ML072960570

8.1.1 JPM 115*2AP

Respond To ERCW Pump Trip per AOP-M.01

PREPAREDI

REVISED BY:

VALIDATED BY:

APPROVED BY:

CONCURRED:

(Operations Training Manager)

(Operations Representative)

Date!

Validat ion not required for minor enhancements, procedure Rev changes that do

not affect the JPM , or individual step changes that do not affect the flow of the JPM.

.. Operations Concurrence required for new JPMs and changes that affect the flow

of the JPM (if not driven by a procedure revision).

(

JPM B.1.f

Page 2 of 13

Rev. 2

NUCLEAR TRAINING

REVISION /USAGE LOG

Revision

Description

Pages

Prepared/

Number

Of Revision

V

Date

Affected

Revised By :

0

New JPM for NRC Exam. Update for procedure rev. And

V

12/4/01

all

L. Pauley

reorder JPM step 8 and console operator action.

1

Updated to current revision and IC. Rewrote to include

Y

8/1 6/04

All

MG Croteau

returning to section 2.1 after header break isolated.

Extensive rewrite. Needs full validation run includina time.

I

2

Removed AOP-M.03 evaluation, Steps 26-33. Updated

N

2/5/07

All

RH Evans

to.current procedure revision. Minor Format chances

-

I

,

-

- --

. -----

- ---

-

I

i

-

I

--

-

- -

-

I

._..-

I

-

.-

i

_.-

I

-

,

---

I

-

I

._- -

I

.

I

-

!

I

V - Specify if the JPM change will require another validation (Y or N).

See cover sheet for criteria.

JPM B.l.I

Page 3 of 13

Rev. 2

(

SEQUOYAH NUCLEAR PLANT

ROISRO

Task:

Respond to ERCW Pump Trip

Note: This JPM satisfies Simulator Manipulation "L".

JAITA task # : 0000620501

(RO)

KIA Ratings:

076A2 .01

076A4 .01

076K6.04

(3.5/3.7)

(2.9/2.9)

(2.1/2.2)

076K4.06

076A2.02

(2.8/3.2)

(2.7/3.1)

Task Standard:

STANDBY A TRAIN ERCW Pump has been started and the auto start selection switch is selected away from

Q-A ERCW Pump position. ERCW Header leak has been isolated.

ln-Plant

_

x

Eva luation Method :

Simulator _

....!:>.__

======================================================================

Performer:

NAME

Start Time

(

Performance Rating : SAT

UNSAT

Performance Time

Finish Time

Eva luator:

/

SIGNATURE

DATE

===============================================================

COMMENTS

c

JPM B.1.f

Page 4 of 13

Rev. 2

SPECIAL INSTRUCTIONS TO EVALUATOR:

1.

Critical steps are identified within the step

2.

Sequenced steps identified by an "s"

3.

Any UNSAT requires comments

4.

Initialize the simulator in IC #16. Ensure a-A ERCW pump is in service and the selector switch is selected for

a -A. Ensure 1B-B CCP is running and 1A-A is in standby.

5.

Activate MF #RW01G (Trips a -A ERCW Pump)

6.

Freeze the simulator until the operator has been briefed and is ready to perform task.

7.

Console operator must insert malfunction RW13B at 90% prior to JPM step 8.

8.

See specific JPM steps for required remote function manipulations.

g.

Ensure operator performs the following required actions for SELF-CHECKING ;

a.

Identifies the correct unit, train, component. etc.

b.

Reviews the intended action and expected response.

c.

Compares the actual response to the expected response.

Validatio n Time: CR. 30 mins

Local

_

Tools/Equipment/Procedures Needed:

AOP-M.01, Section 2 and 2.1, 2.10

References:

Reference

Loss of ERCW

Title

Rev No.

15

(

===============================================================

READ TO OPERATOR

Direction s to Trainee :

I will explain the Initial conditions, and state the task to be performed. All control room steps shall be

performed for this JPM. I will provide initiating cues and reports on other actions when directed by you. When

you complete the task successfully, the objective for this job performance measure will be satisfied. Ensure

you indicate to me when you understand your assigned task. To indicate that you have completed your

assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

Unit is in mode 1 at 100% power

INITIATING CUES:

You are the e RO and are to monitor the board and respond, as a reader/doer. to any event that may occur.

Inform SM when any required action(s) associated with the failure have been completed.

Job Performance Checklist:

JPM B.l.I

Page 5 of 13

Rev. 2

(

Examiner NOTE:

STEP/STANDARD

Candidate may perform the ARP actions. They are identical to

procedure steps.

SATIUNSAT

_UNSAT

STEP 1.:

Obtain a copy of the appropriate procedure.

Start Time__

Cue:

The SM will evaluate Tech Specs, TRM, and the REP

STANDARD:

A copy of the AOP-M.01 has been obtained and goes to section 2.1 .

COMMENTS:

STEP 4.:

[3]

CHECK two A Train ERCW Pumps AVAILABLE.

STANDARD:

Operator verifies at least 2 A train ERCW pumps available

COMMENTS:

_SAT

UNSAT

(

Job Performance Checklist:

STEP/STANDARD

STEP 5.:

(4)

CHECK 1A and 2A ERCW supply header pressures and flows

NORMAL:

a.

Supply Header pressures [between 78 psig and 124 psig]:

1-PI-67*493A

2-PI-67*493A

JPM B.l.I

Page 6 of 13

Rev. 2

SAT/UNSAT

_

UNSAT

STANDARD:

COMMENTS:

Operator checks header pressures are between 78 and 124 psig on

both A Train indicators.

STEP 6,:

b.

Supply Header flows [expected value].

1-FI-67-61

2-FI-67-61

_

UNSAT

STANDARD:

COMMENTS:

Operator checks there is flow on the A train supply header as indicated

on both indicators.

(

Console operator insert malfunction RW13B at 90% prior to checking header flows.

STEP 7,:

(5)

CHECK 1B and 2B ERCW supply header pressures and flows

NORMAL:

a.

Supply Header pressures [between 78 psig and 124 psig]:

1-PI-67-488A

2-PI-67-488A

b.

Supply header flows [expected value]:

1-FI-67-62

2-FI-67-62

_

UNSAT

Cue:

STANDARD:

COMMENTS:

If asked, ERCW pipe break has occurred.

Operator checks header pressures are between 78 and 124 psig on

both B Train indicators. Flows are abnormal, transitions to section

2.10.

-..

EVAI.UATOR NOTE:

Tne followino steDsare from section 2.10:

)

\\

FROM

SEQL.X:YAH OPERATOR TRA I NING

Job Performance Cneckust:

PI-rnE NO* . : 423 843 4339

STEP/STANDARD

Apr . 04 2007 04 :22PM P6

JPM 6.1.f

Page 7 of 13

Rev. 2

SATIUNSAT

STEF~:

[1]

Stop and LOCK OUT All Train B ERCW Pumps

_SAT

C'!!<:

If asked, leak rate has slowect.

STNJDARD:

Operator places all running B train ERCW pumps in pun-to-lock

position, This step Is critical to prevent pumping water out the

break.

COMMENTS;

STEP~:

[2]

DISPATCH operators witn radios to perform tne fOllowing:

PERFORM Appendix F, ERCW Rx MOV Board ERCW Valves.

PERFORM Appendix G, ERCW MeC Valves.

ENSURE all pumping station watertlqht doons are CLOSED.

f!!!!:

Play role of AUO and acknowlectge the request.

STANDARD:

Operator dispatcnes operators to perform the required appendices and

actions. This step is critical to supply power to valves needed to

isolate the leak.

STEP 10.:

[3]

ENSURE 1A and 2A CCPs RUNNING.

Play role of /,/2 CRO and start2A CCP

_UNSAT

Critical Step

_SAT

_UNSAT

Critical Slep

_SAT

_UNSAT

Operator starts 1A*A charging pump. This step is critical to supply

RCP seals and normal charging from A train equipment.

Critical Step

(

- - - .

_ ~

Job Performance Checklist:

STEP/STANDARD

EVALUATOR NOTE:

The followino steos are from section 2.10:

STEP 8.:

(1)

Stop and LOCK OUT All Train B ERCW Pumps

JPM B.l.I

Page 7 of 13

Rev. 2

SAT/UNSAT

_

Cue:

If asked, leak rate has slowed.

STANDARD:

COMMENTS:

Operator places all running B train ERCW pumps in pull-to-lock

position. Th is step is critical to prevent pumping water out the

break.

_

UNSAT

Critical Step

(

STEP 9.:

[2]

DISPATCH operators with radios to perform the following:

PERFORM Appendix F, ERCW Rx MOV Board ERCW Valves.

PERFORM Appendix G, ERCW MCC Valves.

ENSURE all pumping station watertight doors are CLOSED.

Cue:

Play role of AUO and acknowledge the request.

STAND ARD:

Operator dispatches operators to perform the required appendices and

actions. This step is critical to supply power to valves needed to

isolate the leak.

NOTE :

Once Appendix G is complete, state that the leak is stopped.

COMMENTS:

STEP 10.:

(3)

ENSURE 1A and 2A CCPs RUNNING.

Cue:

Play role of U2 CRO and start 2A CCP

_SAT

UNSAT

Critical Step

UNSAT

STANDARD:

COMMENTS:

Operator starts 1A-A charging pump. This step is critical to supply

RCP seals and normal charging from A train equ ipment.

Critical Step

Job Performance Checklist:

STEP/STANDARD

JPMB.1.f

Page 8 of 13

Rev. 2

SAT/UNSAT

(

STEP 11.:

[4] STOP and LOCK OUT effected equipment:

-

a.

PLACE the following pumps in PULL TO LOCK:

-

UNSAT

1B CCP

2BCCP

1B SI Pump

Crit ical Step

2B5 1Pump

Cue:

Play role of U2 CRO and Stop/Lockout asso ciated pumps

STANDARD:

Operator secures the running pumps in the control room and dispatches

an AUO to lockout the B Aux Control Air Compressor. This step is

critical to prev ent start of ECCS equipment without cooling water

available to the room coolers.

COMMENTS:

STEP 12.:

b.

DISPATCH operator to place Train B Aux Air Compressor in

-

SAFE STOP.

-

UNSAT

-

Cue:

Play role of AUO and acknowledge the request.

STANDARD:

Operator secures the running pumps in the control room and dispatches

an AUO to lockout the B Aux Control Air Compressor

COMMENTS:

STEP 13.:

[5]

OPEN alternate ERCW supply to B train DGs:

-

1-FCV-67-65 (1B DG)

2-FCV-67-65 (2B DG)

-

UNSAT

Cue:

Play role of U2 CRO/AUO and acknowledge the request.

STANDARD:

Operator opens 1-FCV-67-65 and directs opening of 2-FCV-67-65.

Critical Step

COMMENTS:

Job Performance Checklist:

STEPISTANDARD

EVALUATOR NOTE: RCP Temperature alarms may come in dependinq on pace.

STEP 14.:

[6] ISOLATE B Train ERCW Header rupture:

a. CLOSE 1-FCV-67-489, Header 1B Isol Before Strainer [ERCW

MCC 1BB Compl. 3C].

b. CLOSE 2-FCV-67-489, Header 2B Isol Before Strainer [ERCW

MCC 2BB Compl. 3C].

Cue:

Play role ofAUO and acknowledge the request.

STANDARD :

Operator notifies an AUO to close the valves to isoiate the B ERCW

header. This step is critical to isolate the ERCW leak.

COMMENTS:

Console Operator perform the following to isolate the leak:

MRF RWRV489

0%

MRF RWR2V489 0%

JPM B.1.f

Page 9 of 13

Rev. 2

SATIUNSAT

_

UNSAT

Critical Step

STEP 15.:

[7]

OPERATE available A Train ERCW Pumps to maintain pressure

between 78 psig and 124 psig.

(

STANDARD :

COMMENTS:

Operator will start an additional A train pump. This step is critical to

return ERCW supply header pressure to normal.

_SAT

_

UNSAT

Critical Step

Pressure is less than 78 psig, but procedure also allows reducing flow to non-essential

equipment to raise pressure.

,

FROM

SEQUCYAH OPERATOR TRAINI NG

Pl-rnE NO.

423 843 4339

Apr. 04 2007 04:22PM P7

(

\\. ,,-..,

(

Job Pe,10rmance Checkl ist:

STEP/STANDARD

EVAI.UATOR NOTE: RCP Temoerature alarms may come in deoendinc on oace.

~) 14.:

(6) ISOLATE B Train ERCW Header rupture:

a. CLOSE 1-FCV*67-489, Header 1B Isol Before Strainer [ERCW

MCC 1BB Compt, 3C].

b. CLOSE 2*FCV-67-489, Header 28 Isol Before Strainer [ERCW

MCC 288 Com pt. 3C).

9!J!:

Play role ofAUO and acknowledge the request.

Q!!!.:

Respond 1.FCV-67-489 & 2-FCV-B7-489 are closed, the leak;s

stopped.

No'rE:

Once Appendix G Is complete, state that the leak is stopped.

STAtIDARD:

Operator notifies an AUO to close the valves to isolate the B ERCW

header. This step is critical to isolate the ERCW leak.

COM ~ 'ENTS :

Console Operator perform the following to isolate lhe leak:

MRF 'lWRV489 0%

MRF 'lWR2V489 001o

STEP~ :

(7)

OPERATE available A Train ERCW Pumps to maintain pressure

between 78 psig and 124 psig.

Operator will start an additional A train pump. This step is critical to

relum ERCW supply header pressure to normal.

Pressure is less than 78 psig, but procedure also allows reducing flow to non-essential

equiprr ent to raise pressure.

JPM 8.1.f

Page 9 of 13

Rev. 2

SATIUNSAT

_SAT

_UNSAT

Critical Step

_SAT

_

UNSAT

Critical Step

(

Job Performance Checklist:

STEP/STANDARD

STEP 16.:

[8]

EVALUATE aligning Train A ERCW to supply Train B:

a.

IF aligning 1A to 26 header is desired, THEN

PERFORM the following:

I)

DISPATCH personnel to CLOSE 0-67-1501 CCS Htx OB2 Inlet

valve.

2)

WHEN 0-67-1501 CLOSED, THEN OPEN 1-FCV-67-147, Hdr

1A to Hdr 2B Isol Valve [Rx MOV Bd 1A2-A cl9A] AND

RECORD the time

3)

WHEN 1-FCV-67-147 has been OPEN for approximately 10

minutes, THEN OPEN 0-67-1501 CCS Htx 062 Inlet valve

JPM B.1.f

Page 10 of 13

Rev. 2

SAT/UNSAT

_SAT

_UNSAT

Critical Step

Cue:

STANDARD:

COMMENTS:

Direct operator to align 1A and 2A ERCW Supplies to Train B

Play role ofAVO and acknowledge the request. When 1-FCV-67-

147 has been directed opened, cue that 10 minutes have elapsed.

Operator dispatches an AUO to close 0-67-1501, open 1-FCV-67-147

and reopens 0-67-1501 after 1-FCV-67-147 has been open for -10

minutes. This step is critical to supply cooling water to A train

equipment.

(

Console Operator perform the following to open 1-FC

0-67-1501):

MRF RWRV489

100%

LetA-~ ~";

C'\\A '~~'

\\<-cJ""

\\"'\\?<'~

D~ ""S\\-('CM""'-~ .

STEP 17.:

b. IF aligning 2A to 1B header is desired, THEN PERFORM the

following:

OPEN 1-FCV-67-424, Hdr 1B to Hdr 2A CCS HX Isol Valve [Rx

MOV Bd 1A2-A Compl. 96] AND RECORD the Time

ENSURE 1-FCV-67-223, Hdr 1B to Hdr 2A Isol Valve is OPEN.

[Rx MOV Bd 1A2-A Compl. 8B].

ENSURE 2-FCV-67-223, Hdr 2A to Hdr 1B Isol Valve is OPEN.

[Rx MOV Bd 2A2-A Compl. 8B].

UNSAT

Critical Step

(

Cue:

Play role ofAVO and acknowledge the request.

STANDARD:

Operator dispatches an AUO to open 1-FCV-67-424, and ensures that

1-FCV-67-223 and 2-FCV-67-223 are open. This step is critical to

supply cooling water to A train equipment.

COMMENTS:

Console Operator perform the following to open 1-FCV-67-424 (1/2-FCV-67-223

are already open):

MRF RWRV424

100%

Job Performance Checklist:

JPM 8 .1.1

Page 11 of 13

Rev. 2

STEP/STANDARD

STEP 18.:

[9] START additional Lower Compartment Cooling Fans and CRDM Fans as

required to maintain containment temperature.

(

STANDARD:

NOTE:

COMMENTS:

Operator checks containment temperature and starts fans if needed.

Operator may start the 1C Lower Compartment Cooler.

SAT/UNSAT

_

_

UNSAT

STEP 19.: [10]

MONITOR Containment Pressure and Temperature.

STANDARD:

Operator monitors containment temperature and pressure.

COMMENTS:

STEP 20.:

[11] CHECK 1A and 2A ERCW header pressures and flows adequate for

current alignment:

1-1'1-67-61 and 2-FI-67-61, at expected value

1-PI-67-493 and 2-PI-67-493

_

_

UNSAT

UNSAT

(

STANDARD:

COMMENTS:

Operator checks above indicators and observes parameters are normal.

If not starts additional A train ERCW pumps (see JPM step 15).

STEP 21.:

[12] RESTORE equipment:

_SAT

a.

b.

CHECK Train 8 ERCW header supplied from Train A crosstie.

RESTORE the following hand switches as applicable:

18-8 CCP to A-AUTO

18-8 SI Pump to A-AUTO

28-8 CCP to A*AUTO

28-8 SI Pump to A-AUTO

UNSAT

Critical Step

Cue:

Play role ofAUO and acknowledge the request.

STANDARD:

Operator restores 8 Train components to service. This step is critical

to restore 8 train ECCS equipment.

COMMENTS:

STEP 22.:

[13]

EVALUATE isolation of non-essential A Train CCS heat loads USING

-

Appendix E, CCS Heat Load Reduction.

-

UNSAT

Cue:

SM will perform the evaluation

STANDARD:

Operator ensures Appendix E evaluated.

COMMENTS:

STEP 23.:

[14] ENSURE all ACBs opened USING the following appendixes:

-

Appendi x F, ERCW Rx MOV Board Appendix R Valves

-

UNSAT

Appendix G, ERCW MCC Appendix R Valves

Cue:

Play role of AUO and acknowledge the request.

STANDARD:

Operator dispatches an AUO to perform the appendices.

COMMENTS:

~

STEP 24.:

[15]

REFER to the following:

-

Appendix B, Affected Equipment List (Header 1B)

-

UNSAT

Appendix D, Affected Equipment List (Header 2B)

Appendix P, Potential Tech Spec Impacts

Cue:

SM will refer to the Appendices.

STANDARD :

Operator ensures Appendix B referred to.

COMMENTS:

STEP 25.:

[16)

REFER TO AOP-M.03, Loss of Component Cooling Water.

-

Cue:

Another operator will evaluate to AOP-M.03.

-

UNSAT

STANDARD :

Operator ensures AOP-M.03 referred to.

COMMENTS:

Stop Time__

(

Job Performance Checklist:

STEPISTANDARD

End of JPM

JPM B.1.f

Page 12 of 13

Rev. 2

SAT/UNSAT

(

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control

room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you.

Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task return the handout sheet I provided

you.

INITIAL CONDITIONS:

Unit is in mode 1 at 100% power

INITIATING CUES:

You are the C-RO and are to monitor the board and respond, as a reader/doer, to any

event that may occur.

Inform SM when any required action(s) associated with the failure have been

completed

TENNESSEE VALLEY AUTHORITY

SEQUOYAH NUCLEAR PLANT

AOI PROGRAM MANUAL

ABNORMAL OPERATING PROCEDURES

LOSS OF ESSENTIAL RAW COOLING WATER

Revision 15

QUALITY RELATED

D. A. PORTER

W T. LEARY

OPERATIONS

APPROVED BY:

-'-'--'-'=-~'_'_'_

_

RESPONSIBLE ORGAN IZATION: _""""--'=-'-'-'-'-'-'-""-'--'<-

_

(

EFFECTIVE DATE: 07/21106

REVISION

DESCRIPTION:

Incorporated various enhancements to Sect. 2.11 based upon feedback

from REP drill (PER 97828, NB-060173, NB-060178). Relocated

caution, notes, and administrative actions from Section 2.0.

Incorporated other enhancements and minor corrections.

INTENT CHANGES TO SECTION 2.11 OF THIS PROCEDURE

MUST BE APPROVED BY PORCo

(

SON

1.0

PURPOSE

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

(

This procedure provides the actions necessary to mitigate the effects of an ERCW pump or

piping failure.

.

Page 2 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.0

OPERATOR ACT IONS

RESPONSE NOT OBTAINED

CAUTION:

ERCW header rupture in Auxiliary Building could fill the passive sump

in 15 minutes. Prompt action is needed.

(

1.

DIAGNOSE the failure:

IF...

GO TO SECTION

PAGE

ERCW Pump(s) tripped or failed

2.1

ERCW pump failure

5

High flow ERCW Supply Header 1A

2.2

Supply Hdr 1A Failure

8

to Aux Bldg

High flow ERC W Supply Header 18

2.3

Supply Hdr 1B Failure

12

to Aux Bldg

High flow ERCW Supply Header 2A

2.4

Supply Hdr 2A Failure

16

to Aux Bldg

High flow ERCW Supply Header 28

2.5

Supply Hdr 2B Failure

22

to Aux Bldg

Indications of an ERCW Return Header rupture

2.6

Return Hdrrupture

27

(must be diagnosed locally since M-27 indications

in Aux Bldg

are not affected)

Low flow ERCW Supply Header 1A and 2A,

2.7

SupplyHeader 1AJ2A

38

AND

Failurein Yard Area

STRAINER OIFF PRESS HIGH alarm LIT

[M-27A, C-3 and/or 0 -2]

Low flow ERCW Supply Header 18 and 2B,

2.8

Supply Header 18/28

52

AND

Failure in YardArea

STRAINER OIFF PRESS HIGH alarm LIT

[M-27A, C-6 and/or 0 -5]

(step continued on next page)

Page 3 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.0

OPERATOR ACTIONS (Continued)

3.

(Continued)

RESPONSE NOT OBTAINED

(

IF...

GO TO SECTION

PAGE

Low flow ERCW supply headers 1A and 2A.

AND

STRAINER DIFF PRESS alarms DARK

[M-27A, C-3 and D-2],

AND

at least one of the following alarms LIT:

ERCW DECK SUMP LEVEL HI alarm LIT

2.9

Supply Header A

63

[1-M-15B, A-3]

Failure Upstream of

Strainer InletValves

-

ERCW DECK SUMP PMP RUNNING

[1-M-15B, D-2 or D-4]

MECH EQUIP SUMP LVL HI alarm LIT

[1-M-15A, B-6]

Low flow ERCW supply headers 1Band 2B,

AND

STRAINER DIFF PRESS alarms DARK [M-27A,

C-6 and D-5],

AND

at least one of the following alarms LIT:

ERCW DECK SUMP LEVEL HI alarm LIT [1-

2.10

Supply Header B

71

Failure Upstream of

M-15B , A-3]

Strainer Inlet Valves

ERCW DECK SUMP PMP RUNNING [l -M-

15B, D-2 or D-4]

MECH EQUIP SUMP LVL HI alarm LIT [l -M-

15A, B-6]

Loss of flow on ALL ERCW supply headers

2.11

Loss of all ERCW flow

77

in modes 1-4.

END OF SECTION

Page 4 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

(

I STEP I

ACTION/EXPECTED RESPONSE

2.1

ERCW Pump Failure

1.

IDENTIFY and LOCK OUT failed ERCW

pump.

2.

START additional ERCW pumps

as required to maintain supply header

pressure between 78 psig and 124 psig.

3.

CHECK two Train A ERCW Pumps

AVAILABLE,-

4.

CHECK 1A and 2A ERCW supply

header pressures and flows NORMAL:

a.

Supply header pressures

[between 78 psig and 124 psig]:

1-PI-67-493A

2-PI-67-493A

b.

Supply header flows

[expected value]:

1-FI-67-61

2-FI-67-61

RESPONSE NOT OBTAINED

IF less than two Train A ERCW Pumps

available,

THEN

EVALUATE isolation of non-essential Train A

CCS heat loads USING Appendix E, ecs

Heat Load Reduction [C.1]

IF BOTH 1A AND 2A ERCW Headers

FAILED,

THEN

GO TO Section 2.9, ERCW Supply

Header A Failure Prior to ERCW

Strainer Inlet Valves.

IF 1A OR 2A ERCW Header FAILED,

THEN

RETURN TO Section 2.0 for diagnosis.

-_...~

Page 5 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

(

STEP I

ACTION/EXPECTED RESPONSE

2.1

ERCW Pump Failure (cont'd)

5.

CHECK 1Band 2B ERCW supply header

pressures and flows NORMAL:

a.

Supply header pressures [between

78 psig and 124 psig]:

1*PI-67-488A

2*PI-67-488A

b.

Supply header flows [expected value]:

1*FI-67-62

2-FI-67-62

6.

DISPATCH personnel to INSPECT

failed pump(s) and determine cause

for failure.

7.

NOTIFY STA to evaluate Tech Spec

LCO 3.7.4, ERCW System.

8.

CHECK ERCW pump loading amps

NORMAL.

RESPONSE NOT OBTAINED

IF BOTH 1B AND 2B ERCW Headers

FAILED,

THEN

GO TO Section 2.10, ERCW Supply

Header B Failure Prior to ERCW

Strainer Inlet Valves.

IF 1B OR 2B ERCW Header FAILED,

THEN

RETURN TO Section 2.0 for diagnosis.

INVESTIGATE abnormal amp readings:

CHECK header flows and pressures.

IF amps are high due to only one pump

available,

THEN

EVALUATE isolation of non-essential ERCW

loads.

Page 6 of 142

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LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

(

I STEP I

ACTION/EXPECTED RESPONSE

2.1

ERCW Pump Failure (cont'd)

9.

TRANSFER emergency power selector

switch away from failed pump.

10.

EVALUATE need to close and place

clearance on manual discharge valve

for failed pump.

11.

GO TO appropriate plant procedure.

--~.--

RESPONSE NOT OBTAINED

END OF SECTION

Pag e 7 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.2

ERCW Supply Header 1A Failure to Auxiliary Building

CAUTION:

During operation, CCP and SI Pumps may experience bearing fail ure

10 minutes after a loss of ERCW cooling.

1.

DISPATCH personnel 10 locate rupture.

2.

DISPATCH operators with radios to perform

Appendix F, Rx MOV Bd ERCW Valves.

[Aux Bldg, 749' elev, Rx MOV Boards].

3.

ENSURE 1B-B CCP is running.

4.

STOP and LOCK OUT the following:

1A-ACCP

1A-A SI Pump

5.

DISPATCH operato r to place

Aux Air Compressor A-A in SAFE-STOP.

[AB el. 734', Refuel Floor]

6.

START additional Lower Compartment

Cooling Fans and CRDM Fans as required

to maintain containment temperature.

Page 8 of 142

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LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.2

ERCW Supply Header 1A Failure to Auxiliary Building (cont'd)

NOTE:

This section isolates ruptures in the Auxiliary Building downstream of 1-FCV-67-81 .

A rupture in the AB pipe tunnel upstream of 1-FCV-67-81 and downstream of the

flow elements is isolated using Section 2.7 (Train A) for yard area breaks.

c

7.

NOTIFY local operator to CLOSE

1-FCV-67-81, Aux Bldg Hdr 1A lsol Valve

[Rx MOV Bd 1A2-A Compt 3C]

8.

CHECK rupture ISOLATED.

9.

NOTIFY locai operator to CLOSE

the following valves:

1-FCV-67-147 , Hdr 1A to Hdr 28 lsol

Valve [Rx MOV Bd 1A2-A Cornpt. 9A]

1-FCV-67-127 , Hdr 1A Supply to Space

Coolers, N C, & Air Compressors

[Rx MOV Bd 1A2-A Cornpt, 7A]

10.

ENSURE the following valves are

CLOSED:

1-FCV-67-125, Containment Spray

HX 1A ERCW Supply [O-M-27A]

1-FCV-67-99, Lower Compt Cooier

1C Supply lsol [O-M-27A]

1-FCV-67-107, Lower Compt Cooler

1A Supply lsol [O-M-27A]

IF rupture is upstream of 1-FCV-67-81 ,

THEN

GO TO Section 2.7.

--~.--

Page 9 of 142

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LOSS OF ESSENTIAL RAW COOLING WAT ER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.2

ERCW Supply Heade r 1A Failure to Auxiliary Building (cont'd)

11.

DISPATCH an operator to CLOSE the

following valves:

1-67-524A. Supply Hdr 1A to Inst Room

Coole r 1A [el. 669' Penetration Room,

above 1B-B Disch Ductwork]

1-67-521 A. Hypochlorite Treatment

Circulation Line Isolation

[elev 669' TDAFWP Rm N Wall near AFW

1-FCV-3-136A]

1-67-675,-ERCW Isol to A Shutdown

Board Room AlC Water Chiller

[elev 714' near AFW LCV 1-LCV-3-148]

12.

OPERATE ERCW Pumps as necessary

to perform the following:

CONTROL pressure between 78 psig

and 124 psig.

MAINTAIN support of system loads.

13.

REFER TO the following:

Appendix A, Affected Equipment List

(Header 1A)

Appendix P, Potentia l Tech Spec

Impacts.

Page 10 of 142

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LOSS OF ESS ENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.2

ERCW Supply Header 1A Failure to Auxiliary BUilding (cont'd)

14.

ENSURE all breakers reopened

USING Appendix F, Rx MOV Board

ERCW Valves.

15.

GO TO appropriate plant procedure.

--..--

END OF SECTION

Page 11 of 142

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LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.3

ERCW Supply Header 1B Failure to Auxiliary Building

CAUTION:

During operation, CCP and SI Pumps may experience bearing failure 10

minutes after loss of ERCW coo ling.

1.

DISPATCH personnel to locate failure.

2.

DISPATCH operators with radios to perform

Appendix F, Rx MOV Board ERCW Valves.

[Aux Bldg el. 749', Rx MOV Boards].

3.

ENSURE 1A-A CCP RUNNING.

4.

STOP and LOCK OUT the following:

1B-B 51 Pump

5.

START additional Lower Compartment Cooling

Fans and CRDM Fans as required to maintain

containment temperature.

Page 12 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.3

ERCW Supply Header 1B Failure to Auxiliary Building (cont'd)

NOTE:

This section isolates ruptures downstream of 1-FCV-67-82. A rupture in the

A8 pipe tunnel upstream of 1-FCV-67-82 and downstream of the flow elements is

isolated using Section 2.8for yard area breaks.

(

6.

NOTIFY local operator to CLOSE

1-FCV-67-82. Aux Bldg Hdr 1B Isol Valve

[Rx MOV 8d 1B2-B Compt 3C]

7.

CHECK rupture ISOLATED.

8.

NOTIFY local operator to CLOSE

the following valves:

1-FCV-67-424 , Hdr 18 to Hdr 2A

Isol Valve

[Rx MOV Bd 1A2-A Compt. 981

1-FCV-67-128, Hdr 18 Supply

to Space Coolers, AlC, & Air Compressors

[Rx MOV 8d 182-8 Compt. 6C]

9.

ENSURE the following valves CLOSED:

1-FCV-67-123, Containment Spray

HX 1B ERCW Supply [O-M-27Al

1-FCV-67-83, Lower Compt Cooler

1D Supply Isol [O-M-27A]

1-FCV-67-91, Lower Compt Cooler

18 Supply Isol [O-M-27Al

IF rupture is upstream of 1-FCV-67-82,

THEN

GO TO Section 2.8.

--~.--

Page 13 of 142

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LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.3

ERCW Supply Header 1B Failu re to Auxiliary Building (cont'd)

10.

DISPATCH an operator to CLOSE the

following valves:

1-67-524B, Supply Hdr 1B to Inst Room

Cooler 1B [AB, 669' elev. Penetration

Room, above 1B-B Disch Ductwork].

1-67-521B, Hypochlorite Treatment

Circulation Line Isolation

[elev 669' TDAFWP Rm North Wall]

11.

OPERATE ERCW Pumps as necessary

to perform the following:

CONTROL pressure between 78 psig

and 124 psig.

MAINTAIN support of system loads.

12.

REFER TO the following:

Appendix B, Affected Equipment List

(Header 1B)

Appendix P, Potential Tech Spec

Impacts.

Page 14 of 142

(,

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.3

ERCW Supply Header 1B Failure to Auxiliary BUilding (cont'd)

13.

ENSURE all breakers reopened

USINGAppendix F, Rx MOV Board

ERCW Valves.

14.

GO TO appropriate plant procedure.

---.--

END OF SECTION

Page 15 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.4

ERCW Supply Header 2A Failure to Auxiliary Building

CAUTIONS:

During operation, CCP and SI Pumps may experience bearing failure

10 minutes after loss of ERCW cooling.

Loss of 2A ERCW Supply Header affects both Units Train A CCS Heat

Exchangers. Isolation of ruptured header and restoration of ERCW to intact

CCS Heat Exchangers is time critical to prevent tripping both Units .

Isolation or realignment of 2A ERCW Header affects CCS cooling to RCPs.

1.

DISPATCH personnel to locate failure.

2.

ENSURE 2B-B CCP in service.

3.

STOP and LOCKOUT the following

pumps:

2A-A CCP

2A-A 51 Pump

4.

DISPATCH operators with radios

to perform Appendix F, Rx MOV Bd

ERCWValves. [Aux Bldg, el. 749',

Rx MOV Boards].

Page 16 of 142

(

saN

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.4

ERCW Supply Header 2A Failure to Auxiliary Building (cont'd)

5.

MONITOR the following on both Units:

REACTOR COOLANT PUMPS

MOTOR THRUST BEARING TEMP

HIGH [XA-55-5B, E-3] alarm DARK.

IF Thrust Bearing temperature

exceeds 200' F,

THEN

PERFORM the following:

a.

TRIP the affected Unit's Rx.

b.

STOP the affected Unit's RCPs.

c.

IF in Mode 1, 2, or 3,

THEN

GO TO E-O, Reactor Trip or Safety

Injection, WHILE continuing with this

procedure. [C.2]

---.--

IF in Mode 4 or 5,

THEN

STABILIZE RCS temperature

USING RHR shutdown cooling.

NOTE

The following step isolates the 2A ERCW supply to 1A1/1A2 CCS HX.

If rupture is NOT successfully isolated then step 7 RNO will cross-tie 1B and 2A

ERCW headers to supply the 1A1/1A2 CCS HX.

6.

NOTIFY local operator to CLOSE

2-FCV-67-22 3, Hdr 2A to Hdr 1B Isol

Valve. [Rx MOV Bd 2A2-A Compt. 8B)

Page 17 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

[ STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.4

ERCW Supply Header 2A Failure to Auxiliary Building (cont'd)

CAUTION

Opening crosstie valve 1-FCV-67-424 (in Step 7.RNO) may result in severe

fouling or flow blockage of 1A1I1A2 CCS Heat Exchanger. If plant con ditions

and time permits , CCS Hx 1A2 should be isolated prior to opening crosstie

valve. After approximately 10 minutes, 1A2 CCS Hx will be returned to service.

NOTE

When ERCW Headers are crosstied, the actions of LCO 3.0.3 are applicable.

Steps to record lime valve is opened should be used as aid for tracking LCO times.

(

7.

CHECK Supply Header 2A parameters

to determine if rupture is ISOLATED:

2-FI-67-61 at expected value

2-PI-67-493A between 78 psig and

124 psig -

PERFORM the following:

a.

IF CCS Hx 1A2 to be isolated prior to

opening crosstie valve,

THEN

PERFORM the following:

1) CLOSE 1-67-1501 CCS Hx 1A2

Inlet Iso1Vlv.

2) WHEN 1-67-1501 CLOSED,

THEN

OPEN 1-FCV-67-424, Hdr 1B to Hdr 2A

CCS HX Isol Valve. [Rx MOV Bd 1A2-A

Cornpt. 9B]

3) RECORD time

4) IF CCS Hx 1A1 indicates fouling or flow

blockage OR 1-FCV-67-424 has been

OPEN for approx. 10 minutes,

THEN

OPEN 1-67-1501 Inlet to 1A2 CCS Hx.

5) GO TO Substep c...

b.

OPEN 1-FCV-67-424, Hdr 1B to Hdr 2A

ecs HX Isol Valve

[Rx MOV Bd 1A2-A Compl. 9B].

RECORD time

(

(Step Continued on next page)

Page 18 of 142

(

-.

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.4

ERCW Supply Header 2A Failure to Au xiliary Building (cont'd)

7.

(Continued)

c.

TRIP Unit 2 Rx.

d.

STOP Unit 2 RCPs.

e.

IF Unit 2 was in Mode 1, 2, or 3,

THEN

GO TO E-O, Reactor Trip or Safety Injection,

WHILE continuing with this procedure. [C.2]

--~.--

f.

IF in Mode 4 or 5,

THEN

STABILIZE RCS temperature using RHR

shutdown cooling.

g.

CLOSE the following valves:

2-FCV-67-81 , Aux Bldg Hdr 2A 1501Valve.

[Rx MOV Bd 2A2-A Compl. 3C]

2-FCV-67-127, Hdr 2A Supply to Space

Coolers, AlC, & Air Compressors

[Rx MOV Bd 2A2-A Compl. 7A]

2-FCV-67-146, 2A-1/2A-2 CCS

HX Outlet 1501[O-M-27A]

2-FCV-67-125, Containment Spray

HX 2A ERCW Supply [O-M-27A]

2-FCV-67-99, Lower Compt

Cooler 2C Supply 1501 [O-M-27A]

2-FCV-67-107, Lower Compt

Cooler 2A Supply 1501[O-M-27A]

2-FCV-67-130, Upper Compt

Cooler 2A Supply Isol [O-M-27A]

2-FCV-67-133, Upper Compt

Cooler 2C Supply 1501 [O-M-27A]

(step continued on next page)

Pag e 19 of 142

(

'>"

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.4

ERCW Supply Header 2A Failure to Aux iliary Building (cont'd)

(

7.

(Continued)

8.

CLOSE 1-FCV-67-146, lAl/1A2 CCS HX

Outlet Isol.

9.

Unit 1 Only:

PERFORM the following:

a. TRIP Unit 1 reactor.

b. STOP Unit 1 RCPs.

c.

CHECK if in Mode 1, 2, or 3.

d. GO TO E-O, Reactor Trip or Safety

Injection, WHILE continuing in this

procedure. [C.2]

--..--

h.

DISPATCH an operator to CLOSE

the following valves:

2-67-524A, Supply Hdr 2A to Inst

Room Cooler 2A. [Aux Bldg

el. 669' Pen Rm, above Ductwork

by panel 2-L-329]

2-67-521A, Hypochlorite Treatment

Circulation Line Isolation

[el. 669' TDAFWP Rm by ERCW

supply valves]

i.

GO TO Step 10.

c.

STABILIZE RCS temperature

USING RHR shutdown cooling.

GO TO Step 10.

Page 20 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.4

ERCW Supply Header 2A Failure to Auxiliary Building (cont'd)

1O.

OPERATE Train A and B ERCW Pumps

as necessary to perform the following:

CONTROL pressure between 78 psig

and 124 psig.

MAINTAIN support of system loads.

11.

START additional Lower Compartment

Cooling Fans and CRDM Fans as required

to maintain containment temperature.

12.

REFER to the following:

Appendix C, Affected Equiprnent List

(Header 2A)

Appendix P, Potential Tech Spec

Impacts.

13.

ENSURE all breakers reopened

USING Appendix F, Rx MOV Board

ERCW Valves.

14.

REFER TO AOP-M.03, Loss of

Component Cooling Water.

15.

GO TO appropriate plant procedure.

---.--

IF ERCW pressure is high,

THEN

EVALUATE opening ERCW supply

to Containment Spray HX and/or DG HXs

to reduce pressure.

END OF SECTION

Page 21 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.5

ERCW Supply Header 2B Failure to Auxiliary Building

CAUTION:

During op eration, CCP and SI Pumps may experience bearing failure 10

minutes afte r loss of ERCW cooling.

1.

DISPATCH personnel to locate rupture.

2.

DISPATCH operators with radios to

perform Append ix F, Rx MOV Board

ERCWValves. [Aux Bldg el. 749',

Rx MOV Boards].

3.

ENSURE 2A-A CCP RUNNING.

4.

STOP and LOCK OUT the following:

2B-B SI Pump

5.

DISPATCH operator to place Aux Air

Compressor B-B in SAFE STOP.

[Aux Bldg, 734' elev, Refuel Floor]

NOTE

The following step removes all cooling water from the OB1/0B2 CCS HX.

6.

CLOSE 2-FCV-67-147, Hdr 2B to Hdr 1A

1501 Valve. [Rx MOV Bd 2B2-B

Compl. 3B].

Pag e 22 of 142

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.5

ERCW Supply Header 2B Failure to Au xiliary Building (cont'd)

CAUTION 1

Crosstying A and B train ERCW supply headers should only be performed if

cooling is urgently required for Unit 1 Train B CCS related equipment.

LCO 3.0.3 may be applicable.

CAUTION 2

Opening of crosstie valve 1-FCV-67-147 (in Step 7.RNO) may result in fouli ng or

blockage of OB1/0B2 CCS Hx. If time permits, CCS Hx OB2should be isolated

prior to opening crosstie valve to prevent fouling BOTH heat exchangers.

After approx. 10 min, OB2 CCS Hx will be returned to service.

NOTE

ERCW flow on 2B header will be very low if rupture was isolated in previous step.

7.

CHECK ERCW Supply Hdr 2B

parameters to determine if Rupture

ISOLATED :

2-FI-67-62 , at expected value

2-PI-67-488A between 78 psig and

124 psig.

a.

CLOSE 2-FCV-67-82. Aux Bldg Hdr 2B

1501Valve. [Rx MOV Bd 2B2-B

Compt. 3C]

b.

IF desired to isolate OB2CCS Hx

prior to opening crosstie valve,

THEN

PERFORM the following:

1) CLOSE 0-67-1501 CCS Hx OB2 Inlet.

2) WHEN 0-67-1051 CLOSED,

THEN

OPEN 1-FCV-67-147, Hdr 1A to Hdr

2B 1501Valve. [Rx MOV Bd 1A2-A

Compt. gAl.

RECORD time

_

3) IF CCS Hx OB2 indicates fouling or

flow blockage

OR 1-FCV-67-147 has been OPEN

for approximately 10 minutes,

THEN

OPEN 0-67-1501 CCS Hx OB2 Inlet.

4) GO TO Substep d....

(Step continued on next page)

Pag e 23 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.5

ERCW Supply Header 2B Failure to Auxiliary Building (cont'd)

l

7.

(Continued)

c.

EVALUATE opening 1-FCV-67-147.

Hdr 1A to Hdr 2B 1501 Valve [Rx MOV Bd

1A2-A Cornpt. 9A].

RECORD time

_

d.

IF desired.

THEN

PLACE O-FCV-67-152 in the 35%

position.

e.

CLOSE the followin g valves :

2-FCV-67-128. Hdr 2B Supply to

Space Coolers. AlC & Air

Compressors

[Rx MOV Bd 2B2-B Compt, 6C]

2-FCV-67-123. Containment Spray

HX 2B ERCW Supply [O-M-27A]

2-FCV-67-83. Lower Compt

Cooler 2D Supply 1501[O-M-27A]

2-FCV-67-91. Lower Compt

Cooler 2B Supply 1501[O-M-27Al

2-FCV-67-138. Upper Compt

Cooler 2B Supply 1501[O-M-27Al

2-FCV-67-141 . Upper Compt

Coole r 2D Supply 1501[O-M-27A]

(Step continued on next page)

Page 24 of 142

c

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/E XPECTED RESPONSE

RESPONSE NOT OBTAINED

2.5

ERCW Supply Header 2B Failure to Auxiliary Building (cont'd)

7.

(Continued)

f.

DISPATCH an operator to CLOSE the

following valves:

2-67-524B, Supply Hdr 2B to Inst

Room Cooler 2B

[Aux Bldg, 669' elev, Penetration

Room, above Ductwork by panel

2-L-26A].

2-67-675, ERCW Isol to B

Shutdown Board Room A/C Water

Chiller

[Aux Bldg, elev 714' 12' up at

Col R-A-12].

2-67-521B, Hypochlorite

Treatment Circulation Line Isol

[elev 669' TDAFWP Rm by ERCW

supply valves]

g.

IF 1A ERCW header was aligned to

OB1 /0B2 CCS HX,

THEN

GO TO Step 9.

(

8.

ENSURE the following valves are closed:

0-FCV-67-152, CCS HX OB1/0B2 Disch

Valve to Hdr B

0*FCV-67-151, CCS HX OB1/0B2 Disch

Valve to Hdr A

[Rx MOV Bd 1A2-A Compl. 80]

Page 25 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.5

ERCW Supply Header 2B Failure to Auxiliary Building (cont'd)

g.

START additional Lower Compartment

Cooling Fans and CRDM Fans as required

to maintain containment temperature.

10.

OPERATE ERCW Pumps as necessary

to perform the following:

CONTROL pressure between 78 psig

and 124 psig.

MAINTAIN support of system loads

(

11.

REFER TO the following:

Appendix D, Affected Equipment List

(Header 2B)

Appendix P, Potential Tech Spec

Impacts.

12.

ENSURE all breakers reopened

USING Appendix F, Rx MOV Board

ERCW Valves.

13.

REFER to AOP-M.03, Loss of

Component Cooling Water.

14.

GO TO appropriate plant procedure.

--...--

IF ERCW header pressure is high,

THEN

EVALUATE opening ERCW supply to

Containment Spray HX and/or DG HXs

to reduce pressure.

END OF SECTION

Page 26 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.6

ERCW Return Header Rupture in the Auxiliary Building

CAUTIONS :

During operation , CCP and SI Pumps may experience bearing failure

10 minutes after loss of ERCW cooling .

Loss of 2A ERCW Supply Header affects both Units Train A CCS Heat

Exchangers.

(

NOTES

ERCW supply and return headers are located in the pipe tunnels above the

TDAFWP rooms.

Pipe Tunnel

Supply Header

Return Header

Unit 1

1A and 1B

A

Unit 2

2A and 2B

B

MCR indications on M-27 are not indicative of a return header rupture. Field

observation is required to identify rupture size and location.

1.

DISPATCH personnel to locate rupture.

2.

DISPATCH operators with radios to

perform the following:

Appendix F. Rx MOV Board ERCW

Valves . [Aux Bldg, 749' elev]

Appendix H, Diesel Aux Bd ERCW Valves

[Diesel Bldg]

Pag e 27 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP ' I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.6

ERCW Return Header Rupture in the Auxiliary Building (cont'd)

CAUTION 1

Opening crossti e valve 1-FCV-67-424 in the following step may resu lt in severe

fouling or flow blockage of 1A1/1A2 CCS Heat Exchanger, therefore , the CCS

Hx 1A2 should be isolated prior to opening. After approximately 10 minutes

1A2 CCS Hx will be returned to service.

CAUTION 2

Isolation or realignment of 2A ERCW Supply Header will result in loss of ERCW

Cooling water to all Train A CCS HX and therefore. a loss of CCS cooling to the

RCPs.

CAUTION 3

The effects of flooding and loss of cooling to critical components should be

eval uated prior to ini tiating actions to isolate or crosstie ERCW headers.

NOTES:

Rupture of Return Header 'A' will result in Unit 2 being tripped. Aligning 1B

ERCW supply header to 1ACeS HX allows Unit 1 time to perform a controlled

shutdown.

When ERCW Headers are crosstied the actions of LCO 3.0.3 are applicable.

Steps to record the time a valve is opened should be used as an aid for

tracking LCO action times.

(

3.

DETERMINE if isolation of ERCW Return

Header A is required:

a.

CHECK for rupture on ERCW Return

a.

GO TO Step 4.

Header A (based upon break location and

~

reports from personnel in field).

~

b.

ENSURE 1B-B and 2B-B CCPs

RUNNING.

c.

STOP and LOCK OUT the following:

1A-ACCP

2A-ACCP

1A-A SI Pump

2A-A SI Pump

(step continued on next page)

Page 28 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2,6

ERCW Return Header Rupture in the Auxiliary Building (con t'd)

3.

d.

DISPATCH operator to place

Aux Air Compressor A-A in SAFE STOP.

[Aux Bldg eI734', Refuel Floor]

e,

ALIGN 1B ERCW to 1A1/1A2 CCS HX:

1) DISPATCH personnel to CLOSE

1-67-1501 CCS Hx 1A2

Inlet Isol Vlv.

2) WHEN 1-67-1501 CLOSED,

THEN

OPEN 1-FCV-67-424, Hdr B to Hdr 2A

CCst-lX Isol Valve

[Rx MOV Bd 1A2-A Compl. 9Bl

(

RECORD time

3) WHEN 1-FCV-67-424 has been OPEN

for aproximately 10 minutes,

THEN

OPEN 1-67-1501 Inlet to 1A2 CCS Hx.

f.

ISOLATE Aux Bldg 1A and 2A Headers:

CLOSE 1-FCV-67-B1, Aux Bldg

Hdr 1A Isol Valve . [Rx MOV Bd 1A2-A

Compl. 3C]

CLOSE 1-FCV-67-223, Hdr 1B to

Hdr 2A Isol Valve. [Rx MOV Bd 1A2-A

Compl. BB]

CLOSE 2-FCV-67-B1 , Aux Bldg

Hdr 2A Isol Valve

[Rx MOV Bd 2A2-A Compl. 3C].

g.

ENSURE only one Train A ERCW pump

RUNNING.

(Step continued on nex1 page)

Page 29 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.6

ERCW Return Header Rupture in the Auxiliary Building (cont'd)

NOTE:

Substep h provides protection for the in service Train A ERCW pump by providing a

flow path through the D/G HX.

(

3.

h.

OPEN A train ERCW supplies to

D/G HXs to provide a flow path

for running Train A ERCW pump:

ERCW Headers

DG

NOR Supplv

ALT Supply

1A-A

1-FCV-67-66

2A-A

2-FCV-67-66

18-8

1-FCV-67-65

28-8

2-FCV-67-65

i.

OPERATE ERCW pumps as

necessary to perform the following:

CONTROL pressure between

78 psig and 124 psig.

MAINTAIN support system

loads.

NOTE:

Unit 2 will be tripped due to lack of ERCW to the CCS HX 2A112A2.

j.

Unit 2 Only:

PERFORM the following:

1)

TRIP reactor.

2)

STOP RCPs.

3)

GO TO E-O, Reactor Trip or

Safety Injection.

--~.--

(Step continued on next page.)

Page 30 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.6

ERCW Return Header Rupture in the Auxiliary Building (cont'd)

3_

k.

ENSURE CCS HX OB1/0B2 Discharge

aligned to Hdr B:

ENSURE 0-FCV-67-152, CCS

HX OB110B2 Disch Valve to Hdr B

OPEN

ENSURE 0-FCV-67- 151, CCS

HX OB1/0B2 Disch-Valve to Hdr A

CLOSED. [Rx MOV Bd 1A2-A

Compt. 80]_

I.

CLOSE Header A Discharge to Cold

Water Channel Isolations:

0-FCV-67-12 [Diesel Aux Bd 2A2-A

Compt. 3C]

C

0-FCV-67-364

[Diesel Aux Bd 2B2-8 Compt. 4B]

m.

DISPATCH an operator to CLOSE

DG returns to Hdr A:

[Diesel Bldg, outside DG Rooms]:

1-67-511A, 1A DG

1-67-516A, 1B DG

2-67-511 A, 2A DG

2-67-516A, 2B DG

n.

REFER TO following append ixes:

Appendix A, Affecte d Equipment List

(Header 1A)

Appendix C, Affected Equipment List

(Header 2A)

0 _

GO TO Step 5. ..

C

Page 31 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.6

ERCW Return Header Rupture in the Auxiliary Build ing (cont'd)

CAUTION:

The effects of flooding and loss of cooling to critical components sho uld be

evaluated prior to initiating actions to isolate or crosstie ERCW headers .

NOTES:

MCR indications on M-27 are not indicative of a return header rupture.

Field observation is required to identify rupture size and location.

Rupture of Return Header B will require Unit 1 to be tripped in substep 4.i

due the unavailability of cooling water for 1A1/1A2 CCS HX.

4.

DETERMINE if isolation of ERCW Return

Header B is required:

a.

CHECK for rupture on ERCW Return

HeaderB (based upon break location

and reports from personnel in field).

b.

ENSURE 1A-A and 2A-A CCPs

RUNNING.

c.

STOP and LOCK OUT the following:

1B-B Sl Pump

2B-B SI Pump

d.

PLACE Aux Air Compressor B-B

in SAFE STOP. [Aux Bldg el 734'.

Refuel Floor]

e.

ISOLATE Aux Bldg 1Band 2B Headers:

CLOSE 1-FCV-67-82. Aux Bldg

Hdr 18 Isol Valve. [Rx MOV 8d 1B2-8

Compl. 3C]

CLOSE 2-FCV-67-82, Aux Bldg

Hdr 2B 1501 Valve

[Rx MOV Bd 2B2-8 Compl. 3C].

a.

GO TO Step 5.

(

(step continued on next page)

Page 32 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.6

ERCW Return Header Rupture in the Auxili ary Building (cont'd)

NOTE:

CCS HX 1A111A2 outlet flow is to Discharge Header 8. The following substep

isolates ERCW to this HX.

c

4.

f.

CLOSE 1-FCV-67-223, Hdr 18 to

Hdr 2A Isol Valve

[Rx MOV 8d 1A2-A Compl. 88].

g.

ENSURE only one Train 8 ERCW pump

RUNNING.

NOTE:

Substep h provides protection for the in service Train 8 ERCW pump by providing a

flow path through the DIG HX.

h.

OPEN 8 train ERCW supplies to

DIG HXs to provide a flow path for

the running Train 8 ERCW pump:

ERCW Headers

DG

NOR Supply

ALT Supply

1A-A

1-FCV-67-68

2A-A

2-FCV-67-68

18-8

1-FCV-67-67

28-8

2-FCV-67-67

(

NOTE :

1.

Unit 1 will be tripped due to lack of ERCWto the CCS HX 1A1/1A2.

Unit 1 Only:

PERFORM the following:

1) TRIP reactor.

2) STOP RCPs.

3)

GO TO E-O, Reactor Trip or

Safety Injection.

--~.--

(step continued on next page)

Page 33 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.6

ERCW Return Header Rupture in the Au xiliary BUilding (cont'd)

4.

j.

CLOSE Header 8 Discharge to Cold

Wate r Channel Isolations:

O-FCV-67-14. [Diesel Aux 8d 282-8

Compl. 3C)

O-FCV-67-365. [Diesel Aux 8d 2A2-A

Compl. 48]

k.

DISPATCH an operator to CLOSE

DG returns to Hdr 8:

[Diesel 8ldg, outside DG Rooms]:

-

1-67-516B , 1A DG

1-67-511B,1BDG

2-67-5168,2ADG

2-67-511 B, 2B DG.

I.

REFER TO following appendixes :

Appendix 8 , Affected Equipment

List (Header 18)

Appendix 0 , Affected Equipment

List (Header 2B)

(step continued on next page)

Pa ge 34 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.6

ERCW Return Header Ruptu re in the Auxiliary Building (cont'd)

NOTE:

The following substep may be performed to provide cooling water

to the Train 8 CCS HX, if it is urgently needed.

4.

m.

IF aligning cooling water to CCS HX

081/082 is desired,

THEN

PERFORM the following:

1) ALIGN outlet of CCS HX 8 to

Discharge Header A:

OPEN 0-FCV-67-151, CCS HX

081/082 Disch Valve to Hdr A.

(Rx MOV 8d 1A2-A Compl. 8D]

CLOS E 0-FCV-67-152, CCS

HX 081/082 Disch Vlv to Hdr 8.

2) CLOSE the following valves:

2-FCV-67-128, Hdr 28 Supply

to Space Coolers, N C & Air

Comp o [Rx MOV 8d 282-8

Compl. 6C]

2-FCV-67-123 , Containment

Spray HX 28 ERCW Supply

[0-M-27A]

2-FCV-67-83, Lower Compt

Cooler 2D Supply Isol [0-M-27A]

2-FCV-67-91, Lower Compt

Cooler 28 Supply Isol [0-M-27A]

2-FCV-67-138, Upper Compt

Cooler 28 Supply Isol [0-M-27A]

2-FCV-67-141, Upper Compt

Cooler 2D Supply Isol [0-M-27A]

(Step Continued on next page)

Page 35 of 142

c

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP

[

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAI NED

(

2.6

ERCW Return Header Rupture in the Auxiliary Building (cont'd)

4.

m.

3)

DISPATCH personnel to CLOSE the

following valves:

2-67-524B, Supply Hdr 2B to Inst

Room Cooler 2B [Aux Bldg, 669'

elev, Penetration Room, above

Ductwork by panel 2-L-26A]

2-67-521B, Hypochlorite

Treatment Circulation Line

Isolation [AB 669' TDAFWP Rm

by ERCW Supply Valves]

- 2-67-675, ERCW Isol to B

Shutdown Board Room AlC Water

Chiller [AB elev 714' 12' up,

Col R-A12].

4)

OPEN 2-FCV-67-82, Aux Bldg Hdr 2B

Isol Valve [Rx MOV Bd 2B2-B

Comp!. 3C].

Pag e 36 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.6

ERCW Return Heade r Rupture in the Auxiliary Building (cont'd)

5.

OPERATE ERCW Pumps as necessary

to perform the following:

CONTROL pressu re between 78 psig

and 124 psig.

MAINTAIN support of system loads.

6.

START additional Lower Compartment

Cooling Fans and CRDM Fans as required

to maintain containment temperature.

7.

REFER TO Appendix p. Potential Tech

Spec Impacts.

8.

ENSURE all breakers opened

USING the following appendixes:

Appendix F. Rx MOV Board ERCW Valves

Appendix H, Diesel Auxil iary Board Valves

[D/G Building]

9.

GO TO appropriate plant procedure.

---.--

END OF SECTION

Page 37 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.7

ERCW Supply Header 1A/2A Failure in Yard Area

RESPONSE NOT OBTAINED

CAUTIONS:

During operation. CCP and SI Pumps may experience bearing failure

10 minutes after loss of ERCW cooling.

Loss of 2A ERCW Supply Header affects both Units' Train A CCS Heat

Exchangers. Isolation of ruptured Unit and restoration of ERCW to intact

CCS Heat Exchangers is time critical to prevent tripping both Units.

NOTE:

Engineering may be able to identify ruptured yard header using yard piping

drawings (17W300 series).

(

1.

DISPATCH personnel to locate failure.

2.

DISPATCH operators with radios to

PERFORM the following appendixes:

Appendix F, Rx MOV Board ERCW

Valves [Aux Bldg, 749' elev, Rx MOV

Boards]

Appendix G, ERCW MCC Valves

[ERCW Pumping Station]

3.

START additional Train A ERCW

Pumps as required to maintain pressure

between 78 psig and 124 psig.

Page 38 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOP*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (cont'd)

(

4.

MONITOR the following on both Units:

REACTOR COOLANT PUMPS

MOTOR THRUST BEARING TEMP

HIGH alarm DARK [XA-55-5B, E-3]

5.

OPEN alternate ERCW supply for the 1A

and 2A DG HX to ensure cooling water is

available:

1-FCV-67-68 (1A DG)

2-FCV-67-68 (2A DG)

6.

ENSURE 1B-B and 2B-B CCPs

RUNNING.

IF Thrust Bearing temperature

exceeds 200°F,

THEN

PERFORM the following:

a.

TRIP the affected Unit's Rx.

b.

STOP the affected Unit's RCPs.

c.

IF in Mode 1, 2 or 3,

THEN

GO TO E-O, Reactor Trip or Safely

Injection, WHILE continuing in this

procedure . [C.2]

---.--

IF in Mode 4 or 5.

THEN

STABILIZE RCS temperature

USING Train B RHR shutdow n cooling.

Page 39 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (cont'd)

7.

STOP and LOCK OUT the following:

1A-A CCP

1A-A 51 Pump

2A-A CCP

2A-A 5 1Pump

8.

DISPATCH operator to place Train A

Aux Air Compressor in SAFE STOP.

[Aux Bldg. 734' elev, Refuel Floor]

Page 40 of 142

(

-.

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A/2A Failu re in Yard Area (cont'd)

CAUTION

Opening crosstie valve 1-FCV-67-424 (in following step) may result in severe

fouling/blockage of 1A1I1A2 CCS Heat Exchanger. If plant conditions and time

permits, CCS Hx 1A2 should be isolated prior to opening crosstie valve. After

app roximately 10 minu tes 1A2 CCS Hx will be returned to service.

NOTE

Crosstying 1Band 2A ERCW headers before the ruptured header has been

identified will ensure ERCW cooling is available to ALL Train A CCS HX.

When ERCW Headers are crosstied the actions of LCO 3.0.3 are applicable.

Steps to record the time valve is opened should be used as an aid for tracking

LCO action times.

With CCS available to RCP oil coolers tripping both units can be avoided

providing time for an orderly shutdown.

9.

EVALUATE performing the following to

crosslie 1Band 2A ERCW headers:

a.

IF desired to isolate 1A2 CCS Hx

prior to opening crosstie valve,

THEN

PERFORM the following:

1)

CLOSE 1-67-1501 CCS Hx 1A2

Inlet Isol Vlv.

2)

WHEN 1-67-1501 CLOSED,

THEN

OPEN 1-FCV-67-424. Hdr 1B to Hdr

2A CCS HX Isol Valve

[Rx MOV Bd 1A2-A Compt. 9B].

RECORD Time

_

3)

IF CCS Hx 1A1 indicates fouling or

blockage OR 1-FCV-67-424 has been

OPEN for approximately 10 minutes,

THEN

OPEN 1-67-1501 Inlet to 1A2 CCS Hx.

4)

GO TO Substep C....

(step continued on next page)

Page 41 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (cont'd)

9.

b.

OPEN 1-FCV-67-424 and

RECORD Time

_

c.

ENSURE 1-FCV-67-223 is OPEN.

d.

ENSURE 2-FCV-67-223 is OPEN.

10.

MONITOR ERCW header pressure

and flow:

OPERATE ERCW pumps as required.

11.

MONITOR running CCP temperatures

on both units.

12.

START additional lower containment cooler

fans and CRDM fans as necessary.

NOTE

If the rupture is on the crosstie header at the CCW building (IPS), and is isolated in

the following step, then restoration of the 1Band 2A ERCW headers to normal

configuration must be performed as expeditiously as possible.

13.

ISOLATE 1Af2A ERCW

Crosstie Header:

CLOSE 1-FCV-67-22, ERCW

Strainer 1A-A Isol Valve

[Rx MOV Bd 1A2-A CampI. 3A].

CLOSE 2-FCV-67-22, ERCW

Strainer 2A-A Isol Valve

[Rx MOV Bd 2A2-A Cornpt. 3A].

Page 42 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (cont'd)

14.

DO NOT CONTINUE UNTIL Crosstie

Header is isolated (Step 13 complete).

NOTE

Number of pumps in service should be considered when evaluating header flows

and pressures to determine if rupture is isolated.

15.

DETERMINE if rupture is isolated:

a.

CHECK 1A and 2A ERCW supply

header parameters NORMAL:

1,2-FI-67-61 at expected value

1,2-PI-67-493A between 78 psig and

124 psig

b.

EVALUATE flood damage at CCW

Building (IPS).

a.

GO TO Notes prior to step 19.

......

Page 43 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (cont'd)

NOTE:

After isolation of a rupture on the ERCW crosstie header in the CCW bUilding (IPS),

1Band 2A ERCW header alignment must be restored to normal configuration as

expeditiously as possible.

16.

PERFORM the following to restore 1Band 2A

ERCW headers if they were crosstied:

a.

CHECK 1B and 2A ERCW headers

crosstied.

b.

CLOSE 1-FCV-67-424 and

RECORD time

_

c.

ENSURE 1-FCV-67-223 is OPEN.

d.

ENSURE 2-FCV-67-223 is OPEN.

17.

CONTROL ERCW pumps as required

to maintain pressure between 78 psig and

124 psig.

18.

GO TO appropriate plant procedure.

--~.--

a.

GO TO Step 17.

Page 44 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOP*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (cont'd)

NOTES:

Train A ERCW header failure in the yard area could result in all Train A header

pressures indicating low. After ERCW crosstie header valves at CCW have been

isolated, strainer HIGH DIFF PRESSURE alarm may indicate the failed header.

If no differential press alarms are illumi nated. isolating 1A header first

(in Step 20) would have the least effect on the plant.

19.

CHECK Stra iner Diff Press High alarms

on 0-XA-55-27A are DARK:

HEADE R 1A-A STRAINER DIFF

PRESS HIGH- window 0-2

HEADER 2A-A STRAINE R DIFF

PRESS HIGH- window C-3

IF window 0-2 and C-3 are both illuminated.

THEN

GO TO step 20.

IF window 0-2 is illuminated,

THEN

a.

ISOLATE 1A ERCW Header rupture:

CLOSE 1-FCV-67-492, Hdr 1A Isol

Before Strainer. [ERCW MCC 1AA

Cornpt. 3C].

CLOSE 1-FCV-67-81, Hdr 1A Isol to

Aux Bldg. [Rx MOV Bd 1A2-A

Cornpt. 3C]

b.

GO TO Note prior to step 22...

IF window C-3 is illuminated.

THEN

a.

ISOLATE 2A ERCW Header rupture:

CLOSE 2*FCV-67-492 , Hdr 2A Isol

Before Strainer. [ERCW MCC 2AA

Compl. 3C].

CLOSE 2-FCV-67-81, Hdr 2A Isol to

Aux Bldg. [Rx MOV Bd 2A2-A

Compl. 3C]

b.

GO TO Note prior to step 21...

Page 45 of 142

('

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M .01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A12A Failure in Yard Area (cont'd)

NOTE:

If 1A ERCW header rupture is isolated in the following step, then restoralion of 1B

and 2A headers to normal configuration must be performed as expeditiously as

possible.

20.

ISOLATE 1A ERCW Header rupture:

a.

CLOSE the following valves

1-FCV-67-492, Hdr 1A Isol

Before Strainer [ERCW MCC 1M

Compt. 3C]

1-FCV-67-81, Hdr 1A Isol to Aux Bldg

[Rx MOV Bd 1A2-A Compt. 3C]

b.

WHEN valves are closed.

THEN

GO TO Note before step 22.

Page 46 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (cont'd)

NOTE

Number of pumps in service should be considered when evaluating header fiows

and pressures to determine if rupture is isolated.

21.

DETERMINE if Rupture is isolated:

(

a.

CHECK 1A ERCW header

parameters at expected values:

1-FI-67-61

1-PI-67-493A

b.

GO TO step 25.

a.

RESTORE 2A ERCW header:

OPEN 2-FCV-67-492, Hdr 2A Isol

Before Strainer- [ERCW MCC Bd

2M

Compl. 3C]

OPEN 2-FCV-67-81, Hdr 2A Isol to

Aux Bldg. [Rx MOV Bd 2A2-A

Compl. 3A]

GO TO Step 20 to isolate 1A header.

Page 47 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOP-M .01

Rev. 15

STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (cont'd)

NOTE

Number of pumps in service should be considered when evaluating header flows

and pressures to determine if rupture is isolated.

22.

DETERMINE if Rupture is isolated:

(

a. CHECK 2A ERCW header parameters

at expected values:

2-FI-67-61 at expected value

2-PI-67-493A at expected value

b. IF 1Band 2A ERCW headers were

crosstied,

THEN

PERFORM the following:

1) CLOSE 1-FCV-67-424 and

RECORD time

_

2) ENSURE 1-FCV-67-223 is OPEN.

3) ENSURE 2-FCV-67-223 is OPEN.

a.

RESTORE 1A ERCW Header:

OPEN 1-FCV-67-492, Hdr 1A Isol

Before Strainer. [ERCW MCC 1M

Compl. 3C]

OPEN 1-FCV-67-81. Hdr 1A Isol to Aux

Bldg. [Rx MOV Bd 1A2-A Compl. 3C]

ISOLATE 2A ERCW Header rupture:

CLOSE 2-FCV-67-492, Hdr 2A Isol

Before Strainer. [ERCW MCC 2M

Compl. 3C].

CLOSE 2-FCV-67-81. Hdr 2A Isol to

Aux Bldg. [Rx MOV Bd 2A2-A

Compl. 3A]

GO TO Step 25.

Page 48 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (cont'd)

CAUTION

Crosstying 1A and 2B train ERCW supply headers should only be performed if

cooling is urgently required for Unit 1 Train A Component Cooling Water related

equipment. LCO 3.0.3 may be applicable.

23.

DETERMINE if ERCW Hdr 28 should be

aligned to supply 1A header:

(

a.

CHECK if restoration of 1A ERCW header

from Train B supply is required.

b.

EVALUATE performing the following

to align 28 to 1A header:

ENSURE 2-FCV-67-147. Hdr 2B

to Hdr 1A OPEN. [Rx MOV 8d

282-8 Compt. 38]

OPEN 1-FCV-67-147 [Rx MOV 8d

1A2-A Compt. gAl and

RECORD Time

_

a.

.GO TO step 26.

NOTE

Due to the increased demand after headers are crosstied expect abnormal flow and

pressure indications.

24.

CHECK 28 ERCW header pressures and

flows NORMAL:

2-FI-67-62, at expected value

2*PI-67-488A. between 78 psig and

124 psig

START additional "8" Train ERCW pumps

as necessary

ISOLATE non-essential ERCW loads

as necessary.

DO NOT CONTINUE UNTIL header

pressure and flow are acceptable

for the current alignment.

l

Page 49 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

AOP-M.0 1

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

c.

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (con t'd)

25.

RESTORE equipment, with cooling water

available , as desired for applicable

Train A ERCW header:

1A CCP to A-AUTO

1A 81 Pump to A-AUTO

A-A Aux Air Compressor to AUTO

[Aux Bldg, 734' elev, Refuel Floor]

2A CCP to A-AUTO

2A 81Pump to A-AUTO

26.

EVALUATE isolation of non-essential

Train A CCS heat loads USING App. E,

CCS Heat Load Reduction.

27.

OPERATE ERCW Pumps as necessary

to perform the following :

CONTROL pressure between 78 psig

and 124 psig.

MAINTAIN support of system loads.

Page 50 of 142

('

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

c..

2.7

ERCW Supply Header 1A/2A Failure in Yard Area (cont'd)

28.

REFER TO Appendix P, Potential Tech

Spec Impacts.

29.

ENSURE all breakers reopened

USING the following appendixes:

Appendix F, ERCW Rx MOV Board

Appendix R ERCW Valves

Appendix5}, ERCW MCC Appendix R

Valves

30.

GO TO appropriate plant procedure.

---.--

END OF SECTION

Page 51 of 142

('

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

STEP I

ACTION/EXPECTED RESPONSE

2.8

ERCW Supply Header 1B/28 Failure in Yard Area

RESPONSE NOT OBTAINED

(

CAUTION:

During ope ration , CCP and SI Pumps may experience bearing failu re

10 minutes after loss of ERCW cooling.

NOTE:

Engineering may be able to identify ruptured yard header using yard piping drawings

(17W300 series).

1.

DISPATCH personnel to locate failure.

2.

DISPATCH operators with radios

to perform the following appendixes:

Appendix F, Rx MOV Board ERCW

Valves. [Aux Bldg, el. 749', Rx MOV

Boards]

Appendix G, ERCW MCC Valves

[ERCW Pumping Stations]

3.

MONITOR ERCW header pressure:

CONTROL Train B ERCW Pumps

as required to maintain pressure

between 78 psig and 124 psig.

4.

OPEN alternate ERCW supply to DG HX:

1-FCV-67-65 (1B DG)

2-FCV-67-65 (2B DG)

Pag e 52 of 142

(

saN

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.8

ERCW Supply Header 1B/2B Failure in Yard Area (cont'd)

5.

ENSURE 1A-A and 2A-A CCPs

RUNNING.

6.

STOP and LOCK OUT affected

equipment:

a.

PLACE the following pumps in

PULL TO LOCK:

1B-B SI Pump

2B-B SI Pump

b.

DISPATCH operator to place Train B

Aux Air Compressor in SAFE STOP.

[Aux Bldg, 734' elev , Refuel Floor]

7.

ISOLATE 1B/2B ERCW Crosstie Header:

CLOSE 1-FCV-67-24, ERCW Strainer

1B-B 1501Valve

[Rx MOV Bd 1B2-B Cornpt. 3A].

CLOSE 2-FCV-67-24, ERCW Strainer

2B-B 1501 Valve

[Rx MOV Bd 2B2-B Compt. 3A].

8.

DO NOT CONTINUE UNTIL crosstie

header is isolated.

Page 53 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

1 STEP

I

ACTION/EXPECTED RESPONSE

RESPONSE NOT 08TAINED

2.8

ERCW Supply Header 18/28 Failure in Yard Area (cont'd)

NOTE

Number of pumps in service should be considered when evaluating header flows

and pressures to determine if rupture is isolated.

9.

DETERMINE if rupture is isolated:

a.

CHECK 1Band 2B ERCW supply

header parameters NORMAL:

1,2-FI-67-62

1,2-PI-67-488A

b.

EVALUATE flood damage at CCW Bldg

(IPS).

a.

GO TO Notes prior to step 10...

c.

GO TO appropriate Plant Procedure.

--~.--

(

Page 54 of 142

(

LOSS OF ESSENTIAL RAW COOLING W ATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.8

ERCW Supply Header 1B/2B Failure in Yard Area (cont'd)

NOTES

B train ERCW header failure in the yard area could result in all 8 train

header pressures and flows indicating low.

After the crosstie header valves at the IPS have been isolated the HIGH DIFF

PRESSURE alarm may indicate the failed header.

10.

CHECK Strainer Differential Pressure

High Alarms on O-XA-55-27A are dark:

HEADER 18-B STRAINER DIFF

PRESS HIGH (window D-5)

HEADER 28-8STRAIN ER DIFF

PRESS HIGH (window C-6)

IF window D-5 and C-6 are both illuminated,

THEN

GO TO Step 11.

IF window D-5 is illuminated,

THEN

a.

ISOLATE 18 ERCW header rupture

CLOSE 1-FCV-67-489, Hdr 18 Isol

8efore Strainer [ERCW MCC 18-B

Compl. 3C].

CLOSE 1-FCV-67-82 AB Hdr 18 Isol

[Rx MOV 8d 182-8 Com pI. 6C]

b.

GO TO Note prior to Step 13...

IF window C-6 is illuminated.

THEN

a.

ISOLATE 2B ERCW header rupture

CLOSE 2-FCV-67-489 Hdr 2B lsot

Before Strainer

[ERCW MCC 2BB Compl. 3C].

CLOSE 2-FCV-67-82 AB Hdr 28 Isol

[Rx MOV Bd 282-8 Compt. 6C]

b.

GO TO Note prior to Step 12...

.c...

Page 55 of 142

RESPONSE NOT OBTAINED

I STEP I

ACTION/EXPECTED RESPONSE

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

2.8

ERCW Supply Header 1B/2B Failure in Yard Area (cont'd)

11.

ISOLATE 1B ERCW Header rupture:

a.

CLOSE 1-FCV-67-489. Hdr 1B Isol

Before Strainer. [ERCW MCC 1B-B

Comp!. 3C]

b.

CLOSE 1-FCV-67-82. AB header 1B

Isolation Valve to Aux Bldg

[Rx MOV Bd 2A2-A Comp!. 3C]

c

GO TO the Note before step 13.

a-

NOTE

Number of pumps in service should be considered when evaluating header flows

and pressu res to determine if rupture is isolated .

12.

DETERMINE if Rupture is ISOLATE D:

a.

CHECK 1B ERCW header

parameters at expected values :

1-FI-67-62

1-PI-67-488A

b.

GO TO the Note before step 16.

a-

a.

RESTORE 2B ERCW Header:

OPEN 2-FCV-67-489. 2B ERCW

header Isolation before strainer

[ERCW MCC 1B-B Comp!. 3C]

OPEN 2-FCV-67-82 AB Hdr 2B \\sol

[Rx MOV Bd 2B2-B Cornpt, 6C]

GO TO Step 11 to isolate 1B header.

---~

(

Page 56 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOP*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.8

ERCW Supply Header 1B/2B Failure in Yard Area (cont'd)

NOTE

Number of pumps in service should be considered when evaluating header flows

and pressures to determine if rupture is isolated.

(

13.

CHECK 2B ERCW header parameters to

determine if rupture is isolated:

2-FI-67-61

2-PI-67-493A

a.

RESTORE 1B ERCW Header:

OPEN 1-FCV-67-489 , Hdr 1B Isol

Before Strainer

[ERCW MCC 1B-B Compl. 3C]

OPEN 1-FCV-67-82, Hdr 1B Isolation

Valve to Aux Bldg

[Rx MOV Bd 2A2-A Compl. 3C]

b.

ISOLATE 28 ERCW header:

CLOSE 2-FCV-67-489 Hdr 28 Isol

8efore Strainer

[ERCW MCC 2BB Compl. 3C].

CLOSE 2-FCV-67-82, Hdr 28 Isol

valve to Aux 8ldg.

[Rx MOV 8d. 282-8 Compl. 3C]

c.

GO TO Cautions prior to Step 16.

..

Page 57 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT 08TAINED

2.8

ERCW Supply Header 18/28 Failure in Yard Area (cont'd)

CAUTION

Crosstying 2A and 18 train ERCW supply headers should only be performed

if cooling is urgently requi red for Unit 1 Train 8 CCS related equipment.

LCO 3.0.3 may be applicable.

14.

EVALUATE aligning ERCW Hdr 2A to

supply 1B loads:

c

(

a.

CHECK additional cooling needed for 1B

train equipment:

b.

EVALUATE crosstying 2A and 1B ERCW

supply headers as follows:

1) OPEN 1-FCV-67-424

[Rx MOV Bd 1A2-A CampI. 9Bl

and

RECORD Time

_

2) ENSURE 1-FCV-67-223, Hdr 1B to

Hdr 2A OPEN. [Rx MOV Bd 1A2-A

CampI. 8B)

3) ENSURE 2-FCV-67-223, Hdr 2A to

Hdr 1B OPEN. [Rx MOV Bd 2A2-A

Cornpt, 8B]

a.

GO TO the note before step 19.

a-

Page 58 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.8

ERCW Supply Header 1B/2B Failure in Yard Area (cont'd)

15.

CHECK 2A ERCW header pressure and

flow NORMAL:

(

a.

CHECK the following:

2-FI-67-61. at expected value

2-PI-67-493A, between 78 psig

and 124 psig

b.

GO TO Step 18.

a.

START additional "A" Train ERCW

pumps as necessary.

ISOLATE non-essential ERCW loads

as necessary.

DO NOT CONTINUE UNTIL header

pressure and flow are ACCEPTABLE

for the current alignment.

Page 59 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.8

ERCW Supply Header 1B/2B Failure in Yard Area (cont'd)

CAUTION 1

Crosstying 1A and 28 train ERCW supply headers should only be performed

if cooling is urgently required for Unit 2 Train B CCS related equipment.

LCO 3.0.3 may be applicable.

CAUTION 2

Opening of crosstie valve 1*FCV-67-147 may result in severe fouling or flow

blockage of 1A1/1A2 CCS Heat Exchanger, therefore, the CCS Hx 1A2 should

be isolated prior to opening. After approximately 10 minutes 1A2 CCS Hx will

be returned to service.

NOTE

1A ERCW header will supply 081 and OB2 CCS heat exchangers if 1A and 2B

ERCW headers are crosstied.

16.

DETERMINE if ERCW Hdr 1A should be

aligned to supply Hdr 2B loads:

a.

CHECK if restoration of 2B ERCW

header from Train A supply is required.

b.

ENSURE 2-FCV-67-147, Hdr 2B to

Hdr 1A OPEN. [Rx MOV Bd 2B2-B

Compl. 3B]

c.

CLOSE 0-67-1501 CCS Hx 1A2 Inlet

Isolation Vlv.

d.

WHEN 0-67-1501 CLOSED,

THEN

OPEN 1-FCV-67-147 [Rx MOV Bd 1A2-A

Compl. 9A] and

RECORD Time

_

e.

WHEN 1-FCV-67-147 has been OPEN

for approximately 10 minutes,

THEN

OPEN 0-67-1501 CCS Hx 1A2 Inlet

Isolation Vlv.

a.

GO TO Slep 19.

Page 60 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.8

ERCW Supply Heade r 1B/2B Failure in Yard Area (cont'd)

17.

CHECK 1A ERCW header pressures and

flows NORMAL:

1-FI-67-61, at expected value

1-PI-67-493A, between 78 psig and

124 psig

START additional "A" Train ERCW

pumps as necessary

ISOLATE non-essential ERCW loads

as necessary.

DO NOT CONTINUE UNTIL header

pressure and flow is acceptable

for the current alignment.

NOTE

2A ERCW header may have been aligned to supply 1B ERCW header in step 14.

1A ERCW header may have been aligned to supply 2B ERCW header in step 16.

18.

IF any ERCW headers were crosstied,

THEN

RESTORE the applicable equipment

as desired:

1B CCP to A-AUTO

18 SI Pump to A-AUTO

28 CCP to A-AUTO

28 SI Pump to A-AUTO

Train B Aux Air Compressor to AUTO

[Aux Bldg, 734' elev, Refuel Floor]

19.

EVALUATE isolation of non-essential

Train A CCS heat loads

USING Appendix E, CCS Heat Load

Reduction.

Page 61 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.8

ERCW Supply Header 1B/2B Failure in Yard Area (cont'd)

20.

OPERATE ERCW Pumps as necessary

to maintain pressure between 78 psig

and 124 psig.

21.

ENSURE all breakers reopened

USING the following:

Appendix F, ERCW Rx MOV Board

ERCW Valves

Appendix G, ERCW MCC Valves

22.

REFER TO the following:

Appendix A, Affected Equipment List

(Header 1A)

Appendix C, Affected Equipment List

(Header 2A)

Appendix P, Potential Tech Spec

Impacts

23.

REFER TO AOP-M.03, Loss of

Component Cooling Water.

24.

GO TO appropriate plant procedure.

--.*--

END OF SECTION

Page 62 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.9

ERCW Supply Header A Failu re Upstream of ERCW Strainer Inlet Valves

CAUTION:

During operation, CCP and SI Pumps may experience bearing failure

10 minutes after loss of ERCW.

1.

STOP and LOCK OUT all Train A ERCW

Pumps.

2.

DISPATCH operato rs with radios to

perform the following:

PERFORM Appendix F, Rx MOV Board

ERCWValves

[Aux Bldg el. 749', Rx MOV Boards]

PERFORM Appendix G, ERCW MCC

Valves [ERCW Pumping Station]

ENSURE all pumping station watertight

doors are CLOSED

[ERCW Pumping Station]

Page 63 of 142

c

SON

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.9

ERCW Supply Header A Failu re Upstream of ERCW Strainer Inlet Valves (cont'd)

CAUTION:

Loss of 2A ERCW Supply Header affects both Units' Train A CCS Heat

Exchangers. Restoration of ERCW to intact CCS Heat Exch angers is time

critical to prevent tripping both Units.

3.

MONITOR the following on both units:

REACTOR COOLANT PUMPS

MOTOR THRUST BEARING TEMP

HIGH alarm DARK [M-5B window E-3].

4.

ENSURE 1B-B and 2B-B CCPs

RUNNING.

IF Thrust Bearing temp exceeds 200' F,

THEN

PERFORM the following:

a.

TRIP the affected Unit(s) Rx.

b.

STOP affected Unit(s) RCPs.

c.

IF in Mode 1, 2, or 3,

THEN

GO TO E-O, Reactor Trip or Safety

Injection, WHILE continuing with this

procedure. [C.2]

---.--

IF in Mode 4, 5, or 6,

THEN

STABILIZE RCS temperature

USING RHR shutdown cooling.

Page 64 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.9

ERCW Supply Header A Failure Upstream of ERCW Strainer Inlet Valves (cont'd)

5.

STOP and LOCK OUT affected

equipment:

a.

PLACE the following pumps in

PULL TO LOCK:

1A-A CCP

1A-A SI Pump

2A-ACCP

2A-A SI Pump

b.

DISPATCH operator to place Train A

Aux Air Compressor in SAFE STOP.

[Aux Bldg, 734' elev, Refuel Floor]

6.

OPEN alternate ERCW supply to DGs

to ensure cooling water is available:

1-FCV-67-68 (1 A DG)

2-FCV-67-68 (2A DG)

Page 65 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.9

ERCW Supply Header A Failure Upstream of ERCW Strainer Inlet Valves (cont'd)

NOTE

Flooding at the ERCW station may prevent FCVs from closing. Manual valves are

located south of the CCW station and are normally locked open.

7.

ISOLATE Train A ERCW Header rupture:

a.

CLOSE 1-FCV-67-492. Header 1A Isol

Before Strainer [ERCW MCC 1M

Cornpt, 3C]

b.

CLOSE 2-FCV-67-492 , Header 2A Isol

Before Stra iner. [ERCW MCC 2M

Compt.3C]

8.

OPERATE available Train B ERCW

Pumps as necessary to perform the

followinq;

CONTROL pressure between 78 psig and

124 psig.

MAINTAIN support of system loads.

a.

CLOSE 1-VLV-67-518A, ERCW

Supply Isolation Valve.

b.

CLOSE 2-VLV-67-518A, ERCW

Supply Isolation Valve.

Page 66 of 142

c

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.9

ERCW Supply Header A Failure Upstream of ERCW Strainer Inlet Valves (cont'd)

CAUTION 1

Loss of 2A ERCW Supply Header affects both Units' Train A CCS Heat

Exchangers. Restoration of ERCW to intact CCS Heat Exchangers is time

critical to prevent tripping both Units.

CAUTION 2

Opening crosstie valve 1-FCV-67-424 may result in fouling or blockage of CCS

HX. If time permits, CCS Hx 1A2 and 2A2 should be isolated prior to opening.

After approx. 10 minutes, 1A2 CCS Hx will be returned to service.

NOTES:

Crosstying ERCW headers 1Band 2A in following step allows time for orderly

shutdown by ensuring CCS cooling for RCPs. LCO 3.0.3 may be applicable.

With the ERCW header crosstie valves at the CCW (IPS) station open, 1B

header will supply 2A and 1A ERCW Aux Bldg supply headers. Additional

Train B ERCW pumps may have to be started.

9.

ALIGN ERCW header 18 to supply 2A:

a.

IF desired to isolate 1A2 and 2A2 CCS

Hx prior to opening crosstie valve,

THEN

PERFORM the following:

1) CLOSE the following CCS Hx Inlet

valves:

1-67-1501 CCS Hx 1A2

2-67-1501 CCS Hx 2A2

2) WHEN CCS Inlet valves CLOSED,

THEN

OPEN 1-FCV-67-424

[Rx MOV Bd 1A2-A Compl. 98]

and

RECORD Time

_

IF 18 ERCW header will NOT be aligned

to supply 2A header,

THEN

PERFORM the following:

a. TRIP BOTH Unit's Reactors.

b. STOP both units RCPs.

c.

IF in Modes 1, 2, or 3,

THEN

GO TO E-O,

WHILE continuing in this procedure.

--~.--

d. IF in modes 4, 5, or 6,

THEN

STABILIZE RCS Temperature

USING RHR shutdown Cooling.

GO TO Step 15.

(Step Continued on next page)

Page 67 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.9

ERCW Supply Header A Failure Upstream of ERCW Strainer Inlet Valves (cont'd)

9.

a.

3) WHEN 1-FCV-67-424 has been OPEN

for approximately 10 minutes ,

THEN

OPEN CCS Inlet Valves:

1-67-1501 CCS Hx 1A2

2-67-1501 CCS Hx 2A2

4) GO TO Substep c,..

b.

OPEN 1:.FCV-67-424 [Rx MOV Bd 1A2-A

Cornpt, 9Bl

and

RECORD Time

_

c.

ENSURE 1-FCV-67-223 , Hdr 1B to Hdr 2A

OPEN. [Rx MOV Bd 1A2-A Cornpt, 8B]

d.

ENSURE 2-FCV-67-223, Hdr 2A to Hdr 1B

OPEN . [Rx MOV Bd 2A2-A Cornpt . 8B]

10.

EVALUATE if 2B header should be crosstied

with 1A header:

a.

CHECK if additional flow for 1A heade r

is required from 2B heade r:

b.

OPEN 1-FCV-67-147, Hdr 1A to

Hdr 2B Isol Valve

[Rx MOV Bd 1A2-A Cornpt . gAl and

RECORD the time.

_

c.

ENSURE 2-FCV-67-147, Hdr 2B to

Hdr 1A Isol Valve is OPEN.

[Rx MOV Bd 2B2-B Compl. 3B].

a.

GO TO step 11.

Page 68 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.9

ERCW Sup ply Header A Failure Upstream of ERCW Strainer Inlet Valves (cont'd )

11,

START additional Lower Compartment

Cooling Fans and CRDM Fans

as required to maintain containment

temperature.

12.

MONITOR Containment Pressure and

Temperature.

(

13.

CHECK 1Band 2B ERCW header flows

and pressures NORMAL:

l-FI-67-62

2-FI-67-6 2

1-PI-67-488A

2-PI-67-488A

14.

RESTORE equipment:

a.

CHECK Train A ERCW header

supplied from Train B crosstie.

b.

RESTORE the following handswitches

as applicable:

1A-A CCP to A-AUTO

1A-A 51Pump to A-AUTO

Train A Aux Air Compressor to AUTO

[Aux Bldg, 734' elev, Refuel Floor]

2A-A CCP to A-AUTO

2A-A 51Pump to A-AUTO

START additional "B" Train ERCW

pumps as necessary.

ISOLATE non-essential ERCW loads

as necessary.

DO NOT CONTINUE UNTIL header

pressure and flow are adequate for

current alignment.

a.

GO TO step 16.

Page 69 of 142

LOSS OF ESSENTIAL RAW COOLING WATER

Rev, 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.9

ERCW Supply Header A Failure Upstream of ERCW Strainer Inlet Valves (cont'd)

15.

EVALUATE isolation of non-essential

Train A ees heat loads

USING Appendi x E, ees Heat Load

Reduction.

16.

ENSURE all breakers open

USING the following appendixes:

Appendix F. ERCW Rx MOV Board

Valves

AppendixG, ERCW MCC Valves

17.

REFER to the following appendices:

Appendix A, Affected Equipment List

(Header 1A)

Appendix C, Affected Equipment List

(Header 2A)

Appendix P, Potential Tech Spec

Impacts.

18.

REFER TO AOP-M.03, Loss of

Component Cooling Water

19.

GO TO appropriate plant procedure.

--~.--

END OF SECTION

Page 70 of 142

(

"

SON

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.10 ERCW Supply Header B Failure Upstream of ERCW Strainer Inlet Valves

CAUTION:

During operation, CCP and 51Pumps may experience bearing failure

10 minutes after loss of ERCW cooling.

1,

STOP and LOCK OUT all Train B ERCW

Pumps,

2,

DISPATCH operators with radios

to perform the following:

PERFORM Appendix F, Rx MOV Board

ERCW Valves

[Aux Bldg el. 749', Rx MOV Boards],

PERFORM Appendix G, ERCW MCC

Valves ,

[ERCW Pumping Stations]

ENSURE all pumping station watertight

doors are CLOSED. [ERCW Pumping

Station],

3,

ENSURE 1A-A and 2A-A CCPs

RUNNI NG.

4,

STOP and LOCK OUT affe cted

equipment:

a,

PLACE the following pumps in

PULL TO LOCK:

1B-B SI Pump

2B-B SI Pump

b.

DISPATCH operator to place Train B

Aux Air Compressor in SAFE STOP,

[Aux Bldg , 734' elev, Refuel Floor]

Page 71 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.10 ERCW Supply Header B Failure Upstream of ERCW Strainer Inlet Valves (cont'd)

5.

OPEN alternate ERCW supply to

Train B OGs

1-FCV-67-65 (1B OG)

2-FCV-67-65 (2B DG)

NOTE

Flooding at the ERCW station may prevent FCVs from closing. Manual valves are

located south of the CCW station and are normally locked open.

6.

ISOLATE Trai n B ERCW Header rupture:

l

a.

CLOSE 1-FCV-67-489, Header 1B 1501

Before Strainer [ERCW MCC 1B-B

Compl. 3C].

b.

CLOSE 2-FCV-67-489. Header 2B 1501

Before Strainer [ERCW MCC 2B-B

Cornpt, 3C].

7.

OPERATE available Train A ERCW

Pumps to maintain pressure

between 78 psig and 124 psig.

a.

CLOSE 1-VLV-67-518B, ERCW Supply

Isolation Valve

b.

CLOSE 2-VLV-67-518B , ERCW Supply

Isolation Valve

Page 72 of 142

(

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LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev . 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.10 ERCW Supply Header B Failure Upstream of ERCW Strainer Inlet Valves (cont'd)

CAUTION 1

Crosstying A and B train ERCW supply headers should only be performed if

cooling is urgently required for Train B CCS related equipment. LCO 3.0.3

may be applicable.

CAUTION 2

Opening of crosstie valve 1-FCV-67-147 may result in severe fOUling or flow

blockage of OB1/0B2 CCS Heat Exchanger, therefore the CCS Hx OB2 should be

isolated prior to opening. Afte r approximately 10 minutes OB2 CCS Hx will be

returned to service.

NOTE

The following step allows 1A ERCW header to supply 2B ERCW header

(including OB1 and OB2 CCS HX).

With the ERCW header crosstie valves at the CCW (IPS) station open, 1A

_header will supply 2B and 1B ERCW Aux Bidg supply headers.

8.

EVALUATE aligning Train A ERCWto

supply Train B:

a.

IF aligning 1A to 2B header is desired,

THEN

PERFORM the following:

1) DISPATCH personnel to CLOSE

0-67-1501 CCS Hx OB2 Inlet valve.

2) WHEN 0-67-1501 CLOSED,

THEN

OPEN 1-FCV-67-147, Hdr 1A to

Hdr 2B Isol Valve

[Rx MOV Bd 1A2-A Compl. 9A] and

RECORD time

_

3) WHEN 1-FCV-67-147 has been OPEN

for approximately 10 minutes,

THEN

OPEN 0-67-1501 CCS Hx OB2 Inlet

valve

(step continued on next page)

Page 73 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.10 ERCW Supply Header B Failure Upstream of ERCW Strainer Inlet Valves (cant'd)

8.

b.

IF aligning 2A to 1B header is desired,

THEN

PERFORM the following:

OPEN 1-FCV-67-424. Hdr 1B to

Hdr 2A CCS HX 1501 Valve

[Rx MOV Bd 1A2-A Cornpt. 9B] and

RECORD the Time

_

ENSURE 1-FCV-67-223, Hdr 1B

to Hdr 2A 1501 Valve is OPEN.

[Rx ~OV Bd 1A2-A Cornpt. 8B].

ENSURE 2-FCV-67-223, Hdr 2A

to Hdr 1B 1501 Valve is OPEN.

[Rx MOV Bd 2A2-A Compl. 8B].

9.

START additional Lower Compartment

Cooling Fans and CRDM Fans

as required to maintain containment

temperature.

10.

MONITOR Containment Pressure and

Temperature.

Page 74 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev.

15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

2.10 ERCW Supply Header B Failure Upstream of ERCW Strainer Inlet Valves (cont'd)

11.

CHECK 1A and 2A ERCW header

pressures and flows adequate for current

alignment:

1-FI-67-61 and 2-FI-67-61,

at expected value

1-PI-67-493A and 2-PI-67-493A

12.

RESTORE equipment:

a.

CHECK Train 8 ERCW header

supplied from Train A crosstie.

b.

RESTORE the following handswitches

as applicable:

18-8 CCP to A-AUTO

18-8 81 Pump to A-AUTO

28-8 CCP to A-AUTO

28-8 81 Pump to A-AUTO

Train 8 Aux Air Compressor to AUTO

[Aux 8ldg, 734' elev, Refuel Floor]

START additional "A" Train ERCW

pumps as necessary.

ISOLATE non-essential ERCW loads as

necessary.

DO NOT CONTINUE UNTIL header

pressure and flow are adequate for

current alignment.

a.

GO TO step 14.

Page 75 of 142

c

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

RESPONSE NOT OBTAINED

(

2.10 ERCW Supply Header B Failure Upstream of ERCW Strainer Inlet Valves (cont'd)

13.

EVALUATE isolation of non-essential

Train A CCS heat loads

USING Appendix E, CCS Heat Load

Reduction.

14.

ENSURE all breakers opened

USING the following appendixes

Appendix F, Rx MOV Board ERCW

Valves

Appendix G, ERCW MCC Valves

15.

REFER TO the following:

Appendix B, Affected Equipment List

(Header 1B)

Appendix D, Affected Equipment List

(Header 2B)

Appendix P, Potential Tech Spec

Impacts.

16.

REFER TO AOP-M.03, Loss of

Component Cooling Water.

17.

GO TO appropriate plant procedure.

---a--

END OF SECTION

Page 76 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow [C.3]

RESPONSE NOT OBTAINED

NOTES

EOPs are not applicable if BOTH trains of ERCW are lost unless specifica lly

directed by this section,

This section takes priority over all other AOPs, Other AOPs should NOT be

performed concurrently except for AOP-T.01 (Security Events).

1,

ENSURE reactor TRIPPED: [M-4]

IF reactor CANNOT be tripped from MCR,

THEN

Reacto r trip breakers OPEN

DISPATCH operator to perform

one of the following:

Reactor trip bypass breakers OPEN

or DISC.QNNECTED

OPEN reactor trip breakers and

MG set output breakers locally.

Neutron flux DROPPING

[AB el. 759 MG Set Room]

Rod bottom lights LIT

Rod position indicators less than

OPEN MG set breakers at 480V Unit

or equa l to 12 steps.

Boards, [T8 el. 685 and 706]

2,

ENSURE turbine TRIPPED:

Turbine stop valves CLOSED.

3.

PLACE the following equipment

in STOP/PULL TO LOCK:

CCPs

Reactor Coolant Pumps

IF turbine CANNOT be tripped,

THEN

ENSURE MSIV and MSIV bypass valve

handswitches in CLOSE position.

Page 77 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOP-M .01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

4.

DEPRESS EMERGENCY STOP

pushbuttons for all diesel generators.

5.

MONITOR at least one shutdown board

energized from start bus.

6.

PLACE the following equipment switches

in PULL TO LOCK:

ERCW pumps

RHR pumps

Si pumps

Containment spray pumps

7.

NOTIFY 8M and STA to evaluate the

following:

EPIP-1, Emergency Plan

Classification Matrix

Tech Spec LCO 3.0.3, 3.7.4,

and 3.8.1.1

RESPONSE NOT OBTAINED

AITEMPT to restore power to

one shutdown board from start bus.

IF power CANNOT be immediately restored

to at least one shutdown board,

THEN

GO TO ECA-O.O, Loss of all AC Power.

Page 78 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

RESPONSE NOT OBTAINED

CAUTION 1

Temporary cooling water supply from HPFP to one CCP should be established

as soon as possible.

CAUTION 2

CCS for the unit NOT supplying SFP cooling will have a faster heatup rate.

Therefore, establishing temporary cooling to a CCP on the unit NOT supplying

th e SFP is more time critical.

8.

INITIATE temporary cooling to one CCP

and Station Air compressors:

a.

DETERMINE which CCP to install

temporary cooling water supply.

b.

DISPATCH operators to

PERFORM Appendix I, Temporary

Cooling to CCP Oil Coolers.

c.

DISPATCH operator to PLACE

Air Compressors in SAFE-STOP:

Station Air Compressors

Aux Air Compressors

d,

DISPATCH operator and Mechanical

Maintenance to perform

Appendix J, Temporary Cooling to

Station Air Compressors.

Page 79 of 142

(

saN

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

RESPONSE NOT OBTAINED

NOTE 1

NOTE 2

Appe ndix 0 contains two copies of handout pages identifying continuous action steps.

TO AFW Level Control Valves fail open on loss of air. LCVs may be operated from

main control room until essential air is lost.

9.

MONITOR RCS temperature:

a.

IF T-cold is less than 547°F

and dropping,

THEN

PERFORM the following:

1) ENSURE atmospheric relief valves

and s!eam dumps CLOSED.

(

2) CHECK TO AFW pump RUNNING

3) STOP and PULL-TO-LOCK

MO AFW pumps.

4) CONTROL AFW flow to

between 440 and 600 gpm:

ADJUST TO AFW speed

USING EA-3-1.

OPERATE TO AFW LCVs

as necessary

(if essential air available).

5) MAINTAIN total feed flow greater

than 440 gpm UNTIL narrow range

level is greater than 10% [25% AOV]

in at least one S/G.

b.

IF T-cold is greater than 552°F and rising,

THEN

DISPATCH operator to locally operate

S/G # 1 and 4 atmospheric relief valves

USING EA-1-2.

2) GO TO Step 10.

4) IF TO AFW flow CANNOT be adjusted,

THEN

DISPATCH AUO(s) to perform

EA-3-4, Local Alignment of

TO AFW LCV Backup Air Supply.

Pag e 80 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW fl ow (cont'd )

RESPONSE NOT OBTAINED

NOTE

The backup high pressure air bottles can provide four operations of each

TD AFW LCV after essential control air is lost.

10.

MONITOR AFW pump status:

a.

ENSURE TDAFW pump RUNNING.

b.

CONTROL TD AFW flow

USING EA-3-1, MCR Operation of TD

AFW Pump.

c.

DISPATCH AUO(s) to perform

EA-3-4, Local Alignment of

TD AFW LCV Backup Air Supply.

d.

WHEN backup air supply is depleted,

THEN

DISPATCH AUO(s) to locally operate

TDAFW LCVs USING Appendix L, Local

Control of Turbine Driven AFW LCVs.

e.

ENSURE MD AFW pumps STOPPED.

f.

MAINTAIN AFW flow

greater than 440 gpm UNTIL narrow

range level greater than 10% [25% ADV]

in at least one S/G

a. ENSURE MD AFW pumps supplying

AFW by performing the following:

1) ENSURE at least one MD AFW pump

RUNNING.

2) DISPATCH operator to locally control

MDAFW flow USING Appendix K.

3)

MAINTAIN total feed flow greater

than 440 gpm UNTIL narrow range

level is greater than 10% [25% ADV]

in at least one S/G.

4) GO TO Step 11.

Page 81 of 142

('

LOSS OF ESSENTIAL RAW COOLING WATER

AOP*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

11.

CONTROL S/G narrow range levels

between 10% [25% ADV]

and 50%:

CONTROL TO AFW pump speed

(if running),

CONTROL AFW LCVs.

12,

ENSURE Steamlines and Main

Feedwater ISOLATED:

a.

ENSURE MSIV handswitches in CLOSE

position.

b.

ENSURE MSIV bypass valves CLOSED,

c.

ENSURE MFW Isolation Valves

CLOSED.

d.

ENSURE Slowdown Isolation Valves

CLOSED.

RESPONSE NOT OBTAINED

IF S/G level is greater than 50%.

THEN

STOP AFW pumps as necessary.

NOTE

FRPs are not applicable. Shift Manager and TSC should be notified of any red or

orang e path conditions.

(

13.

MONITOR FR-O status trees

for information only.

Page 82 of 142

(

LOSS OF ESSENTIA L RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP

I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

14.

CHECK RCS ISOLATED:

RESPONSE NOT OBTAINED

a.

ENSURE Pressurizer PORVs CLOSED.

a. IF pressurizer pressure

less than 2335 psig,

THEN

CLOSE pressurizer PORVs.

b.

ENSURE Normal Letdown Valves

CLOSED:

FCV-62-69

FCV-62-70

FCV:!?2-72

FCV-62-73

FCV-62-74

c.

ENSURE Excess letdown isolation valves

CLOSED:

FCV-62-54

FCV-62-55

(

d.

VERIFY RCS and Pressurizer sample

valves CLOSED:

[status panels 6K and 6L]

FCV-43-3 or FCV-43-2

FCV-43-12 or FCV-43-11

FCV-43-23 or FCV-43-22

d. NOTIFY Chern Lab to CLOSE valves.

Page 83 of 142

(

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LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

(

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

15.

MAINTAIN RCS T-cold between 540'F

and 552'F USING Local Control of SIG

1 and 4 atmospheric relief valves:

DISPATCH personnel with radio to

perform EA-1-2, Local Control of S/G

PORVs.

16.

ISOLATE CST from hotwell to conserve

CST water for...AFW use:

a.

PLACE auto makeup to hotwell from

CST controller L1C-2-9 in MANUAL

and

CLOSE makeup valve.

b.

PLACE hotwell pump discharge to CST

dumpback controller L1C-2-3 in MANUAL

and

CLOSE dumpback valve.

c.

MONITOR hotwellievel stable or

dropping.

d.

ESTABLISH CST makeup as required.

RESPONSE NOT OBTAINED

c.

DISPATCH operator to locally isolate CST

from hotwell USING EA-2-1, Condenser

Makeup Isolation.

Page 84 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

(

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

17.

MONITOR containment vacuum relief

normal :

a.

CHECK containment pressure

less than 1.0 psig.

b.

VERIFY containment vacuum relief

isolation valves OPEN: [PaneI 6K]

FCV-30-46 OPEN

FCV-30-47 OPEN

FCV-30-4 8 OPEN.

18.

START one containment air return fan.

19.

ALIGN CCP suction to RWST:

a.

ENSURE RWST Suction Valves

LCV-62-135 AND LCV-62-136 OPEN.

b.

ENSURE VCT Outlet Valves

LCV-62-132 OR LCV-62-133 CLOSED.

RESPONSE NOT OBTAINED

a. GO TO Step 18.

b. OPEN valves [M-9]

Page 85 of 142

(-,

LOSS OF ESSENTIAL RAW COOLING WATER

AOP*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW now (cont'd)

RESPO NSE NOT OBTAINED

CAUTION

NOTE 1

NOTE 2

Restoring seal injection to hot RCP seals following loss of all seal cooling

could result in thermal shock to RCP seals. If all seal cooling has been

lost, RCP sea ls should be isolated PRIOR TO restarting a CCP.

CCS heatup rate will be slower for unit suppl ying Spent Fuel Pit cooling.

If RCP seal injection and thermal barrier flowpaths are isolated , subsequent

cool down of RCP seals will be accomplished later by RCS cooldown.

(

20.

MONITOR RCP seal cooling available:

a.

CHECK Train A CCS Outlet

temperature less than 130°F.

[TR-70-161]

a.

ISOLATE Thermal Barrier Cooling

by performing the following :

1)

STOP Thermal Barrier Booster Pumps

on affected Unit AND

PLACE in PULL-TO-LOCK.

2)

CLOSE Thermal Barrier Valves:

FCV-70-133 0r1 34

FCV-70-87 or 90

3)

STOP CCS pumps A-A and B-B

on affected Unit and

PLACE in PULL*TO-LOCK.

4)

STOP CCS pump CoS and

PLACE in PULL*TO-LOCK.

5)

GO TO Substep 20.b.......

(step continued on next page)

Page 86 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev . 15

STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

20.

b.

CHECK RCP seal cooling flow

in service:

CCP running and supplying RCP

Seal Injection flow

Thermal barrier cooling in service.

RESPONSE NOT OBTAINED

b. IF Thermal barrier Cooling

AND RCP seal injection flow are lost.

THEN

PERFORM the following:

1) DISPATCH operator to locally isolate

RCP seals by performing Appendix N,

Local Isolation of RCP Seal Injection.

2) CLOSE FCV-62-61 or

FCV-62-63. [M-5]

Page 87 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

RESPONSE NOT OBTAINED

CAUTION

If thermal barrier cooling is NOT in service, restarting CCP prior to

locally isolating seal injection flowpath (Appendix N) could result in

thermal shock to seal package.

21.

MONITOR if CCP can be started:

a.

CHECK temporary cooling water supply

a. WHEN temporary cooling water is

to CCP oil coolers establis hed.

established to CCP,

THEN

PERFORM Substeps 21.b through f.

GO TO Step 22.

b.

CHECK RCP Thermal Barrier Cooling

in service.

c.

START CCP supplied by temporary

cooling water.

d.

DISPATCH operator to locally

control charging flow USING

VLV-62-535 or VLV-62-536

(B-B CCP room).

e.

MONITOR CCP bearing and motor

windi ng temperatures.

b. WHEN seal injection flowpath

is isolated (Appendix N).

THEN

PERFORM Substeps 21.c through f.

GO TO Step 22.

(step continued on next page)

Page 88 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP

I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

21.

f.

CONTROL CCP flow:

1) CHECK CCPIT valves CLOSED.

2) CHECK seal injection flowpath

available.

3) ENSURE FCV-62-90 and FCV-62-91

CLOSED.

4) ADJUST seal injection flow

to maintain between 6 and 13 gpm

USING one of the following:

FCV-62-93 (if control air available)

local control (VLV-62-535 or

VLV-62-536).

RESPONSE NOT OBTAINED

1) GO TO Step 22.

2)

ESTABLISH Normal Charging flowpath :

a) ENSURE FCV-62-90 AND FCV-62-91

OPEN.

b) ADJUST charging flow USING

FCV-62-93 (if control air available)

or Local control to maintain

Pressurizer level.

c)

GO TO Step 22.

Pag e 89 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

(

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (co nt'd)

22.

MONITOR pressurizer pressure:

a.

Pressurizer pressure

between 2210 and 2260 psig.

RESPONSE NOT OBTAINED

a.

IF pressure less than 2210 psig

and dropping,

THEN

PERFORM the following:

1)

ENSURE pressurizer PORVs

CLOSED.

IF pressurizer PORV

CANNOT be closed ,

THEN

CLOSE associated block valve .

2)

IF SI signal is NOT actuated,

THEN

ENSURE all available

pressurizer heaters ON.

b.

IF pressure greater than 2260 psig

and rising.

THEN

PERFORM the followi ng:

1)

ENSURE all pressurizer

heaters OFF.

2)

ENSURE pressure controlled

USING pressurizer PORV(s).

Page 90 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev.

15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flo w (cant'd)

23.

MAINTAIN pressurizer level

between 20% [35% ADV] and 65%:

a.

CONTROL charging flow to maintain

pressurizer level.

b.

OPERATE Reactor Vessel Head Vents

as necessary to maintain pzr level

between 20% [35% ADVj and 65%:

1) OPEN head vent block valve

FSV-68-394 OR FSV-68-395.

2) OPEN head vent throttle valve

FSV-68-396 OR FSV-68-397.

3) WHEN desired pzr level is achieved,

THEN

CLOSE Head Vent Valves.

RESPONSE NOT OBTAINED

a. IF low pressurizer level is the result of

RCS cooldown,

THEN

STOP RCS cooldown.

IF NO CCP is running,

THEN

GO TO Step 24.

Page 91 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

24.

MONITOR if RCS cooldown

should be started:

a.

CHECK Pressurizer level

greater than 10% [20% ADV].

b.

VERIFY Natural Circulation

USING EA-68-6, Monitoring Natural

Circulation Conditions.

c.

NOTIFY TSC (when staffed) to

perform Appendix M. TSC Actions in

event of loss of ERCW.

d.

DO NOT CONTINUE

UNTIL CCP has been started.

e.

GO TO Step 39 to initiate

plant cooldown .

RESPONSE NOT OBTAINED

a.

IF pzr level CANNOT be maintained

greater than 10% [20% ADV].

THEN

PERFORM the following:

1) INITIATE SI signal.

2) GO TO Step 25 to initiate

RCS cooldown and depressurization.

=--

Page 92 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

I STEP I

ACTIONIEXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

RESPONSE NOT OBTAINED

CAUTION

NOTE

Allowing RCS pressure to drop below 100 psig prior to isolating CLAs

could result in nitrogen injecti on into the RCS.

Cooldown rate should be maintained as close to 1OO' Flhr as possible.

(

25.

DEPRESSURIZE Intact SIGs

to reduce RCS pressure to

less than 200 psig:

a.

MAINTAIN at least one S/G

narrow range level

greater than 10% [25% ADV].

b.

MAINTAIN T*cold cooldown rate

less than 100'Flhr.

c.

DUMP steam from Intact SIGs

USING atmospheric reliefs.

d.

WHEN RCS pressure

between 100 psig and 200 psig,

THEN

STOP cooldown and

MAINTAIN current plant conditions.

a. PERFORM the following:

1) CONTROL atmospheric reliefs

to stop SIG depressurization.

2) MAINTAIN maximum AFW flow

UNTIL level greater than 10%

[25% ADV] in at least one SIG.

3) WHEN level greater than 10%

[25% ADVj in at least one S/G ,

THEN

PERFORM Substeps 25.b., 25.c.

and 25.d.

4) GO TO Step 26.=--

c.

DUMP steam from Intact SIGs

USING EA*1*2, Local Control of SIG

PORVs.

Page 93 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOP*M.01

Rev.

15

(

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flo w (cont'd)

26.

RESET SI signal after 60 second

time delay.

27.

VERIFY the following ESF actuations:

a.

CCPIT valves aligned:

FCV*63-25 and FCV-63-26 OPEN

FCV-63-39 and FCV-63-40 OPEN

FCV-62-90 and FCV-62*91 CLOSED.

b.

Containment Ventilation Isolation

dampers CLOSED:

Panel 6K CNTMT VENT GREEN

Panel 6L CNTMT VENT GREEN.

c.

Phase A valves CLOSED:

Panel 6K PHASE A GREEN

Panel 6L PHASE A GREEN.

RESPONSE NOT OBTAINED

b.

PERFORM the following:

1) ACTUATE PHASE A AND CNTMT

VENT ISOL.

2) ENSURE dampers CLOSED.

3) NOTIFY TSC to determine corrective

action for dampers without power or

indication.

c.

PERFORM the following:

1) ACTUATE PHASE A.

2) ENSURE valves CLOSED.

3) NOTIFY TSC to determine corrective

action for dampers without power or

indication.

Page 94 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

(

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

28.

MONITOR Phase B status:

Phase B NOT ACTUATED

Containm ent pressure

less than 2.81 psig.

29.

CHECK reactor SUBCRITICAL:

IRM startup rate zero or negative

SRM startup rate zero or negative.

RESPONSE NOT OBTAINED

PERFORM the following:

a.

ENSURE PHASE B ACTUATED.

b.

ENSURE Phase B valves CLOSED:

Panel 6K PHASE B GREEN

Panel 6L PHASE B GREEN.

c.

RESET Containment Spray.

CONTROL atmospheric reliefs

to stop S/G depressurization.

ALLOW RCS to heat up.

Page 95 of 142

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

30.

CHECK whether cooldown

should be stopped:

a. CHECK RCS pressure between

100 psig and 200 psig.

b. STOP S/G depressurization.

c.

ISOLATE CLAs:

1) DISPATCH personnel to restore

power to CLA isolation valves

USING EA-201-1, 480V Board

Room Breaker Alignments.

2) CLOSE CLA isolation valves.

3) NOTIFY local personnel to

remove power to CLA isolation

valves USING EA-201-1, 480 V

Board Room Breaker Alignments.

31.

CHECK CCP in service.

32.

CHECK Core Exit TCs

less than 1200°F.

RESPONSE NOT OBTAIN ED

a. CONTINUE depressurization until RCS

between 100 psig and 200 psig.

NOTIFY TSC to EVALUATE operating one

RHR pump to restore pressurizer level.

IF at least 5 core exit TCs

greater than 12000F AND rising,

THEN

GO TO SACRG-1, Severe Accident Control

Room Guideline Initial Response

---.--

Pag e 96 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

(

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

33.

CHECK CCPIT flow NOT required:

a.

RCS subcooling based on core exit T/Cs

greater than 40'F.

b.

Secondary heat sink:

Narrow range level in at least one

S/G greater than 10% [25% ADV].

OR -

Total feed flow to S/Gs

greater than 440 gpm.

RESPONSE NOT OBTAINED

IF criteria NOT met,

THEN

GO TO Step 29.

c.

d.

RCS pressure stable or rising.

Pressurizer level

greater than 10% [20% ADV].

l

34.

ENSURE CCPIT ISOLATED:

CLOSE inlet isolation valves

FCV-63-39 and FCV-63-40.

CLOSE outlet isolation valves

FCV-63-26 and FCV-63-25.

Page 97 of 142

c

LOSS OF ESSENTIAL RAW COOLING WATER

AOP*M.01

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

35.

ESTABLISH charging flow:

a.

OPEN charging flow isolation valves

FCV-62-90 and FCV-62-91.

b.

CHECK alternate or normal charging

isolation valve FCV-62-85 or

FCV-62-86 OPEN.

c.

ADJUST FCV-62-93 OR

locally control manual valves

(VLV-62-535 OR VLV-62-536)

as neces sary to maintain pzr level.

36.

MONITOR ECCS flow NOT required:

Pressurizer level is maintained

greater than 10% [20% ADV]

RCS subcooling based on core exit

TICs greater than 40'F.

RESPONSE NOT OBTAINED

IF ECCS flow is required,

THEN

PERFORM the following:

1) OPEN CCPIT valves:

FCV-63-25 AND FCV-63-26

FCV-63-39 AND FCV-63-40.

2) CLOSE charging valves:

FCV-62-90 AND FCV-62-91.

3) GO TO Step 29.

-_.....

Page 98 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

(

I STEP I

ACTION /EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

37.

MAINTAIN pressurizer level

between 20% [35% ADV] and 65%:

a.

CONTROL charging flow to maintain

pressurizer level.

b.

OPERATE Reactor Vessel Head Vents

as necessary to maintain pressurizer

level between 20% [35% ADV] and 65%:

1) OPEN head vent block valve

FSV-68-394 OR FSV-62-395 .

2) OPEN head vent throttle valve

FSV-68-396 OR FSV-68-397 .

3) WHEN desired Pzr level is achieved,

THEN

CLOSE Head Vent Valves.

38.

GO TO Step 48.

Page 99 of 142

RESPONSE NOT OBTAINED

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev.

15

(

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

39.

EMERGENCY BORATE RCS to cold

shutdown boron concentration

USING EA-68-4. Emergency Boration.

40.

INITIATE RCS cooldown to Mode 4:

a.

MAINTAIN T-cold cooldown rate

less than 50*F/hr.

b.

DUMP steam USING atmospheric

relief(s).

c.

MAINTAIN 5/G narrow range level

between 10% [25% ADV] and 50%.

d.

MAINTAIN RCS T-cold and pressure

within limits USING Tech Spec

temperature/pressure limit curves.

41.

DEPRESSURIZE RCS to 1920 psig

to permit SI block:

a. DEPRESSURIZE RCS to 1920 psig

USING one pressurizer PORV.

b.

BLOCK 51 signals:

Low pressurizer pressure SI

Low steamline pressure SI.

c. MAINTAIN RCS pressure

less than 1920 psig.

RESPONSE NOT OBTAINED

c. CONTROL feed flow as necessary.

Page 100 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

42.

MONITOR RCS cooldown:

Core exit TICs DROPPING

T-hot DROPPING

RCS subcooling RISING

(based on core exit T/Cs).

43.

INITIATE RCS depressurization:

a.

MAINTAIN RCS subcoclinq based on

core exit-T/Cs greater than 140' F.

b.

REFER TO ES-O.2 Curve 3 (Curve 4),

Natural Circulation Cooldown NO CRDM

Fans Running - 140' F Subcooling.

c.

INITIATE RCS depressurization

USING one pressurizer PORV.

44.

CONTINUE RCS cooldown and

depressurization:

a.

MAINTAIN T-cold cooldown rate

less than 50' F/hr.

b.

MAINTAIN RCS subcooling based on

core exit T/Cs greater than 140' F.

c.

MAINTAIN RCS T-cold and pressure

within limits USING Tech Spec

temperature/pressure limit curves.

RESPONSE NOT OBTAINED

a. STOP RCS depressurization and

ESTABLISH required subcooling.

b. STOP RCS depressurization and

ESTABLISH required subcoolinq,

Page 101 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

RESPONSE NOT OBTAINED

NOTE

"Unexpected pressurizer level changes indicative of vessel voiding" is defined

as an unexplained level rise when reducing RCS pressure OR an unexplained

level drop when raising RCS pressure.

(

45.

MONITOR for steam voids

in reactor vessel:

a. CHECK for the following indications

of steam voids:

unexpected pressurize r level

changes indicative of voiding

RVLlS upper plenum range

less than 104%.

b. REPRESSURIZE RCS within limits of

Tech Spec temperature/pressure limit

curves to collapse voids in system

and CONTINUE cooldown.

a.

GO TO Step 46.

l

46.

WHEN RCS pressure

less than 1000 psig.

THEN

ISOLATE CLAs:

a.

DISPATCH personnel to restore power to

CLA isolation valves USING EA-201-1,

480V Board Room Breaker Alignments.

b.

CLOSE CLA isolation valves.

c.

NOTIFY local personnel to remove power

to CLA isolation valves USING EA-201-1 ,

480 V Board Room Breaker Alignments.

Page 102 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

RESPONSE NOT OBTAINED

CAUTION

The up per head should be allowed to cool for a minimum of BB hours

prior to complete depressurization of the RCS.

47.

MAINTAIN plant conditions stable:

RCS subcoolinq based on

core exit T/Cs greater than 100' F

Pzr level between 20% [35% ADV]

and 65%

Intact S/G narrow range levels

between_10% [25% ADV]

and 50%.

48.

ENSURE TSC notified (when staffed)

to perform Appendix M, TSC Actions in

event of loss of ERCW.

49.

SHUT DOWN unnecessary plant

equipment:

REFER TO 0-GO-12 , Realignment of

Secondary Equipment Following

ReactorlTurbine Trip.

Page 103 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I

ACTION/EXPECTED RESPONSE

2.11 Loss of all ERCW flow (cont'd)

50.

ENSURE RCS BORATED for natu ral

circulation cool down to cold shutdown

conditions USING EA-68-4, Emergency

Boration.

51.

WHEN sufficient ERCW available to

support plant cooldown,

THEN

EVALUATE plant cooldown to Mode 5.

RESPONSE NOT OBTAINED

END OF SECTION

Page 104 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

3.0

SYMPTOMS AND ENTRY CONDITIONS

3.1

Symptoms

A.

Any of the following annunciators may indicate a failure in the ERCW system:

PANEL XA-55-27A, ERCW

A-1

UNIT 1 HEADER A PRESSURE LOW

A-4

UNIT 1 HEADER 8 PRESSURE LOW

8-1

PUMP J-A DISCH PRESS LOW

8-2

PUMP R-A DISCH PRESS LOW

8-3

UNIT 2 HEADER A PRESSURE LOW

8-4

PUMP M-8 DISCH PRESS LOW

8-5

PUMP L-8 DISCH PRESS LOW

8-6

-

UNIT 2 HEADER 8 PRESSURE LOW

C-1

PUMP K-A DISCH PRESS LOW

C-2

PUMP Q-A DISCH PRESS LOW

C-3

UNIT 2 HEADER 2A-A STRAINER DIFF PRESS HIGH

C-4

PUMP N-8 DISCH PRESS LOW

C-5

PUMP P-8 DISCH PRESS LOW

C-6

UNIT 2 HEADER 28-8 STRAINER DIFF PRESS HIGH

D-1

ERCW 480V MCC 1A-A OR 2A-A UNDERVOLTAGE

D-2

HEADER 1A-A STRAINER DIFF PRESS HIGH

D-4

ERCW 480V MCC 18-8 OR 28-8 UNDERVOLTAGE

D-5

HEADER 18-8 STRAINER DIFF PRESS HIGH

XA-55-27B-A, ERCW/CCS

E-3

ERCW PUMP MOTOR OVERLOAD

E-4

ERCW/CCS PUMP MOTOR TRIP

Page 105 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

3.1 Symptoms (cont'd)

XA-55-27B-B, CCS

0-3

I

HX 1-A1/1-A2 OUTLET TEMPERATURE HIGH

XA-55-27B-D, CCS

C-1

HX 0-81/0-82 OUTLET TEMPERATURE HIGH

0-3

HX 2-A1/2-A2 OUTLET TEMPERATURE HIGH

1-XA-55-15A, ERCW/CCW/FIRE PROTECTION

8-6

I

LS-40-720 MECH EQUIP SUMP LVL HI

1-XA-55-15B, ERCW/CCW/FIRE PROTECTION

A-3

I

O-LS-40-81D ERCW DECK SUMP LEVEL HI

XA-55-5C, VENTILATION

8-3

MS-30-241 LOWER COMPT MOISTURE HI

B-4

MS-30-240 UPPER COMPT MOISTURE HI

B. Any of the following parameters may indicate a failure of the ERCW system:

1.

ERCW header A or B indicates low pressure on PI-67-493A or PI-67-488A.

2.

ERCW Pump discharge pressure indicates low.

PI-67-433A, Pump J-A

PI-67-437A. Pump K-A

PI-67-461A, Pump Q-A

PI-67-465A. Pump R-A

PI-67-441A. Pump L-B

PI-67-445A, Pump M-B

PI-67-453A, Pump N-B

PI-67-457A, Pump P-B

Page 106 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOP-M .01

Rev. 15

(

3.1 Symptoms (cont'd)

3.

ERCW supply header high or low flow .

1-FI-67-61 , Hdr 1A

1-FI-67-62, Hdr 1B

2-FI-67-61, Hdr 2A

2-FI-67-62, Hdr 2B

4.

Indication of flooding in the Reactor, Auxiliary, or Turbine Buildings.

5.

Visua l indication of an ERCW pip ing rupture.

3.2 Entry Conditions

AOP-T.01

Page 107 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOP-P.01 , Loss of Offsite Power

Rev.

15

(

4.0

REFERENCES

4.1

Performance

A.

EPIP-1, Emergency Plan Classification Matrix

B.

E-O, Reactor Trip or Safety Injection

C.

AOP-M.03, Loss of Component Cooling Water

D.

E.

AOP-R.04, Reactor Coolant Pump Malfunctions

F.

TI-28, Curve Book

G.

1(2)-SO-2/3-1, Condensate and Feedwater System

H.

0-SO-1-2, Steam Dump System

J.

1(2)-SO-5-1, Feedwater Heaters and Moisture Separator Reheaters

I.

0-GO-1 2, Realignment of Secondary Equipment Following ReactorlTurbine Trip

K.

0-GO-6, Power Reduction From 30% Reactor Power to Hot Standby

4.2

Plant Drawings

A.

47W805-1

B.

1(2)-47W803-1

C.

1(2)-47W804-1

D.

45N647-1

E.

45N601-1

Page 108 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX A

AFFECTED EQUIPMENT LIST (HEADER 1A)

AOp*M.01

Rev. 15

Page 1 of 1

1.

Centrifugal Charging Pump 1A Oil Cooler (Note 1)

2.

Safety Injection Pump 1A Oil Cooler (Note 1)

3.

Auxiliary and Control Air Compressor A (Note 1)

4.

Station Service Air Compressors and Space/Room Cooling Equipment (Note 2)

5.

Lower Containment Coolers 1A and 1C (Note 3 & 4)

6.

Upper Containment Coolers 1A and 1C (Note 3 & 4)

7.

Control Rod Drive Vent Coolers 1A and 1C (Note 3 & 4)

8.

Instrument Room Cooler 1A (Note 3 & 4)

9.

Main Control Room AlC Condenser A (Note 4)

10.

Electric Board Room AlC Condenser A (Note 4)

11.

Shutdown Board Room AlC Chiller A (Note 4)

12.

Containment Spray Heat Exchanger 1A (Note 5)

13.

Turbine AFW Pump 1A-S Emergency Suction (Note 5)

14.

Motor Driven AFW Pump 1A Emergency Suction (if return header A is out-of-service)

(Note 5)

15.

Unit 1 RCP Motor Coolers 1 and 3 (Note 6)

l

Note 1 :

Note 2 :

Note 3 :

Note 4:

Note 5 :

Note 6 :

Damage is imminent unless equipment is stopped.

Stop equipment if ERCW supply from 1B is not available.

Containment parameters may increase due to inadequate cooling.

Start redundant equipment and secure affected components.

ERCW not normally required.

REFER TO AOP-R.04, Reactor Coolant Pump Malfunctions, if alarming.

Page 109 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATE R

APPENDIX 8

AFFECTED EQUIPMENT LIST (HEADER 18)

AOP-M .01

Rev. 15

Page 1 of 1

1.

Centrifugal Charging Pump 1B Oil Cooler (Note 1)

2.

Safely Injection Pump 1B Oil Cooler (Note 1)

3.

Station Service Air Compressors and Space/Room Cooling Equipment (Note 2)

4.

Lower Containment Coolers 1B and 1D (Note 3 & 4)

5.

Upper Containment Coolers 1Band 1D (Note 3 & 4)

6.

Control Rod Drive Vent Coolers 1Band 10 (Note 3 & 4)

7.

Instrument Room Cooler 1B (Note 3 & 4)

8.

Main Control Room AlC Condenser B (Note 4)

9.

Electric Board Room AlC Condenser B (Note 4)

10.

Shutdown Board Room AlC Chiller B (Note 4)

11.

Containment Spray Heat Exchanger 1B (Note 5)

12.

Turbine AFW Pump 1A-S Emergency Suction (Note 5)

13.

Motor Driven AFW Pump 1B Emergency Suction (if return header B is out-of-service)

(Note 5)

14.

Unit 1 RCP Motor Coolers 2 and 4 (Note 6)

Note 1 :

Note 2 :

Note 3 :

Note 4 :

Note 5 :

Note 6 :

Damage is imminent unless equipment is stopped.

Stop equipment if ERCW supply from 1A is not available.

Containment parameters may increase due to inadequate cooling.

Start redundant equipment and secure affected components.

ERCW not normally required.

REFERTO AOP-R.04, Reactor Coolant Pump Malfunctions, if alarming.

Page 110 of 142

c

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX C

AFFECTED EQUIPMENT LIST (HEADER 2A)

Rev. 15

Page 1 of 1

1.

Centrifugal Charging Pump 2A Oil Cooler (Note 1)

2.

Safety Injection Pump 2A Oil Cooler (Note 1)

3.

CCS Heat Exchangers 1A1/1 A2 and 2A1/2A2 (Note 2)

4.

Lower Containment Coolers 2A and 2C (Note 3 & 4)

5.

Upper Containment Coolers 2A and 2C (Note 3 & 4)

6.

Control Rod Drive Vent Coolers 2A and 2C (Note 3 & 4)

7.

Instrument Room Cooler 2A (Note 3 & 4)

8.

Space and room cooling equipment (Note 4)

9.

Containment Spray Heat Exchanger 2A (Note 5)

10.

Turbine AFW Pump 2A-S Emergency Suction (Note 5)

11 .

Motor Driven AFW Pump 2A Emergency Suction (if return header A is out-of-service)

(Note 5)

12.

Unit 2 RCP Motor Coolers 1 and 3 (Note 6)

c..

Note 1 :

Note 2 :

Note 3 :

Note 4 :

Note 5:

Note 6 :

Damage is imminent unless equipment is stopped.

Monitor RCPs for TRIP criteria. Multiple systems affected.

REFER TO AOP-M.03, Loss of Component Cooling Water.

Containment parameters may increase due to inadequate cooling.

Start redundant equipment and secure affected components.

ERCW not normally required.

REFER TO AOP-R.04, Reactor Coolant Pump Malfunctions, if alarming.

Page 111 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX D

AFFECTED EQUIPMENT LIST (HEADER 28)

AOP*M.01

Rev. 15

Page 1 of 1

1.

Centrifugal Charging Pump 2B Oil Cooler (Note 1)

2.

Safety Injection Pump 2B Oil Cooler (Note 1)

3.

Auxiliary and Control Air Compressor B (Note 1)

4.

CCS Heat Exchangers OB1 /0B2 (Note 2)

5.

Lower Containment Coolers 2B and 2D (Note 3 & 4)

6.

Upper Containment Coolers 2B and 2D (Note 3 & 4)

7.

Control Rod Drive Vent Coolers 2B and 2D (Note 3 & 4)

8.

Instrument Room Cooler 2B (Note 3 & 4)

9.

Space and room cooling equipment (Note 4)

10.

Containment Spray Heat Exchanger 2B (Note 5)

11.

Turbine AFW Pump 2A-S Emergency Suction (Note 5)

12.

Motor Driven AFW Pump 2B Emergency Suction (if return header B is out-of-service)

(Note 5)

13.

Unit 2 RCP Motor Coolers 2 and 4 (Note 6)

(

Note 1 :

Note 2 :

Note 3:

Note 4 :

Note 5 :

Note 6 :

Damage is imminent unless equipment is stopped.

Multiple systems affected.

REFER TO AOP-M.03, Loss of Component Cooling Water.

Containment parameters may increase due to inadequate cooling.

Start redundant equipment and secure affected components.

ERCW not normally required.

REFER TO AOP-R 04, Reactor Coolant Pump Malfunctions, if alarming.

Page 112 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX E

CCS HEAT LOAD REDUCTION [C.1]

AOP-M .01

Rev. 15

Page 1 of 1

The Unit US/SRO shall determine which CCS equipment should be isolated or shutdown to reduce the

heat load on Train A CCS Heat Exchangers. The loads listed below are in the order of least severe to

most severe plant impact. (1-47W859-2 and 2-47W859-3)

c..

1.

Waste Gas Compressors

2.

Sample Heat Exchangers

3.

Post-Accident Sample Coolers

4.

Hot Sample Chillers

5.

Excess Letdown Heat Exchanger

6.

Spent Fuel Pit Heat Exchangers

7.

RCP Thermal Barrie rs

8.

Letdown Heat Exchanger

9.

Seal Water Heat Exchanger

10.

RCP Upper & Lower Oil Coolers

70-51 8, INLET (690, by drto WGC)70-520, OUTLET (690, by dr to WGC)70-573, INLET (690, Outside RHR Hx Rm)

FCV-70-183, RETURN

70-766, INLET (706. PASFarea)

SAME AS SAMPLE HX

FCV-70-143, INLET

FCV-70-85, OUTLET

O-FCV-70-40, 41 INLETS

O-FCV-70-1 , 11 OUTLETS

FCV-70-133,134 INLETS

FCV-70-87,90 OUTLETS70-574 , INLET (714, Near Letdown Hx Rm)70-581 , INLET (690, Outside RHR Hx Rm)70-585, OUTLET (690, Outside Seal Water Hx Rm)

FCV-70-139,140,141 INLETS

FCV-70-89, 92 OUTLETS

Page 1130f 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX F

RX MOV BOARD ERCW VALVES

Rev. 15

Page 1 of 2

NOTE 1

NOTE 2

When power is placed on the following valves, record lime breaker is closed and

opened in the narrative log. An operator shall remain at the breaker and in contact with

the MCR while power is on. If a fire develops, position the valve(s) as required and

remove power.

Breakers for Appendix R valves 1,2-FCV-67-22 and 24 are locked.

(

PERFORM the following:

a.

TRANSFER control power to AUXILIARY.

b. CLOSE breakers.

c.

NOTIFY Unit Operator to log Appendix R breakers CLOSED.

d. STAND BY for direction from Control Room to manipulate valves.

e.

OPEN breakers when directed by the Control Room.

f.

NOTIFY Unit Operator to log Appendix R breakers OPEN.

BREAKER

VALVE NAME

VALVE NUMBER

Rx MOV Bd 1A2-A CampI. 3A

ERCW Strainer 1A-A 1501 Valve

1-FCV-67-22

Rx MOV Bd 1A2-A CampI. 3C

Aux Bldg Hdr 1A Isol Valve

1-FCV-67-81

Rx MOV Bd 1A2-A CampI. 7A

Hdr 1A Supply to Space Coolers,

1-FCV-67-127

AlC, & Air Compressors

Rx MOV Bd 1A2-A CampI. 8B

Hdr 1B to Hdr 2A Isol Valve

1-FCV-67-223

Rx MOV Bd 1A2-A CampI. 9A

Hdr 1A to Hdr 2B Isol Valve

1-FCV-67-147

Rx MOV Bd 1A2-A Cornpt. 9B

Hdr 1B to Hdr 2A CCS HX Isol Valve

1-FCV-67-424

Rx MOV Bd 1A2-A CampI. 80

CCS HX OB1/0B2 Disch Valve to Hdr

O-FCV-67-151

A

Rx MOV Bd 1B2-B CampI. 3A

ERCW Strainer 1B-B Isol Valve

1-FCV-67-24

Rx MOV Bd 1B2-B CampI. 3C

Aux Bldg Hdr 1B Isol Valve

1-FCV-67-82

Rx MOV Bd 1B2-B CampI. 6C

Hdr 1B Supply to Space Coolers,

1-FCV-67-128

AlC, & Air Compressors

(

Page 114 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX F

RX MOV BOARD ERCW VALVES

Rev. 15

Page 2 of 2

NOTE

When power is placed on the following valves , record time breaker is closed and

opened in narrative log. An operator shall remain at the breaker and in contact with

MCR while power is on. If a fire develops, position valve(s) as required and remove

power.

r:

(,

PERFORM the following :

a.

TRA NSFER control power to AUXILIARY

b.

CLOSE breakers

c.

NOTIFY Unit Operator to log Appendix R breakers CLOSED

d.

STAND BY for direction from Control Room to manipulate valves.

e.

OPEN breakers Whendirected by the Control Room.

f.

NOTIFY Unit Operator to log Appendix R breakers OPEN.

BREAKER

VALVE NAME

VALVE NUMBER

Rx MOV Bd 2A2-A Compl. 3A

ERCW Strainer 2A-A Isol Valve

2-FCV-67-22

Rx MOV Bd 2A2-A Compt. 3C

Aux 81dg Hdr 2A Isol Valve

2-FCV-67-81

Rx MOV Bd 2A2-A Compt. 7A

Hdr 2A Supply to Space Coolers,

2-FCV-67-127

AlC, & Air Compressors

Rx MOV Bd 2A2-A Compl. 8B

Hdr 2A to Hdr 1B Isol Valve

2-FCV-67-223

Rx MOV 8d 282-B Cornpt, 3A

ERCW Strainer 2B-8 Isoi Valve

2-FCV-67-24

Rx MOV 8d 282-B CompI. 38

Hdr 28 to Hdr 1A Isol Valve

2-FCV-67-147

Rx MOV 8d 282-B Compl. 3C

Aux Bldg Hdr 28 Isol Vaive

2-FCV-67-82

Rx MOV Bd 282-B Compl. 6C

Hdr 28 Supply to Space Coolers,

2-FCV-67-128

AlC, & Air Compressors

Page 115 of 142

(

saN

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIXG

ERCW MCC VALVES

Rev. 15

Page 1 of 1

NOTE

When power is placed on the following valves , record time breaker is ciosed and

opened in narrative log. An operator shall remain at the breaker and in contact with

MCR while power is on. If a fire develops , position valve(s) as required and remove

power.

PERFORM the following:

a.

TRANSFER control power to AUXILIARY

b.

CLOSE breakers

c.

NOTIFY Unit Operator to log Appendix R breakers CLOSED

d.

STAND BY for direction from Control Room to manipulate valves.

e.

OPEN breakers when directed by the Control Room.

e

f.

NOTIFY Unit Operator to log Appendix R breakers OPEN.

BREAKER

ERCW MCC 1M Compl. 3C

ERCW MCC 1B-B Compt. 3C

ERCW MCC 2A-A CompI. 3C

ERCW MCC 2B-B Compl. 3C

VALVE NAME

Hdr 1A Isol Before Strainer

Hdr 1B Isol Before Strainer

Hdr 2A Isol Before Strainer

Hdr 2B Isol Before Strainer

Page 116 of 142

VALVE NUMBER

1-FCV-67-492

1-FCV-67-489

2-FCV-67-492

2-FCV-67-489

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX H

DIESEL AUXILIARY BOARD APPENDIX R VALVES

Rev. 15

Page 1 of 1

NOTE

When power is placed on Appendix R valves record time breaker is closed and opened

in narrative log.

An operator shail remain at the breaker and in contact with MCR while

power is on. If a fire develops , position valve(s) as required and remove power.

(

PERFORM the foliowing:

a.

TRANSFER control power to AUXILIARY

b.

CLOSE breakers

c.

NOTIFY Unit Operator to log Appendix R breakers CLOSED

d.

STAND BY for direction from Control Room to manipulate vaives.

e.

OPEN breakers when directed by the Control Room.

f.

NOTIFY Unit Operator to log Appendix R breakers OPEN.

BREAKER

VALVE NAME

VALVE NUMBER

Diesel Aux Bd 2A2-A Compl. 3C

Hdr A Discharge to

O-FCV-67-12

Cold Water Channel Isol

Diesel Aux Bd 2A2-A Compl. 4B

Hdr B Discharge to

O-FCV-67-365

Cold Water Channel Isol

Diesel Aux Bd 2B2-B Compl. 3C

Hdr B Discharge to

O-FCV-67-14

Cold Water Channel Isol

Diesel Aux Bd 2B2-B Compl. 4B

Hdr A Discharge to

O-FCV-67-364

Cold Water Channel Isoi

Page 117 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX I

Page 1 of 7

Installation of Temporary Cooling (HPFP) to CCP Oil Coolers

Rev. 15

CAUTION

This appendix should be completed as quickly as possible. Normal

RADCON requirements may be waived to expedite installation of temporary

cooling.

NOTE 1

If the accountability siren sounds, operator should continue performing this

appendix. The SM should be aware of task assignments and personnel

locations .

NOTE 2

Temporary cooling to the CCP oil coolers is accomplished by installing a hose

connection from a HPFP hose station to the oil heat exchangers on the CCP

pump skid. This appendix requires removal of a portion of the permanent ERCW

supply piping to the Bearing Oil Heat Exchanger to allow hookup of the

temporary hoses.

NOTE 3

Fire hose lengths, pre-fabricated tee connections and tools required for hookup

are maintained in the EOI/AOP supply box on Aux Bldg el 669' (next to door for

HUT BRoom).

[1]

DETERMINE which CCP to connect temporary cooling: (NA pump not connected)

A-ACCP

B-B CCP

D

[2]

OBTAIN fire hoses (two 50 ft sections), 4 foot red rubber hose, tee connection

and tools from EOI/AOP Storage Locker. [AB el 669, next to HUT B Room door]

D

l

[3]

CLOSE ERCW Supply Valve to CCP Oil Cooler. (NA valve not operated)

Pump

Valve ID

Description

Position

A-ACCP

VLV-67-704A

ERCW Sup A-A CCP Oil Cooler

CLOSED D

B-B CCP

VLV-67-704B

ERCW Sup B-B CCP Oil Cooler

CLOSED D

Page 118 of 142

(

'.

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX I

Page 2 of 7

AOp*M.01

Rev. 15

[4]

CLOSE ERCW Return Valve to CCP Oil Cooler. (NA valve not operated)

Pump

Valve 10

Description

Position

A-ACCP

VLV-67-705A

ERCW Ret A-A CCP Oil Cooler

CLOSED 0

B-B CCP

VLV-67-705B

ERCW Ret B-B CCP Oil Cooler

CLOSED 0

[5]

REMOVE Drain plug and OPEN ERCW Drain Valve to CCP Oil Cooler.

(NA valve not operated)

.

Pump

Valve ID

Description

Position

A-ACCP

VLV-67-1547A

ERCW Drain A-A CCP Oil Cooler

OPEN 0

B-B CCP

VLV-67-1546B

ERCW Drain B-B CCP Oil Cooler

OPEN 0

NOTE

Piping is identified with ID tags at disconnect points.

[6]

DISCONNECT ERCW INLET (supply) piping at the

compression fittings (two places) shown in Figure 2 of this Appendix and

REMOVE piping section.

[7]

CONNECT temporary hose compression fittings to Oil Cooler

and ERCW inlet valve as shown in Figure 3:

Compression fitting connected to Oil Cooler

(6" hard tubing with compression nut from tee connection).

Compression fitting connected to ERCW inlet valve

(4 foot red rubber hose with compression nut).

Page 119 of 142

o

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX I

Page 30f7

Rev. 15

[8]

CONNECT gated WYE hose connection to the nearest HPFP hose station:

(NA valves not used)

1-26-668 (near Waste Gas Decay Tank Gallery)

2-26-668 (Between Boric Acid Evaporator control panels)

0-26-662 (near elevator)

D

c.

[9]

ENSURE valves on Gated WYE are CLOSED.

D

[10]

ROLL out fire hose (with female end at gated wye and male connection

in pump room) AND CONNECT two 50 ft. lengths together.

D

[11]

CONNECT Fire hose to gate wye.

D

[12]

CONNECT Fire hose to tee connection.

D

[13]

CHECK all hose connections are complete and hose not kinked .

D

[14]

CLOSE ERCW Drain Valve to CCP Oil Cooler. (NA valve not operated)

Pump

Valve 10

Description

Position

A-ACCP

VLV-67-1547A

ERCW Drain A-A CCP Oil Cooler

CLOSED D

B-B CCP

VLV-67-1546B

ERCW Drain B-B CCP Oil Cooler

CLOSED D

Page 120 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX I

Page 4 of 7

AOP-M .01

Rev. 15

[15]

ENSURE ERCW Isolation Valves to CCP Oil Coolers OPEN. (NA valves not operated)

Pump

Valve ID

Description

Position

A-ACCP

VLV-67-1544A

ERCW to Bearing Oil Cooler

OPEN 0

VLV-67-1545A

ERCW Supply to Gear Oil Cooler

OPEN 0

B-B CCP

VLV-67-1544B

ERCW to Bearing Oil Cooler

OPEN 0

VLV-67-1545B

ERCW Supply to Gear Oil Cooler

OPEN 0

[16]

OPEN ERCW Return Valve from CCP Oil Cooler: (NA valve not operated)

Pump

Valve ID

Description

Position

A-ACCP

VLV-67-705A

ERCW Ret A-A CCP Oil Cooler

OPEN 0

B-B CCP

VLV-67-705B

ERCW Ret B-B CCP Oil Cooler

OPEN 0

[17]

OPEN Gated Wye routing valve that supplies the hose connection.

0

[18]

OPEN Hose Station Valve to provide HPFP to CCP Oil Coolers.

0

[19]

VERIFY fire hose pressurized.

0

[20]

NOTIFY UO that temporary cooling water connection to CCP is complete.

0

[21]

BREACH CCP room door OPEN to allow room cooling.

0

[22]

COORDINATE with Maintenance or Fire Ops to install smoke removal fan

to circulate air through CCP room.

0

C

Page 121 of 142

r:

n

-~,

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

APPENDIX I

Page 5 of 7

Figure 1

CCP Pump Skid

67-1545A(B)

CCP

Motor

Drain Valve -

Gear HI---I

Box

--

Pump

67-1544A(B)

67-704A(B)

Cooling

Water

Supply

Gear Box Oil Hx

Bearing Oil Hx

Page 122 of 142

67-705A(B)

Cooling

water

Return

(

LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

APPE NDIX I

Page 6 of 7

Figu re 2

CCP Heat Exchanger and Piping Configuration

67-704A(B)

ERCW Cooling Water Supply Piping

67-1544A(B)

Remove this

section of piping

to allow

installation of

temporary hoses

...

ERCW Outlet

from H.

Disconnect Compression fittings here ~

--oIT T

(two places) to aifow removal of piping.

Bearing Oil Hx

ERCW Cooling Water Discharge Piping

67-705A(B)

(

Page 123 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

APPENDIX I

Page 7 of 7

Figu re 3

CCP Heat Exchanger and Piping Configuration

(shown w ith permanent piping removed and temporary hose installed )

67-704A(B)

Redrubber

hose -4 ft.

Tee

connection

6" stainless steel

tubing from Tee to

Hx

67-1544A(B)

ERCW Supply piping

Cooling Water

Outlet

--+1

from Hx

ERCWReturn piping (discharge)

Bearing Oil Cooler.

CoolingWater to+_\\l-

_

Gear Oil Cooler

Connect compression fittings on temporary hose~_-r---------o~1r

to permanent pipinghere

Return flow from

Gear Oil cooler

Install Gated Wye

Fire Hose(two 50 ft

sections)

/

Fire hoseconnection

~...."".~

1-26-668

2-26-668

0-26-662

Page 124 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIXJ

Page 1 of 6

Installation of Temporary Cooling Station Air Compressors

AOp*M.01

Rev. 15

NOTE 1

This appendix will install a temporary supply of cooling water to the Station Air

Compressors. A RCW connection at the Turb ine Bldg Space Cooler 1A

(el 685 next to stair well) will be disconnected and an adapter fitted to the piping . An

adapter will also be fitted to the ERCW supply to the air compressors at

VLV-67-1104 & 1105. A fire hose will be installed between the two temporary

connections. All components and tools will be stored in an AOP/EOI cabinet located

on el 685 Turb Bldg. Under the U1 stairwell.

NOTE 2

This Appendix incorporates two parts. Part I provides instructions to install

temporary cooling from the RCW system . Part II returns the compressor to service

and air system.

-

PART I INSTALLATION OF TEMPORARY CONNECTIONS

PARTS AND TOOLS REQUIRED:

2 Adapters:

(1) 3 inch 150# flange with 2-1/2 inch male fire hose thread

(1 ) 2" female pipe thread to a 2-1/2" female fire hose thread

Gasket

Tools for installation: 16" pipe wrench for removal of 2" pipe cap and two wrenches

Approximately 100 feet of fire hose.

c.

1.

CLOSE 1-VLV-24-946 RCW supply to Turbine Bldg Space Cooler 1A.

2.

CLOSE 1-VLV-24-903 RCW outlet from Turbine Bldg Space Cooler 1A.

NOTE

Cooler and piping is not drained . Flanges should be broken to allow draining.

3.

DISCONNECT RCW piping at top flange of 1-TCV-24-210

and at the bottom flange of the flex piping AND

REMOVE rcv and flex piping.

Page 125 of 142

o

c

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIXJ

Page 2 of 6

Rev. 15

(_.

4.

IF RCW isolation valve 1-VLV-24-946 is leaking through,

THEN

CLOSE 1-VLV-24-902 header isolation valve.

5.

INSTALL 3 inch 150# flange with 2-1/2 inch fire hose thread adapter

at top flange where TCV was removed .

6.

REMOVE 2 inch cap at 0-67-1104 and 1105.

(located on ERCW piping above the "8" Station Air Compressor).

7.

INSTALL 2 inch-pipe adapter at 0-67-1104 and 1105.

8.

OBTAIN 100 feet (two 50 ft lengths) of 2-1/2 inch fire hose from Fire Ops

or local hose station.

9.

INSTALL fire hose between adapters, ensuring that the

hose is not kinked.

Page 126 of 142

o

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIXJ

Page 3 of 6

Rev. 15

PART II

AIR COMPRESSOR START AND SYSTEM ALIGNMENT

NOTE

This section will align and start Station Air Compresso r A

or B. Air compressors C and D cannot be started until

after non-essential air pressure is restored.

1.

ALIGN temporary cooling water by performing the following:

a. ENSURE Part I of this appendix to connect temporary cooling is

complete.

0

b. NOTIFY MCR to CLOSE O-FCV-67-205, ERCW supply to Air

Compressors.

0

c. NOTIFY MCR to CLOSE O-FCV-67-208, ERCW supply to Air

Compressors.

0

d. OPEN 0-VLV-67-1104 [above B Station Air Compressor].

0

e. OPEN O-VLV-67-1105 [above B Station Air Compressor].

0

f.

IF 1-VLV-24-946 was leaking through in Part I,

THEN

ENSURE 1-VLV-24-902 RCWheader isol valve is OPEN.

0

g. OPEN 1-VLV-24-946 RCW supply to Turbine Bldg Cooler 1A.

0

h. VERIFY temporary hose pressurized.

0

(

2.

ENSURE service air receiver isolation valve rO-PCV-33-41

CLOSED.

Page 127 of 142

o

c

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIXJ

Page 4 of 6

AOp*M.01

Rev. 15

PART II

AIR COMPRESSOR START AND SYSTEM ALIGNMENT

NOTE

If compressor tripped due to high oil temperature, the oil must cool before the

alarm/trip condition can be reset.

3.

ENSURE compressor trip signals RESET, as follows:

a.

DEPRESS IO-HS*32*25Bl to reset air compressor trip signals.

b.

CHECK Air Compressor A trip lights DARK:

Low OIL PRESSURE

High OIL TEMPERATURE

(

High DISCHARGE AIR PRESSURE.

c.

CHECK Air Compressor B trip lights DARK:

Low OIL PRESSURE

High OIL TEMPERATURE

High DISCHARGE AIR PRESSURE.

4.

PLACE Air Compressor A AUTO/HAND switch IO*HS-32*25Dl

in HAND.

5.

PLACE Air Compressor B AUTO/HAND switch IO-HS-32-26Al

in HAND.

(

Page 128 of 142

o

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIXJ

Page 5 0f 6

Rev. 15

PART II

AIR COMPRESSOR START AND SYSTEM ALIGNMENT

6.

PLACE rHS-32-25Al in Position 1 (AB).

7.

ENSURE rO-HS-32-25F 1for Air Compressor A in PULL TO START.

8.

DEPRESS rO-HS-32-25El to start Air Compressor A.

9.

ENSURE rO-HS-32-26Dl for Air Compressor B in PULL TO START.

1O.

DEPRE~S rO-HS-32-26Bl to start Air Compressor B.

11.

CHECK operation of Air Compressors A and B:

a.

Air Compressor A cooling water flow INDICATED

on rO-FG-32-44Bl.

b.

Air Compressor B cooling water flow INDICATED

on rO-FG-32-24Bl.

12.

MAINTAIN air pressure in receiver tanks

between 80 psig and 100 psig.

o

NOTE 1

NOTE 2

rO-FCV-32-821 and IO-FCV-32-851 close automatically below

approximately 69 psig.

Handswitch must be held in OPEN position until aux air header is

pressurized.

(

13.

OPEN Train A control air supply rO-FCV-32-821 to supply

Train A auxiliary air [Aux Bldg, elev 734, Panel 0-L-321].

14.

OPEN Train B control air supply rO-FCV-32-851 to supply

Train B auxiliary air [Aux Bldg, elev 734, Panel 0-L-322].

Page 129 of 142

o

c

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIXJ

Page 6 of 6

AOp*M.01

Rev. 15

(

PART II

AIR COMPRESSOR START AND SYSTEM ALIGNMENT

15.

NOTIFY MCR that control air pressure has been restored

AND remote control of the followi ng systems may be restored:

Auxiliary Feedwater LCVs

Charging Flow Control

Atmospheric Relief Valves

16.

IF Phase B is NOT actuated,

THEN

ESTABLISH air to containment on selected unit:

[714 pen room]

UNIT

VALVE

DESCRIPTION

OPEN

NUMBER

..j

FCV-32-80

Reactor Bldg Train A essential air isolation

0

1

FCV-32-102

Reactor Bldg Train B essential air isolation

0

FCV-32-110

Reactor Bldg nonessential air isolation

0

FCV-32-81

Reactor Bldg Train A essential air isolation

0

2

FCV-32-103

Reactor Bldg Train B essential air isolation

0

FCV-32-111

Reactor Bldg nonessential air isolation

0

Page 130 of 142

o

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX K

Page 1 of 2

LOCAL CONTROL OF MOTOR-DRIVEN AFW FLOW

Rev. 15

NOTE

If the accountability siren sounds, operator should continue performing this

appendix. The 8M should be aware of task assignments and personnel

locations.

c..

1. IDENTIFY applicable unit:

Unit 1__

Unit2.__

2. OBTAIN radio, gloves and M-5 key.

NOTE 1

-

On loss of power or air, the MD AFW main LCVs fail open and the

bypass LCVs fail closed.

NOTE 2

AFW isolation valves in the following step are locked open.

3. WHEN directed to control Motor Driven Auxiliary Feedwater flow,

THEN

THROTTLE or CLOSE motor-driven AFW isolation valves as directed:

SIG

VALVE NUMBER

LOCATION

./

1

VLV-3-836

Inside Wl/VR,

0

on platform

AS el. 714 Pen Rm

0

2

VLV-3-835

Above Wl/VR entrance

VLV-3-834

AS el. 714 Pen Rm

0

3

Above Wl/VR entrance

VLV-3-837

Inside Wl/VR,

0

4

on platform

Page 131 of 142

o

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX K

Page 2 of 2

LOCAL CONTROL OF MOTOR-DRIVEN AFW FLOW

Rev. 15

c

4. WHE N directed to restore Motor Driven AFW control to Main Control Room,

THEN

LOCK OPEN AFW isolation valves as directed:

S/G

VALVE NO.

LOCATION

LOCKED

OPEN

1

VLV-3-836

Inside WVVR,

0

on platform

2

VLV-3-835

AS el. 714 Pen Rm

0

-

Above WVVR entrance

3

VLV-3-834

AS el. 714 Pen Rm

0

Above WVVR entrance

4

VLV-3-837

Inside WVVR ,

0

on platform

Page 132 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX L

Page 1 of 1

LOCAL CONTROL OF TURBINE DRIVEN AFW LCVS

Rev. 15

NOTE

On loss of power or control air, the TO AFW pump LCVs fail open,

1, OBTAIN handheld lighting, radios, and gloves .

2. ESTABLISH communications between local operator and MCR.

o

NOTE

TD AFW LCVs are turned clockwise to close.

3. COORDINATE with MCR and CONTROL S/G levels by locally operating handwheels

on appropriate LCVs:

S/G

LCV

LOCATION

THROTTLED

CLOSED

1

LCV-3-174

Inside West Valve Vault Room

0

2

LCV-3-173

AS el. 714 Pent. Rm Above WVVR Entrance

0

3

LCV-3-172

AS el. 714 Pent. Rm Above WVVR Entrance

0

4

LCV-3-175

Inside West Valve Vault Room

0

Page 133 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX M

Page 1 of 1

TSC ACTIONS IN THE EVENT OF LOSS OF ERCW

Rev. 15

NOTE 1

NOTE 2

The appendix provides listing of immediate concerns and recommendations

to be evaluated when the TSC is activated. This is not an all inclusive list.

Applicable portions of the following procedures may be used to establish

temporary cooling water:

O-MA-REM-OOO-001.0. Extended Station Blackout

O-MA-MSC-317-200.0. Connection of Blackout Diesel Driven Pump

to High Pressure Fire Protection System on Loss of ERCW

O-MA-MSC-3 17-200.2. Connection of High Pressure Fire Protection

to ERCW on Loss of ERCW

1.

NOTIFY TSC to evaluate the following:

Providing makeup supply to CSTs.

Providing temporary cooling water

supplies to the following components.

MCR chiller packages.

Diesel Generators

Provid ing temporary area/room cooling

to the following components.

CCP rooms

MDAFW pump area

RHR pump room

Maintenance of Fire Protection Storage

Tank level.

Initiation of repairs to restore ERCW

system

Establishing temporary ERCW

for long term plant operation and plant

shutdown.

Pag e 134 of 142

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIXN

Page 1 of 1

. LOCAL ISOLATION OF RCP SEAL INJECTION

Rev. 15

NOTE

If the accountability siren sounds. operator should continue performing this

appendix. The 8M should be aware of task assignments and personnel

locations.

1.

IDENTIFY applicable unit:

Unit 1

Unit 2__

2. OBTAIN-radio and gloves.

3. ISOLATE RCP seal injection:

[Aux Bldg. elev 690, reach rods outside seal water injection filter cubicles]

a. CLOSE seal water injection filter bypass [VLV-62*5461.

b. CLOSE seal water injection filter A outlet [VLV-62-549J.

c.

CLOSE seal water injection filter B outlet [VLV-62-5501.

4. NOTIFY MCR that seal injection is isolated on affected unit.

END OF TEXT

Page 135 of 142

o

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX 0

Page 1 of 4

HANDOUT FOR SECTION 2.1 1

LOSS OF ALL ERCW FLOW

COPY 1 (page 1 of 2)

Rev. 15

c.

STEP

ACTION

9.

MONITOR RCS temperature:

a. IF T-cold less than 54rF. THEN

CONTROL AFW flow to SIGs between 440 and 600 gpm :

b. IF T-cold greater than 552°F, THEN locally operate atmospheric relief valves

10.

MONITOR AFW pump status

a. CONTROL TO AFW flow USING EA-3-1 .

d. WHEN backup air supply depleted. THEN DISPATCH personnel to locally control

TO.!-FW LCVs USING Appendix L.

e. MAINTAIN AFW flow greater than 440 gpm

UNTIL narrow range level greater than 10% [25% ADV] in at least one S/G.

11.

CONTROL SIG narrow range levels between 10% [25% ADV] and 50%.

13.

MONITOR FR-O status trees for information only.

15.

MAINTAIN RCS T-cold between 540°F and 552°F USING Local Control of

S/G #1 and 4 atmospheric relief valves.

16.c

MONITOR hotweilleveis stable or dropping .

17.

MONITOR containment vacuum relief normal:

IF containment pressure less than 1.0 psig then verify containment vacuum relief

valves OPEN .

20.

MONITOR RCP seal cooling available:

a. CHECK Train A CCS Outlet temperature less tha n 130°F.

b. CHECK RCP seal cooling flow in service:

CCP running and supplying RCP Seal Injection flow.

Thermal barrier cooling in service.

21.

MONITOR if CCP can be started:

a. CHECK Tem porary cooling wate r is established to CCP oil cooler.

b. CHECK thermal barrier cooling in service OR seal injection flowpath isolated.

e.

MONITOR CCP bearing and motor winding temperatures .

f.

CONTROL CCP flow.

Pag e 136 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX 0

Page 2 of 4

HANDOUT FOR SECTION 2.11

LOSS OF ALL ERCW FLOW

COPY 1 (page 2 of 2)

Rev. 15

(

STEP

ACTION

22.

MONITOR pressurizer pressure between 2210 and 2260 psig.

23.

MAINTAIN pressurizer level between 20% [35% ADV] and 65%.

24.

MONITOR if RCS cooldown should be started.

a.

CHECK pzr level greater than 10% [20% ADV].

25.

a. MAINTAIN SIG level greater than 10% [25% ADV] while depressu rizing S/Gs.

c. STOP cooldown and MAINTAIN current plant conditions if

Charging pump started

-T-cold less than 280°F.

RCS pressure between 100 psig and 200 psig.

26.

MONITOR SI signal status.

28.

MONITOR Phase B actuated .

36.

MONITOR ECCS fiow NOT required:

Pressurizer level is maintained greater than 10% [20% ADV].

RCS subcooling based on core exit TICs greater than 40°F.

37.

MAINTAIN pressurize r level betwee n 20% [35% ADV] and 65%.

42.

MONITOR RCS cooldown.

43.

INITIATE RCS depressurization:

a. MAINTAIN RCS subcooling based on core exit TICs greater than 140°F.

44.

CONTINUE RCS cooldown and depressurization:

a.

MAINTAIN T-cold cooldown rate less than 50°F/hr.

b. MAINTAIN RCS subcooling based on core exit TICs greater than 140°F.

c.

MAINTAIN RCS T-cold and pressure within limits USING Tech Spec

temperaturelpressure limit curves.

45.

MONITOR NO steam voids in reactor vessel.

46.

WHEN RCS pressure less than 1000 psig. THEN

ISOLATE CLAs.

47.

MAINTAIN plant conditions stable.

Pag e 137 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX a

Page 3 of 4

HANDOUT FOR SECTION 2.11

LOSS OF ALL ERCW FLOW

COpy 2 (page 1 of 2)

Rev. 15

(

STEP

ACTION

9.

MONITOR RCS temperature:

a. IF T-cold less than 54rF. THEN

CONTROL AFW flow to SIGs between 440 and 600 gpm :

b.

IF T-cold greater than 552°F, THEN locally operate atmospheric relief valves

10.

MONITOR AFW pump status

a. CONTROL TO AFW flow USING EA-3-1.

d. WHEN backup air supply depleted, THEN

DIS£,ATCH personnel to iocally control TO AFW LCVs USING Appendix L.

e.

MAINTAIN AFW flow greater than 440 gpm

UNTIL narrow range level greater than 10% [25% AOV] in at least one S/G .

11.

CONTROL S/G narrow range levels between 10% [25% AOV] and 50%.

13.

MONITOR FR-O status trees for information only.

15.

MAINTAIN RCS T-cold between 540°F and 552°F USING Local Control of

S/G #1 and 4 atmospheric relief valves.

16.c

MONITOR hotweilleveis stable or dropping.

17.

MONITOR containment vacuum relief normal:

IF containment pressure less than 1.0 psig then verify conta inme nt vacuum relief

valves OPEN.

20.

MONITOR RCP seal cooling available:

a. CHECK Train A CCS Outlet temperature less than 130' F.

b. CHECK RCP seal coo ling flow in service:

CCP running and supplying RCP Seal Injection flow .

The rmal barrier cooling in service.

21.

MONITOR if CCP can be started :

a. CHECK Temporary cooling water is established to CCP oil cooler.

b. CHECK thermal barrier cooling in service OR seal injection flowpath isolated.

e.

MONITOR CCP bearing and motor winding temperatures.

f.

CONTROL CCP flow .

Page 138 of 142

(

saN

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX 0

Page 4 of4

HANDOUT FOR SECTION 2.11

LOSS OF ALL ERCW FLOW

COPY 2 (page 2 of 2)

AOp*M.01

Rev. 15

STEP

ACTION

22.

MONITOR pressurizer pressure between 2210 and 2260 psig.

23.

MAINTAIN pressurizer level between 20% [35% ADV] and 65%.

24.

MONITOR if RCS cooldown should be started.

a. CHECK pzr level greater than 10% [20% ADV].

25.

a. MAINTAIN SIG level greater than 10% [25% ADV] while depressurizing S/Gs.

c.

STOP cooldown and MAINTAIN current plant conditions if

Charging pump started

-f-cold less than 280"F.

RCS pressure between 100 psig and 200 psig.

26.

MONITOR SI signal status.

28.

MONITOR Phase B actuated.

36.

MONITOR ECCS flow NOT required:

Pressurizer level is maintained greater than 10% [20% ADV].

RCS subcooling based on core exit TICs greater than 40"F.

37.

MAINTAIN pressurizer level between 20% [35% ADV] and 65%.

42.

MONITOR RCS cooldown.

43.

INITIATE RCS depressurization:

a. MAINTAIN RCS subcooling based on core exit TICs greater than 140°F.

44.

CONTINUE RCS cooldown and depressurization:

a. MAINTAIN T-cold cooldown rate less than 50°F/hr.

b. MAINTAIN RCS subcooling based on core exit TICs greater than 140'F.

c.

MAINTAIN RCS T-cold and pressure within limits USING Tech Spec

temperaturelpressure limit curves.

45.

MONITOR NO steam voids in reactor vessel.

46.

WHEN RCS pressure less than 1000 psig, THEN

ISOLATE CLAs.

47.

MAINTAIN plant conditions stable.

Page 139 of 142

(

LOSS OF ESSENTIAL RAW COOLING WATER

APPENDIX P

Page 1 of 2

POTENTIAL TECH SPEC IMPACTS

Rev. 15

NOTES

When ERCW Headers are crosstied the actions of LCO 3.0.3 are applicable.

Steps to record the time a cross-connect valve is opened should be used

as an aid for tracking LCO action times .

With one or both ERCW loops inoperable, all affected LCOs should be

evaluated. Only LCO 3.7.4 and any which have more limiting requirements

need to be logged as entered.

1.

EVALUATE the following Tech Specs

and TRM for applicability:

3.0.3, Limiting Condition for Operation

TR 3.1.2.1, Boration Flowpath - Shutdow n

TR 3.1.2.2, Boration Flowpath - Operating

TR 3.1.2.3, Charging Pump - Shutdown

TR 3.1.2.4, Charging Pump - Operating

3.4.1.1, Reactor Coolant Loops - Startup

and Power Ops

3.4.1.2, Reactor Coolant Loops and

Coolant Circulation - Hot Standby

3.4.1.3, Reactor Coolant Loops and

Coolant Circulation - Shutdown

Page 140 of 142

(

1.

(Continued)

LOSS OF ESSENTIAL RAW COOLI NG WATER

APPENDIX P

Page 2 of 2

Rev. 15

3.5.2. ECCS Subsystems T-avg ;:, 350°F

3.5.3, ECCS Subsystems T-avg < 350°F

3.6.1.8, EGTS - Cleanup Subsystem

3.6.1.5, Containment Air Temperature

3.6.2.1. Containment Spray

3.6.2.2, Lower Containment Coolers

3.7.1.2. Auxiliary Feedwater

3.7.3, Component Cooling Water

3.7.4, ERCW

3.7.8, ABGTS

3.8.1.1. A.C. Sources - Operating

3.8.1.2. A.C. Sources - Shutdown

END OF TEXT

Page 141 of 142

(

SON

LOSS OF ESSENTIAL RAW COOLING WATER

COMMITMENT LIST

Rev. 15

SUMMARY OF

COMM ITMENT ID

COMMITMENT

C.1

Identify non-essential heat loads

that could be isolated in the event

system realignment is required.

S 64 940314 800

C.2

Provide guidance on the required

use of AOls during the performance

of EOPs.

EPM-4, EOI Program Manual

User's Guide

C.3

Developed section 2.11 to address

operator response to complete

loss of ERCW.

Page 142 of 142

COMMITMENT

CORRESPONDENCE

NCO 940176001

SQPER9301 77

IFI-93-300-02

NCO 020002001

(

PREPARED!

REVISED BY:

VALIDATED BY:

APPROVED BY:

JPM 6.1 .g

Page 1 of 9

Rev. 0

SEQUOYAH NUCLEAR PLANT

8.1.g

Respond to Spray Valve Failure

Original Signatures on FHe

Date/

Date!

(Operations Training Manager)

CONCURRED:

(Operations Representative)

Date!

Validation not required for minor enhancements, procedure Rev changes that do

not affect the JPM , or individual step changes that do not affect the flow of the JPM.

.. Operations Concurrence required for new JPMs and changes that affect the flow

of the JPM (if not driven by a procedure revision).

(

JPM B.1 .g

Page 2 of 9

Rev. 0

NUCLEAR TRAINING

REVISION/USAGE LOG

Revis ion

Description

Pages

Prepared/

Number

Of Revision

V

Date

Affected

Revised Bv:

0

Inilial lssue

-

y

2/13/07

All

RH Evans

I

!

I

,,

--

I,

I

..-

,

.-

-

--

._.

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

- .

I

._-

._---

-

. -

.'- -

i

-~

- -

.~

-

I

-~-

I

i

- -

j

I

v . Specify if the JPM change will require another validation (Y or N).

See cover sheet for criteria.

JPM B.1 .g

Page 3 of 9

Rev. 0

(

SEQUOYAH NUCLEAR PLANT

RO/SRO

Task:

Respond to Spray Valve failure

JAITA task # : 3210140401

(RO)

0150050101

(ROJ

0150040101

(RO)

0000910501

(RO)

K/A Ratings:

010A2.02

3.9/3.9

010A4.01

3.7/3.5

008AA2.19

3.4/3.6

Task Standard:

Reps supplying failed spray valve are tripped. Pressurizer heaters are energized.

In-Plant

_

x

Evaluation Method :

Simulator _

-..!>.__

=======================================================================

Performer:

NAME

Start Time

_

Perfo rmance Rating : "SAT _

_

UNSAT __

Performance Time

Finish Time

_

DATE

SIGNATURE

-

_

/,- -

-

Evaluator:

(

=======================================================================

COMMENTS

(

JPM 8 .1.g

Page 4 of g

Rev. 0

SPECIAL INSTRUCTIONS TO EVALUATOR:

1.

Critical steps are identified within the step.

2.

Sequenced steps identified by an "s"

3.

Any UNSAT requires comments

4.

Initialize the simulator in IC 90 or initialize the simulator in IC 16 and complete the following:

a.

Initiate a reactor trip and insert malfunction, IMF RC06A f:20 to partially open one spray valve simulating a

partially stuck open spray valve;

b.

Allow RCS pressure to drop to, but not less than, approximately 2100-2150 psig at ES-0.1 Step 8,

MONITOR Pressurizer pressure control;

c.

Turn the 'D' bank pressurizer heaters off; and,

d.

Freeze the simulator.

5.

Ensure operator performs the following required actions for SELF-CHECKING;

a.

Identifies the correct unit, train, component, etc.

b.

Reviews the intended action and expected response.

c.

Compares the actual response to the expected response.

Validation Time: CR.

11 mins

Tools/Equipment/Procedures Needed:

ES-0.1

References:

Reference

Local

Title

Rev No.

A.

ES-0.1

Reactor Tri

Res onse

30

c.

(

==================================================================

READ TO OPERATOR

DIRECTIONS TO TRAINEE:

I will explain the initial conditions, and state the task to be performed. All control room steps shall be

performed for this JPM. i will provide initiating cues and reports on other actions when directed by

you. When you complete the task successfully, the objective for this job performance measure will be

satisfied. Ensure you indicate to me when you understand your assigned task. To indicate that you

have completed your assigned task return the handout sheet I provided you.

INITIAL CONDITIONS:

1.

Unit has tripped.

2.

Transition to ES-0.1 has been performed.

INITIATING CUES:

You have been directed to stabilize the unit in accordance with ES-0.1, beginning at step 1.

Notify the US when the unit is stable

Evaluator Note:

Applicant may take action related to critical steps prior to reaching

required steps by use of the ES-O.1 Handout.

STEP 1.:

Obtain the appropriate procedure.

-

STANDARD:

Operator obtains a copy of ES-O.1.

-

UNSAT

COMMENTS:

Start Time--

STEP 2.:

[1]

MONITOR SI NOT actuated:

-

SI ACTUATED permissive DARK [M-4A, D4]

-

UNSAT

STANDARD : Determines SI is NOT actuated by observing annunciator M-4A-D4

permiss ive is dark

COMMENTS:

STEP 3.:

[2]

VERIFY generator breakers OPEN.

-

STANDARD:

Verifies generator breakers open by observing green lights on 1-M-1

-

UNSAT

benchboard.

COMMENTS :

STEP 4.:

[3]

MONITO R RCS temperatures:

-

RCPs Running: CHECK T-Tavg stable at or trending to between

-

UNSAT

547°F and 552°F.

STANDARD:

Determines T-Tavg is stable at or trending to between 54rF and 552°F.

COMMENTS:

(

Job Perform ance Checklist:

STEP/STANDARD

JPM B.1.g

Page 5 of 9

Rev. 0

SATIUNSAT

STEP 5.

[4]

MONITOR feedwater status:

-

T-Tavg less than 550°F.

-

UNSAT

MFW regulating valves CLOSED.

MFW regulating bypass valve controller outputs ZERO.

MFW isolation valves CLOSED.

MFW pumps TRIPPED.

MFW flow ZERO.

Total feed flow to SIGs greater than 440 gpm.

STANDARD:

Determines Tavg is NOT less than 550°F and goes to step 5.

COMM ENTS:

STEP 6.:

[5]

CHECK if emergency boration is required:

-

[aJ

VERIFY all control rods fully inserted:

-

UNSAT

Rod bottom lights LIT

Rod position indicators less than or equal to 12 steps.

-

STANDARD:

Determines All rod Bottom lights are illuminated.

STEP 7.:

[b]

MONITOR RCS temperature:

-

T-Tavg greater than 540°F if any RCP running

-

UNSAT

STANDARD:

Determines T-Tavg is approximately 551°F

COMMENTS:

STEP 8.:

[6]

ANNOUNCE reactor trip USING PA system.

-

STANDARD:

Announces reactor trip over PA system

-

UNSAT

COMMENTS:

(

Job Performance Checklist:

STEP/STANDARD

JPM B.1.g

Page 6 of 9

Rev. 0

SAT/UNSAT

Job Performance Checklist:

STEP/STANDARD

JPM B.1.g

Page 7 of 9

Rev. 0

SAT/UNSAT

(

STEP 9.:

[7]

MONITOR pressurizer level control:

-

CHECK pressurizer level greater than 17%.

-

UNSAT

VERIFY charging IN SERVICE.

VERIFY letdown IN SERVICE.

CHECK pressurizer level trending to 25% (normal range

20% to 30%).

STANDARD:

Determines Charging and Letdown are in service and PZR level is >17%

and trending to 25%.

COMM ENTS:

,

STEP 10.:

[8] MONITOR pressurizer pressure control:

-

Pressurizer pressure greater than 1870 psig.

-

UNSAT

Pressurizer pressure stable at or trending to 2235 psig (normal

range 2210 psig to 2260 psig).

STANDARD:

Determines PZR pressure >1870 but NOT trending toward 2210-2260

psig. -

COMM ENTS :

EVALUATOR NOTE:

JPM steps 11,12 and 13 are from procedure step 8 RNO

STEP 11.:

IF pressure less than 2235 psig and dropping, THEN

-

PERFORM the following:

-

UNSAT

ENSURE pressurizer PORVs CLOSED . (not critical)

ENSURE spray valves CLOSED. (not critical)

Critical Step

IF spray valve(s) CANNOT be closed, THEN STOP RCPs #\\

and 2.

IF pressurizer pressure continues to drop, THEN STOP

additional RCPs as necessary. (not critical)

ENSURE all pressurizer heaters ON.

STANDARD:

Stops Number 1 & 2RCP by rotating handswitches counter-clockwise.

COMMENTS:

Job Performance Checklist:

STEP/STANDARD

JPM B.1.g

Page 8 of 9

Rev. 0

SAT/UNSAT

(

STEP 12.:

IF pressure less than 2235 psig and dropping, THEN

PERFORM the following:

ENSURE pressurizer PORVs CLOSED. (not critical)

ENSURE spray valves CLOSED. (not critical)

IF spray valve(s) CANNOT be closed, THEN STOP RCPs #1

and 2.

.IF pressurizer pressure continues to drop, THEN STOP

additional RCPs as necessary. (not critical)

ENSURE all pressurizer heaters ON.

UNSAT

Crit ical Step

Stop Time__

(

STANDARD:

Manually energized PZR heater Bank D by rotating handswitch

clockwise.

COMMENTS:

End of JPM

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

DIRECTION TO TRAINEE:

I will explain the initial conditions, and state the task to be performed . All control

room steps shall be performed for this JPM, including any required communications.

I will provide initiating cues and reports on other actions when directed by you.

Ensure you indicate to me when you understand your assigned task. To indicate

that you have completed your assigned task return the handout sheet I provided

you.

INITIAL CONDITIONS:

Unit has tripped.

Transition to ES-O.1 has been performed.

INITIATING CUES:

You have been directed to stabilize the unit in accordance with ES*O.1,

beginning at step 1.

Notify the US when the unit is stable

I

(

TENNESSEE VALLEY AUTHORITY

SEQUOYAH NUCLEAR PLANT

EOI PROGRAM MANUAL

EMERGENCYSUBPROCEDURE

ES*0.1

REACTOR TRIP RESPONSE

Revision 30

QUALITY RELATED

D. A PORTER

PREPAREO/PROOFREAD BY: __""",",-J:LJw.!.!~=-!.L

_

(

RESPONSIBLE ORGANIZATION:

-,>!O,-PE!=!RAl=.T!.!.IO~N",-S

_

W. T. LEARY

APPROVED BY:.

....l!.!"--L.l£O!:l!:l.L-

_

EFFECTIVE DATE:

08101/2005

REVIS ION

DESCRIPTION:

Added new step which checks generator PCBs open. This step is

being relocated from E-Q Step 3 in conjunction with incorporation

of E-OA Revised step 11.b to provide details on placing steam

dumps in pressure mode.

This procedure has a handout page (2 copies) and foldo ut page.

I

(

REACTOR TRIP RESPONSE

FOLDOUT PAGE

IES*0.1

Rev. 30

(

51 ACTUAnON CRITERIA

IF either of the following conditions occurs:

RCS subcooling based on core exit TICs less than 40 °F

Pressurizer level CANNOT be maintained greater than 5%,

THEN

ACTUATE SI and GO TO E-O, Reactor Trip or Safety Injection.

EVENT DIAGNOSTICS

IF both trains of shutdown boards deenergized,

THEN

GO TO ECA-O.O, Loss of All AC Power.

TANK SWITCHOVER SETPOINTS

IF CST level less than 5%,

THEN

ALIGN AFW suction to ERCW.

Page 1a of15

REACTOR TRIP RESPONSE

I

ES-0.1

____"'---

Rev. 30

I

(

HANDOUT

Page 1 of 2

(

STEP

ACTI ON

FOP

IF RCS subcoolinq based on core exit TICs less than 40'F

OR Pressurizer level CANNOT be maintained greater than 5%,

THEN ACTUATE SI and GO TO E*O, Reactor Trip or Safety Injection.

FOP

IF CST level less than 5%,

THEN ALIGN AFW suction to ERCW.

1.

MONITOR SI NOT actuated :

3.

MONITOR RCS temperatures stable at or trending to between 54rF and 552'F.

3.c.

(if RCS temperature continues to drop)

RNa

CONTROL total feed flow to minimize RCS cooldown.

MAINTAIN total feed flow greater than 440 gpm UNTIL narrow range level

greater than 10% in at least one S/G.

4.

MONITOR feedwater status: (verify F'NI when T-avg less than 550'F)

5.b.

MONITOR RCS temperatures greater than 540'F.

7.

MONITOR pressurizer level control: (pressurizer level greater than 17%)

7.a.

(if pzr level less than 17%)

RNa

3)

CONTROL charging to restore pressurizer level greater than 17%.

4)

WHEN pressurizer level greater than 17%,

THEN OPERATE pressurizer heaters as necessary.

7.c.

(if letdown not in service)

RNO

WHEN charging established AND pressurizer level greater than 17%,

THEN ESTA BLISH letdown.

7.d.

(if pzr level is NOT trending to 25%)

RNO

CONTROL charging and letdown to maintain pressurizer level at 25%

(normal range 20% to 30%).

8.

MONITOR pressurizer pressure control : (pzr pressure greater than 1870 psig

and stable at or trending to 2235 psig)

8.b.2)

(if pzr pressure greater than 2235 psig and rising)

RNO

CONTROL pressure.

9.

MAINTAIN SIG narrow range levels: (between 10% and 50%)

9.a.

(if SIG levels less than 10%)

RNO

MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 10%.

Page 1b of 15

1

-

REACTOR TRIP RESPONSE

I

ES-O.1

______________________

~ev.30

I

(

HANDOUT

Page20f2

STEP

ACTION

12.b. 2).

RNO

(if NO Rep can be started)

MONITOR natural circulation.

13.

MONITOR if source range channels should be reinstated:

(IRM flux less than 10. 4 % power)

15.

MAINTAIN stable plant conditions:

a.

Pressurizer pressure at 2235 psig (normal range 2210 psig to 2260 psig)

b. Pressurizer level at 25% (normal range 20% to 30%)

c.

SIG narrow range levels between 10% and 50%

d. RCS temperature at 547"F (between S40'F and 550'F)

(

Page 1c of 15

I

(

saN

REACTOR TRIP RESPONSE

HANDOUT

Page 1 of 2

IES-0.1

Rev. 30

(

STEP

ACTI ON

FOP

IF RCS subcooling based on core exit TICs less than 40'F

OR Pressurizer level CANNOT be maintained greater than 5%,

THEN ACTUATE SI and GO TO E-O. Reactor Trip or Safety Injection.

FOP

IF CST level less than 5%,

THEN ALIGN AFW suction to ERCW.

1.

MONITOR 51 NOT actuated:

3.

MONITOR RCS temperatures stable at or trending to between 547"F and 552'F.

3.c.

(if RCS temperature continues to drop)

RNa

CONTROL total feed flow to minimize RCS cooldown.

MAINTAIN total feed flow greater than 440 gpm UNTIL narrow range level

greater than 10% in at least one S/G.

4.

MONITOR feedwater status: (verify FWI when T-avg less than 550'F)

5.b.

MONITOR RCS temperatures greater than 540'F.

7.

MONITOR pressurizer level control: (pressurizer level greater than 17%)

7.a.

(if pzr level less than 17%)

RNa

3)

CONTROL charging to restore pressurizer level greater than 17%.

4)

WHEN pressurizer level greater than 17%.

THEN OPERATE pressurizer heaters as necessary.

r,c.

(if letdown not in service)

RNa

WHEN charging established AND pressurizer level greater than 17%,

THEN ESTABLISH letdown.

7.d.

(if pzr level is NOT trending to 25%)

RNa

CONTROL charging and letdown to maintain pressurizer level at 25%

(normal range 20% to 30%).

8.

MONITOR pressurizer pressure control: (pzr pressure greater than 1870 psig

and stable at or trending to 2235 psig)

8.b.2)

(if pzr pressure greater than 2235 psig and rising)

RNa

CONTROL pressure.

9.

MAINTAIN SlG narrow range levels: (between 10% and 50%)

9.a.

(if SIG levels less than 10%)

RNa

MAINTAIN total feed flow greater than 440 gpm UNTIL level greater than 10%.

Page 1d of 15

saN

STEP

REACTOR TRIP RESPONSE

HANDOUT

Page2 of 2

ACTION

IES-0.1

Rev. 30

12.b.2).

(if NO RCP can be started)

RNO

MONITOR natural circulation.

13.

MONITOR if source range channels should be reinstated:

(IRM nux less than 10' 4 % power)

15.

MAINTAIN stable plant conditions:

a. Pressurizer pressure at 2235 psig (normal range 2210 psig to 2260 psig)

b. Pressurizer level at 25% (normal range 20% to 30%)

c.

SIG narrow range levels between 10% and 50%

d. RCS temperature at 547°F (between 540'F and 550'F)

Page 1e of 15

J

1.0

PURPOSE

REACTOR TRIP RESPONSE

IES-O.1

Rev. 30

This procedure providesthe necessary instructions to stabilize and control the plant

following a reactor trip WITHOUT a safety injection.

2.0

SYMPTOMS AND ENTRY CONDITIONS

2.1

ENTRY CONDITIONS

E-O

Reactor Trip or Safety Injection

SI NOT actuated and NOT required

3.0

OPERATOR ACTIONS

Page 2 of 15

I

(

REACTOR TRIP RESPONSE

IES-O,1

____..L-

R_e_v_,_3_0__-'

ISTEPIIACTlONIEXPECTED RESPONSE

IIRESPONSE NOT OBTAINED

NOTE

This procedure has a foldout page.

1.

MONITOR 81NOT actuated:

SI ACTUATED permissive DARK

[M-4A, D4]

IF 81 actuated,

THEN

GO TO E*O, Reactor Trip or Safety

Injection. a--

2.

VERIFY generator breakers OPEN.

OPEN generator breakers.

Page 3 of 15

IL..

_

I

REACTOR TRIP RESPONSE

IES-O.1

l..-

--'-

R_e_v_"_3_0__-.J

ISTEP IIACTION/EXPECTED RESPONSE

IIRESPONSE NOT OBTAINED

3.

MONITOR RCS temperatures:

IF any RCP running,

THEN

CHECK T-avg stable at or trending to

between 54rF and 552°F.

IF RCPs stopped,

THEN

CHECK T-cold stable at or trending

to between 547°F and 552°F.

IF temperature less than 547°F

and dropping,

THEN

PERFORM the following:

a.

ENSURE steam dumps and

atmospheric reliefs CLOSED .

b. ENSURE S/G blowdown isolation

valves CLOSED.

c.

IF cooldown continues,

THEN

PERFORM the following:

1) CONTROL total feed flow

USING EA-3-B, Manual Control of

AFWFlow.

2)

MAINTAIN total feed flow

greater than 440 gpm

UNTIL narrow range level

greater than 10%

in at least one S/G.

3)

DEPRESS RESET

on MSR control panel.

4) IF any MSR temp control valve

fails to close,

THEN

ISOLATE HP steam to MSRs.

d.

IF cooldown still continues,

THEN

CLOSE MSIVs and bypass valves.

IF temperature greater than 552°F

and rising,

THEN

DUMP steam to condenser.

DUMP steam USING atmospheric

reliefs.

Page 4 of 15

REACTOR TRIP RESPONSE

IES-0.1

Rev. 30

ISTEPIIACnONIEXPECTED RESPONSE

IIRESPONSE NOT OBTAINED

4.

MONITOR feedwater status:

a.

T-avg less than 550°F.

a.

GO TO Step 5.

b.

MFW regulating valves CLOSED.

b.

CLOSE valves.

c.

MFW regulating bypass valve controller

c.

CLOSE valves.

outputs ZERO.

d.

MFW isolation valves CLOSED.

d.

CLOSE valves.

e.

MFW pumps TRIPPED.

e.

TRIP MFW pumps.

f.

MFWflow ZERO.

g.

Total feed flow to SIGs

greater than 440 gpm.

f.

CLOSE feedwater heater isolation

MOVs as necessary.

DISPATCH personnel to isolate MFW

regulating and regulating bypass

valves USING EA-3-12. Local

Isolation of Main Feedwater.

g. ESTABLISH AFW flow

as necessary.

IF AFW flow CANNOT be established,

THEN

ESTABLISH main feedwater flow

USING EA-2-2, Establishing

Secondary Heat Sink Using Main

Feedwater or Condensate System.

Page 5 of 15

J

REACTOR TRIP RESPONSE

IES-O.1

___________________________R_e_v_o_3_0

_

ISTEPIIACTION/EXPECTED RESPONSE

IIRESPONSE NOT OBTAINED

5.

CHECK if emergency boration is required :

a.

VERIFY all control rods fully inserted:

Rod bottom lights LIT

Rod position indicators

less than or equal to 12 steps.

b.

MONITOR ReS temperature:

T-avg greater than 540°F

if any RCP running

T-cold greater than 540"F

if all RCPs stopped.

6.

ANNOUNCE reactor trip

USING PA system.

a.

IF any of the following conditions

exists:

two or more RPls Indicate

greater than 12 steps

two or more control rod positions

CANNOT be determined,

THEN

EMERGENCY BORATE

USING EA-68-4 , Emergency

Boralion.

b.

EMERGENCY BORATE

as necessary to maintain shutdown

margin USING EA*68.4 , Emergency

Boration.

Page 6 of 15

,

REACTOR TRIP RESPONSE

IES-O.1

'--

R_e_v_,_3_0__...J

ISTEP IIACTION/EXPECTED RESPONSE

IIRESPONSE NOT OBTAINED

7.

MONITOR pressurizer level control:

(

a.

CHECK pressurizer level

greater than 17%.

b.

VERIFY charging IN SERVICE.

c.

VERIFY letdown IN SERVICE.

d.

CHECK pressurizer level

trending to 25%

(normal range 20% to 30%).

a.

PERFORM the following:

1) ENSURE normal and excess

letdown ISOLATED.

2) ENSURE pressurizer heaters OFF.

3) CONTROL charging to restore

pressurizer level greater than 17%.

4) WHEN pressurizer level

greater than 17%,

THEN

OPERATE pressurizer heaters

as necessary.

b.

ESTABLISH charging

USING EA-62-5, Establishing Normal

Charging and Letdown.

c.

WHEN charging established

AND pzr level greater than 17%,

THEN

ESTABLISH letdown USING EA-62-5,

Establishing Normal Charging and

Letdown.

d.

CONTROL charging and letdown

to maintain pressurizer level at 25%

(normal range 20% to 30%).

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8.

MONITOR pressurizer pressure control:

a.

Pressurizer pressure

greater than 1870 psig.

b.

Pressurizer pressure

stable at or trending to 2235 psig

(normal range 2210 psig to

2260 psig).

a.

ENSURE SI ACTUATED.

GO TO E-O, Reactor Trip or Safety

Injection. *

b.

IF pressure less than 2235 psig

and dropping,

THEN

PERFORM the following:

1) ENSURE pressurizer PORVs

CLOSED.

IF pressurizer PORV

CANNOT be closed,

THEN

CLOSE its block valve.

2) ENSURE spray valves CLOSED .

IF spray valve(s) CANNOT be

closed,

THEN

STOP RCPs #1 and 2.

IF pressurizer pressure

continues to drop,

THEN

STOP additional RCP

as necessary.

3) ENSURE all pressurizer heaters

ON.

(step continued on next page)

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8.

b.

(continued)

IF pressure greater than 2235 psig

and rising,

THEN

PERFORM the following:

1) ENSURE all pressurizer heaters

OFF.

2) CONTROL pressure USING normal

spray.

(

IF normal spray NOT available

AND letdown in service,

THEN

CONTROL pressure USING

EA-62-4, Establishing Auxiliary

Spray.

IF normal spray NOT available

AND letdown NOT in service,

THEN

ENSURE pressure controlled

with pressurizer PORV(s).

9.

MAINTAIN SIG narrow range levels:

a.

Greater than 10%.

a.

MAINTAIN total feed flow

greater than 440 gpm

UNTIL level greater than 10%

in at least one S/G.

b.

Between 10% and 50%.

b.

IF level in any SIG continues to rise,

THEN

ENSURE feed flow STOPPED

to that SlG.

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10.

VERIFY AC busses ENERGIZED

from start busses.

PERFORM the following:

a.

ENSURE diesel generators supplying

shutdown board loads as necessary:

CCPs

ERCW pumps.

AFWpumps.

Thermal barrier booster pumps.

CCSpumps.

Pressurizer heaters A-A and B-B.

b.

ATIEMPT to restore offsite power

USING EA-202-1 , Restoring Off-Site

Power to 6900V Shutdown Boards.

c.

ENSURE control air compressors

A and B started USING EA*32-2,

Establishing Control and Service Air.

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CAUTION

Annlng steam dumps in pressure mode with demand signal

present could result in rapid RCS cooldown.

(

.,'

11.

DETERMINE if steam dump to condenser

available:

a.

CHECK condenser AVAILABLE:

c-s CONDENSER INTERLOCK

permissive LIT [M-4A, E6l

At least one Intact SIG MSIV

OPEN.

b.

PLACE steam dumps in

STEAM PRESS mode:

1) PLACE steam dumps in OFF.

2) ENSURE steam dumps in

steam pressure mode.

3) ENSURE zero output (demand).

4)

PLACE steam dumps in ON.

5) ADJUST steam dump controller

setpoint to 84% (1005 psig)

in AUTO.

a. USE atmospheric reliefs in AUTO

and set for 84% (1005 psig).

IF atmospheric reliefs

NOT functioning in AUTO,

THEN

USE manual control of atmospheric

reliefs.

IF local control of atmospheric reliefs

is necessary,

THEN

DISPATCH personnel to dump steam

USING EA-1-2, Local Control of

SIG PORVs.

GO TO Note prior to Step 12.

=--

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NOTE

Loop 2 RCP and associated spray valve will provide adequate spray flow

for RCS pressure control. If Loop 2 is not available, all three remaining

RCPs may be required to ensure adequate spray flow.

.'

12.

CHECK RCP #2 RUNNING.

PERFORM the following :

a.

IF NO RCPs running,

THEN

ENSURE all RCS dilution

STOPPED.

b.

ATIEMPT to start RCP(s)

to provide normal pzr spray:

1) ESTABLISH conditions for

starting RCP(s) USING EA-S8-2,

Establishing RCP Start

Conditions .

2) IF RCP start conditions

established ,

THEN

START RCP #2 (if available)

OR RCPs #1, 3, and 4.

IF NO RCP can be started,

THEN

MONITOR natural circulation

USING EA-68-S, Monitoring

Natural Circulation Conditions.

IF natural circulation

CANNOT be verified,

THEN

RAISE steam dump rate.

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13,

MONITOR if source range channels

should be reinstated:

a, CHECK intermediate range flux

less than 10" % power

on operable channels,

a,

GO TO Step 14,

b. CHECK source range channels

REINSTATED.

b.

REINSTATE source range channels

by simultaneously placing both

SRM TRIP RESET-BLOCK switches

to RESET position, [M-4]

c. SELECT one SRM and one IRM on

NR=4S recorder,

d. ENSURE audio count rate operation,

B. RESET shutdown monitor alarm

setpoints. [M-13]

f,

WHEN shutdown monitor ALARM

LEDs dark AND HIGH FLUX AT

SHUTDOWN bistable lights dark,

THEN

PLACE HIGH FLUX AT SHUTDOWN

alarm block switches in NORMAL

[M-13]

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14.

SHUT DOWN unnecessary plant

equipment:

REFER TO D-G0-12 , Realignment

Of Secondary Equipment Following

ReactorlTurbine Trip.

15.

MAINTAIN stable plant conditions:

a.

Pressurizer pressure at 2235 psig

(normal range 2210 psig to 2260 psig)

b.

Pressurizer level at 25%

(normal range 20% to 30%)

c. S/G narrow range levels

between 10% and 50%

d.

RCS temperature at 547°F

(between 540°F and 550°F):

T-avg if any Rep running

T-cold if all RCPs stopped.

16.

PERFORM EA-D-9. Post Trip

Administrative Requirements

and Recovery Actions.

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17.

DETERMINE if natural circulation

cooldown is required:

a. CHECK at least one RCP RUNNING.

a. IFplant cooldown required

with NO RCP available,

THEN

GO TO ES-0.2, Natural Circulation

Cooldown.---.--

DO NOT CONTINUE this procedure

UNTIL at least one Rep restarted.

(

b.

Ct!ECK at least one AFW pump

AVAILABLE.

c.

SELECT appropriate procedure:

b. DO NOT CONTINUE this procedure

UNTIL at least one AFW pump

AVAILABLE.

o-GO-6, Power Reduction from

30% Reactor Power to Hot

Standby (if maintaining hot

standby)

0-GO-7, Unit Shutdown from Hot

Standby to Cold Shutdown