Text

Nov/Dec 2002-301 Exam Final Jpms
	ML030560832
Person / Time
Site:	Vogtle
Issue date:	01/10/2003
From:	Ernstes M; Operator Licensing and Human Performance Branch
To:	Gasser J; Southern Nuclear Operating Co
References
	50-424/02-301, 50-425/02-301, ES-301, ES-301-2 50-424/02-301, 50-425/02-301
	Download: ML030560832 (141)
	v • d • e

Final Submittal (Blue Paper)

1.

Administrative Questions/JPMs

2.

In-plant JPMs

3.

Control Room JPMs (simulator JPMs)

VOGTLE EXAM 2002-301 50-424 AND 50-425 NOVEMBER 26, &

DECEMBER 2 - 13, 2002

ES-301 Control Room Systems Form ES-301-2 (R8, Si) and Facility Walk-Through Test Outline Facility:

Vocltle Date of Examination:

12/02/02 Exam Level (circle one): RO / SRO(I)

Operating Test No.:

,-nrnt B.1 Control Room Systems System / JPM Title Type Code*

Safety Function

a.

D/G 1A Parallel Operating with Failure of LubeOil A, S, N, L 6

K/A: 064A2.01, 064A2.03,

b.

Manually Initiate Containment Spray A, S,M 5

K/A: 026A2.03, 069AA2.02

c.

Start a Reactor Coolant Pump A, S, M, L 4P K/A: 002A1.05

d.

Spurious CIA Response S, N 2

K/A: 004A2.12

e.

Initiate RCS Boration using BTRS D, S 1

K/A:004A4.07

f.

Bypass Containment Hi-1 Following a Loss of Heat Sink CR, L, D 7

K/A: 01 2A4.04

g.

Reduce Containment pressure following a CVI CR, S 8

K/A: 029A1.03 B.2 Facility Walk-Through

a.

Control Pzr Pressure and S/G Level from Shutdown Panel A,N 8

K/A:, 068AA1.03, 068AA1.28

b.

TDAFW Local Manual Control w/o DC power D

4S K/A: 061A2.03, 061A2.04 c

Locally Isolate RCP Seals D, R 4P K/A: 003A4.01

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

ES-301 Control Room Systems Form ES-301-2 (R8, S1) and Facility Walk-Through Test Outline Facility:

Voqtle Date of Examination: 12/02/02 Exam Level (circle one): USRO Operating Test N B.1 Control Room Systems System /JPM Title Type Code*

Safety Function

a.

b.

Manually Initiate Containment Spray A, S, M 5

K/A: 026A2.03, 069AA2.02 C.

d.

Spurious CIA Response S, N 2

K/A: 002A2.12

e.

f.

Bypass Containment Hi-i Following a Loss of Heat Sink CR,L, 0 7

K/A: 012A4.04

9.

B.2 Facility Walk-Through

a.

Control Pzr Pressure and SIG Level from Shutdown Panel A,N 8

K/A:, 068AA1.03, 068AA1.28 c

Locally Isolate RCP Seals D, R 4P

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

613/4 SOUTHERN A

COMPANY Energy to Serve Your World' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-13427 D/G 1 A PARALLEL OPERATING WITH FAILURE OF LUBE OIL Revision 0 November 14, 2002

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions:

Assigned Task:

Following a 11 day D/G 1A outage maintenance and engineering support are standing by for a D/G 1A test run. D/G 1A was started by the last shift and is now operating unloaded with the D/G output breaker open.

The outside area SO is stationed at the D/G to support the run.

The USS has directed you to parallel D/G 1A to the grid and raise load to 7000 kw using SOP-13427-1 Section 4.2.1.

2

NRC-JP-13427 JPM INFORMATION Evaluation Method Evaluation Location Performance Time:

Performed

[ ] Simulator minutes

[ Simulated

[ Control Room OVERALL JPM EVALUATION

[

SATISFACTORY

[

UNSATISFACTORY Examiner Comments:

Examiner's Signature:

3

[ ] Unit 1

[ ] Unit 2

NRC-JP-13427 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 19251-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.17035-1

1.

2.

3.

Reset to IC 14 Start D/G 1A allow it to run unloaded until all annunicators are clear Acknowledge alarms and freeze simulation Setup time: 5 minutes DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions:

Assigned Task:

Following a 11 day D/G 1A outage maintenance and engineering support are standing by for a D/G 1A test run. D/G 1A was started by the last shift and is now operating unloaded with the D/G output breaker open.

The outside area SO is stationed at the D/G to support the run.

The USS has directed you to parallel D/G 1A to the grid and raise load to 7000 kw using SOP-13427-1 Section 4.2.1.

4

NRC-JP-13427 JPM STEPS START TIME:

5 STEP 1 SAT Le UNSAT L&.f Paralleling Diesel Generator To 4160V Bus

-&D

ENSURE the Diesel Generator 1A Sync Mode Selector Switch TS-DG1A is in AUTO

-,D

ENSURE Breaker 1AA02-05 and 1AA02-01 Synchronization Switches are OFF d, 0

PLACE the Breaker 1AA02-19 Synchronization Switch to ON

'aD

VERIFY Diesel Generator is in the Parallel Mode by observing the blue DSL GEN 1A UNIT MODE/FAST START light is not illuminated.

'aD

SET the Diesel Generator Load Pot 1-SE-4915 to 1.00 STEP 2 CRITICAL (,)

SAT O1 UNSAT 0,K Adiust DIG 1A voltage and frequency 0D

SELECT 1AA02 4160V Bus phase voltage of the highest value

'aD1

SELECT the Diesel Generator 1A (1 B) voltage of the lowest value

'aD

VERIFY Sync Scope Meter is rotating, Synchronizing Lights are bright at the 6 o'clock position, Synchronizing lights are dark at the 12 o'clock position, and the Red AUTO SYNC PERMISSIVE LIGHT comes on near the 12 o'clock position aD 0

ADJUST generator voltage to approximately 50V above the highest phase of the bus voltage

'aD

ADJUST the generator speed until the Sync Scope needle is rotating slowly in the clockwise direction (fast)

NRC-JP-13427 JPM STEPS 6

STEP 3 CRITICAL (,)

SAT 0, UNSAT De Closing DIG 1 A output breaker

,O

When the Sync Scope needle reaches the 11 o'clock position DEPRESS and HOLD the Diesel Generator 1A AUTO SYNC PERMISSIVE PUSHBUTTON PB-DG1A

,,s

VERIFY that the DG1A (DG1 B) OUTPUT BRKR 1AA02-19 CLOSES

.D

VERIFY that generator loads to approximately 700 kW

.D

ADJUST generator voltage to obtain kVAR loading between 200 and 300 kVAR positive (Out).

AD

PLACE Breaker 1 AA02-19 (1 BA03-19) Synchronization Switch to OFF

NRC-JP-13427 JPM STEPS STEP 4 CRITICAL (*)

SAT DO UNSAT De Respond to decreasing DIG 1A lube oil pressure

-e

Acknowledge DG-1A lube oil alarms and reference procedure 17035-1

-z. 0 Note that DG-1A should have tripped when ALB035 B02 Alarmed

'aD

Trip D/G 1A using either the normal or emergency trip pushbuttons

'aD

Verify DG-1A output breaker (1AA02-19) opens and engine stops Simulator operator:

Override ALB035B06 (High lube oil filter D/P) to on Panel Drawings-EAB3-ALB35-606-ON Override ALB035 B01 (Lo pressure), and then B02 (Lo Pressure Trip) to on after student references appropriate ARP Panel Drawings-EAB3-ALB35-B01 -ON Panel Drawings-EAB3-ALB35-BO1 -ON STOP TIME:

7

SOUTHERNA COMPANY Energy to Serve Your World PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-13003 START A REACTOR COOLANT PUMP Revision 0 November 14,2002

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions:

Assigned Task:

A plant startup is in progress with the unit in Mode 4. Per UOP 12001, RCPs 1 and 4 have been started. The standby alignment has been verified for RCP 3 and an operator has performed a visual inspection.

SGBD has been in service for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and the temperature is stable.

Adequate SD Margin has been verified.

The USS has directed you to "Start RCP 3 using 13003", and verify proper operation.

2

NRC-JP-13003 JPM INFORMATION 3

OPERATOR'S NAME:

EVALUATION DATE:

/

JPM TITLE:

Start a Reactor Coolant Pump REVISION:

0 COMPLETION TIME:

20 minutes APPLICATION:

RO/SRO TASK NUMBER:

B.1.c K/A:

002A1.05 Evaluation Method

[

Performed

[

Simulated Evaluation Location

[

Simulator

[

Control Room

[

Unit 1

[

Unit 2 Performance Time:

minutes OVERALL JPM EVALUATION E ] SATISFACTORY

[

UNSATISFACTORY Examiner Comments:

Examiner's Signature:

NRC-JP-13003 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 13003-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©.are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

13003, Reactor Coolant Pump Operation

1.

2.

3.

4.

5.

6.

7.

8.

Reset to IC3 (BOL Mode 4)

Verify open both breakers for RCP 3. (Do not start lift pump)

Verify SGBD for all 4 SGs Establish stable plant conditions Set ALB08EO4 & F04 on a trigger to turn on Activate trigger 10 seconds after RCP is started Ack/Reset alarms Freeze simulator Setup time: 4 minutes DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

A plant startup is in progress with the unit in Mode 4. Per UOP 12001, RCPs 1 and 4 have been started. The standby alignment has been verified for RCP 3 and an operator has performed a visual inspection. SGBD has been in service for 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months and the temperature is stable. Adequate SD Margin has been verified.

The USS has directed you to "Start RCP 3 using 13003", and verify proper operation.

4 i

NRC-JP-13003 JPM STEPS START TIME:

5 STEP 1 SAT 02 UNSAT 0,K Verify proper AT for pump start mD

Verify secondary water temperature

10OF above RCS loop Tcold

'aD

Record value in Unit Control Log CUE The USS will record the AT value in the USS Control Log.

STEP 2 CRITICAL (,)

SAT De UNSAT De Start the oil lift pump

'aD

RCP 3 oil lift pump running

'aD

Oil permissive light lit

NRC-JP-13003 JPM STEPS STEP 3 SAT 0,K UNSAT 02 Establish RCP startina conditions

,,a i

Verify visual inspection CUE When requested: "Local inspection and hand rotation is complete."

.-D

Seal injection flow 8 to 13 gpm

Seal leakoff flow determined to be w/in normal operating range

.r

Seal AP > 200 psid

.r&D

VCT pressure > 18 psig

1-1 o The following annunciators windows dark:

RCP Standpipe Hi & Lo level alarms (ALB08)

RCP Upper & Lower Oil Rsvr Hi/Lo level alarms (ALB1 1)

ACCW Clr Lo Flow,Clr Oulet Hi Temp,& Therm Barrier Hi Flow alarms (ALB04)

,&D

RCS pressure and temperature within acceptable region of 12001, Fig 1 6

STEP 4 SAT 02*

UNSAT

-I Verify vibration alarms clear 0-

The following annunciators dark:

RCP Frame and Shaft Vibration Alert (ALB-08)

RCP Frame and Shaft Hi Vibration (ALB-08)

NRC-JP-13003 JPM STEPS STEP 5 CRITICAL (,)

SAT De UNSAT D0e Start the RCP 0D

SGBD temperatures < 10OF above RCS temperature

Oil lift pump running > 2 minutes

-. D

Ensure CNMT personnel clear of RCP before starting aD

HS-0497A placed in START aD

HS-0497B placed in START "7

STEP 6 SAT Dz UNSAT 0,K Stop RCP oil lift pumi a3D

RCP 3 running > 1 minute a.D

RCP 3 oil lift pump stopped

NRC-JP-13003 JPM STEPS STOP TIME:

Field Notes 8

STEP 7 CRITICAL (*)

SAT Oe UNSAT Oz Verify improper RCP operation and stop RCP A.D

Adjust charging as necessary to control Pressurizer level.

A6D

,* The following paramters observed:

RCS pressure normal RCS loop flow normal RCP vibration alarms (ALB08E04 & ALB08FO4) illuminated Dispatch Control Building SO to RCP vibration monitor RCP seal injection flows 8 to 13 gpm RCP seal leakoff flows determined to be w/in normal operating range RCP seal AP > 200 psid A.D

Stop RCP 3 by placing either HS-0497A or HS-0497B placed in STOP When requested the Control Building SO reports "RCP #3 shaft vibration at 22 mils and increasing" Simulator Operator: Bring in the Alert alarm for RCP #3 allow time for the operator to locally respond then bring in the HIGH alarm.

STEP 8 SAT OA!

UNSAT Oe*

Report to USS

-z&

- RCP #3 was started and had to be stopped due to high vibration

4 SOUTHERNSAn COMPANY Energy to Serve Your World' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-J P-17006-001 Spurious CIA Response Revision 0 10/24/02 b 10 I.

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

REMEMBER: All steps required for this task are to be simulated.

Plant equipment is not to be operated.

Initial Conditions:

Assigned Task:

A SPURIOUS CIA ACTUATION OCURRED WHILE I&C PERSONNEL WERE TAKING VOLTAGE MEASUREMENTS IN THE SSPS CABINENTS WITH THE UNIT AT 100% POWER. ALL MEASURING EQUIPMENT HAS BEEN DISCONNECTED AND SSPS CABINET DOORS CLOSED.

Complete all actions using ARP 17006-1 "E06" as guidance to return systems to normal operation following a spurious CIA.

2

NRC-JP-17006 JPM INFORMATION 3

Evaluation Method

[

Performed

[] Simulated Evaluation Location

[

Simulator

[] Control Room

[

Unit 1

[I Unit 2 Performance Time:

minutes OVERALL JPM EVALUATION

[ ] SATISFACTORY

[ ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

NRC-JP-17006 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 17006-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©.."are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.17006-1

1.

2.

3.

Reset to IC14 (MOL 100%)

Initiate a manual CIA Set charging flow to 85 gpm in manual with = 9 gpm seal injection flow

4. Ensure LV-459,460 closed, HV-8149A,B,C, closed and HV-8152,8160, and 15214 closed

5. Ack/Reset alarms

6. Freeze simulator Setup time: 7 minutes DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard.

Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

REMEMBER: All steps required for this task are to be simulated.

Plant equipment is not to be operated.

INITIAL CONDITIONS:

Assigned Task:

A SPURIOUS CIA ACTUATION OCCURRED WHILE I&C PERSONNEL WERE TAKING VOLTAGE MEASUREMENTS IN THE SSPS CABINENTS WITH THE UNIT AT 100% POWER.

ALL MEASURING EQUIPMENT HAS BEEN DISCONNECTED AND SSPS CABINET DOORS CLOSED.

Complete all actions using ARP 17006-1 "E06" as guidance to return systems to normal operation following a spurious CIA.

4

NRC-JP-17006 JPM STEPS START TIME:

5 STEP 1 CRITICAL (,)

SAT OD UNSAT f1lg Restore Instrument Air to Containment eO

RESET Phase A by placing both 1-HS-40120 and 1-HS-40122 to RESET position

OPEN Instrument Air to containment 1-HV-9378 using both 1-HS-9378A & 1-HS-9378B STEP 2 CRITICAL (,)

SAT OA*

UNSAT EJA*

Establish normal system alignment

-&D e Section 4.4.2 of 13006 selected aD

Verify orifice isolations HV-8149A, B, & C CLOSED a, 0

Verify letdown isolations LV-459 and LV-460 CLOSED

-d, 0 Verify Pressurizer Aux Spray Valve HV-8145 CLOSED 1-1O

CVCS HELB isolation HV-15214 OPEN zO

Letdown isolations HV-8160 and HV-8152 OPEN

,D

, Place pressure controller PIC-1 31 in MAN at 50% to 75% demand aD

Place temperature controller TIC-0130 in MAN at 50% demand

-nDO o Verify PRZR level > 17%

NRC-JP-17006 JPM STEPS STEP 3 CRITICAL()

SAT DO UNSAT De Establish normal system aliqnment

,d,D

1-HV-8147 ALTERNATE CHARGING TO LOOP 4 CUE Unit 1 is operating on Cycle 11 aD

OPEN 1-HV-8106 and 1-HV-8105 CHARGING TO RCS ISOLATION

-aD

+Adjust charging flow to 80-90 gpm (Maintain RCP seal injection 8-13 gpm) 6 STEP 3 CRITICAL (,)

SAT 0-6.

UNSAT D02 Establish letdown flow Note: Letdown pressure may be allowed to fluctuate temporarily while establishing letdown flow, but must be stabilized within the required band. Charging flow will have to be adjusted to

Ž desired letdown flow in order to stabilize letdown parameters.

iD

Letdown isolations LV-459 and LV-460 OPEN, aD

Orifice isolation HV-8149B or HV-81 49C OPEN CUE Unit 1 is operating on Cycle 11 aD

PIC-131 adjusted to attain 360 to 380 psig onPI-131A

,Dk 0

Record the letdown orifice that was placed in service in the Unit Control Log CUE The USS will ensure the RO makes a log entry about the letdown orifice placed in service."

NRC-JP-17006 JPM STEPS 7

STEP 3 SAT D]5 UNSAT O7 Place letdown controllers in automatic

.l

PIC-131 in AUTO

Letdown pressure 360 to 380 psig on PI-131A E-

TIC-130 in AUTO 0F

Letdown temperature < 115 OF on TI-130 STEP 4 SAT D7K UNSAT Dec Verify Proper system operation

Regen heat exchanger outlet (letdown) on TI-1 27 verified < 380 OF 0aD a Maintain PRZR level within 1% of program CUE "The RO will monitor and control PRZR level."

NRC-JP-17006 JPM STEPS STOP TIME:

8 STEP 6 SAT 0,K UNSAT De Report to USS

,s.D Systems Restored to normal operations following CIA

SOUTHERN A COMPANY Energy to Serve Your World" PLANT VOGTLE CONTROL ROOM OPERATOR

/

JOB PERFORMANCE MEASURE NRC-JP-13010 INITIATE RCS BORATION USING BTRS Revision 0 November 14, 2002

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions:

The crew is preparing to reduce power to 75% to remove MFP B from service.

BTRS demineralizers 4, 5, 6, and 7 have been equilibrated with the current RCS boron concentration. In addition, the extra RO has placed the BTRS system in standby alignment.

Assigned Task:

The USS has directed you to "Initiate boration of RCS using BTRS demineralizers 4, 5, 6, and 7", per Section 4.2.4 of 13010-1.

2

NRC-JP-13010 JPM INFORMATION 1

3 OPERATOR'S NAME:

EVALUATION DATE:

I

/

JPM TITLE:

Initiate RCS Boration Using BTRS REVISION:

0 November 14, 2002 COMPLETION TIME: 20 minutes APPLICATION:

RO/SRO TASK NUMBER:

B.1.e K/A NUMBER:

004A4.07

NRC-JP-13010 INSTRUCTIONS TO EXAMINER DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard.

Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

Assigned Task:

The crew is preparing to reduce power to 75% to remove MFP B from service.

BTRS demineralizers 4, 5, 6, and 7 have been equilibrated with the current RCS boron concentration. In addition, the extra RO has placed the BTRS system in standby alignment.

The USS has directed you to "Initiate boration of RCS using BTRS demineralizers 4, 5, 6, and 7", per Section 4.2.4 of 13010-1.

4 This JPM is based on the latest rev of 13010-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during performance of this JPM.

REQUIRED ITEMS:

1.

13010, Boron Thermal Regeneration System SIMULATOR SETUP:

1.

Reset to IC14

2.

Perform 13010-1 section 4.1.2

3.

Place BTRS Chiller in service per 13010-1 section 4.1.3, RF: CV24

4.

Ack/Reset alarms

5.

Freeze simulator Setup time: 10 minutes

NRC-JP-13010 JPM STEPS START TIME:

STEP 2 CRITICAL (,)

SAT De UNSAT De Allan BTRS Svstem for Boration pen pen pen pen AD AD aD AD CUE AD ND AD Notes:

BTRS Demin Isolation valve, HS-7010E o BTRS Demin Isolation valve, HS-7010D o BTRS Demin Isolation valve, HS-7010C 0 BTRS Demin Isolation valve, HS-7010B o IV requested "The extra RO will perform the IV."

HIC-387 to 0% Borate position Ensure HV-8115 remains open Place TIC-381A in manual at 0% demand 5

STEP 1 SAT De UNSAT De Establish prestart alignment

-&D e Verify standby alignment lAW section 4.1.2 CUE "The extra RO has performed section 4.1.2."

-, 0

Place the BTRS Chiller in service lAW section 4.1.3 CUE "The ABO has placed the BTRS Chiller in service."

,.D o BTRS Demin outlet isolation valves open CUE If requested, "The USS desires that demins 4, 5, 6, and 7 be used to borate the RCS."

CUE "The ABO has opened 1-1208-U4-263, 262, 261, and 260.

CUE The SSS will ensure the IV is performed.

CUE The USS will ensure the DEMIN CONTROL LOG is updated."

Notes:

NRC-JP-13010 JPM STEPS 6

NRC-JP-13010 JPM STEPS STEP 3 CRITICAL (,)

SAT De UNSAT De Initiate boration

-O

Place HS-10351 in the BORATE position

1-1

Verify white BORATE light lit (this will occur after auto system alignment is complete)

-z&]*

Ensure HV-7054 is OPEN

-d

Close HV-8115 by placing HS-8115 in AUTO

,z-&

Adjust TIC-381 to = 1400 and place controller in AUTO (adjust pot if required)

Note: this step is considered SAT if temperature is below 1400 before continuing on to the next step

,d, 0 Verify BTRS demin inlet @ 1400 on TI-381 and return header @ 1150 on TI-386 esO

HIC-387 output lowered to initiate boration

,z.D 0

Boronometer indication of BTRS outlet concentration rising Notes:

STEP 4 SAT De UNSAT DO Report to USS aD

RCS boration initiated using BTRS Notes:

STOP TIME:

.7

G I -ý-

i SOUTHERNA COMPANY Energy to Serve Your World" PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-13509 BYPASS CONTAINMENT HI-i FOLLOWING A Loss OF HEAT SINK Revision 0 November 14, 2002

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

REMEMBER: All steps required for this task are to be simulated.

Plant equipment is not to be operated.

Initial Conditions:

Assigned Task:

While responding to a Loss of Heat Sink on Unit __, Containment pressure reached the Hi-i setpoint. The crew is preparing to establish feedwater flow in accordance with step 6 of 19231-C.

The USS has directed you to "Bypass Containment Hi-1 pressure channels __ - PB936B and - - PB935B by initiating 13509-C."

2

NRC-JP-13509 JPM INFORMATION OPERATOR'S NAME:

EVALUATION DATE:

/

JPM TITLE:

REVISION:

COMPLETION TIME:

APPLICATION:

TASK NUMBER:

K/A NUMBER:

Evaluation Method Evaluation Location Performance Time:

Bypass Containment Hi-1 Following a Loss of Heat Sink 0

November 14, 2002 10 minutes RO/SRO B.1.f 01 2A4.04 Performed Simulator minutes Simulated

[ Control Room

[ ] Unit 1 OVERALL JPM EVALUATION

[

SATISFACTORY

[ ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

3

[ ] Unit 2 i

NRC-JP-13509 INSTRUCTIONS TO EXAMINER This JPM is based on 13509-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

2.

13509-C, BTI Panel Operation Two (2) BTI panel keys COMPONENT LOCATION:

Main Control Room Note to Examiner: Permission from the USS must be obtained to open the Protection Cabinet doors. A BTI key may be obtained from the USS.

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

REMEMBER: All steps required for this task are to be simulated.

Plant equipment is not to be operated.

INITIAL CONDITIONS:

ASSIGNED TASK:

While responding to a Loss of Heat Sink on Unit __, Containment pressure reached the Hi-1 setpoint. The crew is preparing to establish feedwater flow in accordance with step 6 of 19231-C.

The USS has directed you to "Bypass Containment Hi-1 pressure channels __ - PB936B and __ - PB935B by initiating 13509-C."

4 i

NRC-JP-13509 JPM STEPS START TIME:

5 STEP 1 SAT O:

UNSAT 0,K Verify initial conditions Note: Permission from the appropriate USS will be required to open the Protection Cabinet doors to access the BTI panels.

,aD

Checklist 2 & 3 bistables circled (13509-C) aD[

Obtain BTI Enable keys CUE The USS has provided the proper BTI keys STEP 2 CRITICAL (,)

SAT De UNSAT De Bypass NSSS Channel II Hi-1 bistable, 936B

-EJ

Verify circuit breaker is ON

-d,

Verify red power available LED illuminated CUE The red power LED is illuminated

,0

. Keylock switch positioned to BYPASS ENABLE & Verify LED illuminates CUE The LED is illuminated a D Verify ALB05 B02 illuminated CUE ALB05 B02 is illuminated

'0

PB936B BTI switch #34 positioned to BYPASS

'.r-I e Verify 936B LED illuminated CUE 936B LED is illuminated AD

Verify TSLB extinguished CUE The TSLB for 936B is extinguished

NRC-JP-13509 JPM STEPS STEP 4 SAT DQ.

UNSAT 0i-@!

Report to USS DO o Containment Hi-1 Channels 936 and 935 are bypassed STOP TIME:

Field Notes 6

STEP 3 CRITICAL (,)

SAT DO.e UNSAT De Bypass NSSS Channel III Hi-1 bistable. 935B

Verify circuit breaker is ON a.D

Verify red power available LED illuminated CUE The red power LED is illuminated mD

Keylock switch positioned to BYPASS ENABLE & Verify LED illuminates CUE The LED is illuminated

'd,

Verify ALB05 C02 illuminated CUE ALB05 C02 is illuminated DO

PB935B BTI switch #34 positioned to BYPASS amD

Verify 935B LED illuminated CUE 935B LED is illuminated

-n-1

Verify TSLB extinguished CUE The TSLB for 935B is extinguished

13 /

4 SOUTHERN AM COMPANY Energy to Serve Your World PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-13125 REDUCE CONTAINMENT PRESSURE FOLLOWING CVI Revision 11 October 4, 2000 I

NRC-JP-13125 This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions:

Assigned Task:

During a pressure relief operation, a spurious CVI was actuated while I&C was troubleshooting a faulty slave relay. The testing has been terminated and the CVI signal has been reset.

The USS has verified the existing Gaseous Release Permit is still valid and has directed you to "Initiate containment pressure relief" per Section 4.4.1 of 13125-1 and reduce Containment pressure to 0 psig.

i

NRC-JP-13125 Examiner's Signature:

OPERATOR'S NAME:

EVALUATION DATE:

JPM TITLE:

Reduce Containment Pressure Following CVI REVISION:

11 October 4, 2000 COMPLETION TIME: 20 minutes APPLICATION:

RO/SRO TASK NUMBER:

B.1.g K/A NUMBER:

029A1.03 Evaluation Method

[

Performed

[

Simulated Evaluation Location

[

Simulator

[

Control Room

[

Unit 1

[

Unit 2 Performance Time:

minutes OVERALL JPM EVALUATION

[ ] SATISFACTORY E ] UNSATISFACTORY Examiner Comments:

NRC-JP-13125 This JPM is based on the latest rev of 13125-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

13125, Containment Purge System

1.

2.

3.

4.

5.

Reset to IC14 Place Mini-Purge supply fan in service per 13125 Remove Mini-Purge supply fan from service when Containment pressure is = 0.5 psig Ack/Reset alarms Freeze simulator Setup time: 10 minutes DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard.

Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

ASSIGNED TASK:

During a pressure relief operation, a spurious CVI was actuated while I&C was troubleshooting a faulty slave relay. The testing has been terminated and the CVI signal has been reset.

The USS has verified the existing Gaseous Release Permit is still valid and has directed you to "Initiate containment pressure relief" per Section 4.4.1 of 13125-1 and reduce Containment pressure to 0 psig.

NRC-JP-13125 JPM STEPS START TIME:

Notes:

STEP 1 SAT flg UNSAT ODe Procedure and section reference

sO

13125 section 4.4.1 CUES:

(1)

If requested, "The USS does not desire to start additional containment coolers."

(2)

When requested, "The USS has obtained an updated gaseous release permit."

(3)

All Radiation monitors are operable Notes:

STEP 2 CRITICAL (,)

SAT O1e UNSAT ODe*

Initiate containment pressure relief

'aD

Containment pressure verified between 0.3 and 4.4 psig CUE Containment pressure is 0.5 psig

-.D

Mini-purge exhaust damper (1/2)HV-12592 CLOSED CUE Red light OFF; Green Light ON

,nD

Mini-purge ORC isolation (1/2)HV-2629B OPEN CUE Red light ON; Green Light OFF

'aD

Mini-purge IRC isolation (1/2)HV-2628B OPEN CUE Red light ON; Green Light OFF CUE If requested, "The USS has logged the initiation of Containment pressure relief and notified Chemistry."

NRC-JP-13125 JPM STEPS STEP 4 CRITICAL(,

SAT Oz UNSAT De Stop pressure relief

-e&

Containment pressure -0.1 to +0.1 psig CUE Containment pressure is 0 psig CUE If requested, "The USS will log the final Containment pressure and stop time on the gaseous release permit."

mEJ

Mini-purge exhaust fan (1/2)HS-2631 B STOPPED CUE Red light OFF; Green light ON 50D

Mini-purge Containment isolation (1/2)HV-2629B CLOSED CUE Red light OFF; Green light ON a0

Mini-purge Containment isolation (1/2)HV-2628B CLOSED CUE Red light OFF; Green light ON a0

Mini-purge exhaust damper (1/2)HV-12592 CLOSED CUE Red light OFF; Green light ON Notes:

STEP 3 CRITICAL (,)

SAT De UNSAT 02 Place containment mini-purge exhaust fan in service

,m0

Containment pressure <+0.3 psig CUE Containment pressure is now 0.2 psig

ŽsO

Mini-purge exhaust damper (1/2)HV-12592 OPEN CUE Red light ON; Green light OFF aD

Mini-purge exhaust fan running using (1/2)HS-2631 B CUE Red light ON; Green light OFF d,

0 Place (1/2)HV-12592 in AUTO Notes:

JPM STEPS STEP 5 SAT De UNSAT Oe Document termination of containment pressure relief

-mE]

Chemistry notified CUE "The USS will notify Chemistry that the pressure relief is secured."

-&O

The following valves verified CLOSED using Checklist 3 Preaccess purge inlet (1/2)HV-2593 Mini-purge exhaust Containment isolation (1/2)HV-2628B Mini-purge exhaust Containment isolation (1/2)HV-2629B Mini-purge supply Containment isolation (1/2)HV-2626B Mini-purge supply Containment isolation (1/2)HV-2627B CUE Red light OFF; Green light ON (For All Valves)

Independent verification requested for Checklist 3 CUE "The EXTRA RO will perform the IV on checklist 3."

Notes:

NRC-JP-13125 STOP TIME:

STEP 6 SAT De UNSAT 02*

Report to USS

,n,0 Containment pressure relief completed Notes:

1l-4 SOUTHERN A COMPANY Energy to Serve Your World' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-18038 CONTROL PRZR PRESSURE AND SG LEVEL FROM REMOTE SHUTDOWN PANELS Revision 0 November 14, 2002

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

REMEMBER: All steps required for this task are to be simulated.

Plant equipment is not to be operated.

Initial Conditions:

Assigned Task:

Unit control room has been evacuated due to fire. You have responded to Shutdown Panel-.

PRZR pressure is 2200 psig and lowering. SG WR levels are - 60% and lowering.

The USS has directed you to "Restore PRZR pressure and SG level using 18038, steps 11 and 12", and control within required procedure limits.

2

NRC-JP-18038 JPM INFORMATION OPERATOR'S NAME:

EVALUATION DATE:

JPM TITLE:

REVISION:

COMPLETION TIME:

APPLICATION:

TASK NUMBER:

K/A NUMBER:

_ /

__/

Control PRZR Pressure and SG level From Remote Shutdown Panels 16 August 15, 2001 10 minutes RO/SRO B.2.a 068AA1.03, 068AA1.28 3

Evaluation Method

[

Performed

[

Simulated Evaluation Location

[

Simulator

[] Control Room

[

Unit 1

[1 Unit 2 Performance Time:

minutes OVERALL JPM EVALUATION

[ ] SATISFACTORY E ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

NRC-JP-18038 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 18038-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

2.

18038-1/2, Operation From Remote Shutdown Panels PSDA(B) room key COMPONENT LOCATION:

PSDA(B) Rooms, Control Building, Level A DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard.

Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

REMEMBER: All steps required for this task are to be simulated.

Plant equipment is not to be operated.

INITIAL CONDITIONS:

Assigned Task:

Unit control room has been evacuated due to fire. You have responded to Shutdown Panel

. PRZR pressure is 2200 psig and lowering. SG WR levels are = 60% and lowering.

The USS has directed you to "Restore PRZR pressure and SG level using 18038, steps 11 and 12", and control within required procedure limits.

4 i

NRC-JP-18038 JPM STEPS START TIME:

5 STEP 1 CRITICAL (,)

SAT 0,K UNSAT De Control PRZR pressure Note: All controls would have been transferred to Local at step 7. The operator should demonstrate knowledge of pressure control by expressing the need to operate sprays/heaters to stabilize pressure between 2220 and 2260 psig.

PORV (1/2)PV-455A(456A) closed CUE Red light is OFF; Green light is ON CUE Provide indication that PRZR pressure is 2200 psig and lowering slowly.

[PSDA only] Sprays (1/2)PV-455B and (1/2)PV-455C closed CUE Demand meter indicates 0%; Green down arrow pushbutton is illuminated; Red light is OFF; Green light is ON "the stem mounted switches"

'mDEl

Backup heater (1/2)HS-10469B(10470B) in ON CUE Red light is ON; Green light is OFF CUE Provide indication that PRZR pressure is 2220 psig and rising slowly

,,a[

Heaters and Sprays operated to maintain PRZR pressure between 2220 and 2260 psig

NRC-JP-18038 JPM STEPS STOP TIME:

STEP 2 CRITICAL (,)

SAT De UNSAT De Control Steam Generator level Note: The operator should demonstrate knowledge of level control by expressing the need to adjust AFW flow to stabilize SG WR levels between 65% and 70%.

,&D MDAFW pump A(B) running CUE Red light is ON; Green light is OFF CUE If referenced discharge pressure is 1700 psig CUE SIG 1/4 levels are 60% and slowly lowering (Train "A" shutdown panel)

CUE S/G 213 levels are 59% and slowly lowering (Train "B" shutdown panel)

E*

Flow control Train "A" (1/2)FV-5137 and (1/2)FV-5139, Train "B"(1/2)FV-5134 and (1/2)FV-5132 throttled open CUE Red light is ON; Green light is ON aD

Miniflow (1/2)FV-5155(5154) verified open CUE Red light is ON; Green light is OFF

-,3D

AFW flow verified CUE AFW flow is 175 gpm S/Gs 1/4 (Train "A" shutdown panel)

CUE AFW flow is 190 gpm S/Gs 2/3 (Train "B" shutdown panel) a&D

FCVs operated to maintain SG WR levels between 65% and 75%

CUE Provide indication WR S/G levels are slowly rising STEP 3 SAT 02 UNSAT 0-K Report to USS

-DO

PRZR pressure and SG level being maintained Field Notes 6

L32-13 SOUTHERN Sn COMPANY Energy to Serve Your World' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-J P-18034 Turbine Driven AFW Pump Local Manual Control without DC Power Revision 0 November 14, 2002

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

REMEMBER: All steps required for this task are to be simulated.

Plant equipment is not to be operated.

Initial Conditions:

Assigned Task:

The plant just experienced a trip due to a lightning strike in the switchyard. This caused a lock out relay to actuate on __AA02 and a fault on OCDI. The MDAFW pump B is tagged out for maintenance.

The USS, with SS approval, has directed you to "Locally start the Unit TDAFW pump using Attachment E of 18034-2

RQ-JP-18034-002 JPM INFORMATION 3

Evaluation Method

[

Performed

[

Simulated Evaluation Location

[

Simulator

[

Control Room

[ ] Unit 1

[

Unit 2 Performance Time:

minutes OVERALL JPM EVALUATION

[ ] SATISFACTORY

[

UNSATISFACTORY Examiner Comments:

Examiner's Signature:

RQ-J P-18034-002 INSTRUCTIONS TO EXAMINER This JPM is based on 18034-1. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

18034-1/2 Attachment E, TDAFW Pump Local w/o DC Power COMPONENT LOCATION:

TDAFWP Room DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

REMEMBER: All steps required for this task are to be simulated.

Plant equipment is not to be operated.

INITIAL CONDITIONS:

The plant just experienced a trip due to a lightning strike in the switchyard. This caused a lock out relay to actuate on __AA02 and a fault on OCDI. The MDAFW pump B is tagged out for maintenance.

ASSIGNED TASK:

The USS, with SS approval, has directed you to "Locally start the Unit using Attachment E of 18034-TDAFW pump 4

RQ-J P-18034-002 JPM STEPS START TIME:

STEP 2 SAT Ler UNSAT Fe Verify steam supply valve shut r-I

,E Verify that (1/2)-HV-5106 is CLOSED.

CUE If located and verified correctly, state "(112)-HV-5106 is in the position you see now."

STEP 3 SAT DQ!

UNSAT De; Verify Trip and Throttle Valve open

,d]

Verify that TDAFW Pump Trip & Throttle Valve is LATCHED.

CUE If located and verified correctly, state "Trip and Throttle Valve latching mechaninsm is in the position you see now."

-&D

Verify that TDAFW Pump Trip & Throttle Valve is OPEN.

CUE If located and verified correctly, state "Trip and Throttle Valve is in the position you see now."

STEP 4 SAT DQ UNSAT Oz Locate FI-15100 to allow monitoring TDAFW Pump performance

&D

Locate (1/2)-FI-15100 inTDAFW Pump room.

5

RQ-J P-18034-002 JPM STEPS STEP 5 CRITICAL (*)

SAT &f UNSAT L&e Start TDAFW Dump to suplyv feed flow to Steam Generators aD

Throttle OPEN TDAFW Pump Steam Supply (1/2)-HV-5106.

CUE If valve throttled open correctly, state "Steam flow can be (1/2)-HV-5106."

heard due to opening

-nFD

Observe (1/2)-Fl-15100 and Adjust (1/2)-HV-5106 to attain 140gpm miniflow.

CUE Give cues to determine the operators ability to control proper miniflow rate as required. As steam flow is increases, feedback an increase in miniflow flowrate. The operator should take actions to control at approximately 140 gpm.

STOP TIME:

Field Notes 6

f520 C

SOUTHERN COMPANY Energy to Serve Your WorldS PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-19100 LOCALLY ISOLATE RCP SEALS Revision 0 November 14, 2002

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

REMEMBER: All steps required for this task are to be simulated.

Plant equipment is not to be operated.

Initial Conditions:

Assigned Task:

The crew is responding to a loss of all AC power on Unit __ per 19100.

Power has been lost for 12 minutes and is not expected to be restored in the near future.

The USS has directed you to "Locally close the following Unit __

valves to isolate the RCP seals:

ACCW supply isolation ORC, -- HV-1979(AB-A

),

RCP seal injection isolation valves ORC,

-HV 8103A/B(AB-A

), & -- HV-8103C/D(FHB-A-),

RCP seal return isolation ORC, _-HV-8100(AB-A 2

NRC-JP-19100 JPM INFORMATION OPERATOR'S NAME:

EVALUATION DATE:

/

JPM TITLE:

REVISION:

COMPLETION TIME:

APPLICATION:

TASK NUMBER:

K/A NUMBER:

Locally Isolate RCP seals 13 September 10, 2001 15 minutes RO/SRO B.2.c 003A4.01 Evaluation Method

[] Performed

[] Simulated Evaluation Location

[

Simulator

[

Control Room

[

Unit 1

[

Unit 2 Performance Time:

minutes OVERALL JPM EVALUATION

[

SATISFACTORY

[

UNSATISFACTORY Examiner Comments:

Examiner's Signature:

3

NRC-JP-19100 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 19100-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©.are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

COMPONENT LOCATION:

1.

RWP and associated dosimetry

2.

Hearing Protection UNIT 1 1979 (AB-A12); 8103A/1B (AB-A09); 8103C/D (FHB-A10); and 8100 (AB-A09)

UNIT 2 1979 (AB-A105); 8103A/B (AB-A103); 8103C/D (FHB-AO1); and 8100 (AB-A103)

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

REMEMBER: All steps required for this task are to be simulated.

Plant equipment is not to be operated.

INITIAL CONDITIONS:

The crew is responding to a loss of all AC power on Unit _

per 19100. Power has been lost for 12 minutes and is not expected to be restored in the near future.

ASSIGNED TASK:

The USS has directed you to "Locally close the following Unit __

RCP seals:

valvesto isolate the ACCW supply isolation outside, _-HV-1979(AB-A

),

RCP seal injection isolation valves, _-HV-8103A/B(AB-A_

),

and __-HV-8103C/D(FHB-A

),

RCP seal return isolation outside, _-HV-8100(AB-A

)."

4 i

NRC-JP-19100 JPM STEPS START TIME:

5 STEP 1 CRITICAL (,)

SAT D02 UNSAT De Isolate ACCW Return from RCPs

-D

ACCW containment isolation (1/2)HV-1 979 located.

-d0

(1/2)HV-1979 CLOSED.

STEP 2 CRITICAL (,)

SAT 0Oe UNSAT Oz Isolate RCP seal injection Note: If these valves are inaccessible, the path of ingress should be to the closest point allowed by radiological conditions and using local maps identify valve locations.

,IO

RCP seal injections (1/2)HV-8103A and B located.

-d

(1/2)HV-8103A and B CLOSED.

,aD

RCP seal injections (1/2)HV-8103C and D located.

-eB

(1/2)HV-8103C and D CLOSED.

NRC-JP-19100 JPM STEPS STOP TIME:

Field Notes 6

STEP 3 CRITICAL (,)

SAT OD UNSAT De Isolate RCP seal return Note: If these valves are inaccessible, the path of ingress should be to the closest point allowed by radiological conditions and using local maps identify valve locations.

. Seal return (1/2)HV-8100 located.

,d0

(1/2)HV-8100 CLOSED.

STEP 4 SAT 0De UNSAT 0.*

Report to USS

-,D

RCP seals are locally isolated.

II

ES-301 Administrative Topics Outline Form ES-301-1 (R8, Si)

Facility:

Voqtle Date of Examination:

12/02/02 Examination Level (circle one): RO Operating Test Number:

tt-1 J Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A.1 Shift Manning Requirement CONDUCT OF K/A: G2.1.1, G2.1.4 OPERATIONS Calculate Boron Addition Following Reactor Trip with 3 stuck CONDUCT OF Control Rods OPERATIONS K/A: G2.1.23 A.2 Review Clearance for Containment Spray Pump, Train "A" EQUIPMENT K/A: G2.2.13 CONTROL A.3 Calculate Worker Dose Using Survey Maps RADIATION K/A: G2.3.4 CONTROL A.4 Make Emergency Notifications with Failure of the ENN EMERGENCY K/A: G2.4.43 PLAN

ES-301 Administrative Topics Outline Form ES-301-1 (R8, Si)

Facility:

Voatle Date of Examination:

12/02/02 Examination Level (circle one): ISRO/ USRO Operating Test Number:

'-i na_4 Administrative Describe method of evaluation:

Topic/Subject

1. ONE Administrative JPM, OR Description

2. TWO Administrative Questions A.1 Shift Manning Requirements CONDUCT OF K/A: G2.1.1, G2.1.4 OPERATIONS Calculate Boron Addition Following Reator Trip with 3 Stuck CONDUCT OF Control Rods OPERATIONS K/A: G2.1.23 A.2 Review Clearance for Containment Spray Pump "A" EQUIPMENT K/A: G2.2.13 CONTROL A.3 Question Topic - License Requirements for Conducting a Waste Release with Inoperable Instrumentation and Administrative RADIATION Controls Ensuring Requirements Met.

CONTROL K/A: G2.3.6 Question Topic - Selection Process for Individuals Performing Emergency Entries into Radiation Fields Resulting in Exceeding Permissible Exposure Limits.

K/A: G2.3.4 A.4 Perform an Emergency Action Level Classification and EMERGENCY Recommend Protective Actions PLAN K/A: G2.4.41, G2.4.44

SOUTHERNAM COMPANY Energy to Serve Your World' PLANT VOGTLE NRC-JP-10003 SHIFT MANNING REQUIREMENTS 10003-C October 04,2002 Rev #0

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

"* Unit 1 in MODE 6 for refueling outage with fuel movement in progress.

"* Unit 2 is defueled Assigned Task:

Part #1 Fill in the Minimum shift composition on the table provided for each unit and common personnel.

Part #2 The total number of personnel required is

Evaluation Method [

Performed Evaluation Location [

Simulator Performance Time:

minutes E ] Simulated

[

Control Room

( ] Unit 1 OVERALL JPM EVALUATION

[ ] SATISFACTORY

[

UNSATISFACTORY Examiner Comments:

Examiner's Signature:

OPERATOR'S NAME:

EVALUATION DATE:

I I

JPM TITLE:

SHIFT MANNING REQUIREMENTS COMPLETION TIME:

20 minutes APPLICATION:

RO/SRO TASK NUMBER:

A.l.a, Conduct of Operations K/A NUMBER:

G2.1.1, G2.1.4

[ ] Unit 2 i

INSTRUCTIONS TO EXAMINER DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

"* Unit 1 in MODE 6 for refueling outage with fuel movement in progress.

"* Unit 2 is defueled Assigned Task:

Part #1 Fill in the Minimum shift composition on the table provided for each unit and common personnel.

Part #2 The total number of personnel required is

JPM STEPS Unit 1 Common Unit 2 SS SRO RO NLO STA Total personnel required to meet MINIMUM shift composition is

JPM STEPS Answer Key.

Start Time:

(a) SRO required for fuel movement Total personnel required to meet MINIMUM shift composition is Stop Time 7.

Field Notes:

Unit 1 Common Unit 2 SS SRO 1 (a)

RO 1

1 NLO 1

1 1

STA None None None

AýýuU SOUTHERNSA.

COMPANY Energy to Serve Your World PLANT VOGTLE NRC-JP-19001 Calculate Boron Addition Following Reactor Trip With 3 Stuck Control Rods October 04,2002 Rev #0

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip

"* EOL

"* RCS Boron Concentration is at 200 ppm

"* BAST Boron Concentration is 7100 ppm

"* RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

"* Reactor Trip Breakers are open

"* Power Range Ni's indicate 0%

"* DRPI indicates that 3 rod failed to fully insert

" The RO actuates both the QMCB Reactor Trip Handswitches and announces the Reactor Tripped

" The Operating Crew has entered 19001-C to stablize the plant On Step 3 on 19001-C the USS checks all "FULLY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

OPERATOR'S NAME:

EVALUATION DATE:

- /

JPM TITLE Calculate Boron Addition Following Reactor Trip With 3 Stuck Control Rods REVISION:

0 Date: October 04, 2002 COMPLETION TIME: 15 minutes Application:

RO "Evaluation Method

[] Performed Evaluation Location

[ ] Simulator Performance Time:

minutes

[ ] Simulated

] Control Room

[ ] Unit 1 OVERALL JPM EVALUATION

[ ] SATISFACTORY E ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

[ I Unit 2 i

INSTRUCTIONS TO EXAMINER Direction To Operator:

This JPM is based on latest revision of 19001-C. If this revision is no longer current, verify this JPM is in accord with the latest procedural revision. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable.

REQUIRED ITEMS:

1. Calculator

2. PTDB (Plant Technical Data Book)

3. 19001-C Initial Conditions: Given the Following Conditions/Events on Unit 1:

Automatic Reactor Trip due to Main Turbine Trip

"* EOL

"* RCS Boron Concentration is at 200 ppm

"* BAST Boron Concentration is 7100 ppm

"* RCS is at 2235 psig and 557 degrees F.

On step 1 of 19000-C the following conditions are observed:

"* Reactor Trip Breakers are open

"* Power Range Ni's indicate 0%

"* DRPI indicates that 3 rod failed to fully insert

"* The RO actuates both the QMCB Reactor Trip Handswitches and announces the Reactor Tripped

"* The Operating Crew has entered 19001-C to stablize the plant

"* On Step 3 on 19001-C the USS checks all "FULLY INSERTED" Assigned Task: How many gallons of boric acid must be added to the RCS under the stated conditions?

I

START TIME:

STEP 1 CRITICAL (.)

SAT Oz Boron Addition to UNSAT De the RCS calculated Determine that 154 ppm is required for each stuck rod For three stuck rods boration requird is:(154 ppm) X (3 Rods) = 462 ppm Calculate the required boration using equation for PTDB tab 2.3 4252 (+ or - 50) gallons of boric acid added to the RCS STOP TIME:

Field Notes AD ADl

Calculation:

(154 ppm) X (3 Rods) = 462 ppm RCS Boron Concentration = 61346 X Ln (7100 - 200 / 7100 - 662) = 4252 gallons of Boric Acid

4 SOUTHERN AM COMPANY Energy to Serve Your World PLANT VOGTLE NRC-JP-00304 Review Clearance for Containment Spray Pump Train "A" October 04,2002 Rev #0 i

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions:

"* Unit 1 is at 100% Reactor Power on 10/04/02

"* A planned outage for Containment Spray Pump Train "A" to replace the pump seals is to be installed on 10/05/02

"* The scope of the work requires that the motor be electrically isolated and the pump drained.

"* NSCW cooling water to the pump is NOT required to be tagged as part of the boundary.

"* The LCO has been written and will be entered when the clearance is authorized by the USS Assigned Task:

Verify clearance hold points for Containment Spray Pump Train "A" are correct.

OPERATOR'S NAME:

Evaluation Method Evaluation Location Performance Time:

Performed

] Simulator minutes

[ ] Simulated

[ Control Room

[ I Unit 1 OVERALL JPM EVALUATION

[ ] SATISFACTORY

[ ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

"EVALUATION DATE:

-I/

/

JPM TITLE:

Review Clearance for Containment Spray Pump Train "A" REVISION:

0 Date: October 04, 2002 COMPLETION TIME: 30 minutes Application:

RO/SRO

[ ] Unit 2 I

INSTRUCTIONS TO EXAMINER Direction To Operator:

This JPM is based on the latest revision of 00304-C. If this revision is no longer current, verify this JPM is in accord with the latest procedural revision. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable.

REQUIRED ITEMS:

1. Current revision of 00304-C Initial Conditions:

"* Unit 1 is at 100% Reactor Power on 10/04/02

"* A planned outage for Containment Spray Pump Train "A" to replace the pump seals is to be installed on 10/05/02

"* The scope of the work requires that the motor be electrically isolated and the pump drained.

"* NSCW cooling water to the pump is NOT required to be tagged as part of the boundary

"* The LCO has been written and will be entered when the clearance is authorized by the USS Assigned Task: Verify clearance hold points for Containment Spray Pump Train "A" are correct.

i I

START TIME:

STOP TIME:

Field Notes STEP 1 CRITICAL (,)

SAT OE UNSAT De Containment Spray Pump Train "A" clearance review

1

Errors on clearance identified.

1. Step 2 breaker should be 1 AA02-14

2. Step 3 Control Room Handswitch should be 1-HV-9003A

3. Step 6 should be 1ABD-30

4. Step 13 should be 1HV-9003A

5. Step 16 should be 1-1206-U4-115

CLEARANCE SHEET C e 2Equipment Number:

Clearance# 10210011 1-1206-P6-001 Equipment

Description:

CONTAINMENT SPRAY PUMP TRAIN "A" Reason For Clearance (include WO No.):

Replace pump seals (1-02-111)

Additional WOs:

Requested by: Al Sweat Extension: 3963 Beeper: 111 Requires LCO:

Locked Valves:

Fire Protection Impaired:

IV Required:

Z] Yes [--]No

Yes n] No

[]Yes ENo OYea [--]NO Prepared by: Al Sweat Date: 10/04/02 Reviewed by:

Date:

Authorized by:

Date:

Time:

Installed by."

Date:

Time:

Verified by:

Date:

Time:

SUBCLEARANCES; NAME GROUNDING DEVICES VERIFIED Printed in first space REMOVED AND SUBCLEARANCE Signature in second space RELEASED BY:

PRINT AND SIGNATURE WORK DOC EXT.

DATE TIME SIGNATURE DATE TIME

1.

2.

3.

4.

5.

COMMENTS:

NSCW cooling line not required to be tagged out for this work.

Front t of 4

Clearance #

10210011 Prepared by: AL SWEAT EQUIPMENT TO BE CLEARED AND TAGGED TAGS TO BE REMOVED AND EQUIPMENT RETURNED 1-1206-P6-001 TO SERVICE AS SPECIFIED 01 1RHS-1o0940 PTL Containment Spray Train "A" QMCB Control Handswitch 02 1 1AAo2-15 I Disconnect Supply Breaker to Containment Spray Train "A" Pump 03 1 HS-9003B I CL/Normal Pump Discharge Isolation Motor Operated Valve from Containment Sump 04 1 1HS-9001 CIJAUTO Pump Discharge Isolation Motor Operated Valve 05 i.HS-01A ICL/Normal Pump Discharge Isolation Motor Operated Valve from RWST 06 iBsD-o OFF 1HS-9003B feeder breaker 07 1 ABD-48 OFF 1 HS-9001 A feeder breaker 08 ABD-41 OFF 1 HS-9017A feeder breaker 09 1 SBBDS0W-K2 OPEN Alarm relay 10 1 1ABD48W-K2 OPEN Alarm Relay 11 I1ABD41W-K2 OPEN Alarm Relay 12 11AYE-34 OFF 1-1206-P6-001 Motor Space Heater 13 1HV-9003B Closed Pump Discharge Isolation Motor Operated Valve from Containment Sump Handwheel

Clearance # 10210011 Prepared by: Al Sweat EQUIPMENT TO BE CLEARED AND TAGGED TAGS TO BE REMOVED AND EQUIPMENT RETURNED 1-1206-P6-001 TO SERVICE AS SPECIFIED 14 IHV-9001A.closed Pump Discharge Isolation Motor Operated Valve Handwheel 15 1 IHV-9017A Closed Pump Discharge Isolation Motor Operated Valve from RWST Handwheel 16 1 -1206-1u.4-114 Closed 1HV-90039 bypass line Isolation valve S

20&IU4-Wi4 Closed Spray eductor manual Isolation valve (Normally Locked Closed) 18 1-1206-U4-006 Closed Pump Discharge RWST test line (Normally Locked Closed) 19 1-1206-U4-109 Open Containment Spray Train "A" Pump casing drain 20 1-1206-U4-112 Open Containment Spray Train "A" Pump suction line drain 21 1-1 20&oX4-1 08 UnaOpn Containment Spray Train "A" Pump Discharge line vent 22 1-1206-U.14-108 Unflangel I

I Open Containment Spray Train "A" Pump casing vent

Clearance #

Prepared by:

10210011 Al Sweat TECH SPEC #

LCO #

SI #

3.6.6 1-02-111 P&CD ELEM ELEC CONN Extended Active Clearance Quarterly Audits:

DATE INITIAL DAT INMTAL DATE IINITIAL_

I

Answer Key CLEARANCE SHEET Equipment Number:

Clearance# 10210011 1-1206-P6-001 Equipment

Description:

CONTAINMENT SPRAY PUMP TRAIN "A" Reason For Clearance (include WO No.):

Replace pump seals Additional WOs:

Requested by: Al Sweat Extension: 3963 Beeper: 111 Requires LCO:

Looked Valves:

Fire Protection Impaired:

IV Required:

[]

Yes E-]No

[]Yes []

No E-]Yes []No

[]Yes E']No Prepared by:

Date:

Reviewed by:

IDate:

Authorized by:

Date:

Time:

Installed by:

Date:

Time:

Verified by:

Date:

Time:

SUBCLEARANCES NAME GROUNDING DEVICES VERIFIED Printed in first space REMOVED AND SUBCLEARANCE Signature In second space RELEASED BY:

PRINT AND SIGNATURE WORKDOC EXT.

DATE TIME SIGNATURE DATE TIME

1.

2.

3.

4.

5.

COMMENTS:

NSCW cooling line not required to be tagged out for this work.

Front 1 of 4

Answer Key Clearance #

10210011 Prepared by: AL SWEAT EQUIPMENT TO BE CLEARED AND TAGGED TAGS TO BE REMOVED AND EQUIPMENT RETURNED 1-1206-P6-001 I TO SERVICE AS SPECIFIED I

Pump Discharge Isolation Motor Operated Valve from Containment Sump Handwheel 01 1fHS-10940 PTL Containment Spray Train "A" QMCB Control Handswitch 02 1 AAO2-14*.

Disconnect Supply Breaker to Containment Spray Train "A" Pump 03 I1HS-9003A...

C IC/Normal Pump Discharge Isolation Motor Operated Valve from Containment Sump 04 1 HS-90o1A ICIAUToO Pump Discharge Isolation Motor Operated Valve 05 1 HS-9017A ICL/Normal Pump Discharge Isolation Motor Operated Valve from RWST 06 1fABDO*O-OFF 1 HS-9003A feeder breaker 07 1 fABD-48 OFF 1 HS-9001 A feeder breaker o0 B

1AD-41 OFF IF 1 HS-9017A feeder breaker 09 1ABD3OW-K2**

N "NotReuired" ROPEN Alarm relay 10 1 2A5D46W-K2 OPEN--

Alarm relay 11 1 ABD41W-K2 oPEN Alarm relay 12 11AYEl-34 OFF 1-1206-P6-001 Motor Space Heater 13 11HV-9003A.*.

Closed

Cl Answer Key earance #10210011 Prepared by: Al Sweat EOUIPMENTTO BE CLEARED AND TAGGED AT STO F 1-1206-P6-001 TO SERVICE

00 I '°L!

IcZesa W

14 1 HV-9001A Closed Pump Discharge Isolation Motor Operated Valve Handwheel 15 1HV-9017A Closed Pump Discharge Isolation Motor Operated Valve from RWST Handwheel 16 1112oor-U-115...

IClosed 1HV-9003A bypass line isolation valve 17 1-1206-U4-006Co Containment Spray Train "A" test line to RWST (Normally Locked Closed) 18 1-1206-.u4-034 Cled I

Cl o Spray eductor manual isolation valve (Normally Locked Closed) 19I 1-120-U1°g 1oPEN 1

Containment Spray Train "A" Pump casing drain (Normally Locked Closed) 20 1-1206-U4-112 Open Containment Spray Train "A" Pump suction line drain 1-126-X410BUncap/

21 1-12064-1Open Containment Spray Train "A" Pump Discharge line vent 22 1-1206-U4-108 Ti nfian7 Containment Spray Train "A" Pump casing vent

Answer Key Clearance #

Prepared by:

10210011 Al Sweat TECH SPEC #

LCO#

SI#

P&ID MECH ELEM ELEC CONN Extended Active Clearance Quarterly Audits:

DATE INITIAL DATE DATE INITIAL

Lo 5.

SOUTHERNA COMPANY Energy to Serve Your World' PLANT VOGTLE NRC-JP-00920 CALCULATE WORKER DOSE USING SURVEY MAPS October 04,2002 Rev #0 i

JPM INFORMATION This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

1 You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

Unit 1 in MODE 5 for refueling outage.

The Operating Crew has entered 18019-C "Loss of RHR" Section "B" The Auxiliary Building System Operator has been dispatched to shut Recirculation to RWST isolation Valve" Assigned Task:

1-1205-U4-027 "RHR Given that Auxiliary Building System Operator is required to:

- Remain in the area for 15 minutes to shut 1-1205-U4-027

- Will receive 10 mRem TEDE while transiting to the valve Using the Radiological Information Survey Map provided calculate the "TOTAL" dose the Auxiliary Building System Operator will receive following the task.

JPM INFORMATION Evaluation Method [ ] Performed Evaluation Location [ ] Simulator Performance Time:

minutes Simulated

] Control Room

[

Unit 1 OVERALL JPM EVALUATION

[ ] SATISFACTORY

[ ] UNSATISFACTORY Examiner Comments:

Examiner's Signature:

1'6 OPERATOR'S NAME:

"EVALUATION DATE:

JPM TITLE:

CALCULATE WORKER DOSE USING SURVEY MAPS COMPLETION TIME: 20 minutes Application:

RO/SRO Task Number:

RO A.3 K/A Number:

G2.3.4

[ ] Unit 2 I

INSTRUCTIONS TO EXAMINER DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

Unit 1 in MODE 5 for refueling outage.

The Operating Crew has entered 18019-C "Loss of RHR" Section "B"

" The Auxiliary Building System Operator has been dispatched to shut 1-1205-U4-027 "RHR Recirculation to RWST isolation Valve" Assigned Task:

Given that Auxiliary Building System Operator is required to:

- Remain in the area for 15 minutes to shut 1-1205-U4-027

- Will receive 10 mRem TEDE while transiting to the valve Using the Radiological Information Survey Map provided calculate the "TOTAL" dose the Auxiliary Building System Operator will receive following the task.

JPM STEPS Start Time:

STEP 1 SAT Cle UNSAT Cr (300 mrem/hr) (lhr/60min) (15 min) = 75 mrem + 20 mrem = 95 mrem +/- 2 mrem Stop Time Field Notes

RHR Train "A" Mezzanine Room 1RD-48 MEZZ Remote Gamma Dose Survey #11111 Survey Points 1

2 3

4 5

6 7

U Danger High Radiation B/G 300 mrem/hr Danger High Radiation B/G 300 mrem/hr Danger High Radiation B/G 300 mrem/hr Danger High Radiation BIG 300 mrem/hr Danger High Radiation BIG 700 mrem/hr Hot Spot 1700/300 mrem/hr Hot Spot 1900/500 mrem/hr Airborne

<.2 DAC Total

= Back Ground Radiation Levels S

S o A3 6L 3

1 SOUTHERN A COMPANY Energy to Serve Your World' PLANT VOGTLE NRC-JP-ODCM LIQUID RELEASE WITH 1 RE-001 8 INOPERABLE October 04,2002 Rev #0

INSTRUCTIONS TO EXAMINER This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

"* Unit 1 is at 100% Reactor Power The Auxiliary Building System Operator has just completed processing WMT #9 for release.

"* 1RE-0018 was declared INOPERABLE on the last shift.

Under what conditions can this tank be released?

Assigned Task:

INSTRUCTIONS TO EXAMINER OPERATOR'S NAME:

EVALUATION DATE:

I I

JPM TITLE:

LIQUID RELEASE WITH 1RE-0018 INOPERABLE COMPLETION TIME: 20 minutes Evaluation Method [ ] Performed

[ ] Simulated Evaluation Location E ] Simulator

[

Control Room

[ ] Unit 1

[

Unit 2 Performance Time:

minutes OVERALL JPM EVALUATION

[ ] SATISFACTORY

[

UNSATISFACTORY Examiner Comments:

Examiner's Signature:

INSTRUCTIONS TO EXAMINER DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

INITIAL CONDITIONS:

Unit 1 is at 100% Reactor Power The Auxiliary Building System Operator has just completed processing WMT #9 for release.

.11 RE-0018 was declared INOPERABLE on the last shift.

Under what conditions can this tank be released?

Assigned Task:

JPM STEPS START TIME:

Stop Time Field Notes STEP 1 SAT 0'*

UNSAT 02 Per Offsite Dose Calculation Manual (ODCM)

(1) Two independent samples are analyzed (2) Two technically qualified members of the facility staff independently verify the discharge line valving and the release rate calculations.

spo A4k;.2-,

SOUTHERN COMPANY Energy to Serve Your World' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-91301 EMERGENCY EXPOSURE GUIDELINES SRO ONLY October 04,2002 Rev 0 i

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions:

Given the following Conditions/Events on Unit 1:

" Major fuel damage occurred from a loose part in the RCS

" SGTRonS/G#1

" A General Emergency has been declared

" 1PV-3000, Loop #1 ARV has failed open Assigned Task:

HP has estimated that in the time it will take for a person to access the area and manually isolate the failed open ARV, they would receive 45 Rem (TEDE).

As the Emergency Director which of the following worker(s) would you select for the task?

I. 21 year old declared pregnant female, who is fully aware of the risks and current annual exposure is 520 mRem.

2. 45 year old male volunteer, who's lifetime exposure is 31 Rem, 27 Rem of which is classified as emergency exposure from a previous event.

3. 23 year old female volunteer, who has been briefed on the task and fully aware of the risks with a current annual exposure of 710 mRem.

4. 50 year old male, non-volunteer, who has been briefed on the task and fully aware of the risks with a current annual exposure of 111 mRem.

5. 40 year old male volunteer, who due to experience could complete the task in the least amount of time and has only received 4 Rem emergency exposure during this event.

2

JPM INFORMATION OPERATOR'S NAME:

EVALUATION DATE: -I--I-JPM TITLE:

EMERGENCY EXPOSURE GUIDELINES COMPLETION TIME: 15 minutes Application:

SRO Evaluation Method

( ) Performed Evaluation Location [ 3 Simulator Performance Time:

minutes Simulated Control Room

( ) Unit I OVERALL JPM EVALUATION I ) SATISFACTORY 3

) UNSATISFACTORY Examiner Comments:

Examiner's Signature:

3

( ) Unit 2

JPM INFORMATION 4

I I

JPM STEPS 1

DIRECTIONS TO OPERATOR Initial Conditions:

Given the following Conditions/Events on Unit 1:

"* Major fuel damage occurred from a loose part in the RCS

"* SGTR on S/G #1

"* A General Emergency has been declared

"* 1PV-3000, Loop #1 ARV has failed open Assigned Task:

HP has estimated that in the time it will take for a person to access the area and manually isolate the failed open ARV, they would receive 45 Rem (TEDE).

As the Emergency Director which of the following worker(s) would you select for the task?

I. 21 year old declared pregnant female, who is fully aware of the risks and current annual exposure is 520 mRem.

2. 45 year old male volunteer, who's lifetime exposure is 31 Rem, 27 Rem of which is classified as emergency exposure from a previous event.

3. 23 year old female volunteer, who has been briefed on the task and fully aware of the risks with a current annual exposure of 710 mRem.

4. 50 year old male, non-volunteer, who has been briefed on the task and fully aware of the risks with a current annual exposure of 111 mRem.

5. 40 year old male volunteer, who due to experience could complete the task in the least amount of time and has only received 4 Rem emergency exposure during this event.

5

JPM STEPS START TIME:

Stop Time Field Notes 6

STEP 1 CRITICAL (*)

UNSAT O-SAT De-Worker selected for task per 91301 -C "Emergency Exposure Guildlines" a&D 23 year old female volunteer, who has been briefed on the task and the risks.

0Q il-SOUTHERNAM COMPANY Energy to Serve Your World' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-J P-91002 MAKE EMERGENCY NOTIFICATIONS WITH FAILURE OF THE ENN Revision 0 November 19, 2002

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

G THis IS A TIME CRITICAL JPM 0 Initial Conditions:

An emergency has been declared and the Shift Superintendent has assumed the duties of the Emergency Director. The emergency recall system activation is not required because it normal working hours.

Assigned Task:

The Emergency Director has directed you to establish communications, and transmit the Emergency Notification form to all State and Local authorities.

NRC-JP-91002 JPM INFORMATION OPERATOR'S NAME:

EVALUATION DATE:

__/

/ __

JPM TITLE:

REVISION:

COMPLETION TIME:

Application:

Task Number:

K/A Number:

10CFR55.45 Ref.:

Evaluation Method

[] Per Evaluation Location

[

Sim Performance Time:

OVERALL JPM EVALUATION Make Emergency Notifications with Failure of the ENN 0

November 19, 2002 15 minutes TIME CRITICAL D

RO / SRO 40003 194001A1.16 RO:

3.1 SRO:

4.4 11 rformed iulator minutes

[ Simulated Control Room

[ ] SATISFACTORY Examiner Comments:

Examiner's Signature:

[1 UNSATISFACTORY

NRC-JP-91002 INSTRUCTIONS TO EXAMINER "This JPM is based on the latest rev of 91002-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©.are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#) are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

2.

SIMULATOR SETUP:

Notes to Examiner:

Procedure 91002-C, Emergency Notifications, Checklist 2 VEGP Emergency Response Telephone Directory Simulator not required for JPM performance (1)

Checklist 2, Sheet 2, Emergency Notification, should be completed with the exception of Steps 3, 4, and 6 prior to the start of this JPM. Step I.A, THIS IS A DRILL, should always be recorded.

(2)

Step 3 of the Emergency Notification form must be completed within 15 minutes of the time documented in Step 6.A. The start time of this JPM should be the time recorded in Step 6.A.

(3)

Ensure the ENN telephone jack in the rear of the ENN telephone has the "Simulator" cord installed.

DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard.

Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

This is a TIME CRITICAL JPM INITIAL CONDITIONS:

ASSIGNED TASK:

An emergency has been declared and the Shift Superintendent has assumed the duties of the Emergency Director. The emergency recall system activation is not required because it normal working hours.

The Emergency Director has directed you to establish communications, and transmit the Emergency Notification form to all State and Local authorities.

NRC-JP-91002 JPM STEPS START TIME:

TIME CRITICAL STEP 1 CRITICAL (,)

SAT Oz!

UNSAT OD Initiate roll call Note: The Emergency Response Telephone Directory, or the dial code card, should be consulted as needed for required ENN dial codes. The dial code, *, should be used initially to ring ALL required agencies.

r-IO

Burke County notified CUE Burke County is on the line

-[

GEMA notified CUE GEMA is on the line aD

Aiken County notified CUE Aiken County is on the line

'aD

SRS notified CUE SRS is on the line

'aD

Allendale County notified CUE Allendale County is on the line

'-aD

State of South Carolina notified CUE South Carolina is on the line

'aD

Barnwell County CUE Do not respond when Barnwell County is hailed

NRC-JP-91002 JPM STEPS STEP 2 CRITICAL()

SAT Eie*

UNSAT OA*

Notify Barnwell County

'aD

Commercial telephone line (803) 541-1161 NRC CUE When proper number identified, provide the cue that "Barnwell County has been reached and will responded to ENN."

Nlote: For initial notifications the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months warning point commercial telephone line should be notified.

'&D

Barnwell County directed to respond to ENN STEP 3 SAT De UNSAT De Transmit facsimile Note: On the Fax machine in the Simulator, the pushbutton labeled "NOTIFY(Training)" should be depressed to simulate "NOTIFY", if necessary a cue to the examinee should be provided that for simulation purposes, the "NOTIFY (Training)" pushbutton should be used to transmit the fax.

,aD

Place message face down in transmit tray

'OD

"NOTIFY(Training)" pushbutton depressed

NRC-JP-91002 JPM STEPS STOP TIME:

TIME CRITICAL time stops STEP 4 CRITICAL (,)

SAT Oz UNSAT 02 Communicate notification via ENN 0

Lines 1 & 2 transmitted 0D

Examinee's name provided in Line 2, "Reported By" a02

Line 3, Transmittal time & date completed CUE Simulator operator CUE After completion of Emergency Notification form line 3, provide the following cue, "The State of South Carolina request that you authenticate number 39."

.D

Control Room confirmation phone number transmitted STEP 5 CRITICAL()

SAT Oz UNSAT 02*

Message authentication

-,s~o

Authentication codeword correctly provided.

NOTE For NRC Examiner "39 is mine-sweeper"~

NRC-JP-91002 JPM STEPS Field Notes:

STEP 6 CRITICAL (,)

SAT D**

UNSAT 0,@!

Transmit classification data

'.D

Emergency Classification

'aDI

Emergency declaration time and date

,&D 0

Emergency description STEP 7 CRITICAL (,)

SAT ODe UNSAT 0g Transmit current plant radiological conditions

'aD

Plant condition aD

Emergency rad release status

',D

Current meteorological data

'aD

Recommended protective actions

'kD O ED approval, time, & date STEP 8 SAT D1 UNSAT O1.e Notify ED

'aD

Initial Emergency Notification completed

,5w 4ALf 4

SOUTHERNCA COMPANY Energy to Serve Your World' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-91001 CLASSIFY AN EMERGENCY EVENT - ALERT Revision 0 October 04, 2002 i

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

G THIS IS A TIME CRITICAL JPM 0 Initial Conditions:

The following is the sequence of events as they occurred on Unit 1:

1. Unit 1 is at 100% power

2. Unit 2 is in MODE 5 to replace RCP #1 seal package

3. At 1100 a fire in the Unit 2 protection cabinet channel 1 results in both Control Rooms being evacuated.

4. At 1111 Control is established at the Unit 1 shutdown panels with conditions stable in MODE 3

5. At 1113 Control is established at the Unit 2 shutdown panels with RCS temperature stable at 110 degrees F.

Assigned Task:

You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress, considering past events, and their impact on the current plant conditions".

2

NRC-JP-91001 JPM INFORMATION Evaluation Method [ ] Performed Evaluation Location [

Simulator Performance Time:

minutes OVERALL JPM EVALUATION Examiner Comments:

E ] Simulated

[ ] Control Room

[

Unit 1

[ I SATISFACTORY

[ ] Unit 2

[ ] UNSATISFACTORY Examiner's Signature:

3 OPERATOR'S NAME:

EVALUATION DATE:

I

/

JPM TITLE:

Classify an Emergency Event - ALERT I REVISION:

0 COMPLETION TIME: 15 minutes THIS IS A TIME CRITICAL JPM Application:

SRO ONLY

NRC-JP-91001 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 91001-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "@..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#)

are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

91001-C, Emergency Classification and Implementing Instructions None G THIS IS ATIME CRITICAL JPM G DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

Initial Conditions:

The following is the sequence of events as they occurred on Unit 1:

1. Unit 1 is at 100% power

2. Unit 2 is in MODE 5 to replace RCP #1 seal package

3. At 1100 a fire in the Unit 2 protection cabinet channel 1 results in both control being evacuated.

4. At 1111 Control is established at the Unit 1 shutdown panels with conditions stable in mode 3

5. At 1113 Control is established at the Unit 2 shutdown panels with RCS temperature stable at 110 degrees F.

Assigned Task:

You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress, considering past events, and their impact on the current plant conditions".

4 i

SIMUL OR SETUP:

NRC-JP-91001 JPM STEPS START TIME:

STOP TIME:

Field Notes 5

STEP 1 CRITICAL (,)

SAT 0I"5 UNSAT 02 Classify the event

&o

Plant conditions evaluated aD

Emergency event classified as a ALERT EMERGENCY Per 91001-C figure 1 the fuel cladding barrier is intact figure 2 the RCS barrier is intact figure 3 the Containment barrier is intact figure 4 an ALERT EMERGENCY is declared due to (HAZARDS Column):

Control Room evacuation has been initiated OR Fire in vital area with damage to safety related equipment

SOUTHERNS COMPANY Energy to Serve Your World' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-91001 CLASSIFY AN EMERGENCY EVENT - SCENARIO #1 Revision 0 October 04, 2002 I

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

This is a TIME CRITICAL JPM Initial Conditions:

Classify the Scenario.

Assigned Task:

You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress, considering past events, and their impact on the current plant conditions".

2

NRC-JP-91001 JPM INFORMATION Evaluation Method [

Performed Evaluation Location [

Simulator Performance Time:

minutes

[

Simulated Control Room

[

Unit 1 OVERALL JPM EVALUATION

[

SATISFACTORY

[

UNSATISFACTORY Examiner Comments:

Examiner's Signature:

3 OPERATOR'S NAME:

EVALUATION DATE:

I I

JPM TITLE:

CLASSIFY AN EMERGENCY EVENT - SCENARIO #1 REVISION:

0 COMPLETION TIME: 15 minutes This is a TIME CRITICAL JPM Application:

SRO ONLY

[ ] Unit 2 i

NRC-JP-91001 INSTRUCTIONS TO EXAMINER DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

This is a TIME CRITICAL JPM Initial Conditions:

Classify the Scenario.

Assigned Task:

You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress, considering past events, and their impact on the current plant conditions".

4 This JPM is based on the latest rev of 91001-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#)

are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

1.

91001-C, Emergency Classification and Implementing Instructions SIMULATOR SETUP:

None i

i

NRC-JP-91001 JPM STEPS START TIME:

STOP TIME:

Field Notes 5

STEP 1 CRITICAL (,)

SAT DO UNSAT OD Classify the event 1-4&

Plant conditions evaluated a0

Emergency event classified as a SITE AREA EMERGENCY Per 91001-C figure 1 the fuel cladding barrier potential loss figure 2 the RCS barrier potential loss figure 3 the Containment barrier is intact figure 4 an SITE AREA EMERGENCY is declared due to (Barrier Column):

Potential loss of both the fuel clad and RCS barriers Also SITE AREA EMERGENCY is declared due to (Plant Systems Column)

Mode 1 & 2 Automatic reactor trip setpoint exceeded and reactor could not be tripped from the control room.

4 SOUTHERNSi COMPANY Energy to Serve Your World PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-91001 CLASSIFY AN EMERGENCY EVENT - SCENARIO #2 Revision 0 October 04, 2002

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

This is a TIME CRITICAL JPM Initial Conditions:

Classify the Scenario.

Assigned Task:

You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress, considering past events, and their impact on the current plant conditions".

2

NRC-JP-91001 JPM INFORMATION 3

OPERATOR'S NAME:

EVALUATION DATE: __I

/

JPM TITLE:

CLASSIFY AN EMERGENCY EVENT-- SCENARIO #2 REVISION:

0 COMPLETION TIME: 15 minutes This is a TIME CRITICAL JPM Application:

SRO ONLY i

NRC-JP-91001 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 91001-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#)

are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

91001-C, Emergency Classification and Implementing Instructions None DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

This is a TIME CRITICAL JPM Initial Conditions:

Classify the Scenario.

Assigned Task:

You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress, considering past events, and their impact on the current plant conditions".

4 i

NRC-JP-91001 JPM STEPS START TIME:

STOP TIME:

Field Notes 5

STEP 1 CRITICAL (,)

SAT D02 UNSAT 0D*

Classify the event

-e

s Plant conditions evaluated zaD

Emergency event classified as a ALERT EMERGENCY Per 91001-C figure 1 the fuel cladding barrier is intact figure 2 the RCS barrier potential OR loss of the RCS barrier*

figure 3 the Containment barrier is intact figure 4 an ALERT EMERGENCY is declared due to (Barriers Column):

Loss OR potential loss of the RCS barrier

RCS leak >Capacity of charging pump OR

RCS leak in progress and subcooling <24 F.

SOUTHERNSA COMPANY Energy to Serve Your World' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-91001 CLASSIFY AN EMERGENCY EVENT - SCENARIO #3 Revision 0 October 04, 2002

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

This is a TIME CRITICAL JPM Initial Conditions:

Classify the Scenario.

Assigned Task:

You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress, considering past events, and their impact on the current plant conditions".

2

NRC-JP-91001 JPM INFORMATION Evaluation Method [] Performed Evaluation Location [

Simulator Performance Time:

minutes

] Simulated

] Control Room

[ ] Unit 1 OVERALL JPM EVALUATION

[

SATISFACTORY

[

UNSATISFACTORY Examiner Comments:

Examiner's Signature:

3 OPERATOR'S NAME:

EVALUATION DATE:

I I

JPM TITLE:

CLASSIFY AN EMERGENCY EVENT - SCENARIO #3 REVISION:

0 COMPLETION TIME: 15 minutes This is a TIME CRITICAL JPM Application:

SRO ONLY

[ ] Unit 2 i

NRC-JP-91001 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 91001-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#)

are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

91001-C, Emergency Classification and Implementing Instructions None DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

This is a TIME CRITICAL JPM Initial Conditions:

Classify the Scenario.

Assigned Task:

You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress, considering past events, and their impact on the current plant conditions".

4

NRC-JP-91001 JPM STEPS START TIME:

STOP TIME:

Field Notes 5

STEP 1 CRITICAL (,)

SAT O-z UNSAT O7e Classify the event r-IsD e Plant conditions evaluated 1-s.

Emergency event classified as a ALERT EMERGENCY Per 91001-C figure 1 the fuel cladding barrier is intact figure 2 the RCS barrier potential OR loss of the RCS barrier*

figure 3 the Containment barrier is intact figure 4 an ALERT EMERGENCY is declared due to (Barriers Column):

Loss OR potential loss of the RCS barrier

RCS leak >Capacity of charging pump OR

RCS leak in progress and subcooling <24 F.

SOUTHERN Sn COMPANY Energy to Serve Your World' PLANT VOGTLE CONTROL ROOM OPERATOR JOB PERFORMANCE MEASURE NRC-JP-91001 CLASSIFY AN EMERGENCY EVENT - SCENARIO #4 Revision 0 October 04, 2002 i

This information describes the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the task before beginning. You will be allowed access to any item normally used to perform this task.

This is a TIME CRITICAL JPM Initial Conditions:

Classify the Scenario.

Assigned Task:

You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress, considering past events, and their impact on the current plant conditions".

2

NRC-JP-91001 JPM INFORMATION 3

OPERATOR'S NAME:

EVALUATION DATE:

I

/

JPM TITLE:

CLASSIFY AN EMERGENCY EVENT - SCENARIO #4 REVISION:

0 COMPLETION TIME: 15 minutes This is a TIME CRITICAL JPM Application:

SRO ONLY Evaluation Method [ ] Performed

[ ] Simulated Evaluation Location [

Simulator

[

Control Room

[

Unit 1

[

Unit 2 Performance Time:

minutes OVERALL JPM EVALUATION

[ ] SATISFACTORY

[

UNSATISFACTORY Examiner Comments:

Examiner's Signature:

NRC-JP-91001 INSTRUCTIONS TO EXAMINER This JPM is based on the latest rev of 91001-C. Verify this JPM is in accord with the latest procedural revision prior to use. Cues preceded by a "©..." are provided to enhance simulation of this JPM and should only be used when the simulator is unavailable. Cues designated by (#)

are to be provided to the examinee during the performance of this JPM.

REQUIRED ITEMS:

SIMULATOR SETUP:

1.

91001-C, Emergency Classification and Implementing Instructions None DIRECTIONS TO OPERATOR You will be given information describing the Initial Conditions, Assigned Task, and the Task Standard. Please ensure you understand the assigned task before beginning. You will be allowed access to any item normally used to perform this task.

This is a TIME CRITICAL JPM Initial Conditions:

Classify the Scenario.

Assigned Task:

You have been directed to "Determine the HIGHEST emergency classification level based on events which are in progress, considering past events, and their impact on the current plant conditions".

4 i

NRC-JP-91001 JPM STEPS START TIME:

STEP 1 CRITICAL (,)

SAT D, UNSAT 0@

Classify the event

,s-I Plant conditions evaluated 1-1[

Emergency event classified as a NOUE EMERGENCY Per 91001-C figure 1 the fuel cladding barrier is intact figure 2 the RCS barrier is intact figure 3 the Containment barrier is intact figure 4 an NOUE EMERGENCY is declared due to (Other Column):

Uncontrolled depressurization of one or more Steam Generators STOP TIME:

Field Notes 5

ML030560832

Text

Description:

Description:

Navigation menu

Search