

8. Allow temperatures to j stabilize, then shift , ,

1-HIC-110 to AUTO. l I

9. Restore RCP Bleedoff flow to VCT:
a. Open RCP Sleedoff Isolation Valves:

l I 1-CVC-505-CV 1-CVC-506-CV

b. Shut RC Drain Tank Drain To Cntmt Floor, 1-RCW-4258-SV.

I 

                                                                        \

l l l 

        ~~

EOP-7 Rcv. 1/ Unit 1 Page 18 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS X. MAINTAIN RgS SUBCOOLING BETWEEN 30 AND 140 F:

1. Raise subcooling by any of the following:
a. Cecuring Auxiliary Spray.
b. Operate il or 13 Backup Heaters as necessary to raise RCS pressure:

(1) Charge closing spring usir.g manual lever at 480V breakers 52-1127 . and 52-1427. (2) Push the PUSH-TO-CLOSE button on breaker fr)nts. { l 2. Lower subcooling by any of the following:

a. Securing Pressurizer Heaters.
b. Initiating Auxiliary Spray (1) Record temperature differential between Pressurizer and Regenerative Host Exchanger Outlet.

(2) Open Auxiliary Spray Valve, 1-CVC-517-CV. (3) Shut Loop Charging Valves: 1-CVC-518-CV 1-CVC-519-CV

EOP-7 Rov. 1/ Unit 1 Pcga 19 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS I I (4) Shift 1-HIC-100 to MANUAL and shut Pressurizer Spray Valves: 1-RC-100E-CV 1-RC-100F-CV Y. MONITOR FOR CORE AND RCS VOIDING: 

             - CAUTION -

Potential for void formation increases rapidly when pressure ,. decreases below 1500 PSIA.

1. Letdown flow greater than charging flow.
2. Rapid unexplained increase in pressurizer level during l an RCS pressure reduction.
3. Loss of subcooled margin as determined using CET temperatures.
4. "REACTOR VESSEL WATER LEVEL LOW" alarm.

k l

EOP-7 R;v. 1/ Unit 1 Page 20 of 36 RECOVERY ACTIONS ALTERNATE ACTIONS { )I I . Z. IF VOIDING INHIBITS HEAT REMOVAL, THEN REDUCE OR ELIMINATE VOIDED AREA:

1. Shut Letdown Isolation Valve, 1-CVC-515-CV.
                        - CAUTION -

The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

2. Pressurize the RCS to 2.1 .IF pressurizing the RCS does
                                                                                          ' HOT restore heat removal, maigtain subcooling as near                                             THEN operate Reactor Vessel 140 F as practical.

Vent Valves per 01-1G. 

                         - CAUTIOE -

If voids exist in the S/G tubes, l I a rapid RCS pressure reduction will occur when the voids collap se.

3. IF voiding occurs in the S/G tubes (saturation pressure of S/G greater than saturation pressure of RCS),

THEN cool the S/G by raising any of the following:

a. Steaming rate.
b. Feed rate,
c. S/G Blowdown rate.

AND, maintaining less than 100 F/h cooldown rate. l I l --

EOP-7 Rcv. 1/ Unit 1 Pcg2 21 of 36 III. _ RECOVERY ACTIONS ALTERNATE ACTIONS l I AA. ENERGIZE SUPPORT EQUIPMENT AS NECESSARY TO FACILITATE SHUTDOWN AND VERIFY LOAD REMAINS WITHIN RATINGS: 

                 - CAUTION -

If the following load limits can be maintained, actuation of the LOCI Sequencer will not cause a D/G overload condition: without 13 AEM Pump - 1400 KW with 13 AEW Pump - 1800 KW These limits may be exceeded if additional power is required to safely, efficiently shut down the plant. The D/G should not be operated above 3250 KW. 

                  - CAUTION -

SMECO load limit is 260 AMPS.

1. Start a Main Exhaust Fan.
2. Start Containment Air Cooler (s) in LOW to maintain containment 0 temperature below 120 F.
3. Start a Cavity Cooling Fan to maintain cavity cogling temperature below 200 F.
4. IF "SFP LEVEL TEMP HI" alarm received,
            ,1_TIEN start Spent Euol Pool Cooling Pump (s).
5. Strip MCC-101AT and MCC-101BT of all loads, by opening individual MCC breakers.

I 2

EOP-7 Rcv. 1/ Unit 1 Page 22 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS

6. IF 11 4KV Bus is energized

_AND 14 4KV Bus is NOT energized, THEN tie MCC-101BT to MCC-101AT:

a. Close MCC-101AT Feeder Breaker, 52-1109.

I b. Open MCC-101BT Main Feeder Breaker, 52-10141.

c. Close Tie Breakers:

52-10120 52-10160

d. Energize loads per step AA.9, page 22.
7. IF 14 4KV Bus is energized AND 11 4KV Bus is NOT energized, THEN tie MCC-201AT to l I MCC-101BT:
a. Close MCC-101BT Feeder Breaker, 52-1419.
b. Open MCC-101AT Main Feeder Breaker, 52-10101.

l

c. Cicse Tie Breakers: '

52-10120 52-10160

d. Energize loads per step AA.9, page 23.

l 1 l 4 >

EOP-7 R0v. 1/ Unit 1 Page 23 of 36 II. RECOVERY ACTIONS ALTERNATE ACTIONS

8. IF both 11 AND 14 4KV Buses are energized, THEN energize MCC-101AT and MCC-101BT:
a. CJone MCC-101AT Feeder Breaket, .> 4 - 110 9 ,

b Close MCC-101BT Feeder Breaker, 52-1419.

c. Energize loads per step AA.9, page 23,
9. Energize MCC-101AT and MCC-101BT loads:
a. Turbine Building Lighting Transformer Breaker, 52-10103.
b. Turning Gear 011 Pump Breaker, 52-10102.

l I

c. Turbine Oil Lift Pump Breakers:

52-10106 52-10107 52-10108 52-10109 52-10110

d. Turbine Turning Gear Piggyback Motor and Turning Gear Motor I Brecker, 52-10105,
e. Technical Support Center HVAC Breaker, 52-10111.
f. Distribution Panel 11 Breaker, 52-10116.
g. Telephone Transformer 1 Breaker, 52-10118.
h. 11 S/G Feed Pump Turning l

D Gear Breaker, 52-10121.

EOP-7 Rov. 1/ Unit 1 Page 24 of 36 4 jII. RECOVERY ACTIONS AL_T_E_RNATE_ ACTIONS 5, i. SRW Pump Room Vent Fan, @0 52-10124 (Restart SRW 7 Pump Room Ventilation, 

    ,                               per 01-15).
j. Technical Support Center Computer Breaker, 52-10122.
k. Turbine Oil Lift Pump Breakers:

52-10146 52-10147 52-10148 52-10149

1. AFW Pump Room Air Conditioner Breaker, 52-10150.
m. 17. S/G Feed Pump Turning Gear Breaker, 52-10161.

I I

n. Distribution Panel 111 Breaker, 52-10162.
10. IF emergency power requested by Security, THEN place disconnect switch 2Y211, located on the North wall of Unit 2 27 ft Switchgear Room, in the EMERGENCY position.

AB. MINIMIZE 250V DC BATTERY DISCHARGE:

1. Energize 15 or 25 Battery Charger on 13 250V DC Bus.
2. Ensure Main Turbine has stopped rotating or is on Turning Gear.
3. Verify Turning Gear Oil Pump running.

g

EOP-7 R0v. 1/ Unit 1 Page 25 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I

4. Stop Turbine Emergency Oil Pump and place handswitch in AUTO.
5. IF bearing oil header i pressure less than 25 PSIG, THEN etart Turbine Emergency Oil Pump.

AC. LOWER MAIN GENERATOR HYDROGEN PRESSURE TO 2 PSIG:

1. Align Two-Position Valvo, 1-0-01, to VENT position. .,
2. Throttle open Generator Vent Line Isolation Valve, 1-G-03.
3. vnUDI Main Generator hydrogen pressure decreases to 2 PSIG, THEN perform the following:
a. Shut 1-G-03.
b. Secure Emergency H Seal 2

Oil Pump.

EOP-7 rov. 1/ Unit 1 Page 26 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I AD. If LOCI SEQUENCER IS ACTUATED AND TURBINE MCCs ARE BEING SUPPLIED BY D/G, THEN DE-ENERGIZE MCC-101AT 100 MCC-101BT.

1. II rapid D/G load reduction 1.1 If rapid D/G load needed, reduction NOT needed, THEN perform the following: THEN perform the following locally:
a. Open 11A 480V Bus Feeder Breaker, 52-1112. a. Open MCC-101AT Main Feeder Breaker,
b. Open 14B 480V Bus Feeder 52-10101.

Breaker, 52-1413. 

                                                                               ,b. Open MCC-101BT Main
c. Locally open MCC-101AT Feeder Breaker, Main Feeder Breaker, 52-10141.

52-10101.

d. Locally open MCC-101BT Main Feeder Breaker,

{ } 52-10141.

e. Close 11A 480V Bus Feeder Breaker, 52-1112.
f. Close 14B 480V Bus Feeder Breaker. 52-1413.

AE. MAINTAIN VCT LEVEL BETWEEN 60 AND 100 INCHES:

1. MHEN VCT makeup required, THEN shift Charging Pump suction to RWT:
a. Open RWT To Charging Pump Suction Valve, 1-CVC-504-MOV.
b. Observe VCT level 1.b.1 If VCT level NOT increasing, increasing. THEU shut VCT outlet Valve, 1-CVC-501-MOV.

I I c. Ensure Charging Pump (s) AMPS steady. 1

EOP-7 Rcv. 1/ Unit 1 Page 27 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS 

                                                     /
2. WHEN VCT increases to 100 inches, THEN shift Charging Pump suction to VCT:
a. Open VCT Outlet Valve, 1-CVC-501-MOV.
b. Shut RWT To Charging Pump Suction Valve, 1-CVC-504-MOV.

AF. IF FORCED CIRCULATION DES 1 RED AND PUMP RESTART CRITERIA MET, THEN RESTART RCPs WHEN POWER , AVAILABLE: 

                - CAUTION -

Uncontrolled restoration of g g cooling to hot RCP seals may cause degradation of the metallic seating surfaces by thermal shock,

1. IF Component Cooling is isolated to RCP seals, THEN reduce RCP lowor oseal temperature below 280 F prior to initiating full cooling flow to the RCPs:
a. Shut Component Cooling Supply Containment Manual Isolation Valve, 1-CC-284, located in 5 ft East Penetration Room,
b. Open Component Cooling Containment Isolation Valves:

1-CC-3832-CV 1-CC-3833-CV

c. Slowly open 1-CC-284 to throttle component l l cooling flow until lower seal temperatgres are less than 280 F.

EOP-7 R0v. 1/ Unit 1 Pcgo 28 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I ,

d. WHEN lower seal temperatgres are less than 280 F, THEN fully open 1-CC-284.
2. IF an RCP lower seal temperature exceeded 280 F, THEN an engineering evaluation is required prior to restarting that RCP.
3. Raise pressurizer level to at least 155 inches.
4. Lowgr Teold to less than 525 F.
5. Verify RCP restart criteria:
a. RCS subgoolir:q greater than 30 F.
b. At least one S,'C available for heat removel.

l I

c. Pressurizer level greater than 155 inches and stable.
d. Tcold less than 525 F.
e. RCS temperature and pressure greater than the minimum operating limits per RCP curve on Attachment (1).
               - NOTE -

Starting an RCP may cause a pressurizer level transient.

6. vnH24 RCP restart criteria are met, IIMN start one RCP in a loop with an operable S/G:
a. Verify "r7MPT CLG FLOW LO" alarm clear.

EOP-7 Rov. 1/ Unit 1 Pcga 29 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS l l

b. Start Oil Lift Pump.
c. Insert RCP sync stick,
d. Start one RCP.
e. Monitor RCP running current:

Tavo Current 525 to 572 F 238 to 210 AMPS and steady 210 to 525 F 264 to 238 AMPS and steady

7. Monitor RCP seal parameters following pump restart.
8. Allow backflow to equalize temperatures in opposite loop.
9. Start second RCP in opposite l ) loop per steps AF.6 and AF.7, pages 28 and 29.
10. Secure Auxiliary Spray:
a. Open Loop Charging Valves:

1-CVC-518-CV 1-CVC-519-CV

b. Shut Auxiliary Spray Valve, 1-CVC-517-CV.
c. Shift Pressurizer Spray Controller, 1-HIC-100, to AUTO.
11. hSQQ{ RCPs restarted,

_TIJEH implement appropriate operating procedure AND complete administrative post-trip actions of this procedure. l I 

                                                        -           - _ _ - -     - _ _ _  _ ~

EOP-7 R;v. 1/ Unit 1 Pcga 30 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I AG. DETERMINE TIME UNTIL COOLDOWN REQUIRED:

1. Determine total water available for use as makeup.
2. Determine time until commencement of required cooldown per Attachment (11).
3. IF RCS cooldown required, 3.1 IF RCS cooldown NOT THEN implement Natural required, Circulation Cooldown (AOP-3F) THEN implement Loss of AND complete administrative Flow / Natural Circulation post-trip actions of this ,(AOP-3E) AND complete procedure. administrative post-trip actions of this procedure.

l I i l l l l l l l I

EOP-7 l R v. 1/ Unit 1 ! Page 31 of 36 l I AH. ADMINISTRATIVE POST-TRIP ACTIONS: 

                                    - NOTE -

The following actions may be accomplished whenever feasible. They may be done in any order.

1. Refer to ERPIP to determine appropriate emergency response actions.
2. Perform notifications per CCI-118,
3. Notify ESO of trip.
4. Request RCS Boron and Iodine sample.
5. Perform shutdown margin calculation per NEOG 2 and 7.
6. Complete transient log entries per CCI-301.

l l 7. Recall post-trip review (preferably within 30 minutes of trip).

8. Perform post-trip review per CCI-111,
9. Monitor turbine bearing temperatures.
10. Continue Main Turbine shutdown per applicable step of OI-43A.

END OF SECTION III. I I P 1

EOP-7 l R v. 1/ Unit 1 Pcg2 32 of 36 i > . 

                     .V. SAFETY FUNCTION STATUS CHECK A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to exiting from this procedure.

B. Perform intermediate safety function status checks at 10 minute intervals until plant conditions stabilize. C. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied. D. Review data and verify that safety function acceptance criteria are satisfied. E. When EOP completed, then perform final safety function check. REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK l I

c. WRNI power at RPS less than 3% __________ less than 1%
b. SUR (DPM) at RPS negative __________ O When Power Restorg
c. CEA status all inserted _____,____ all inserted or Boration status:

appropriate concentation increasing S/D margin BAST level decreasing __________ N/A N/A l l

EOP-7 R v. 1/ Unit 1 Page 33 of 36 l I RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND INVENTORY PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. Pressurizer less less pressure (PSIA) than 2300 __________

than 2300

b. Pressurizer level 4 (inches) (1) 50 to 180 __________

130 to 180

c. RgS subcooling 30 to 140 __________

30 to 140 ( F) (2) (1) Pressurizer level may decrease below 50 inches depending upon RCS leakrate and time power unavailable. (2) RCS subcooling may decrease below 30 F depending upon RCS leakrate and time power unavailable. If CET temperatures remain less tb or equal to saturation temperature, for existing RCS pressure, thr he i ) Core is covered. l I

EOP-7 RCV. 1/ Unit 1 Pega 34 ef 36 l I CORE AND RCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. RCS Tcold ( F) less than 545 ________

less than 535

b. CET ( F) (3) constant constant or decreasing ________

or decreasing

c. Tgot minus Teold

( F): 1 Natural Circulation 10 to 50 ,,______ 10 to 50 Forced Circulation N/A ________ less than 5 j

d. S/G pressure (PSIA) less than I less than l 1000 ________

920

e. S/G level (inches) (-)170 to (-)24 to l

{ ) (+)30 ________ (+)30  ! l

f. Condensate Storage greater greater Tank level (ft) than 5 ________

than 5 (3) CET temperatures may increase while Natural Circulation is being established. l I

EOP-7 R2v. 1/ Unit 1 Pcga 35 of 36 l I VITAL SAFETY FUNCTJON ACCEPTANCE CRITERIA AUXILIARIES CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

c. 4KV vital buses one 11 and 14 (4) de-energized __________

energized

b. Instrument Air greater pressure (PSIG) (4) decreasing __________

than 88

c. Component Cooling

(# pumps running)(4) O __________ 1 or 2 _

d. Component Cooling Head Tank level greater than greater (inches) (5) 30 __________

than 20

o. Saltwater

(# Pumps running)(4) 0 __________ 1 or 2 d I f. Service Water (# pumps running)(4) 0 __________ 1 or 2

g. Service Water Head Tank level greater than greater (inches) (5) 30 __________

than 30 battery

h. 125V DC buses charger 11, 12, 21, 22 energized __________

energized

i. 120V AC vital battery buses charger l 11, 12, 13, 14 energized __________

energized _ (4) Intermediate criteria based on initial conditions prior to i restoration of a 4KV vital bus. l (5) Refer to 01-15 and 01-16 for filling head tanks. l I l i > 1 l

EOP-7 , R3v. 1/ Unit 1 Page 36 of 36 

 $   I NORMAL                                   SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT ENVIRONMENT                          CRITERIA       INTERMEDIATE        CRITERIA      FINAL PARAMETERS                                                    CHECK                  CHEC':
c. Containment pressure (PSIG) N/A ___$[h___ less than 0.7
b. Containment tgmperature N/A

( F) N/A _________ less than 120

c. Containment level ,

(inches) N/A ___f[h___ less than 4 NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL TO CONTAINMENT CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. Noble Gas Monitor (6) alarm alarm clear __________

clear (6) Available when power restored. STATUS CHECK COMPLETE AT NUMBER TIME 1 2 3 4 d I L

EOP-7 RCV. 1/ Unit. 2 Pcg3 1 o f '36 l I . CALVERT CLIFFS NUCLEAR POWER PLANT EOP-7 STATION BLACKOUT REVISION 1 SIGNATURE DATE i, I k PREPARED BY; ,8// b.1<f A / /.2-/? E9 VERIFIED BY; att/F 3 Ach7W //L F // > 

                  /

POSRC; MEETING # 93-1 / 2. - \o - W6 APPROVED BY; ON _ smer:# /__Z- t c 'd 2 

                !(arfage'riNuclear Operations or General Supervisor-Operations if POSRC review is not required l I

EOP-7 R;v. 1/ Unit 2 Pcgo 2 of 36 l I LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION 1 1 2 1 3 1 4 1 5 1 6 1 7 1 8 1 9 1 10 1 11 1 12 , 1 13 1 14 1 15 1 16 1 17 1 18 1 19 1 I I 20 1 21 1 22 1 23 1 24 1 25 1 26 1 27 1 28 1 29 1 30 1 31 1 32 1 33 1 34 1 35 1 36 1 l I

EOP-7 l R v. 1/ Unit 2 i Pcga 3 of 36 l I STATION BLACKOUT I. PRECAVfIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function. B. Systems shifted to manual must be monitored frequently to ensure correct operation. C. At least two independent indications should be used, when availaolo, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments. D. In Natural Circulation, increased"loop transport time causes a 5 to 10 minuto delay in temperature responses to a plant change. Pressurizer level and pressure responses typically provide better indication of RCS response during this period. E. If cooling down with a S/G isolated, an inverted delta T(Tcold higher than Thot) may be observed in the idle loop. This is due l I to a small amount of reverae heat transfer in the isolated S/G. The inverted delta T is not expected to have any significant effect on natural circulation flow in the operating S/G loop. F. The concentration of boron in RCS makeup water should be consiatent with maintaining the required shutdown margin. G. Personnel should be prepared for the possibility of inadequate lighting in access areas and equipment rooms. H. Excessive Diesel Generator loading can result if a SIAS is received and the LOCI sequencer actuates. Non-vital loads should be manually shed immediately upon receiving a SIAS. I. If a pump or component fails, the cause of the failure should be determined prior to restarting or starting a standby pump or component to prevent a common failure. I I 

                                                                                                ~

EOP-7 RCv. 1/ Unit 2 Page 4 of 36 l I II. ENTRY CONDITIONS The presence of one or more of the following conditions indicates that a Station Blackout may have occurred: A. Loss of Control Room lighting on both Units. B. 500KV Red and Black Bus power available lights de-energized. C. Diesel Generators not loaded. D. No RCPs running on either Unit. E. All 4KV Unit bus power available lights de-energized. I i l

EOP-7 RCv. 1/ Unit 2 Pcgo 5 cf 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS I l A. VERIFY POST-TRIP IMMEDIATE ACTIONS COMPLETED. B. COMMENCE INTERMEDIATE SAFETY FUNCTION STATUS CHECK. C. DETERMINE APPROPRIATE EMERGENCY RESPONSE ACTIONS PER THE ERPIP. D. PROTECT RCS FROM EXCESSIVE COOLDOWN AND CONDE!!SER FROM OVERPRESSURE:

1. Shut both MSIVs.
2. Shut S/G Blowdown Valves:
           ?-BD-4010-CV 2-BD-40ll-CV 2-BD-4012-CV 2-BD-4013-CV E. ESTABLISH S/G HEAT SINK:
1. Establish S/G heat removals
a. Establish communications with an operator stationed to manually operate Atmospheric Dump Velves at the 45 ft level of the Auxiliary Building.

94 EOP-7 R v. 1/ Unit 2 Pega 6 of 36 III. RECOVERY _ ACTIONS ALT Q ATE ACTIONS I I , 

                     - NOTE -

Atmospheric Dump Valves are reverse acting, i.e., clockwise to open, counterclockwise to shut,

b. Adjust Atmospheric Dump Valves to maintain S/G pressures between 850 and 920 PSIA.

21 S/G 22,1,'G 2-MS-3939-CV 2-MS-3938 CV

2. Establish AFW flow to the ,

S/Gs:

a. Start 21 or 22 AFW Pump- 2.a.1 Start 21 or 22 AFW Pump by by opening AFW Steam opening AFW Steam Supply Supply Valves: Bypass Valves:

2-MS-4070-CV 2-MS-102 l I 2-MS-407.-CV 2-MS-105

b. Adjust AFW Flow Control Valves to restore and maintain S/G levels -
                                                                                    ^

between (-)170 and (+)30 inches and trending towards 0 inches. 

                        - NOTE -

Turbine Building N Storage Tanks may be used if Li@,id N2 System unavailable,

c. Align nitrogen to supply AFW Flo; Control Valves by opening the following valves located in SRW Room:

(1) N, Supply To AFW Amplifier Air System, N -107. 2 { ) (2) AFW Amplifier Air System N 2 Backup Supply, 2-IA 190.

l' EOP-7 R v. 1/ Unit 2 Pcga 7 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIO}LS

d. Assign an operator to control AFW discharge pressure locally:

(1) Open AFW Pump Room double doors. (2) Establish communications. (3) Adjust turbine governor control knob to maintain AFW Pump discharge 1 pressure 100 PSI greater than S/G pressure. . F. CONFIRM NATURAL CIRCULATION IN AT LEAST ONE LOOP: l I - NOTE - Wide range Thot may be obtained from Subcooled Margin Monitor i per Attachment (10). I 1. Thet minu Teold between 10 and 50 F.

2. Teold constant or decreasing.
3. Thct constant or decreasing.
                          - NOTE -

CET temperature may be read locally per AOP-7H.

4. CEi temperatures consistent with Thot.
5. Steaming rate affects primary temperature.

f

EOP-7 R v. 1/ Unit 2 Pcg3 8 of 36 III. RECOVERY ACTIONS ETERNATE ACTIONS i I G. MINIMIZE RCS INVENTORY LOSS:

1. Shut Letdown Isolation Valves:

2-CVC-535-CV 2-CVC-516-CV - 2. Maintain an RCP Bleedoff j flowpath: ) a. Shut RCP Bleedoff Isolation Valves: 2-CVC-505-CV 2-CVC-506-CV ,

b. Open RCP Bleedoff RV Isolation, 2-CVC-507-CV.
c. Open RC Drain Tank Drain To Cntmt Floor Valve, 2-RCW-4258-SV.

l I

3. Shut RCS Sample Isolation Valve, 2-PS-5464-CV.
4. Shut Reactor Vessel and Pressurizer Vent Valves:

2-RC-103-SV 2-RC-104-SV 2-RC-105-SV 2-RC-106-SV H. VERIFY EMERGENCY DC PUMP OPERATION:

1. Turbine Emergency Oil Pump.
2. Emergency Air Side Pieal Oil Pump.
3. S/G Teed Pump Emergency Oil Pumps, l I

EOP-7 ROV. 1/ Unit L Pcg3 9 cf 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS l I I. ALIGN ELECTRICAL SYSTEMS FOR POWER RESTORATION:

1. Open the following 13KV breakers:
a. U-4000-23 Feeder, 252-2101.
b. U-4000-21 Feeder, 252-2102.
c. U-4000-22 Feeder, 252-2103.
d. Service Bus 21 Feeder, 252-2104,
e. Tie Breaker Service Bus 21, 252-2105.
2. Open the following 4KV I I breakers:
a. 21 4KV Bus Normal Feeder, 152-2101.
b. 21 4KV Bus Alternate Feeder, 152-2115.
c. Switchyard Feeder, 152-2113.
d. 22 4KV Bus Noriaal E eeder, 152-2201.
e. 22 4KV Bus Alternate Feeder, 152-2209.

23 4KV Bus Normal Feeder, l f. 152-2311. l

g. 23 4KV Bus Alternate l Feeder, 152-2301.

1

h. 24 4KV Bus Normal Feeder, 152-2401.

I I l

i. 24 4KV Bus Alternate Feeder, 152-2414.

EOP-7 Rcv. 1/ Unit 2 Pcg3 10 of 36 III. MCOVERY_ ACTIONS ALTERNATE ACTIONS

j. 25 4KV Bus Feeder, 152-2501.
k. 26 4KV Bus Feeder, 152-2604.
3. Place 4KV Bus LOCI /SD Saquencer Manual Initiate Keyswitches for 21 and 24 4KV Buses in ON, J. ALIGN FEED SYSTEMS FOR POWER )

RESTORATION:

1. Place 23 AFW Pump in PULL-TO-LOCK.
2. Verify S/G Feed Pumps trip ed.
3. Place Condensate Booster Pumps in PULL-TO-LOCK.
4. Place Condensate Pumps in PULL-TO-LOCK.
5. Place Heater Drain Pumps in PULL-TO-LOCK.

K. MONITOR RCS DEPRESSUR12.\ TION.

1. IF "PRSR PRESS BLOCK A(B)

PERMITTED" elar:n(s) received, EIEN block SI AS A(B) . l >

EOP-7 R v. 1/ Unit 2 Pcg3 11 cf 36 III. _ RECOVERY ACTIONS ALTERNATE ACTIONS l I - L. IF RCS SUBCOOLIgG DECREASES TO LESS THAN 30 F, THEN COOg DOWN TO MAINTAIN 30 TO 50 F SUBCOOLING, USING CET TEMPERATURES:

1. Operate AFW to maintain S/G levels between (-)170 and

(+)30 inches. 

                     - NOTE -

If two phase naturgl circulation is in progress, 30 F subcooling cannot be achieved. CET , temperatures constant or decreasing indicates adequate core cooling.

2. Operate Atmospheric Dump Vafves to maintain 30 to 50 F subcooling.

I l M. ALIGN BACKUP WATER SUPPLIES FOR AEW AS NECESSARY: 

                                                          - NOTE -

Thre following step will cause CST levels to equalize.

1. IF 12 CST level decreases 1.1 IF 21 CST HOT available, to 5 ft, THEN line up 11 CST as TIIEU line up 21 CST as alternate suction supply:

alternate auction supply:

a. Locally open 11 CST AEW
a. Locally open 21 CST AFW Pump Suction Valves Fump Suction Valves:

1-AFW-131 2-AFW-131 1-AFW-167 , 1 2-AEW-167 1 l l

EOP-7 R v. 1/ Unit 2 Pcg3 12 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS i l

b. Locally shut 12 CST b. Locally open 12 CST AFW Unit 2 AEW Pump Suction Pump Suction Valves:

Valve, 2-AFW-161. 1-AEW-161

c. Confirm normal CST level 2-AFW-161 responsu.
c. Confirm normal CST level response.
2. If DI Water Storage Tank 2.1 IF gravity fill of CST NOT level is greater than 10 ft, effective, TIIEN gravity fill 12 CST TIIEN connect fire hoses to by opening 12 CST Fill fill CSTs.

Valve, 0-DW-284. N. ENSURE CONTAINMENT INTEGRITY.

1. 1F unable to ensure the Containment Normal Sump Drain Isolation Valves shut from the Control Room:

g 2-EAD-5462 MOV 2-EAD-5463-MOV THEN locally check valves shut. O. RESTORE POWER TO AT LEAST ONE 4KV BUS.

1. Start 21 or 12 D/G per 01-21 1.1 Restore power from the 500KV and close the associated D/G Switchyard per the applicable output breaker. procedure
a. 01-28, 500KV Switchyard,
b. OI-27B, 13KV System,
c. OI-27C, 4KV System.

1.2 Restore power to 21 or 24 4KV Bus using SMECO feede* per  ; OI-27E. { l

EOP-7 R;v. 1/ Unit 2 Pcg3 13 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS l l s P. MHEN AT LEAST ONE VITAL 4KV BUS IS ENERGIZED, THEN VERIFY SHUTDOWN SEQUENCER LOADS OPERATING:

1. Service Water Pump (s).
2. Saltwater Pump (s).
3. Instrument Air Compressor.
4. 11 or 12 Control Room Ventilation.
5. Switchgear Room Ventilation. ,

Q. RESTORE REACTOR MCCs PJH) INSTRUMENT BUSES: I I 1. IF 24 4KV Bas is energized AND 21 4KV Bus is NOT energized, THEN tie MCC-214 to MCC-204:

a. Open MCC-214 Main Feeder Breaker, 52-21401.
b. Close MCC-214 Tie l Breaker, 52-21420,
c. Close MCC-204 Tie Breaker, 52-20420. l
2. IF 21 4KV Bue is energized '

bND 24 4KV Bus is NOT energized, THEN tie MCC-204 to MCC-214: l

a. Open MCC-204 Main Feeder l Breaker, 52-20401.
b. Close MCC-204 Tie Breaker, 52-20420.

{ f c. Close MCC-214 Tie Breaker, 52-21420. i

EOP-7 Rov. 1/ Unit 2 Pcga 14 of 36 III. _ RECOVERY ACTIONS ALTERNATE ACTIONS I I  ! R. RESTORE COMPONENT COOLING FLOW:

1. IF RCP lower seal 1.1 IF seal gemperature less temperature above 280 F, than 280 F, THEN shut Component Cooling THEN start a Component Supply Containment Isolation Cooling Pump.

Valve, 2-CC-3832-CV AND start a Component Cooling Pump.

2. Verify Component Cooling Heat Exchanger on service is being supplied from an operating Saltwater Header.

S. COMMENCE RCS BORATION:

1. Open Loop Charging Valves:

2-CVC-518-CV l 2-CVC-519-CV

2. Shut Auxiliary Spray Valve, 2-CVC-517-CV.
3. Start all available Charging Pumps.
4. Shut VCT Makeup Valve, 2-CVC-512-CV.
5. Open Boric Acid Direct Makeup Valve, 2-CVC-514-MOV.
6. Start a Boric Acid Pump. 6.1 IF Boric Acid Fumps NOT available, MIEN establish gravity feed
a. Open BAST Gravity i'eed Valves:

2-CVC-508-MOV  ; 2-CVC-509-MOV  ! Shut VCT Outlet Valve,  ! b. 2-CVC-501-MOV. l l I

EOP-7 R;v. 1/ Unit 2 Pcgo 15 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS

7. WHEN shutdown margin requirement of NEOG-11 is achieved, THEN secure borations
a. Open VCT outlet Valve, 2-CVC-501-MOV.
b. Stop Boric Acid Pump (s).

T. RESTC1E RCS INVENTORY.

1. Operate Charging or HPSI Pump (s) as necessary to restore and maintain pressurizer level between 101 and 160 inchen.

1 IF INSTRUMENT AIR LOST, I I TEIEN RESTORE INSTRUMENT AIR:

1. Align fire main to supply cooling water to air compressors per OI-19,
2. Start at least one Instrument Air Compressor per 0I-19,
3. WHEN service water cooling restored to Turbine Building, THEN return air compressor nervice water lineup to normal.

I

l EOP-7 R;v. 1/ Unit 2 Page 16 of 36 II. RECOVERY _ ACTIONS ALTERNATE _ ACTIONS

7. RESTORE INSTRUMENT AIR TO CONTAINMENT:
1. Open Cntmt Instrument Air Isolation MOV, 2-IA-2080-MOV.
                      - NOTE -

2-HS-2085 located on West wall of 27 ft Switchgear Room; Rey #80 in Control Room Key Locker.

2. Open Cntmt Instrument Air Supply CV, 2-IA-2085-CV, by momentarily placing ,

2-HS-2085 in OPEN.

d. RESTORE LETDOWN AND BLEEDOFF FLOW:

l I

1. Open Loop Charging Valves:

2-CVC-518-CV 2-CVC-519-CV

2. Shut Auxiliary Spray Valve, 2-CVC-517-CV.
3. Verify at le.ast one Charging Pump operating.
4. Shift Letdown Control Valve Contro'.ler, 2-HIC-llo, to MANUAL.

F. Adjust controller to shut Letdown Control Valves.

6. Open Letdown Isolation Valves:

2-CVC-515-CV 2-CVC-516-cV l I

EOP-7 Rav. 1/ Unit 2 Pcg3 17 cf 36 III. _ RECOVERY _ ACTIONS ALTERNATE ACTIONS 

                  - NOTE -

Degasifier Pumps are powered from non-vital power supply. Excessive diversion may cause Degasifier to overfill.

7. Slowly open the Letdown Control Valve noting the increase in letdown pressure as read on 2-PIC-201, until 2-PIC-201 takes control of the Letdown Backpressure Regulating Valve.
8. Allow temperatures to stabilize, then shift ,

2-HIC-110 to AUTO.

9. Restore RCP Bleedoff flow to VCT:
a. Open RCP Bleedoff Isolation Valves:

2-CVC-505-CV 2-CVC-506-CV l

b. Shut RC Drain Tank Drain i To Cntmt Floor, l 2-RCW-4258-SV. I I

I >

EOP-7 Rov. 1/ Unit 2 PCg3 18 ef 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS I I X. MAINTAIN RgS SUBCOOLING BETWEEN 30 AND 140 F:

1. Raise subcooling by any of l the following:
a. Securing Auxiliary Sprey.

l b. Operate 21 or 23 Backup Heaters as necessary to raise RCS pressures (1) Charge closing spring using manual lever at 480V breakers 52-2127 , and 52-2427. (2) Push the PUSH-TO-CLOSE button on breaker fronts. I I 2. Lower subcooling by any cf , the following: l l

a. Securing Pressurizer l Heaters,
b. Initiating Auxiliary Spray:

(1) Record temperature differential between Pressurizer and Regenerative Heat Exchanger Outlet. (2) Open Auxiliary Spray Valve, 2-CVC-517-CV. (3) Shut Loop Charging Valves: 2-CVC-518-CV 2-CVC-519-CV l I

EOP-7 R v. 1/ Unit 2 PCgo 19 cf 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS I I (4) Shift 2-HIC-100 to MANUAL and shut Pressuriser Spray Valves 2-RC-100E-CV 2-RC-100F-CV Y. MONITOR FOR CORE AND RCS VOIDING: 

               - CAUTION -

Potential for void formation increases rapidly when pressure , decreasen below 1500 PSIA.

1. Letdown flow greater than charging flow.
2. Rapid unexplained increase in pressurizer level during I I an RCS pressure reduction.
3. Loss of subcooled margin as determined using CET temperatures.
4. "REACTOR VESSEL WATER LEVEL LOW" alarm.

I i i l l 4 l l 

                                                                         )

EOP-7 l R v. 1/ Unit 2 Pcg3 20 of 36 l III. RECOVERY ACTIONS ALTERNATE ACTIONS ll l . Z. IF VOIDING INHIBITS HEAT REMOVAL, THEN REDUCE OR ELIMINATE VOIDED AREA:

1. Shut Letdown Isolation Valve, 2-CVC-515-CV.
                  - CAUTION -

The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

2. Pressurize the RCS to 2.1 .1E pressurizing the RCS does maigtain subcooling as near HOT restore heat removal, 140 F as practical. THEN operate Reactor Vessel Vent Valves per 01-1G.
                  - CAUTION -

If voids exist in the S/G tubes, a rapid RCS pressure reduction l I will occur when the voids collapse.

3. if voiding occurs in the S/G tubes (saturation pressure of S/G greater than saturation pressure of RCS),

THEN cool the S/G by raising any of the following:

a. Steaming rate.
b. Feed rate,
c. S/G Blowdown rate.

AND maintaining less than o 100 F/h cooldown rate. l l

EOP-7 R v. 1/ Unit 2 PCg3 21 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS i I AA. ENERGIZE SUPPORT EQUIPMENT AS NECESSARY TO FACILITATE SHUTDOWN AND VERIFY LOAD REMAINS WITHIN RATINGS: 

                   - CAUTION -

If the following load limits can be maintained, actuation of the LOCI Sequencer will not cause a D/G ove-'.oad condition y thout 23 AEW Pump - 1400 KW th 23 AEM Pump - 1800 KW These limits may be exceeded if additional power is required to safely, efficiently shut down the plant. The D/G should not be operated above 3250 KW. 

                   - CAUTION -

SMECO load limit is 260 AMPS.

1. Start a Main Exhaust Fan.
2. Start Containment Air Cooler (s) in LOW to maintain containment temperature below 120 F.
3. Start a Cavity Cooling Fan to maintain cavity cogling temperature below 200 F.
4. If "SFP LEVEL TEMP HI" alarm received, THEN start Spent Fuel Fool Cooling Pump (s).
5. Strip MCC-201AT and MCC-201BT of all Ivads, by opening individual MCC breakers.

EOP-7 R v. 1/ Unit 2 PCgo 22 of 36 III. RECOVERY ACTION _S bLTERNATE ACTIONS ( l .

6. If 24 4KV Bus is energized AND 21 4KV Bus is NOT energized,

_TTIEN tie MCC-201 AT to MCC-201BT:

a. Close MCC-201BT reeder Breaker, 52-2419.
b. Open MCC-201AT Main Feeder Breaker, 52-20101,
c. Close Tie Breakers:

52-20120 52-20160

d. Energize loads per step AA.9, page 23.
7. IF 21 4KV Bus is energized AND 24 4KV Bus is NOT anergized, MLEN tie MCC-201BT to l I MCC-201AT:
a. Close MCC-201AT Feeder Breaker, 52-2109.
b. Open MCC-201BT Main Feeder Breaker, 52-20141.
c. Close Tie Breakers:

52-20120 52-20160

d. Energize loada per step AA.9, page 23.

EOP-7 Rcv. 1/ Unit 2 Pcga 23 of 36 III. _RE_C_0_VERY _ ACTION _S AI.TERNATElCTIONS l I .

8. IF both 21 AND 24 4KV Buses are energized,

_IM energize MCC-201AT T and MCC-201BT:

a. Close MCC-201AT Feeder Breaker, 52-2109.
b. Close MCC-201BT Feeder Breaker, 52-2419.
c. Energize loads per step AA.9, page 23.
9. Energize MCC-201AT and MCC-201BT loads:
a. Turbine Building Lighting Transformer Breaker, 52-20103.
b. Turbine 011 Lift Pump Breaker, 52-20106.

l l c. Turbine Turning Gear Motor Breaker, 52-20105,

d. Distribution Panel 21 Breaker, 52-20116.
e. 21 S/G Feed Pump Turning Gear Breaker, 52-20121.
f. AFW Pump Room Air Conditioner Breaker, 52-20150.
g. 22 S/G Feed Pump Turning Gear Breaker, 52-20161,
h. Distribution Panel 211 Breaker, 52-20162.
1. SRW Pump Room Vent Fan, 1 5ng 52-20149 (Restart SRW N7 Pump Room Ventilation, 8g per 01-15). l l

1 { I i I

EOP-7 R v. 1/ Unit ? PCga 24 of 36 III. RECOVERY ACTIONS ALTERNATE ACT_I_ONS l I U$ 

=

i E

10. If emergency power requested by Security, TI M place disconnect switch 2Y211, located on the North wall of Unit 2 27 ft
  • Switchgear Room, in the EMERGENCY position.

AB. MINIMIZE 250V DC BATTERY DISCHARGE: l l

1. Energize 15 or 25 Battery Charger on 13 250V DC Bus.
2. Ensure Main Turbine has stopped rotating or is on Turning Gear.
3. Verify Bearing oil Pump running.
4. Stop Turbine Emergency Oil Pump and place handswitch in AUTO.
5. If bearing oil header pressure less than 15 PSIG,

_THEN start Turbine Emergency 011 Pump. l l

EOP-7 R;v. 1/ Unit 2 Pcg3 25 of 36 g III. RECOVERY ACTIONS ALTERNATE ACTIOt[S i I AC. LOWER MAIN GENERATOR HYDROGEN PRESSURE TO 2 PSIG:

1. Throttle open Generator Bottom Vent To Atmosphere Valve, 2-0-06.
2. MREN Main Generator hydrogen pressure decreases to 2 PSIG, THEN perform the followings
a. Shut 2-G-06.
b. Secure Emergency Air Side Seal Oil Pump. ,

AD. IF LOCI SEQUENCER IS ACTUATED AND TURBINE MCCs ARE BEING SUPPLIED BY D/G, THEN DE-ENERGIZE MCC-101AT AND MCC-201BT.

1. IF rapid D/G load reduction 1.1 IF rapid D/G load needed, reduction NOT needed, THEN perform the following: THEN perform the following locally:
a. Open 21A 480V Bus Feeder Breaker, 52-2112. a. Open MCC-201AT Main Feeder Breaker,
b. Open 24B 480V Bus Feedet 52-20101.

Breaker, 52-2413.

b. Open MCC-201BT Main 4
c. Locally open MCC-201AT Feeder Breaker, Main Feeder Breaker, 52-20141.

52-20101,

d. Locally open MCC-201BT Main Feeder Breaker, 52-20141,
e. Close 21A 480V Bus Feeder Breaker, 52-2112.
f. Close 24B 480V Bus Feeder Breaker, 52-2413.

l I

l EOF-7 l Rsv. 1/ Unit 2 Pcga 26 of 36 l III. RECOVERY ACTIONS  % TERNATE _ ACTIONS l I , AE. MAINTAIN VCT LEVEL BETWEEN 60 AND  ; 100 INCHES:

1. WilEN VCT makeup required, THEN shift Charging Pump suction to RWT:
a. Open RWT To Charg3ng Pump Suction Valve, 2-CVC-504-MOV.
b. Observe VCT level 1.b.1 IE VCT level NOT increasing, increasing. THEN shut VCT Outlet Valve, 2-CVC-501-MOV.
c. Ensure Charging Pump (s) ,

AMPS steady.

2. WHEN VCT increases to 100 inches, THEN shift Charging Pump ,

suction to VCT: l l l

a. Open VCT Outlet Valvo, 2-CVC-501-MOV.

1

b. Shut RWT To Charging l Pump Suction Valve, l 2-CVC-504-MOV. l l

1 1 

 $                            >                                                                              l l

l l l

EOP-7 R v. 1/ Unit 2 PCgo 27 of 36 III. RECOVERY ACTIONS ALTERNATE ACTIONS k l AF. IF FORCED CIRCULATION DESIRED AND PUMP RESTART CRITERIA MET, THEN RESTART RCPs WHEN POWER AVAILABLE: 

                 - CAUTION -

Uncontrolled restoration of cooling to hot RCP seals may cause degradation of the metallic seating surfaces by thermal shock.

1. IF Component Cooling is isolated to RCP seals, THEN reduce RCP lowern seal .,

temperature below 280 F prior to initiating full cooling flow to the RCPs:

a. Shut Component Cooling Supply Containment Manual Isolation Valve, 2-CC-284, I I located in 5 ft East Penetration Room.
b. Open Component Cooling Containment Isolation Valves:

2-CC-3832-CV 2-CC JC33-CV

c. Slowly open 2-CC-284 to throttle component cooling flow until lower seal temperatgres are less than 280 F.
d. WHEN lower seal temperatgres are less than 280 F, IgEN fully open 2-CC-284.

l I

EOP-7 R v. 1/ Unit . Pcg3 28 of 36 III. RECOVERY ACTIONS ALTER _NATE ACTIONS i I .

2. IF an RCP lower seal temperature exceeded 280 F, THEN an engineering evaluation is required prior to restarting that RCP.
3. Raise pressurizer level to at least 155 inches.
4. Lovgr Tcold to less than 525 F.
5. Verify RCP restart criteria
a. RCS subgooling greater than 30 F.
b. At least one S/G available for heat removal,
c. Pressurizer level greater than 155 inches and stable,
d. Tcold less than 525 F.

l l

e. RCS temperature and pressure greater than the minimum operating limits per RCP curve on Attachment (1).
                    - NOTE -                                                                                                       l l

l Starting an RCP may cause a pressurizer level transient.

6. WHEN RCP restart criteria j are met, THEN start one RCP in a loop with an operable S/G:
a. Verify "COMPT CLG FLOW LO" alarm clear.

l I

EOP-7 RCv. 1/ Unit 2 Page 29 of 36 III. RECOVERY ACTIONS ALTERNATE _ ACTIONS

b. Start Oil Lift Pump.
c. Insert RCP sync stick.
d. Start one RCP.
e. Monitor RCP running current:

Tavo Current 525 to 572 F 238 to 210 AMPS and steady 210 to 525 F 264 to 238 AMPS and steady

7. Monitor RCP seal parameters following pump restart.
8. Allow backflow to equalize temperatures in opposite loop.

( ) 9. Start second RCP in opposite loop per steps AF.6 and AF.7, pages 28 and 29.

10. Secure Auxiliary Sprays
a. Open Loop Charging Valves:

2-CVC-518-CV 2-CVC-519-CV

b. Shut Auxiliary Spray Valve, 2-CVC-517-CV. ,
c. Shift Pressurizer Spray Controller, 2-HIC-100, to AUTO.
11. WHEN RCPs restarted, .

3102i implement appropriate l operating procedure AND i complete administrative  ! l post-trip actions of this procedure. l,

EOP-7 RCv. 1/ Unit 2 Pcga 30 cf 36 III. RECOVERY _ ACM' IONS ALTERNATE ACTIONS I I AG. DETERMINE TIME UNTIL COOLDOWN REQUIRED:

1. Determine total water available for use as makeup.
2. Determine time until commencement of required cooldown per Attachment (11),
3. If RCS cooldown required, 3.1 If RCS cooldown NOT JJURf implement Natural required, Circulation Cooldown (AOP-3F) TREN inplement Loss of 6ND complete admioistrative Flow / Natural Circulation post-trip actions af thir ,(AOP-2E) bHD complete procedure, admin:istrative post-trip actions of this procedure.

I I I >

EOP-7 R;v. 1/ Unit 2 PCgo 31 cf 35 I I  % AH. ADMINISTRATIVE POST-TRIP ACTIONS: 

                                                                     - HOIE -

The following actions may be accomplished whenever feasible. They may be done in any order.

1. Refer to ERPIP to determine appropriate emergency response actions.
2. Perform notifications per CCI-118.
3. Notify ESO of trip.
4. Request RCS Boron and Iohine sample,
5. Perform shutdown margin calculation per NEOG 9 and 11.
6. Complete transient log entries per CCI-301.

l l 7. Recall post-trip review (preferably within 30 minutes of trip).

8. Perform post-trip review per CCI-111, 1
9. Monitor turbine bearing temperatures.
10. Continue Main Turbine shutdown per applicable step of OI-43A.

END OF SECTION III. l l

EOP-7 R;v. 1/ Unit 2 Pcga 33 of 36 l l IV. #METY FUNCTION STATUS CIIEC]; A. The STA (or person designated by STA) will perform the intermediate and final safety function checks respectively on entry and prior to-exiting from this procedure. B. Perform intermediate safety function status checks at 10 minute intervals until plant conditions stabilize. C. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied. D. Review data and verify that safety function af.ceptance et)teria are satisfied. E. When EOP completed, then perform final safety function check. REACTIVITY SAFETY FUNCTICM ACCEPTANCE CRITERIA CONTROL , PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK l I

a. WRNI power at RPS less than 3% ,,,,,,,,,, less than 1%
b. SUR (DPM) at RPS negative __,,,,,,,,

O _ ,, When Power Restored

c. CEA status all inserted all inserted or Boration status:

appropriate concentation increasing ,,,,,...... S/D margin _ BAST level decreasing ,,,,,,,,,, N/A N/A _

EOP-7 R v. 1/ Unit 2 Pego 33 of 36 RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND !!NENTORY PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL , CHECX CHECK

c. Jressurizer less less pressure (PSIA) than 2300 ,,,,,,,,,,

than 2300

b. Pressuritor level (anches) (1) 50 to 180 ,,,,,,,,,,

130 to 100 , 30 to 140 30 to 140

c. Rgs subcooling ,,,,,,,,,,

( F) (2) (1) Pressurizer leval may decrease below 50 inches depending upon RCS leakrate and time power unsvailable. (2) ROS cubcooling may decrease below 30 F depending upon RCS leakrate and time power unavailable. If CET temperatures remain less than or equal to saturation temperature, for existing RCS pressure, then the i l l Core is covered. s I 1 l

EOP-7 Rev. 1/ Unit 2 Page 36 of 36 l I CORE AND RCS SAFETY FUNCTION ACCEPTANCE f 3RIA REAT REMOVAL PARAMETERS CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK , a. RCS Tcold ( F) less than 545 ________ less than 535

b. CET ( F) (3) constant constant or decreasing ________

or decreasing C

c. TgotminusTcold

( F): Natural Circulation 10 to 50 __.,_____ 10 to 50 Forced Circulation N/A ________ less than 5 5

d. S/G pressure (PSIA) less than less than 1000 __,____,

920

e. S/G level (inches) (-)170 :o (-)24 to

(+)30 ________ (+)30

f. Condensate Storage greater greatyc.  ;

Tank level (ft) than 5 ________ than 5 (3) CET temperatures ma/ increase while Natural Circulation is being established. I 1 I

EOP-7 Rnv. 1/U, tit 2 Page 35 of 36 l I 

                                                                   /

VITAL SAFETY FUNCTION ACCEPTANCE CRITERIA AUXILIARIES CRITERIA INTERMEDIATE CRITERIA FINAL , CHECK CHECK l l

c. 4KV vital buces one l 21 and 24 (4) de-energized ,,_________

energized

b. Instrument Air greater I pressure (PSIG) (4) decreasing ____,,____

than 88

c. Component Cooling

(# pumps running)(4) O __________ 1 or 2

d. Component Cooling Head Tank level greater than greater (inches) (5) 30 __________

than 20

o. Saltwater  !

(# pumps running)(4) 0 __________ 1 or 2 __ i I f. Service Water (# pumps running)(4) O __________ 1 or 2

g. Service Water Head Tank level greater than greater (inchec) (5) 30 __________

than 30 battery

h. 125V DC buses charger 11, 12, 21, 22 energized __________

energized

i. 120V AC vital battery buses charger 21, 22, 23, 24 energized __________

energized (4) Intermediate criteria based on initial conditions prior to restoration of a 4KV vital bus. (5) Refer to 01-15 and 01-16 for filling head tanks. l 1

EOP-7 Rcv. 1/ Unit 2 Pcga 36 of 36 I I NORMAL SAFETY FUNCTION ACCEPTANCE CRITERIA CONTAINMENT > ENVIRONMENT CRITERIA INTERMEDIATE CRITERIA FINAL PARAMETERS CHECK CHECK

a. Containment pressure (PSIG) N/A ___ __

less than 0.7

b. Containment tgmperature N/A

( F) N/A _________ less than 120

c. Containment level
                                                             .N/A           less than 4 (inches)                    N/A             _________

NORMAL RADIATION SAFETY FUNCTION ACCEPTANCE CRITERIA LEVELS EXTERNAL l I TO CONTAINMENT CRITERIA INTERMEDIATE CRITERIA FINAL CHECK CHECK

a. Noble Gas Monitor (6) alar' alarm clear _________,

clear (6) Available when power restored. STATUS CHECK COMPLETE AT NUMBER TIME ) 1 2 3 4 _ j

EOP-8 i R0v. 1/ Unit 1 I Pcg3 1 of 49 l I CALVERT CLIFFS NUCLEAR POWER PLANT EOP-8 FUNCTIONAL RECOVERY PROCEDURE REVISION 1 l I SIGNATURE DATE I PREPARED BY; _ M1 ) e ~~ / / 2 [/ 6/hi' 7 t'A N 7 > N-N I\ / VERIFI . POSRC; MEETING # f3 -7 

                                                    / 2-\c %

APPROVED BY; 7-A A n.m w / D \C *'E % ' Ma'ndg'eMNuclear Operations or General Supervisor-Operations if POSRC review la not required j l l 1

I E0P-8 Rr,v . 1/ Unit 1 Pcga 2 of 49 l I LIST OF EFFECTIVE PAGES PAGE NUMBER REVISION PAGE NUMBER REVISION 1 1 25 ,, 1 2 1 26 1 3 1 27 1 4 1 28 1 5 1 29 1 6 1 30 1 7 1 31 1 8 1 32 1 9 1 33 1 10 1 34 1 11 1 35 1 12 1 , 36 1 13 1 37 1 14 1 38 1 15 1 39 1 16 1 40 1 17 1 41 1 18 1 42 1 i 19 1 43 1 { } 20 1 44 1 21 1 45 1 22 1 46 1 23 1 47 1 24 1 48 1 49 1 5

EOP-8 Rcv. 1/ Unit 1 Pega 3 of 49 l I ' I. ENTRY CONDITIONS The operator should enter the Functional Recovery Procedure under the following circumstances: A. EOP-O has been completed but an event diagnusis cannot be made. OB B. An event diagnosis has been made and one of the EOP-1 through 7 procedures has been implemented but one or more safety functions are not meeting their acceptance criteria and the reason for the violation has not been established. OB l 1 I C. An event diagnosis has been*made and one of the EOP-1 through 7 procedures has been implemented but a subset of l parameters for a single safety function are not meetir.g l their acceptance criteria and the Shift Supervisor desires j to reference EOP-8 to obtain additional guidance for a specific problem. I I For the conditions of A or B, EOP-8 should be implemented in its entirety. The safety functions with the out of spec acceptance criteria should be addressed first. When EOP-8 is implemented, the safety function stntus check of EOP-8 should be implemented until an appropriate optimum recovery procedure is selected. EOP-3 need not be implemented if the parameters of a safety function are outside of their acceptance criteria andr

1. Reason for the vialation has been established, MD
2. Action has been identified that will return the parameter (s) to within their acceptance criteria, SND
3. The Shift Supervisor determines the recovery of the out of spec parameter (s) to within acceptance criteria to be imminent.

I I

EOP-8 R;v. 1/ Unit 1 Pcgo 4 of 49 RCACTIVITY CONTROL I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function. B. Systems shifted to manual operation must be monitored frequently to ensure correct operation. C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments. , D. The operator should not leave reactivity contrcl until this function is fulfilled. If necessary, other urgent safety functions may be pursued in parallel but attempts to establish reactivity control must be continued until the acceptance criteria are met. E. If possible, maintain RCS temperature greater than 515 F until $ I reactivity control criteria are satisfied. F. The concontration of boron in RCS makeup water should be consistent with maintaining the required shutdown margin. 3 G. When borating the RCS it is possible for a large difference in boron concentration to develop between the RCS and pressurizer fluids if main or auxiliary spray is not operated at intervals. If spray is unavailable, the RCS boron concentration should be increased by 50 ppm to maintain the required shutdown margin should a pressurizer outsurge occur. l I

EOP-8 Rcv. 1/ Unit 1 Page 5 of 49 l l I II. REACTIVITY CONTROL ACCEPTANCE CRITERIA A. IF any of the following conditions exist:

1. All CEAs inserted and WRNI power decreasing.

9B

2. RCS boration in progress and WRNI power decreasing.

9B

3. WRNI power less than 10 ~4 % and constant or decreasing.

THEN Reactivity Control Safety Function is satisfied. B. WHEN Reactivity Control Safety Function is satisfied, THEN proceed to the next safety

  • function in jeopardy.

III. RECOVERY ACTIONS A. INITIATE REACTOR SHUTDOWN BY CEA INSERTION: 12 Depress both sets of Manual Reactor Trip Buttons. 9B

2. De-energize CEDM Motor Generator Sets:
a. Open feeder breaker to 12A 480V Bus,
b. Open feeder breaker to 13A 480V Bus.
c. Open tie breakers to 12A and 13A 490V Buses.

9B 32 Depress local Emergency Trip Buttons on the Trip Circuit Breakers. OR l I l l [

EOP-8 R;v. 1/ Unit 1 Pcgo 6 of 49 I l B. INITIATE REACTOR SHUTDOWN BY BORATION: 12 Establish charaino flowpath to RCS:

a. Normal CVCS lineup:

(1) Open Loop Charging Valves: 1-CVC-518-CV 1-CVC-519-CV (2) If Loop Charging Valves shut, THEN charging may continue through Loop Charging Valves Bypass Valve, 1-CVC-188. OR

b. Charging through Aux HISI Header:

(1) Open SI Discharge To Charging Header Core Flush Valve, 1-CVC-269-MOV. { l (2) Shut Charging Header Containment Isolation Valve, , 1-CVC-183, located in > ft West Penetration Room. (3) Shut HPSI Aux Header Isolation Valve, 1-SI-656-MOV. (4) Shut Letdown Isolation Valves: 1-CVC-515-CV 1-CVC-516-CV (5) Open any one of the four Aux HPSI Header Valver: 1-SI-617-MOV 1-SI-627-MOV 1-SI-637-MOV 1-SI-647-MOV 22 Establish boric acid flowpath to Charcing Pumps:

a. BAST Lineup (1) Ensure BAST levela greater than zero.

(2) Shut VCT Makeup Valve, 1-CVC-512-CV. I (3) Open Boric Acid Direct Makeup Valve, 1-CVC-514-MOV. l

EOP-8 Rcy. 1/ Unit 1 Page 7 of 49 i I (4) Open BAST Gravity Feed Valves: 1-CVC-508-MOV 1-CVC-509-MOV (5) Shut VCT Outlet Valve, 1-CVC-501-MOV. (6) Start Boric Acid Pumps. (7) Start all available Charging Pumps. (8) Ensure Charging Pump discharge prer,sure greater than RCS pressure. OR

b. RWT Lineup: ,

(1) Ensure RWT level greater than 2 ft. (2) Open RWT To Charging Pump Suction Valve, 1-CVC-504-MOV. q g (3) Shut VCT Outlet Valve, 1-CVC-501-MOV. (4) Start all available Charging Pumps. (5) Ensure Cnarging Pump discharge pressure greater than RCS pressure. 

                                                                                     - -_____ -    a

EOP-8 R0v. 1/ Unit 1 Page 8 of 49 l I RCS PRESSURE AND INVENTORY CONhROL I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function. B. Systems shifted to manual operation must be monitored frequently to ensure correct operation. C. At least two independent indications should be used, wh i available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments. , D. Solid watgr operation of the Pressurizer should be avoided unless 30 F subcooling cannot be maintained. If the RCS is solid, closely monitor RCS makeup or letdown and avoid system heatup or cooldown rates which could induce rapid pressure excursions. j l E. Indications of high RCS inventory (high pressurizer level) may be caused by the displacement of water from voided areas of the RCS. Operation of letdown under these conditions may lower RCS pressure and, subsequently, increase RCS voiding. l l

I EOP-8 rov. 1/ Unit 1 Pcgo 9 of 49 i > . II. RCS PRESSURE AND INVENTORY ACCEPTANCE CRITERfA A. IF either of the following conditions exist:

1. RCS pressure and temperature are within the limits per Attachment (1) and:
a. Pressurizer level is between 35 and 250 inches.
b. RCS subcooling is greater than 30 F, using CET temperatures.
c. RVLMS indicates that the Core is covered.

OB

2. RCS prensure and temperature are within the limits per Attachment (1) and:
a. All available Charging Pumps running,
b. HPSI and LPSI Pumps are injecting water into RCS per Attachments (12) and (13).

g g c. RVLMS indicatos that the Core is covered. THEN RCS Pressure and Inventory Safety Function is satisfied. B. WHEN RCS Pressure and Inventory Safety Function is satisfied, THEN proceed to the next safety function in jeopardy. III. RECOVERY ACTIONS A. ENSURE AUTOMATIC CONTROL OF PRESSURIZER LEVEL AND PRESSURE: 12 Manually operate control systems which are not providing correct automatic control of pressurizer level or pressure:

a. 1F Pressurizer Level Control System NOT restoring level to 160 inches, THEN manually operate charging and letdown to stabilize level in indicating ranga.
b. IF Pressurizer Pressure Control System NOT restoring pressure to setpoint value,

( ) THEN manually operate heaters and sprays to maintain RCS subcooling between 30 and 140 F. l

EOP-8 Rav. 1/ Unit 1 Page 10 of 49 l I 2 Ensure automatic protective actions occurs

a. Verify PORVs open at 2400 PSIA and shut by 2300 PSIA.
b. IE RCS pressure decreases to 1725 PSIA, THEN verify SIAS actuation AND commence SIAS Verification Checklist, Attachment (2),
c. JF RWT level decreases to between 0.5 and 1.0 ft QR "ACTUATION SYS RAS TRIPPED" alarm received, THEN verify RAS actuation AND commence RAS Verification Checklist, Attachment (6).

B. MONITOR FOR RCP TRIP CRITERIA. 11 Trip RCPs as indicated below:

a. If RCS pressure decreases to 1725 PSIA, THEN trip 11A and 12B RCPs QR trip 11B and 12A RCPs.

j g b. IE RCS pressure decreases to less than 1300 PSIA, THEN trip all RCPs.

c. IE CIS has actuated, THEN trip all RCPs.

C. MAINTAIN ADEQUATE WATER SUPPLY TO PUMPS CONTROLLING RCS INVENTORY: 

                                                                        - CAUTION -

Long term injection of concentrated boric acid could result in degraded core heat removal due to plating out the boron. 1._ Charcino Pumps alloned to BASTS using Boric Acid Pumps:

a. Shut VCT Makeup Valve, 1-CVC-512-CV.
b. Open Boric Acid Direct Makeup Valvo, 1-CVC-514-MOV.
c. Start a Boric Acid Pump.
                             ~OR l                     l

EOP-8 R;v. 1/ Unit 1 Page 11 of 49 l I 21 Charaino Pumps aligned to BAST 3 usind cravity feed:

a. Shut VCT Makeup Valve, 1-CVC-512-CV.
b. Open BAST Gravity Feed Valves:

1-CVC-508-MOV 1-CVC-509-MOV

c. Shut VCT Outlet Valve, 1-CVC-501-MOV.

9B 31 Charoing Pumps aligned to VCT:

a. Ensure VCT level greater than 50 inches.
b. Open VCT Outlet Valve, 1-CVC-501-MOV.

9B l 42 Charging Pumps alioned to RWT: g a. Open RWT To Charging Pump Suction Valve, 4 1-CVC-504-MOV.

b. Shut VCT Outlet Valve, 1-CVC-501-MOV.
c. Shut Boric Acid Direct Makeup Valve, 1-CVC-514-MOV.
d. Secure Boric Acid Pumps.

9B 51 HPSI and LPSI Pumps aligned to RWT:

a. Open RWT Outlet Valves:

1-SI-4142-MOV , 1-SI-4143-MOV ( (

b. Ensure RWT level greater than 4 ft.

9B

EOP-8 RCv. 1/ Unit 1 Page 12 of 49 I I 61 HPSI and LPSI Pumps aligned to containment sump:

a. Monitor containment water level to ensure adequate suction water supply,
b. Place SI Pump Mini Flow Lockout Switches in ON.

F

c. Commence RAS Verification Checklist, Attachment (6).
d. Shut RWT Outlet valves:

1-SI-4142-MOV 1-SI-4143-MOV w D. MAINTAIN AT LEAST ONE RCS MAKEUP PATH: 12 Normal charcino patb:

a. Open Loop Charging Valves:

1-CVC-518-CV { } 1-CVC-519-CV

b. IF Loop Charging Valves shut, THEN charging may continue through Loop Charging Valves Bypass Valve, 1-CVC-188.

9B 21 Charging through Aux HPSI Header:

a. Open SI Discharge To Charging Header Core Flush Valve, 1-CVC-269-MOV.
b. Shut Charging Header Containment Isolation Valve, 1-CVC-183, located in 27 ft West Penetration Room.
c. Shut HPSI Aux Header Isolation Valve, 1-SI-656-MOV.
d. Shut Letdown Isolation Valves:

1-CVC-515-CV 1-CVC-516-CV l I

EOP-8 R;v. 1/ Unit 1 Page 13 of 49 i I

e. Open any one of the four Aux HPSI Header Valves:

1-SI-617-MOV 1-SI-627-MOV 1-SI-637-MOV 1-SI-647-MOV OB 32 HPSI Pump makeup to RCS in SIAS or RAS mode:

a. Check RCS pressure less than 1270 PSIA.
b. IF RCS pressure greater than 1270 PSIA, THEN depressurize per guidelines in step F.2.e., page 18.
c. Open Main and Aux HPSI Uendor Valves:

1-SI-616-MOV 1-SI-617-MOV 1-SI-626-MOV 1-SI-627-MOV 1-SI-636-MOV 1-SI-637-MOV 1-SI-646-MOV 1-SI-647-MOV l l 42 LPSI Pump makeup,

a. Check RCS pressure less than 180 PSIA.
b. Open LPSI Header Valves:

1-SI-615-MOV 1-SI-625-MOV 1-SI-635-MOV 1-SI-645-MOV E. ESTABLISH AND MAINTAIN RCS MAKEUP FLOW: 12 Charging Pump makeup

a. Start all available Charglac Pumps.
b. Ensure Charging Pump discharge pressure greater than RCS pressure,
c. Ensure pump running current between 75 and 95 AMPS.

l I OR I

EOP-8 Rcv. 1/ Unit 1 Page 14 of 49 l I 22 HPSI Pump makeup in SIAS mode:

a. Start 11 and 13 HPSI Pumps,
b. IE 11 or 13 HPSI Pump fails, THEN start 12 HPSI Pump AND align to appropriate header.
c. Verify HPSI flow per Attachment (12).

98 32 HPSI Pump makeup in RAS mode:

a. Start 11 or 13 HPSI Pumps,
b. If HPSI flow greater th9 n 1000 GPM with two HPSI Pumps operating, l THEN equally throttlei HPSI flov to 1000 GPM.
c. IE HPSI flew greater than 600 GPM with one HPSI Pump operating, THEU equally throttle HPSI flow to 600 GPM.

l I - CAUTIQU - To prevent pump damage, minimum flow per operating HPSI Pump is 30 GPM.

d. If HPSI Pump cavitation occurs in recirculation mode, THEN throttle HPSI flow per Attachment (12).
e. If Attachment (12) does NOT allow throttling HPSI i flow, I THEN align Containment Spray Pump (s) to HPSI Pump l suction:

(1) IE 11 HPSI Pump cavitating,  ! THEN open 11 SDC HX To HPSI Suction Valve, 1-SI-653-MOV AND start 11 Containment Spray Pump. (2) If 13 HPSI Pump cavitating, v To HPSI Suction Valvo, THEN open 12 SDC li. 1-SI-662-MOV AND start 12 Containment Spray Pump. 9B I I

EOP-8 Rcv. 1/ Unit 1 Page 15 of 49 l I l i 42 LPSI Pump makeugi

a. Place 11 or 12 LPSI Pump RAS Override Switch in OVERRIDE.
b. Start selected LPSI Pump.
c. Verify LPSI flow per Attachment (13).

F. MAINTAIN SUBCOOLED MARGIN BETWEEN 30 AND 140 F: 

                                            -CAUTION-The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

12 Raise subcooling by any of the following: _ NOTE-g Pressurizer Backup Heater Banks 11 and 13 trip on U/V and SIAS.

a. Energize Pressurizer Heater (s).

OR

b. Operate Turbine Bypass or Atmospheric Dump Valves to maximize RCS gooldown, while maintaining cooldown rate less than 100 F/h.

OR

c. IF unable to obtain desired cooldown rate with Turbine Bypass and Atmospheric Dump Valves, THEN use steam driven AFW Pump (s) to increase cooldown rate.

OR

d. Raise HPSI flow to RCS.

OR I I f _ - - - - - - - - --

EOP-8 R0v. 1/ Unit 1 Pcg3 16 of 49 l I

e. Charging system pressurization:

(1) Charge as necessary to maintain at least 30 F subcooling. (2) IF high pressurizer level secures backup Charging Pumps AND more than one Charging Pump required, THEN locally initiate SIAS A6 and B6 AND secure # Boric Acid Pump as needed. (3) Secure Charging Pumps not required to maintain subcooling. OR

f. Solid plant pressurization (1) Station a dedicated' pressure control watch at the JC05 and IC06 panels.

(2) Verify letdown flowpath operable. (3) Secure all but one Charging Pump by placing in PULL-TO-LOCK. (4) Charge as necessary wgth remaining pump to maintain a minimum 30 F subcooling. (5) Closely monitor makeup or draining and any heatup or cooldown to avoid rapid pressure excursions. 22 Lower subcoolina by any of the following:

a. De-energize Pressurizer Heater (s).

OR

b. Lower RCS cooldown rate.

OR 1 1

EOP-8 R;v. 1/ Unit 1 Page 17 of 49 l I

c. IFthefollowingconditionscanbemaintained:

(1) At least 30 F subcooling. (2) Pressurizer level greater than 101 inches. (3) At least one S/G available for heat removal. (4) RVLMS indicates that the Core is covered. THEN throttle HPSI or charging flow as necessary to maintain subcooling between 30 and 140 oF. OR -

d. Initiate Auxiliary Spray (1) Place Instrument Air CIS Override Switch, 1-HS-2080A, in OVERRIDE.

(2) cpen Cntmt Instrument Air Isolation MOV, 1-IA-2080-MOV. g (3) Record temperature differential between Pressurizer and Regenerative Heat Exchanger Outlet. (4) Open Auxiliary Spray Valve, 1-CVC-517-CV. (5) Shut Loop Charging Valves: 1-CVC-518-CV 1-CVC-519-CV _-_ NOTE-1-HS-2085 located on West wall of 27 ft Switchgear Room; Key #85 in Control Room Key Locker. (6) Open Cntmt Instrument Air Supply CV, 1-IA-2005-CV, by momentarily placing 1-HS-2085 in OPEN. (7) Shif t Pressurizer Spray Valve Controller, 1-HIC-100, to MANUAL and shut Pressurizer Spray Valves: 1-RC-100E-CV 1-RC-100F-CV l l

EOP-8 R v. 1/ Unit 1 Page 18 of 49 l I (8) Maigtain pressurizer cooldown rate less than 200 F/h. OR

e. PORV depressurization:

(1) Shift Letdown Control Valve Controller, 1-HIC-110, to MANUAL and shut Letdown Control Valves: 1-CVC-110P-CV 1-CVC-110Q-CV (2) De-energize the Pressurizer Heaters ny placing all handswitches in OFF. (3) Start all available. Containment Air Coolers in HIGH with maximum SRW flow. (4) Open Main and Aux HPSI Header Valves: 1-SI-616-MOV 1-SI-617-MOV 1-SI-626-MOV 1-SI-627-MOV 1-SI-636-MOV 1-SI-637-MOV l I 1-SI-646-MOV 1-SI-647-MOV (5) Verify both PORV Block Valves open. (6) Start all available Charging Pumps. (7) Start 11 and 13 HPSI Pumps. (8) Pull two High Pressurizer Pressure Trip Units. (9) Verify PORVs open. (10) WHEU subcooling less than 140"F, THEU insert High Pressurizer Pressure Trip Units that were previously pulled AND ensure "PORV ENERGIZED" alarni clear. G. VERIFY RCS TEMPERATURE AND PRESSURE WITHIN THE LIMITS PER ATTACHMENT (1). l

EOP-8 R v. 1/ Unit 1 Page 19 of 49 l I CORE AN9 RCS HEAT REMOVAL' I. PRECAUTIONS A. Do not adopt manut.1 operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function. B. Systems shifted to manual operation must be monitored frequently to ensure correct operation. C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments. , D. If an initial RCS cooldown rate exceeds Technical Specification limits, the potential exists for pressurized thermal shock of the Reactor Vessel unless post accident pressure and temperature limits are restored and maintained. E. If both S/Gs boil dry, only attempt to refill one S/G to I k reinitiate core cooling. F. In Natural Circulation, increased loop transport time causes a 5 to 10 minute delay in temperature responses to a plant change. Pressurizer level and pressure responses, if available, typically provide better indication of RCS response during this period. G. If cooling down with a S/G isolated, an inverted delta T (Tcold higher than Thot) may be observed in the idlo loop. This is due to a small amount of reverse heat transfer in the isolated S/G. The inverted delta T is not expected to have any significant affect on natural circulation flow in the operating S/G loop. 1

EOP-8 Rov. 1/ Unit 1 Page 20 of 49 l I II. CORE AND RCS HEAT REMOVAL ACCEPTANCE CRITERI5 A. IF any of the following conditions exist:

1. One S/G with level between (-)250 and (+)50 inches and trending toward zero and
a. RCS flow by Forced Flow or Natural Circulation,
b. RCS subcooling greater than 30 F using CETs.
c. CET temperatures constant or decreasing,
d. RNLMS indicates that the Core is covered.

OB

2. One S/G with feedwater flow greater than 150 GPM and level being restored and:
a. RCS flow by Forced Flow or Natural Circulation.
b. RCS subcooling greater than 30 F using CETs.

l I c. CET temperatures constant or decreasing,

d. RVLMS indicates that the Core is covered.

OB

3. HPSI or LPSI Pumps injecting water into RCS and CET temperatures constant or decreasing.

OB

4. Once Through Core cooling in progress and CET temperatures constant or decreasing.

THEN Core and RCS Heat Removal Safoty Function is satisfied. B. MHEN Core and RCS Heat Removal Safety Function is satisfied, IIIEN proceed to the next safety function in jeopardy. l I

EOP-8 R;v. 1/ Unit 1 Page 21 of 49 III. RECOVERY ACTIONS A. MAINTAIN S/G OPERABILITY:

1. IF an uncontrolled cooldown occurs, THEN isolate both S/Gs
a. Shut both MSIVs.
b. Shut S/G Feedwater Isolation Valves:

4 1-FW-4516-MOV 1-FW-4517-MOV

c. Shut MSIV Bypass Valves: i i

1-MS-4045-MOV ) 1-MS-4052-MOV I

d. Shut AFW Steam Supply Valves by placing handswitches

{ } in CLOSE: 1-MS-4070-CV 1-MS-4071-CV

e. Shut AFW Block Valves by placing handswitches in CLOSE:

l 11 S/G _12 S/G I 1-AEW-4520-CV 1-AEW-4530-CV l 1-AEW-4521-CV 1-AFW-4531-CV 1-AEW-4522-CV 1-AFW-4532-CV 1-AEW-4523-CV 1-AEW-4533-CV

f. Shut Lpatream drains by placing handswitch 1-HS-6622 in CLOSE.
g. Shut S/G Blowdown Valves:

1-BD-4010-CV 1-BD-4011-CV 1-BD-4012-CV 1-BD-4013-CV

h. Shut Atmospheric Dump Valves.

EOP-8 Rcv. 1/ Unit 1 Pcga 22 of 49 l I

1. 1F one S/G has a steam line rupture, THEN maintain unaffected S/G operability durin9 blowdown phase per EOP-4, Step J, page 10.
j. WHEU cooldown rate less than 100 F/h,
               .THEN establish S/G(s) as heat sink.

9R 2 Control steam flow and_ maintain Tcold less than 540 F:

a. Operate Turbine Bypass Valves from Control Room. l OR
b. Operate Atmospheric Dump Valves from Control Room.

OR

c. Operate Atmospheric Dump Valves from 1C43:

(1) Verify 1C43 Atmospheric Dump Controllers at 0% output. (2) Align Hand Transfer Valves to IC43 position: 1 11 S/G 12 S/G 1-HV-3938A 1-HV-3939A 1-HV-3938B 1-HV-3939B (3) Open Atmospheric Dump Valve (s) using IC43 controller (s). OR 

                                   -HOTE-Atmospheric Dump Valves are reverse acting,     i.e., clockwise to open, counterclockwise to shut.
d. Manually open Atmospheric Dump Valves by using chain operator.

OR

e. Manually position Turbine Bypass Valves.

OR l I

EOP-8 R;v. 1/ Unit 1 Pcgo 23 of 49 I I 

                                 -CAUTION-operating history indicates F,G Safety Valves may fail to rescat completely after lifting.
f. Manually open S/G Safety Valves (1) Lower S/G pressure as low as possible using other heat remo'al methods prior to attempting manual operation of S/G Safety Valve.

(2) Operate manual lifting lever to open S/G Safety Valve. OR 

                                -CAUTION-The following step may blow out the condenser Rupture Disks and may cause equipment damage.
g. Align steam drains to Condenser:

(1) Open upstream drains by placing handswitch { } l-HS-6622 in OPEN. (2) Open downstream drains by placing handswitch 1-HS-6600 in OPEN. (3) IF MSIVs shut, THEN open MSIV Bypass Valves. OR 

                                -CAUTION-                              j The following step will blow out the Condenser Rupturo Disks and may cause equipment damage.
h. IF additional heat removal required AND condenser vacuum NOT available, TI(EN open Turbine Bypass Valve (s):

(1) Open all doors to the outside on the 45 ft Turbine Building. (2) Notify personnel to evacuato 45 ft Turbino I Building. i l q g (3) Manually operate Turbine Bypass Valve (s) as directed by Control Room personnel. l l

EOP-8 R:v. 1/ Unit 1 Page 24 of 49 h I

3. Control Main Feedwater flow to S/Gs:
a. Ensure main feed rate is maitataining a constant level or controlled increase in S/G level.
                                 -CAUTION-Severe waterhammer may occur if Main Feed Ring is allowed to drain then subsequently refilled.
b. Establish a shutdown feed system lineup:

(1) One operating S/G Feed Pump. (2) One operating Condensatte Booster Pump. (3) One operating Condensate Pump. (4) Both Heater Drain Pumps tecurod.

c. WHEN manual control of feed flow rate desired OB S/G levels between (-)24 and (+)30 inches, THEN perform the following:

(1) Depress Feed Regulating Bypass Valve Reset Buttons. (2) Adjust Feed Regulating Bypass Valve (s) to raise S/C levels to approximately 0 inches.

d. WHEU S/G levels are 0 inches, THEU shift Feed Regulating Bypass Controllers to AUTO.

OB

4. IF Main Foodwater NOT available, THEN_ feed S/Gs with AFW:
a. Establish condensate sources:

(1) Confirm 12 CST operable: (a) Ensure 12 CST level greater than 5 ft. (b) Open 12 CST Unit 1 AEW Pump Suction Valve, 1-AFH-161. , 4 i , I l 

                                                                        =

EOP-8 Rav. 1/ Unit 1 Page 25 of 49 l I 

                                -CAUTICN, Before transferring AFW Pump suction to an alternate supply the possibility of suction line or CST rupture should be considered.

(2) IF 12 CST NOT operable, THEN line up 11 CST as alternate suction supply: (a) Locally open 11 CST AFW Pump Suction Valves: 1-AFW-131 1-AFW-167 (b) Local!) shut 12 CST Unit 1 AEW Pump Suction Valve, 1-AFW-161. (c) Confirm normal, CST level response. (OR) 

                                 -NOTE-                                   l The following step will cause CST levels to equalize.                  '

l k (3) IF 11 CST NOT available, ' TUEU line up 21 CST as alternate suction supply: 1 (a) Locally open 01 CST AFW Pump Suction Valves: , l 2-AFW-131 2-AFW-167 l tily open 12 CST AEW Pump Suction Valves: 

                           ..W-161 2-AFW-161 (c)  Confirm normal CST level response.

1 (OR)  ; 1 (4) Align Fire System to 13 AFW Pump ruction: ' (a) Shut 13 AFW Pump Suction Valvo, 1-AEW-182. (b) Connect fire hoses between pump suction und a fire main. (c) Open Fire !!ose Connection Isolation Valve, { ) 1-AFW-180. (OR)

i E0P-8 Rev. 1/ Unit 1 Page 26 of 49 (5) Align Fire System to 23 AFW Pump suction for cross connected operat. ion: (a) Shut 23 AFW Pump Suction Valve, 2-AFW-182. (b) Connect fire hoses between pump suction and a 3 , fire main. R (c) Open Fire Hose Connection Isolation Valve, 2-AEW-180. (OR) (#) ,IF Condensate Pump available, adEN transfer hotwell inventory to 11 CST: k (a) Shift Hotwell Level Controller, 1-LIC-4405-CV, to MANUAL. (b) Adjust Controllar to open Hotwell To CST Dump CV, 1-CD-4405-CV. (c) Shut one Condensate Pump Discharge Valvet { I 11 Pump 1-CD-106 12 Pump 1-CD-313 13 Pump 1-CD-120 (d) Start appropriate Condensate Pump. (e) Slowly open pump discharge valve to maintain flow rate loss than 2000 GPM. (f) Stop pum: 1en cadLation occurs. (q) Shut Hotwell To CST Dump CV, 1-CD-4405-CV. 

 ,                     (OR)

[ / ij (7) Emergency fill 11 UST from Fire Syst' - ' f, (a) Connect fire hose between firo house hose manifold and 11 CST Emergency Hose Connection

f. Valvo, 1-CD-312.
           ;h
           ,y (b)   Open 11 CST Emergency Hose Connection Valve, l-CD-312.

(c) E n s u r e .1 .' "ST level increasing. (OR)

EOP-8 R;v. 1/ Unit 1 Pego 27 of 49 i I (8) Emergency fill 21 CST from Fire Systems (a) Connect fire hose between fire house hose manifold and 21 CST Emergency Hose Connection Valve, 2-CD-312. (b) Open 21 CST Emergency Hose connection Valve, 2-CD-312. (c) Ensure 21 CST level increasing.

b. Establish AFW flowpaths (1) Open aJl motor and steam driven train AFW Block Valves:

11 S/G , _12 S/G 1-AFW-4520-CV 1-AFW-4530-CV 1-AFW-4521-CV 1-AFW-4531-CV 1-AFW-4522-CV 1-AFW-4532-CV 1-AFW-4523-CV 1-AFW-45,3-CV 

     .,     (2) IF AFW block Valve (s) will MOT open from Control

{ p Room, THEN locally open valve (s) using Hand Transfer Station (s) on North wall of SRW Room. (3) Open AEW Flow Control Valves: 11 S/G 12 S/G 1-AFW-4511-CV 1-AFW-4512-CV 1-AFW-4525-CV 1.-AFH-4535-CV (4) IF AFW Flow Control Valve (s) will NOT open, 4 THEN locally throttle open bypaes valve (s): 

                's)   4511-CV 11 S/C Bypass Valve, 1-AFW-163,        l located in 27 ft East Penetration Room.        )

l (b) 4525-CV 11 S/G Bypass Valve, 1-AEW-195, j located in SRW Room. i l (c) 4512-CV 12 S/G Dypass Valve, 1-AFW-165, l located '.n 27 f t East Penetration Room. j (d) 4535-CV 12 S/G Bypass Vrive, 1-AhW-196, I located in SRW Room. I I

i EOP-8 RSv. 1/ Unit 1 Page 28 of 49

c. Start at least one AFW Pump
                                    -CAUTION-D/G supplying power to 13 AFW Pump flow limit is 300 GPM:

otherwise, flow limit is 575 GPM. (1) Start 13 AEW Pumps (a) Place 13 AFW Pump Handswitch in START. (b) Ensure normal pump running current of 60 to 70 AMPS. (c) Ensure 13 AFW Pump flow of 150 GPM per S/G. (OR) , (2) Start 11 or 12 AFW Pump: (a) Open 11 and 12 AFW Pump Main Steam Supply Valves: 1-MS-109 l 1-MS-107 (b) Open 11 or 12 S/G AFh Steam Supply Valves: 1-MS-4070-CV 1-MS-4071-CV (c) Open 11 and 12 AFW Pump Turbine Throttle /Stop Valves: 1-MS-3986 1-MS-3988 (d) Verify 11 or 12 AFW Pump discharge pressure approximately 100 PSI greater than S/G pressure. l l (e) Verify 11 or 12 AFW Pump flow of 150 GPM per S/G. (f) Ensure nermal or emergency AFW Room Ventflation operable. l 1 (OR) i I 4

EOP-8 ROV. 1/ Unit 1 Pcg3 29 of 49 l I (3) IF unable to feed S/Gs with 0 nit 1 AFW Pumps, THEN establish Unit 2 to Unit 1 cross connect operations (a) Shut Unit 2 motor train AFW Bluck Valves: 2-AEW-4522-CV 2-AFW-4523-CV 2-AFN-4532-CV 2-AFW-4533-CV (b) Open Unit 2 to tinit 1 AFW Cross Connect Valve, 2-AEW-4560-CV. 

                                  -CAM 7 ION-l D/G Supplying power to 23 AFW Pump flow limit is 300 GPM; otherwise, flow limit is 575 GPM.

(c) Start 23 AEW Pamp by placing handswitch in START. (d) Ensure normal pump running current of 60 to l 70 AMPS. l I (e) Maintain 150 GPM flow to each S/G using Unit 1 AFW Flow Control Valves: 1-AEW-4525-CV 1-AFW-4535-CV I (OR) l l r l l l l 1 i i I l I ] l 

                                                                          ~  ,

l l

EOP-8 Rev. 1/ Unit 1 , Page 30 of 49 l I 

                                                            -CAUTION-D/G supplying power to 13 AFW Pump flow limit is 300 GPM; otherwise, flow limit is 575 GPM.

(4) Locally start 13 AEW Pumps (a) Press LLOSE button at 152-1116. 

                                                            -CAUTION-Removing control power fuses causes a loss of overcurrent, undervoltage and ground protection.

(b) IF breaker fails to close, THEN remove breaker control power fuses AND press CLOSE button at 152-1116. (OR) (5) Locally start 11 or 12 AFW Pump (a) Turn turbine governor control knob 

                  }

counterclockwipa to the minimum position. (b) Isolate the Instrument Air to the Turbine Governor Controller (s): 1-I/P-3987 ' 1-I/P-3989 (c) Open - filter drains on controllors to allow local control. (d) Open AFW Staam Supply Bypass Valves: 1-MS-102 1-MS-105 (e) Open 11 and 12 AFW Pump Turbine Throttle /Stop Valves: 1-MS-3986 1-MS-3988 (f) Adjust turbine gcVernor control knob to maintain AFh Pump discharge pressure 100 PSI , greater than S/G pressure. l I OR

a EOP-8 R;v. 1/ Unit 1 Pcg3 31 cf 49 I I

5. IF AFW flow to S/G NOT established ShD power available to Condensate and Condensate Booster Pump, THEN depressurize S/G to allow feeding with condensate Booster Pumps
a. Verify S/G heat removal available per step A.2, page 22.
b. Establish maximum cooldown rate not exceeding 100 F/h.
c. MHEN "SGIS A(B) BLOCK PERMITTED" alarm (s) received, 21DQi block SGIS A(B).
d. IF SGIS actuates, THFN block SGIS AND reset SGIS signal.

(1) Place Condensate Booster Pumps in PULL-TO-LOCK. (2) Match handswitches p,r SGIS Verification Checklist, Attachment (7). (3) Bleck SGIS. (4) Reset SGIS signal.

e. Open S/G Feedwater Isolation Valves,
f. Shut Main Feed Regulating Valves,
g. Depress Feed Regulating Bypass Valve Reset Buttons.
h. Manually adjust Feed Regulating Bypass Valve "e:.. rollers to 30% output.
i. Open Condensate Precoat Filter and Condensate Demin 6

Bypass Valves,

j. Verify one Condensate Pump running.
k. Verify one Conder. sate Booster Pump running.
1. Place Heat Drain Pump Handswitches in PULL-10-LOCK.

i i i l l

EOP-0 R;v. 1/ Unit 1 Pcg3 32 cf 49 l I NOTE-Feedwater flow to S/Gs should start when S/G pressure decreases to approximately 500 PSIA.

m. Monitor feedwater flow to S/G:

(1) Main Feed Regulating Valve Differential Pressure Controller indicates greater than O. (2) S/G level constant or increasing. 62 Establish RCS Flows

a. Ensure at least one RCP operating in a loop with an operable S/G.

OR

b. Confirm Natural Circulation in at least one operable S/G loops
                                 -NOTE-l I Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10).

(1) Thot minus Tcold between 10 and 50 F. (2) Tcold constant or decreasing. (3) Thot constant or decreasing. (4) CET temperatures consistent with Thot. (5) Steaming rate affectu primary temperature,

c. Monitor for Core and RCS voiding:
                                -CAUTION-Potential for void formation increases rapidly when pressure decreases below 1500 PSIA.

(1) Letdown flow greater than charging flow. i (2) Rapid unexplained increase in pressurizer level during an RCS pressure reditction. l l 4 1 1

EOP-8 R;v. 1/ Unit 1 Pcg; 33 of 49 i > . (3) Loss of subcooled margin as determined using CET temperatures. (4) "REACTOR VESSEL WATER LEVEL LOW" alarm,

d. IF voiding inhibits heat removal, THEN reduce or eliminate voided areas (1) Shut the Letdovn Isolation Valve, 1-CVC-515-CV.

(2) Pregsurize the RCS to maintain subcooling as near 140 F as practical. (3) IF pressurizing the RCS does NOT eliminate the voids, THEN operate Reactor Vessel Vent Valves per 01-10. 

                                                                                    -CAUTION'-

Il voids exist in the S/G tubes, a rapid RCS pressure reduction will occur when the voids collapse. (4) 1F voiding occurs in the S/G tubes (saturation pressure of S/G greater than saturation pressure { g of RCS), THEN cool the S/G by raising any of the following: (a) Steaming rate. (b) Feed rate. g (c) S/G Blowdown rate. AND maintaining less than 100 F/h cooldown rate. OR B. SAFETY INJECTION CORE COOLING. r 12 Ensuro HgSI or LPSI flow maintaining CET temperatures less than 560 F and constant or decreasing. OR l I

EOP-8 R;v. 1/ Unit 1 Pcg3 34 cf 49 l I

c. ONCE THROUGH CORE COOLING.

12 Commence once Throuch Core Coolinot 

                                                                     -CAUTION-After S/G becomes ineffective for heat removal, once Through Corg Cooling must be initiated prior to CET temperatures reaching 560 F to ensure adequate heat removal,
d. WHEN either of the following conditions exists (1) Steaming S/G becomes ineffective and CET temperatures begin to increase.

(2) HPSI or LPSI flow ibeufficient and CET temperatures begin to increase. THEN commence Once Through Core Cooling.

b. Shift Letdown Control Valve Controller, 1-HIC-110, to MANUAL and shut Letdown Control Valves:

1-CVC-110P-CV 1-CYC-110Q-CV

c. Start all available Charging Pumps,
d. Open Main and Aux HPSI Header Valvent 1-SI-616-MOV 1-SI-617-MOV 1-SI-626-MOV 1-SI-627-MOV 1-SI-636-MOV 1-SI-637-MOV 1-SI-646-MOV 1-SI-647-MOV
e. Start 11 and 13 HPSI Pumps,
f. De-energize the Pressurizer Heaters by placing all handswitches in OFF.
c. Start all available Containment Ait Coolers in HIGH vith maximum SRW flow.

I I

EOP-8 R;v. 1/ Unit 1 Pcga 35 of 49

h. Open both PORVs:

(1) WHEN "PRSR PRESS BLOCK A(B) PERMITTED" alarm (s) received, THKH block SIAS A(B). (2) Verify both PORV Block Valves open. (3) Pull two High Pressurizer Pressure Trip Units. (4) Verify PORVs open.

1. IF containment pressure increases to 2.0 PSIG AND still increasing, THEN start one Containment Spray lump and open associated Cntmt Spray Header CV.

11 or 12 1-SI-4150-CV 1-SI-4151-CV

j. IF containment pressure increases to 2.8 PSIG, THEN verify ESFAS actuation AND commence Verification Checklists:

l I (1) SIAS per Attachment (2). (2) CIS per Attachment (4).

k. IF containment pressure 11 creases to 4.25 PSIC, THEN verify CSAS actuation AND commence Verification Checklist, Attachment (3).
1. Confirm initiation of once Through Core Coo)ing.

(1) WHEN RCS pressure is less than 1270 PSIA, THEN ensure HPSI flow AND CET temperatures constant or decreasing. l

m. Using CgT temperatures, maintain subcooling bet. 30 and 140 F per Attachment (1) by throttling HPSI .

(1) Lower subcooling by lowering HPSI flow. (2) Raise subcooling by raising HPSI flow.

n. Continue cooldown using once Through Core Cooling "ntil feedwater restored or shutdown cooling entry
                      .onditions are established.

I

EOP-8 y R;v. 1/ Unit 1 Pcga 36 of 49 l I COffrAI)SEENT ISOLATION I. PRECAUTIONS A. Local radioactivity levels should be determined before attempting local manual valve isolation. II . CC)frAIidODff ISOLATION ACCEPTANCE _ CRITERIA A. IF either of the following conditions exist:

1. Containment pressure less than 0.7 PSIG and the following RMS alarms clears
a. S/G Blowdown. , ,
b. Condenser Off-Gas,
c. Main Vent Gaseous (1-RI-5415).
d. Containment Radiation Monitors.

{ } e. Noble Gas Monitor. OB

2. Each containment penetration required to be shut has an isolation valve shut.

THEN Containment Isolation Safety Function is satisfied. B. WHEN Containment Isolation Safety Function is satisfied, THEN proceed to the next Safety Function in jeopardy. l l

EOP-8 R;v. 1/ Unit 1 Pcg3 37 cf 49 l I III. RECOVERY ACTIONS A. VERIFY AUTOMATIC PROTECTIVE ACTIONS OCCUR. L Verify SIAS, CIS, CSAS:

a. H containment pressure increases to 2.0 PSIG,

_THEN verify ESFAS actuation AND commence Verification Checklists: (1) SIAS per Attachment (2). (2) CIS per Attachment (4),

b. H containment pressure increases to 4.25 PSIG, DIEN verify CSAS actuation AND commence Verification Checklist, Attachment (3).

B. H A SIAS, CIS, CSAS VALVE FAILS TO SHUT, { h _THEN SHUT LOCALLY OB SHUT NEXT V.\LVE OUT FROM PENETRATION. C. CHECK LOCKED VALVE DEVIATION LOG TO DETERMINE IF A!W MANUAL CONTAINMENT ISOLATION VALVES NEED TO BE SHUT. D. H S/G HAS A RUPTURED TUBE AND S/G NOT REQUIRED FOR HEAT REMOVAL, THEN ENSURE S/G ISOLATED. C. _I_F CONTAINMENT RMS ALARM RECEIVED, DIEN START ALL AVAILABLE IODINE FILTER FANS. l

EOP-8 R;v. 1/ Unit 1 Page 38 of 49 l I CORTAI)tDENT ENVIRO) MENT l I. PRECAUTIONS None l II. CORTAIP30Effr ENVIRO)4GEFr ACCEPTANCE CRITERIA A. If either of the following conditions exist:

1. Containment temperature and pressure are constant or j decreasing and i a. Containment temperature is less than 222 UF.
b. Containment pressure is less than 2.8 PSIG.
c. H, concentration less than 2% (only necessary if greater than four hours since initiation of event.)

OB

2. Containment temperature and pressure are constant or decreasing and:
a. Containment Spray flow is greater than 1350 GPM.
b. H 7 concentration less than 2% (only neccesary if greater than four hours since initiation of event.)

TIIEN Containment Environment Safety Function is satisfied. B. NHEN Containment Environment Safety Function is satisfied, THEN proceed to the next safety function in jeopardy. ' l I

EOP-8 R;v. 1/ Unit 1 Pega 39 of 49 l I ' III. RECOVERY ACTIONS A. VERIFY AUTOMATIC PROTECTIVE ACTIONS OCCUR.

1. VERIFY SIAS, CIS, CSAS:
a. IE containment pressure increases to 2.8 PSIC, TIJEU verify ESFAS actuation AND commence Verification Checklists:

(1) SIAS per Attachment (2). (2) CIS per Attachment (4),

b. IF containment pressure' increases to 4.25 PSIG, THEN verify CSAS actuation uMD commence Verification Check 11st, Attachment (3).
                =-     .

B. MAINTAIN CONTAINMENT COOLING. l l I 12 Maintain at least one of the following minimum cantainment cooling combinations in operation while containment pressure is above 4.25] SIG:

a. Two Containment Spray trains.

OR

b. One Containment Spray train and any two Containment Air Coolers with maximum SRW flow.

OR

c. Three Containment Air Coolers with maximum SRW flow.

NN 22 Verify SRW Pump Room Ventilation in service, per 01-15. E 

 =

l l l I 1 1

EOP-8 R;v. 1/ Unit 1 Poca 10 cf 49 C. IIYDROGEN CONTROL: 12 Direct Chemistry to place Hydrogen Monitors in service. 22 Establish containment ventilation to ensure no local hydrocen accumulation: __

a. Start available containment Air Coolers,
b. Start available Cavity Cooling Fans,
c. Start Pressurizer Ventilation Fan.
3. IF hydrogen concentration increases to 1%,

THEN start Hydrocen Recombiners per OI-41A. OB 41 W!- approval of SEC, establish Hydrogen Purge System Operation per OI-41B. , ( I

EOP-8 R;v. 1/ Unit 1 Page 41 of 49 I I 1 IV. SAFETY FUNCTION STATUS CHECK A. The STA (or person designated by STA) will perform the safety function status checks at 10 minute intervals until plant conditions stabilize. B. Immediately notify Shift Supervisor or Control Room Supervisor if any cafety function criteria is not being satisfied. C. Review data and verify that safety function acceptance criteria are satisfied. D. When all safety functica acceptance criteria are being satisfied, diagnosis of event (s) may begin. E. The safety function status chegks of EOP-8 should continue until an appropriate optimum recovery procedure is selected. l I l >

EOP-8 R;v. 1/ Unit 1 Paga 42 of 49 l l REACTIVITY CONTROL ACCEPTANCE CRITERIb REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL .,_ PARAMETERS CRITERIA STATUS CHECF.

a. WRNI power decreasing ,,__,,,,_________________,,_,,,_
b. SUR (DPM) negative _,,____,,____,,____,,,_, ____,._
c. CEA status all inserted ___________,,,_____,,_,,,,,_____,

or Boration status concentation increasing ,______,,,,_,,,,_________,,,_,,_ BAST /RWT level decroaning ,,,__,,,,,___,,,,,,____,,,,_,,_, l l Reactivity Control Safety Function is saticfied if CRITERIA $3TISFIED

a. All CEAs inserted and WRNI power decreasing.

OR

b. RCS bo.*ation in progress and WRNI power decreasing, OR
c. WRNI power less than 10 -4 % and constant or I decreasing.

1 l 1

EOP-8 R;v. 1/ Unit 1 Page 43 of 49 { } RCS PRESSURE AND INVENTORY ACCEPTANCE CRITERIA RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND INVENTORY PARAMETERS CRITERIA STATUS CHECK

a. Pressurizer within limits pressure (PSIA) per Attachment (1) ,,_________ ....,____,,_______,
b. Pressurizer level (inches)* 35 to 250 ____,,,___________,,,_ ,_______
c. Charging flow greater than 40 ,______,,_________,,_____.,____

(GPM)

d. HPSI flow (GPM) per Attachment (12).____________,,_________,,__,,,_
e. LPSI flow (GPM) per Attachment (13) __,,,_________,,,,,,,,,,_____,,
f. RCS Subcooling ( F) 30 to 140 -------------------------------
g. RVLMS core covered -------------------------------

l l

  • Limit may be exceeded for solid plant operation.

RCS Pressure and Inventory Safety Function is satisfied if: CRITFRIA SATISFIED

a. RCS pressure and temperature are within the limits per Attachment (1) and (1) Pressurizer level is between 35 and 250 inches.

(2) RCS subcooling is greater than 30 F using CET temperatures. f (3) RVLMS indicates that the Core is covered. ,__,,,___,___,,,,, l OR l b. RCS pressuro and temperature are within the limits per Attachment (1) and (1) All available Charging Pumps running. (2) HPSI and LPSI Pumps are injecting water { g into RCS per Attachment (12) and (13). (3) RVLMS indicates that the Core is covered. _____________,,,__

EOP-8 R;v. 1/ Unit 1 PCg3 44 of 49 i I . CORE AND RCS HEAT REMOVAL ACCEPTANCE CRITERIA CORE AND RCS SAFETY EUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL PARAMfTERS CRITERIA STATUS CHECK l a. S/G pressure (PSIA) less than 960 ________ ...______ ..______.... l l b. S/G 1evel (inches) (-)250 to (+)50 ______..___________________ ... l c. CST level (ft) greater than 5 _______________________________ ' d. Feedwater flow (GPM) greater than 150 . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , , _ _

e. CET ( F) less than 560 __,____________________________
f. RCS Subcooling ( F) 30 to 140 _______...,____________________

1

g. RVLMS core covered ...___..__....._________.......

{ } h. Tcold ( F) less than 540 ________________ ....______ ... l l 1.TgotminusTeold 1 ( F) 1 Natural Circulation 10 to 50 _______.__..___.....__.....___. Ferced Circulation less than 10 ___......__.........____...___.. l l j. HPSI flow (GPM) per Attachment (12) ...... ____..........________..

k. LPSI flow (GPM) per Attachment (13) ..... __ ..,__________ .... ___

l l l l 1 l l l l I I 1 1 l l l l

EOP-8 R;v. 1/ Unit 1 Page 45 of 49 till . Core and RCS Heau Removal Safety Function is satisfied ift CRITERIA SATISFIED

a. One S/G with level between (-)2S0 and

(+)5O inches and trending toward zero ands (1) RCS flow by Forced Flow or Natural Circulation. (2) RCS subcooling greater than 30 F using CETs. (3) CET temperatures constant or decreasing. (4) RVLMS indicates that the Core is covered. ____,,,,____,_______ OR

b. One S/G with feedwater flow greater than 150 GPM and level being restored and:

(1) RCS flow by Forced Flow or Natural Circulation. I (2) RCS subcooling greater than 30 F using CETs. (3) CET temperatures constant or decreasing. (4) RVLMS indicates that the Core is covered. ,_,,,,,,,,,,,,,,,,,, OR

c. HPSI or LPSI Pumps injecting water into RCS and CET temperatures constant or decreasing. ____,,,_,______,,,,,

OR

d. Once Through Core Cooling in progress and CET temperatures constant or decreasing. ,,,,,,,,___________,

l I

EOP-8 5 R;v. 1/ Unit 1 l Page 46 of 49 l l VITAL AUXILIARIES ACCEPTANCE CRITERIA VITAL SAFETY FUNCTION ACCEPTANCE CRITERIA AUXILIARIES CRITERIA STATUS CHECK

a. 4KV vital buses 11 or 14 energized ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
b. Instrument Air greater pressure (PSIG) than 88 ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,
c. Component Cooling

(# Pumps running) 1 or 2 ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,

d. Saltwater

(# Pumps running) 1 or 2 ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,

e. Service Water

(# pumps running) 1 or 2 ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,, I f. 125V DC buses 11, 12, 21, 22 energized ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,

g. 120V AC vital buses 11, 12, 13, 14 energized ,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,

Refer to appropriate AOP for any Vital Auxiliaries in jcopardy, l l l

EOP-8 R;v. 1/ Unit 1 Page 47 of 49 l l CONTAINMENTISOLATIONACCEPTANCE_CRINRIA CONTAINMENT SAFETY FUNCTION ACCEPTANCE CRITERIA ISOLATION PARAMETERS CRITERIA STATUS CHECK

a. Containment less than pressure (PSIG) 0.7 ______,,_____________________,,,
b. S/G B/D RMS alarm clear ____,,_________________________,
c. Condenser Off-Gas RMS alarm clear _________________,,,,,_______,,_,
d. Main Vent Gaseous RMS (1-R1-5415) alarm clear ,,,,_,,______,,__,,,,,,____,,___
e. Containment Radiation Monitors alarms clear ______,,___,______,,____,,,,,,,,
f. Noble Gas Monitor alarm clear

{ } ,,,,,,______,,__,,______________

g. Containment all required penetration valves to be shut are shut ,,,__,__,___,,__,,,,___,,_______

Containment Isolation Safety Function is satisfied if: CRITERIb EATISFIED

a. Containment pressure less than 0.7 PSIG and the following RMS alarms clears (1) S/G Blowdown.

(2) Condenser Off-Gas. (3) Main Vent Gaseous (1-R1-5415). (4) Containment Radiation Monitors. (5) Noble Gao Monitor, _________,,,,_______ OR l l b. Each containment penetration required to be shut has an isolation valve shut. ,______,,,,,,_______

EOP-8 R;v. 1/ Unit 1 Page 48 of 49 I I CONTAINMFET ENVIRONMENT ACCEPTANCE _,. CRITERIA CONTAINMENT SAFETY FUNCTION ACCEPTANCE CRITERIA ENVIRONMENT CRITERIA STATUS CHECK

a. Containment less than temperature ( F) 222 ___,,___________________________
b. Containment less than Pressure (PSIG) 2.8 ,,______,,,_... __,,,,____,,,,__
c. Containment spray greater than flow (GPM) 1350 .. ,______________________________
d. Hydrogen less than concentration 2% . ,,,,,___,,,,,,_______________,

Containment Environment Safety Function is satisfied if: d I CRITERIA SATISFIED

a. Containment temperature and pressure are constant ot decreasing and :

(1) Congainment temperature is less than 222 F. (2) Cont..inment pressure is less than 2.8 PSIG. (3) H, concentration less than 2% (only nBeessary if greater than four hours since initiation of event.) ,_______ _____ _____ OR

b. Containment temperature and pressure are constant or decreasing and :

(1) Containment Spray flow is greater than 1350 GPM. (2) H 3 concentration less than 2% (only n8cessary if greater than four hours j } since initiation of event.) ,________,,,,,. ___,

EOP-8 rov. 1/ Unit 1 Page 49 of 49 STATUS CHECK COMPLETE AT NUMBER TIME 1 2 3 4 i i I

EOP-8 R;v. 1/ Unit 2 Pcg3 1 of 49 CALVERT CLIFFS NUCLEAR POWER PLANT EOP-8 FUNCTIONAL RECOVERY PROCFEURE REVISION 1 b 2 RE ~ ';' \ DATE f ( ' 

                                                                     /T ' / ~ 3 7 I I PREPARED BY;            ~ 7 17 / M % ._ ,      .
                                                       /   _     /
                                                    ,_       g VERIFIED BY;          . MWJ?d               m ut-             //L        F #7 POSRC;
                       /

MEETING W 'EG-1 / 2. - t o - T?> APPROVED BY; ON 4,wsw / 2- * ' 5' 'c! Min 6gef-Nuclear Operations or General Supervisor-Operations if POSRC review is not required

EOP-8 R v. 1/ Unit 2 Pcgo 2 of 49 I I .. LIST OF EFFECTIVE PA,qES PAGE NUMBER REVISION PAGE NUMBER REVISIO!j 1 1 25 1 2 1 26 1 3 1 27 1 4 1 28 1 5 1 29 1 6 1 30 1 7 1 31 1 8 1 32 1 9 1 33 1 10 1 34 1 11 1 35 1 12 1 ,, 36 1 13 1 37 1 14 1 38 1 15 1 39 1 16 1 40 1 17 1 41 1 18 1 42 1 19 1 43 1 I I 20 1 44 1 21 1 45 1 22 1 46 1 23 1 47 1 24 1 48 1 49 1 l I l l l 4 I 1 i

EOP-8 RCv. 1/ Unit 2 PCg3 3 cf 49 I I ' I. ENTRY CONDITIONS The operator should enter the Functional Recovery Procedure under the following circumstances: A. EOP-O has been complated but an event diagnosis cannot be made. OB B. An event diagnosis has been made and one of the EOP-1 through 7 procedures has been implemented but one or more safety functions are not meeting their acceptance criteria and the reason for the violation has not been established. OB C. An event diagnosis has been'made and one of the EOP-1 through 7 procedures has been implemented but a subset of parameters for a single safety function are not meeting their acceptance criteria and the Shift Supervisor desires to reference EOP-8 to obtain additional guidance for a specific problem. For the conditions of A or B, EOP-8 should be implemented in its entirety. The safety functions with the out of spec acceptance criteria should be addressed first. When EOP-8 is implemented, the safety function status check of EOP-8 should be implemented until an appropriate optimum recovery procedure is selected. EOP-8 need not be implemented if the parameters of a safety function are outside of their acceptance criteria and:

1. Reason for the violation has been established, bHD
2. Action has been identified that will return the parameter (s) to within their acceptance criteria, bHD
3. The Shift Supervisor determines the recovery of the out of spec parameter (s) to within acceptance criteria to be imminent.

l l

EOP-8 Rov. 1/ Unit 2 Page 4 of 49 l I REACTIVITY CONTROL I. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function. B. Systems shifted to manual operation must be monitored frequently to ensure correct operation. C. At least two indeperdent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments. D. The operator should not leave reactivity control until this function is fulfilled. If necessary, other urgent safety functions may be pursued in parallel but attempts to establish reactivity control must be continued until the acceptance criteria are met. E. If possible, maintain RCS temperature greater than 515 F until reactivity control criteria are satisfied. F. The concentration of boron in RCS makeup water should be consistent with maintaining the required shutdown margin. G. When borating the RCS it is possible for a large difference in boron concentration to develop between the RCS and pressurizer fluids if main or auxiliary spray is not operated at intervals. If spray is unavailable, the RCS boron concentration should be increased by 50 ppm to maintain the required shut (,ki margin should a pressurizer outsurge occur. 1 l l l l 1

EOP-8 RCv. 1/tinit 2 Pcga 5 of 49 i I II. REACTIVITY CONI'ROL ACCEPTANCE CRITERIA A. 1F any of the following conditions exist:

1. All CEAs inserted and WRNI power decreasing.

9B

2. RCS boration in progress and WRNI power decreasing.

9B 

                                               -4
3. WRNI power less than 10  % and constant or decreasing.

THEN Reactivity Control Safety Function is satisfied. B. WHEN Reactivity Control Safety function is satisfied, THEN proceed to the next safety function in jeopardy. III. RECOVERY ACTIONS I I A. INITIATE REACTOR SHUTDOWN BY CEA INSERTION: 11 Depress both sets of Manual Reactor Trip Buttons, 1 l ! 9B l

2. De-energize CEDM Motor Generator _. Sets:  !

l a. Open feeder breaker to 22A 480V Bus,

b. Open feeder breaker to 23A 480V Bus. I i
c. Open tie breakers to 22A and 23A 480V Buses.

9R ! 12 Depress local Emergency Trip Buttons on the Trip Circuit l Breakers. I l OR l I i

EOP-8 Rcv. 1/ Unit 2 Pcg3 6 cf 49 l l . B. INITIATE 'AEACTOR SHUTDOWN BY BORATION: 12 Establish charcino flowpath to RCS:

a. Normal CVCS lineup (1) Open Loop Charging Valves:

2-CVC-518-CV 2-CVC-519-CV (2) IF Loop Charging Valves shut, THEN charging may continue through Loop Charging Valves Bypass Valve, 2-CVC-188. OR

b. Charging through Aux HPSI Header:

(1) Open SI Discharge To Charging Header Core Flush Valve, 2-CVC-269-MOV. l I (2) Shut Charging Header Contninment Isolation Valve, 2-CVC-183, located in 27 ft West Penetration Room. (3) Shut HFSI Aux Header Isolation Valve, 2-SI-656-MOV. (4) Shut Letdown Isolation Valves:  ! 2-CVC-515-CV  ; 2-7VC-516-CV l (5) Open any one of the four Aux HPSI Header Valves: ) 1 2-SI-617-MOV  ! 2-SI-627-MOV l 2-SI-637-MOV 2-SI-647-MOV

2. Eetablish boric acid flovpath to Charging Pumps:
a. BAST Lineup (1) Ensure BAST levels greater than zero.

(2) Shut VCT Makeup Valve, 2-CVC-512-CV. l I (3) Open Boric Acid Direct Makeup Valve, 2-CVC-514-MOV.

EOP-8 R v. 1/ Unit 2 Pcg3 7 of 49 l l (4) Open BAST Gravity Feed Valves: 2-CVC-508-MOV 2-CVC-509-MOV (5) Shut VCT Outlet Valve, 2-CVC-501-MOV. (6) Start Boric Acid Pumps. (7) Start all available Charging Pumps. (8) Ensure Charging Pump discharge pressure greater than RCS pressure. OR

b. RWT Lineup: ,,

(1) Ensure RWT level greater than 2 ft. (2) Open RWT To Charging Pump Suction Valve, 2-CVC-504-MOV. (3) Shut VCT Outlet Valve, 2-CVC-501-MOV. (4) Start all available Charging Pumps. , I (5) Ensure Charging Pump discharge pressure greater than RCS pressure. . l l

EOP-8 R;v. 1/ Unit 2 Pcgo 8 of 49 I I RCS PRESSURE AND_ INVENTORY CONhROL I. PRBCAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function. B. Systems shifted to manual operation must be monitored frequently to ensure correct operation. C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inceasistencies between instruments. .. D. Solid watgr operation of the Pressurizer should be avoided unless 30 F subcooling cannot be maintained. If the RCS is solid, closely monitor RCS makeup or letdown and avoid system heatup or cooldown rates which could induce rapid pressura excursions. I I E. Indications of high RCS inventory thigh pressurizer level) may be caused by the displacement of water from voided areas of the RCS. Operation of letdown under theme conditions may lower RCS pressure and, subsequently, increase RCS voiding, k I

EOP-8 Rcv. 1/ Unit 2 Page 9 of 49 l I II. RCS PRESSURE AND INVENTORY ACCEPTANCE CRITER A A. IF either of the following conditions exist:

1. RCS pressure and temperature are within the limits por Attachment (1) and
a. Pressurizer level is between 35 and 250 inches.
b. RCS subcooling is greater than 30 F, using CET temperatures.
c. RVLMS indicates that the Core is covered.

QB

2. RCS pressure and temperature are within the limits per Attachment (1) and
a. All available Charging Pumps running,
b. HPSI and LPSI Pumps are injecting water into RCS per Attachments (12) and (13).

l I c. RVLMS indicates that the core is covered. THEU RCS Pressure and Inventory Safety Function is satisfied. B. MITEN RCS Pressure and Inventory Safety Function is satisfied, TUEN proceed to the next safety function in je;pardy. III. RECOVERY ACTIONS A. ENSURE AUTOMATIC CONTROL OF PRESSURIZER LEVEL AND PRESSURE: 12 Manually operate control systems which are not providing  ; correct automatic control of pressurizer level or l pre _s su re : I

a. IF Pressurizer Level Control System NOT restoring level to 160 inches, l THEU manually operate charging and letdown to l stabilize level in indicating range. l l
b. IF Pressurizer Pressure Control System HOT restoring  !

j g pressure to setpoint value,  ! THEN manually operate heaters ande sprays to maintain , RCS subcooling between 30 and 140 F. l l l l

EOP-8 R;v. 1/ Unit 2 Page 10 of 49 l I 21 Ensure automatic protective actions occurs

a. Verify PORVs open at 2500 PSIA and shut by 2300 PSIA.
b. IE RCS pressure decreases to 1725 PSIA, THEN verify SIAS actuation AND commence SIAS Verification Checklist, Attachment (2),
c. II RWT level decreases to between 0.5 and 1.0 ft OR "ACTUATION SYS RAS TRIPPED" alarm received, TK?H verify RAS actuation AND commence RAS Verification Checklist, Attachment (6).

B. MONITOR FOR RCP TRIP CRITERIA. 11 Trip RCPs as indicated below:

a. If RCS pressure decreases to 1725 PSIA, THEU trip 21A and 22B RCPs OR trip 21B and 22A RCPs.
b. II RCS presnure decreases to less than 1300 PSIA, I k 2' HEN trip all RCPs.
c. IE CIS hau actuated, TITEN trip all RCPs.

C. MAINTAIN ADEQUATE WATER SUPPLY TO PUMPS CONTROLLING RCS INVENTORY: 

                                 - CAUTION -

Long term injection of concentrated boric acid could result in degraded core heat removal due to plating out the boron, b Charcino Pumps alicqed to BASTS _us_iaq Boric Acid Pumps:

a. Shut VCT Makeup Valve, 2-CVC-512-CV. j 1
b. Open Boric Acid Direct Makeup Valve, 2-CVC-514-MOV.
c. Start a Boric Acid Pump. ]

OB i I l l 1 i

EOP-8 rov. 1/ Unit 2 Pcg3 11 of 49

2. Charoina Pumps alicned to BASTS usind cravity feeds
a. Shut VCT Makeup Valve, 2-CVC-512-CV.
b. Open BAST Gravity Feed Valves:

2-CVC-508-MOV 2-CVC-509-MOV

c. Shut VCT Outlet Valve, 2-CVC-501-MOV.

OR 32 Charoino Pumps aligned to VCT:

a. Ensure VCT level greater than 50 inches.
b. Open VCT Outlet Valve, 2-CVC-503-MOV.

OB 42 Chargina Pumps aligned to RWT:

a. Open RWT To Charging Pump Suction Valvo, I I 2-CVC-504-MOV.
b. Shut VCT Outlet Valvo, 2-CVC-501-MOV.
c. Shut Boric Acid Direct Makeup Valve, 2-CYC-514-MOV.
d. Secure Boric Acid Pumps.

OB

5. HPSI and LPSI Pumps aligned to RWT:
a. Open RWT Outlet Valves:

2-SI-4142-MOV 2-SI-4143-MOV

b. Ensure RWT level greater than 4 ft. l l

l OR l I 1 l l

6 EOP-8 R;v. 1/ Unit 2 Pcg3 12 of 49 A l 62 HPSI and__LPSI Pumps aligned to containment sump:

a. Monitor containment water level to ensure adequate auction water supply,
b. Place SI Pump Mini Flow Lockout Switches in ON,
c. Commence RAS Verification Checklist, Attachment (6).
d. Shut RWT Outlet valves:

2-SI-4142-MOV 2-SI-4143-MOV D. MAINTAIN AT LEAST ONE RCS MAKEUP PATH: 13 Normal charginq path:

a. Open Leop Charging Valves:

g 2-CVC-518-CV 4 2-CVC-519-CV

b. IF Loop Charging Valves shut, THEN charging may continue through Loop Charging Valves Bypass Valve, 2-CVC-188.

OB

2. Charging through Aux _HPSI Header
a. Open SI Discharge To Charging Header Core Flush Valve, 2-CVC-269-MOV.
b. Shut Charging Header Containment Isolation Valve, 2-CVC-183, located in 27 ft West Penetration Room.
c. Shut HPSI Aux Header Isolation Valve, 2-SI-656-MOV.

i

d. Shut Letdown Isolation Valves:

2-CVC-515-CV 2-CVC-516-CV l i l l 1 1

EOP-8 Rsv. 1/ Unit 2 F0po 13 ef 49 I I

e. Open any one of the four Aux HPSI Header Valves:

2-SI-617-MOV 2-SI-627-MOV 2-SI-637-MOV 2-SI-647-MOV 9B 32 HPSI Pump makeup to RCS in SI'S or RAS moder

a. Check RCS prosaure less that 1270 PSIA.
b. IF RCS pressure greater than 1270 PSIA, THEN depressurice per guidelines in stop F.2.e., paq s 18,
c. Open Main and Aux HPSI Ueader Valves:

2-SI-616-MOV 2-SI-617-MOV 2-SI-626-MOV 2-SI-627-MOV 2-SI-636-MOV 2-SI-637-MOV 2-SI-646-MOV 2-SI-647-MOV 

          -OR l     I 42    LPSI Pump makeup,
a. Check RCS pressure lose than 180 PSIA.
b. Open LPSI Header Valvos:

2-SI-615-MOV 2-SI-625-MOV 2-SI-635-MOV 2-SI-645-MOV E. ESTA'4LISH AND MAINTAIN RCS MAKEUP FLOW: 11 Charging Pump makeup 1

a. Start all available Charging Pumps.
b. Ensure Charg!ng Pump discharge pressure greater than RCS preseure,
c. Ensure pump running current between 75 and 95 AMPS.

l l OR

EOP-8 R;v. 1/ Unit 2 PagJ 14 cf 49 I 22 HPSI Pump makeup in SIAS mode

a. Start 21 and 23 HPSI Pumps,
b. IE 21 or 23 HPSI Pump fails, DIEU start 22 HPSI Pump AND align to appropriate header.
c. Verity HPSI flow per Attachment (12).

9B

3. HP9I Pump _ makeup _in RAS mode:
a. Start 21 or 23 HPSI Pumps.
b. If HPSI flow greater than 1000 GPM with two HPSI Pumps operating, IIIEN squally throttle HPSI flow to 1000 GPM.
c. IE HPSI flow greater than 600 GPM with one HPSI Pump operating, WIEN equally throttle HPSI flow to 600 GPM.

I I - CAUTION - To prevent pump damage, minimum flow per operating HPSI Pump in 30 GPM.

d. IE HPSI Pump cavitation occurs in recirculation mode, 31HRJ throttla HPSI flow per Attachment (12),
e. IF Attachment (12) does N93 allow throttling HPSI flow, THEN align Containment Spray Pump (s) to HPSI Pump suction:

(1) IF 21 HPSI Pump cavitating, TIIEN open 21 SDC HX To HPSI Suction Valve, 2-SI-663-MOV SND start 21 Containment Spray Purp. (2) IE 23 HPSI Pump cavitating, THEN open 22 SDC HX To HPSI Suction Valve, 2-SI-662-MOV 6ND start 22 Containment Spray Pump. OB  ; I l

EOP-8 R v. 1/ Unit 2 Pega 15 of 49 

       .41   LPSI Pump makeup:_
a. Place 21 or 22 LPSI Pump RAS Override Switch in OVERRIDE.
b. Start selected LPSI Pump.
c. Verify LPSI flow per Attachment (13).

F. MAINTAIN SUBCOOLED MARGIN BETWEEN 30 AND 140 F: 

                             -CAUTION-The potential exists for pressurized thermal shock from an excessive cooldown rate followed by a repressurization.

12 Raise _subcooling by any of the followinct 

                                -NOTE-Pressurizer Backup Heater Banks 21 and 23 trip on U/V and SIAS.
a. Energize Pressurizer Heater (s).

OR

b. Operate Turbine Bypass or Atmospheric Dump Valves to maximize RCS gooldown, while maintaining cooldown rate less than 100 F/h.

OR

c. IF unable to obtain desired cooldown rate with Turbine Bypass and Atmospheric Dump Valves,
                  ))Up! uso steam driven AFW Pump (s) to increase cooldown rate.

OR

d. Raise HPSI flow to RCS.

OR 1 l k l

EOP-8 R;v. 1/ Unit 2 Pcg3 16 of 49 I I ,

e. Charging system pressurization:

(1) Charge as necessary to maintain at least 30 F subcooling. (2) 1E high pressurizer icvel securcs backup Charging Pumps AND more than one Charging Pump required, THEN locally initiate SIAS A6 and B6 bMD secure Boric Acid Pump as needed. (3) Secure Charging Pumps not required to maintain subcooling. OR l

f. Solid plant pressurization (1) Station a dedicated' pressure control watch at the  ;

2C05 and 2C06 panels. (2) Verify letdown flowpath operable. ) (3) Secure all but one Charging Pu.np by placing in PULL-TO-LOCK. l l I (4)Chargeasnecessarywgthremainingpumpto maintain a minimum 30 F subcooling. i (5) Closely monitor makeup or draining and any heatup or cooldown to avoid rapid pressure excursions.

2. Lower subcooling__bv any of the fellowingt l
a. De-energize Pressurizer Heater (s).

OR

b. Lower RCS cooldown rate. i l

OR i l l l l i k

t EOP-8 rov. 1/ Unit 2 Pcg3 17 of 49 I I

c. IF the following conditions can be maintained:

(1) At least 30 F subcooling. (2) Pressurizer level greater than 101 inches. (3) At least one S/G available for heat removal. (4) RVLMS indicates that the Core is covered. DJEH throttle HPSI or cherging flow as,necessary to maintain subcooling between 30 and 140 F. OR

d. Initiate Auxiliary Spray:

(1) Place Instrument Air CIS Override Switch, 2-HS-2080A, in OVEREIDE. (2) Open Cntmt Instrument Air Isolation MOV, 2-IA-2000-MOV. g (3) Record temperature differential between 4 Pressurizer and Regenerative Heat Exchanger Outlet. (4) Open Auxiliary Spray Valve, 2-CVC-517-CV. (5) Shut Loop Charging Valves: 2-CVC-518-CV 2-CVC-519-CV NQTE: 2-HS-2005 located on West wall of 27 ft Switchgear Room; Key #80 in Control Room Key Locker. (6) Open Cntmt Instrument Air Supply CV, 2-IA-2085-CV. by momentarily placing 2-HS-2085 in OPEN. (7) Shift Pressurizer Spray Valve Controller, 2-HIC-100, to MAMUAL and shut Pressurizer Spray Valves: 2-RC-100E-CV 2-RC-100F-CV I I

EOP-8 R v. 1/ Unit 2 Pcga 18 cf 49 I I (C)MaigtainpressurizercooldowNratelessthan 200 F/h. OR

e. PORV depressurizations (1) Shift Letdown Control Valve Controller, 2-HIC-110, to MANUAL and shut Letdown Control Valves:

2-CVC-?.10P-CV 2-CVC-110Q-CV (2) De-energize the Pressurizer Heaters by placing all handswitches in OFF. (3) Start all available. containment Air Coolers in HIGH with maximum SAW flow. (4) Open Main and Aux HPSI Header Valves: 2-SI-616-MOV 2-SI-617-MOV 2-SI-626-MOV 2-SI-627-MOV 2-SI-636-MOV 2-SI-637-MOV I I 2-SI-646-MOV 2-SI-647-MOV (5) Verify both PORV Block Valves open. (6) Start all available Charging Pumps. (7) Start 21 and 23 HPSI Pumps. (8) Pull two High Pressurizer Press *are Trip Units. (9) Verify PORVs open. (10) NHKH subcooling less than 140 F, _UQW insert High Pressurizer Pressure Trip Units that were previously pulled SND ensure "PORV ENERGIZED" alarm clear. G. VERIFY RCS TEMPERATURE AND PRESSURE WITHIN THE LIMITS PER ATTACHMENT (1). I I

EOP-8 Rcv. 1/ Unit 2 Pcg3 19 cf 49 I I . CORS AND RCS IIEAT REMOVAL

1. PRECAUTIONS A. Do not adopt manual operation of automatically controlled systems unless a malfunction is apparent or automatic system operation will not support the maintenance of a safety function.

B. Systems shifted to manual operation must be monitored frequently to ensure correct operation. C. At least two independent indications should be used, when available, to evaluate and corroborate a specific plant condition since an incident could induce inconsistencies between instruments. , D. If an initial RCS cooldown rate exceeds Technical Specification limits, the potential exists for pressurized thermal shock of the Reactor Vessel unless post accident pressure and temperature limits are restored and maintained. E. If both S/Gs boil dry, only attempt to refill one S/G to I ! reinitiate core cooling. F. In Natural Circulation, increased loop transport time causes a 5 to 10 minute delay in temperature responses to a plant change. Pressurizer level and pressure responses, if available, typically provide better indication of RCS response during this period,

c. If cooling down vith a S/G isolated, an inverted delta T (Teold higher than Thot) may be observed in the idle loop.

This is due to a small amount of reverse heat transfer in the isolated S/G. The inverted delta T is not expected to have any significant affect on natural circulation flow in the operating S/G loop. I I l

EOP-8 R v. 1/ Unit 2 Page 20 of 49 I I II. CORE _AND_RCS HEAT REMOVA W Ef_TANCE CRITERIk A. IF any of the following conditions exist:

1. One S/G with level between (-)250 and (+)50 inches and trending toward zero ands
a. RCS flow by Forced Flcw or Natural Circulation.
b. RCS subcooling greater than 30 F using CETs.
c. CET temperatures constant or decreasing.
d. RVLMS indicates that the Coro is covered.

OB

2. One S/G with feedwater flow' greater than 150 GPM and level being restored and:

I a. RCS flow by Forced Flow or Natural Circulation. l l b. RCS subcooling greater than 30 F using CETs. I c. CET temperatures constant or decreasing.

d. RVLMS indicates that the Core is covered, i ~OR 1
3. HPSI or LPSI Pumps injecting water into RCS and CET temperatures constant or decreasing.

OB

4. Once Through Core Cooling in progress and CET temperatures )

l constant or decreasing. { THEN Core and RCS Heat Removal Safety Function is satisfied. l l l B. WHEN Core and RCS Heat Removal Safety Function is satisfied, l TUEN proceed to the next safety function in jeepardy, 1 1 I 1 h l l l l l

EOP-8 Rcv. 1/ Unit 2 Pcg] 21 of 49 l I ,, III. RECOVERY ACTIONS A. MAINTAIN S/G OPERABILITY: 11 IE an uncontrolled cooldown occurs, TID'.H i solate both S/Gs :

a. Shut both MSIVs.
b. Shut S/G Feedwater Isolation Valves:

2-FW-4516-MOV 2-FW-4517-MOV

c. Shut MSIV Bypass Valves'I 2-MS-4045-MOV 2-MS-4052-MOV
d. Shut AFW Steam Supply Valves by placing handswitches in CLOSE:

2-MS-4070-CV 2-MS-4071-CV

e. Shut AFW Block Valves by placing handswitches in CLOSE:

21 S/G 22 S/G 2-AFW 4520-CV 2-AFW-4530-CV 2-AFW-4521-CV 2-AFW-4531-CV 2-AFW-4522-CV 2-AFW-4532-CV 2-AFW-4523-CV 2-AFH-4533-CV

f. Shut upstream drains by placing handswitch 2-HS-6622 in CLOSE.
g. Shut S/G Blowdown Valves:

2-BD 4010-CV 2-BD-4011-CV 2-BD-4012-CV 2-BD-4013-CV

h. Shut Atmospheric Dump Valves.

l I l

E0P-8 R;v. 1/ Unit 2 Pcg3 22 cf 49 ( I .

i. IF one S/G has a steam line rupture, 3342f maintain unaffected S/G operability during blowdown phase per EOP-4, Step J, page 10.
j. WHEU cooldown rate less than 100 F/h, IHEU establish S/G(s) as heat sink.

OB 12 Control steam flow and maintain Teold less than 540 F:

a. Operate Turbine Bypaes Valves from Control Room.

OR

b. Operate Atmospheric Dump Valves from Control Room.

OR

c. Operate Atmospheric Dump Valves from 2C43:

(1) Verify 2C43 Atmospheric Dump Controllers at 0% output. I k (2) Align Hand Transfer Valves to 2C43 position: 71 S/0 22_S/G 2 -IN- 3939A 2 -IN-393 8 A 2-IN- 3 93 9B 2 -IN-3 93 8B (3) Open Atmospheric Dump Valve (s) using 2C43 controller (s). OR 

                                    -80T5-Atmospheric Dump Valves are reverse acting,         i.e., clockwise to open, counterclockwise to shut.
d. Manually open Atmospheric Dump Valves by using chain l operator.

OR i

e. Manually position Turbine Bypass Valves.

OR \ > 1 l l l

EOP-8 R v. 1/ Unit 2 Pcq3 23 of 49 I I 

                                                                                  -CAUTION-Operating history indicates S/G Safety Valves may fail to reseat completely after lifting.
f. Manually open S/G Safety Valver (3) Lower S/G pressure as low as possible using other heat remeval methods prior to attempting manual operation of S/G Safety Valve.

(2) Operate manual lifting lever to open S/G Safety Valve. OR 

                                                                                   -CAUTIOM-The following step may blow out the Condenser Rupture Diska and may cause equipment damage.
g. Align steam drains to Condenser:

(1) Open upstream drains by placing handswitch I 2-HS-6622 in OPEN. (2) Open downstream drainn by placing handswitch 2-HS-6600 in OPEN. (3) IE MSIVs shut, THEN open MSIV Bypass Valves. OR 

                                                                                    -CNnigN-The following step will blow out the Condenser Rupture Disks and may cause equipment damage,
h. If additional heat removal required SND condenser vacuum HOT available, THEN open Turbine Bypass Valve (s):

(1) Open all doors to the outside on the 45 ft Turbine Building. (2) Notify personnel to evacuate 45 ft Turbine ' Building. (3) Manually operate Turbine Bypasr Valve (s) as l ) directed by Control Room personnel.

EOP-8 R;v. 1/ Unit 2 Pcg? 24 of 49 I I  % 32 Control Main Feedwater flow to S/Get

a. Ensure main feed rate is maintaining a constant level or controlled increase in S/G level.
                                      -CAUTION-Severe waterhammer may occur if Main Feed Ring is allowed to drain then subsoquently refilled,
b. Establish a shutdown food aystem lineups (1) One operating S/G Feed Pump.

(2) One operating Condansate Booster Pump. (3) One operating Condeonate Pump. (4) Both Hoater Drain Pumps secured,

c. WHEN manual control of feed flow rate desired OR S/G levels between (-)24 and (+)30 inches, THEU perform the following:

I l (1) Depress Feed Regulating Bypass Valve Reset Buttons. (2) Adjust Feed Regulating Bypass Valve (s) to raise S/G levels to approximately 0 inches,

d. WHEN S/G levels are 0 inches, IHEN shift Feed Regulating Bypass Controllers to AUTO.

OB 44 IF Main Feedwater HOI available, , I)1EN feed S/Gs with AFW: 1

a. Establish condensate sources (1) Confirm 12 CST operable:

(a) Er,sure 12 CST level greater than 5 ft. (b) Open 12 CST Unit 2 AFW Pump Suction Valve, 2-AEW-161. (OR) { l

EOP-8 R v. 1/ Unit 2 PCg3 25 cf 49 I I 

                                     -CAUTION-Before transferring AFW Pump nuction to an alternate supply the possibility of suction line or CST rupture should be considered.

(2) IF 12 CST HOI operable, THEM line up 21 CST as alternate auction supply (a) Locally open 21 CST AFW Pump Suction Valves: 2-AFW-131 2-AFW-167 (b) Locally shut 12 CST Unit 2 AFW Pump Suction Valve, 2-AFW-161. (c) Confirm normal., CST level response. (OR) 

                                      -N_OTE-The following step will cause CST levels to equalize.

l I (3) IF 21 CST NOT available, IREN line up 11 CST as alternate auction supply; (a) Locally open 11 CST AFW Pump Suction Valves: 1-AFW-131 1-AFW-167 (b) Locally open 12 CST AEW Pump Suction Valves: 1-AFW-161 2-AFW-161 (c) Confirm normal CST level response. (OR) (4) Align Fire System to 23 AFW Pump suction: l (a) Shut 23 AFW Pump Suction Valve, 2-AFW-182. (b) Connect fire hoses between pump suction and a fire main. (c) Open Fire Hose Connection Isolation Valve, ! 2-AFW-180. { } (OR) l

EOP-8 R:v. 1/ Unit 2 Pcg3 26 cf 49 l I (5) Align T Jtem to 13 AFW Pump suction for cross connects _ perations (a) Shut 13 AEK' Pump Suction Valve, 1-AFW-182. (b) Connect fire hoses between pump suction and a  : fire main. (c) Open Fire Hose Connection Isolation Valve, 1-AFW-180. (OR) (6) IF Condensate Pump available, THEN transfer hotwell inventory to 21 CST: (a) Shift Hotwell Level Controller, 2-LIC-4405 CV, to MANUAL. (b) Adjust Controller to open Hotwell To CST Dump CV, 2-CD-4405-CV. (c) Shut one Condensate Pump Discharge Valves l I 21 Pump 7-CD-106 22 Pump 2-CD-113 23 Pump 2-CD-120 (d) Start appropriate Condensate Pump. (e) Slowly open pump discharge valve to maintain flow rate less than 2000 GPM. (f) Stop pump when cavitation occurs. (g) Shut Hotwell To CST Dump CV, 2-CD-4405-CV. , I (OR) (7) Emergency fill 21 CST from Fire Systems (a) Connect fire hose between fire house hose l manifold and 21 CST Emergency Hose Connection i Valve, 2-CD-312. (b) Open 21 CST Emerg9ncy Hose Connection Valve, 2-CD-312. (c) Ensure 21 CST level increasing. l l (OR) l l

EOP-8 R;v. 1/ Unit 2 Pcg3 27 of 49 i I I (8) Emergency fill 11 CST froin Fire Systems (a) Connect fire hose between fire house hose manifold and 11 CST Emergency Hose Connection Valve, 1-CD-312. (b) Open 11 CST Emergency llose Connection Valve, 1-CD-312. l l Ensure 11 CST level increasing. (c) l b. Establish AFW flovpaths (1) Open all motor and steam driven train AFW Block Valves: 21 S/G , 22 S/G ! 2-AFW-4520-CV 2-AFW-4530-CV l 2-ATW-4521-CV 2-AFW-4531-CV 2-AFW-4522-CV 2-AFW-4532-CV [ 2-AFW-4523-CV 2-AFW-4533-CV g (2) LP AFW Block Valve (s) will HOT open from Control 4 I Room, IUKU locally open valve (o) using Iland Transfer l Station (s) on South wall of SRW Room. (3) Open ATH Flow Control Valves: 21 S/_G 27_ S/G 2-AFW-4511-CV 2-AFW-4512-CV 2-AFW-4525-CV 2-AFW-4535-CV (4) IF AFW Flow Control Valve (s) will NOT open, IDEN locally throttle open bypass valve (s): ! (a) 4511-CV 21 S/G Bypass Valve, 2-AFW-163, located in 27 ft East Penetration Room. (b) 4525-CV 21 S/G Bypass Valve, 2-AFW-195, located in SRW Room. (c) 4512-CV 22 S/G Bypass Valve, 2-AFW-165, located in 27 ft East Penetration Room. (d) 4535-CV 22 S/G Bypass Valve, 2-AFW-196, located in SRW Room. l l I I l l l

EOP-8 RCv. 1/ Unit 2 Pcg3 28 cf 49 l I ~

c. Start at least one AFW Pump:
                                    -CAUTIOH-D/G supplying power to 23 AFW Pump flow limit is 300 GPM; o the rwise, flow limit is 575 GPM.

(1) Start 23 AFW Pump: (a) Place 23 AFW Pump Handswitch in START. (b) Ensure normal puup running current of 60 to 70 AMPS. (c) Ensure 23 AFW Pump flow of 150 GFM per S/G. (OR) , (2) Start 21 or 22 ..t. ' tmpi (a) Open 21 and 22 AFW Pump Main Steam Supply Valves: 2-MS-109 l I 2-MS-107 (b) Open 21 or 22 S/G AFW Steam Supply Valveu: 2 MS-4070-CV 2-MS-4071-CV (c) Open 21 and 22 ArW Pump Turbine Throttle /Stop Valves: 2-MS-3986 2-MS-3988 (d) Verify 21 or 22 AFW Pump discharge pressure approximately 100 PSI greater than S/G pressure. (e) Verify 21 or 22 AFW Pump flow of 150 GPM per S/G. (f) Ensure normal or emergency AFW Room Ventilation operable. (OR) { l

EOP-8 R v. 1/ Unit 2 Pega 29 of 49 (3) IF unable to feed S/Gs with bnit 2 AFW Pumps, THEN establish Unit 1 to Unit 2 cross connect operation: (a) Shut Unit 1 motor train AFW Block Valves: g 1-AFW-4522-CV 1-AFW-4523-CV 1-AFW-4532-CV 1-AFW-4533-CV (b) Open Unit 1 to Unit 2 AFW Cross Connect Valve, 1-AEW-4550-CV. 

                                   -CAUTION-D/G Supplying power to 13 AFW Pump flow limit is 300 GPM; otherwise, flow limit is 575 GPM.

(c) Start 13 AEW Pump by placing handswitch in START. (d) Ensure normal pump running current of 60 to 70 AMPS. (e) Maintain 150 GPM flow to each S/G using Unit 2 AFW Flow Control Valves: 2-AFW-4525-CV 2-AFW-4535-CV (OR) i l l l l l l

EOP-8 R;v. 1/ Unit 2 Pcga 30 of 49 l I 

                                                   ~
                                 -CAUTION-D/G supplying power to 23 AFW Pump flow limit is 300 GPM; otherwise, flow limit is 575 GPM.

(4) Locally start 23 AEW Pump: (a) Press CLOSE button at 152-2415. 

                                 -CAUTION-Removing control power fuses causes a loss of overcurrent, undervoltage and ground protection.

(b) IF breaker fails to close, THEN remove or,eaker control power fuses AND press CLOSE button at 152-2415. (OR) (5) Locally start 21 or 22 AFW Pump: (a) Turn turbine governor control knob I I counterclockwise to the minimum position. (b) Isolate the Instrument Air to the Turbine Governor Controller (s): 2-I/P-3987 2-I/P-3989 (c) Open air filter drains on controllers to allow local control. (d) Open AFW Steam Supply Bypass Valves: l l 2-MS-102 1 2-MS-105 (e) Open 21 and 22 AFW Pump Turbine Throttle /Stop Valves: l 2-MS-3986 l 2-MS-3988 I (f) Adjust turbine governor control knob to I maintain AEW Pump discharge pressure 100 PSI greater than S/G pressure. l l OB l l

EOP-8 Rcv. 1/ Unit 2 Pcga 31 of 49 l I 51 IF AFW flow to S/G NOT established AkD power available to Condensate and Condensate Booster Pump, THEN depressurize S/G to allow feeding with Condensate Booster Pump

a. Verify S/G heat removal available per step A.2, page 22.
b. Establish maximum cooldown rate not exceeding 100 F/h.
c. WHEN "SGIS A(B) BLOCK PERMITTED" alarm (s) received, THEN block SGIS A(B).
d. IE SGIS actuates, THEN block SGIS AND reset SGIS signal.

(1) Place Condensate Bopster Pumps in PULL-TO-LOCK. (2) Match handswitches per SGIS Verification Checklist, Attachment (7). (3) Block SGIS. (4) Reset SGIS signal.

e. Open S/G Feedwater Isolation Valves.
f. Shut Main Feed Regulating Valves.
g. Depress Feed Regulating Bypass Valve Roset Buttons.
h. Manually adjust Feed Regulating Bypass Valve Controllers to 30% output.
1. Open Condensate Precoat Filter and Condensate Domin Bypass Valves.
j. Verify one Condensate ? ump running.
k. Verify one Condensate Booster Pump running.
1. Place Heater Drain Pump Handswitches in PULL-TO-LOCK.

I I

EOP-8 R;v. 1/ Unit 2 Pcg] 32 of 49 i I 

                                  .-M01E-Feedwater flow to S/Gs should start when S/G pressure decreases to approximatell 500 PSIA.
m. Monitor feedwater flow to S/G:

(1) Main Feed Regulating Valvo Differential "ressure Controller indicates greater than O. (2) S/G level constant or increasing. 62 Establish RCS Flows

a. Ensure at least one RCP operating in a loop with an operable S/G.

OR

b. Confirm Natural Circulation in at least one operable S/G loop:
                                   -NO_TE -

I I Wide range Thot may be obtained from Subcooled Margin Monitor per Attachment (10). (1) Thot minus Teold between 10 and 50 F. (2) Tcold constant or decreasing. (3) Thot constant or decreasing. (4) CET temperatures consistent with Thot. (5) Steaming rate affects primary temperature.

c. Monitor for Core and RCS voiding:
                                 -CAUTICN-                              ,

1 Potontial for void formation increanos rapidly when pressure decreason below 1500 PSIA.  ; 1 (1) Letdown flow greater than charging flow. l l (2) Rapid unexplained increase in pressurizer level I during an RCS pressure reduction. 1 1

l EOP-8 l Rov. 1/ Unit 2 i Pcga 33 of 49 l 1 i I (3)LossofsubcooledmarginasbeterminedusingCET temperatures. (4) "REACTOR VESSEL WATER LEVEL LOW" alarm.

d. IF voiding inhibits heat removal, THEN reduce or eliminate voided area (1) Shut the Letdown Isolation Valve, 2-CVC-515-CV.

(2) Pregsurize the RCS to maintain subcooling as near 140 F as practical. (3) IF pressurizing the RCS does NOT eliminate the voids, THEN operate Reactor Vessel Vent Valves per OI-1G. 

                                   -CAUTIONS If voids exist in the S/G tubes, a rapid RCS pressure reduction will occur when the voids collapse.

(4) IF voiding occurs in the S/G tubes (saturation pressure of S/G greater than saturation pressure I of RCS), THEN cool the S/G by raising any of the following (a) Steaming rate. (b) Feed rate. (c) S/G 2 lowdown rate. AND maintaining less than 100 F/h cooldown rate. OR B. SAFETY INJECTION CORE COOLING. 12 Ensure HgSI or LPSI flow maintaining CET temperatures less than 560 F and constant or decreasino. { ) OR

EOP-8 R;v. 1/ Unit 2 Pega 34 of 49 l l C. ONCE THROUGH CORE COOLING. 12 Commence Once Through Core Cooline. 

                                                          -CAUTION-After S/G becomes ineffective for heat removal, Once Through Corg Cooling must be initiated prior to CET temperatures reaching 560 F to ensure adequate heat removal.
a. WHEN either of the following conditions exist:

(1) Steaming S/G becomes ineffective and CET temperatures begin to increase. (2) HPSI or LPSI flow insufficient and CET temperatures begin to increase. THEN commence Once Through Core Cooling.

b. Shift Letdown Control Valve Controller, 2-HIC-110, to MANUAL and shut Letdown Control Valves:

2-CVC-110P-CV 2-CVC-110Q-CV

c. Start all available Charging Pumps.
d. Open Main and Aux HPSI Header Valves:

2-SI-616-MOV 2-SI-617-MOV 2-SI-626-MOV 2-SI-627-MOV 2-SI-636-MOV 2-SI-637-MOV 2-SI-646-MOV 2-SI-647-MOV )

e. Start 21 and 23 HPSI Pumps.
f. De-energize the Pressurizer Heaters by placing all handswitches in OFF. j
g. Start all available Containment Air Coolers in HIGH .

with maximum SRW flow. k

l EOP-8 R3v. 1/ Unit 2 Page 35 of 49 l I

h. Open both PORVs:

(1) WHEN "PRSR PRESS BLOCK A(B) PERMITTED" alarm (s) received, THEN block SIAS A(B). (2) Verify both PORV Block Valves open. (3) Pull two High Pressurizer Pressure Trip Units. (4) Verify PORVs open.

1. If containment pressure increases to 2.0 PSIG AND still increasing, THEN start one Containment Spray Pump and open associated Cntmt Spray Header CV.

21 or 22 2-SI-4150-CV 2-SI-4151-CV

j. IF containment pressure increases to 2.8 PSIG, THEN verify ESFAS actuation AND commence Verification Checklists:

q g (1) SIAS per Attachment (2). (2) CIS per Attachment (4).

k. IF containment pressure increases to 4.25 PSIG, 2]EU verify CSAS actuation AND commence Verification Checklist, Attachment (3).
1. Confirm initiation of Once Through Core Cooling.

(1) WHEN RCS pressure is less than 1270 PSIA, THEN ensure HPSI flow AND CET temperatures constant or decreasing._

m. Using CgT temperatures, maintain subcooling between 30 and 140 F por Attachment (1) by throttling HPSI flows (1) Lower subcooling by lowering HPSI flow.

(2) Raise subcSoling by raising HPSI flow,

n. Continue coolduwn using Once Through Core Cooling i until feedwater restored or shutdown cooling entry i conditions are establinhed.

1

EOP-8 R v. 1/ Unit 2 Pcg3 36 of 49 CONTAINMENT ISOLATION I. PRECAUTIONS A. Local radioactivity levels should be determined before attempting local manual valve isolation. II. CONTAINMENT ISOLATION ACCEPTAPK:E CRITERI A A. IF either of the following conditions exist:

1. Containment pressure less than 0.7 PSIG and the following RMS alarms clears
a. S/G Blowdown. .
b. Condenser Off-Gas.
c. Main Vent Gaseous (2-RI-5415). i
d. Containment Radiation Monitors.

I e. Noble Gas Monitor. 9B

2. Each containment penetration required to be shut has an isolation valve shut.

THEN Containment Isolation Safety Function is satisfied. B. WHEN Containment Isolation Safety Function is satisfied, TUEH proceed to the next Safety Function in jeopardy. I I l

EOP-8 Rcv. 1/ Unit 2 Pcga 37 of 49 l l III. RECOVERY ACTIONS A. VERIFY AUTOMATIC PROTECTIVE ACTIONS OCCUR. 12 Verify SIA3, CIS, CSAS:

a. IF containment pressure increases to 2.8 PSIG, THEN verify ESFAS actuation AND commence Verification Checklists:

(1) SIAS per Attachment (2). (2) CIS per Attachment (4).

b. IF containment pressure increases to 4.25 PSIG, THEN verify CSAS actuation bHD commence Verification Checklist, Attachment (3).

l I B. IF A SIAS, CIS, CSAS VALVE FAILS TO SHUT, THEN SHUT LOCALLY OR SHUT NEXT VALVE OUT FROM PENETRATION. C. CHECK LOCKED VALVE DEVIATION LOG TO DETERMINE IF ANY MANUAL CONTAINMENT ISOLATION VALVES NEED TO BE SHUT. D. IF S/G HAS A RUPTURED TUBE AND S/G NOT REQUIRED FOR HEAT REMOVAL, RIE}! ENSURE S/G ISOLATED. E. JF CONTAINMENT RMS ALARM RECEIVED, RIElf START ALL AVAILABLE IODINE FILTER FANS. I I

I EOP-8 Rev. 1/ Unit 2 Pega 38 of 49 l I CONTAINMENT ENVIRONMENT I. PRECAUTIONS None II. CONTAINMENT ENVIRONMENT ACCEPTANCE CRITERIA A. IF either of the following conditions exist:

1. Containment temperature and pressure are constant or decreasing and:
a. Containment temperature is less than 222 F.
b. Containment pressure is*1ess than 2.8 PSIG.
c. H, concentration less than 2% (only necessary if greater than four hours sirice initiation of event.)

OB l l 2. Containment temperature and pressure are constant or decreasing and:

a. Containment Spray flow is greater than 1350 GPM.
b. H 7 concentration less than 2% (only necessary if greater than four hours since initiation of event.)

l THEU Containment Environment Safety Function is satisfied. T l B. WHEU Containme.it Environment Safety Function is satisfied, l THEN proceed to the next safety function in jeopardy. l i l l l l I 1 i l l

EOP-8 R2v. 1/ Unit 2 Pega 39 of 49 I I III. RECOVERY ACTIONS A. VERIFY AUTOMATIC PROTECTIVE ACTIONS OCCUR. 12 VERIFY SIAS, CIS, CSAS:

a. IF containment pre saure increases to 2.8 PSIG, THEN verify ESFAS sctuation AND commence Verification Checklists:

(1) SIAS per Attachment (2). (2) CIS per Attachment (4).

b. IF containment pressure increases to 4.25 PSIG, THEN verify CSAS actuation AND commence Verification Checklist, Attachment (3).

B. MAINTAIN CONTAINMENT COOLING. 12 Maintain at least one of the following minimum containment cooling combinations in operation whi13 containment pressure is above 4.25 PSIO:

a. Two Containment Spray trains.  !

OR

b. One Containment Spray train and any two Containment Air Coolers with maximum SRW flow.

I OR

c. Three Containment Air Coolers with maximum SRW flow. ,

5'; 22 Verify SRW Pump Room Ventilation in service, por 01-15. l l m

EOP-8 R3v. 1/ Unit 2 Pcga 40 of 49 l I  : C. HYDROGEN CONTROL: 12 Direct Chemistry to place Hydrogen Monitors in pervice. 21 Establish containment ventilation to ensure no local hydrocen accumulations

a. Start available Containment Air Coolers,
b. Start available Cavity Coolinc Fans.
3. IF hydrogen concentratica increassa to 1%,

THEN start Hydrocen Recambiners por OI-41A. OB 42 With approval of GEC, establish Hydrogen Purge System Operation per OI-41B. l I I I

EOP-8 R v. 1/ Unit 2 Pcga 41 of 49 l I IV. SAFETY FUNCTION STATUS CHECK A. The STA (or person designated by STA) will perform the safety function status checka at 10 minute intervals until plant conditions stabilize.  ; B. Immediately notify Shift Supervisor or Control Room Supervisor if any safety function criteria is not being satisfied. C. Review data and verify that safety function acceptance criteria are satisfied. D. When all safety function acceptance criteria are being satisfied, diagnosis of event (s) may begin. The safety function status checks of EOP-8 should continue E. until an appropriate optimum recovery procedure .s selected. . g l P 1 1

EOP-8 Rcv. 1/ Unit 2 Pega 42 of 49 i I REACTIVITY CONTROL ACCEPTANCE CRITERIA REACTIVITY SAFETY FUNCTION ACCEPTANCE CRITERIA CONTROL PARAMETERS CRITERIA STATUS CHECK

o. WRNI power decreasing _______________________________,
b. SUR (DPM) negative ________________________________
c. CEA status all ireerted ________________________________

or Soration status: concentation increasing ________________________________ BAST /RWT level decreasing ________________________________ Reactivity Control Safety Function is satisfied ift CRITERIA SATISFIED

a. All CEAs inserted and WRNI power decreasing. _______,,,_____________

OR

b. RCS boration in progress and WRNI power decreasing. _______________________

OR

c. WRNI power less than 10 ~4 % and constant or decreasing. _______________________

1 l l l I l 1

EOP-8 R2v. 1/ Unit 2 Pcga 43 of 49 { } RCS PRESSURE AND INVENTORY ACCEPTANCE CRITERIA RCS PRESSURE SAFETY FUNCTION ACCEPTANCE CRITERIA AND INVENTORY PARAMETERS CRITERIA STATUS CHECK

c. Pressurizer within limits pressure (PSIA) per Attachment (1) _______________________________
b. Pressurizer level (inches)* 35 to 250 _____________________,,,_______
c. Charging flow greater than 40 ________________,,_____________

(GPM)

d. HPSI flow (GPM) per Attachment (12) ,______________________________
o. LPSI flow (GPM) per Attachment (13) _______________________________

30 to 140 -------------------------------

f. RCS Subcooling ( F) core covered -------------------------------
q. RVLMS I I
  • Limit may be exceeded for solid plant operation.

RCS Pressure and Inventory Safety Function is satisfied if: CRITERIA SATISFIED

c. RCS pressure and temperature are within the limits por Attachment (1) ands (1) Pressurizer level is between 35 and 250 inches.

(2) RCS subcooling is greater than 30 F using CET temperatures. (3) RVLMS indicates that the Core is covered. .,______,,,,______ OR

b. RCS pressure and temperature are within the limits per Attachment (1) ands (1) All available Charging Pumps running.

(2) HPSI and LPSI Pumps are injecting water into RCS per Attachment (12) and (13). (3) RVLMS indicates that the Core is covered. ,,,_______________

EOP-8 R;v. 1/ Unit 2 PCg3 44 of 49 l I CORE AND RCS HEAT REMOVAL ACCEPTANCE ChtITERIA CORE AND RCS SAFETY FUNCTION ACCEPTANCE CRITERIA HEAT REMOVAL PARAMETERS CRITERIA STATUS CHECK

o. S/G pressure (PSIA) less than 960 _______________________________
b. S/G level (inches) (-)250 to (+)5O _______________________________
c. CST level (ft) greater than 5 _______________________________
d. Feedwater flow (GPM) greater than 150 ,______________________________
o. CET ( F) less than 560 ______________________________.
f. RCS Subcooling ( F) 30 to 140 _______________________________
g. RVLMS core covered ,,,_____________________________

I I h. Teold ( F) less than 540 _______________________________

i. Tgot minus Tcold

( F) Natural circulation 10 to 50 __________________________ ___ Forced Circulation less than 10 _______________________________

j. HPSI flow (GPM) per Attachment (12) _______________________________
k. LPSI flow (GPM) per Attachment (13) ,,_____________________________

1 1 1

EOP-8 R3v. 1/ Unit 2 Pcgo 45 of 49 i I CoreandRCSHeatRemovalSafetyFunctionissatisfiddif CRITERIA SATISFIED

c. One S/G with level between (-)250 and

(+)50 inches and trending toward zero and (1) RCS flow by Forced Flow or Natui 1 Circulation. (?) RCS subcooling greater than 30 F using CETs. (3) CET temperatures constant or decreasing. (4) RVLMS indicates that the Core is covered. ____________________ 1 OR

b. One S/G with feedwater flow greater than 150 GPM and level being restored ands (1) RCS flow by Forced Flow or Natural Circulation. 1 1

(2) RCS subcooling greater than 30 F using CETs.  ; (3) CET temperatures constant or decreasing. (4) RVLMS indicates that the Core is covered. ____________________ l OR i

c. IIPSI or LPSI Pumps injecting water into RCS and CET temperatures constant or j decreasing. ____________________ l l

OR l

d. Once Through Core Cooling in progress and CET temperatures c..aetant or decreasing. ____________________

l I

EOP-8 Rcv. 1/ Unit 2 Pc.g 3 46 of 4? l I VITAL AUXILIARIES ACCEPTANCE CRITE51IA VITAL SAFETY FUNCTION ACCEPTANCE CRITERIA AUXILIARIES CRITERIA STATUS CHECK

o. 4KV vital buses 21 or 24 energized _______________________________
b. Instrument Air greater pressure (PSIG) than 88 _______________________________
c. Component Cooling

(# pumps running) 1 or 2 ,_______________,,______________

d. Saltwater

(# pumps running) 1 or 2 _______________________________

o. Service Water

(# pumps running) 1 or 2 _______________________________ { I f. 125V DC buses 11, 12, 21, 22 energized _______________________________

g. 120V AC vital buses 21, 22, 23, 24 energized _______________________________

Refer to appropriate AOP for any Vital Auxiliaries in jeopardy. l I

EOP-8 R;v. 1/ Unit 2 Pega 47 of 49 I I CONTAINMENT ISOLATION ACCEPTANCE CRIT $RIA CONTAINMENT SAFETY FUNCTION ACCEPTANCE CRITERIA ISOLATION PARAMETERS CRITERIA STATUS CHECK

c. Containment less than Pressure (PSIG) 0.7 ________________________________
b. S/G B/D RMS alarm clear ________________________________
c. Condenser Off-Gas RMS alarm clear ________________________________
d. Main Vent Gaseous RMS (2-Rl-5415) alarm clear ________________________________
o. Containment Radiation Monitors alarms clear ________________________________
f. Noble Gas Monitor alarm clear _,______________________________
g. Containment all required penetration valves to be shut are shut . ______________________________

Containment Isolation Safety Function is satisfied if: CRITERIA SATISFIED

a. Containment pressure less than 0.7 PSIG and the following RMS alarms clear (1) S/G Blowdown.

(2) Condenser Off-Gas. (3) Main Vent Gaseous (2-Rl-5415). (4) Containment Radiation Monitors. (5) Noble cas Monitor. _________________,.. OR Each containment penetration required to l ) b. be shut has an isolation valve shut, __,____,________,,__ l

EOP-8 Rav. 1/ Unit 2 Pcga 48 of 49 COJUAINMENT ENVIRONMENT ACCEPTANCE CRITERIA r;ONV INMENT SAFETY FUNCTION ACCEPTANCE CRITERIA L.W.~ "ONMENT __ CRITERIA STATUS CHECK

c. Containmert less than tem,3rature (*A*) 222 __________________________._____
b. Containment less than Presture (PSIG) 2.8 ________________________________
c. Containment spray greater than flow (GPM) 1350 _3,_____________________________
d. Hydrogen less than concentration 2% ________________________________

Containment Environment Safoty Function is satisfied if I k CRITERIA SATISFIED

c. Containment temperature and pressure are constant or decreasing and :

(1) Congainment temperature is less than 222 F. (2) Containment pressure is less than 2.8 PSIO. (3) H 3 concentration less than 2% (only n8cessary if greater than four hours since initiation of event.) _________.,__________ OR

b. Containment temperature and pressure are constant or decreasing and :

(1) Containment Spray flow is greater than 1350 GPM. (2) H 3 concentration lors than 2% (only n8cessary if greater than four hours { ) since initiation of event.) ____________________

EOP-8 R';v . 1/ Unit 2 Pcg3 49 of 49 I I STATUS CHECK COMPLETE AT NUMBER TIME 1 2 3 4 l l l l l l I

ATTACHMENTS R v. 1/ Unit 1 l l CALVERT CLIFFS NUCLEAR POWER PLANT ATTACHMF#fS REVISION 1 SIGNATURE DATE PREPARED BY; G M L .O ~ / \7 c-O 

                                                                                             ~%

j l VERIFIED BY; 4 / /2//o/# 7 _/ POSP.0; _ MEETING # W3~7 / 2- ic '8 *3 APPROVED BY; _h a , we / 7 - W - (c',*6 MarfageY-Huclear Operations or General Supervisor-Operations if POSRC review to not required l I

1 ATTACHMENTS I Rsv. 1/ Unit 1 ) ( ) . L_IST OF EFFECTIVE PAGES ATTACHMENT PAGE REVISION 1 1 1 2 1 1 2 2 1 2 3 1 2 4 1 2 5 , 1 3 1 1 4 1 1 5 1 1 { } 6 1 1 7 1 1 8 1 1 8 2 1 9 1 1 i 10 1 1 l 11 1 1 l i 12 1 1 13 1 1 l l l 4 f 1 l

i ATTACHMENT (1) ATTAcm ENTS MY.1/LMIT i RCS PRESSURE TEMPERATURE LIMITS PAst i OF i 10-40 YEAR CURVE 2400. iiii .. >isi iiii siii iiii iiii iiis siis iisi iiii sisi 

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Attcchm:nta R v. 1/ Unit 1 Pcg3 1 cf 5 ATTACUMENT (2) l I SIAS VERIFICATION CHECKLIST . 1C08, 1C09, IC10

c. 11 and 13 HPSI Pumps .................................... Running
b. 11 and 12 LPSI Pumps ........... ........................ Running
c. HPSI Aux Header Isolation Valvo, 1-SI-656-MOV ........... Open
d. 4 Main HPSI Header Valves:

1-SI-616-MOV 1-SI-626-MOV 1-SI-636-MOV 1-SI-646-MOV ............................................ Open

o. 4 Aux HPSI Header Valves:

1-SI-617-MOV 1-SI-627-MOV 1-SI-637-MOV 1-SI-647-MOV ............................................ Open 4 g f. 4 LPSI Header Valves: 1-SI-615-MOV 1-SI-625-MOV 1-SI-635-MOV 1-SI-645-MOV ............................................ Open

g. 4 SI Tank Check Valve Leakage Drain Valves:

1-SI-618-CV 1-SI-628-CV 1-SI-638-CV 1-SI-648-CV .. .......................................... Shut *

h. 4 SI Tank Outlet Valves:

1-SI-614-MOV 1-SI-624-MOV 1-SI-634-MOV 1-SI-644-MOV ............................................ Open

1. SI Tank Recirc to RCDT Isolation Valve, 1-SI-661-CV ..... Shut
  • o HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET OF SIAS CAN BE ACCOMPLISHED FROM THE CONTROL ROOM.

Att: chm:nta rov. 1/ Unit 1 Pcga 2 cf 5 ATTACUMENT (2) { } SIAS VERIFICATION _ CHECKLIST ,

j. 2 Cntmt Spray Hender CVs:

1-SI-4150-CV 1-SI-4151-CV ............................................ Open

k. 2 Cntmt Purge Supply Valves:

1-CPA-1410-CV 1-CPA-1411-CV ........................................... Shut *

1. 2 Cntmt Purge Exhaust Valves:

1-CPA-1412-CV 1-CPA-1413-CV ........................................... Shut *

m. RCDT Pump Containment Isolation Valve,*1-RCW-4260-CV .... Shut *
n. 2 Waste Gas Cntmt Isolation Valves:

1-WGS-2180-CV 1-WGS-2181-CV ........................................... Shut

  • 4 g o. 2 Containment RMS Isolation Valves:

1-CRM-5291-CV 1-CRM-5292-CV ........................................... Shut *

p. 2 Containment Normal Sump Drain Isolation Valves:

1-EAD-5462-MOV 1-EAD-5463-MOV .......................................... Shut *

q. RCS Sample Isolati< /cive, 1-PS-5464-CV ................ Shut *
r. Containment licating Water Isolation Valve, 1 - Plf- 6 579 -MOV . Shut *
o. 2 Ilydrogen Purge Cntmt Isolation Valves:

1-lip-6900-MOV 1-l!P-6901-MOV ........................................... Shut

  • 0 IIANDSWITCl! MUST DE PLACED IN POST-ACCIDENT POSITION DEFORE RESET OF ,

SI AS CAN DE ACCOMPLIS!!ED FROM Tile CONTROL ROOM. l l l l I i i

Atttchm:nto 1 R;v. 1/ Unit 1 l Page 3 of 5 l ATTACHMENT (2) i SIAS VERIFICATION CHECKLIST . IC07

a. 2 Letdown Isolation Valves:

1-CVC-515-CV 1-CVC-516-CV ............................................ Sh'a t * ;

b. 11, 12, and 13 Charging Pumps ........................... Running
c. VCT Outlet Valve, 1-CVC-501-MOV ......................... Shut
d. VCT Makeup Valve, 1-CVC-512-CV .......................... Shut
o. Boric Acid Direct Makeup Valvo, 1-CVC-514-MOV ........... Open
f. 11 and 12 Boric Acid Pumps ...... ....'.................. Running
g. 2 DAST Gravity Feed Valves:

1-CVC-508-MOV 1-CVC-509-MOV ........................................... Open { l h. 2 Boric Acid Recirculation Valves: l 1-CVC-510-CV l 1-CVC-511-CV ............................................ Shut  !

1. 2 RCP Bleedoff Isolation Valves: .

1-CVC-505-CV i 1-CVC-506-CV .................. ......................... Shut

  • 1 1C06
c. 11 and 13 Pressurizer Backup Heaters .................... Off l

l IC13

c. 11 and 12 Component Cooling Pumps ....................... Running l
b. 11 and 12 Saltwater Pumps ............................... Running o

llANDSWITCli MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET OF SIAS CAN BE ACCOMPLISilED FROM T!!E CONTROL ROOM.

Attc. chm:nta R:v. 1/ Unit 1 Page 4 of 5 ATTACHMENT (2) i l SIAS VERIFICATION CHECKLIST .

c. 11 and 12 Service Water Pumps ........................... Running
d. 2 SDC HX Component Cooling Outlet Valves:

1-CC-3828-CV 1-CC-3830-CV ............................................ Open

e. 4 SRW Turbino Building Header Isolation Valves:

1-SRW-16?O-CV 1-SRW-1637-CV 1-SRW-1638-CV 1-SRW-1639-CV ........................................... Shut

f. 2 Circulating Water Pump Room Air Coolgr Isolation Velves:

1-SW-5250-MOV 1-SW-5251-MOV ........................................... Shut

g. 11 and 12 Saltwater Air Compressors ..................... Running (Y 2C24A
a. 11 Component Cooling HX Saltwater Inlet and Outlet Valves:

1-SW-5160-CV 1-SW-5206-CV ......... DO NOT MATCH HANDSWITCH .......... Shut

b. 12 Component Cooling HX Saltwater Inlet Valve, 1-SW-5162-CV ......... DO NOT MATCH HANDSWITCH .......... Shut
c. 12 Component Cooling HX Saltwater Outlet Valves:

1-SW-5208-CV 1-SW-5163-CV ......... DO NOT MATCH HANDSWITCH .......... Shut

d. 11 SRW HX Saltwater Outlet Valve, 1-SW-5210-CV .......... Full Open
o. 12 SRW HX Saltwater Outlet Valve, 1-SW-5212-CV .......... Full Open l I

a Atttchm:nto Rcv. 1/ Unit 1 Pcg3 5 of 5 ATTACHMENT (2) l I SIAS VERIFICATION CHECKLIST . l IC18, IC19, IC2O

o. 11 Diesel Generator ..................................... Running
b. 12 Diesel Generator ..................................... Running
c. 21 Diesel Generator ..................................... Running 1C34
c. 11 Containment Purge Exhaust Fan ........................ Off
b. 11 Containemnt Purge Supply Fan ......................... Off 1C90 (45 ft S/G B/D Sample Panel)
c. Pressurizer vapor Sample Valve, 1-PS-5465-CV ............ Shut
b. Preusurizer Liquid Sample Valve, 1-PS-5466-CV ........... Shut I I c. RCS Hot Leg Sample Valve, 1-PS-5467-CV .................. Shut 1C101 (45 ft Solid Waste)
c. Quench Tank 0 2 Sample Valve, 1-PS-6531-SV ............... Shut 1

i i i 1 l l l

Att: chm';nto R;v. 1/ Unit 1 Pcg3 1 cf 1 ATTACHMENT (3) l I CSAS VERIFICATION CHECKLIST . ICO3

a. 11 and 12 Main Steam Isolation Valves:

1-MS-4043-CV 1-MS-4048-CV ............................................ Shut *

b. 11 and 12 S/G Feedwater Isolation Valves:

1-FW-4516-MOV 1-FW-4517-MOV ........................................... Shut *

c. 11 and 12 S/G Feed Pumps ................................ Tripped
d. 11 and 12 Heater Drain Pumps ............................. Off
c. 11, 12, and 13 Condensate Booster Pumps ................. Off 1C00, IC09, IC10
c. 11 and 12 Containment Spray Pumps ....................... Running
b. 4 Containment Air Cooler 8 Inch Outlet Valves:

1-SRW-1582-CV 1-SRW-1585-CV 1-SRW-1590-CV 1-SRW-1593-CV ........................................... Open

c. 11, 12, 13, and 14 Containment Air Coolers .... , Running in low i

IC13 l 1

c. 11 SFP Cooler Service Water Isolation Valves:

1-SRW-1596-CV 1-SRW-1597-CV ........................................... Shut l l 6 HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET OF CSAS CAN BE ACCOMPLISHED FROM THE CONTROL ROOM. l l l 1

Atttchm:nto R;v. 1/ Unit 1 Pcg3 1 of 1 ATTACHMDTI (4) l l _CIS_ VERIFICATION CHECKLIST i ICO9, IC10

a. 11, 12, and 13 Iodine Filter Fans ....................... Running
b. 11 and 12 Penetration Room Vent Fans .................... Running
c. 11 and 12 Penetration Room Vent Filters Isolation Dampers Open
d. Component Cooling Containment Isolation Valves:

1-CC-3832-CV 1-CC-3833-CV ............................................ Shut *

e. Containment Instrument Air Isolation MOV, 1-IA-2080-MOV . Shut *
f. Instrument Air CIS Override, 1-HS-2080$ ................. Normal
  • 1C13
a. Component Cooling Supply To Liquid Waste Evaporator Isolation Valves:

l I 1-CC-3840-CV 1-CC-3842-CV ............................................ Shut HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION SEFORE RESET OF CIS CAN BE ACCOMPLISHED FROM THE CONTROL ROOM. l 1 1

Attcchm:nto R;v. 1/ Unit 1 : PCg3 1 of 1 ATTACHMENr (5) ( ) CRS VERIFICATION CHECKLIST , 1C10

c. 2 Cntmt Purge Supply Valves:

1-CPA-1410-CV Shut

  • 1-CPA-1411-CV ...........................................
b. 2 Cntmt Purge Exhaust Valves:

1-CPA-1412-CV Shut

  • 1-CPA-1413-CV ...........................................
c. 2 Hydrogen Purge Cntmt Isolation Valves:

1-HP-6900-MOV . Shut

  • 1-HP-6901-MOV ...........................................

1C34 11 Containment Purge Exhaust Fan ......................... Off a. Off I I b. 11 Containment Purge Supply Fan .......................... HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET OF CRS CAN BE ACCOMPLISHED FROM THE CONTROL ROOM. l I

Att chm nto R v. 1/ Unit 1 Pcg3 1 cf 1 ATIACIDGDff (6) l I RAS VERIFICATION CHECKLIST , IC08, 1C09, ICIO

a. 11 and 12 LPSI Pumps .................................... Off
b. SI Pump Mini Flow Isolation Valves:

1-SI-659-MOV 1-SI-660-MOV ............................................ Shut

c. Containment Sump Discharge Valves:

1-SI-4144-MOV 1-SI-4145-MOV ........................................... Open 2C24A

a. 11 Component Cooling HX Saltwater Inlet Valve, 1-SW-5160-CV ............................................ Open
b. 11 Component Cooling HX Saltwater Outlet Valve, 1-SH-5206-CV ............................................ Auto I l
c. 12 Component Cooling HX Saltwater Inlet Valve, 1-SW-5162-CV ............................................ Open
d. 12 Component Cooling HX Sal *. water Outlet Valves:

1-SW-5208-CV 1-SW-5163-CV ............................................ Auto

e. 11 SRW FX Saltwater Outlet Valve, 1-SW-5210-CV .......... Auto
f. 12 SRW HX Saltwa:er Outlet Valve, 1-SW-5217 CV .......... Auto I

l l l I l l l l k l l l l

Att chm:nte R;v. 1/ Unit 1 Pago 1 cf 1 ATTACIDUNI (7) I > SGIS VERIFICATION CHECKLIST , 1CO3

c. 11 and 12 Main Steam Isolation Valves:

1-MS-4043-CV 1-MS-4048-CV ............................................ Shut *

b. 11 and 12 S/G Feedwater Isolation Valves:

1-FW-4516-MOV 1-FW-4517-MOV ........................................... Shut *

c. 11 and 12 S/G Feed Pumps ................................ Tripped
d. 11 and 12 Heater Drain Pumps ..........,.................. Off
o. 11, 12, and 13 Condensate Booster Pumps ................. Off o

HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET OF l I SGIS CAN BE ACCOMPLISHED FROM THE CONTROL ROOM. I >

l Attcclun:nto Et;v. 1/1Jnit 1 Page 1 of 2 ATTACHMENT (8) VIDE RANGE STEAM GENERAIDR MVEL TABLE FOR VARIABLE STEAM GENERAIDR PRESSURES & VARIABLE CONTAINMENT TEMPERATURES INDICATED LEVEL FOR INDICATED LEVEL FOR INDICATED LEVEL FOR AMBIENT CRDit AMBITRT CN1WT AMBIERT CRINT TEMP 120 F TEMP 200 F TEMP 300 F S/G PRESSURE S/G PRESSURE S/G PRESSURE ACTUAL (PSIA) (PSIA) (PSIA) LEVEL 900 500 100 900 500 100 900 500 100 

      -400        -400     -401     -401       -386    -387 ,. -398   -353      -361   -369
      -390        -390     -395     -400       -371    -376     -386  -344      -350   -357
      -380        -380     -383     -388       -361    -366     -373  -334      -340   -345
      -370        -370     -372      376       -351    -355     -361  -324     -329    -333
      -360       -360      -361     -364       -341    -344     -349  -314       310  -320 l I    -350       -350      -350     -351      -331     -333     -337  -304     -307   -308
      -340       -340      -340     -339       -321    -323     -324  -294     -296   -296
      -330       -330      -329     -327      -311     -312     -312  -284     -285   -283
      -320       -320      -318     -315       -300    -301     -300  -274     -275   -271
      -310       -310      -308     -302      -290     -290     -287  -265     -263   -259
      -300       -300      -297     -291      -280     -280     -275  -255     -253   -247
      -290       -290      -286     -278       -273     269     -262   245     -242   -234
      -280       -280      -275     -266      -264     -235     -250  -235     -231     222 270       -270      -265     -253      -258     -247     -238   225     -220   -210
      -260       -260      -254     -242      -244     -237     -226  -215""~-210       197
      -250       -250      -243     -230      -234     -226     -214   201     -199   -185
      -240          240    -233     -216      -224     -215     -201    195      188  -173
      -230       -230      -222     -204      -214     -204     -189  -185     -177   -161
      -220       -220      -211     -192      -204     -194     -176  -176     -166   -148
      -210       -210      -200     -180      -194     -183     -164  -166     -156   -136
      -200       -200       190      168      -184     -172     -151  -156     -145   -124
      -190       -190      -179     -155      -174     -160    -139   -146     -134   -111 l I    -180       -180      -168     -143      -164     -160    -127   -136       123  -99
      -170       -170      -157     -132        154    -139    -115   -126     -112   -87

l l Attcclun:nto R;v. 1/ Unit 1 , Pcgo 2 cf 2 l l ATTACHMENT (8) I I WIDE RANGE SIT.AM GENERATUR 12 VEL TAB 12 FOR VARIABIE STEAM GENERATUR PRESSURES & VAkl ABIE. CONTAINMENT TIMPERATURES (cont'd) INDICATED LEVEL FOR INDICATED LEVEL FOR INDICATED LEVEL FOR INT AMBIENT CgTNT AMBIENT CRINT AMBIEST IT.MP 120 Cg*F TEMP 200 F TEMP 300 F S/G PRESSURE S/G PRESSURE S/G PRESSURE ACTUAL (PSIA) (PSIA) (PSIA) LEVEL 900 500 100 900 500 100 900 500 100 

    -160       -160     -146    -119       -144            -129 , -103                           -116     -101   -75
    -150       -150     -135    -107        134            -118         -91                      -106     -91    -62
    -140       -140     -124    -95        -125            -107        -79                       -97      -80    -50
    -130       -130     -114    -83        -115            -92         -66                       -87      -69    -38
    -120       -120     -103    -70        -105            -86          -54                      -77      -38    -25 q g  -110       -110     -92     -58        -95             -75        -42                        -67      -47    -13
    -100        100     -81     -46        -86             -64        -30                        -57      -37    -1
    -90        -90      -70     -33        -76             -53        -18                         47      -26   +12
    -80        -80      -59     -21        -66             -43        -6                         -37      -15   +24
    -70        -70      -49     -9         -76             -32     +7                            -27      -4    +36
    -60        -60      -38     +3          46             -21     +19                           -18      +7    +48
    -50        -50      -27     +15        -36             -11     +31                           -8       +18   +61
    -40        -40                         -26 6   +28                             0  +44                           +2       +28   +63.5
    -30        -30      -5      + *+ 1     -16           +11       +56                           +12      +39   +63.5
    -20        -20      +6      +53        -7            +22       +0.       5                   +22      +50   +63.5
    -10        -10      +16     +63.5      +3            +32       + 6 3 .                     +32      +61   +63.5 0          0       +27     +63.5      +13           +43       +63.5                         +42      +63.5 +63.5 10        +10      +38     +63.5      +23           +54       +63.5                         +52      +63.5 +63.5 20        +20      +49     +63.5      +33           +63.5     +63.5                         +62      +63.5 +63.5 30        +30      +60     +63.5      +43           +63.5     +63.5                         +63.5    +63.5 +63.5   ;

40 +40 +63.5 +63.5 +53 +63.5 +63.5 +63.5 +63.5 +63.5 f 50 +50 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5 +C3.5 q g 60 +60 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5

Attccivn:nto R;v. 1/ Unit 1 Page 1 cf 1 ATTACHMENT (9) PRESSURIZER IEVEL TABIE FOR VARIABM PR),SSURIZER MSSU_RES & VARI ABM CONTAINNENT 'IT.MPF.RATURES INDICT.TED IEVEL FOR INDICATED LEVEL FOR INDICATED LEVEL FOR AMBIENTCgm AMBIENT cgm AMBIENT CRINT TEMP 120 F TEMP 200 F TEMP 250 F PRESSURIZER PRESSURE PRESSb.tIZER PPI3SURE PRESSURIZER PRESSURE ACTUAL (PSIA) (PSIA) (PSIA) LEVEL 300 1000 2250 300 1000 2250 300 1000 2250 50 25 29 50 39 44 , 68 53 57 82 75 65 61 75 84 80 94 99 95 109 100 107 96 100 128 116 119 140 128 134 125 149 131 125 167 152 143 183 167 159 150 191 167 150 211 188 168 228 201 183 g 175 236 205 175 248 222 192 270 237 208 200 278 240 200 294 2'59 216 310 274 233 

                                                          ~~

250 362 308 250 370 332 267 370 344 274 300 370 370 300 370 370 318 370 370 334 350 370 370 350 370 310 368 370 370 370 370 370 370 370 370 370 370 370 370 370 t > l l

Att chm:nts R;v. 1/ Unit 1 Pcgo 1 cf 1 ATTACHMENT (10) PROCEDURE TO_ READ Thot ON _SUBCOOTED MARGIN _ MONITOR

1. a) If in Press Mode: Depress control switch 3 times within 3 seconds.

This will illuminate temperature and start testing sequence. When the unit is in the test mode, the decimal indicator furthest to the right flashes every 1/2 second, b) If in Temperature Mode: Depress control switch 4 times within 3 seconde. This will start testing sequence. When the Unit is in the test mode, the decimal indicator l I furthest to the right flashes every 1/2 second.

2. Test #0 has started (number sequencing - fast speed). To advance the Test #, depress the control switch. Thiw will illuminate PRESS and the display will count from 1 to 16 (in slow speed). When number "5" is displayed, depress the control switch. This will illuminate TEMP and indicate Thot on the display. Thot will be displayed for a maximum of 20 minutes at which point it automatically returns to normal operation (Press Margin Display). To return to normal operation prior to this 20 minute delay, depresc the control switch. This will illuminate PRESS, count to 16, and automatically return to pressure margin display. To read temp margin, depress the control switch once to illuminate TEMP.

> e l _ 9 MAKEUP WATER REQUIRED FOR RCS COOLDOWN MAKEUP REQUIRED VS. TIME UNTIL RCS COOLDOWN IS COMMENCED cam ca 88-1137 ( 1 FT. - 9636.78 CAL. ) 600 340 . . . . - j- . . . a 660 m 338 / c 648 h 328 / . If 620 0 31B / y / g oss t see 

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ATTACHMENTS R v. 1/ Unit 2 I I i CALVERT CLIFFS NUCLEAR POWER PLANT A'1"rACIDG2Rf2 REVISION 1 SIGNATURE DATE PREPARED BY; r G>Q w 2 _ / G "3' O { ) VERIFIED BY; 1 _ Ar%@ //2[r 7 POSRC; {~ MEETING # D 'l / 7 * \ 0 'E APPROVED BY; Y[ s,wtp / M C ' ' 76 Man ger-Nuclear Operations or General Supervisor-Operations if POSRC review is not required i I

ATTACHMCNTS RSv. 1/ Unit 2 l I LIST OF_ EFFECTIVE PAGES ATTAC_IIMENT Pb_GF; REVISIOB 1 1 1 2 1 1 2 2 1 2 3 1 2 4 1 2 5 , 1 3 1 1 4 1 1 5 1 1 l I 6 1 1 7 1 1 8 1 1 8 2 1 9 1 1 10 1 1 

       *1                   1                1 12                    1               1 13                    1               1

   '                                                                                                                                      1 ATTACHMENT (1)                                               ATTAcments           l MV. t /LNIT 2 RCS PRESSURE TEMPERATURE LIMITS                                                     raw     ws           :

g 2400.1,i, iiii .... ,,,, iiii 10-40 YEAR CURVE iiii iiii .... . .. iii, iii, ,,,, ii>> iiii. l

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5 s  ; /)i / / i E  :
                                                                   //                                 //                              :

l1000  : // ' 

                                                                                                    /n/                               !
                                                                                                  /'///
                  ~

i 800 

                                                               /                     --
/ / ///  !  !
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                                                      /     ///              2
                                                                                ,;r       2
                                                                                            /
                                                                                                      '     -~ -e (I Ptb9. 1 PUMP.

i 

                                                      } / l                                          t PthP OPNi!TE L(QP)              ~

l , KAX PRESS 

                                           /

2 dR E Cs f /- [ WNE te RbP SAME LOOP. i- 

                                     /                                /                             s Pt*FA                             g i
                            /

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                                                             /

l O O 50 100 150 200 250 300 350 400 450 500 550 G00 650 700 REACTOR COOLANT SYSTEM TEMPERATURE ( F) i __

Attcchm:ntc R;v. 1/ Unit 2 Pogo 1 cf 5 ATIACHMENT (2) I I SIA_S VERIFICATJUN CHECKLIST .. 2C08,_2C09, 2C10

a. 21 and 23 HPSI Pumps .................................... Running
b. 21 and 22 LPSI Pumps .................................... Running
c. HPSI Aux Header Isolation Valve, 2-SI-656-MOV ........... Open
d. 4 Main HPSI Header Valves:

2-SI-616-MOV 2-SI-626-MOV 2-SI-636-MOV 2-SI-646-MOV ............................................ Open

e. 4 Aux HPSI Header Valves:

2-SI-617-MOV 2-SI-627-MOV 

        ?-LI-637-MOV 2-SI-647-MOV ............................................                   Open l l f. 4 LPSI Header Valves:

2-SI-615-MOV 2-SI-625-MOV 2-SI-635-MOV 2-SI-645-MOV ..........................................., Open 9 4 SI Tank Chock Valve Leakage Drain Valves: 2-SI-618-CV 2-SI-628-CV 2-SI-638-CV 2-SI-648-CV .............. .............................. Shut *

h. 4 SI Tank Outlet Valves:

2-SI-614-MOV 2-SI-624-MOV 2-SI-634-MOV 2-SI-644-MOV ...................................... .. .. Open

1. SI Tank Recirc to RCDT Isolation Valve, 2-SI-661-CV ..... Shut
  • HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET q

OF SIAS CAN DE ACCOMPLISHED FROM THE CONTROL ROOM. l l

Attcchm:nto R;v. 1/ Unit 2 Pcg3 2 Cf 5 ATTACUMENT (2) I VERIFICATlON CITECKLI_SJ EISS ,.

j. 2 Cntmt Spray Header CVs:

2-SI-4150-CV 2-SI-4151-CV ............................................ Open

k. 2 Cntmt Purge Supply Valves:

2-CPA-1410-CV 2-CPA-1411-CV ........................................... Shut *

1. 2 Cntmt Purge Exhaust Valves:

2-CPA-1412-CV 2-CPA-1413-CV ........................................... Shut *

m. RCDT Pump Containment Isolation Valve,'2-RCW-4260-CV .... Shut *
n. 2 Waste Gas Cntmt Isolation Valves:

2-WGS-2180-CV 2-WGS-2181-CV ........................................... Shut

  • l I o. 2 Containment RMS Isolation Valves:

2-CRM-5291-CV 2-CRM-5292-CV ........................................... Shut *

p. 2 containment Normal Sump Drain Isolation Valves:

2-EAD-5462-MOV 2-EAD-5463-MOV .......................................... Shut *

q. RCS Sample Isolation Valve, 2-PS-5464-CV ................ Shut *
r. Containment Heating Wate? Isolation Valve, 2-PH-6579-MOV. Shut *
s. 2 Hydrogen Purge Cntmt Isolation Valves:

2-HP-6900-MOV 2-9T-6901-MOV ........................................... Shut

  • HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET OF SIAS CAN BE ACCOMPLISHED FROM THE CONTROL ROOM.

l l

Attcchm:nts R;v. 1/ Unit 2 Pcga 3 of 5 A'ITACHMENP (2) { ) .. 

                               .S_IAS _ VERIFICAT LO!LCIJECILIAT 2 C07,
a. 2 Letdown Isolation Valves:

2-CVC-515-CV 2-CVC-516-CV ............................................ Shut *

b. 21, 22, and 23 Charging Pumps ........................... Running
c. VCT Outlet Valve, 2-CVC-501-MOV ......................... Shut
d. VCT Makeup Valve, 2-CVC-512-CV ......................... Shut
e. Boric Acid Direct Makeup Valve, 2-CVC-514-MOV ........... Open
f. 21 and 22 Boric Acid Pumps ...........).................. Running
g. 2 BAST Gravity Feed Valves:

2-CVC-508-MOV 2-CVC-509-MOV ........................................... Open I I h, 2 Boric Acid Recirculation Valves: 2-CVC-510-CV 2-CVC-511-CV ............................................ Shut

1. 2 RCP Bleedoff Isolation Valves:

2-CVC-505-CV 2-CVC-506-CV ............................................ Shut

  • 2C06
a. 21 and 23 Pressurizer Backup Heaters .................... Off RC12
a. 21 and 22 Component Cooling Pumps ....................... Running
b. 21 and 22 Saltwater Pumps ............................... Running ,

1 i l

  • l HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET OF 1 j } SIAS CAN BE ACCCMPLISHED FRON THE CONTROL ROOM.

l l l l l l

Attachm:nto R v. 1/ Unit 2 Pcg3 4 of 5 ATTACIDGDff (2) ( ) p_lAS VERIFIC_ATION CHE9EI1S_T 4 ,

c. 21 and 22 Service Water Pumps ........................... Running
d. 2 SDC HX Component Cooling Outlet Valves:

2-CC-3828-CV 2-CC-3830-CV ............................................ Open

e. 4 SRW Turbine Building Header Isolation Valves:

2-SRW-1600-CV 2-SRW-1637-CV 2-SRW-1638-CV 2-SRW-1639-CV ........................................... Shut

f. 2 Circulating Water Pump Room Air Cooler Isolation Valves:

2-SW-5250-MOV 2-SW-5251-MOV ........................................... Shut

g. 21 and 22 Saltwater Air Compressors ..................... Running i l I 2Q236
a. 21 Component Cooling hX Saltwater Inlet and Outlet Valves:

2-SW-5160-CV 2 - SW- 5 2 0 6 - CV . . . . . . . . . DO NOT MATCII IIANDSW I TCil .......... Shut

b. 22 Component Cooling HX Saltwater Inlet Valve, 2-SW-5162-CV ......... DO NOT MATCII 11ANDSWITCII .......... Shut
c. 22 Component Cooling HX Saltwater Outlet Valves:

2-SW-5208-CV 2 - SW- 516 3 -CV . . . . . . . . . DO NOT MATCII HANDSWITCll . . . . . . . . . . Shut

d. 21 SRW HX Saltwater Outlet Valve, 2-SW-5210-CV .......... Full Open )

1

e. 22 SRW HX Saltwater Outlet Valve, 2-SW-5212-CV .......... Full Open l

1 j l l l 1 l l 1

Attcchm:nts R;v. 1/ Unit 2 PCga 5 of 5 ATTACHMENT (2) ( l MAS VER.IFICAT!oH CHE_CKLLST ,. IC18, IC19, IC20

a. 11 Diesel Generator ..................................... Running
b. 12 Diesel Generator ..................................... Running l
c. 21 Diesel Generator ..................................... Running JC34
a. 21 Containment Purge Exhaust Fan ........................ Off t

i b. 21 Containemnt Purge Supply Fan ......................... Off \ . l 2C90 (45 ft S/G B/D Sample Panel)

a. Press'arizer Vapor Sample Valve, 2-PS-5465-CV ............ Shut l

l l b. Pressurizer Liquid Sample Valve, 2-PS-5466-CV ........... Shut I c. RCS Hot Leg Sample Valve, 2-PS-5467-CV .................. Shut IC102 (45 ft Solid Waste)

a. Quench Tank 0 2 Sample Valve, 2-PS-6531-SV ............... Shut l

l l l l l l l l l

Attcchm:nto R;v. 1/ Unit 2 PCg] 1 Cf 1 j ATTACHMENT (3) ( ) C_SAS VERIFICATION CIIECELIJ2T , 2C03

a. 21 and 22 Main Steam Isolation Valves:

2-MS-4043-CV 2-MS-4040-CV ............................................ Shut *

b. 21 and 22 S/G Feedwater Isolation Valves:

2-FW-4516-MOV 2-FW-4517-MOV ........................................... Shut *

c. 21 and 22 S/C Feed Pumps ................................ Tripped
d. 21 and 22 Heater Drain Pumps ..........,.................. Off
e. 21, 22, and 23 Condensate Booster Pumps ................. Off 2 C 0 8 ,__2_Q_0 9 , 2_p10 a, 21 and 22 Containment Spray Pumps ....................... Running
b. 4 Containment Air Cooler 8 Inch Outlet Valves:

2+SRW-1582-CV 2-SRH-1585-CV 2-SRW-1590-CV 2-5RW-1593-CV ........................................... Open

c. 11, 22, 23, and 24 Containment Air Coolers ...... Running in low 1C13
a. 12 SFP Cooler Service Water Isolation Valves:

2-SRW-1598-CV 2-FRW-1599-CV ........................................... Shut HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET OF CSAS CAN BE ACCOMPLISHED FROM THE CONTROL ROOM. I I

AttCchm:nto rov. 1/ Unit 2 Pcg3 1 of 1 ATTACHMENT (4) CIS _VERIFIQEQ}L CIIECKId_S_T ., 2009, 2C10

a. 21, 22, and 23 Iodino Filter Fans ....................... Running
b. Il and 22 Penetration Room Vent Fans .................... Running
c. 21 and 22 Penetration Room Vent Filters Isolation Dampers Open
d. Component Cooling Containment Isolation Valves:

2-CC-3832-CV 2-CC-3833-CV ............................................ Shut *

e. Containment Instrument Air Isolation MOV, 2-IA-2080-MOV . Shut *
f. Instrument Air CIS override, 2-HS-2080$ ................. Normal
  • 2C12
a. Component Cooling Supply To Liquid Waste Evaporator Iselation Valves:

l l 2-CC-3840-CV 2-CC-3842-CV ............................................ Shut e \ HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET l OF CIS CAN BE ACCOMPLISHED FROM THE CONTROL ROOM. l

Attcchm:nto R:v. 1/ Unit 2 Pcg3 1 of 1 ATTACIIMENT (5) ( ) C_RS VERIFICA'UON CIIECELLST 2C10

a. 2 Cntmt Purge Supply Valves:

2-CPA-1410-CV 

        ?.-CPA-1411-CV ...........................................        Shut *
b. 2 Cntmt Purge Exhaust Valves:

2-CPA-1412-CV 2-CPA-1413-CV ........................................... Shut *

c. 2 Hydrogen Purge Cntmt Isolation Valves.

2-HP-6900-MOV . 2-HP-6901-MOV ........................................... Shut

  • 1C33
a. 21 Containment Purge Exhaust Fan .........................

Off I I b. 21 Containment Purge Supply Fan .......................... Off HANDSWITCil MUST BE PLACED !!i POST-ACCIDEliT POS!TIO!i BEFORE RESET OF CRS Call BE ACCOMPLISHED FROM THE CONTROL ROOM. l I

Att chm:nto R v. 1/ Unit 2 l PCgo 1 Cf 1 ATTACIDENT (6) ( > BA.S VERLFI_ CATION _ CITEC_KIdST 1909, 2009, 3010

c. 21 and 22 LPSI Pumps .................................... Off

! b. SI Pump Mini Flow Isolation Valves: l 2-SI-659-MOV l 2-SI-660-MOV ............................................ Shut t

c. Containment Sump Discharge Valves:

2-SI-4144-MOV 2-SI-4145-MOV ........................................... Open l 2C2.4b I

a. 21 Component Cooling HX Saltwater Inlet Valve, 2-SW-5160-CV ............................................ Open i b. 21 Component Cooling RX Saltwater Outlet Valve, 2-SW-5206-CV ............................................ Auto I c. 22 Component Cooling RX Saltwater Inlet Valve, l 2-SW-5162-CV ............................................ Open
d. 22 Component Ceoling HX Saltwater Outlet Valves:

1 2-SW-5208-CV 2-SW-5163-CV . ......................................... Auto 1

e. 21 SRW HX Saltwater outlet Valve, 2-SW-5210-CV .......... Auto j f. 22 SRW RX Saltwater outlet Valve, 2-SW-5212-CV .......... Auto l

l l 1 l l I l

Att: chm:nts R:v. 1/ Unit 2 Pcg3 1 of 1 ATTACIDENT (7) ( l EGl1LyERLFICATJOJLCIIECKIdST C ., 1901

a. 21 and 22 Main Steam Isolation Valves:

2-MS-4043-CV 2-MS-4048-CV ............................................ Shut *

b. 21 and 22 S/0 Feedwater Isolation Valves:

2-FW-4516-MOV 2-FW-4517-MOV ........................................... Shut *

c. 21 and 22 S/G Feed Pumps ................................ Tripped
d. 21 and 22 Heater Drain Pumps ..........,.................. Off ,
e. 21, 22, and 23 Condensate Booster Pumps ................. Off HANDSWITCH MUST BE PLACED IN POST-ACCIDENT POSITION BEFORE RESET OF I I SGIS CAN BE ACCOMPLISHED FROM THE CONTROL ROOM.

AttCerun:nto Rov. 1qJnit 

                                                                                               /        2 Pcg] 1 cf 2 ATTACIDEET (8)

( I WIDE RANGE STEAM GENERAER II. VEL TABII. FOR VARIABif, STEAM GENERATUR ERESSURES & VARI ABII. CONTAINMENT TT.MPERATURES INDICATED LEVEL FOR INDICATED LEVEL FOR INDICATED LEVEL FOR AMBIENT Cp AMBIEh7 CNDfT AMBIENT Cp TEMP 300 F TEMP 120 F TEMP 200 F S/G PRESSURE S/G PRESSURE S/G PRESSUKE ACTUAL (PSIA) (PSIA) (PSIA) 900 500 100 900 500 100 900 500 100 LEVEL 

    -400        -400         401  -401         -386      -387       -398       353        361    -369 s
    -390        -390         335  -400         -371      -376       -386    -344       -350      -357
    -380        -380         383  -388            361    -366       -373    -334       -340      -345
    -370        -370       -372   -376         -351      -355       -361    -324          329      333
    -360        -360       -361   -364            341    -344       -349    -314       -318      -320
    -350        -350         350  -351         -331      -333       -337    -304       -307      -308

{ } 

    -340         -340        340     339       -321      -323       -324    -294       -296        296
    -330         -330      -329   -327         -311      -312       -312       284     -285  283
    -320           320     -318   -315         -300      -301       -300    -274       -275      -271
    -310           310       308  -302         -290       -290      -287       265      -263       259
    -300           300       297  -291          -280      -280      -275    -255        -253       247 290          290       286     278          273       269     -262    -245        -242       234 280          280       275   -266         -264      -258       -250    -235       -231       222
     -270        -270        265   -253         -258      -247       -238       225       220      210 260        -26J       -254   -242         -244      -237       -226       215       210      197
     +250           250       243    230        -234        226      -214       201     -199      -185
     -240           240     -233   -216         -224      -215       -201       195     -188      -173    !

230 -230 222 -204 214 204 189 185 -177 161 j 

     -220         -220        211  -192         -204      -194       -176    -176       -166      -148    l
     -210         -210        200  -180         -194        183      -164    -166          156    -136    i
     -200         -200      -190   -168          -184      -172      -151       156        145    -124
     -190         -190      -179   -155          -1 +      -160       -139      146      -134       111 l

180 180 -168 143 -164 15 0 -127 -136 -123 99 { l 

     -170         -170      -157    -132         -154      -1'39      -115      126      -112       87 l

AttCerun:nts R;v. 1/1Jnit 2 Pego 2 of 2 ATTACHMTXT (8) ( ) WIDE RANGE FITAM GENERATUR IIVEL TABIE. FOR VARIABIE 677.AM GENERATUR TRESSURES & _YARIJBJEMA1NMFXT TT.MU.,RATURES (cont'd) Ih'DICATED IIVEL FOR Ih'DICATED LEVEL FOR Ih'DICATED LEVEL FOR AMBIEhT CN*nff AMBIENT Ch*IHT AMBIENT Ch'nff TEMP 120 F ."EMP 200 F TIMP 300 F S/G PRESSURE S/G PRESSURE S/G PRESSURE ACTUAL (PSIA) (PSIA) (PSIA) 900 500 100 900 500 100 900 500 100 LEVEL 160 160 -146 -119 -144 -129,, -103 -114 -101 -75 

      -150       -150        -135    -107        -134      -118      91   -106      -91    -62
      -140        -140       -124    -95         -125      -107    -79    -97       -80      50 130        -130       -114      83          115       92      66     87      -69    -38
      -120        -120       -103      70          105       86      54   -77       -58    -25
      -110        -110          92   -58         -95       -75       42   -67       -47    -13

( ) 

      -100        -100          81     46          86        64    -30    -57       -37      1 90         -90         -70    -33         -76       -53     -18      47      -26    +12 80           80        -59      21          66       -43    -6       37      -15    +24
      -70         -70           49   -9          -76        -32    +7       27        4    +36 60           60          38   +3            46        21    +19      18      +7     448
      -50         -50         -27    +15           36       -11    +31      8       +18    +61 40          40        -16    +28           26         0    +44     +2       +28    +63.5 30         -30        -5     +41          -16       +11    +56     +12       +39   +63.5 20           20       +6     +53          -7        +22    +63.5   +22       +50   +63.5 10         -10        +16     +63.5       +3        +32    +63.5   +32       +61   +63.5 0            0        +27     +63.5       +13       +43    +63.5   +42       463.5  +63.5 10         +10        +38     +63.5       +23       +54    +63.5   +52       +63.5  +63.5 20         +20        +49     +63.5       +33       +63.5   463.5  +62       +63.5  +63.5 30         +30        +60     +63.5       +43       + 61 5  +63.5  +63.5     +63.5  +63.5  j 40         +40         +63.5  +63.5       +53       +63.5   +63.5  +63.5     +63.5  +63.5
                                                                                                   ]

50 +50 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5 l 60 +60 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5 +63.5 { } l 1 l j

Attectun nta Rov. 1/Th11t 2 Pcga 1 of 1 ATTACHMEhT (9) - I k PRESSURIZER MVEL TABM FOR VARIABLE PRESSURIZER PRESSURES & VARIABM CONTAINNENT 'IIMPERATURES INDICATED LEVEL FOR INDICATED LEVEL FOR INDICATED LEVEL FOR AMBIERT CRTMT AMBIERT CNTtfT AMBIE'TT CNTMT TEMP 120 F TEMP 200 F TEMP 250 F 

                                                                                            ~

PRESSURIZER PRESSURE PRESSU21ZER PRESSURE PRESSURIZER PRESSURE ACTUAL (PSIA) (PSIA) (PSIA) LEVEL 300 1C'^ 2250 300 1000 2250 300 1000 2250 50 25 29 50 39 44 ,, 68 53 57 82 75 65 61 75 84 80 94 99 95 109 100 107 96 100 128 116 119 140 128 134 

     ~ 125        149     131     125        167     152      143     183      167    159 150     191     167     15n        211     188      168     228      201    183 175    236      205     175        248     222      192     270      237    208 I k 200    278      240     200        2?4     259      216     310      274    233 25E~   362      308     250        370     332      267     370      344    274 300     370     370     300        370     370      318     370      370    334 350     370     370     350        370     370      368     370      370    370 310     370     370     370        370     370      370     370      370    370 I

l i l l l l l l J

Attcchm:nto R3v. 1/ Unit 2 Pcg; 1 of 1 ATTACHMENT (10) PROCEDURE TO READ Thot ON SUBCOOLED MARGIN MONITOR

1. a) If in_ Press Mode: Lepress control switch 3 times within 3 seconds.

This will illuminate temperature and start testing sequence. When the unit is in the test mode, the decimal ir.dicator furthest to the right flashes every 1/2 second, b) If in Temperature Moder Depress' control switch 4 times within 3 seconds. This will start testing sequence. When the Unit is in the test mode, the decimal indicator furthest to the right flashes every 1/2 second.

2. Test #0 has started (number sequencing - fast speed). To advance the Test #, depress the control switch. This will illuminate PRESS and the display will count from 1 to 16 (in slow speed). When number "5" is displayed, depress the control switch. This will illuminate TEMP and indicate Thot on the display. Thot will be displayed for a maximum of 20 minutes at which point it automatically returns to normal operation (Press Margin Display). To return to normal operation prior to this 1

20 minute delay, depress the control switch. This will l l illuminate PRESS, count to 16, and automatically return to 1 pressure mar,in display. To read temp margin, depress the l q g control switch once to illuminate TEMP. 1 l l

MAKEUP WATER REQUIRED FOR RCS C00LDOWN MAKEUP REQUIRED VS. TIME UNTIL RCS COOLDOWN IS COMMENCED CCOM CR 88-1137 ( 1 FT. = 9636.78 CAL. ) 600 340 g. . . . . . . . . . . . . . . .- . . 

                                                                                                                                                                                                        /

a 660 m 330 o 640 h 320 7 - E 620 0 3IB  ! / ta. < 600 < 300

/  :
                                                                                                                                                                                                             ~

M f ~ sB0 290 -t -- 7 s se0 > 2.  : - - g E - 540 E 9m a 270 !  ! s- o  : /  : a g ]ys20 ,,y260  ; 

                                                                                                                                            /                                                                ;

g x 500 $ x 250 f. / i  ! hh400 h240 f 

                                                                                                                           /
                                                                                                                                   /                                     -!'

s d 460 5 d 230 

                   =

<n gv 440 

          *n- 220  -
                                                                                                          /                                                                                                  i g    40 ;      zie ;

7  ; 

    '" B      200 ;                                                                      '

g 7  ; E I" [ / [ I 360 I 180 ; 7 

                                                                                                                                                                                                              ;                >gg j    340   [   170 [                                                                                                                                                                                           [                te (9
                                                                                                                                                                                                                               ~

R 320 0 160 5 ' s 3,g 33e E. / . . . . . . . . . . . . . . . . . . . . . .:  ?!= 

                                                                                                                                                                                                                               -Hm 0                                                2          4           6              8                        10       12         14         16       18            20         22        24 u

HOURS REMAltilttG Ut1TIL COOLDOWN HUST BE COMMENCED e _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _____m- _ _ _ _ _ _ . - - __ __ __ - - __ __ _ __

O O O HIGH PRESSURE SAFETY INJECTION FLOW RCS PRESSURE VS. row i 

                                                ' ,                                                                         i        MINI kM FLOW REQUIREb -

3g s "%  % FOR CORE COOLING - h N 2 ti 

                                                                                                     \ rs]' UAINS {
                                                                        \                                                                HOURS                  _

after LOCA FLC GPM)_ 1000 - 

                                                                                                                                           ?.          396 1 ItrSt U AIN
                                                                                                                      \

3 361 [ 

                                    ~

i T T 4 333 0 \ \ 8 277 E 

                                    ~

800 ' 12 250 h g 

                                             -                                                                                                                   ~

24 207 u, , , x 

                                              ~
                                    . ooo                                                            .                                     -

m s a e 4oo vi c - 200 5 _ -i - N 3-a ' ' o aoo 4oo 800 ooo iooo iaoo 14o0 isoo 

                                                                                                          -1n. -                                                                                                                                                                                                                                 _

__-___m.__ __ _______._________m_ _ _ _ ___ _ _ - -

p - s LOW PRESSURE SAFETY INJECTION FLOW RCS PRESSURE VS. FLOW 200 , ji l . l . in ^ 

                                                                                        %   m N

150 . m. . N - q .  % -

U - h g -

G ! S 120 , S , i 100 b - en l N h ) 8 C ! 80 - 1 40 . 20 , 

                                                                ,                                              i n
                                                                                                                                            -       Rhb m-0 l                                                            0  500   1000 1500            2000       2500   T,000     3500         4000    4500 LPSI FLOW (GPM)
  • w

_ _ . _ _ _ _ _ _ . _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _}}

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