Text

Initial Exam 2009-301 Draft Sim/IN-Plant JPMs
	ML092870799
Person / Time
Site:	Browns Ferry
Issue date:	10/13/2009
From:	; Division of Reactor Safety II
To:	;
References
	50-259/09/301, 50-260/09/301, 50-296/09/301, JPM No. 347, Rev. 0, U-000-EM-39
	Download: ML092870799 (368)
	v • d • e

JPM NO. 347 REV. NO. 0 PAGE 1 of 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER: 347 TITLE: 3-EOI APPENDIX 7D - ALTERNATE RPV INJECTION SYSTEM LINEUP - STANDBY COOLANT TASK NUMBER: U-OOO-EM-39 SUBMITTED BY: DATE: _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: _____________________ DATE: ___ _ _

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 347 REV. NO. 0 PAGE 2 of 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 3/28/09 All Initial issue

JPM NO. 347 REV. NO. 0 PAGE 3 of 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ______________________________________________

RO SRO DATE: ____________

JPM NUMBER: 347 TASK NUMBER: U-000-EM-39 TASK TITLE: 3-EOI APPENDIX 7D - ALTERNATE RPV INJECTION SYSTEM LINEUP - STANDBY COOLANT KIA NUMBER: 203000A4.07 KIA RATING: RO 4.5 SRO 4.5 TASK STANDARD: PERFORM CORRECT EQUIPMENT MANIPULATIONS REQUIRED TO INJECT MAKEUP INTO THE RPV AS DIRECTED BY 3-EOI APPENDIX-7D PERFORMANCE LOCATION: SIMULATOR X PLANT _ CONTROL ROOM_

REFERENCES/PROCEDURES NEEDED: 3-EOI APPENDIX 70, REV 2 VALIDATION TIME: SIMULATOR: 10:00 LOCAL: _______

MAX. TIME ALLOWED: ________ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS AITACHED? YES ____ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _____________________ DATE: _ _ _ _ _ __

JPM NO. 347 REV. NO. 0 PAGE 4 of 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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 perfonnance measure will be satisfied. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are a Unit 3 Operator. a loss of Off-site power has caused a Reactor Scram on Unit 3. Due to an unisolable leak and several equipment failures, the Unit Supervisor has detennined that RPV water level cannot be maintained above -162".

INITIATING CUES: The Unit Supervisor has directed you to inject with Standby Coolant to the RPV using RHR System I as directed by 3-EOI Appendix-7D, "ALTERNATE RPV INJECTION SYSTEM LINEUP STANDBY COOLANT."

JPM NO. 347 REV. NO. ° PAGE 5 of 12 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Identified or obtained copy of 3-EOI Appendix-7D.

SAT UNSAT N/A _ _ COM MEN TS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

1. VERIFY RHR SYSTEM I available for Standby Coolant as follows (Unit 3, Panel 3-9-3):

a. VERIFY CLOSED the following valves:

3-FCV-74-61, 3-FCV-74-60, RHR SYS I DW SPRAY INBD VLV RHR SYS I DW SPRAY OUTBD VLV

3-FCV-74-57, RHR SYS I SUPPR CHBR/POOL ISOL VLV

3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE

3-FCV-74-59, RHR SYS I SUPPR POOL CLGITEST VLV

3-FCV-23-46, RHR HX 3B RHRSW OUTLET VLV STANDARD:

Verifies 3-FCV-74-61, 3-FCV-74-60, 3-FCV-74-57, 3-FCV-74-58, 3-FCV-74-59, and 3-FCV-23-46 are closed by observing illuminated Green only light above each handswitch.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 347 REV. NO. 0 PAGE 6 of 12 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

b. VERIFY RHR Pumps 3A and 3C are NOT running STANDARD:

Verifies 3A and 3B RHR pumps are Not running by observing illuminated Green only light above each handswitch.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

c. PLACE 3-BKR-074-0100, RHR HTX A-C DISCH XTIE (TO U-2) VLV FCV-74-100 (M010-171) to ON (480V RMOV Board 3B, Compartment 19A)

Simulator driver: When dispatched, simulator driver calls back after 1 minute and reports breaker closed for 3-FCV-74-100 STANDARD:

Dispatches AUO to close breaker for 3-FCV-74-100 at 3B 480v RMOV bd, compartment 19A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 347 REV. NO. 0 PAGE 7 of 12 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

2. START RHRSW Pumps B1 and B2 STANDARD:

Starts RHRSW pumps B1 and B2 using handswitches O-HS-23-15AJ3 and O-HS 19AJ3 respectively (Critical) and verifies Red only light above each handswitch (Not Critical)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

3. NOTIFY Unit 1 Operator to VERIFY CLOSED 1-FCV-23-46, RHR HEAT EXCHANGER B COOL WATER OUTLET VLV (Unit 1, Panel 1-9-3)

I Simulator driver: When contacted as Unit 1 Operator, report 1-FCV-23-46 Closed STANDARD:

Contacts Unit 1 Operator to verify 1-FCV-23-46 closed SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 347 REV. NO. 0 PAGE 8 of 12 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

4. NOTIFY Unit 2 Operator to perform the following (Unit 2, Panel 2-9-3):

a. VERIFY CLOSED 2-FCV-23-46, RHR HX 2B RHRSW OUTLET VLV I Simulator driver: When contacted as Unit 2 Operator, report 2-FCV-23-46 Closed STANDARD:

Contacts Unit 2 Operator to verify 2-FCV-23-46 closed SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

b. OPEN 2-FCV-23-57, STANDBY COOLANT VLV FROM RHRSW I Simulator driver: When contacted as Unit 2 Operator, report 2-FCV-23-57 Open STANDARD:

Contacts Unit 2 Operator to Open 2-FCV-23-57 SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 347 REV. NO. 0 PAGE 9 of 12 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

5. INJECT Standby Coolant into RPV as follows (Unit 3, Panel 3-9-3):

a. CLOSE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE STANDARD:

Closes 3-FCV-74-52 (Critical) and verifies Green only light illuminated above handswitch (Not Critical)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

b.

STANDARD:

OPEN 3-FCV-74-100, RHR SYS I U-2 DISCH XTIE Opens 3-FCV-74-100 (Critical) and verifies Red only light illuminated above handswitch (Not Critical)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 347 REV. NO. 0 PAGE 10 of 12 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

c. OPEN 3-FCV-74-53, RHR SYS I LPCIINBD INJECT VALVE STANDARD:

Opens 3-FCV-74-53 (Critical) and verifies Red only light illuminated above handswitch (Not Critical)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

d. THROTILE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE, to control injection STANDARD:

Throttles Open 3-FCV-74-52 (Critical) and verifies Red only light illuminated above handswitch (if opened fully) (Not Critical) or Red and Green lights illuminated (if throttled) (Not Critical) and verifies flow to the Reactor vessel using 3-FI-74-50 and verifies level recovering using 3-U-3-58A or B on panel 9-5 or from ICS computer Emergency Range level (Critical)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

CUE: When flow is verified to Unit 3 Reactor from Loop I RHR (Standby Coolant) and level verified recovering, Report That completes this task.

JPM NO. 347 REV. NO. 0 PAGE 11 of 12 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 12 of 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

- - - - A A" ' ' *"'**************************

IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

- - - - '" '" '" '" '" '" A********************************************************************

INITIAL CONDITIONS: You are a Unit 3 Operator. a loss of Off-site power has caused a Reactor Scram on Unit 3. Due to an unisolable leak and several equipment failures, the Unit Supervisor has determined that RPV water level cannot be maintained above -162".

INITIATING CUES: The Unit Supervisor has directed you to inject with Standby Coolant to the RPV using RHR System I as directed by 3-EOI Appendix-7D, "ALTERNATE RPV INJECTION SYSTEM LINEUP STANDBY COOLANT."

PAGE 12 of 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are a Unit 3 Operator. a loss of Off-site power has caused a Reactor Scram on Unit 3. Due to an unisolable leak and several equipment failures, the Unit Supervisor has determined that RPV water level cannot be maintained above -162".

INITIATING CUES: The Unit Supervisor has directed you to inject with Standby Coolant to the RPV using RHR System I as directed by 3-EOI Appendix-7D, "ALTERNATE RPV INJECTION SYSTEM LINEUP STANDBY COOLANT."

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EOI PROGRAM MANUAL SECTION IX 3-EOI APPENDIX-7D ALTERNATE RPV INJECTION SYSTEM LINEUP STANDBY COOLANT REVISION 2

PREPARED BY: M. Morrow PHONE: 3708 RESPONSIBLE ORGANIZATION: Operations APPROVED BY: A. S. Bhatnagar EFFECTIVE DATE: 10/26/00 LEVEL OF USE: REFERENCE USE VALIDATION DATE: 02/14/92 QUALITY-RELATED

HISTORY OF REVISION/REVIEW 3-EOI APPENDIX-7D

REV.

NO.

0 DATE:

7/28/95 REVISED PAGES ALL REASON FOR CURRENT REVISION New procedure. Necessary to support implementation of BFNP Unit 3 EOIs.

1 10/5/95 1 Added Step 1.c. to close breaker for 3-FCV-74-100.

2 Added Step 5.a. to close LPCI outboard inject valve so that it can be throttled open.

2 10/26/00 All Converted to MS-Word.

3-EOI APPENDIX-7D Rev. 2 Page 1 of 2 3-EOI APPENDIX-7D ALTERNATE RPV INJECTION SYSTEM LINEUP STANDBY COOLANT LOCATION: Unit 3 Control Room ATTACHMENTS: None

1. VERIFY RHR SYSTEM I available for Standby Coolant as follows (Unit 3, Panel 3-9-3):

a. VERIFY CLOSED the following valves:

3-FCV-74-61, RHR SYS I DW SPRAY INBD VLV --

3-FCV-74-60, RHR SYS I DW SPRAY OUTBD VLV --

3-FCV-74-57, RHR SYS I SUPPR CHBR/POOL ISOL VLV --

3-FCV-74-58, RHR SYS I SUPPR CHBR SPRAY VALVE --

3-FCV-74-59, RHR SYS I SUPPR POOL CLG/TEST VLV --

3-FCV-23-4 6, RHR HX 3B RHRSW OUTLET VLV. --

b. VERIFY RHR Pumps 3A and 3C are NOT running. --

c. PLACE 3-BKR-074-0100, RHR HTX A-C DISCH XTIE (TO U-2) VLV FCV-74-100 (M010-171) to ON (480V RMOV Board 3B, Compartment 19A).

2. START RHRSW Pumps B1 and B2.

3. NOTIFY Unit 1 Operator to VERIFY CLOSED 1-FCV-23-46, RHR HEAT EXCHANGER B COOL WATER OUTLET VLV (Unit 1, Panel 1-9-3).

4. NOTIFY Unit 2 Operator to perform the following (Unit 2, Panel 2-9-3):

a. VERIFY CLOSED 2-FCV-23-46, RHR HX 2B RHRSW OUTLET VLV

b. OPEN 2-FCV-23-57, STANDBY COOLANT VLV FROM RHRSW.

3-EOI APPENDIX-7D Rev. 2 Paae 2 of 2

5* INJECT Standby Coolant into RPV as follows Panel 3-9-3):

a.

(Unit 3, CLOSE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE.

b. OPEN 3-FCV-74-100, RHR SYS I U-2 DISCH XTIE.

c. OPEN 3-FCV-74-53, RHR SYS I LPCI INBD INJECT VALVE.

d. THROTTLE 3-FCV-74-52, RHR SYS I LPCI OUTBD INJECT VALVE, to control injection.

LAST PAGE

JPM NO. 399 REV. NO. 0 PAGE 1 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER: 399 TITLE: 3-SR-3.3.2.1.2 RWM FUNCTIONAL TEST FOR STARTUP TASK NUMBER: U-085-SU-02 Copy of 3-SR-3.3.2.1.2 required complete up thru step 7.0[3] (current REV) - give to Applicant (SR already in progress) 3-SR-3.1.3.5(A) Control Rod Movement Data Sheet needs to be open to Group 1 SUBMITTED BY: DATE: _ _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: _____________________ DATE: _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 399 REV. NO. 0 PAGE 2 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 03/13/09 All Initial Issue

JPM NO. 399 REV. NO. 0 PAGE 3 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: _______________________________________________

RO SRO DATE: _____________

JPM NUMBER: 399 TASK NUMBER: U-085-SU-02 TASK TITLE: 3-SR-3.3.2.1.2 RWM FUNCTIONAL TEST FOR STARTUP KIA NUMBER: 201006 A2.05 KIA RATING: RO ~ SRO 3.5 TASK STANDARD: Perform 3-SR-3.3.2.1.2 RWM Functional Test for Startup PERFORMANCE LOCATION: SIMULATOR X PLANT __ CONTROL ROOM --

REFERENCES/PROCEDURES NEEDED: 3-SR-3.3.2.1.2, Rev 3, 3-01-85, Rev 64 VALIDATION TIME: SIMULATOR:. _ _...;...15;;;;..;.:..;;;..;00~ LOCAL: _____

MAX. TIME ALLOWED: _ _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS: Copy of 3-SR-3.3.2.1.2 required complete up to step 7.0[4] (current REV) - give to Applicant after SR found in Book. 3-SR-3.1.3.5(A)

Control Rod Movement Data Sheet needs to be open to Group 1.

ADDITIONAL COMMENT SHEETS ATTACHED? YES _ _ NO x RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ______________DATE: _ _ _ _ __

JPM NO. 399 REV. NO. 0 PAGE 4 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are a Unit Operator on Unit 3. Unit 3 is making preparations for startup using the A2 Startup Sequence. The RWM in operation per 3-01-85, Control Rod Drive System.

Reactor Engineering has performed 3-SR-3.3.2.1.7, RWM Program Verification.

3-SR-3.3.2.1.2, "RWM Functional Test for Startup," has been completed up thru step 7.0[3].

INITIATING CUES: The Unit Supervisor directs you to continue performance of 3-SR-3.3.2.1.2, "RWM Functional Test," for Startup at step 7.0[4]. A Reactor Engineer is present and monitoring as needed.

JPM NO. 399 REV. NO. 0 PAGE 5 of 17

START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Locates SR in book in the Simulator (then Examiner hands copy to Candidate)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x 7.0 PROCEDURE STEPS

[4]

STANDARD:

RECORD the start date AND time, reason for test, plant conditions AND ANY pre-test remarks on Attachment 1, Surveillance Procedure Review Form in Section 8.0.

Records start date and time, reason for test (startup) on Attachment 1.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

NOTE ALL operations are performed on Panel 3-9-5 in the main Control Room unless otherwise noted.

JPM NO. 399 REV. NO. 0 PAGE 6 of 17 PERFORMANCE STEP:

[5]

CRITICAL x NOT CRITICAL PLACE the Control Rod Drive (CRD) POWER switch (3-HS-85-46) momentarily to OFF AND next SWITCH to ON.

STANDARD:

Places 3-HS-85-46 to OFF and back to ON.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[6] VERIFY ALL control rods are deselected on the rod select matrix.

STANDARD:

Verifies no rod selected.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 399 REV. NO. 0 PAGE 7 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7] PERFORM the RWM Functional Test as follows:

[7.1] VERIFY OR PLACE the RWM in operation per 3-01-85.

STANDARD:

N/A - Given in initial conditions.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7.2] [NER/C] REQUEST Reactor Engineering to PERFORM 3-SR-3.3.2.1 .7 OR VERIFY performance of 3-SR-3.3.2.1. 7.

[INPO SOER 84-002)

STANDARD:

N/A - Given in initial conditions.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

I CUE: Examiner, as Reactor Engineer, initial step [7.2].

JPM NO. 399 REV. NO. 0 PAGE 8 of 17

~ ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7.3] REFER to the Control Rod Movement Data Sheet from 3-SR-3.1.3.5(A) to identify a rod from RWM Group 02.

STANDARD:

Uses Control Room copy of 3-SR-3.1.3.5(A) to identify a Group 2 rod in the A2 Startup Sequence.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7.4] RECORD below the rod chosen:

~ Rod Number:

STANDARD:

Records identified rod (can be ANY control rod from RWM Group 2 (A2 Startup Sequence) - (02-31,26-07,58-23,42-55,10-39,42-07,58-39, 26-55, 10-23,50-15,50-47,18-47,18-15,50-31,34-47,18-31,34-15,42-39, 26-39, 26-23, 42-23, or 34-31)

SAT UNSAT N/A _ _ COM ME NTS: _ _ _ _ __

~

JPM NO. 399 REV. NO. 0 PAGE 9 of 17

~ ****************************************************************************************************

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[7.5] SELECT the rod recorded in Step 7.0[7.4].

STANDARD:

Selects rod from A2 Startup Sequence Group 2.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7.6] VERIFY the SELECT ERROR status block on the RWM display is in alarm (red background).

STANDARD:

~ Verifies Select Error in alarm.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

~

JPM NO. 399 REV. NO. 0 PAGE 10 of 17

~ ****************************************************************************************************

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[7.7] NOTCH the selected rod to position 02.

STANDARD:

Notch withdraws selected rod to position 02.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7.8] VERIFY that the rod moved to position 02 is identified as a withdraw error on the RWM display.

STANDARD:

~ Verifies rod at position 02 has a withdraw error on the display.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

~

JPM NO. 399 REV. NO. 0 PAGE 11 of 17

~ ****************************************************************************************************

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[7.9] PLACE the CRD Control switch (3-HS-85-48) to ROD OUT NOTCH AND VERIFY the following:

[7.9.1] The selected control rod does NOT withdraw.

STANDARD:

Places control switch 3-HS-85-48 to rod out notch and verifies the selected rod does NOT withdraw.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

~ [7.9.2] The WITHDRAW BLOCK status block on the RWM display is in alarm (red background).

STANDARD:

Verifies the Withdraw Block status block on the RWM display is in alarm.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

~

JPM NO. 399 REV. NO. 0 PAGE 12 of 17

~ ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7.9.3] RWM ROD BLOCK (3-XA-55-5B, Window 35) is in ALARM.

STANDARD:

Verifies RWM Rod Block alarm 3-XA-55-5B, window 35 is in alarm.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[7.10] INSERT the selected rod from position 02 to 00.

STANDARD:

~ Inserts selected rod from position 02 to 00.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

~

JPM NO. 399 REV. NO. a PAGE 13 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL

[7.11] VERIFY the WITHDRAW BLOCK status block on the RWM display x

is NOT in alarm.

STANDARD:

Verifies the Withdraw Block status block on the RWM display is NOT in alarm.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7.12] VERIFY RWM ROD BLOCK (3-XA-55-5B, Window 35) will RESET.

STANDARD:

Verifies RWM Rod Block alarm 3-XA-55-5B, window 35 alarm will reset.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ _ __

JPM NO. 399 REV. NO. 0 PAGE 14 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL

[7.13] REFER to the Control Rod Movement Data Sheet from 3-SR-x 3.1.3.5(A) to identify a rod from RWM Group 01.

STANDARD:

Uses Control Room copy of 3-SR-3.1.3.5(A) to identify a Group 1 rod in the A2 Startup Sequence.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7.14] RECORD below the rod chosen:

STANDARD:

Rod Number:

Records identified rod (can be ANY control rod from RWM Group 1 (A2 Startup Sequence)-(58-31, 34-07, 02-23,18-55,50-39,19-07,02-39,34-55,50-23,10-15,10-47,42-47,42-15,10-31,26-47,42-31,26-15,18-39, 34-39,34-23,18-23, or26-31)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 399 REV. NO. 0 PAGE 15 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

[7.15] SELECT the rod recorded in Step 7.0[7.14].

STANDARD:

Selects rod from A2 Startup Sequence Group 1.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

[7.16] VERIFY that rod Group 01 is indicated as the latched group on the RWM Panel.

STANDARD:

Verifies Select Error in alarm.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 399 REV. NO. 0 PAGE 16 of 17

~ ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM

~

STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ __

~

PAGE 17 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are a Unit Operator on Unit 3. Unit 3 is making preparations for startup using the A2 Startup Sequence. The RWM is in operation per 3-01-85, Control Rod Drive System.

Reactor Engineering has performed 3-SR-3.3.2.1.7, RWM Program Verification.

3-SR-3.3.2.1.2, "RWM Functional Test for Startup," has been completed up thru step 7.0[3].

INITIATING CUES: The Unit Supervisor directs you to continue performance of 3-SR-3.3.2.1.2, "RWM Functional Test for Startup," at step 7.0[4]. A Reactor Engineer is present and monitoring as needed.

PAGE 17 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are a Unit Operator on Unit 3. Unit 3 is making preparations for startup using the A2 Startup Sequence. The RWM is in operation per 3-01-85, Control Rod Drive System.

Reactor Engineering has performed 3-SR-3.3.2.1.7, RWM Program Verification.

3-SR-3.3.2.1.2, "RWM Functional Test for Startup," has been completed up thru step 7.0[3].

INITIATING CUES: The Unit Supervisor directs you to continue performance of 3-SR-3.3.2.1.2, "RWM Functional Test for Startup," at step 7 .0[4]. A Reactor Engineer is present and monitoring as needed.

Browns Ferry Nuclear Plant

Unit 3 Surveillance Procedure 3-SR-3.3.2.1.2 RWM Functional Test for Startup Revision 0003 Quality Related Level of Use: Continuous Use Effective Date: 04-12-2007 Responsible Organization: RXE, Reactor Engineering

Prepared By:

Approved By:

M, David Riden @24S0 J. Mike Keck

BFN RWM Functional Test for Startup 3-SR-3.3.2.1.2 Unit 3 Rev. 0003 Page 2 of 10 Current Revision Description Pages Affected: All Type of Change: Revision Tracking Number: 004 Revision 0003. This procedure was converted from a Unit 1 Word 2003 (XP) version using Revision 0001, Tracking No. 003 into a revised Unit 3 Word 2003 (XP) version initially converted from Revision 002, Tracking No. 003 of 2-SR-3.3.2.1.2 located in the BSL active file, and issued to support BFN Unit 3.

Revision 0003 was made to add Unit 3 enhancements and to make the format for this procedure series for all three Units consistent with like Table of Contents, styles and RXE preferences. These additional changes did NOT alter the intent of the procedure.

BFN RWM Functional Test for Startup 3-SR-3.3.2.1.2 Unit 3 Rev. 0003 Page 3 of 10 Table of Contents

1.0 INTRODUCTION

.......................................................................................................... 4 1.1 Purpose ........................................................................................................................ 4 1.2 Scope ............................................................................................................................ 4 1.3 Frequency ..................................................................................................................... 4 1.4 Applicability ................................................................................................................... 4

2.0 REFERENCES

............................................................................................................. 5 2.1 Unit 3 Technical Specifications ................. .................................................................... 5 2.2 Updated Final Safety Analysis Report (UFSAR) ..... ...................................................... 5 2.3 Drawings ....................................................................................................................... 5 2.4 Other Documents .......................................................................................................... 5 3.0 PRECAUTIONS AND LIMITATIONS ........................................................................... 5 4.0 PREREQUiSiTES ......................................................................................................... 6

5.0 6.0 7.0 SPECIAL TOOLS AND EQUIPMENT RECOMMENDED ............................................ 6 ACCEPTANCE CRITERIA ........................................................................................... 6 PROCEDURE STEPS .................................................................................................. 7 8.0 ILLUSTRATIONS/ATTACHMENTS ............................................................................. 9 Attachment 1: Surveillance Procedure Review Form ..................................................... 10

BFN RWM Functional Test for Startup 3-SR-3.3.2.1.2 Unit 3 Rev. 0003 Page 4 of 10

1.0 INTRODUCTION

1.1 Purpose This Surveillance Procedure performs the channel functional test for Rod Worth Minimizer (RWM) function for startup. This procedure demonstrates operability of the RWM in conformance with the requirements specified in Technical Specification (TS) Surveillance Requirement (SR) 3.3.2.1.2.

1.2 Scope The channel functional test is performed for the RWM to demonstrate that the entire system will perform its intended function. The channel functional test is performed by attempting to withdraw a control rod NOT in compliance with the prescribed sequence and verifying a control rod block occurs. This test is performed as soon as possible after the applicable conditions are entered. This test fully satisfies the requirements of Technical Specification SR 3.3.2.1.2. It may also be used to partially satisfy the requirements of Technical Specification SR 3.10.8.2.

Normally, this Surveillance Procedure will be performed during reactor startup after entering Mode 2 just prior to control rod withdrawals for the purpose of making the reactor critical.

1.3 Frequency Once every 92 days. NOT required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at :::; 10% Rated Thermal Power (RTP) in MODE 2.

1.4 Applicability Modes 1 and 2 with THERMAL POWER:::; 10% RTP (SR 3.3.2.1.2).

Mode 5 with the reactor mode switch in the startup/hot standby position (SR 3.10.8.2).

BFN RWM Functional Test for Startup 3-SR-3.3.2.1.2 Unit 3 Rev. 0003 Page 5 of 10

2.0 REFERENCES

2.1 Unit 3 Technical Specifications A. Section 3.3.2.1, Control Rod Block Instrumentation.

B. Section 3.10.2, Reactor Mode Switch Interlock Testing.

C. Section 3.10.8, SHUTDOWN MARGIN (SDM) Test - Refueling.

2.2 Updated Final Safety Analysis Report (UFSAR)

A. Section 7.7, Reactor Manual Control System.

B. Section 7.16, Plant Process Computer.

2.3 Drawings A. 3-729E857, Rod Worth Minimizer System Elementary Diagram.

B. 3-730E321, Reactor Manual Control System Elementary Diagram.

2.4 Other Documents A. 3-SR-3.1.3.5(A), Control Rod Coupling Integrity Check.

B. 3-SR-3.3.2.1.7, RWM Program Verification.

C. 3-GOI-100-1A, Unit Startup and Power Operation.

D. 3-01-85, Control Rod Drive System.

3.0 PRECAUTIONS AND LIMITATIONS A. Whenever ANY step is failed, the Reactor Engineer (RE) OR Shift Technical Advisor (STA) should be notified for assistance.

B. Refer to 3-01-85 whenever moving control rods.

BFN RWM Functional Test for Startup 3-SR-3.3.2.1.2 Unit 3 Rev. 0003 Page 6 of 10 Date~

4.0 PREREQUISITES

[1 ] This copy of 3-SR-3.3.2.1.2 is verified to be the most current revision. uO

[2] The following personnel are available to perform this Surveillance Procedure:

One (1) UO AND One (1) RE.

[3] The reactor is in Mode 2.

5.0 SPECIAL TOOLS AND EQUIPMENT RECOMMENDED None 6.0 ACCEPTANCE CRITERIA

A. Responses which fail to satisfy the following Acceptance Criteria (AC) constitute unsatisfactory Surveillance Procedure results AND require immediate notification of the Unit Supervisor (US) at the time of the failure:

1. The rod block function of the RWM for an out-of-sequence rod shall be verified by attempting to move an out of sequence control rod AND verifying a control rod block occurs.

B. Steps which determine the above criteria are designated by (AC) next to the signoff blank.

BFN RWM Functional Test for Startup 3-SR-3.3.2.1.2 Unit 3 Rev. 0003 Page 7 of 10 7.0 PROCEDURE STEPS

[1] VERIFY that the following initial conditions are satisfied:

[1.1 ] ALL precautions AND limitations in Section 3.0 have been reviewed.

[1.2] ALL prerequisites in Section 4.0 are satisfied. ub

[2] OBTAIN permission from Unit Supervisor (US) to perform this 3-SR-3.3.2.1.2 test procedure:

US Signature Time

[3] [NRC/C] NOTIFY Unit Operator (UO) before commencing this 3-SR-3.3.2.1.2 test procedure. [RPT 82-16, LER 259/8232].

[4] RECORD the start date AND time, reason for test, plant conditions AND ANY pre-test remarks on Attachment 1, Surveillance Procedure Review Form in Section 8.0.

NOTE ALL operations are performed on Panel 3-9-5 in the main Control Room unless otherwise noted.

[5] PLACE the Control Rod Drive (CRD) POWER switch (3-HS-85-46) momentarily to OFF AND next SWITCH to ON.

[6] VERIFY ALL control rods are deselected on the rod select matrix.

BFN RWM Functional Test for Startup 3-SR-3.3.2.1.2 Unit 3 Rev. 0003 Page 8 of 10 Date _ __

7.0 PROCEDURE STEPS (continued)

[7] PERFORM the RWM Functional Test as follows:

[7.1] VERIFY OR PLACE the RWM in operation per 3-01-85.

[7.2] [NERlC] REQUEST Reactor Engineering to PERFORM 3-SR-3.3.2.1.7 OR VERIFY performance of 3-SR-3.3.2.1.7. [INPO SOER 84-002]

RE

[7.3] REFER to the Control Rod Movement Data Sheet from 3-SR-3.1.3.S(A) to identify a rod from RWM Group 02.

[7.4] RECORD below the rod chosen:

Rod Number: - - - - -

[7.5] SELECT the rod recorded in Step 7.0[7.4].

[7.6]

[7.7]

VERIFY the SELECT ERROR status block on the RWM display is in alarm (red background).

NOTCH the selected rod to position 02.

[7.8] VERIFY that the rod moved to position 02 is identified as a withdraw error on the RWM display.

[7.9] PLACE the CRD Control switch (3-HS-85-48) to ROD OUT NOTCH AND VERIFY the following:

[7.9.1] The selected control rod does NOT withdraw. (AC)

[7.9.2] The WITHDRAW BLOCK status block on the RWM display is in alarm (red background). (AC)

[7.9.3] RWM ROD BLOCK (3-XA-55-5B, Window 35) is in ALARM.

[7.10] INSERT the selected rod from position 02 to 00.

[7.11] VERIFY the WITHDRAW BLOCK status block on the RWM display is NOT in alarm.

[7.12] VERIFY RWM ROD BLOCK (3-XA-55-5B, Window 35) will RESET.

l I I <

BFN RWM Functional Test for Startup 3-SR-3.3.2.1.2 Unit 3 Rev. 0003 Page 9 of 10 Date _ __

7.0 PROCEDURE STEPS (continued)

[7.13] REFER to the Control Rod Movement Data Sheet from 3-SR-3.1.3.5(A) to identify a rod from RWM Group 01.

[7.14] RECORD below the rod chosen:

Rod Number:

[7.15] SELECT the rod recorded in Step 7.0[7.14].

[7.16] VERIFY that rod Group 01 is indicated as the latched group on the RWM Panel.

[8] RECORD the appropriate test information on Attachment 1, Surveillance Procedure Review Form (located in Section 8.0)

AND COMPLETE up to the Unit Supervisor review.

[9] NOTIFY the UO that this SR test procedure is complete.

8.0

[10] NOTIFY the US that this SR test procedure is complete.

ILLUSTRATIONS/ATTACHMENTS Attachment 1, Surveillance Procedure Review Form.

.J I I 4' BFN RWM Functional Test for Startup 3-SR-3.3.2.1.2 Unit 3 Rev. 0003 Page 10 of 10 Attachment 1 (Page 1 of 1)

Surveillance Procedure Review Form REASON FOR TEST: DATEITIME STARTED 7;phy /AQ.,J rr Scheduled Surveillance DATEITIME COMPLETED

o System Inoperable (Explain in Remarks) PLANT CONDITIONS ----

o Maintenance (WO No. _ _ _ _ _ __

o Other (Explain in Remarks)

PRE-TEST REMARKS:

PERFORMED BY:

Initials Name (Print)

",-0 C).,,\';i: q,rt'l.O~ (Test Dir/Lead Perf)

(Test Dir/Lead Perf)

Delays or Problems (If yes, explain in POST-TEST REMARKS)? DYes DNo Acceptance Criteria Satisfied? DYes DNo If the above answer is no, the Unit Supervisor shall determine if an LCO exists. LCO DYes DNo UNIT SUPERVISOR Date lOR (OPS) _ _ _ _ _ _ _ _ _ _ Date _ _ _ _ _ _ __

SCHEDULING COORDINATOR Date POST-TEST REMARKS:

JPM NO. 43F REV. NO.2 PAGE 1 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER: 43F TITLE: EOI APPENDIX-11B -ALTERNATE PRESSURE CONTROL-RCIC TEST MODE (FROM STANDBY)

TASK NUMBER: U-OOO-EM-54 SUBMITTED BY: DATE: _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: _______________ DATE: _ _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 43F REV. NO.2 PAGE 2 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 10/06/06 All Initial issue 1 09/22/07 All General revision 2 03/27/09 All General revision & re-format

JPM NO. 43F REV. NO.2 PAGE 3 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: _____________________________________________

RO SRO DATE: ___________

JPM NUMBER: 43F TASK NUMBER: U-000-EM-54 TASK TITLE: EOI APPENDIX-11B -ALTERNATE PRESSURE CONTROL-RCIC TEST MODE (FROM STANDBY)

KIA NUMBER: 241000A4.02 KIA RATING: RO 4.1 SRO 4.1

- - - - AAAAA**********************************************************************************

TASK STANDARD: PERFORM OPERATIONS NECESSARY TO PLACE RCIC IN THE TEST MODE FROM STANDBY FOR ALTERNATE RPV PRESSURE CONTROL AS DIRECTED BY 2-EOI APPENDIX-11 B PERFORMANCE LOCATION: SIMULATOR X PLANT - CONTROL ROOM_

REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-11 B, Rev 5 VALIDATION TIME: SIMULATOR: 10:00 LOCAL: ________

MAX. TIME ALLOWED: ________ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS ATTACHED? YES ____ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ___________________ DATE: ___________

JPM NO. 43F REV. NO.2 PAGE 4 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an operator. The Unit 2 reactor has scrammed and bypass valves are not responding properly for pressure control. EOI-1 has been followed to RC/P-11. RCIC is in standby readiness.

INITIATING CUES: The UNIT SUPERVISOR directs you to place RCIC in Alternate RPV Pressure Control as directed by 2-EOI Appendix-11 B.

JPM NO. 43F REV. NO.2 PAGE 5 of 17 START TIME _ _ _ _ __

Simulator Driver: This JPM requires 71-9 tripped and failure of RCIC controller after time delay {trigger off of 71-8 valve).

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 2-EOI Appendix-11 B.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 43F REV. NO.2 PAGE 6 of 17 CAUTION

Operating RCIC turbine below 2100 rpm may result in unstable system operation and equipment damage.

Elevated Suppression Chamber pressure may trip the RCIC turbine on high exhaust pressure.

Operating RCIC Turbine with suction temperatures above 140°F may result in equipment damage.

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

1. IF ..... Emergency RPV Depressurization is required ,

OR Steam Cooling is required, THEN ... EXECUTE EOI Appendix 16A and 168 as necessary to bypass RCIC Low RPV Pressure and Test Mode Isolation Interlocks.

I CUE: Emergency depressurization and steam cooling are not required.

STANDARD:

determined NOT to execute EOI Appendix 16A or 168.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 43F REV. NO.2 PAGE 7 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

2. IF ..... Suppression Pool level CANNOT be maintained below 5.25 in.,

THEN ... EXECUTE EOI Appendix 16E concurrently with this procedure to bypass HPCI High Suppression Pool Level Suction Transfer Interlock.

STANDARD:

Determined Suppression Pool level <5.25 inches and EOI Appendix-16E not required.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

3. IF ..... RCIC Turbine is operating and NOT required for RPV level control, THEN ... ALIGN RCIC in test mode as follows:

a. OPEN 2-FCV-71-38, RCIC PUMP CST TEST VLV.

b. VERIFY OPEN 2-FCV-73-36, HPCIIRCIC CST TEST VLV.

c. CLOSE 2-FCV-71-39, RCIC PUMP INJECTION VALVE.

d. CONTINUE in this procedure at Step 5.

STANDARD:

N/A - RCIC is Not operating.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 43F REV. NO.2 PAGE 8 of 17 PERFORMANCE STEP:

4. IF .....

THEN ...

CRITICAL RCIC is in standby readiness, START RCIC as follows:

NOT CRITICAL x

a. VERIFY CLOSED 2-FCV-71-39, RCIC PUMP INJECTION VALVE.

STANDARD:

Verified only GREEN valve position indicating lamp illuminated above 2-HS-71-39A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

b. VERIFY RESET and OPEN 2-FCV-71-9, RCIC TURB TRIPITHROT VALVE RESET.

STANDARD:

Recognizes FCV-71-9 is tripped. Resets and Opens FCV-71-9 (Critical) and Verifies illuminated RED position indicating lamp above 2-ZI-71-9.(Not Critical)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 43F REV. NO.2 PAGE 9 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

c. VERIFY OPEN the following valves:

2-FCV-71-38, RCIC PUMP CST TEST VLV STANDARD:

Held 2-HS-71-38A in the OPEN position until valve is open (Critical) and Verified only RED valve position indicating lamp illuminated above associated control switch (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

STANDARD:

2-FCV-71-25, RCIC LUBE OIL COOLING WTR VLV Placed 2-HS-71-25A in the OPEN position (Critical) and Verified only RED valve position indicating lamp illuminated above associated control switch (Not Critical).

SAT UNSAT N/A _ _ . COMMENTS: _ _ _ _ __

JPM NO. 43F REV. NO.2 PAGE 10 of 17

~ ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

2-FCV-71-34, RCIC PUMP MIN FLOW VALVE STANDARD:

Placed 2-HS-71-34A in the OPEN position and verified only RED valve position indicating lamp illuminated above associated control switch.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

2-FCV-73-36, HPCI/RCIC CST TEST VLV.

STANDARD:

~ Placed 2-HS-73-36A in the OPEN position (Critical) and Verified only RED valve position indicating lamp illuminated above associated control switch (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 43F REV. NO.2 PAGE 11 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

d. PLACE 2-HS-71-31A, RCIC VACUUM PUMP, handswitch in START.

STANDARD:

Placed 2-HS-71-31A in the START position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

e. OPEN 2-FCV-71-8, RCIC TURBINE STEAM SUPPLY VLV, to start RCIC Turbine.

STANDARD:

Placed 2-HS-71-8A in the OPEN position (Critical) and verified illuminated RED valve position indicating lamp above hand switch (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 43F REV. NO.2 PAGE 12 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

f. VERIFY RCIC Turbine speed accelerates to above 2100 rpm.

STANDARD:

Verified speed greater than 2100 rpm indicated on 2-SI-71-42A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

5. VERIFY proper RCIC minimum flow valve operation as follows:

a. IF ...... RCIC flow is above 120 gpm,

THEN .... VERIFY CLOSED 2-FCV-71-34, RCIC PUMP MIN FLOW VALVE.

STANDARD:

When 2-FIC-71-36A indicated flow> 120 gpm, verified only GREEN valve position indicating lamp illuminated above 2-HS-71-34A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 43F REV. NO.2 PAGE 13 of 17

~ ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

b. IF ..... . 80TH of the following exist:

RCIC Initiation signal is NOT present, AND

RCIC flow is below 60 gpm, THEN .... VERIFY OPEN 2-FCV-71-34, RCIC PUMP MIN FLOW VALVE.

STANDARD:

Verified RCIC flow> 60 gpm as indicated on 2-FIC-71-36A and/or RCIC initiation lamp located above XS-71-52 Not illuminated.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

~ ****************************************************************************************************

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

6. THROTTLE 2-FCV-71-38, RCIC PUMP CST TEST VLV, to control RCIC pump discharge pressure at or below 1100 psig.

STANDARD:

Throttled 2-FCV-71-38 to maintain pressure on 2-PI-71-35A at or below 1100 psig. (ONLY CRITICAL if pressure exceeds 1100 psig - any pressure < 1100 psig is acceptable.)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

~

JPM NO. 43F REV. NO.2 PAGE 14 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

7. ADJUST 2-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL, controller to control RPV pressure.

STANDARD:

Candidate recognizes RCIC Flow Controller Failure and places 2-FIC-71-36A in Manual and adjusts the flow controller in conjunction with the 2-FCV-71-38, RCIC PUMP CST TEST VL V to obtain:

RCIC flow 120-600 gpm on 2-FIC-71-36A.

RCIC discharge pressure ~ 1100 psig on 2-PI-71-35A.

RCIC speed> 2100 rpm on 2-SI-71-42A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 43F REV. NO.2 PAGE 15 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

8. IF ..... RCIC injection to the RPV becomes necessary, THEN ... ALIGN RCIC to RPV as follows:

a. OPEN 2-FCV-71-39, RCIC PUMP INJECTION VALVE.

b. CLOSE 2-FCV-71-38, RCIC PUMP CST TEST VLV.

c. GO to EOI Appendix 5C.

I CUE: Injection to the vessel with RCle is Not desired at this time.

STANDARD:

N/A - Injection to vessel not required per CUE.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

I CUE: That completes this task.

JPM NO. 43F REV. NO.2 PAGE 16 of 17

~ ****************************************************************************************************

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM

~

STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

~

PAGE 17 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an operator. The Unit 2 reactor has scrammed and bypass valves are not responding properly for pressure contro/. EOI-1 has been followed to RC/P-11. RCIC is in standby readiness.

INITIATING CUES: The UNIT SUPERVISOR directs you to place RCIC in Alternate RPV Pressure Control as directed by 2-EOI Appendix-11 B.

PAGE 17 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an operator. The Unit 2 reactor has scrammed and bypass valves are not responding properly for pressure control. EOI-1 has been followed to RC/P-11. RCIC is in standby readiness.

INITIATING CUES: The UNIT SUPERVISOR directs you to place RCIC in Alternate RPV Pressure Control as directed by 2-EOI Appendix-11 B.

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EOI PROGRAM MANUAL SECTION IX 2-EOI APPENDIX-11 8 ALTERNATE RPV PRESSURE CONTROL SYSTEMS RCIC TEST MODE REVISION 5

PREPARED BY: D. Powell PHONE: 2528 RESPONSIBLE ORGANIZATION: Operations APPROVED BY: Tony Elms EFFECTIVE DATE: 08/22/2007 LEVEL OF USE: REFERENCE USE EOI VALIDATION DATE: 02/14/1992 QUALITY-RELATED

HISTORY OF REVISION/REVIEW 2-EOI APPENDIX-11 B

REV.

NO.

5 REVISED PAGES 1

REASON FOR CURRENT REVISION TR# 06 - Step 2: Changed suppression pool level at which Appendix-16E is implemented to 5.25 in. This is in agreement with NESSD 2S-073-057A(8)-00-02 for the setpoint where HPCI suction swap occurs.

2-EOI APPENDIX-llB Rev. 5 Page 1 of 3 2-EOI APPENDIX-llB ALTERNATE RPV PRESSURE CONTROL SYSTEMS RCIC TEST MODE LOCATION: Unit 2 Control Room ATTACHMENTS: None CAUTION

Operating RCIC turbine below 2100 rpm may result in unstable system operation and equipment damage.

Elevated Suppression Chamber pressure may trip the RCIC turbine on high exhaust pressure.

Operating RCIC Turbine with suction temperatures above 140°F may result in equipment damage.

1. IF ..... Emergency RPV Depressurization is required, OR Steam Cooling is required, THEN ... EXECUTE EOI Appendix l6A and l6B as necessary to bypass RCIC Low RPV Pressure and Test Mode Isolation Interlocks.

2. IF ..... Suppression Pool level CANNOT be maintained below 5.25 in.,

THEN ... EXECUTE EOI Appendix l6E concurrently with this procedure to bypass HPCI High Suppression Pool Level Suction Transfer Interlock.

3. IF ..... RCIC Turbine is operating and NOT required for RPV level control, THEN ... ALIGN RCIC in test mode as follows:

a. OPEN 2-FCV-7l-38, RCIC PUMP CST TEST VLV.

b. VERIFY OPEN 2-FCV-73-36, HPCI/RCIC CST TEST VLV.

c. CLOSE 2-FCV-7l-39, RCIC PUMP INJECTION VALVE.

d. CONTINUE in this procedure at Step 5.

2-EOI APPENDIX-11B Rev. 5 Page 2 of 3

4. IF ..... RCIC is in standby readiness, THEN ... START RCIC as follows:

a. VERIFY CLOSED 2-FCV-71-39, RCIC PUMP INJECTION VALVE.

b. VERIFY RESET and OPEN 2-FCV-71-9, RCIC TURB TRIP/THROT VALVE RESET.

c. VERIFY OPEN the following valves:

2-FCV-71-38, RCIC PUMP CST TEST VLV

2-FCV-71-25, RCIC LUBE OIL COOLING WTR VLV

2-FCV-71-34, RCIC PUMP MIN FLOW VALVE

2-FCV-73-36, HPCI/RCIC CST TEST VLV.

d. PLACE 2-HS-71-31A, RCIC VACUUM PUMP, handswitch in START.

e. OPEN 2-FCV-71-8, RCIC TURBINE STEAM SUPPLY VLV, to start RCIC Turbine.

f. VERIFY RCIC Turbine speed accelerates to above 2100 rpm.

5. VERIFY proper RCIC minimum flow valve operation as follows:

a. IF ...... RCIC flow is above 120 gpm, THEN .... VERIFY CLOSED 2-FCV-71-34, RCIC PUMP MIN FLOW VALVE.

b. IF ...... BOTH of the following exist:

RCIC Initiation signal is NOT present, AND

RCIC flow is below 60 gpm, THEN .... VERIFY OPEN 2-FCV-71-34, RCIC PUMP MIN FLOW VALVE.

6. THROTTLE 2-FCV-71-38, RCIC PUMP CST TEST VLV, to control RCIC pump discharge pressure at or below 1100 psig.

7. ADJUST 2-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL, controller to control RPV pressure.

2-EOI APPENDIX-lIB Rev. 5 Page 3 of 3

8. IF ..... RCIC injection to the RPV becomes necessary, THEN ... ALIGN RCIC to RPV as follows:

a. OPEN 2-FCV-71-39, RCIC PUMP INJECTION VALVE.

b. CLOSE 2-FCV-71-38, RCIC PUMP CST TEST VLV.

c. GO to EOI Appendix 5C.

LAST PAGE

JPM NO. 343F REV. NO. 0 PAGE 1 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER: 343F TITLE: EOI APPENDIX-11B - ALTERNATE PRESSURE CONTROL-RCIC TEST MODE (FROM STANDBY)

TASK NUMBER: U-OOO-EM-54 SUBMITTED BY: DATE: _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: _ _ _ _ _ _ _ _ __ __ DATE: _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 343F REV. NO. 0 PAGE 2 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 0 08/02/08 All Initial issue

JPM NO. 343F REV. NO. 0 PAGE 3 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: ______________________________________________

RO SRO DATE: ____________

JPM NUMBER: 343F TASK NUMBER: U-000-EM-54 TASK TITLE: EOI APPENDIX-11B - ALTERNATE PRESSURE CONTROL-RCIC TEST MODE (FROM STANDBY)

KIA NUMBER: 241000A4.02 KIA RATING: RO 4.1 SRO 4.1 TASK STANDARD: PERFORM OPERATIONS NECESSARY TO PLACE RCIC IN THE TEST MODE FROM STANDBY FOR ALTERNATE RPV PRESSURE CONTROL AS DIRECTED BY 3-EOI APPENDIX-11 B PERFORMANCE LOCATION: SIMULATOR X PLANT - CONTROL ROOM_

REFERENCES/PROCEDURES NEEDED: 3-EOI Appendix-11 B, Rev 3 VALIDATION TIME: SIMULATOR: 10:00 LOCAL: ______

MAX. TIME ALLOWED: ________ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS AITACHED? YES ___ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: ____________________ DATE: _ _ _ _ _ __

JPM NO. 343F REV. NO. 0 PAGE 4 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an operator. The Unit 3 reactor has scrammed and bypass valves are not responding properly for pressure control. EOI-1 has been followed to RC/P-11. RCIC is in standby readiness.

INITIATING CUES: The UNIT SUPERVISOR directs you to place RCIC in Alternate RPV Pressure Control as directed by 3-EOI Appendix-11 B.

JPM NO. 343F REV. NO. 0 PAGE 5 of 17 START TIME _ _ _ _ __

Simulator Driver: This JPM requires 71-9 tripped and failure of RCIC controller after time delay (trigger off of 71-8 valve).

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 3-EOI Appendix-11 B.

SAT UNSAT N/A _ _ COMMENTS: _ _ __ _ _

JPM NO. 343F REV. NO. 0 PAGE 6 of 17 CAUTION

Operating RCIC turbine below 2100 rpm may result in unstable system operation and equipment damage.

Elevated Suppression Chamber pressure may trip the RCIC turbine on high exhaust pressure.

Operating RCIC Turbine with suction temperatures above 140°F may result in equipment damage.

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

1. IF ..... Emergency RPV Depressurization is required, OR Steam Cooling is required, THEN ... EXECUTE EOI Appendix 16A and 168 as necessary to bypass RCIC Low RPV Pressure and Test Mode Isolation Interlocks.

I CUE: Emergency depressurization or steam cooling are not required.

STANDARD:

Determined NOT to execute EOI Appendix16A or 168.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 343F REV. NO. 0 PAGE 7 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

2. IF ..... Suppression Pool level CANNOT be maintained below 5.25 in.,

THEN ... EXECUTE EOI Appendix 16E concurrently with this procedure to bypass HPCI High Suppression Pool Level Suction Transfer Interlock.

STANDARD:

Determined Suppression Pool level < +5.25 inches and EOI Appendix-16E not required.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

3. IF .....

THEN ...

a.

b.

RCIC Turbine is operating and NOT required for RPV level control, ALIGN RCIC in test mode as follows:

OPEN 3-FCV-71-38, RCIC PUMP CST TEST VLV.

VERIFY OPEN 3-FCV-73-36, HPCI/RCIC CST TEST VLV.

c. CLOSE 3-FCV-71-39, RCIC PUMP INJECTION VALVE.

d. CONTINUE in this procedure at Step 5.

STANDARD:

N/A - RCIC is Not operating.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 343F REV. NO. 0 PAGE 8 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

4. IF ..... RCIC is in standby readiness, THEN ... START RCIC as follows:

a. VERIFY CLOSED 3-FCV-71-39, RCIC PUMP INJECTION VALVE.

STANDARD:

Verified only GREEN valve position indicating lamp illuminated above 3-HS-71-39A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

b.

STANDARD:

VERIFY RESET and OPEN 3-FCV-71-9, RCIC TURB TRIPITHROT VALVE RESET.

Recognizes FCV-71-9 is triPpe~ and Opens FCV-71-9 (Critical) and Verifies illuminated RED position indicaft~~I;~l~ above 3-ZI-71-9.(Not Critical)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 343F REV. NO. 0 PAGE 9 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

c. VERIFY OPEN the following valves:

3-FCV-71-38, RCIC PUMP CST TEST VLV STANDARD:

Held 3-HS-71-38A in the OPEN position until valve is open (Critical) and Verified only RED valve position indicating lamp illuminated above associated control switch (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

STANDARD:

3-FCV-71-25, RCIC LUBE OIL COOLING WTR VLV Placed 3-HS-71-25A in the OPEN position (Critical) and Verified only RED valve position indicating lamp illuminated above associated control switch (Not Critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 343F REV. NO. 0 PAGE 10 of 17 PERFORMANCE STEP:

CRITICAL 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE NOT CRITICAL x STANDARD:

Placed 3-HS-71-34A in the OPEN position and verified only RED valve position indicating lamp illuminated above associated control switch.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

3-FCV-73-36, HPCI/RCIC CST TEST VLV.

STANDARD:

Placed 3-HS-73-36A in the OPEN position (Critical) and Verified only RED valve position indicating lamp illuminated above associated control switch (Not Critical).

COMMENTS: _ _ _ _ __

SAT UNSAT N/A _ _

JPM NO. 343F REV. NO. 0 PAGE 11 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

d. PLACE 3-HS-71-31A, RCIC VACUUM PUMP, handswitch in START.

STANDARD:

Placed 3-HS-71-31A in the START position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

e. OPEN 3-FCV-71-8, RCIC TURBINE STEAM SUPPLY VLV, to start RCIC Turbine.

STANDARD:

Placed 3-HS-71-8A in the OPEN position (Critical) and verified illuminated RED valve position indicating lamp above hand switch (Not Critical).

COMMENTS: _ _ _ _ __

SAT UNSAT N/A _ _

JPM NO. 343F REV. NO. 0 PAGE 12 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

f. VERIFY RCIC Turbine speed accelerates to above 2100 rpm.

STANDARD:

Verified speed greater than 2100 rpm indicated on 3-SI-71-42A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

5. VERIFY proper RCIC minimum flow valve operation as follows:

a. IF ..... . RCIC flow is above 120 gpm,

STANDARD:

THEN .... VERIFY CLOSED 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE.

When 3-FIC-71-36A indicated flow> 120 gpm, verified only GREEN valve position indicating lamp illuminated above 3-HS-71-34A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 343F REV. NO. 0 PAGE 13 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

b. IF ..... . BOTH of the following exist:

RCIC Initiation signal is NOT present, AND

RCIC flow is below 60 gpm, THEN .... VERIFY OPEN 3-FCV-71-34, RCIC PUMP MIN FLOW VALVE.

STANDARD:

Verified RCIC flow> 60 gpm as indicated on 3-FIC-71-36A and/or RCIC initiation lamp located above XS-71-52 Not illuminated.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

6. THROTTLE 3-FCV-71-38, RCIC PUMP CST TEST VLV, to control RCIC pump discharge pressure at or below 1100 psig.

STANDARD:

Throttled 3-FCV-71-38 to maintain pressure on 3-PI-71-35A at or below 1100 psig. (ONLY CRITICAL if pressure exceeds 1100 psig - any pressure < 1100 psig is acceptable.)

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 343F REV. NO. 0 PAGE 14 of 17 PERFORMANCE STEP: CRITICAL x NOT CRITICAL

7. ADJUST 3-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL , controller to control RPV pressure.

STANDARD:

Candidate recognizes RCIC Flow Controller Failure and places 3-FIC-71-36A in Manual and adjusts the flow controller in conjunction with the 2-FCV-71-38, RCIC PUMP CST TEST VL V to obtain:

RCIC flow 120-600 gpm on 3-FIC-71-36A.

RCIC discharge pressure ~ 1100 psig on 3-PI-71-35A.

RCIC speed> 2100 rpm on 3-SI-71-42A.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 343F REV. NO. 0 PAGE 15 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

8. IF ..... RCIC injection to the RPV becomes necessary, THEN ... ALIGN RCIC to RPV as follows:

a. OPEN 3-FCV-71-39, RCIC PUMP INJECTION VALVE.

b. CLOSE 3-FCV-71-38, RCIC PUMP CST TEST VL V.

c. GO to EOI Appendix 5C.

I CUE: Injection to the vessel with RCIC Is Not desired at this time.

STANDARD:

N/A -Injection to vessel not required per CUE.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

I CUE: That completes this task.

JPM NO. 343F REV. NO. 0 PAGE 16 of 17 PERFORMANCE STEP: CRITICAL NOT CRITICAL x PERFORMER demonstrated the use of SELF CHECKING during this JPM STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

END OF TASK STOP TIME: _ _ _ _ _ __

PAGE 17 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an operator. The Unit 3 reactor has scrammed and bypass valves are not responding properly for pressure control. EOI-1 has been followed to RC/P-11. RCIC is in standby readiness.

INITIATING CUES: The UNIT SUPERVISOR directs you to place RCIC in Alternate RPV Pressure Control as directed by 2-EOI Appendix-11 B.

PAGE 17 of 17 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE

- - - - >t*'" >t'" "'***************************************************************************** '" "'*'''' " '

IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an operator. The Unit 3 reactor has scrammed and bypass valves are not responding properly for pressure control. EOI-1 has been followed to RC/P-11. RCIC is in standby readiness.

INITIATING CUES: The UNIT SUPERVISOR directs you to place RCIC in Alternate RPV Pressure Control as directed by 2-EOI Appendix-11 B.

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT EOI PROGRAM MANUAL SECTION IX 3-EOI APPENDIX-11 B ALTERNATE RPVPRESSURECONTROLSYSTEMS RCIC TEST MODE REVISION 3

PREPARED BY: D. Powell PHONE: 2528 RESPONSIBLE ORGANIZATION: Operations APPROVED BY: Tony Elms EFFECTIVE DATE: 08/22/2007 LEVEL OF USE: REFERENCE USE EOI VALIDATION DATE: 02/14/1992

QUALITY-RELATED

HISTORY OF REVISION/REVIEW 3-EOI APPENDIX-11 8

REV.

NO.

3 REVISED PAGES 1

REASON FOR CURRENT REVISION TR# 04 - Step 2: Changed suppression pool level at which Appendix-16E is implemented to 5.25 in. This is in agreement with 3-SIMI-738 for the setpoint where HPCI suction swap occurs.

3-EOI APPENDIX-11B Rev. 3 Page 1 of 3

~--------------------~

3-EOI APPENDIX-lIB ALTERNATE RPV PRESSURE CONTROL SYSTEMS RCIC TEST MODE LOCATION: Unit 3 Control Room ATTACHMENTS: None CAUTION

Operating RCIC turbine below 2100 rpm may result in unstable system operation and equipment damage.

Elevated Suppression Chamber pressure may trip the RCIC turbine on high exhaust pressure.

Operating RCIC Turbine with suction temperatures above 140°F may result in equipment damage.

1. IF ..... Emergency RPV Depressurization is required, OR Steam Cooling is required, THEN ... EXECUTE EOI Appendix 16A and 16B as necessary to bypass RCIC Low RPV Pressure and Test Mode Isolation Interlocks.

2. IF ..... Suppression Pool level CANNOT be maintained below 5.25 in.,

THEN EXECUTE EOI Appendix 16E concurrently with this procedure to bypass HPCI High Suppression Pool Level Suction Transfer Interlock.

3. IF ..... RCIC Turbine is operating and NOT required for RPV level control, THEN ... ALIGN RCIC in test mode as follows:

a. OPEN 3-FCV-71-38, RCIC PUMP CST TEST VLV.

b. VERIFY OPEN 3-FCV-73-36, HPCI/RCIC CST TEST VLV.

c. CLOSE 3-FCV-71-39, RCIC PUMP INJECTION VALVE.

d. CONTINUE in this procedure at Step 5.

3-EOI APPENDIX-lIB Rev. 3 Page 2 of 3

4. IF ..... RCIC is in standby readiness, THEN ... START RCIC as follows:

a. VERIFY CLOSED 3-FCV-7l-39, RCIC PUMP INJECTION VALVE.

b. VERIFY RESET and OPEN 3-FCV-7l-9, RCIC TURB TRIP/THROT VLV RESET.

c. VERIFY OPEN the following valves:

3-FCV-7l-38, RCIC PUMP CST TEST VLV

3-FCV-7l-25, RCIC LUBE OIL COOLING WTR VLV

3-FCV-7l-34, RCIC PUMP MIN FLOW VALVE

3-FCV-73-36, HPCI/RCIC CST TEST VLV.

d. PLACE 3-HS-7l-3lA, RCIC VACUUM PUMP, handswitch in START.

e. OPEN 3-FCV-7l-8, RCIC TURBINE STEAM SUPPLY VLV, to start RCIC Turbine.

f. VERIFY RCIC Turbine speed accelerates to above 2100 rpm.

5. VERIFY proper RCIC minimum flow valve operation as follows:

a. IF ..... RCIC flow is above 120 gpm, THEN ... VERIFY CLOSEDD 3-FCV-7l-34, RCIC PUMP MIN FLOW VALVE.

b. IF ..... BOTH of the following exist:

RCIC Initiation signal is NOT present, AND

RCIC flow is below 60 gpm, THEN ... VERIFY OPEN 3-FCV-7l-34, RCIC PUMP MIN FLOW VALVE.

6. THROTTLE 3-FCV-7l-38, RCIC PUMP CST TEST VLV, to control RCIC pump discharge pressure at or below 1100 psig.

3-EOI APPENDIX-lIB Rev. 3 Page 3 of 3

7. ADJUST 3-FIC-71-36A, RCIC SYSTEM FLOW/CONTROL, controller to control RPV pressure.

8. IF ..... RCIC injection to the RPV becomes necessary, THEN ... ALIGN RCIC to RPV as follows:

a. OPEN 3-FCV-71-39, RCIC PUMP INJECTION VALVE.

b. CLOSE 3-FCV-71-38, RCIC PUMP CST TEST VLV.

c. GO to EOI Appendix 5C.

LAST PAGE

JPM NO. 81 REV. NO. 8 PAGE 1 OF 12 I

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE I

JPM NUMBER: 81 TITLE: RESPOND TO UNCOUPLED CONTROL ROD (MULTIPLE NOTCHES)

TASK NUMBER: U-OOO - AB-02 SUBMITTED BY: DATE: - - - - -

VALIDATED BY: DATE: -----------

APPROVED: DATE: - - - - -

TRAINING PLANT CONCURRENCE: DATE: -----------

OPERATIONS

Examination JPMs Require Operations Training Manager or Designee Approval and Plant Concurrence

JPM NO. 81 REV. NO. 8 PAGE 2 OF 12 I

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE I

REVISION LOG Revision Effective Pages Description Number Date Affected of Revision 2 10/4/94 ALL GENERAL REVISION 3 12/14/95 4 CHANGED PROCEDURE FROM 2-AOI-85-1 TO 2-AOI-85-2 4 12/16/96 ALL PROCEDURE CHANGE, ADDED NON-CRIT STEP ON TOUCH STAAR, CHANGED ASOS TO US.

5 11/10/99 ALL PROCEDURE REVISION, FORMAT DOCUMENT, CHANGED MGT. EXPECT. TO PLANT WORK EXPECT., ADDED NON-CRIT. STEP 3-WAY COMM.

6 10/11/00 ALL GENERAL REVISION 7 9/1/02 ALL GENERAL REVISION 8 8/21/03 ALL FORMAT; EDITORIAL

JPM NO. 81 REV. NO. 8 PAGE 3 OF 12 I

BROWNS FERRY NUCLEAR PLANT I JOB PERFORMANCE MEASURE OPERATOR: ___________________________________

RO SRO DATE: ______________________

JPM NUMBER: 81 TASK NUMBER: U-000-AB-02 TASK TITLE: RESPOND TO AN UNCOUPLED CONTROL ROD K/A NUMBER: 201003A2.02 K/A RATING: RO 3.7 SRO: 3.8 TASK STANDARD: PERFORM OPERATIONS NECESSARY TO RESPOND TO AN UNCOUPLED CONTROL ROD AS DIRECTED BY 2-AOI-85-2 LOCATION OF PERFORMANCE: SIMULATOR X PLANT CONTROL ROOM REFERENCES/PROCEDURES NEEDED: 2-AOI-85-2, REV 12 VALIDATION TIME: CONTROL ROOM: 11:00 LOCAL:

MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME: CONTROL ROOM -----LOCAL COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY

UNSATISFACTORY -------

SIGNATURE: DATE:

--~E~XAM~=I=NE==R~----------------

I BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE I

IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. 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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator. Unit 2 is in the startup mode withdrawing control rods in RWM Group 1. Control rod 02-23 was withdrawn from 00 to position 48 and has just been checked for coupling integrity. CONTROL ROD OVERTRAVEL annunciator (2-XA 5A, Window 14) is in alarm and control rod 02-23 has been verified to be uncoupled.

INITIATING CUES: The UNIT SUPERVISOR has directed you to respond to the uncoupled control rod as directed by 2-AOI-85-2.

JPM NO. 81 REV. NO. 8 PAGE 5 OF 12 START TIME - - - - - -

NOTE; SELECT A STARTUP IC WITHDRAWING RODS TO POSITION 48 AND INSERT THE UNCOUPLED MALFUNCTION FOR ROD 02-23 AND WITHDRAW IT TO POSITION 48 TO GENERATE THE DRIFT AND OVERTRAVEL ANNUNCIATORS.

Performance Step: Critical Not Critical X WHEN REQUESTED BY EXAMINER identify/obtain copy of required procedure.

Standard:

IDENTIFIED OR OBTAINED copy of 2-AOI-85-2.

SAT- - - UNSAT- - - N/A COMMENTS:

JPM NO. 81 REV. NO. 8 PAGE 6 OF 12 4.0 OPERATOR ACTIONS 4.1 Immediate Actions Performance Step: Critical X Not Critical 4.1.1 STOP all control rod withdrawal.

Standard:

DID NOT ATTEMPT further rod withdrawal.

SAT- - - UNSAT- - - N/A - - - COMMENTS:

4.2 Subsequent Actions Performance Step: Critical Not Critical X 4.2.1 NOTIFY Reactor Engineer to evaluate the uncoupled control rod for its impact on core thermal limits and rod worth.

Standard:

NOTIFIED Reactor Engineer to evaluate the rod for its impact on core thermal limits and rod worth.

SAT- - - UNSAT- - - N/A COMMENTS:

CUE: [WHEN REACTOR ENGINEER ASKED] NO THERMAL LIMIT OR ROD WORTH PROBLEMS AS LONG AS NO OTHER RODS BEYOND THIS ROD IN THE SEQUENCE ARE WITHDRAWN PAST POSITION 00.

JPM NO. 81 REV. NO. 8 PAGE 7 OF 12 4.2.2 ADJUST the rod pattern as directed by the Reactor Engineer throughout the performance of this procedure.

4.2.3 IF the control rod drive is at position 48 and with Reactor Engineer concurrence, THEN PERFORM the following:

CUE: THE REACTOR ENGINEER AGREES THAT STEP 4.2.3 SHOULD BE PERFORMED TO RECOUPLE THE CONTROL ROD.

Performance Step Critical X Not Critical

Standard:

4.2.3.1 NOTCH INSERT the control rod drive to position 46 to attempt to couple the control rod.

NOTCHED control rod drive in to notch 46.

SAT UNSAT_ _N/A_ _ COMMENTS: _ _ _ _ _ _ _ _ _ _ _ _ __

Performance Step : Critical Not Critical X 4.2.3.2 RESET associated annunciators.

Standard:

RESET CONTROL ROD OVERTRAVEL and CONTROL ROD DRIFT annunciators.

SAT- - - UNSAT- - - N/A COMMENTS:

JPM NO. 81 REV. NO. 8 PAGE 8 OF 12 Performance Step : Critical X Not Critical 4.2.3.3 NOTCH WITHDRAW the control rod drive to position 48.

Standard:

NOTCH WITHDREW the affected control rod to position 48.

SAT- - - UNSAT- - - - N/A COMMENTS:

Performance Step : Critical X Not Critical 4.2.3.4 PERFORM a coupling check.

Standard:

PERFORMED coupling integrity check by giving another notch withdrawal signal. VERIFIED control rod still uncoupled by observing CONTROL ROD OVERTRAVEL and CONTROL ROD DRIFT alarms and loss of control rod position indication.

SAT- - - UNSAT----- N/A COMMENTS:

JPM NO. 81 REV. NO. 8 PAGE 9 OF 12 Performance Step Critical X Not Critical 4.2.3.5 IF coupling integrity check fails, THEN CONTINUOUSLY INSERT control rod to position 00 to attempt to latch control rod with control rod drive mechanism.

Standard:

CONTINUOUSLY INSERTED the affected control rod to 00.

SAT- - - UNSAT- - - N/A COMMENTS:

Performance Step Critical X Not Critical 4.2.3.5.1 RESET associated annunciators.

Standard:

RESET CONTROL ROD OVERTRAVEL and CONTROL ROD DRIFT annunciators on Panel 2-9-5.

SAT- - - UNSAT- - - - - - - N/A COMMENTS:

NOTE: HAVE CONSOLE OPERATOR DELETE ROD UNCOUPLED MALFUNCTION.

JPM NO. 81 REV. NO. 8 PAGE 10 OF 12 CUE: REACTOR ENGINEERING HAS EVALUATED THERMAL LIMITS AND ROD WORTH AND RECOMMENDS THAT CONTROL ROD 02-23 BE CONTINUOUSLY WITHDRAWN FROM 00 TO 48. WE UNDERSTAND NOTCH WITHDRAWAL IS REQUIRED PER 2-AOI-85-2. FOR EXPEDIENCY WE WOULD LIKE OT USE "RONOR" TO WITHDRAW THE ROD. UNIT SUPERVISOR DIRECTS YOU TO RONOR CONTROL ROD 02-23 TO POSITION 48.

Performance Step Critical X Not Critical 4.2.3.5.2 NOTCH WITHDRAW the control rod drive to position 48.

Standard:

NOTCH WITHDREW the affected control rod to position 48.

SAT- - - UNSAT- - - N/A COMMENTS:

Performance Step Critical X Not Critical 4.2.3.5.3 PERFORM a coupling check.

Standard:

APPLIED notch withdraw signal to the affected control rod.

DETERMINED control rod now coupled by presence of control rod position indication and/or lack of associated annunciators.

SAT- - - UNSAT- - - N/A COMMENTS:

NOTE: COUPLING INTEGRITY IS SATISFIED IF CRD NOTCH OVERRIDE SWITCH IS USED AND ROD IS WITHDRAWN TO POSITION 48.

END OF TASK STOP TIME

JPM NO. 81 REV. NO. 8 PAGE 11 OF 12 GENERIC WORK PRACTICES Performance Step: Critical Not Critical X PERFORMER demonstrated the use of SELF CHECKING during this JPM.

Standard:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT- - - UNSAT- - - - N/A COMMENTS:

Performance Step: Critical Not Critical X PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM.

Standard:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT- - - UNSAT- - - - N/A COMMENTS:

I I BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. 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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator. Unit 2 is in the startup mode withdrawing control rods in RWM Group 1. Control rod 02-23 was withdrawn from 00 to position 48 and has just been checked for coupling integrity . CONTROL ROD OVERTRAVEL annunciator (2-XA 5A, Window 14) is in alarm and control rod 02-23 has been verified to be uncoupled.

INITIATING CUES: The UNIT SUPERVISOR has directed you to respond to the uncoupled control rod as directed by 2-AOI-85-2.

BROWNS FERRY NUCLEAR PLANT I JOB PERFORMANCE MEASURE I

IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. 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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator. Unit 2 is in the startup mode withdrawing control rods in RWM Group 1. Control rod 02-23 was withdrawn from 00 to position 48 and has just been checked for coupling integrity. CONTROL ROD OVERTRAVEL annunciator (2-XA-SS-SA, Window 14) is in alarm and control rod 02-23 has been verified to be uncoupled.

INITIATING CUES: The UNIT SUPERVISOR has directed you to respond to the uncoupled control rod as directed by 2-AOI-8S-2.

Browns Ferry Nuclear Plant

Unit 2 Abnormal Operating Instruction 2-AOI-85-2 Uncoupled Control Rod Revision 0012 Quality Related Level of Use: Continuous Use Effective Date: 01-24-2007 Responsible Organization: OPS, Operations

Prepared By:

Approved By:

Terry K. Boyer John T. Kulisek

BFN Uncoupled Control Rod 2-AOI-85-2 Unit 2 Rev. 0012 Page 2 of 8 Current Revision Description Pages Affected: All Type of Change: Data File Conversion Tracking Number: 0013 This procedure was converted from Word 95 to Word 2002 (XP) using Rev 11.

Minor editorial changes were made to enhance clarity and conform to the Technical Procedure Writers Guide.

BFN Uncoupled Control Rod 2-AOI-85-2 Unit2 Rev. 0012 Page 3 of 8 Table of Contents 1.0 PURPOSE .................................................................................................................... 4 2.0 SyMPTOMS ................................................................................................................. 4 3.0 AUTOMATIC ACTIONS ............................................................................................... 4 4.0 OPERATOR ACTIONS ................................................................................................ 5 4.1 Immediate Actions ........................................................................................................ 5 4.2 Subsequent Actions ...................................................................................................... 5

5.0 REFERENCES

............................................................................................................. 8 5.1 Technical Specifications ............................................................................................... 8 5.2 Final Safety Analysis Report ......................................................................................... 8 5.3 Plant Instructions .......................................................................................................... 8 5.4 Plant Drawings .............................................................................................................. 8 5.5 Vendor Manuals ............................................................................................................ 8

6.0 ILLUSTRATIONS/ATTACHMENTS ............................................................................. 8

BFN Uncoupled Control Rod 2-AOI-85-2 Unit 2 Rev. 0012 Page 4 of 8 1.0 PURPOSE This abnormal operating instruction provides symptoms, automatic actions and operator actions for an uncoupled control rod.

2.0 SYMPTOMS NOTE If a control rod is uncoupled and being withdrawn to any position other than position 48, the Rod Position Information System will display normal control rod movement. Power must be monitored to determine if the control rod is following its associated drive.

A. Nuclear instrumentation does not respond to control rod movement.

B. CONTROL ROD OVERTRAVEL annunciator (2-XA-55-5A, Window 14) in alarm.

C. Digital display and red backlighting for the uncoupled control rod on the full core display is extinguished.

3.0 AUTOMATIC ACTIONS None

BFN Uncoupled Control Rod 2-AOI-85-2 Unit 2 Rev. 0012 Page 5 of 8 4.0 OPERATOR ACTIONS 4.1 Immediate Actions

[1 ] STOP all control rod withdrawal. o 4.2 Subsequent Actions

[1 ] NOTIFY Reactor Engineer to evaluate the suspect uncoupled control rod for its impact on core thermal limits and rod worth. o

[2] ADJUST rod pattern as directed by Reactor Engineer throughout performance of this procedure. o

[3] IF control rod drive is at position 48, THEN, with Reactor Engineer concurrence, PERFORM the following: 0

[3.1] NOTCH INSERT control rod drive to position 46 to attempt to couple the control rod. 0

[3.2]

[3.3]

[3.4]

RESET associated annunciators.

NOTCH WITHDRAW control rod drive to position 48.

PERFORM coupling check.

0 0

0

[3.5] IF coupling integrity check fails, THEN CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism. 0

[3.5.1] RESET associated annunciators. o

[3.5.2] NOTCH WITHDRAW control rod to position 48. o

[3.5.3] PERFORM coupling check. o

BFN Uncoupled Control Rod 2-AOI-85-2 Unit 2 Rev. 0012 Page 6 of 8 4.2 Subsequent Actions (continued)

[4] IF the control rod drive is at any position other than notch 48 THEN with Reactor Engineer concurrence, after thorough evaluation of the reactor core conditions, PERFORM one of the following sub-steps as directed by the Reactor Engineer. 0

[4.1] ATTEMPT to latch control rod by fully inserting control rod as follows: o

[4.1.1 ] CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism. o

[4.1.2] NOTCH WITHDRAW control rod to position 48. o

[4.1.3] PERFORM coupling check. o

[4.1.4] IF coupling integrity check fails, THEN

CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism.

A. RESET associated annunciators.

o o

B. NOTCH WITHDRAW control rod to position 48. o C. PERFORM coupling check. o

[4.2] ATTEMPT to latch control rod by inserting control rod one notch as follows: o

[4.2.1] NOTCH INSERT control rod drive one notch to attempt to couple control rod. o

[4.2.2] NOTCH WITHDRAW control rod drive to position 48. o

[4.2.3] PERFORM coupling check. o

BFN Uncoupled Control Rod 2-AOI-85-2 Unit 2 Rev. 0012 Page 7 of 8 4.2 Subsequent Actions (continued)

[4.2.4] IF coupling integrity check fails, THEN CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism. o A. RESET associated annunciators. o B. NOTCH WITHDRAW control rod to position 48. o C. PERFORM coupling check. o CAUTION Technical Specification 3.1.3 applies to a control rod which CANNOT be coupled to its drive.

[5] IF coupling integrity check fails after above actions have been carried out, THEN

[5.1 ] CONTINUOUSLY INSERT control rod drive to position 00 AND REMOVE the associated hydraulic o

control unit from service until corrective action is performed. REFER TO 2-01-85. o

[5.2] RESET associated annunciators. o

BFN Uncoupled Control Rod 2-AOI-85-2 Unit 2 Rev. 0012 Page 8 of 8

5.0 REFERENCES

5.1 Technical Specifications Section 3.1, Reactivity Control Systems.

Section 5.4, Procedures.

Section 5.5, Programs and Manuals.

5.2 Final Safety Analysis Report Section 3.4, Reactivity Control Mechanical Design.

Section 13.6, Normal Operations 5.3 Plant Instructions 2-ARP-9-5, Panel 9-5 Annunciator Response Procedure.

2-01-85, Control Rod Drive System.

5.4 Plant Drawings 45N620-6, Wiring Diagram Annunciator.

2-47E61 0-85-1 , Mechanical Control Diagram CRD Hydraulic System.

104B2506 Sheet 2, Connection Diagram Position Indicator Probe.

730E321 Sheet 10, Elementary Diagram Reactor Manual Control System.

5.5 Vendor Manuals GEK-32539B in GEK-779-A, Volume 3, Part 2, Book 3, General Electric, Rod Position Information System, Contract 90744 BFN-CVM-21 05.

6.0 ILLUSTRATIONS/ATTACHMENTS None

JPM NO. 81 REV. NO. 8 PAGE 1 OF 12 I

BROWNS FERRY NUCLEAR PLANT I JOB PERFORMANCE MEASURE JPM NUMBER: 81 TITLE: RESPOND TO UNCOUPLED CONTROL ROD (MULTIPLE NOTCHES)

TASK NUMBER: U-OOO-AB-02 SUBMITTED BY: DATE: -----------

VALIDATED BY: DATE: _ _ _ __

APPROVED: DATE: _ _ _ __

TRAINING PLANT CONCURRENCE: DATE: -----------

OPERATIONS

Examination JPMs Require Operations Training Manager or Designee Approval and Plant Concurrence

JPM NO. 81 REV. NO. 8 PAGE 2 OF 12 I BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE I

REVISION LOG Revision Effective Pages Description Number Date Affected of Revision 2 10/4/94 ALL GENERAL REVISION 3 12/14/95 4 CHANGED PROCEDURE FROM 2-AOI-85-1 TO 2-AOI-85-2 4 12/16/96 ALL PROCEDURE CHANGE, ADDED NON-CRIT STEP ON TOUCH STAAR, CHANGED ASOS TO US.

5 11/10/99 ALL PROCEDURE REVISION, FORMAT DOCUMENT, CHANGED MGT. EXPECT. TO PLANT WORK EXPECT., ADDED NON-CRIT. STEP 3-WAY COMM.

6 10/11/00 ALL GENERAL REVISION 7 9/1/02 ALL GENERAL REVISION 8 8/21/03 ALL FORMAT; EDITORIAL

JPM NO. Sl REV. NO. S PAGE 3 OF 12 I

BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE I

OPERATOR: ___________________________________

RO SRO DATE:

JPM NUMBER: Sl TASK NUMBER: U-000-AB-02 TASK TITLE: RESPOND TO AN UNCOUPLED CONTROL ROD K/A NUMBER: 201003A2.02 K/A RATING: RO 3.7 SRO: 3.S TASK STANDARD: PERFORM OPERATIONS NECESSARY TO RESPOND TO AN UNCOUPLED CONTROL ROD AS DIRECTED BY 3-AOI-S5-2 LOCATION OF PERFORMANCE: SIMULATOR X PLANT CONTROL ROOM REFERENCES/PROCEDURES NEEDED: 3-AOI-S5-2, REV 6 VALIDATION TIME: CONTROL ROOM: 11:00 LOCAL:

MAX. TIME ALLOWED: (Completed for Time Critical JPMs only)

PERFORMANCE TIME: CONTROL ROOM ----- LOCAL COMMENTS:

Additional comment sheets attached? YES NO RESULTS: SATISFACTORY _______UNSATISFACTORy _______

SIGNATURE: __~~~~~________________DATE:

EXAMINER

BROWNS FERRY NUCLEAR PLANT I JOB PERFORMANCE MEASURE I

IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. 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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator. Unit 3 is in the startup mode withdrawing control rods in RWM Group 1. Control rod 02-23 was withdrawn from 00 to position 48 and has just been checked for coupling integrity. CONTROL ROD OVERTRAVEL annunciator (3-XA-SS-SA, Window 14) is in alarm and control rod 02-23 has been verified to be uncoupled.

INITIATING CUES: The UNIT SUPERVISOR has directed you to respond to the uncoupled control rod as directed by 3-AOI-8S-2.

JPM NO. 81 REV. NO. 8 PAGE 5 OF 12 START TIME __________

NOTE; SELECT A STARTUP IC WITHDRAWING RODS TO POSITION 48 AND INSERT THE UNCOUPLED MALFUNCTION FOR ROD 02-23 AND WITHDRAW IT TO POSITION 48 TO GENERATE THE DRIFT AND OVERTRAVEL ANNUNCIATORS.

Performance Step: Critical Not Critical X WHEN REQUESTED BY EXAMINER identify/obtain copy of required procedure.

Standard:

IDENTIFIED OR OBTAINED copy of 3-AOI-85-2.

SAT- - - UNSAT- - - N/A _ __ COMMENTS:

JPM NO. 81 REV. NO. 8 PAGE 6 OF 12 4.0 OPERATOR ACTIONS 4.1 Immediate Actions Performance Step: Critical X Not Critical 4.1.1 STOP all control rod withdrawal.

Standard:

DID NOT ATTEMPT further rod withdrawal.

SAT- - - UNSAT_ __ N/A COMMENTS: _ _ _ _ _ _ _ _ _ _ _ _ ___

4.2 Subsequent Actions Performance Step: Critical Not Critical X 4.2.1 NOTIFY Reactor Engineer to evaluate the uncoupled control rod for its impact on core thermal limits and rod worth.

Standard:

NOTIFIED Reactor Engineer to evaluate the rod for its impact on core thermal limits and rod worth.

SAT- - - UNSAT- - - N/A COMMENTS:

CUE: [WHEN REACTOR ENGINEER ASKED] NO THERMAL LIMIT OR ROD WORTH PROBLEMS AS LONG AS NO OTHER RODS BEYOND THIS ROD IN THE SEQUENCE ARE WITHDRAWN PAST POSITION 00.

JPM NO. 81 REV. NO. 8 PAGE 7 OF 12 4.2.2 ADJUST the rod pattern as directed by the Reactor Engineer throughout the performance of this procedure.

4.2.3 IF the control rod drive is at position 48 and with Reactor Engineer concurrence, THEN PERFORM the following:

CUE: THE REACTOR ENGINEER AGREES THAT STEp 4.2.3 SHOULD BE PERFORMED TO RECOUPLE THE CONTROL ROD.

Performance Step Critical X Not Critical

Standard:

4.2.3.1 NOTCH INSERT the control rod drive to position 46 to attempt to couple the control rod.

NOTCHED control rod drive in to notch 46.

SAT UNSAT_ _N/A_ _ COMMENTS: _ _ _ _ _ _ _ _ _ _ _ _ __

Performance Step : Critical Not Critical X 4.2.3.2 RESET associated annunciators.

Standard:

RESET CONTROL ROD OVERTRAVEL and CONTROL ROD DRIFT annunciators.

SAT- - - UNSAT- - - N/A COMMENTS:

JPM NO. 81 REV. NO. 8 PAGE 8 OF 12 Performance Step : Critical X Not Critical 4.2.3.3 NOTCH WITHDRAW the control rod drive to position 48.

Standard:

NOTCH WITHDREW the affected control rod to position 48.

SAT- - - UNSAT- - - - N/A COMMENTS:

Performance Step : Critical X Not Critical 4.2.3.4 PERFORM a coupling check.

Standard:

PERFORMED coupling integrity check by giving another notch withdrawal signal. VERIFIED control rod still uncoupled by observing CONTROL ROD OVERTRAVEL and CONTROL ROD DRIFT alarms and loss of control rod position indication.

SAT- - - UNSAT- - - - N/A COMMENTS:

JPM NO. 81 REV. NO. 8 PAGE 9 OF 12 Performance Step Critical X Not Critical 4.2.3.5 IF coupling integrity check fails, THEN CONTINUOUSLY INSERT control rod to position 00 to attempt to latch control rod with control rod drive mechanism.

Standard:

CONTINUOUSLY INSERTED the affected control rod to 00.

SAT- - - UNSAT----- N/A COMMENTS: _____________________

Performance Step Critical X Not Critical 4.2.3.5.1 RESET associated annunciators.

Standard:

RESET CONTROL ROD OVERTRAVEL and CONTROL ROD DRIFT annunciators on Panel 3-9-5.

SAT- - - - UNSAT- - - - N/A COMMENTS:

NOTE: HAVE CONSOLE OPERATOR DELETE ROD UNCOUPLED MALFUNCTION.

JPM NO. 81 REV. NO. 8 PAGE 10 OF 12 CUE: REACTOR ENGINEERING HAS EVALUATED THERMAL LIMITS AND ROD WORTH AND RECOMMENDS THAT CONTROL ROD 02-23 BE CONTINUOUSLY WITHDRAWN FROM 00 TO 48. WE UNDERSTAND NOTCH WITHDRAWAL IS REQUIRED PER 3-AOI-85-2. FOR EXPEDIENCY WE WOULD LIKE TO USE "RONOR" TO WITHDRAW THE ROD. UNIT SUPERVISOR DIRECTS YOU TO RONOR CONTROL ROD 02-23 TO POSITION 48.

Performance Step Critical X Not Critical 4.2.3.5.2 NOTCH WITHDRAW the control rod drive to position 48.

Standard:

NOTCH WITHDREW the affected control rod to position 48.

SAT- - - UNSAT- - - N/A - - - COMMENTS:

Performance Step Critical X Not Critical 4.2.3.5.3 PERFORM a coupling check.

Standard:

APPLIED notch withdraw signal to the affected control rod.

DETERMINED control rod now coupled by presence of control rod position indication and/or lack of associated annunciators.

SAT- - - UNSAT- - - N/A - - - COMMENTS:

NOTE: COUPLING INTEGRITY IS SATISFIED IF CRD NOTCH OVERRIDE SWITCH IS USED AND ROD IS WITHDRAWN TO POSITION 48.

END OF TASK

STOP TIME____________

JPM NO. 81 REV. NO. 8 PAGE 11 OF 12 GENERIC WORK PRACTICES Performance Step: Critical Not Critical X PERFORMER demonstrated the use of SELF CHECKING during this JPM.

Standard:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT- - - UNSAT- - - - N/A

- - - -COMMENTS: - - - - - - - - - - - - - - - -

Performance Step: Critical Not Critical X PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM.

Standard:

PERFORMER utilized 3-WAY COMMUNICATION in accordance with plant standards.

SAT- - - UNSAT- - - - N/A COMMENTS:

I BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASORE I

IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. 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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator. Unit 3 is in the startup mode withdrawing control rods in RWM Group 1. Control rod 02-23 was withdrawn from 00 to position 48 and has just been checked for coupling integrity. CONTROL ROD OVERTRAVEL annunciator (3-XA-SS-SA, Window 14) is in alarm and control rod 02-23 has been verified to be uncoupled.

INITIATING CUES: The UNIT SUPERVISOR has directed you to respond to the uncoupled control rod as directed by 3-AOI-8S-2.

I BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE I

IN-SIMULATOR: I will explain the initial conditions and state the task to be performed. 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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator. Unit 3 is in the startup mode withdrawing control rods in RWM Group 1. Control rod 02-23 was withdrawn from 00 to position 48 and has just been checked for coupling integrity. CONTROL ROD OVERTRAVEL annunciator (3-XA 5A, Window 14) is in alarm and control rod 02-23 has been verified to be uncoupled.

INITIATING CUES: The UNIT SUPERVISOR has directed you to respond to the uncoupled control rod as directed by 3-AOI-85-2.

Browns Ferry Nuclear Plant

Unit 3 Abnormal Operating Instruction 3-AOI-85-2 Uncoupled Control Rod Revision 0006 Quality Related Level of Use: Continuous Use Effective Date: 05-24-2005 Responsible Organization: OPS, Operations Prepared By: Donald R. Heard Approved By: Jeffrey A. Kimberlin

BFN Uncoupled Control Rod 3-AOI-85-2 Unit 3 Rev.OOOS Page 2 of7 Current Revision Description Pages Affected: All Type of Change: ENHANCEMENT Tracking Number: 007 This procedure was converted from Word 95 to Word 2002 (XP) using Rev 5.

Changed the Level of Use from Reference Use to Continuous Use (PCR 05001200)

BFN Uncoupled Control Rod 3-AOI-85-2 Unit3 Rev.OOOS Page 3 of7 1.0 PURPOSE This abnormal operating instruction provides symptoms, automatic actions and operator actions for an uncoupled control rod.

2.0 SYMPTOMS NOTE If a control rod is uncoupled and being withdrawn to any position other than position 48, the Rod Position Information System will display normal control rod movement. Power must be monitored to determine if the control rod is following its associated drive.

Nuclear instrumentation does NOT respond to control rod movement.

CONTROL ROD OVERTRAVEL annunciator (3-XA-SS-SA, Window 14) in alarm.

Digital display and red backlighting for the uncoupled control rod on the full core display is extinguished.

3.0 AUTOMATIC ACTIONS None

BFN Uncoupled Control Rod 3-AOI-85-2 Unit3 Rev.OOOS Page 4 of7 4.0 OPERATOR ACTIONS 4.1 Immediate Actions

[1 ] STOP all control rod withdrawal. o 4.2 Subsequent Actions

[1] NOTIFY Reactor Engineer to evaluate the suspect uncoupled control rod for its impact on core thermal limits and rod worth. 0

[2] ADJUST the rod pattern as directed by the Reactor Engineer throughout the performance of this procedure. 0

[3] IF the control rod drive is at position 48 AND with Reactor Engineer concurrence, THEN PERFORM the following:

[3.1] NOTCH INSERT the control rod drive to position 46 to attempt to couple the control rod. o

[3.2]

[3.3]

[3.4]

RESET associated annunciators.

NOTCH WITHDRAW the control rod drive to position 48.

PERFORM a coupling check.

o o

o

[3.5] IF coupling integrity check fails, THEN CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism.

[3.5.1 ] RESET associated annunciators. o

[3.5.2] NOTCH WITHDRAW control rod to position 48. o

[3.5.3] PERFORM a coupling check. o

BFN Uncoupled Control Rod 3-AOI-85-2 Unit3 Rev. 0006 Page 5 of7 4.2 Subsequent Actions (continued)

[4] IF the control rod drive is at any position other than notch 48 AND with Reactor Engineer concurrence, after thorough evaluation of the reactor core conditions, THEN PERFORM one of the following sub-steps as directed by the Reactor Engineer:

[4.1] ATTEMPT to latch control rod by fully inserting control rod as follows:

[4.1.1] CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism. o

[4.1.2] NOTCH WITHDRAW control rod to position 48. o

[4.1.3] PERFORM a coupling check. o

[4.1.4] IF coupling integrity check fails, THEN

CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism.

A. RESET associated annunciators. o B. NOTCH WITHDRAW control rod to position 48. o

c. PERFORM a coupling check. o

BFN Uncoupled Control Rod 3-AOI-85-2 Unit3 Rev.OOOS Page S of7 4.2 Subsequent Actions (continued)

[4.2] ATTEMPT to latch control rod by inserting control rod one notch as follows:

[4.2.1 ] NOTCH INSERT the control rod drive one notch to attempt to couple the control rod. o

[4.2.2] NOTCH WITHDRAW the control rod drive to position 48. o

[4.2.3] PERFORM a coupling check. o

[4.2.4] IF coupling integrity check fails, THEN CONTINUOUSLY INSERT control rod drive to position 00 to attempt to latch control rod with control rod drive mechanism.

A. RESET associated annunciators. o B. NOTCH WITHDRAW control rod to

C.

position 48.

PERFORM a coupling check.

o o

CAUTION Technical Specification 3.1.3 applies to a control rod which CANNOT be coupled to its drive.

[5] IF coupling integrity check fails after above actions have been carried out, THEN

[5.1] CONTINUOUSLY INSERT control rod drive to position 00 AND REMOVE the associated hydraulic control unit from service until corrective action is performed. REFER TO 3-01-85. o

[5.2] RESET associated annunciators. o

BFN Uncoupled Control Rod 3-AOI-85-2 Unit 3 Rev. 0006 Page 7 of7

5.0 REFERENCES

5.1 Technical Specifications Section 3.1, Reactivity Control Systems Section 5.4, Procedures Section 5.5, Programs and Manuals 5.2 Final Safety Analysis Report Section 3.4, Reactivity Control Mechanical Design Section 13.6, Normal Operations 5.3 Plant Instructions 3-ARP-9-5, Panel 9-5 Annunciator Response Procedure 3-01-85, Control Rod Drive System

5.4 Plant Drawings 45N620-6, Wiring Diagram Annunciator 3-47E61 0-85-1 , Mechanical Control Diagram CRD Hydraulic System 104B2506 Sheet 2, Connection Diagram Position Indicator Probe 730E321 Sheet 10, Elementary Diagram Reactor Manual Control System 5.5 Vendor Manuals GEK-32539B in GEK-779-A, Volume 3, Part 2, Book 3, General Electric, Rod Position Information System, Contract 90744 BFN-CVM-2105 6.0 ILLUSTRATIONS/ATTACHMENTS None

JPM NO. 55 REV. NO. 10 PAGE 1 of 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE JPM NUMBER: 55 TITLE: 2-EOI APPENDIX EMERGENCY VENTING PRIMARY CONTAINMENT TASK NUMBER: U-000-EM-63 SUBMITTED BY: DATE: _ _ __

VALIDATED BY: DATE: _ _ __

APPROVED BY: DATE: _ _ __

TRAINING PLANTCONCURRENCE: _________________ DATE: _ _ _ __

OPERATIONS

Examination JPMs Require Operations Training Manager Approval or Designee Approval and Plant Concurrence

JPM NO. 55 REV. NO. 10 PAGE 2 of 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE REVISION LOG Revision Effective Pages Description Number Date Affected Of Revision 5 11/15/99 All Procedure revision, added 3-way comm.

6 09/08/02 3,4 Delete SS#, delete safety statement 7 01/05/06 All General revision 8 07/29/07 All Update 9 06/20108 All General revision 10 03/27/09 All General revision & re-format

JPM NO. 55 REV. NO. 10 PAGE 3 of 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE OPERATOR: _____________________________________________

RO SRO DATE: _ _ _ _ ___

JPM NUMBER: 55 TASK NUMBER: U-000-EM-63 TASK TITLE: 2-EOI APPENDIX EMERGENCY VENTING PRIMARY CONTAINMENT KIA NUMBER: 295024EA 1.14 KIA RATING: RO 3.4 SRO 3.5 TASK STANDARD: PERFORM CONTROL ROOM OPERATIONS REQUIRED TO EMERGENCY VENTILATE PRIMARY CONTAINMENT PERFORMANCE LOCATION: SIMULATOR X PLANT _ CONTROL ROOM_

REFERENCES/PROCEDURES NEEDED: 2-EOI Appendix-13, Rev 6 VALIDATION TIME: SIMULATOR: 5:00 LOCAL: _ _ __

MAX. TIME ALLOWED: _ _ _ _ _ (FOR TIME CRITICAL JPMs ONLY)

PERFORMANCE TIME:

COMMENTS:

ADDITIONAL COMMENT SHEETS AITACHED? YES _ _ NO RESULTS: SATISFACTORY UNSATISFACTORY EXAMINER SIGNATURE: _ _ _ _ _ _ _ _ _ _ DATE: _ _ _ _ ___

JPM NO. 55 REV. NO. 10 PAGE 4 of 12 BROWNS FERRY NUCLEAR PLANT JOB PERFORMANCE MEASURE IN-SIMULATOR: I will explain the initial conditions and state the task to be performed.

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. When your task is given, you will repeat the task and I will acknowledge "That's Correct". (OR "That's Incorrect", if applicable). When you have completed your assigned task, you will say, "my task is complete" and I will acknowledge that your task is complete.

INITIAL CONDITIONS: You are an Operator. A large leak inside primary containment has developed on Unit 2. The reactor scrammed and several control rods are still not fully inserted to 00 and primary containment pressure is approaching 55 psig and rising. The US is performing EOI-2 at PC/P-15.

INITIATING CUES: The Unit Supervisor directs you to emergency vent primary containment as directed by 2-EOI Appendix-13.

JPM NO. 55 REV. NO. 10 PAGE 5 of 12 START TIME _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x When requested by examiner identify/obtain copy of required procedure.

STANDARD:

Obtained copy of 2-EOI Appendix-13.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

1. NOTIFY Shift Manager / SED of the following:

Emergency Venting of Primary Containment is in progress.

Off-Gas Release Rate Limits will be exceeded.

CUE: [Shift Manager/SED acknowledges] Emergency Primary Containment venting is in progress and Off.-Gas release rate limits will be exceeded.

STANDARD:

Notified Shift Manager/SED by voice contact with examiner.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55 REV. NO. 10 PAGE 6 of 12 PERFORMANCE STEP:

2.

CRITICAL VENT the Suppression Chamber as follows (Panel 9-3):

NOT CRITICAL x

a. IF ................ EITHER of the following exists:

Suppression Pool water level CANNOT be determined to be below 20 ft, OR

Suppression Chamber CANNOT be vented, THEN .......... CONTINUE in this procedure at Step 3.

STANDARD:

Verified Suppression Pool Level below 20 ft using 2-Ll-64-159A, SUPPR POOL WATER LEVEL and/or ICS.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

b. PLACE keylock switch 2-HS-64-222B, HARDENED SUPPR CHBR VENT OUTBD PERMISSIVE, in PERM.

STANDARD:

Placed 2-HS-64-222B in the PERM position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55 REV. NO. 10 PAGE 7 of 12 PERFORMANCE STEP:

c.

CRITICAL NOT CRITICAL CHECK blue indicating light above 2-HS-64-222B, HARDENED SUPPR x

CHBR VENT OUTBD PERMISSIVE, illuminated.

STANDARD:

Verified BLUE indicating lamp above 2-HS-64-222B Illuminated.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL x NOT CRITICAL

d. OPEN 2-FCV-64-222, HARDENED SUPPR CHBR VENT OUTBD ISOL VLV.

STANDARD:

Placed 2-HS-64-222A in the OPEN position (critical) and Verified illuminated RED valve position indicating lamp above associated hand switch (not critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55 REV. NO. 10 PAGE 8 of 12 PERFORMANCE STEP:

e.

CRITICAL x PLACE keylock switch 2-HS-64-221 B, HARDENED SUPPR CHBR NOT CRITICAL VENT INBD PERMISSIVE, in PERM.

STANDARD:

Placed 2-HS-64-221 B in the PERM position.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

f. CHECK blue indicating light above 2-HS-64-221 B, HARDENED SUPPR CHBR VENT INBD PERMISSIVE, illuminated.

STANDARD:

Verified BLUE indicating lamp above 2-HS-64-221 B Illuminated.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55 REV. NO. 10 PAGE 9 of 12 PERFORMANCE STEP:

g.

CRITICAL x OPEN 2-FCV-64-221, HARDENED SUPPR CHBR VENT INBD ISOL NOT CRITICAL VLV.

STANDARD:

placed 2-HS-64-221A in the OPEN position (critical) and Verified illuminated RED valve position indicating lamp above associated hand switch (not critical).

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

h. CHECK Drywell and Suppression Chamber Pressure lowering.

STANDARD:

Verified drywell and suppression chamber pressure lowering by available containment pressure instrumentation and/or ICS.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

JPM NO. 55 REV. NO. 10 PAGE 10 of 12 PERFORMANCE STEP: CRITICAL NOT CRITICAL x

i. MAINTAIN Primary Containment Pressure below 55 psig using 2-FCV 222, HARDENED SUPR CHSR VENT OUTSD ISOL VLV, as directed by SRO.

STANDARD:

None.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

I CUE: [When Orywell Pressure lowering] That completes this task.

JPM NO. 55 REV. NO. 10 PAGE11of12 PERFORMANCE STEP: CRITICAL PERFORMER demonstrated the use of SELF CHECKING during this JPM NOT CRITICAL x STANDARD:

PERFORMER verified applicable components by utilizing SELF CHECKING in accordance with plant standards.

SAT UNSAT N/A _ _ COMMENTS: _ _ _ _ __

PERFORMANCE STEP: CRITICAL NOT CRITICAL x

PERFORMER demonstrated the use of 3-WAY COMMUNICATION during this JPM STANDARD: