ML072960570

8.1.1 JPM 115*2AP

Respond To ERCW Pump Trip per AOP-M.01

(

PREPAREDI

REVISED BY: Date!

VALIDATED BY: * Date!

APPROVED BY: Date!

(Operations Training Manager)

CONCURRED: ** Date!

(Operations Representative)

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

reord er JPM step 8 and console operator action.

1 Updated to current revision and IC. Rewrote to include Y 8/1 6/04 All MG Crot eau

returning to section 2.1 after header break isolated.

Extensive rewrite. Needs full validation run includina time.

I I 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

-

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. -----

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--

- I . _ ..-

.- I - - - -

i _.-

I

- -- I -

,

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-

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._- -

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I -

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( 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 Rat ings :

076A2 .01 (3 .5/3.7) 076K4.06 (2.8/3.2)

076A4 .01 (2 .9/2.9) 076A2 .02 (2 .7/3 .1)

076K6.04 (2.1/2.2)

Task St andard :

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

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

Eva lu at ion Method : Simulator _ x

....!:>._ _ ln-Plant _

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

Performer:

NAME Start Tim e

Performance Rat ing : SAT UNSAT Performance Time Finish Time

( Eva luator: /

SIGNAT URE DATE

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

COMMENTS

JPM B.1.f

Page 4 of 13

Rev. 2

SPECIAL INSTRUCTIONS TO EVALUATOR:

c 1. Critical steps are identified within the step

2. Sequenced steps identified by an "s"

3. Any UNSAT requires comm ents

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 Title Rev No.

AOP-M.01 Loss of ERCW 15

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

( READ TO OPERATOR

Direction s to T rainee :

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.

JPM B.l.I

Page 5 of 13

Rev. 2

Job Performance Checklist:

STEP/STANDARD SATIUNSAT

( SAT

Examiner NOTE: Candidate may perform the ARP actions. They are identical to

procedure steps. _UNSAT

STEP 1.: Obtain a copy of the appropriate procedure. Start Time__

Cue : The SM will evaluate Tech Specs, TRM, and th e 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. _SAT

UNSAT

STANDARD: Operator verifies at least 2 A train ERCW pumps available

COMMENTS :

JPM B.l.I

Page 6 of 13

Rev. 2

Job Performance Checklist:

STEP/STANDARD SAT/UNSAT

( STEP 5.: (4) CHECK 1A and 2A ERCW supply header pressures and flows _ SAT

NORMAL:

a. Supply Header pressures [between 78 psig and 124 psig]: UNSAT

1-PI-67*493A

2-PI-67*493A

STAN DARD : Operator checks header pressures are between 78 and 124 psig on

both A Train indicators.

COMM ENTS:

STEP 6,: b. Supply Header flows [expected value]. _ SAT

1-FI-67-61

2-FI-67-61 UNSAT

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

on both indicators.

COMM ENTS:

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 _ SAT

NORMAL:

a. Supply Header pressures [between 78 psig and 124 psig]: UNSAT

1-PI-67-488A

2-PI-67-488A

b. Supply header flows [expected value]:

1-FI-67-62

2-FI-67-62

Cue: If asked, ERCW pipe break has occurred.

STANDARD: Operator checks header pressures are between 78 and 124 psig on

both B Train indicators. Flows are abnormal , transit ions to section

2.10 .

COMM ENTS:

FROM SEQL.X: YAH OPERATOR TRA I NI NG PI-rnE NO* . : 423 843 4339 Apr . 04 2007 04 :22PM P6

JPM 6.1.f

Page 7 of 13

Rev. 2

) Job Performance Cneckust:

\ STEP/STANDARD SATIUNSAT

-.. EVAI.UATOR NOTE: Tne followino steDs are from section 2.10:

STEF~: [1] Stop and LOCK OUT All Train B ERCW Pumps _SAT

_UNSAT

C'!!<: If asked, leak rate has slowect.

Critical Step

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: _SAT

PERFORM Appendix F, ERCW Rx MOV Board ERCW Valves.

PERFORM Appendix G, ERCW MeC Valves. _UNSAT

ENSURE all pumping station watertlqht doons are CLOSED.

Critical Slep

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. _SAT

Play role of /,/2 CRO and start 2A CCP _UNSAT

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

RCP seals and normal charging from A train equipment.

- - -. _ ~

JPM B.l.I

Page 7 of 13

Rev. 2

Job Performance Checklist:

STEP/STANDARD SAT/UNSAT

EVALUATOR NOTE : The followino steos are from section 2.10:

(

STEP 8.: (1) Stop and LOCK OUT All Train B ERCW Pum ps _ SAT

_ UNSAT

Cue: If asked, leak rate has slowed.

Critical Step

STANDARD : 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.

COMMENTS:

STEP 9.: [2] DISPATCH operators with radios to perform the following: _ SAT

PERFORM Appendix F, ERCW Rx MOV Boa rd ERCW Valves.

PERFOR M Appendi x G, ERCW MCC Valves . UNSAT

ENSURE all pumping station watertight doors are CLOSED.

Critical Step

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.

COMMENT S:

STEP 10.: (3) ENSURE 1A and 2A CCPs RUNNING. SAT

Cue: Play role of U2 CRO and start 2A CCP UNSAT

STAN DARD: Operato r starts 1A-A charging pump . This step is critical to supply Critical Step

RCP sea ls and normal charging from A train equ ipment.

COMM ENTS :

JPMB.1.f

Page 8 of 13

Rev. 2

Job Performance Checklist:

STEP/STANDARD SAT/UNSAT

( STEP 11.: [4] STOP and LOCK OUT effected equipment: - SAT

a. PLA CE the following pumps in PULL TO LOCK: - UNSAT

1B CCP

2BCCP

1B SI Pump Crit ical Step

2B 5 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

crit ic al to prev ent start of ECCS equ ipment w it hout cooling wa ter

available to the room co olers.

COMMENTS:

ST EP 12.: b. DISPATCH operator to place Train B Aux Air Compressor in - SAT

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: - SAT

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

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

Cue: Play ro le of U2 CRO/A UO and acknowledge the request.

STAN DARD : Operator opens 1-FCV-67-65 and directs opening of 2-FCV-67-65. Critical Step

COMMENTS:

(

JPM B.1.f

Page 9 of 13

Rev. 2

Job Performance Checklist:

STEPISTANDARD SATIUNSAT

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

STEP 14.: [6] ISOLATE B Train ERCW Header rupture: SAT

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

MCC 1BB Compl. 3C].

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

MCC 2BB Compl. 3C]. Critical Step

Cu e: Play role of AUO 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 RWR V489 0%

MRF RWR2V489 0%

STEP 15.: [7] OPERATE available A Train ERCW Pumps to maintain pressure _ SAT

between 78 psig and 124 psig.

_ UNSAT

( STANDARD : Operator will start an additional A train pump. This step is cr itical to

return ERCW supply header pressure to normal.

Critical Step

COMMENTS:

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

equipment to raise pressure.

,

FROM SEQUC YAH OPERATOR TRAI NI NG Pl-rnE NO. 423 843 4339 Apr . 04 2007 04 :22PM P7

JP M 8.1.f

Page 9 of 13

Rev. 2

( Job Pe,10rmance Che ckl ist:

STEP/STANDARD

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

SATIUNSAT

~) 14.: (6) ISOLATE B Train ERCW Head er rupture: _SAT

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

MCC 1BB Compt, 3C].

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

MCC 288 Com pt. 3C). Critical Step

9!J!: Play role of AUO 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 va lves to isolate the B ERCW

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

COM ~ 'ENTS:

Console Operator perform the following to is o lat e lhe leak:

MRF 'lWRV489 0%

( MRF 'lWR2V489 001o

STEP~ : (7) OPERATE availab le A Train ERCW Pumps to maintain pressu re _SAT

between 78 psig and 124 psig .

_ UNSAT

Operator will start an add itional A train pump. This step is critical t o

relum ERCW supply header pressure to normal.

Critical Step

Pressure is less than 78 psig , but procedure also allow s reducing flow to no n-essential

equiprr ent to raise pre ssure.

(

JPM B.1.f

Page 10 of 13

Rev. 2

Job Performance Checklist:

STEP/STANDARD SAT/UNSAT

( STEP 16.: [8] EVALUATE aligning Train A ERCW to supply Train B: _SAT

a. IF aligning 1A to 26 header is desired, THEN

PERFORM the following: _UNSAT

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 Critical Step

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

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

Cue: Play role of AVO and acknowledge the request. When 1-FCV-67-

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

STANDARD: 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.

COMMENTS:

LetA-~ ~"; C'\A '~~'

Console Operator perform the following to open 1-FC

(

0-67-1501):

\<-cJ"" \"'\?<'~

MRF RWRV489 100% D~ ""S \-('CM""'-~ .

STEP 17.: b. IF aligning 2A to 1B header is desired, THEN PERFORM the SAT

following:

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

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]. Critical Step

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

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

Cue: Play role of AVO 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%

(

JPM 8 .1.1

Page 11 of 13

Rev. 2

Job Performance Checklist:

STEP/STANDARD SAT/UNSAT

( STEP 18.: [9] START additional Lower Compartment Cooling Fans and CRDM Fans as _ SAT

required to maintain containment temperature.

_ UNSAT

STANDARD: Operator checks containment temperature and starts fans if needed.

NOTE: Ope rator may start the 1C Lower Compartment Cooler.

COMMENTS:

STEP 19.: [10] MONITOR Containment Pressure and Temperature. _ SAT

STANDARD: Operator monitors containment temperature and pressure. _ UNSAT

COMMENTS:

STEP 20.: [11] CHECK 1A and 2A ERCW header pressures and flows adequate for SAT

current alignment:

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

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

( STANDARD: Operator checks above indicators and observes parameters are normal.

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

COMMENTS:

STEP 21.: [12] RESTORE equipment: _ SAT

a. CHECK Train 8 ERCW header supplied from Train A crosstie. UNSAT

b. RESTORE the following hand switches as applicable:

18-8 CCP to A-AUTO Critical Step

18- 8 SI Pump to A-AUTO

28-8 CCP to A*AUTO

28 -8 SI Pump to A-AUTO

Cue: Play role of AUO and acknowledge the request.

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

to restore 8 train ECCS equ ipment.

COMMENTS :

JPM B.1.f

Page 12 of 13

Rev. 2

Job Performance Checklist:

STEPISTANDARD SAT/UNSAT

( STEP 22.: [13] EVALUATE isolation of non-essential A Train CCS heat loads USING - SAT

Appen dix 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 : - SAT

Appendi x F, ERCW Rx MOV Board Appendi x R Valves - UNSAT

Appendix G, ERCW MCC Appe ndix R Valves

Cue : Play ro le o f AUO and acknowledge the request.

STANDARD: Operator dispatches an AUO to perform the appendice s.

COMM ENTS:

~

( STEP 24.: [15] REFER to the following: - SAT

Appendix B, Affected Equipment List (Header 1B) - UNSAT

Appendix D, Affe cted Equipment List (Head er 2B)

Appendi x P, Potential Tech Spec Impacts

Cue : SM will refer to the Appendices.

STAND ARD : Operator ensures Appendix B referred to.

COMMENTS:

STEP 25.: [16) REFER TO AOP-M.03, Loss of Component Cooling Wate r. - SAT

Cue: Another op erator will evaluate to A OP-M.03. - UNSAT

STANDARD : Operator ensures AOP-M.0 3 referred to.

COM MENTS: Stop Tim e__

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 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

RESPONSI BLE ORGAN IZATION : _""""--'=-'-'-'-'-'-'-""-'--'<-

OPERATIONS _

(

APPROVED BY: -----'-'--'-'=-~'_'_'_

W T. LEARY _

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 PORC o

(

AOp*M.01

SON LOSS OF ESSENTIAL RAW COOLING WATER

( Rev. 15

1.0 PURPOSE

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

piping failure. .

(

Page 2 of 142

SQN LOSS OF ESSENTIAL RAW COOLING WATER

( Rev. 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.0 OPERATOR ACT IONS

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 Su pply Header 1A 2.2 Supply Hdr 1A Failure 8

to Aux Bldg

High flow ERC W Suppl y Header 18 2.3 Supply Hdr 1B Failure 12

to Aux Bldg

( High flow ERCW Supp ly 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 ruptu re 2.6 Return Hdr rupture 27

(must be diag nosed locally since M-27 indications in Aux Bldg

are not affected)

Low flow ERCW Supply Header 1A and 2A,

2.7 Supply Header 1AJ2A 38

AND Failure in Yard Area

STRA INER OIFF PRESS HIGH alarm LIT

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

Low flow ERCW Supply Header 18 and 2B, Supply Header 18/28

2.8 52

AND Failure in Yard Area

STRAIN ER OIFF PRESS HIGH alarm LIT

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

(step conti nued on next page)

(

Page 3 of 14 2

SQN LOSS O F ESSENTIAL RAW COOLING WATER

( Rev. 1 5

I STE P I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.0 OPERATOR ACTIONS (Continued)

3. (Co ntinued)

IF... GO TO SECTION PAGE

Low flow ERCW supply heade rs 1A and 2A.

AND

STR AI NER DIFF PRESS alarms DAR K

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

A ND

at least one of the follow ing alarms LIT:

2.9 Supply Header A 63

ERCW DECK SUMP LEVEL HI alarm LIT

Failure Upstream of

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

Strainer Inlet Valves

OR -

ERCW DECK SUMP PMP RUNNING

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

( OR

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],

A ND

at least one of the following alarms LIT:

2.10 Supply Header B 71

ERCW DECK SUM P LEVEL HI alarm LIT [1-

Failure Upstream of

M-15B , A-3]

Strainer Inlet Valves

ERCW DECK SUMP PMP RUNNING [l -M-

15B, D-2 or D-4]

MECH EQUI P SUMP LVL HI alarm LIT [l -M-

15A, B-6]

Loss of flow on A LL ERCW supply headers Loss of all ERCW flow 77

2.11

in modes 1-4.

END OF SECTION

(

Page 4 of 142

SQN LOSS OF ESSENTIAL RAW COOLING WATER AOP -M.01

( Rev. 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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 IF less than two Train A ERCW Pumps

AVAILA BLE,- available,

THEN

EVALUATE isolation of non-essential Train A

( CCS heat loads USING Appendix E, ecs

Heat Load Reduction [C.1]

4. CHECK 1A and 2A ERCW supply IF BOTH 1A AND 2A ERCW Headers

header pressures and flows NORMAL: FAILED,

THEN

a. Supply header pressures GO TO Section 2.9, ERCW Supply

[between 78 psig and 124 psig]: Header A Failure Prior to ERCW

Strainer Inlet Valves .

1-PI-67-493A

2-P I-67-493A

b. Supply header flows IF 1A OR 2A ERCW Header FAILED,

-_...

[expected value]: THEN

RETURN TO Section 2.0 for diagnosis.

~

1-FI-67-61

2-FI-67-61

(

Page 5 of 142

AOp *M .01

( SQN LOSS OF ESSENTIAL RAW COOLI NG W ATER

Rev. 15

STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.1 ERCW Pump Failure (cont'd)

5. CHECK 1Band 2B ERCW supply header IF BOTH 1B AND 2B ERCW Headers

pressures and flows NORMAL: FAILED,

THEN

GO TO Section 2.10, ERCW Supply

a. Supply header pressures [between Header B Failure Prior to ERCW

78 psig and 124 psig]: Straine r Inlet Valves.

1*PI-67-488A

2* PI-67-488A

b. Supply header flows [expected value]: IF 1B OR 2B ERCW Header FAILED,

THEN

1*FI-67-62 RETURN TO Section 2.0 for diagnosis.

( * 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 INVESTIGA TE abnormal amp readings:

NORMAL.

CHECK header flows and pressures.

IF amps are high due to only one pump

availab le,

THEN

EVALUATE isolation of non-essential ERCW

loads.

Page 6 of 142

SQN LOSS O F ESSENTIAL RAW COOLING WATER

( Rev . 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTA INED

2.1 ERCW Pump Failure (cont'd)

9. TRA NSFER emergency power selector

switch away from failed pump.

10. EVALU ATE need to close and place

clearance on manual discharge valve

for failed pump.

11. GO TO appropriate plant procedure.

--~.--

(

END OF SECTION

Pag e 7 of 142

( SON LOSS OF ESSENTIAL RAW COOLI NG WATER

Rev. 15

I STEP I ACTION /EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.2 ERCW Supply Header 1A Failure to Auxil iary 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 ope rators 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 Comp ressor A-A in SAFE-STOP.

[AB el. 734' , Refuel Floor]

6. START additiona l Lower Compartment

Cooling Fans and CRDM Fans as required

to maintain containment temperature.

(

Page 8 of 142

AOp*M.01

( SQN 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 (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 .

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

THEN

GO TO Section 2.7.

--~.--

c 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]

Page 9 of 142

SQN LOSS OF ESSENTIAL RAW COOLING W A T ER

( Rev. 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2. 2 ERCW Supply Heade r 1A Failu re to A uxiliary 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. Hypo chlorite Treatment

Circulation Line Isolation

[elev 669 ' TDAFWP Rm N Wall near AFW

1-FCV-3-136A]

1-67-675,-ERCW Isol to A Shutdow n

Board Roo m AlC Water Chiller

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

(

12. OPERATE ERCW Pumps as nece ssary

to perform the following:

CONTROL pressure between 78 psig

and 124 psig.

MAINTAIN suppo rt of system loads.

13. REFER TO the following :

Appendix A, Affected Equipment List

(Header 1A)

Appendi x P, Potentia l Tech Spec

Impacts .

Page 10 of 14 2

AOP-M .01

SQN LOSS OF ESS ENTIAL RAW COOLI NG WATER

( Rev. 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.2 ERCW Supply Head er 1A Failure to Auxiliary BUilding (con t 'd)

14. ENSURE all breakers reopened

USING Append ix F, Rx MOV Board

ERCW Va lves .

--..--

15. GO TO appropriate plant procedure.

( END OF SECTION

(

Page 11 of 142

SQN 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 Au xiliary Building

CAUTION: During operation , CCP and SI Pumps may expe rience bearing fail ure 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 CCP

1B-B 51 Pump

5. START additional Lower Compartment Cooling

Fans and CRDM Fans as required to maintain

containment temperature.

(

Page 12 of 142

( SQN LOSS OF ESSENTIAL RAW COOLING W ATE R

Re v . 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.3 ERCW Supply Header 1B Failure to Auxiliary Building (con t'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 Sectio n 2.8for yard area breaks.

6. NOTIFY local operat or to CLOSE

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

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

7. CHECK rupture ISOLATED. IF rupture is upstream of 1-FCV-67-82,

THEN

GO TO Section 2.8 .

--~.--

( 8. NOTIFY local operator to CLOSE

the following valve s:

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

Isol Valve

[Rx MOV Bd 1A2-A Compt. 98 1

1-FCV-67-128, Hdr 18 Supply

to Space Coo lers, AlC, & Air Compressors

[Rx MOV 8 d 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 Coole r

18 Supply Isol [O-M-27Al

Page 13 of 142

SQN LOSS OF ESSENTIAL RAW COOLING WATER AOP-M.01

( Rev. 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.3 ERCW Su pply Header 1 B Failu re to Auxili ary Build ing (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].

1-67-521 B, Hypochlorite Treatment

Circulation Line Isolation

[elev 669 ' TDAFWP Rm North Wall ]

11. OPERATE ERCW Pumps as necessary

to perform the followin g:

( * 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)

Appendi x P, Potentia l Tech Spec

Impacts .

(

Page 14 of 142

SQN LOSS OF ESSENTIAL RAW COOLING WATER

(, Rev . 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.3 ERCW Supp ly Header 1B Failure to Auxiliary BUilding (cont'd)

13. ENSURE all breakers reopened

USING Appendix F, Rx MOV Board

ERCW Valves.

14.

---.--

GO TO appropriate plant procedure.

END OF SECTION

(

Page 15 of 142

( SQN 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

AOp*M.01

( saN 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 (cont'd)

5. MONITOR the following on both Units: IF Thrust Bearing temperature

exceeds 200' F,

REACTOR COOLANT PUMPS THEN

MOTOR THRUST BEARING TEMP PERFORM the following:

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

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

AOP-M .01

SON LOSS OF ESS ENTIAL RAW COOLI NG 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 ope ning crosstie

valve. After app roximately 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 PERFORM the following :

to determine if rupture is ISOLATED:

a. IF CCS Hx 1A2 to be isolated prior to

2-FI-67-61 at expected value opening crosstie valve ,

THEN

2-PI-67-493A between 78 psig and PERFORM the followi ng:

124 psig -

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

SQN 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

shutdow n 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 O F ESSENTIAL RAW COOLING WATER

('>"

Rev. 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.4 ERCW Supply Header 2A Failure to Aux il iary Bu ilding (cont 'd)

7. (Continued) 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.

(

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. c. STABILIZE RCS temperature

USING RHR shutdown cooling.

GO TO Step 10.

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

--..- -

Injection, WHILE continuing in this

procedure. [C.2]

Page 20 of 142

SQN LOSS OF ESSENTIAL RAW COOLING WATER AOP-M.01

( 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 IF ERCW pressure is high,

as necessary to perform the following: THEN

EVALUATE opening ERCW supply

CONTROL pressure between 78 psig to Containment Spray HX and/or DG HXs

and 124 psig. to reduce pressure.

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 Equip rnent List

(Header 2A)

Appendix P, Potential Tech Spec

Impacts.

13. ENSURE all breakers reopened

USING Appe ndix F, Rx MOV Board

ERCW Valves.

14. REFER TO AOP-M.03, Loss of

Component Cooling Water.

---.--

15. GO TO appropriate plant procedure.

END OF SECTION

Page 21 of 142

AOp*M .01

SQ N LOSS OF ESSENTIAL RAW COOLING WATER

( Rev. 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.5 ERCW Supply Header 2B Fail ure to Auxiliary Building

CAUTIO N: During op eration , CCP and SI Pumps may expe rience bearing fa il ure 10

m inutes afte r loss of ERCW cooli ng.

1. DISPATCH personnel to locate rupture.

2. DISPATCH ope rators 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 CCP

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 follow ing 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

SQN LOSS OF ESSENTIAL RAW COOLI NG 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 Crossty ing A and B trai n ERCW supply headers shoul d o nly be performed if

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

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 perm its, CCS Hx OB2 should be iso lated

prior to opening crossti e va lve to prevent fouli ng BOTH heat exchangers.

After appro x. 10 min , OB2 CCS Hx will be returned to se rv ice.

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

7. CHECK ERCW Supply Hdr 2B a. CLOSE 2-FCV-67-82. Aux Bldg Hdr 2B

parameters to determine if Rupture 1501Valve. [Rx MOV Bd 2B2-B

ISOLATED : Compt. 3C]

2-F I-67-62 , at expected value b. IF desired to isolate OB2 CCS Hx

prior to opening crosstie va lve,

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

124 psig . 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 minut es,

THEN

OPEN 0-67-1501 CCS Hx OB2 Inlet.

4) GO TO Subst ep d.

(Step continued on next page)

...

Pag e 23 of 142

SQN 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)

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 des ired.

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 . Al C & Air

Compressors

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

2-FCV-67-123. Containment Spra y

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

2-FCV-67-83 . Lower Compt

Coo ler 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 contin ued on next page)

l

Page 24 of 142

c

AOp*M.01

SQN LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

I STEP I ACTION/E XPECTED RESPONSE RESPONSE NOT OBTAINED

2.5 ERCW Supply Header 2B Failu re to Auxiliary Building (con t'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]

(

Pag e 25 of 142

SQN 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 Buildi ng (cont'd)

g. START additional Lower Compartment

Cooling Fans and CRDM Fans as required

to maintain containment temperature.

10. OPERATE ERCW Pumps as necessary IF ERCW header pressure is high,

to perform the following: THEN

EVALUATE opening ERCW supply to

CONTROL pressure between 78 psig Containment Spray HX and/or DG HXs

and 124 psig. to reduce pressure.

MAINTAIN support of system loads

( 11. REFER TO the following:

Appendix D, Affected Equipment List

(Header 2B)

Appendi x 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.

END OF SECTION

Page 26 of 142

AOp*M.01

SQN 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

CAUTIONS : * During operation , CCP and SI Pumps may expe rience bearing failure

10 minutes after loss of ERCW cool ing .

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

( observa tion is required to identify rupture size and location.

1. DISPATCH perso nnel to locate rupture.

2. DISPATCH operato rs 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

AOP-M .01

SQN 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)

CAUTION 1 Ope ning crossti e valve 1-FCV-67-424 in the fo llowing step may resu lt in seve re

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

Hx 1A2 should be isolated prior to opening. After app roximately 10 mi nutes

1A2 CCS Hx will be return ed to service.

CAUTION 2 Isolation or realignment of 2A ERCW Supply Header will resul t in loss of ERCW

Cool ing water to all Train A CCS HX and there fore. a loss of CCS cooling to t he

RCPs.

CAUTION 3 The effects of flooding and loss of cool ing to critical components should be

eval uated prior to ini tiating actions to iso late o r crosstie ERCW head ers.

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

SQN LOSS OF ESSENTIAL RAW COOLING WATER

( Rev . 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2,6 ERCW Return Header Rupture in th e Auxiliary Build ing (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 aproximat ely 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

SQN 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 Tra in A ERCW pump by providing a

flow path through the D/G HX.

3. h. OPEN A tra in ERCW supplies to

D/G HXs to provide a flow path

for running Train A ERCW pump:

ERCW Headers

DG NOR Su pplv 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 perfo rm the following:

CONTROL pressure between

78 psig and 124 psig .

MAINTAIN support system

load s.

NOTE: Unit 2 will be tripped due to lack of ERCW to the CCS HX 2A 112A2.

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

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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 OB1 10B2 Disch Valve to Hdr B

OPE N

ENSURE 0-FCV-67- 151, CCS

HX OB1/0B2 Disch-Valve to Hdr A

CLOSED. [Rx MOV Bd 1A2-A

Com pt. 80] _

I. CLOSE Header A Discharge to Cold

Water Channe l Isolations:

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

Com pt. 3C]

0-FCV-67-364

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

m. DISPATCH an operator to CLOSE

DG returns to Hdr A:

[Diesel Bldg, outside DG Rooms]:

1-67-5 11A, 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

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2.6 ERCW Return Header Rupture in the A uxili ary Build ing (cont'd )

CAUTION: The eff ects 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 a. GO TO Step 5.

Header B (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 CCP

2B-B CCP

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].

(step continued on next page)

(

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2.6 ERCW Return Header Rupture i n the A uxi li ary Bu ilding (cont'd )

NOTE : CCS HX 1A111 A2 outlet flow is to Discharge Header 8 . The follow ing substep

isolates ERCW to this HX.

4. f. CLOSE 1-FCV-67-223, Hdr 18 to

Hdr 2A Isol Valve

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

g. ENSURE only one Tra in 8 ERCW pump

RUNN ING.

NOTE : Substep h provides protection for the in service Tra in 8 ERCW pum p by providing a

flow path through the DIG HX.

h. OPEN 8 train ERCW supplies to

DIG HXs to provide a flow path for

c the running Train 8 ERCW pump :

ERCW Headers

DG NOR Supply ALT Supp ly

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

1. Unit 1 Only:

PERFORM the following:

1) TR IP reactor.

2) STOP RCPs.

3) GO TO E-O, Reacto r Trip or

Safety Injection .

--~.-- (step continued on next page)

(

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2.6 ERCW Return Header Ruptu re 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 8 d 282-8

Compl. 3C)

O-FCV-67-365. [D iesel A ux 8 d 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 ap pe ndixes :

Appendix 8 , Affected Equipment

List (Header 18)

Append ix 0 , Affected Equipment

List (Header 2B)

(step continued on next page)

Pa g e 34 of 142

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2.6 ERCW Ret urn Header Rup tu re in the Auxiliary Building (con t'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 des ired,

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 08 1/082 Disch Vlv to Hdr 8.

2) CLOSE the following valves:

2-FCV-67-128, Hdr 28 Supply

to Space Coole rs, 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

Coole r 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 14 2

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

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2.6 ERCW Return Heade r Rupture in the Au xiliary 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 temperatu re.

( 7. REFER TO Appendix p . Potential Tech

Spec Impacts.

8. ENSURE all breakers ope ned

USING the following appendixes:

App endix 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

Pa ge 37 of 142

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

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 opera tors 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

[ERC W Pumping Station]

3. START additional Train A ERCW

Pumps as requ ired to maintai n pressure

betwe en 78 psig and 124 psig.

(

Page 38 of 142

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

4. MONITOR the following on both Units: IF Thrust Bearing temperature

exceeds 200°F,

REACTOR COOLANT PUMPS THEN

MOTOR THRU ST BEARING TEMP PERFORM the following:

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

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.

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

RUNN ING.

(

Pa ge 39 of 142

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(

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

7. STO P 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]

Pag e 40 of 142

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

CAUTION Open ing crosstie valve 1-FCV-67-424 (in following step) may result in severe

fouling/blockage of 1A1I1A2 CCS Heat Excha nger. If plant co nditions and time

permits , CCS Hx 1A 2 should be isolated prior to opening cross tie valve. After

app rox imately 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

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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

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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

a.

......

GO TO Notes prior to step 19.

b. EVALUATE flood damage at CCW

Building (IPS).

Page 43 of 142

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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 a. GO TO Step 17.

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.

--~.--

Page 44 of 142

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

NOTES: * Tra in A ERCW header failure in the yard area could result in all Tra in A head er

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

isolat ed , strainer HIGH DIFF PRESSU RE alarm may indicate the failed head er.

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

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

19. CHECK Stra ine r Diff Press High alarms IF window 0-2 and C-3 are both illuminated.

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

GO TO step 20.

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 is illum inated,

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

Befor e Strainer. [ERCW MCC 2AA

Compl. 3C] .

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

Aux Bldg . [Rx MOV Bd 2A2-A

Compl. 3C]

Page 45 of 142

b.

..

GO TO Note prior to step 2 1.

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2.7 ERCW Supply Header 1A12A Fail ure in Yard A rea (co nt'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

possib le.

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

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2.7 ERCW Supply Header 1A/2A Failure in Yard A rea (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 a. RESTORE 2A ERCW header:

parameters at expected values:

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

1-FI-67-61 Before Strainer- [ERCW MCC Bd

1-PI-67-493A 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.

b. GO TO step 25.

(

Page 47 of 142

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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 a. RESTORE 1A ERCW Header:

at expected values:

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

2-FI-67-61 at expected value Before Strainer. [ERCW MCC 1M

Compl. 3C]

2-PI-67-493A at expected value

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.

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.

Page 48 of 142

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

CAUTION Crossty ing 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 a. .GO TO step 26.

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 _

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

pressure indications.

24. CHECK 28 ERCW header pressures and START additional "8" Train ERCW pumps

flows NORMAL: as necessary

2-FI-67-62, at expected value ISOLATE non-essential ERCW loads

as necessary.

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

124 psig DO NOT CONTINUE UNTIL header

pressure and flow are acceptable

for the current alignment.

l Page 49 of 142

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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 8 1Pump 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.

c. Page 50 of 142

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2.7 ERCW Supply Header 1A/2A Failure in Yard Are a (con t'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

Appendix 5} , ERCW MCC Appendix R

Valves

30.

---.--

GO TO appropriate plant procedure.

END OF SECTION

c..

Page 51 of 142

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2.8 ERCW Supply Header 1B/28 Failure in Yard Area

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

10 minu tes 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

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2.8 ERCW Supply Header 1B/2B Failure in Ya rd 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 T O LOCK:

1B-B CCP

1B-B SI Pump

2B-B CCP

2B-B SI Pump

b. DISPA TCH opera tor to place Tra in B

Aux Air Compressor in SAF E STOP .

[Aux Bldg, 734' elev , Refue l Floor]

7. ISOLATE 1B/2 B ERCW Crosstie Header:

CLOSE 1-FCV-67-24 , ERCW Straine r

1B-B 1501Val ve

[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

SQN LOSS OF ESSENTIAL RAW COOLING WATER

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(

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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

a.

..

GO TO Notes prior to step 10.

b. EVALUATE flood damage at CCW Bldg

(IPS).

c. GO TO appropriate Plant Procedure .

--~.--

(

Page 54 of 142

SQN LOSS OF ESSENTIAL RAW COOLING W ATE R

Rev. 15

(

I STEP I AC TION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.8 ERCW Supply Header 1B/2B Failure i n 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 cross tie header valves at the IPS have been isolated the HIGH DIFF

PRESSURE alarm may indicate the failed header.

10. CHECK Strainer Differential Pressure IF wi ndow D-5 and C-6 are both illuminated,

High Alarms on O-XA-55-27A are da rk: THEN

GO TO Step 11.

HEADER 18-B STRAIN ER DIFF

PRESS HIGH (window D-5)

HEAD ER 28-8STRAIN ER DIFF

PRESS HIGH (window C-6) IF window D-5 is illumi nated ,

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 Stra iner

[ERCW MCC 2BB Compl. 3C].

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

[Rx MOV Bd 282-8 Com pt. 6C]

b.

..

GO TO Note prior to Step 12.

.c... Pag e 55 of 142

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(

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

11. ISOLATE 1B ERC W 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 Ruptu re is ISOLATE D:

a. CHECK 1B ERCW header a. RESTORE 2B ERCW Header:

para meters at expected values :

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

1-FI-67-62 header Isolation before strainer

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

1-PI-67-488A

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

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

GO TO Step 11 to isolate 1B header.

b. GO TO the Note before step 16. ---~

a-

(

P age 56 of 142

AOP*M.01

SQN LOSS OF ESSENTIAL RAW COOLING WATER

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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 a. RESTORE 1B ERCW Header:

determine if rupture is isolated:

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

2-FI-67-61 Before Strainer

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

2-PI-67-493A

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 8 ldg.

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

c.

..

GO TO Cautions prior to Step 16.

Page 57 of 142

AOp*M .01

( SQN LOSS OF ESSENTIA L RAW COOLING WATER

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 urge ntly requi red fo r Unit 1 Train 8 CCS related equipment.

LCO 3.0.3 may be applicable.

14. EVALUATE aligning ERCW Hdr 2A to

supply 1B loads:

a. CHECK additional cooling needed for 1B a. GO TO the note before step 19.

b.

train equipment:

EVALUATE crosstying 2A and 1B ERCW

a-

supply headers as follows:

c 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]

(

Page 58 of 142

AOp*M.01

( SQN 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)

15. CHECK 2A ERCW header pressure and

flow NORMAL:

a. CHECK the following: a. START additional "A" Train ERCW

pumps as necessary.

2-FI-67-6 1. at expected value

ISOLATE non-essential ERCW loads

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

and 124 psig as necessary.

DO NOT CONTINUE UNTIL header

pressure and flow are ACCEPTABLE

for the current alignment.

b. GO TO Step 18.

(

Page 59 of 142

SQN 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 a. GO TO Slep 19.

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.

Page 60 of 142

SQN LOSS OF ESSENTIAL RAW COOLING WATER

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I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.8 ERCW Supply Heade r 1B/2B Failu re in Yard Area (con t'd)

17. CHECK 1A ERCW header pressures and START additional "A" Train ERCW

flows NORMAL: pumps as necessary

1-FI-67-61, at expected value

ISOLATE non-essential ERCW loads

1-PI-67-493A, between 78 psig and as necessary.

124 psig

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 equi pment

as desired:

1B CCP to A-AUTO

18 SI Pump to A-AUTO

28 CCP to A-AUTO

28 SI Pump to A-A UTO

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 14 2

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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 pressu re between 78 psig

and 124 psig .

21 . ENSURE all breake rs reopened

USING the following :

Append ix 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, Poten tial Tech Spec

Impa cts

23 . REFER TO AO P-M .03 , Loss of

Component Co oling Water.

24.

--.*- -

GO TO appropriate plant procedure .

END OF SECT ION

(

Page 6 2 of 142

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2.9 ERCW Supply Header A Failu re Upstream of ERCW Straine r Inlet Valv es

CAUTION: Dur ing operation, CCP and SI Pumps may experience bearing fail ure

10 minutes after lo ss 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 Appendi x 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 ESS ENTIAL RAW COOLING WATER

Rev. 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.9 ERCW Supply Header A Failu re Ups tream of ERCW Strainer Inlet Valves (con t'd)

CAUTION: Loss of 2A ERCW Supply Header aff ects both Units ' Train A CCS Heat

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

critical to prevent tripping both Units.

3. MONITOR the following on both units: IF Thrust Bearing temp exceeds 200' F,

REACTOR COOLANT PUMPS THEN

MOTOR THRUST BEARING TEMP PERFORM the following:

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

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.

4. ENSURE 1B-B and 2B-B CCPs

RUNNING.

Page 64 of 142

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( 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

SQN 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 statio n and are normally locked open.

7. ISOLATE Train A ERCW Header ruptu re:

a. CLOSE 1-FCV-67-492. Header 1A Isol a. CLOSE 1-VLV-67-518A, ERCW

Before Straine r [ERCW MCC 1M Supply Isolation Valve.

Cornpt , 3C]

b. CLOSE 2-FCV-67-492 , Header 2A Isol b. CLOSE 2-VLV -67-518A , ERCW

Before Stra iner. [ERCW MCC 2M Supply Isolation Valve .

Compt.3C]

8. OPERATE available Train B ERCW

Pumps as necessary to perfo rm the

followinq;

CONTROL pressure between 78 psig and

124 psig.

MAINTAIN support of system loads.

Page 66 of 142

c SQN 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 Stra iner 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 heade r 18 to supply 2A: IF 18 ERCW header will NOT be aligned

to supply 2A header,

a. IF desired to isolate 1A2 and 2A2 CCS THEN

Hx prior to opening crosstie valve, PERFORM the following:

THEN

PERFORM the following: a. TRIP BOTH Unit's Reactors.

1) CLOSE the following CCS Hx Inlet b. STOP both units RCPs.

valves:

c. IF in Modes 1, 2, or 3,

1-67-1501 CCS Hx 1A2 THEN

2-67-1501 CCS Hx 2A2 GO TO E-O,

WHILE continuing in this procedure.

2) WHEN CCS Inlet valves CLOSED,

THEN

OPEN 1-FCV-67-424

--~.--

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

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

and

THEN

RECORD Time _

STABILIZE RCS Temperature

USING RHR shutdown Coolin g.

GO TO Step 15.

(Step Continued on next page)

Page 67 of 142

SQN LOSS O F ESSENTIAL RAW COOLING WATER

( Re v . 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:

1-67-1 501 CCS Hx 1A2

2-67-150 1 CCS Hx 2A2

b.

4) GO TO Substep c ,

..

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

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

d. ENSURE 2-FCV-67-22 3, Hdr 2A to Hdr 1B

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

10. EVALUATE if 2B header should be crosst ied

with 1A header:

a. CHECK if add itional flow for 1A heade r a. GO TO step 11.

is requ ired 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].

Pag e 68 of 142

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SON LOSS OF ESSENTIAL RAW COOLING WATER

( Re v. 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.9 ERCW Sup ply Heade r A Fail ure Upstream of ERCW Strain er 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 START additional "B" Train ERCW

and pressures NORMAL: pumps as necessary.

l-FI-67-62

ISOLATE non-essential ERCW loads

2-FI-67-6 2 as necessary.

1-PI-67 -488A

DO NOT CONTINUE UNTIL header

2-PI-67-488A pressure and flow are adequate for

current alignment.

14. RESTORE equipment:

a. CHECK Train A ERCW header a. GO TO step 16.

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 5 1Pump to A-AUTO

(

Page 69 of 142

SQN 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

Appendix G, ERCW MCC Valves

17. REFER to the following appendices :

Appendix A, Affected Equipment List

(Header 1A)

Appendix C, Affected Equipment List

(Header 2A)

Appendi x 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 m ay experience bearing failure

10 minutes after loss of ERCW cooling .

1, STOP and LOCK OUT all T rain B ERCW

Pumps,

2, DISPATCH operators with rad ios

to perform the foll owi ng:

PERFORM Appendix F, Rx MOV Board

ERCW Valve s

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

PERFORM Appendi x G , ERCW MCC

Va lves , [ER CW Pumping Station s]

ENSURE all pumping station watertight

doors are CLOSED. [E RCW Pumping

Station] ,

3, ENSURE 1A-A and 2A- A CCPs

RUNNI NG.

4, STOP and LOCK OUT affe cted

equipmen t:

a, PLACE the following pumps in

PULL TO LO CK:

1B-B CCP

1B-B SI Pump

2B-B CCP

2B- B SI Pump

b. DISPATCH operator to place Tra in B

Aux Ai r Compressor in SAFE STOP ,

[Aux Bldg , 734' elev, Refuel Floor]

Page 71 of 142

SQN LOSS OF ESSENTIAL RAW COOLI NG 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:

a. CLOSE 1-FCV-67-489, Header 1B 1501 a. CLOSE 1-VLV-67-518B, ERCW Supply

Before Strainer [ERCW MCC 1B-B Isolation Valve

Compl. 3C].

b. CLOSE 2-FCV-67-489. Header 2B 1501 b. CLOSE 2-VLV-67-518B , ERCW Supply

Before Strainer [ERCW MCC 2B-B Isolation Valve

Cornpt, 3C].

7. OPERATE available Train A ERCW

Pumps to maintain pressure

between 78 psig and 124 psig.

l

Page 72 of 142

AOp*M .01

SON LOSS OF ESSENTIAL RAW COOLING WATER

( Rev . 15

I STEP I ACT ION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

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

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

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

may be app licable.

CAUTION 2 Opening of crossti e valve 1-FCV-67-147 may result in severe fOUli ng or flo w

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

AOP-M .01

SQN LOSS OF ESSENTIAL RAW COOLING WATER

( Rev . 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.10 ERCW Supply Header B Failu re Upstrea m of ERCW Strainer Inlet Valves (can t'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

SQN LOSS OF ESSENTIAL RAW COOLING WATER

( Rev. 15

I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.10 ERCW Supply Header B Fail ure Upstream of ERCW Strainer Inl et Valves (cont'd)

11. CHECK 1A and 2A ERCW header START additional "A" Train ERCW

pressu res and flows adequate for current pumps as necessary.

alignment:

ISOLATE non-essential ERCW loads as

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

at expected value

DO NOT CONTINUE UNTIL header

1-PI-67-493A and 2-PI-67-493A pressure and flow are adequate for

current alignment.

12. RESTORE equipment:

a. CHECK Train 8 ERCW header a. GO TO step 14.

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 8 ldg, 734' elev, Refuel Floor]

Page 75 of 142

c SQN LOSS OF ESSE NTIAL 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 Appendi x 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.

---a--

GO TO appropriate plant procedure.

END OF SECTION

(

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2.11 Loss of all ERCW flow [C.3]

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 OR

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 TRIP PED: IF turbine CANNOT be tripped,

THEN

Turbine stop valves CLOSED. ENSURE MSIV and MSIV bypass valve

handswitches in CLOSE position .

3. PLACE the followi ng equipment

in STOP/PULL TO LOCK:

CCPs

Reactor Coolant Pumps

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

4. DEPRESS EMERGENCY STOP

pushbuttons for all diesel generators.

5. MONITOR at least one shutdown board AITEMPT to restore power to

energized from start bus. 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.

6. PLACE the following equipment switches

in PULL TO LOCK:

ERCW pumps

RHR pumps

Si pumps

Contai nment spray pumps

7. NOTIFY 8M and STA to evaluate the

following:

EPIP- 1, Emergency Plan

Classifica tion Matrix

Tech Spec LCO 3.0.3, 3.7.4,

and 3.8.1.1

Page 78 of 142

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2.11 Loss of all ERCW fl ow (con t'd)

CAUTION 1 Temporary cooling water supply from HPFP to one CCP should be est ablished

as soon as possible.

CAUTION 2 CCS for the uni t NOT supplying SFP cooling wi ll have a faster heatu p rate.

The refore, establishing temporary cooli ng to a CCP on the unit NOT supplying

th e SFP is mo re 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 Appe ndix 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

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2.11 Loss of all ERCW flow (con t'd)

NOTE 1 Appe ndix 0 contains two copies of handout pages identifying continuous action steps.

NOTE 2 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 tempe rature:

a. IF T-cold is less than 547°F

and dropping ,

THEN

PERFORM the following:

1) ENSURE atmospher ic relief valves

and s!eam dumps CLOSED.

2) CHECK TO AFW pump RUNNING 2) GO TO Step 10.

3) STOP and PULL-TO-LOCK

MO AFW pumps.

4) CONTROL AFW flow to 4) IF TO AFW flow CANNOT be adjusted,

between 440 and 600 gpm: THEN

DISPATCH AUO(s) to perform

ADJUST TO AFW speed

EA-3-4 , Local Alignment of

USING EA-3-1.

TO AFW LCV Backup Air Supply .

OPERATE TO AFW LCVs

as necessary

(if essentia l air availab le).

5) MAINTAIN total feed flow greater

tha n 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.

(

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2.11 Loss of all ERCW fl ow (con t'd )

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. 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.

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

Page 81 of 142

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2.11 Loss of all ERCW flow (cont'd)

11. CONTROL S/G narr ow range levels IF S/G level is greater than 50%.

between 10% [25% ADV] THEN

and 50%: STOP AFW pumps as neces sary .

CONTROL TO AFW pump speed

(if running) ,

CONTROL AFW LCVs.

12, ENSURE Steamlines and Main

Feedwater ISOLATED:

a. ENSURE MSIV handswitches in CLOS E

position .

b. ENSURE MSIV bypass valves CLOS ED,

c. ENSURE MFW Isolation Valves

CLOSED.

d. ENSURE Slowdown Isolation Valves

CLOSED .

NOTE FRPs are not applicab le. Shift Manage r and T SC should be notified of any red or

orang e path cond itions.

13. MONITOR FR-O status trees

for information only.

(

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2.11 Loss of all ERCW flow (cont'd)

14. CHECK RCS ISOLATED:

a. ENSURE Pressu rizer 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 d. NOTIFY Chern Lab to CLOSE valves .

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

(

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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

dumpbac k controller L1C-2-3 in MANUAL

and

CLOSE dumpback valve.

c. MONITOR hotwellievel stable or c. DISPATCH operator to locally isolate CST

dropping. from hotwell USING EA-2-1, Condenser

Makeup Isolation.

d. ESTABLISH CST makeup as required.

(

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2.11 Loss of all ERCW flow (cont'd)

17. MONITOR containment vacuum relief

normal :

a. CHECK containment pressure a. GO TO Step 18.

less than 1.0 psig.

b. VERIFY containment vacuum relief b. OPEN valves [M-9]

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 Valve s

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

b. ENSURE VCT Outlet Valves

LCV-62-132 OR LCV-62-13 3 CLOSED .

(

Page 85 of 142

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(-, SQN LOSS OF ESSENTIAL RAW COOLING WATER

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2.11 Loss of all ERCW now (cont'd)

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

could resu lt in t he rma l s hoc k to RCP se al s . If all s eal cooling h as been

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

NOTE 1 CCS heatup rate will be slower for unit suppl ying Spent Fue l Pit cooling .

NOTE 2 If RCP sea l injection and the rmal barrier flowpaths are isolated , subsequent

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

20. MONITOR RCP seal coo ling ava ilable:

a. CHECK Train A CCS Outlet a. ISOLATE Therma l Barrier Cooling

temperature less tha n 130°F. by perform ing the following :

( [TR-70-161]

1) STOP Thermal Barrier Booster Pumps

on affected Unit AND

PLACE in PULL-TO-LOCK.

2) CLOSE Th ermal Barrier Valv es :

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)

......

Pag e 8 6 of 14 2

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STEP I ACTION/EXPECTED RESPO NSE RESPONSE NOT OBTAINED

2.11 Loss of all ERCW flow (cont'd)

20. b. CHECK RCP seal cooling flow b. IF The rmal barrier Cooling

in service : AND RCP seal injection flow are lost.

THEN

CCP running and supplying RCP PERFORM the following:

Sea l Injection flow

OR 1) DISPATCH operator to locally isolate

RCP seals by performing Appendix N,

Thermal barrier cooling in service . Local Isolation of RCP Seal Injection.

2) CLOSE FCV-62-61 or

FCV-62-63. [M-5]

Page 87 of 14 2

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

CAUTION If thermal ba rrier cooling is NOT in service , restarting CCP prio r to

locally isolating seal inj ecti on flowpath (Appendix N) could result in

t hermal shock to seal package.

21 . MONITOR if CCP can be sta rted:

a. CHECK temporary cooling water supply a . WHEN temporary cooling water is

to CCP oil coolers establis hed. established to CCP,

THEN

PERFOR M Substeps 21.b through f.

GO TO Step 22.

b. CHECK RCP Thermal Barrier Cooling b. WHEN seal injection flowpath

in service . is isolated (Appendix N).

THEN

PERFORM Substeps 21.c through f.

GO TO Step 22.

c. START CC P supp lied by temporary

cooling water.

d. DISPA TCH opera tor to locally

control charging flow USING

VLV-6 2-535 or VLV-62-536

(B-B CCP room).

e. MONITOR CCP beari ng and motor

windi ng temperatures.

(step continued on next page)

Page 88 of 142

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2.11 Loss of all ERCW flow (cont'd)

21. f. CONTROL CC P flow:

1) CHECK CCPIT valves CLOSED . 1) GO TO Step 22.

2) CHECK seal injection flowpath 2) ESTABLISH Normal Charging flowpath :

available.

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

OPEN .

b) ADJUST charging flow USING

FCV-62-93 (if contro l air available)

or Local contro l to maintain

Pressu rizer level.

c) GO TO Step 22.

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) .

Pag e 89 of 142

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2.11 Loss of all ERCW fl ow (co nt'd)

22. MONITOR pressurizer pressure:

a. Pressurizer pressure a. IF pressure less than 2210 psig

between 22 10 and 2260 psig . and dropping,

THEN

PERFORM the following:

1) ENSURE pressurize r PORVs

CLOSED.

IF pressurizer PORV

CANNOT be closed ,

THEN

CLOS E associated block valve .

( 2) IF SI signal is NOT actuated ,

THEN

ENSURE all avai lable

pressurize r heate rs ON .

b. IF pressure greater than 2260 psig

and rising .

THEN

PERFORM the followi ng:

1) ENSURE all pressu rizer

heaters OFF.

2) ENSURE pressure controlled

USING pressu rizer PORV(s).

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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 a. IF low pressurizer level is the result of

pressurizer level. RCS cooldown,

THEN

STOP RCS cooldown.

IF NO CCP is running,

THEN

GO TO Step 24.

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.

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2.11 Loss of all ERCW flow (cont'd)

24. MONITOR if RCS cooldown

should be started :

a. CHECK Pressurizer level a. IF pzr level CANNOT be maintained

greater than 10% [20% ADV]. greater than 10% [20% ADV] .

THEN

PERFORM the following :

1) INITIATE SI signal.

2) GO TO Step 25 to initiate

RCS cooldown and depressurization.

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 .

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2.11 Loss of all ERCW flow (cont'd)

CAUTION Allowing RCS pressure to drop below 100 psig prio r to isolating CLAs

could result in nitrogen injecti on into the RCS.

NOTE 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 a. PERFORM the following:

narrow range level

1) CONTROL atmospheric reliefs

greater than 10% [25% ADV].

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.

b. MAINTAIN T*cold cooldown rate

less than 100'Flhr.

=--

c. DUMP steam from Intact SIGs c. DUMP steam from Intact SIGs

USING atmospheric reliefs. USING EA* 1*2, Local Control of SIG

PORVs.

d. WHEN RCS pressure

between 100 psig and 200 psig,

THEN

STOP cooldown and

MAINTAIN current plant conditions.

(

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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 b. PERFORM the following:

dampers CLOSED:

1) ACTUATE PHASE A AND CNTMT

Panel 6K CNTMT VENT GREEN VENT ISOL.

Panel 6L CNTMT VENT GREEN . 2) ENSURE dampers CLOSED.

3) NOTIFY TSC to determine corrective

action for dampers without power or

indication.

c. Phase A valves CLOSED: c. PERFORM the following :

Panel 6K PHASE A GREEN 1) ACTUATE PHASE A.

Panel 6L PHASE A GREEN. 2) ENSURE valves CLOSED.

3) NOTIFY TSC to determine corrective

action for dampers without power or

indication.

(

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28. MONITOR Phase B status: PERFORM the following :

Phase B NOT AC TUATED a. ENSURE PHASE B AC TUATED.

Containm ent pres sure b. ENSURE Phase B valves CLOSED :

less than 2.81 psig.

Pa nel 6K PHASE B GREE N

Pan el 6L PHASE B GREEN.

c. RESET Containment Spray.

29 . CHECK reactor SUBCRITICAL: CONTROL atmospheric reliefs

to stop S/G de pressurizat ion.

IRM startup rate zero or negative

ALLOW RCS to heat up.

SRM startup rate zero or neg ative.

(

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I STEP I ACTION /EXPECTED RESPONSE RESPONSE NOT OBTAIN ED

2.11 Loss of all ERCW flow (cont'd)

30. CHECK whether cooldown

should be stopped:

a. CHECK RCS pressure between a. CONTINUE depressurizatio n until RCS

100 psig and 200 psig. 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. NOTIFY TSC to EVALUATE operating one

RHR pump to restore pressurizer level.

32. CHECK Core Exit TCs IF at least 5 core exit TCs

less than 1200°F. greater than 1200 0 F AND rising,

THEN

GO TO SACRG-1, Severe Accident Control

---.--

Room Guideline Initial Response

Pag e 96 of 142

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33. CHECK CCPIT flow NOT required: IF criteria NOT met,

THEN

GO TO Step 29.

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.

(

c. RCS pressure stable or rising.

d. Pressurizer level

greater than 10% [20% ADV].

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.

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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: IF ECCS flow is required,

THEN

Pressurizer level is maintained PERFORM the following:

greater than 10% [20% ADV]

1) OPEN CCPIT valves:

RCS subcooling based on core exit

TICs greater than 40'F. * 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

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37 . MAINTA IN pressurizer level

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

a. CON TROL charg ing flow to mainta in

pressurizer level.

b. OPERATE Reactor Vessel Head Ve nts

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 ach ieved ,

THEN

CLOSE Head Vent Valves.

38. GO TO Step 48 .

(

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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 c. CONTROL feed flow as necessary.

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.

(

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2.11 Loss of a ll 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 a. STOP RCS depressurization and

core exit-T/Cs greater than 140' F. ESTABLISH required subcoo ling.

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

Natural Circulation Cooldown NO CRDM

Fans Runn ing - 140' F Subcooling.

c. INITIATE RCS depressurization

USING one pressurizer PORV.

44 . CONTINUE RCS coold own and

depressurization:

a. MAINTAIN T-cold cooldown rate

less than 50' F/hr.

b. MAINTAIN RCS subcooling based on b. STOP RCS depressurization and

core exit T/Cs greater than 140' F. ESTABLISH required subcoolinq,

c. MAINTAIN RCS T-cold and pressure

within limits USING Tec h Spec

temperature/pressure limit curves .

Page 101 of 142

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I STEP I ACTIO N/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.11 Loss of all ERCW flow (cont'd)

NOTE "Unexpected pressurizer level changes indicative of vesse l voidi ng" 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 a. GO TO Step 46 .

of steam voids :

unexpected pressurize r level

changes indicative of voiding

RVLl S 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.

46 . WHEN RCS pressure

less than 1000 psig.

THEN

ISOLATE CLAs:

a. DISPATCH personnel to restore power to

CLA isolation va lves USING EA-20 1-1,

480V Board Room Breaker Alignments.

b. CLOSE CLA isolation valves .

c. NOTIFY local personnel to remove power

to CLA isolat ion valves USING EA-201-1 ,

480 V Board Room Breaker Alignme nts.

l

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I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OBTAINED

2.11 Loss of all ERCW flow (cont'd)

CAUTION The up per head should be allowed to cool f or a minimum of BB hours

prior to complete depressu rization of the RCS.

47. MAINTAIN plant condit ions 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

eve nt of loss of ERCW.

49 . SHUT DOWN unnecessary plant

equipment:

REFER TO 0-GO-12 , Realignment of

Secondary Equipment Followi ng

ReactorlTurbine Tr ip.

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I STEP I ACTION/EXPECTED RESPONSE RESPONSE NOT OB TAI NED

2.11 Loss of all ERCW flow (cont'd)

50. ENSURE RCS BORATED for natu ral

circulation cool down to col d shutdo wn

conditio ns USING EA-68-4 , Emergency

Bo ration.

51. WHEN sufficient ERCW avail able to

support plant coo ldown ,

T HEN

EVALUATE plant cooldown to Mode 5.

END OF SECTION

Page 104 of 142

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3.0 SYMPTOMS AND ENTRY CONDITI ONS

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 PU MP 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 PU MP 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 UNDER VOLTAGE

D-5 HEADER 18-8 STRAINER DIFF PRESS HIGH

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

E-3 ERCW PUMP MOTOR OVERLO AD

E-4 ERCW/CCS PUMP MOTOR TRIP

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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-67-4 37A. 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

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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-67-6 1, Hdr 2A

2-FI-67-62 , Hdr 2B

4. Indication of flood ing in the Reactor, Au xiliary , or T urbine Buildings.

5. Visua l indicatio n of an ERCW pip ing rupture .

3.2 Entry Conditions

AOP-T.01

(

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(

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. AOP-P.01 , Loss of Offsite Power

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. 45N60 1-1

(

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Page 1 of 1

APPENDIX A

AFFECTED EQUIPMENT LIST (HEADER 1A)

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)

Note 1: Damage is imminent unless equipment is stopped.

Note 2: Stop equipment if ERCW supply from 1B is not available.

Note 3: Containment parameters may increase due to inadequate cooling.

Not e 4: Start redundant equipment and secure affected components.

Note 5: ERCW not normally required.

Note 6: REFER TO AOP-R.04, Reactor Coolant Pump Malfunctions, if alarming.

l Page 109 of 142

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Page 1 of 1

APPENDIX 8

AFFECTED EQUIPMENT LIST (HEADER 18)

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: Damage is imminent unless equipment is stopped.

Note 2: Stop equipment if ERCW supply from 1A is not available.

Note 3: Containment parameters may increase due to inadequate cooling.

Note 4: Start redundant equipment and secure affected components.

No te 5: ERCW not normally required.

Note 6: REFER TO AOP-R.04, Reactor Coolant Pump Malfunctions, if alarming.

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Page 1 of 1

APPENDIX C

AFFECTED EQUIPMENT LIST (HEADER 2A )

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)

Note 1 : Damage is imminent unless equipment is stopped.

Note 2 : Monitor RCPs for TRIP criteria. Multiple systems affected.

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

Note 3: Containment parameters may increase due to inadequate cooling.

Note 4: Start redundant equipment and secure affected components.

Note 5: ERCW not normally required.

Note 6: REFER TO AOP-R.04, Reactor Coolant Pump Malfunctions, if alarming.

c.. Page 111 of 142

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Page 1 of 1

APPENDIX D

AFFECTED EQUIPMENT LIST (HEADER 28)

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 : Damage is imminent unless equipment is stopped.

Note 2 : Multiple systems affected.

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

Note 3: Containment parameters may increase due to inadequate cooling.

Note 4 : Start redundant equipment and secure affected components.

Note 5 : ERCW not normally required.

Note 6 : REFER TO AOP-R 04, Reactor Coolant Pump Malfunctions, if alarming.

(

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Page 1 of 1

APPENDIX E

CCS HEAT LOAD REDUCTION [C.1]

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

heat load on Train A CC S Heat Exchangers. Th e loads liste d below are in the order of least seve re to

most severe plant impact. (1-47W859-2 and 2-4 7W859 -3)

1. W aste Gas Co mpre ssors 70-51 8, INLET (690, by drto WGC)70-520, OUTL ET (690, by dr to WGC)

2. Sample Heat Exchangers 70-57 3, INLET (690, Outside RHR Hx Rm)

FCV-70-183, RETUR N

3. Post-A cciden t Sample Coolers 70-7 66, INLET (706. PASFarea)

4. Hot Sample Chillers SAM E AS SAMP LE HX

5. Excess Letd own Heat Exchanger FCV-70-143, INLET

FCV-70-85, OUTLET

6. Spent Fuel Pit Heat Exchangers O-FCV-70-40, 41 INL ETS

O-FCV-70-1 , 11 OUTLETS

7. RCP Thermal Barrie rs FCV-70-133,134 INLETS

FCV-7 0-87,90 OUT LETS

8. Letdown Heat Exchange r 70-574 , INLET (714, Near Letdown Hx Rm)

9. Seal Water Hea t Exchanger 70-581 , INLET (690, Outside RHR Hx Rm)70-585, OU TLET (690, Outside Seal Water Hx Rm)

10. RCP Upper & Low er Oil Coo lers FCV-70-139,140,14 1 INLETS

FCV-70-89, 92 OU TLETS

c.. Pa ge 1130f 142

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SQN L OSS OF ESSENTIAL RAW COOLING WATER

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Page 1 of 2

APPENDIX F

RX MOV BOARD ERCW VALVES

NOTE 1 When power is placed on the following valves, record lime breaker is close d and

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

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

remove power.

NOTE 2 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 breake rs.

c. NOTIFY Unit Operator to log Append ix R breake rs CLOSED.

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

e. OPEN breake rs 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 Compresso rs

Rx MOV Bd 1A2-A CampI. 8B Hdr 1B to Hdr 2A Isol Valve 1-FCV-67-223

Rx MOV Bd 1A2-A Cam pI. 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 Coole rs, 1-FCV-67-128

AlC , & Air Compressors

(

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Page 2 of 2

APPENDIX F

RX MOV BOARD ERCW VALVES

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.

PERFORM the following :

a. TRA NSFER control power to AUXILIARY

b. CLOSE breakers

c. NOTIFY Unit Operator to log Appendi x 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.

r:

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

(,

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Page 1 of 1

APPENDIXG

ERCW MCC VALVES

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

opened in narrative log . An ope rator shall remain at the brea ker and in conta ct with

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

power.

PERFORM the followi ng:

a. TRANSFER cont rol powe r to AUXILIARY

b. CLOSE breake rs

c. NOTIFY Unit Ope rator to log Appe ndix R breakers CLOSED

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

e e.

f.

OPEN breakers when directed by the Control Room.

NOTIFY Unit Operator to log Appendix R breakers OP EN.

BREAKER VALVE NAME VALVE NUMBER

ERCW MCC 1M Compl. 3C Hdr 1A Isol Before Strainer 1-FCV-67-492

ERCW MCC 1B-B Compt . 3C Hdr 1B Isol Before Strainer 1-FCV-67-489

ERCW MCC 2A-A CompI. 3C Hdr 2A Isol Before Strainer 2-FCV-67-492

ERCW MCC 2B-B Compl. 3C Hdr 2B Isol Before Strainer 2-FCV -67-489

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Page 1 of 1

APPENDIX H

DIESEL AUXILIARY BOARD APPENDIX R VALVES

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 powe r.

PERFORM the foliowing :

a. TRANSFER control power to AUXILIAR Y

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 Discharg e 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

(

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APPENDIX I

Page 1 of 7

Installation of Temporary Cooling (HPFP) to CCP Oil Coolers

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 D

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

[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

l

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APPENDIX I

Page 2 of 7

[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. o

[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). o

Compression fitting connected to ERCW inlet valve

(4 foot red rubber hose with compression nut). o

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APPENDIX I

Page 30f7

[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) D

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

0-26-662 (near elevator) D

[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

c.

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APPEND IX I

Page 4 of 7

[ 15] ENSURE ERCW Isolation Valves to CCP Oil Coole rs OPEN. (NA valves not operated)

Pump Valve ID Description Position

A-AC CP VLV-67-1544A ERCW to Bearing Oil Cooler OPEN 0

VLV-67 -1545A ERCW Supply to Gear Oil Cooler OPE N 0

B-B CCP VLV-67-1544B ERCW to Bearing Oil Cooler OPEN 0

VLV-67- 1545B ERCW Supply to Gear Oil Cooler OPE N 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 CC P 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 OPE N 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

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APPENDIX I

Page 5 of 7

Figure 1

CCP Pump Skid

67-1545A(B)

Drain Valve -

-- 67-1544A(B) 67-704A(B)

Cooling

Water

Supply

CCP Gear HI---I

Motor Box Pump

Cooling

water

Gear Box Oil Hx Return

67-705A(B)

Bearing Oil Hx

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APPE NDIX I

Pa ge 6 of 7

Figu re 2

CCP Heat Exchanger and Piping Configuration

67-704A(B)

ERCW Cooling Water Supp ly Piping

67-1544 A(B)

Disconnect Compression fittings here ~ --oIT T Remove this

(two places) to aifow removal of piping. section of piping

to allow

installation of

temp orary hoses

ERCW Outlet

from H .

...

Bearing Oil Hx

67-705A(B)

ERC W Cooling Wa ter Discharge Piping

(

Page 12 3 of 14 2

AOp*M.01

( SQN LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

APPENDIX I

Pa ge 7 of 7

Fi g u re 3

CCP Heat Exchanger and Piping Co nfigu ra t ion

(shown w ith permanent pip ing removed and temporary hose installed )67-704 A(B)

Cooling Water to+_\l- _

Gear Oil Cooler ERCW Supply piping

67-1544A(B)

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

to permanent piping here Red rubber

hose -4 ft.

Cooling Water

Outlet --+1 6" stainless steel

from Hx tubing from Tee to

Hx

Tee

connection

Bearing Oil Cooler.

Return flow from

Gear Oil cooler

ERCW Return piping (discharge)

Install Gated Wye

/ Fire hose connection

1-26-668

~...."".~

2-26-668 - - - - - - - Fire Hose (two 50 ft

0-26-662 sections)

Page 124 of 142

AOp*M.01

( SQN LOSS OF ESSENTIAL RAW COOLING WATER

Rev . 15

APPENDIXJ

Page 1 of 6

Installation of Temporary Cooling Station Air Compressors

NOTE 1 This appendix wi ll install a temporary suppl y of cooling water to the Station Air

Compressors. A RCW connection at the Turb ine Bldg Space Coo ler 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 Append ix incorporates two parts. Part I provides instructions to install

temporary cool ing 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

Gas ket

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

Approximately 100 feet of fire hose .

1. CLOSE 1-VLV-24-946 RCW supp ly to Turbine Bldg Space Cooler 1A. o

2. CLOSE 1-VLV-24-903 RCW outlet from Turbine Bldg Space Coo ler 1A. o

NOTE Coo ler and pip ing is not drained . Flanges shou ld be bro ken to allow dra ining.

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. o

c.

Page 125 of 142

c SQN LOSS OF ESSENTIAL RAW COOLING WATER AOP-M.01

Rev . 15

APPENDIXJ

Pag e 2 of 6

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

THEN

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

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

at top flange where TCV was removed . o

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

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

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

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

or local hose station. o

9. INSTALL fire hose betwe en adapters, ensuring that the

hose is not kinked. o

(_.

Page 126 of 142

LOSS OF ESSENTIAL RAW COOLING WATER

( SQN

Rev. 15

APPENDIXJ

Page 3 of 6

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 press ure is restored.

1. ALIGN tem porary cooling water by performing the following:

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

com plete. 0

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

Comp ressors. 0

c. NOTIFY MCR to CLOSE O-FCV-67-20 8, ERCW supply to Air

Compressors. 0

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

e. OPEN O-VLV-67-1105 [ab ove B Station Air Compress or]. 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. o

(

Page 127 of 142

c SQN LOSS OF ESSENTIAL RAW COOLING WATER

AOp*M.01

Rev. 15

APPENDIXJ

Page 4 of 6

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. o

b. CHECK Air Compressor A trip lights DARK:

Low OIL PRESSURE o

High OIL TEMPERATURE o

( * High DISCHARGE AIR PRESSURE. o

c. CHECK Air Compressor B trip lights DARK:

Low OIL PRESSURE o

High OIL TEMPERATURE o

High DISCHARGE AIR PRESSURE. o

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

in HAND. o

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

in HAND. o

(

Page 128 of 142

AOP-M .01

SQN LOSS OF ESSENTIAL RAW COOLING WATER

( Rev. 15

APPENDIXJ

Page 5 0f 6

PART II AIR COMPRESSOR START AND SYSTEM ALIGNMENT

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

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

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

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

1O. DEPRE~S rO-HS-32-26Bl to start Air Compressor B. o

11. CHECK operation of Air Compressors A and B:

a. Air Compressor A cooling water flow INDICATED

on rO-FG-32-44Bl. o

b. Air Compressor B cooling water flow INDICATED

on rO-FG-32-24Bl. o

12. MAINTAIN air pressure in receiver tanks

between 80 psig and 100 psig. o

NOTE 1 rO-FCV-32-821 and IO-FCV-32-851 close automatically below

approximately 69 psig.

NOTE 2 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]. o

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]. o

(

Page 129 of 142

c SQN LOSS OF ESSENTIAL RAW COOLING WAT ER AOp*M .01

Rev . 15

APPENDIXJ

Page 6 of 6

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: o

Aux iliary Feedwater LCVs

Char ging Flow Control

Atm ospheric Relief Valves

16. IF Phase B is NOT actuated,

THEN

ESTABLISH air to containment on selected unit:

[714 pen room]

(

VALVE OPEN

UNIT DESCRIPTION ..j

NUMBER

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 isolatio n 0

FCV-32-81 Reacto r Bldg Train A essentia l 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

( SQN LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

APPENDIX K

Page 1 of 2

LOCAL CONTROL OF MOTOR-DRIVEN AFW FLOW

NOTE If the accountabil ity 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_ _

Unit2._ _

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

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 Feedwate r flow,

THEN

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

SIG VALVE NUMBER LOCATION ./

Inside Wl/VR,

1 VLV -3-836 on platform 0

AS el. 714 Pen Rm

2 VLV-3-835 Above Wl/VR entrance 0

AS el. 714 Pen Rm

3 VLV-3-834 Above Wl/VR entrance 0

Inside Wl/VR,

4 VLV-3-837 on platform 0

c..

Page 131 of 142

SQN LOSS OF ESSENTIAL RAW COOLING WATER

( Rev. 15

APPENDIX K

Page 2 of 2

LOCAL CONTROL OF MOTOR -DRIVEN AFW FLOW

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

Inside WVV R,

1 VLV-3-836 0

on platform

AS el. 714 Pen Rm

2 V LV-3-835 0

- Above WVVR entrance

AS el. 714 Pen Rm

3 V LV-3-834 0

Above WVVR entrance

Inside WVVR ,

4 V LV-3-837 0

on platform

c

Page 132 of 142

SQN LOSS OF ESSENTIAL RAW COOLING WATER AOP-M.01

( Rev. 15

APPENDIX L

Page 1 of 1

LOCAL CONTROL OF TURBINE DRIVEN AFW LCVS

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

1, OBTAIN handheld lighting, radios, and gloves . o

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 ope rating handwheels

on app ropriate LCVs:

THROTTLED

S/G LCV LOCATION

CLOSED

1 LCV-3-174 Inside West Va lve Vault Room 0

2 LCV-3-173 AS el. 714 Pent. Rm Above WVVR Entrance 0

3 LCV-3-172 A S el. 714 Pent. Rm Above WVVR Entrance 0

4 LCV- 3-175 Inside West Valve Vau lt Room 0

Page 133 of 142

( SQN LOSS OF ESSENTIAL RAW COOLING WATER

Rev . 15

APPENDIX M

Pa ge 1 of 1

TSC ACTIONS IN THE EVENT OF LOSS OF ERCW

NOTE 1 The appendix provides listing of immediate concerns and recommendations

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

NOTE 2 Applicable portions of the following procedures may be used to establish

temporary cooling wate r:

O-MA-REM-OOO-00 1.0. 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 evalua te the following:

Providing makeup supply to CSTs .

Provid ing temporary cooling wa ter

supplies to the following compo nents .

MCR chiller packages.

Diesel Generators

Provid ing temporary area/room cooling

to the following components .

CCP rooms

MDAFW pump area

RHR pump room

Maintena nce of Fire Protection Storage

Tan k level.

Initiation of repairs to restore ERCW

system

Establishing temporary ERCW

for long term plant operation and plant

shutd own .

Pag e 134 of 142

SQN LOSS OF ESSENTIAL RAW COOLING WATER

Rev . 15

APPENDIXN

Page 1 of 1

. LOCAL ISOLATION OF RCP SEAL INJECTION

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. o

3. ISOLATE RCP seal injection:

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

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

b. CLOSE seal water inject ion filter A outlet [VLV-62-549J. o

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

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

END OF TEXT

Page 135 of 14 2

SQN LOSS OF ESSENTIAL RAW COOLI NG WATER

Rev. 15

APPENDIX 0

Page 1 o f 4

HANDOUT FOR SECTION 2.1 1

LOSS OF ALL ERCW FLOW

COPY 1 (p age 1 of 2)

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 grea ter tha n 552°F , THEN locally operate atmospheric relief valves

10. MONITOR A FW pump stat us

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

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

TO.!-FW LCVs USING Appendix L.

e. MAINTAIN AFW flow greate r than 440 gpm

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

11. CONTROL SIG narrow range levels between 10% [25% A DV] 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 val ves.

16.c MONITOR hotweilleveis stable or dropping .

17. MONITOR containment vacuum relief normal:

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

valves OPEN .

20. MONITOR RCP seal cooling available:

a. CHECK T rain A CCS Outlet temperatur e less tha n 130°F.

b. CHECK RC P seal cooling flow in serv ice:

CC P running and supplying RCP Sea l Inj ection flow .

Thermal barrier cooling in service.

21 . MONITOR if CCP can be started:

a. CHECK Tem porary cooli ng wate r is established to CCP oil coo ler.

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

e. MONITOR CC P bearing and motor winding temperatures .

f. CONTROL CCP flow.

c.

Pag e 136 of 142

SQN AOP-M.01

( LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

APPENDIX 0

Page 2 of 4

HANDOUT FOR SECTION 2.11

LOSS OF ALL ERCW FLOW

COPY 1 (page 2 of 2)

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 condit ions if

Charging pump started

-T-cold less than 280°F.

RCS press ure 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 subcoo ling based on core exit TICs greater than 140°F.

44 . CONTINUE RCS cooldow n and depress urization :

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

tempe raturelpressure 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

SQN LOSS OF ESSENTIAL RAW COOLING WATER

( Rev. 15

APPENDIX a

Page 3 of 4

HANDOUT FOR SECTION 2.11

LOSS OF ALL ERCW FLOW

COpy 2 (p age 1 of 2)

STEP ACTION

9. MONITOR RCS tempera ture :

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

CONTROL A FW flow to SIGs betwe en 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 A FW flow USING EA-3-1.

d. WHEN backup air supp ly depleted, THEN

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

e. MAINTAIN A FW flow greater tha n 440 gpm

UNTI L narrow range level greater tha n 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 contai nment pressure less than 1.0 psig then verify conta inme nt vacuum relief

valves OP EN.

20 . MONITOR RCP seal cool ing available:

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

b. CHECK RCP seal coo ling flow in service:

CCP running and supp lying RCP Seal Injection flow .

The rmal barrier cooling in service .

21. MONITOR if CCP ca n be started :

a. CHECK Temporary cooling water is established to CC P oil cooler.

b. CHECK thermal barrier coo ling in service OR seal injec tion flowpath isolated.

e. MONITOR CCP bearing and motor winding temperatures.

f. CONTROL CC P flow .

(

Page 138 o f 142

AOp*M .01

( saN LOSS OF ESSENTIAL RAW COOLING WATER

Rev. 15

APPENDIX 0

Page 4 of4

HANDOUT FOR SECTION 2.11

LOSS OF ALL ERCW FLOW

COPY 2 (page 2 of 2)

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:

Pressu rizer level is maintained greate r than 10% [20% ADV] .

RCS subcoo ling 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 subcooli ng based on core exit TICs greater than 140°F.

44 . CONTINUE RCS cooldown and depressurization:

a. MAINTAIN T-cold cooldow n 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

AOP-M .01

SQN LOSS OF ESSENTIAL RAW COOLING WATER

( Rev. 15

APPENDIX P

Page 1 of 2

POTENTIAL TECH SPEC IMPACTS

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 entere d.

1. EVALUATE the following Tec h Specs

and TRM for applicability:

3.0.3, Limiting Condition for Ope ration

TR 3.1.2.1, Boration Flowpath - Shutdow n

TR 3.1.2.2, Boration Flowpath - Ope rating

TR 3. 1.2.3, Charging Pump - Shutdown

TR 3.1.2.4 , Charging Pump - Operating

3.4.1.1, Reactor Coola nt 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

Coo lant Circulation - Shutdown

Pa ge 140 of 142

SQN AOP- M.01

LOSS OF ESSENTIAL RAW COOLI NG WATER

( Rev. 15

APPENDIX P

Page 2 of 2

1. (Continued)

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, Compo nent 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 14 1 of 142

SON LOSS OF ESSENTIAL RAW COOLING WATER

( Rev. 15

COMMITMENT LIST

SUMMARY OF COMMITMENT

COMM ITMENT ID COMMITMENT CORRESPONDENCE

C.1 Identify non-essential heat loads NCO 940176001

that could be isolated in the event

system realignment is required .

S 64 940314 800

C.2 Provide guidance on the required SQPER9301 77

use of AOls during the performance IFI-93-300-02

of EOPs.

EPM-4, EOI Program Manual

User's Guide

C.3 Developed section 2.11 to address NCO 020002001

operator response to complete

loss of ERCW.

Page 142 of 142

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

PREPARED !

REVISED BY: Date/

VALIDATED BY: * Date!

APPROVED BY: Date!

(Operations Tra ining Manager)

CONCURRED: ** Date!

(Operations Representative)

Validation not requ ired 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 TRAININ G

REVISION/USAGE LOG

Revis ion Description Pages Prepared/

Number Of Revision V Date Affect ed Revised Bv :

0 Inilial lssue y 2/1 3/07 All RH Evans

-

I

!

I

,,

--

,

I

.. - I ,I .-

- --

._.

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

._- I ._---

- .-

.'- - -~

- -

i .~

( - - - - I I

-~-

I

I i

--

j

I

I 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.

Evaluation Method : Simulator _ x

-..!>._ _ In-Plant _

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

Performer:

NAME Start Time _

Perfo rmance Rating : "SAT _ _ UNSAT _ _ Performance Time Finish Time _

( Evaluator: - - - - - - - - - - - _

SIGNATURE

/,- - - -

DATE

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

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. Identif ies the correct unit, train, compo nent, etc.

b. Reviews the intended action and expected response.

c. Compares the actual response to the expected response.

Validation Time : CR. 11 mins Local

Tools/Equipment/Procedures Needed:

ES-0.1

Refe re nces:

Reference Title Rev No.

A. ES-0.1 Reactor Tri Res onse 30

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

c. READ TO OPERATOR

DIRECTIONS TO TRAIN EE:

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. W hen you complete the task successfully, the objective for this job performa nce 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 CONDITIO NS:

1. Unit has tripped.

2. T ransition 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

(

JPM B.1.g

Page 5 of 9

Rev. 0

Job Perform ance Checklist:

STEP/STANDARD SATIUNSAT

( Evaluator Note: Appli cant may take action related to critical steps prior to reaching

require d steps by use of the ES-O.1 Handout.

STEP 1.: Obtain the appropriate procedure. SAT

-

STANDARD: Operator obtains a copy of ES-O .1. UNSAT

-

COMMENTS: Start Time- -

STEP 2.: [1] MONITOR SI NOT actuated: - SAT

SI ACTUAT ED permissive DARK [M-4A, D4] - UNSAT

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

permiss ive is dark

COMMENTS:

STEP 3.: [2] VERIFY generator breakers OPEN. - SAT

( STA NDARD: Verifies generator breakers open by observ ing green lights on 1-M-1

benchboard.

- UNSAT

COMMENTS :

STEP 4.: [3] MONITO R RCS temperatures: - SAT

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 54r F and 552°F.

COMM ENTS:

JPM B.1.g

Page 6 of 9

Rev. 0

Job Performance Check list:

STEP/STANDARD SAT/UNSAT

( STEP 5. [4] MONITOR feedwater status : - SAT

T-Tavg less than 550°F. - UNSAT

MFW regulating valves CLOSED .

MFW regulating bypass valve controller outputs ZERO.

MFW isolation valves CLOSED.

MFW pumps T RIPPED.

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] CH ECK if emergency boration is required: - SAT

[aJ VERIFY all control rods fully inserted: - UNSAT

Rod bottom lights LIT

- Rod position indicators less than or equal to 12 steps.

STA NDARD: Determines All rod Bottom lights are illuminated.

( SAT

STE P 7.: [b] MONITOR RCS temperature: -

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

STAND ARD: Determines T-Tavg is approximately 551°F

COM MENTS :

STE P 8.: [6] ANN OUNC E reactor trip USING PA system. - SAT

STANDARD : Announces reactor trip over PA system - UNSAT

CO MMENTS:

JPM B.1.g

Page 7 of 9

Rev. 0

Job Performance Checklist:

STEP /STANDARD SAT/UNSAT

( STEP 9.: [7] MONITOR pressurizer level cont rol: - SAT

CHECK pressurizer level greater than 17%. - UNSAT

VER IFY charging IN SERVICE .

VERIFY letdown IN SERVICE.

CHECK pressurizer level trendi ng to 25% (normal range

20% to 30%).

STANDARD: Determines Cha rging and Letdown are in service and PZR level is >17%

and trending to 25%.

COMM ENTS:

,

ST EP 10.: [8] MONITOR pressurizer press ure control: - SAT

Pressur izer pressure greate r than 1870 psig. - UNSAT

Pressurizer pressure stable at or trendi ng to 2235 psig (normal

range 2210 psig to 2260 psig).

STAND ARD: Determ ines 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

ST EP 11.: IF pressu re less than 2235 psig and dropping, TH EN - SAT

PERF ORM the following:

- UNSAT

ENSURE pressurizer PORVs CLOSED . (not critical)

ENSURE spray valves CLOS ED. (not critical) Cr itical Step

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

and 2.

IF pressurize r pressure continues to drop, THEN STOP

additi onal RCPs as necessary. (not cr itical)

ENSURE all pressu rizer heaters ON .

STAND ARD: Stops Number 1 & 2RCP by rotating handswitche s counte r-clockwise.

CO MMENTS:

JPM B.1.g

Page 8 of 9

Rev. 0

Job Performance Checklist:

STEP/STANDARD SAT/UNSAT

( STEP 12.: IF pressure less than 2235 psig and dropping, THEN SAT

PERFORM the following:

UNSAT

ENSURE pressurizer PORVs CLOSED. (no t cri tical)

ENSURE spray valves CLOSED. (not critical) Crit ical Step

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

and 2.

.IF pressurizer pressure continues to drop, TH EN STOP

additional RCPs as necessary. (not cr itical) Stop Time__

ENSURE all pressurizer heaters ON.

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

PREPAREO/PROOFREAD BY: _ _""",",-J:LJw.!.!~=-!.L

D. A PORTER _

( RESPONSIBLE ORGANIZATION: -,>!O,-PE!=!RAl=.T!.!.IO~N",-S _

APPROVED BY:. ....l!.!"--L.l£O!:l!:l.L-

W. T. LEARY _

EFFECTIVE DATE : 08101/2005

REVIS ION

DESCRIPTION : Added new step wh ich chec ks 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.

Th is procedure has a handout page (2 copies) and foldo ut page.

I

(

SQN REACTOR TRIP RESPONSE IRev. 30

ES*0.1

FOLDOUT PAGE

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

I

(

_ _ _ _"'---

REACTOR TRIP RESPONSE

I

ES-0.1

Rev. 30

HANDOUT

Page 1 of 2

STEP ACTI ON

IF RCS subcoolinq based on core exit TIC s less than 40'F

FOP

OR Pressurizer level CANNOT be maintained greater than 5%,

THEN ACTUATE SI and GO TO E*O, Reactor Trip or Safety Injection.

IF CST level less than 5%,

FOP

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. MON ITOR 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 OPERA TE 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 tre nding to 25%)

RNO CONTROL charging and letdown to maintain pressurizer level at 25%

(no rmal range 20% to 30%) .

8. MONI TOR 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 -

I

(

______________________

REACTOR TRIP RESPONSE

I

ES-O.1

~ev.30

HANDOUT

Page20f2

STEP ACTION

12.b. 2). (if NO Rep can be started)

RNO 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 I ES-0.1

Rev. 30

HANDOUT

Page 1 of 2

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.

IF CST level less than 5%,

FOP

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 temperatu res greater than 540'F.

(

7. MONITOR pressurizer level control : (pressurize r level greater than 17%)

7.a. (if pzr level less than 17%)

RNa 3) CONTROL charging to restore pressurizer level greate r than 17%.

4) WHEN pressurizer level greater than 17%.

THEN OPERATE pressu rizer 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 contro l: (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 REACTOR TRIP RESPONSE I ES-0.1

Rev. 30

HANDOUT

Page 2 of 2

STEP ACTION

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 SQN REACTOR TRIP RESPONSE I ES-O.1

Rev. 30

1.0 PURPOSE

This procedure provides the 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

( SQN

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REACTOR TRIP RESPONSE I ES-O,1

R_e_v_, _3_

0 _ _-'

ISTEP IIACTlONIEXPECTED RESPONSE I IRESPONSE NOT OBTAINED

NOTE This procedure has a foldo ut page .

1. MONITOR 81NOT actuated: IF 81 actuated,

THEN

SI ACTUATED permi ssive DARK GO TO E*O, Reactor Trip or Safety

[M-4A, D4] Injection.

a--

2. VERIFY generator breakers OPEN . OPEN generator breakers.

Page 3 of 15

IL.. _

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REACTOR TRIP RESPONSE I ES-O.1

R_e_v_"_3_0_ _-.J

ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

3. MONITOR RCS temperatures : IF temperature less than 547 °F

and dropping,

IF any RCP running, THEN

THEN PERFORM the following:

CHECK T-avg stable at or trending to

a. ENSURE steam dumps and

between 54rF and 552°F.

atmospheric reliefs CLOSED .

OR b. ENSURE S/G blowdown isolation

valves CLOSED .

IF RCPs stopped, c. IF cooldown continues,

THEN

CHECK T-cold stable at or trending

PERFORM the following:

to between 547°F and 552°F.

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

SQN REACTOR TRIP RESPONSE IES-0.1

Rev. 30

ISTEP IIACnONIEXPECTED RESPONSE II RESPONSE 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. 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. Total feed flow to SIGs g. ESTABLISH AFW flow

greater than 440 gpm. 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 SQN REACTOR TRIP RESPONSE

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _R_e_v_o_3_0

I ES-O. 1

_

ISTEP IIACTION/EXPECTED RESPONSE I IRESPONSE NOT OBTAINED

5. CHECK if emergency boration is required :

a. VERIFY all control rods fully inserted: a. IF any of the following conditions

exists:

Rod bottom lights LIT

two or mo re RPls Indicate

greater than 12 steps

Rod position indicators

less than or equa l to 12 steps. OR

two or more control rod positions

CAN NOT be determined,

THEN

EMERGENCY BORATE

USING EA-68-4 , Emergency

Boralion.

b. MONITOR ReS temperature: b . EMERGENCY BORATE

as necessary to maintain shutdown

T-avg greater than 540° F margin USING EA*68.4 , Emergen cy

if any RCP running Boration.

T-cold greater tha n 540"F

if all RCPs stoppe d.

6. ANNOUNCE reac tor trip

USING PA system .

Page 6 of 15

, '--

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REACTOR TRIP RESPONSE

'--

IES-O.1

R_e_v_,_3_0_ _...J

ISTEP IIACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

7. MONITOR pressurizer level control:

a. CHECK pressurizer level a. PERFORM the following:

greater than 17%.

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. VERIFY charging IN SERVICE . b. ESTABLISH charging

USING EA-62-5, Establishing Normal

Charging and Letdown.

c. VERIFY letdown IN SERVICE. c. WHEN charging established

AND pzr level greater than 17%,

THEN

ESTABLISH letdown USING EA-62-5,

Establishing Normal Charging and

Letdown.

d. CHECK pressurizer level d. CONTROL charging and letdown

trend ing to 25% to maintain pressurizer level at 25%

(normal range 20% to 30%). (normal range 20% to 30%).

Page 7 of 15

I

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SON REACTOR TRIP RESPONSE

_ _ _ _ _ _ _ _ __ _ _ _ _ __ _ _ _ _ _____R_e_v_

IES-0.1

. 3_0 _

ISTEP IIACTION/EXPECTED RESPONSE I IRESPONSE NOT OBTAINED

8. MONITOR pressurizer pressure control:

a. Pressurizer pressure a. ENSURE SI ACTUATED.

greater than 1870 psig.

GO TO E-O, Reactor Trip or Safety

Injection.

b. Pressurizer pressure

b. IF pressure less than 2235 psig

stable at or trending to 2235 psig and dropping,

(normal range 2210 psig to THEN

2260 psig). 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 contin ued on next page)

I~ Page 8 of 15

--

I

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REACTOR TRIP RESPONSE

....;....

I ES-0.1

R_e_v_,_30 _

ISTEP II ACTIONIEXPECTED RESPONSE IIRESPONSE NOT OBTAINED

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. Grea ter 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.

(

I~

Page 9 of 15

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REACTOR TRIP RESPONSE

'--

IL-R_e_v_.3_0_ _

ES-O.1

....J

ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

10. VERIFY AC busses ENERGIZED PERFORM the following:

from start busses.

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.

(

Page 10 of 15

SON

_ _ _ _...I-

REACTOR TRIP RESPONSE IES-O.1

R_8_V_"_3_

0 _ _...l

ISTEP IIACnONJEXPECTED RESPONSE II RESPONSE NOT OBTAINED

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 : a. USE atmospheric reliefs in AUTO

and set for 84% (1005 psig).

c-s CONDENSER INTERLOCK

permissive LIT [M-4A, E6l IF atmospheric reliefs

NOT functioning in AUTO,

At least one Intact SIG MSIV THEN

OPEN. 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.

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.

.,'

Page 11 of 15

I

(

SQN REACTOR TRIP RESPONSE IRev. 30

ES-0.1

ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

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 ,

Establish ing 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.

.

'

Page 12 of 15

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REACTOR TRIP RESPONSE I ES*O ,1

R_e_v_,_3_0_ _--'

ISTEP IIACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

13, MONITOR if source range channels

should be reinstated :

a, CHECK intermediate range flux a, GO TO Step 14,

less than 10" % power

on operable channels,

b. CHECK source range channels b. REINSTATE source range channels

REINSTATED. 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]

.,'

Page 13 of 15

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REACTOR TRIP RESPONSE IES-0.1

R_e_v_._30 _

ISTEP II ACTION/EXPECTED RESPONSE IIRESPONSE NOT OBTAINED

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 tempera ture at 547°F

(between 540°F and 550°F):

T-avg if any Rep running

T-co ld if all RCPs stopped.

16. PERFORM EA-D-9. Post Trip

Administrative Requirements

and Recovery Actions.

I~

" Page 14 of 15

__

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( SON REACTOR TRIP RESPONSE I ES*0.1

Rev. 30

ISTEP II ACTION/EXPECTED RESPONSE II RESPONSE NOT OBTAINED

17. DETERMINE if natural circulation

cooldown is required:

a. CHECK at least one RCP RUNNING. a. IF plant 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 b. DO NOT CONTINUE this procedure

AV AILABLE. UNTIL at least one AFW pump

AVAILABLE.

( c. SELECT appropriate procedure:

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