ML082390016

TASK COMPLETION TIMES

Validation Time =

24 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

02/28/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 7

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

R709

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under- no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the reactor operator level.

INITIAL CONDITIONS

Power reduction was in progress per 1-PT-34.3, Turbine valve Freedom Test when a dropped rod

occurred.

The Unit has been stabilized at 85% power with Tavg and Tref matched.

Unit 1 PCS is unavailable.

All ex-core power-range channels are operable.

The Instrument Shop has obtained power range detector current readings.

02/28/08

Page 3 of 7

A copy of 1-PT-22.4, Attachment 4, Unit 1 Power Range Calibration Data is available.

INITIATING CUE

You are requested to perform a Quadrant Power Tilt Ratio determination by hand calculation in

accordance with 1-PT-23, Quadrant Power Tilt Ratio Determination.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Calculator

Copy of 1-PT-22.4, Attachment 4, Unit 1 Power Range Calibration Data.

Evaluator will need a copy of Technical Specifications and Bases for performance of

elements 5 and 6 of this evaluation.

PERFORMANCE STEPS

START TIME

o::::::::=J Record the expected 100% power current readings in attachment 2.1 Procedure Step

ISAT [)

UNSAT []

02/28/08

IStandards

roteS/Comments

IData correctly transcribed from the coPy of 1-PT-22.4 provided.

Page 4 of 7

~l Calculate the normalized detector currents and averages.

IProcedure Step

ISAT []

UNSAT []

I....S_ta...n..d..a_rd..s,--__1Normalized detector currents and averages are calculated.

INoles/Commenls

~ Calculate the quadrant power tilt ratios.

IProcedure Step

'_C_ri_ti_ca_I_S_te--'p'--

1SAT []

UNSAT [ ]

Standards

INotes/Comments

02/28/08

Upper and lower quadrant power tilt ratios are calculated.

~ Individual QPTRs determined per the acceptance criteria of the

attached answer key

AND

~ Maximum QPTR determined to be 1.03738

acceptance criteria: 1.03638 to 1.03838 (+/- 0.001)

Page 50f7

Record the value and location of the largest quadrant power tilt

ratio.

Procedure Step __

l.---

ISAT []

UNSAT []

Standards

Value transcribed from previous step.

Location recorded is N43L.

Notes/Comments

The following elements take place one-on-one with the evaluator,

after the candidate has completed the QPTR calculation in the

classroom.

EVALUATOR'S NOTE

IF QPTR calculations are correct, THEN continue the JPM, otherwise JPM should be terminated at

this point.

~ Identifies QPTR exceeds maximum permissible value of 1.02.

IProcedure Step

ISAT []

UNSAT []

02/28/08

Evaluator's Note

Provide candidate with Technical Specifications and Bases for use in

com letin

this element and element 6.

Demonstration

Ask the applicant to identify whether the acceptance criteria of 1-PT-23

Cues

are met.

Standards

Technical Specification 3.2.4 is identified and QPTR determined to

exceed the LCO 3.2.4 based on given conditions (thermal power of

>50% RTP provided in the IC, so TS 3.2.4 Applicability is met).

rotes/comments

Page 6 of 7

~ Determine maximum allowable power level per TS 3.2.4.

IProcedure Step

I_C_ri_ti_ca_I_S_t---'epL-

1SAT []

UNSAT []

Evaluator's Note

IF the candidate calculated a QPTR of ~ 1.02 and determined that the

LCO was met in element 5, THEN end the evaluation at this point.

IF the candidate calculated a QPTR of ~ 1.02 and determined that the

LCO was NOT met in element 5, THEN provide the following cue.

Demonstration

Cues

Standards

rotes/comments

STOP TIME

02/28/08

Ask the applicant to calculate the maximum power level allowed by

Technical Specification 3.2.4, based on the QPTR.

Maximum power level determined to be 88.79%

(from TS 3.2.4 power must be reduced ~ 3% from RTP for each 1% of

QPTR> 1.00. Therefore 3.738% X 3 = 11.214).

For conservatism power may be rounded down to 88%; based on the

acceptance criteria of element 3 the upper range is 89.086% (rounding

to 89.1 is acceptable).

>>>>> END OF EVALUATION <<<<<

Page 7 of7

QPTR Calculation - Key

DETECTOR

EXPECTED

ACTUAL

NORMALIZED

TILT RATIO

Range (MIN)

Range (MAX)

N41U

156.6

131

0.836526

1.00174

1.00074

1.00274

N41L

184.6

155

0.839653

1.00001

0.99901

1.00101

N42U

165.1

138

0.835857

1.00094

0.99994

1.00194

N42L

167.8

141

0.840286

1.00076

0.99976

1.00176

N43U

167.6

145

0.865155

1.03603

1.03503

1.03703

- -~f

L':-

,-

N43L

. ,

207.8

181

0.871030

1.03738

.*J'

1.03638

1.03838

. -,

-

.~-

-..

N44U

204.3

164

0.802741

0.96129

0.96029

0.96229

N44L

220.4

178

0.807623

0.96186

0.96086

0.96286

Maximum power level based on tilt

88.79

..

..'

\\-)

'.U'

If

....,

,

...

"'.".'

~

",.....

/.

DOMINION

/

North Anna Power Station

1(... ",,--

.,!

)jft==.

Unit :1

1-PT*22.4

Revision 13

Page 27 of 29

,.....,(Page 301'*"4)1*--...'--"""--'-....*....., .'-'-'-=..w...........~-=..................

_~'..;p--.~..........~.......__~c..'.,:........_""'

...........,.,

...,

Attachment 4

Power Range Calibration Data

PCS POINTS

Please enter the following PeS Computer Point values to reflect changes when the Power Range detectors.

are calibrated AND initial the appropriate spaces. IF the PCS computer is inoperable, THEN mark the

corresponding blanks N/A:

y

t4(

PCS

Updated

PCS

4-

~

£

1Y1L

PCS

Updated

. b~'

U

to .:-tf>'07

Date

ISb.b -

167.8

'2olf. 3

'J

, lbr. l

(8.6120

l ..>b'2-'t .

Reviewed By

K0552 InlExcore Offset Ratio (Ch42, Q2):

K05531n1Excore Offset Ratio (Ch43, QI):

K0554 InlExcore Offset Ratio (Ch44, Q3):

2.

AFD Calibration Constant Values:

K0855.DF Calibration Constant for N41:

K0856 DF Calibration Constant for N42:

K0857 DF ~alibrati6n Constant for N43:

K0858 DF Calibration Constant for N44:

3.

I"core Versus Excore Axial Offset Slope Values:

K055 I InlExcore Offset Ratio (Ch41, Q4):

1.

Expected Current Values:

K0821 N41 Upper 100% Expected Current:

'

K0822 N41 Lower 100% Expected Current:

K0823 N42 Upper 100% Expected Current:

K0824 N42 Lower 100% Expected Current:

K0825 N43 Upper 100% Expected Current:

K0826 N43 Lower 100% Expected Current:

K0827 N44 Upper 100% Expected,Current:

K0828 N44 Lower 100% Expected Current:

Instrument Department

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

The unit was shutdown 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months ago.

RHR flow is 3600 gpm.

RCS draindown was in progress with the following equipment in operation:

1 RHR pump

2 RHR Heat exchangers

1 Charging pump

The crew has implemented 1-AP-11, Loss of RHR and is at step 4b.

INITIATING CUE

Using 1-AP-11, Loss of RHR, determine the following:

1.

Minimum required RHR flow.

2.

Level that RHR pumps are required to be stopped based on minimum required RHR flow.

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

Determine minimum required RHR flow and RCS level.

TASK STANDARDS

Given a copy of 1-AP-11, Loss of RHR, the examinee will determine:

Minimum required RHR flow based on time after shutdown.

Minimum RCS level to support continued RHR pump operation based on minimum flow rate.

KIA REFERENCE:

G2.1.25 (3.9/4.2)

ALTERNATE PATH:

TASK COMPLETION TIMES

Validation Time =

10 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

[ ] SATISFACTORY

Page 2 of6

[ ] UNSATISFACTORY

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

INITIAL CONDITIONS

The unit was shutdown 200 hours0.00231 days 0.0556 hours 3.306878e-4 weeks 7.61e-5 months ' ago.

RHR flow is 3600 gpm.

RCS draindown was in progress with the following equipment in operation:

1 RHR pump

2 RHR Heat exchangers

1 Charging pump

The crew has implemented 1-AP-11, Loss of RHR and is at step 4b.

Page 3 of6

INITIATING CUE

The task you are to perform is:

Using 1-AP-11, Loss of RHR, determine the following:

Minimum required RHR flow.

Level that RHR pumps are required to be stopped based on minimum required RHR flow.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Calculator

Copy of 1-AP-11. Loss of RHR, signed off up to Step 4b.

PERFORMANCE STEPS

START TIME

rr=::::J Convert hours to days for use on att.3

IProcedure Step

ISAT []

UNSAT []

Standards

INotes/Comments:

Operator determines time after shutdown for use on attachment 3 is

8.33 days (200 hrs/24hrs per day =8.33 days).

Page 4 of6

lr=J Determine minimum required RHR flow

IProcedure Step: Att.3

'_C_ri_ti_ca__s_te--'p'----

1SAT []

UNSAT []

Standards

Operator determines minimum f10wrate of 2425 gpm.

Acceptance criteria of 2400-2500 gpm based on readability and

figure minor increments of 200 gpm.

Notes/Comments:

Operator will arrive at a value of approximately 3400 gpm if the incorrect

figure in AU. 3 is used.

Determine level that RHR pumps are required to be stopped based

Procedure Step: Att.2

on minimum re uired RHR flow.

I-:.C~ri:..:::ti_=_ca=I--=S:....:.te..:..Jpl:.....-

1SAT []

UNSAT []

Standards

INotes/Comments:

STOP TIME

Operator determines minimum level of 7.05 in. above CL.

Acceptance criteria of 7.0 inches to 7.2 inches based on

acceptance criteria for flow rate from previous step, and readability

and figure minor increments of 0.2".

>>>>> END OF EVALUATION <<<<<

Page 5 of6

CHECKLIST

Calculator

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

Page 6 of6

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

The Unit is in MODE 3 at normal operating temperature and pressure with preparations in progress

for taking the Reactor Critical.

Pressurizer Pressure Controls are in automatic and all PORVs and Block valves are OPERABLE.

1-PT-44.7, PORV Block Valves has been initiated.

The operator has stopped the procedure at Step 6.11 because the thermal overload on the breaker

for 1-RC-MOV-1535 actuated when the control switch for 1-RC-MOV-1535 was taken to close.

The cause of 1-RC-MOV-1535 thermal overload device actuation has not yet been determined.

The Safeguards operator who was dispatched to the breaker has asked the OATC if he should reset

the breaker for 1-RC-MOV-1535 at this time.

INITIATING CUE

You are requested to determine the following:

1)

Technical Specification action requirements if applicable.

2)

Whether or not the Safeguards operator should be directed to reset the breaker for

1-RC-MOV-1535.

3)

If Reactor can be taken critical (SRO ONLY).

02/25/08

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

NEW

Apply Tech Specs.

TASK STANDARDS

Applicable Tech Spec Actions are identified, including action that prohibits Mode change (SRO

ONLY), and determination is made not to continue testing on opposite train equipment.

KIA REFERENCE:

G-2.2.40 (3.4/4.7)

ALTERNATE PATH:

TASK COMPLETION TIMES

Validation Time =

20 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

02/25/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 7

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

NEW

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the Reactor Operator level or

Senior Reactor Operator level as applicable.

.

INITIAL CONDITIONS

The Unit is in MODE 3 at normal operating temperature and pressure with preparations in progress

for taking the Reactor Critical.

Pressurizer Pressure Controls are in automatic and all PORVs and Block valves are OPERABLE.

1-PT-44.7, PORV Block Valves has been initiated.

The operator has stopped the procedure at Step 6.11 because the thermal overload on the breaker

for 1-RC-MOV-1535 actuated when the control switch for 1-RC-MOV-1535 was taken to close.

02/25/08

Page 3 of 7

The cause of 1-RC-MOV-1535 thermal overload device actuation has not yet been determined.

The Safeguards operator who was dispatched to the breaker has asked the OATC if he should reset

the breaker for 1-RC-MOV-1535 at this time.

INITIATING CUE

You are requested to determine the following:

1)

Technical Specification action requirements if applicable.

4)

Whether or not the Safeguards operator should be directed to reset the breaker for

1-RC-MOV-1535.

2)

If Reactor can be taken critical (SRO ONLY).

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Provide trainee copy of 1-PT-44.7, signed off to step 6.11 for reference.

Technical Specifications and Bases

PERFORMANCE STEPS

START TIME

02/25/08

Page 4 of 7

Recognizes condition is entry condition for Technical

S ecifications.

Procedure Step __

ISAT []

UNSAT []

Standards

Technical Specifications require BOTH PORV Block Valves operable in

Modes 1 thru 3. Actuation of the thermal overload device renders

1-RC-MOV-1535 inoperable.

INotes/Comments

~I Review Tech Specs and determine TS 3.4.11.0. applies.

IProcedure Step

ICritical Step

ISAT[]

UNSAT[]

'-------'--------------------

Standards

Determines the following actions apply:

1) Place associated PORV (1-RC-PCV-1456) in manual control -7 1 hr.

and

2) Restore Block Valve to OPERABLE status -7 72 hrs.

INotes/Comments

02/25/08

Page 5 of 7

Determine whether or not the Safeguards operator should be

directed to reset the breaker for 1-RC-MOV-1535.

Procedure Step __

ISAT[]

UNSAT[]

'--------------------

ICritical Step

Standards

Determination is made NOT to reset the breaker at this time. In

accordance with OP-AA-100-1000, Shift Operations, During normal

operations the Shift Manager (ONLY) may authorize resetting of a

tripped circuit breaker, protective relay, or one-time fuse replacement

AFTER determining that a fault DOES NOT exist. For the conditions

given (cause not yet determined) resetting the breaker at this time

would violate the procedure requirement of OP-AA-100-1000.

Notes/Comments

IF the candidate is an RO candidate THEN the Evaluation ends at

this point.

Determines Reactor can not be taken critical (Mode change not

ermitted based on information

rovided.

Procedure Step __

I_C_ri_ti_c_al_S_t_e-'-p

1SAT []

UNSAT []

Standards

Determines based on review of Tech Spec LCO 3.0.4 that Reactor can

NOT be taken critical at this time since the mode change is prohibited

by Tech Specs.

Notes/Comments

This Step is applicable to and thus ONLY critical for the ISRO or

USRO candidates.

>>>>> END OF EVALUATION <<<<<

STOP TIME

02/25/08

Page 6 of 7

None

02/25/08

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

Page 7 of 7

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

Unit shutdown was commenced due to primary to secondary leakage in the B SG.

At 80% power, operators initiated a manual trip due to inability to maintain

Pressurizer level and pressure.

Prior to the trip, 1-CH-RI-128, Reactor Coolant Letdown Radiation Monitor, was reading

6 X104 mRlhr and had been steadily increasing over the last hour.

Operators isolated AFW flow to B SG due to level increasing uncontrollably following the trip.

A Safety valve on the B SG has opened and failed to reseat.

Pressurizer level is off-scale low.

All safeguards equipment is functioning as designed and offsite power is available.

Emergency Response Organization response has been delayed due to icy roads and a

severe winter storm.

INITIATING CUE

You are requested to classify the emergency event and determine any Protective Action

Recommendation if required.

This is a time critical JPM.

02/25/08

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

NEW

Classify event and determine PAR.

TASK STANDARDS

Event is classified as a General Emergency in accordance with EPIP-1.01, TAB B.2; classification is

required to be made within 15 minutes of starting the evaluation.

Protective Action Recommendation determined is PAR A (shelter in place 2 Mile radius and 5 Miles

downwind) selected due to known impediments making evacuation dangerous; PAR is selected

within 14 minutes from the time the Emergency Classification is made.

KIA REFERENCE:

GEN-2.4.41 (2.9/4.6)

GEN-2.4.44 (2.4/4.4)

ALTERNATE PATH:

N/A

TASK COMPLETION TIMES

Validation Time =

12 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

02/25/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 8

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

NEW

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the Senior Reactor Operator

level.

INITIAL CONDITIONS

Unit shutdown was commenced due to primary to secondary leakage in the B SG.

At 80% power, operators initiated a manual trip due to inability to maintain

Pressurizer level and pressure.

Prior to the trip, 1-CH-RI-128, Reactor Coolant Letdown Radiation Monitor, was reading

6 X104 mR/hr and had been steadily increasing over the last hour.

Operators isolated AFW flow to B SG due to level increasing uncontrollably following the trip.

02/25/08

Page 3 of 8

A Safety valve on the B SG has opened and failed to reseat.

Pressurizer level is off-scale low.

All safeguards equipment is functioning as designed and offsite power is available.

Emergency Response Organization response has been delayed due to icy roads and a

severe winter storm.

INITIATING CUE

You are requested to classify the emergency event and determine any Protective Action

Recommendation if required.

This is a time critical JPM.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

None

PERFORMANCE STEPS

START TIME

START TIME IS CRITICAL: Start time begins the 15 minute clock for event

classification (clock stops when classification is made - element 4 of JPM).

02/25/08

Page 4 of 8

Determine the event category using the emergency action level

table index.

Procedure Step __

I_C_ri_ti_c_al_S_t_e!-p

,SAT []

UNSAT []

Standards

[Notes/Comments

Event is identified as a RCS EVENT, Tab B, Attachment 1 of

EPIP-1.01.

Review the emergency action level tab associated with the event

cate 0

.

Procedure Step __

ISAT []

UNSAT []

1L,;;~;,,;;ta;;,;n_d;,;;a;,;,,;rd;;,;;s"----__1Tab B reviewed to determine highest level of classification.

[Notes/Comments

Use available resources to obtain indications of emergency

conditions.

Procedure Step __

ISAT[]

UNSAT[]

I...;;;;S~ta;:.:.n~d~a:.;,;rd:.;;;s~__1Tab B indications compared to Initial Conditions provided in JPM.

INotes/Comments

02/25/08

Page 5 of 8

~ Classify event based on emergency action level being exceeded.

IProcedure Step

ICritical step

ISAT []

UNSAT []

Standards

Notes/Comments

Event is classified as a General Emergency lAW TAB B.2 within 15

minutes of the start of the evaluation.

Record time of declaration here

. This time begins the

14 minute clock for selecting the PAR (element 6 of JPM).

Record time to make classification:

Declaration Time

________ =

minutes

Evaluation Start time

Total Time to classify

Classification is required to be less than or equal to 15 minutes from

the start of the evaluation.

Identify Protective Action Recommendation (PAR) is applicable

based on exceedin

action level for General Emer enc .

Procedure Step __

ISAT []

UNSAT []

02/25/08

Standards

INotes/Comments

EPIP-1.06 Protective Action Recommendation Matrix compared to

Initial Conditions

rovided in JPM.

Page 6 of 8

~I Determine Protective Action Recommendation.

IProcedure Step

I~C...:....ri--:...ti--:...c=al_S:......:t:..::...e.!-p

1SAT []

UNSAT []

Standards

Notes/Comments

Protective Action Recommendation from EPIP-1.06 is PAR A (based on

known impediments make evacuation dangerous), and is selected

within 14 minutes of the event classification (element 4 of JPM).

Record time of PAR selection here:------

Record time to make PAR:

PAR selection Time

_______ =

minutes

Declaration Time

Time required to

(element 4 of JPM)

select PAR

STOP TIME

02/25/08

PAR selection is required to be less than or equal to 14 minutes from

the time of classification (element 4 of JPM).

>>>>> END OF EVALUATION <<<<<

Page 7 of 8

None

02/25/08

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

Page 8 of 8

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

Unit 2 is in Mode 4 exiting a scheduled Refueling Outage.

You have been assigned to assist Craft and Engineering personnel with an emergent work item.

The work will be performed in the vicinity of "A" RHR Heat Exchanger.

Your dose for the year is 300 mrem (all dose has been received at North Anna Site).

No extensions or exemptions have been granted for the entry.

INITIATING CUE

You have been directed to select the appropriate RWP from those provided.

Using the Survey Map provided, calculate your maximum allowable Stay Time in accordance with all

HP Administrative Dose Limits and RWP requirements.

(Assume that all work will take place in the highest dose area adjacent to the "A" RHR Heat

Exchanger AND that dose received in transit to and from the work location is negligible).

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

Determine appropriate RWP and Stay Time.

TASK STANDARDS

Given a choice of RWPs, candidate selects the appropriate RWP for Task performance.

Given a survey map candidate correctly calculates maximum allowable Stay Time.

KIA REFERENCE:

G2.3.7 (3.5/3.6)

ALTERNATE PATH:

LHRA = Locked High Radiation Area

TASK COMPLETION TIMES

Validation Time =

15 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

[ ] SATISFACTORY

Page 2 of6

[ ] UNSATISFACTORY

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

reqUired communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

INITIAL CONDITIONS

Unit 2 is in Mode 4 exiting a scheduled Refueling Outage.

You have been assigned to assist Craft and Engineering personnel with an emergent work item.

The work will be performed in the vicinity of "A" RHR Heat Exchanger.

Your dose for the year is 300 mrem (all dose has been received at North Anna Site).

No extensions or exemptions have been granted for the entry.

Page 3 of6

INITIATING CUE

You have been directed to select the appropriate RWP from those provided

Using the Survey Map provided, calculate your maximum allowable Stay Time in accordance with all

HP Administrative Dose Limits and RWP requirements.

(Assume that all work will take place in the highest dose area adjacent to the "A" RHR Heat

Exchanger AND that dose received in transit to and from the work location is negligible).

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

RWPs to select from

Survey map of work area

Calculator

PERFORMANCE STEPS

START TIME

Page 4 of6

Select appropriate RWP

Procedure Step

ICritical Step

ISAT []

UNSAT []

Standards

Operator selects RWP 08-1502-1

INotes/Comments:

~I Calculate maximum allowable Stay Time

ICritical Step

IProcedure Step

ISAT []

UNSAT []

IStandards

I*Operator calculates 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months as maximum Stay Time.

Notes/Comments

Answer may be expressed in equivalent units (e.g. 240 minutes)

As given in the instructions using the maximum dose rate in the vicinity

of "A" RHR Heat Exchanger the candidate will determine a dose rate of

50 mrem/hr.

Per the RWP the dose limit is 200 mrem. Therefore 200/50 =4 hours.

Selecting an incorrect RWP would yield a plausible but incorrect Stay

Time.

>>>>> END OF EVALUATION <<<<<

STOP TIME

Page 5 of6

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

ADMINISTRATIVE JOB PERFORMANCE MEASURE

Determine appropriate RWP and Stay Time.

CHECKLIST

Survey Map

Selection of RWPs for the candidate to chose from

Calculator

Page 6 of6

unrr L. l"OnlalnmenI,

L.~*I

RHR Flat

I

~L~

~

VHRA =Very High Radiation Area

HPA =Hot Particle Area

CA =Contaminated Area

HRA = High Radiation Area

ARA = Airborne Radioactivity Area

RA = Radiation Area

RMA = Radioactive Material Area

RCA = Radiological Control Area

"*** Radiological Boundary

it*

I

.

r:nnt~r.t ~nrt An r:m

~::amm::ll nnea I;'~.o J:1o.~:)I*Hnru~*

t:levallon

CAM =Continuous Air Monitor

SOP = Step Off Pad

LDWA =Low Dose Waiting Area

NEA = Neutron Exposure Area

N = Neutron Dose Rate

.u.tl_,,~

.l_....IF"\\~*

-

eaSkNumber

1 .OF 1

HP*1081.022ATI.1 (REV 0)

VALID FROM

01-JAN-200809:26

TO 01*DEC-2008 23:59

08-1502-1

REV. NO 0

DOSE RATE ALARM:

1000

mremlHr

BUDGETED DOSE: 600

mrem

DOSE LIMIT ALARM:

200

mrem

ALARA EVALUATION NO:

JOB LOCATIONS:

UNIT 1 & UNIT2 REACTOR CONTAINMENTS.

JOB DESCRIPTION:

General entry during subatmospheric conditions for the purpose of walkdowns, Inspections,

radiological surveys, minor maintenance and adjustments.

THE MAXIMUM POSTED AREA THAT CAN BE ENTERED:

High Radiation Area>15 Remlhr. and <500 Remlhr

RADIOLOGICAL CONDITIONS:*lndicates estimated value for RWP Preparation. See survey forms for details

GENERAL AREA RADIATION LEVELS (mremlhr):

1.0 to 15,000.*

CONTACT/HOT SPOT RADIATION LEVELS (mremlhr):

1,000 to 20,000.*

CONTAMINATION LEVELS (dpm/100cm2):

1,000 to*100,000.*

AIRBORNE RADIOACTIVITY (DAC):

>0.30 *

REQUIRED JOB COVERAGE:

CONTINUOUS

DOSIMETRY REQUIREMENTS:

DADJSRD

TLD

DOSIMETRY COMMENTS:

1.0)Caution: If PAM(DAD) is utilized, ensure PAM(DAD) is

secured 80 that individual can feel the vibration if

PAH(DAD) alarms.

2.0)An alternate means of DAD alarm recognition is

required whenl

2.1)A DAD will be utilized to meet the Technical

specification requirements for entry into a High

Radiation Area or Locked High Radiation Area,

2.2)The area to be entered requires hearing

protection, or the ability to hear DAD alarms may

be hindered by other circumstances (i.e., headset

use, hearing loss).

PROTECTIVE CLOTHING REQUIREMENTS:

1.0)Required protective Clothing:

One Hood

One Pair Coveralls

Rubber Boots

High Top Shoe Covers

Cotton Inserts

One Pair Rubber Gloves

2.0)protective Clothing requirements may be modified by HPSS.

RESPIRATORY REQUIREMENTS:

SCBA

1.0)SCBA,

35% oxygen.

ORIGINAL

Page

2

eaSkNumber

1

OF 1

HP*1081.022 ATr.1 (REV 0)

A RWP PRE-JOB BRIEFING IS REQUIRED:

BRIEFED BY AN HP SUPERVISOR AND SIGN ATTENDANCE SHEET

WORKER INSTRUCTIONS:

1.0)Upon receiving any Dad alarm, ensure equipment is left in a safe condition and

leave the area and report to the Health Physics office.

2.0)A peer check is required upon issuance of DAD to ensure the correct RWP is

selected. This should be accomplished at the dosimetry issue point. The peer

check may be performed by a co-worker, by Health Physics using the BXS-20

EMSN viewer located in the UP Office, or by the HPCC if a telemetric

DAD is used.

3.0)A11 entries into Containment under this RWP will be

XAW VPAP-0106.

4.0)Mini~ize time in High Dose Rate Areas.

5.0)Xf telemetric DAD is used then check in with HP after the telemetric DAD has

been issued to verify that it is transmitting properly.

6.0)No entry into any overhead area of the RCA will be made unless HP has evaluated

the radiological conditions in the area and approved the entry.

HEALTH PHYSICS INSTRUCTIONS:

1.0)CAUTXON:

unit 1 and unit 2 Reactor Containments have posted *very High Radiation

Areas.

No entry into -Very High Radiation Areas- are allowed on this RWP.

2.0)Stop work and leave area if whole body dose rates exceed 9000 mrem/hr.

3.0)Radiation survey requirements:

3.1)As determined by HP supervision.

4.0)Air Sample requirements:

4.1)A full set of air samples

(charcoa1,particu1ate,triti~,<< noble gas) will be

required upon initial entry and upon subsequent entries when air sample data

is no longer considered current.

5.0)Contamination Survey requirements:

5.1)As determined by HP Supervision.

6.0)Te1emetric DADs and use of RMS (laptop) will be used for all entries into motor

cubes or loop rooms,

when the unit is at greater than 5 percent power.

7.0)Neutron Dose determination is required for all entries into areas posted as

"Neutron Dose Calculations Required for Entry*. Calculate each worker'S neutron

dose utilizing the "Neutron and Noble Gas Dose Calculation Record-.

8.0)There will be no entries allowed into the loop rooms under this RWP,

when the

unit is at greater than 5 percent power, without permission of the Manager of

Radiation Protection.

9.0)Stay times required when DAD dose rate alarm is set >1000 mRem/hr or for entry

into posted High Radiation Area Exceeding 15 Rem/hr.

10.0)Note: The Health

Phy~ics Supervisor Operations shall approve this RWP.

ORIGINAL

Page

3

_TaSk Number

1

OF 2

HP.1081.022 ATT. 1(REV 0)

VALID FROM

01.JAN-200B 00:00

TO

31.JAN-200B 23:59

08-5229-1

REV. NO 0

DOSE RATE ALARM:

500

mremlHr

BUDGETED DOSE: 50

mrem

DOSE LIMIT ALARM:

100

mrem

ALARA EVALUATION NO: &6=6t4 ~ ,1./l;r!'o7

JOB LOCATiONS:

Station Property excluding Unit 1 Containment.

JOB DESCRIPTION:

Dose rates <500mrem/hr: Routine duties, walkdowns and valve line-ups by Operations personnel.

REQUIRED JOB COVERAGE:

ROUTINE

AIRBORNE RADIOACTIVITY (DAC):

<0.30

~

THE MAXIMUM POSTED AREA THAT CAN BE ENTERED:

High Radiation Area>1000 mRemlhr. and <15000 mRemlhr

RADIOLOGICAL CONDITIONS:~lndlcates estimated value for RWP Preparation. See survey forms for details

GENERAL AREA RADIATION LEVELS (mrem/hr):

See Radiological Status Boards or speclflc surveyform.

CONTACT/HOT SPOT RADIATION LEVELS (mrem/hr):

See Radiological Status Boards or specific survey form

CONTAMINATION LEVELS (dpm/100cm2):

See Radiological Status Boards or specIfic survey form

--------------------------------------

COVERAGE COMMENTS:

1.01Continuous Health Physics coverage,

a worker with

Radiological cratt training and a dose rate

instrument, or a Digital Alarming Dosimeter with a

knowledge ot work area dose rates required for entry

into -High Radiation Area".

2.01Continuous HP coverage for activites in areas with

general area contamination levels >1,000,000

dp1ll/100cm2.

DOSIMETRY REQUIREMENTS:

DAD/SRD

no

DOSIMETRY COMMENTS:

1.0)Caution: If PAM (DADl

is utilized, ensure PAM(DAD) is

8ecured so that individual can feel the vibration if

PAM (DAD) alarms.

2.0)An alternate means of DAD alarm recognition is

required when,

2.1)A DAD will be utilized to meet the Technical

Specification requirements for entry into a High

Radiation Area or Locked High Radiation Area,

2.2)The area to be entered requires hearing

protection, or the ability to hear DAD alarms may

be hindered by other circumatances (i.e., headset

use, hearing loss).

ORIGINAL

Page

2

_Task Number

1

OF 2

HP*1081.022 ATT.1 (REV 0)

PROTECTIVE CLOTHING REQUIREMENTS:

1.0)Required protective clothing,

One Hood

One Pair Coveralls

Rubber Boots

High Top Shoe Covers

Cotton Inaerts

One Pair Rubber Gloves

2.0)protective Clothing requirements may be modified by HPSS.

3.0)protective Clothing requirements as stated are for entry into "Contaminated

Areas" only.

4.0)Lab coat,

ahoe covers,

and gloves may be worn as apecified by the Health physics

Shift Supervisor.

S.O)Facial protection for entry under the grating il required if respiratory

protection is not required as per the Health physics Shift Superviaor.

6.0)Protective Clothing requirement a for

a "Hot Particle Area"

(HPA)

[in addition to

those stated above]

are:

6.1)Hood, gloves, coveralls,

shoe cove'rs and tape all outer aeams.

6.2)Workers interfacing with individuals/equipment in a

HPA -

Gloves and face

shield.

RESPIRATORY REQUIREMENTS:

FFAP

1.0)Reapiratory Protection requirements

will be determined by HPSS.

PAPH

A RWP PRE-JOB BRIEFING IS REQUIRED:

BRIEFED BY AN HP TECHNICIAN AND SIGN ATTENDANCE SHEET

WORKER INSTRUCTIONS:

1.0)Upon receiving any DAD alarm,

ensure equipment is left in a aafe condition and

leave the area and report to the Health physics office.

2.0)A peer check is required upon issuance of DAD to ensure the correct RWP is

selected. Thia should be accomplished at the dosimetry issue point.

The peer

check may be performed by a co-worker, by Health Physics using the HIS-20

EMSN viewer located in the HP Office.

3.0)Workere are reeponsible for notifying the HPSS prior to venting\\draining

systems, that may affect Radiological Conditiona in an area, to ensure proper

Health Physics Monitoring.

4.0)HPA exit instructions,

4.1)Use extreme care in removing PCs and friaking.

4.2)Workera (including those interfacing with workere/equipment in HPA)

are to

proceed directly to the RCA exit for whole body monitoring.

4.2.1)Workers that will remain in the RCA will be monitored by HP upon exiting

the HPA.

5.0)Do not remove any items from a posted "Hot Particle Area" until authorized by

HP-Ops.

6.0)Notify Health Physics prior to setting up any ladder.

7.0)No entry into any overhead area of the RCA will be made unless HP has evaluated

the radiological conditione in the area and approved the entry.

B.O)Unless continuous Health Physics coverage is provided, workers shall read their

SRD/DAD approximately every 15 minutes.

HEALTH PHYSICS INSTRUCTIONS:

1.0)Stop work and leave area if whole body dose rates exceed 500 =Rem/hr.

2.0)"Hot Particle Area"

(HPA) monitoring requirements I

2.1)Workers exposed skin shall be monitored by HP-Ope every two hours (unless

specified by the HPSS) while the workers are in the HPA.

2.2)Personnel monitoring for workers exiting the HPA will consist of a whole body

scan within 1/2 inch using,

2.2.1)RH-14

(with an HP-210 and background lese than 10,000 cpm); or

2.2.2)RO-2

(open window and background less than 1.0 mRem/hr),

and

2.2.3)Worker rel.ase criteria:

a net reading of less than IB,OOO

cpm or less

ORIGINAL

Page

3

than

~.O mRem/hr at 1/2 inch.

3.0lNeutron Dose datermination is required for all entries into areas posted

equivalent to -Neutron Dose Calculation aequired for Entry".

3.1)Heutron Bubble Dosimeter 8hould be used for all lSFSI activities.

3.2lHeutron and Noble Gas Dose CalculatioQ Record should be used for containment

power entries, equipment hatch PTs,

aQd lSPSl work if bubble dosimetry fails

during use or is not available.

4.0)Stay time calculations shall be performed for all activities requiring continuous

coverage *

_Task Number

1

OF 2

HP-1081.022 An. 1 (REV 0)

.1

ORIGINAL

Page

4

kNumber

1

OF 1 *

C-HP-1081.010 An. 1(REV 9)

VALID FROM

01-SEP*200700:00

TO

31-0CT*200723:59

07*3233-1

REV. NO 0

DOSE RATE ALARM:

1000

mrem/Hr

BUDGETED DOSE: 2680

m~<<;!,'11

DOSE LIMIT ALARM:

100

mrem

ALARA EVALUATION NO: eMa.f t:Jm_

D'O ~

JOB LOCATIONS:

U-1 REACTOR CONTAINMENT.

JOB DESCRIPTION:

All activities in support of U*1 Containment Close-out.

THE MAXIMUM POSTED AREA THAT CAN BE ENTERED:

High Radiation Area>1000 mRemlhr. and <15000 mRemlhr

RADIOLOGICAL CONDITIONS:*lndicates estimated value for RWP Preparation. See survey foOO5 for details

GENERAL AREA RADIATION LEVELS (mrem/hr):

See Current RC.A. survey data.

CONTACT/HOT SPOT RADIATION LEVELS (mremlhr):

See Current R.CA survey data.

CONTAMINATION LEVELS (dpm/100cm2):

See Current RCA. survey data..

"Hot Particle Area"

AIRBORNE RADIOACTIVITY (DAC):

< .30 Historic Data:

REQUIRED JOB COVERAGE:

ROUllNE

COVERAGE COMMENTS:

1.0)Continuous Health Physics coverage,

a worker with

Radiological craft training and a dose rate

instrument, or a Digital Alarming Dosimeter with a

knowledge of work area dose rates reqaired for entry

into "High Radiation Area".

.

2.0)When the DAD dose rate alarm is set >1000 mRem/hr

then stay times and continuous HP coverage is

reqaired.

3.0)Continuous UP coverage for activities in areas with

general area contamination levels >1,000,000

dpm/100cm:l.

DOSIMETRY REQUIREMENTS:

OAD/SRO

TLO

DOSIMETRY COMMENTS:

1.0)Caution: If PAM (DAD) is utilized, ensure PAM (DAD) is

secured so that individual can feel the vibration if

PAM (DAD) alarms.

2.0)An alternate meanS of DAD alarm recognition is

reqaired when:

2.1)A DAD will be utilized to meet the Technical

Specification reqairements for entry into a High

Radiation Area or Locked High Radiation Area,

2.2)The area to be entered reqaires hearing

protection, or the ability to hear DAD alarms may

be hindered by other circumstances (i.e., headset

use, hearing loss).

ORIGINAL

Page

2

akNumber

1

OF 1

C-HP-1081.01 0An. 1 (REV 9)

PROTECTIVE CLOTHING REQUIREMENTS:

1.0)Required Protective clothingl

One Hood

One Pair Coveralls

Rubber Boots

High Top Shoe Covers

Cotton Inserts

One pair Rubber Gloves

2.0)Protective Clothing requirements may be modified by HPSS.

3.0)Protective Clothing requirements for a "Hot particle Area"

(HPA)

[in addition to

those stated above] arel

3.1)Hood, gloves, coveralls,

shoe covers and tape all outer seams.

3.2)Workers interfacing with individuals/equipment in a HPA - Gloves and face

shield.

A RWP PRE-JOB BRIEFING IS REQUIRED:

BRIEFED BY AN HP TECHNICIAN AND SIGN AlTENDANCE SHEET

WORKER INSTRUCTIONS:

1.0)Upon receiving any DAD alarm, ensure equipment is left in a safe condition and

leave the area and report to the Health physics office.

2.0)A peer check is required upon issuance of DAD to ensure the correct RWP is

selected. This should be accomplished at the dosimetry issue point. The peer

check may be performed by a co-worker, by Health Physics using the HI8-20

EMSN viewer located in the HP Office, or by the HPCC if a telemetric

DAD is used.

3.0)Do not handle any foreign objects until surveyed by Health Physics.

3.1)Any foreign object identified shall immediately be brought to the attention"

of Health Physics for survey and determination of disposition.

4.0)Review current R.C.A. survey data of work area prior to entry.

4.0)HPA exit instructions:

4.1)Use extreme care in removing PCs and frisking.

4.2)Workers(including those interfacing with workers/equipment in HPA) are to

proceed directly to the RCA exit for whole body monitoring.

4.2.1)Workers that will remain in the RCA will be monitored by HP upon exiting

the BPA.

4.2.1.1)Do not remove any items from BPA until authorized by HP.

S.O)If telemetric DAD is used then check in with HP after the telemetric DAD has

been issued to verify that it is transmitting properly.

6.0)No entry into any overhead area of the RCA will be made unless HP has evaluated

the radiological conditions in the area and approved the entry.

7.0)Unles8 continuous Bealth Physics coverage is provided, workers shall read their

SRD/DAD approximately every 15 minutes.

HEALTH PHYSICS INSTRUCTIONS:

1.0)Stop work and leave area if whole body dose rates> 3,000 mrem/hr.

2.0)Recovering a foreign object with radiation levels exceeding lS rem/hr @ 30 cm is

not allowed under this RWP.

3.0)"Hot Particle Area"

(BPA) monitoring requirements:

3.1)workers exposed skin .shall be monitored by HP-Ops every two hours

(unle8s

specified by the HPSS) while the workers are in the HPA.

3.2)personne l monitoring for workers exiting the HPA will consist of a whole body

scan within 1/2 inch using:

3.2.1)RM-14 (with an BP-210 and background less than 10,000 cpm); or

3.2.2)RO-2

(open window and background less than 1.0 mRem/hr),

and

3.2.3)Worker release criteria:

a net reading of less than 18,000 cpm or less

than 2.0 mRem/hr at 1/2 inch.

4.0)Stay time calculations shall be performed when DAD dose rate alarm is set >1000

mRem/hr and when continuous coverage is required.

ORIGINAL

Page

3

_aSk Number

1

OF 1

HP*1081.022 An. 1(REV 0)

VALID FROM

01.JAN-2008 10:08

TO 01-DEC-2008 23:59

08-1503-1

REV. NO 0

DOSE RATE ALARM:

100

mrem/Hr

BUDGETED DOSE: 12

mrem

DOSE LIMIT ALARM:

10

mrem

ALARA EVALUAnON NO:

JOB LOCATIONS:

UNIT 1 & UNIT 2 PERSONNEL AND EQUIPMENT HATCHES.

JOB DESCRIPTION:

General entry by Operations, Health Physics, Security and assorted craft personnel for the performance

of routine PT"s, surveys, Inspections and corrective maintenance as required.

THE MAXIMUM POSTED AREA THAT CAN BE ENTERED:

High Radiation Area>15 Remlhr. and <500 Remlhr

RADIOLOGICAL CONDITIONS:"lndicates estimated value for RWP Preparation. See survey fonns for details

GENERAL AREA RADIATION LEVELS (mremlhr):

.02 to 10 (Up to 40 neutron inner wall of equipment hatch) "

CONTACT/HOT SPOT RADIATION LEVELS (mremlhr):

none

CONTAMINATION LEVELS (dpm/100cm2):

< 1000"

AIRBORNE RADIOACTIVITY (DAC):

<.30"

REQUIRED JOB COVERAGE:

CONTINUOUS

DOSIMETRY REQUIREMENTS:

DAD/SRD

TlD

DOSIMETRY COMMENTS:

1.0)Caution: If PAM(DAD) is utilized, ensure PAM (DAD) is

secured so that individual can feel the vibration if

PAM (DAD) alarms.

2.0)An alternate means of DAD alarm recognition is

required when:

2.l)A DAD will be utilized to meet the Technical

Specification requirements for entry into a High

Radiation Area or Locked High Radiation Area,

2.2)The area to be entered requires hearing

protection, or the ability to hear DAD alarms may

be hindered by other circumstances (i.e., headset

uae, hearing loss).

PROTECTIVE CLOTHING REQUIREMENTS:

1.0)Required protective Clothing:

One Hood

One Pair Coveralls

Rubber Boota

High TOp Shoe Covers

Cotton Inserts

One Pair Rubber Gloves

2.0)protective Clothing requirements may be modified by HPSS.

3.0)protective Clothing requirements as stated are for entry into *Contaminated

Areas* only.

ORIGINAL

Page

2

eaSkNumber

1

OF 1

HP-1081.022 AlT. 1 (REV O)

A RWP PRE-JOB BRIEFING IS REQUIRED:

BRIEFED BY AN HP SUPERVISOR AND SIGN ATTENDANCE SHEET

WORKER INSTRUCTIONS:

1.0)Upon receiving any Dad alarm, ensure equipment is left in a safe condition and

leave the area and report to the Health Physics office.

2.0)A peer check is required upon issuance of DAD to ensure the correct RWP is

selected. This should be accomplished at the dosimetry issue point. The peer

check may be performed by a co-worker, by Health Physics using the H1S-20

EHSN viewer located in the HP Office, or by the HPCC if a telemetric

DAD is used.

3.0)No entry into the Unit 1 or unit 2 Reactor containments is allowed on this RWP.

4.0)Minimize time.in High Dose Rate Areas.

5.0)No entry into any overhead area of the RCA will be made unless HP has evaluated

the radiological conditions in the area and approved the entry.

HEALTH PHYSICS INSTRUCTIONS:

1.0)CAUTXONI unit 1 and Unit 2 Reactor Containments have posted -Very High Radiation

Areas-.

No entry into -Very High Radiation Areas- is allowed on this RWP.

2.0)Stop work and leave area if whole body dose rates exceed 100 mrem/hr.

3.0)Radiation survey requirements:

3.1)Gamma of areas being accessed as per HPSS.

3.2)Neutron of areas being accessed as per HPSS.

4.0)Neutron Dose determination is required for all entries into areas posted as

-Neutron Dose Calculations Required for Entry-. Calculate each worker'S neutron

dose utilizing the -Neutron and Noble Gas Dose Calculation Record-.

5.0)Stay times are required for entry into posted High Radiation Area Exceeding 15

Rem/hr.

6.0)Anytime the Unit 1 and or Unit 2 Equipment Hatch doors have been opened,

a peer*

check is required to verify that the door is locked.

7.0)Note: The Health Physics Supervisor (Operations) shall approve this RWP.

ORIGINAL

Page

3

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

Unit shutdown was commenced due to primary to secondary leakage in the B SG.

At 80% power, operators initiated a manual trip due to inability to maintain

Pressurizer level and pressure.

Prior to the trip, 1-CH-RI-128, Reactor Coolant Letdown Radiation Monitor, was reading

6 X1 04 mRlhr and had been steadily increasing over the last hour.

Operators isolated AFW flow to B SG due to level increasing uncontrollably following the trip.

A Safety valve on the B SG has opened and failed to reseat.

Pressurizer level is off-scale low.

All safeguards equipment is functioning as designed and offsite power is available.

Emergency Response Organization response has been delayed due to icy roads and a

severe winter storm.

INITIATING CUE

You are requested to classify the emergency event and determine any Protective Action

Recommendation if required.

This is a time critical JPM.

02/25/08

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

NEW

Classify event and determine PAR.

TASK STANDARDS

Event is classified as a General Emergency in accordance with EPIP-1.01, TAB B.2; classification is

required to be made within 15 minutes of starting the evaluation.

Protective Action Recommendation determined is PAR A (shelter in place 2 Mile radius and 5 Miles

downwind) selected due to known impediments making evacuation dangerous; PAR is selected

within 14 minutes from the time the Emergency Classification is made.

KIA REFERENCE:

GEN-2.4.41 (2.9/4.6)

GEN-2.4.44 (2.4/4.4)

ALTERNATE PATH:

N/A

TASK COMPLETION TIMES

Validation Time =

12 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

02/25/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 8

Dominion

North Anna Power Station

ADMINISTRATIVE JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

NEW

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the Senior Reactor Operator

level.

INITIAL CONDITIONS

Unit shutdown was commenced due to primary to secondary leakage in the B SG.

At 80% power, operators initiated a manual trip due to inability to maintain

Pressurizer level and pressure.

Prior to the trip, 1-CH-RI-128, Reactor Coolant Letdown Radiation Monitor, was reading

6 X1 04 mRlhr and had been steadily increasing over the last hour.

Operators isolated AFW flow to B SG due to level increasing uncontrollably following the trip.

02/25/08

Page 3 of 8

A Safety valve on the B SG has opened and failed to reseal.

Pressurizer level is off-scale low.

All safeguards equipment is functioning as designed and offsite power is available.

Emergency Response Organization response has been delayed due to icy roads and a

severe winter storm.

INITIATING CUE

You are requested to classify the emergency event and determine any Protective Action

Recommendation if required.

This is a time critical JPM.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

None

PERFORMANCE STEPS

START TIME

START TIME IS CRITICAL: Start time begins the 15 minute clock for event

classification (clock stops when classification is made - element 4 of JPM).

02/25/08

Page 4 of 8

Determine the event category using the emergency action level

table index.

Procedure Step __

I_C_ri_ti_c_al_S_t_e.!-p

1SAT []

UNSAT []

Standards

rotes/commenls

Event is identified as a RCS EVENT, Tab B, Attachment 1 of

EPIP-1.01.

Review the emergency action level tab associated with the event

cate or .

Procedure Step __

ISAT []

UNSAT []

I...;;;S_ta_n_d...

a_rd;,;s~__1Tab B reviewed to determine highest level of classification.

rotes/comments

Use available resources to obtain indications of emergency

conditions.

Procedure Step __

ISAT []

UNSAT []

I...;:S;,:;:ta;:.:,n.:.;;:d:.:;;a.:.;;rd;.;;:s~__1Tab B indications compared to Initial Conditions provided in JPM.

INotes/Comments

02/25/08

Page 5 of 8

~ Classify event based on emergency action level being exceeded.

IProcedure Step

ICritical Step

ISAT []

UNSAT []

Standards

Notes/Comments

Event is classified as a General Emergency lAW TAB B.2 within 15

minutes of the start of the evaluation.

Record time of declaration here

. This time begins the

14 minute clock for selecting the PAR (element 6 of JPM).

Record time to make classification:

Declaration Time

________ =

minutes

Evaluation Start time

Total Time to classify

Classification is required to be less than or equal to 15 minutes from

the start of the evaluation.

Identify Protective Action Recommendation (PAR) is applicable

based on exceedin

action level for General Emer enc .

Procedure Step __

ISAT []

UNSAT []

Standards

INotes/Comments

02/25/08

EPIP-1.06 Protective Action Recommendation Matrix compared to

Initial Conditions

rovided in JPM.

Page 6 of 8

[LJ Determine Protective Action Recommendation.

ICritical Step

IProcedure Step

ISAT []

UNSAT []

Standards

Notes/Comments

Protective Action Recommendation from EPIP-1.06 is PAR A (based on

known impediments make evacuation dangerous), and is selected

within 14 minutes of the event classification (element 4 of JPM).

Record time of PAR selection here:

_

Record time to make PAR:

PAR selection Time

_______ =

minutes

Declaration Time

Time required to

(element 4 of JPM)

select PAR

STOP TIME

02/25/08

PAR selection is required to be less than or equal to 14 minutes from

the time of classification (element 4 of JPM).

>>>>> END OF EVALUATION <<<<<

Page 7 of 8

None

02/25/08

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

Page 8 of 8

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

A Reactor Trip occurred from 100% power.

Reactor Coolant System boron concentration prior to trip was 980 ppm.

Core burnup is approximately 9,000 MWD/MTU.

'N BAST is the on-service BAST and is at 14,043 ppm.

The crew has transitioned from 1-E-0, Reactor Trip or Safety Injection to 1-ES-O.1, Reactor Trip

Response with the plant stable.

INITIATING CUE

You are requested to perform Step 7 of 1-ES-0.1, Reactor Trip Response.

02/25/08

A

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

R115 (modified)

Emergency Borate for stuck rods following a Reactor Trip (1-ES-0.1).

TASK STANDARDS

Emergency Boration established using 1-CH-241 manual Emergency Borate Valve. Termination

criteria determined to be 30% change in BAST level or SDM verified using 1-PT-10 series

procedure.

KIA REFERENCE:

024 - AA2.01, (3.8/4.1)

ALTERNATE PATH:

TASK COMPLETION TIMES

Validation Time =

15 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

02/25/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 10

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

R115 (modified)

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the reactor operator level.

INITIAL CONDITIONS

A Reactor Trip occurred from 100% power.

Reactor Coolant System boron concentration prior to trip was 980 ppm.

Core burnup is approximately 9,000 MWD/MTU.

'A' BAST is the on-service BAST and is at 14,043 ppm.

The crew has transitioned from 1-E-0, Reactor Trip or Safety Injection to 1-ES-0.1 , Reactor Trip

Response with the plant stable.

02/25/08

Page 3 of 10

INITIATING CUE

You are requested to perform Step 7 of 1-ES-0.1, Reactor Trip Response.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Copy of 1-ES-0.1, signed off up to step 7 to be provided to applicant.

PERFORMANCE STEPS

START TIME

Procedure Step

7

ICritical Step

ISAT []

UNSAT []

Standards

Observes IRPls and determines 3 rods reading >10 steps (operator

may use IRPI console indications and/or PCS). Operator transitions to

RNO column and carries out RNO actions since TWO or MORE (three

total) IRPls indicate greater than 10 steps.

Notes/Comments

Most RPls will not read EXACTLY zero; for the purposes of this JPM 3

RPls have been intentionally offset to read greater than the 10 step

requirement to be considered not fully inserted:

K-2 reads - 50 steps

F-12 reads - 16 steps

0-12 reads - 12 steps

02/25/08

Page 4 of 10

Place the control switch for the in-service boric acid transfer pump

Procedure Step

in FAST.

7a RNO

ICritical Step

ISAT []

UNSAT []

I....;;S;.:;ta;;;.:.n.:-=d;;;;;a;:.;rd;;,;;;s~__1Control switch for the pump is placed in FAST.

INotes/Comments

Open emergency boration valve 1-CH-MOV-1350.

Procedure Step

7b RNO

ISAT[]

UNSAT[]

Standards

Control switch for the emergency boration valve is placed in OPEN.

Notes/Comments

Valve will thermal out; this may be diagnosed by operator based on the

loss of light indication; operator may elect to dispatch Aux bldg. operator

to check valve and possibly another operator to look at breaker.

Verify Emergency Boration flow.

Procedure Step

7c RNO

ISAT []

UNSAT []

IStandards

INotes/Comments

02/25/08

IOperator observes FI-111 0 indicates < 35 gpm

Page 5 of 10

Locally open 1-CH-MOV-1350 and verify flow.

Procedure Step

7d RNO

ISAT[]

UNSAT[]

IStandards

IDispatches Aux Bldg. operator to locally open 1-CH-MOV-1350.

Notes/Comments

The Aux Bldg. operator will call back to inform operator that the

handwheel will not engage on 1-CH-MOV-1350 and he is unable to open

the valve).

'

Operator may have dispatched the aux. bldg. operator earlier based on

the 1-CH-MOV-1350 malfunction and may elect to have 1-CH-241

opened at this time based on the report that 1-CH-MOV-1350 can not be

opened; this course of action is acceptable.

Establish boration via local emergency borate valve.

Procedure Step

7eRNO

ICritical Step

Standards

ISAT []

UNSAT []

Places blender mode switch in BORATE.

Places blender control switch in START.

Places 1-CH-FCV-1113A control switch in OPEN.

Places 1-CH-FCV-1113B control switch in CLOSE.

Dispatches Aux Bldg. operator to locally open 1-CH-241.

Notes/Comments

Operator may initiate the action to open 1-CH-241 earlier based on the

report that MOV-1350 cannot be opened locally, this course of action is

acceptable.

02/25/08

Page 6 of 10

Record information.

Standards

Procedure Step

7f RNa

ISAT[]

UNSAT[]

The following information is recorded in the procedure:

Start time.

On-service (A) BAST level.

INotes/Comments

02/25/08

Page 7 of 10

Determine stopping criteria.

Procedure Step

7

RNO AND Att. 2

ICritical Step

Standards

ISAT []

UNSAT []

Determines 2 equivalent stuck rods.

-7 1 rod reading> 20 steps.

-7 2 rods reading between 11-20 steps.

ONE of the following options is determined as stopping

criteria:

Option 1

30% change in BAST level (15% for EACH Equivalent Stuck X 2

Equivalent Stuck Rods =30%).

Option 2

Candidate initiates, or directs personnel (STA or Rx Eng.) to

initiate a 1-PT-10 series procedure to verify adequate

Shutdown Margin.

Notes/Comments

There is a third option given in Attachment 2 Step 1C however the note

at the top of Attachment 2 clarifies that the other option, (25 minutes for

each EQSR), is not used as termination criteria since 1-CH-241 is the

flow path.

Operator may identify that less acid (less than a 30% change in BAST

level) may be required based on performance and results of a PT-10

series procedure to determine shutdown margin.

02/25/08

Page 8 of 10

Have the SRO refer to Tech Spec 3.1 .1 .

Procedure Step

7h RNO

ISAT []

UNSAT []

Standards

Oemonstration

Cues

INotes/Comments

STOP TIME

02/25/08

operator states that he would have the SRO refer to Tech Spec 3.1.1.

SRO acknowledges the requirement to review Tech Spec 3.1.1.

At this time another operator will complete the Emergency

Boration.

>>>>> END OF EVALUATION <<<<<

Page 9 of 10

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

Emergency Borate for stuck rods following a Reactor Trip (1-ES-0.1).

CHECKLIST

__ RecalllC #171 (0% power, post-trip)

__ Do Simspray

__ Verify that the 3 RPls indicate as described in notes section of Element 1

Booth Operator Actions:

If called to investigate 1-CH-MOV-1350 due to loss of lights tell the operator you don't see anything

obviously wrong with the valve and if asked there is nobody working in the area.

If called to investigate the breaker for 1-CH-MOV-1350 due to loss of lights tell the operator you

don't see anything obviously wrong with the breaker and if asked there is nobody working in the

area.

When directed to locally open 1-CH-MOV-1350 inform the operator that the handwheel will not

engage on 1-CH-MOV-1350 and you are unable to open the valve.

When called to open 1-CH-241 open the valve by actuating trigger 1 and report action when

complete (valve is set to open on 30 second ramp).

02/25/08

Page 10 of 10

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

Unit is stable at 100% power.

Quarterly control rod operability test was completed 20 minutes ago.

Control bank A control rod P-10 is at 217 steps, as indicated by individual rod position.

1-AP-1.3, Control Rod Out of Alignment, is complete up to the point of aligning the rod using

Attachment 2, Realigning Control Rod--Rod Low.

The SRO desires the affected rod be withdrawn in 3 step increments during realignment.

John Leake has been briefed with Attachment 2 and is standing by to perform any actions required

outside the control room.

INITIATING CUE

You are requested to realign rod P-10 by performing Attachment 2, Realigning Control Rod--Rod

Low, of 1-AP-1.3.

02/25/08

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

R477 (modified)

Respond to a misaligned control rod (1-AP-1.3).

TASK STANDARDS

The misaligned rod P-10 is withdrawn at least 1 rod pull (3 steps) per Attachment 2 of 1-AP-1.3;

Upon observing 2 control rods dropped 1-E-O is entered as required by 1-AP-1.2;

During performance of 1-E-O, the failure of SI to automatically actuate is identified and SI is

manually initiated.

KIA REFERENCE:

013-A4.03 (4.5/4.7)

ALTERNATE PATH:

YES

TASK COMPLETION TIMES

Validation Time =

22 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time=

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date

EVALUATOR'S COMMENTS

02/25/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 13

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

R477 (modified)

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the Reactor Operator level.

INITIAL CONDITIONS

Unit is stable at 100% power.

Quarterly control rod operability test was completed 20 minutes ago.

Control bank A control rod P-10 is at 217 steps, as indicated by individual rod position.

1-AP-1.3, Control Rod Out of Alignment, is complete up to the point of aligning the rod using

Attachment 2, Realigning Control Rod--Rod Low.

The SRO desires the affected rod be withdrawn in 3 step increments during realignment.

02/25/08

Page 3 of 13

John Leake has been briefed with Attachment 2 and is standing by to perform any actions required

outside the control room.

INITIATING CUE

You are requested to realign rod P-10 by performing Attachment 2, Realigning Control Rod--Rod Low, of

1-AP-1.3.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Copy of 1-AP-1.3 signed off to the point of performing Attachment 2, Realigning Control Rod--Rod

Low, to be provided to applicant.

PERFORMANCE STEPS

START TIME

02/25/08

Page 4 of 13

Note: Step 1 of Att. 2 is N/A since rod is not in controlling bank.

Record the affected bank position.

Procedure Step

2 of 1-AP-1.3 Att.2

ISAT[]

UNSAT[]

IL...:;S;;,::ta~n.:.;;d:.:;;a~rd;;,;;s~__1Records CSA 229 steps in procedure.

Notes/Comments

Control bank A group step counters are reading 229 steps (value

corresponds to the ARO position).

Record the misaligned rod position.

Procedure Step

3 of 1-AP-1.3 Att.2

ISAT []

UNSAT []

I...:;S~ta~n;.;;:d~a.:.;;rd:.:;;s~__ 1 Records rod P-10@217steps.

INotes/Comments

02/25/08

Page 5 of 13

Record the number of steps that the rod is misaligned.

Procedure Step

4 of 1-AP-1.3 Att.2

ISAT[]

UNSAT[]

IStandards

roteS/Comments

I Records rod P-10 misaligned by 12 steps.

Place the control rod bank selector switch in BANK SELECT.

Procedure Step

5 of 1-AP-1 .3 Att.2

I,-C_r_it_ic_a_1S_t_e-'-p

1SAT []

UNSAT []

I...;;:S~ta~n;,;;;d:.;;;:a.:.;;rd;,;;;s~__1 Rod control selector switch positioned to CONTROL BANK A position.

[NolesiCommenls

Manually adjust the group step counter to the actual position of the

Procedure Step

misali ned rod.

6 of 1-AP-1.3 Att.2

ICritical Step

ISAT []

UNSAT []

Standards

02/25/08

rotesiCommenls

Page 6 of 13

Locally record the pulse-to-analog converter reading for control

bank A.

Procedure Step

7 of 1-AP-1.3 Att.2

ISAT[]

UNSAT[]

IStandards

ICalls operator (John Leake) to obtain reading per Step 7 of Att. 2

Notes/Comments

Expected reading of 229 steps provided by booth operator.

Locally reset the pulse-to-analog converter for control bank A.

Procedure Step

8 of 1-AP-1.3 Att.2

IL....:C:....:..r.:..:.itl:...::*c..::;:a.:.-1S=-t=..=e.I.:.p

1SAT []

UNSAT []

Standards

Demonstration

IF the operator questions rod bank 10 limit alarm, THEN tell him as the

Cues

SRO that it will be evaluated and to continue with the task.

Notes/Comments

The bank A rod bank 10 limit alarm will come in when the PIA converter is

pulsed down. The operator should acknowledge this as an expected

alarm. The recorder on the vertical panel may be checked, this recorder

is calibrated in % NOT steps.

02/25/08

Page 7 of 13

Open all lift coil disconnect switches for the affected bank, except

Procedure Step

for the switch for the misali ned rod.

9 of 1-AP-1.3 Att.2

ICritical Step

ISAT []

UNSAT []

Standards

Demonstration

Cues

rotes/comments

All lift coil disconnect switches for control bank A are open EXCEPT for

rodP-10.

IF the operator states that he will need another operator to take the

board THEN inform him The balance-of-plant operator has the board.

Have an extra operator independently verify lift coil disconnects.

Procedure Step

10 of 1-AP-1.3 Att.2

ISAT []

UNSAT [)

IStandards

Demonstration

Cues

INotes/Comments

02/25/08

IRequests extra operator (e.g. BOP) to perform step 10 of attachment 2. I

The balance-of-plant operator has completed step 10 of attachment 2.

Page 8 of 13

Adjust turbine load as required to maintain Tavg and Tref within

1.5 de rees F durin

rod withdrawal.

Procedure Step

11 of 1-AP-1.3 Att.2

ISAT []

UNSAT []

Standards

Demonstration

Cues

Operator reviews requirements for maintaining RCS temperature during

reali nment.

IF the operator states that it may be desired to reduce power slightly or

borate prior to rod withdrawal, THEN as the SRO inform them that

Reactor Engineering has determined the worth of the affected rod is

only a few pcm and neither power reduction, nor boration is necessary.

Cue may not be required, but is provided since candidate may feel

that reducing power or adding negative reactivity prior to rod

withdrawal would be a conservative action to take since power is

close to 100.00.

Notes/Comments

The worth of a single CBA rod at 217 steps is negligible, therefore no

adjustments are necessary.

Manually withdraw the affected control rod.

Procedure Step

12 of 1-AP-1.3 Att.2

ICritical Step

ISAT []

UNSAT []

IStandards

IOperator begins withdrawal of rod P-10 in 3 step increments.

Notes/Comments

Based on rod height and power level no actions should be necessary for

maintaining temperature or Reactor power; Rod Control urgent failure

alarm will annunciate as noted in the procedure.

02/25/08

Page 9 of 13

12

Respond to dropped control rods (1-AP-1.2)

Procedure Step

Alternate path step, Step 1 of 1-AP-1.2 has the operator verify

1 RNO of 1-AP-1.2

~~~;(P:~r~~~:~~~t~g~ DROPPED, the RNO is to go to

ICritical Step

ISAT []

UNSAT []

Standards

Operator identifies more than 1 RCCA dropped and initiates a Reactor

Tri

er 1-AP-1.2, Dro

ed Rod, Ste

1 RNO.

Notes/Comments

Automatic Reactor Trip signals are blocked to ensure action is required

by the operator to trip the reactor. The reactor will trip when the reactor

trip switch is placed in trip.

Verify reactor tripped - YES.

Procedure Step

1 of 1-E-0

ISAT []

UNSAT []

02/25/08

Standards

rotes/comments

Operator verifies reactor is tripped (RTBs open, rod bottom lights on,

flux decr~asin

Page 10 of 13

14

Verify turbine trip - NO

Procedure Step

Alternate path step, step 2 of 1-E-O has the operator manually

2 of 1-E-O

trip turbine (automatic trip signal should have occurred also),

the RNO for this step has the operator manually runback the

turbine.

ISAT []

UNSAT []

Standards

INotes/Comments

Attempts to manually trip turbine; based on failure of turbine to

manually trip runs back turbine (places EHC pumps in P-T-L and runs

back turbine until stop valves qo closed) and resets Reheaters.

Verify both ac emergency busses energized - yes.

Procedure Step

3 of 1-E-O

ISAT[]

UNSAT[]

Standards

INotes/Comments

02/25/08

Verifies 1Hand 1J busses both energized by observing volt meters on

1Hand 1J EDG control

anels.

Page 11 of 13

Check if SI is actuated

Procedure Step

4 of 1-E-O

ICritical Step

Standards

Checks low head pumps running- NO.

Any first out annunciator lit - YES.

Operator manually actuates 51.

ISAT[]

UNSAT[]

Demonstration

Cues

Notes/Comments

5TOPTIME

02/25/08

JPM is complete once operator states the E-O immediate operator

actions are com lete.

Annunciator D-E/3 will be lit due to failure of turbine to trip unless

acknowledged prior to performing this step (MSTVs close so condition

clears after MSTVs shut).

The only critical element of this standard is manually actuating 51.

>>>>> END OF EVALUATION <<<<<

Page 12 of 13

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

Respond to a misaligned control rod (1-AP-1.3).

CHECKLIST

__ Recall IC #168 (100% power).

__ Do Simspray.

Ensure rod banks and TavelTref recorder are correct.

Booth Operator Actions:

Respond as extra operator (John Leake) to perform the following:

Using extreme view report PIA converter reading (229 steps) when directed in

Step 7 of Attachment 2.

Using extreme view reset PIA converter for CBA to 217 steps when directed in

Step 8 of Attachment 2 and report completion of step to operator (note: adjust to 1 step increments

for realism prior to pulsing down).

02/25/08

Page 13 of 13

Dominion

North Anna Power Station

JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

Emergency diesel operations have been completed

The diesel did not start on an emergency start signal

Equipment status has been reviewed and supports the performance of this procedure

An operator is available in 1H diesel room

INITIATING CUE

You are requested to transfer the 1H emergency bus from 1H diesel to "G" reserve station service

transformer in accordance with 1-0P-6.1. You are not required to unload the 1H diesel.

05/14/08

Dominion

North Anna Power Station

JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

N518

Transfer an emergency bus from an emergency diesel generator to a reserve station service

transformer on the backboards watchstation (1-0P-6.1, 1-0P-6.2).

TASK STANDARDS

1H emergency bus has been transferred from 1H diesel to "C" RSST

KIA REFERENCE:

064-A4.07 (3.4/3.4)

ALTERNATE PATH:

TASK COMPLETION TIMES

Validation Time =

10 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

StopTime=

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

05/14/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page: 2 of 11

Dominion

North Anna Power Station

(Evaluation)

OPERATOR PROGRAM

N518

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

INITIAL CONDITIONS

Emergency diesel operations have been completed

The diesel did not start on an emergency start signal

Equipment status has been reviewed and supports the performance of this procedure

An operator is available in 1H diesel room

INITIATING CUE

You are requested to transfer the 1H emergency bus from 1H diesel to "C" reserve station service

transformer in accordance with 1-0P-6.1. You are not required to unload the 1H diesel.

05/14/08

Page: 3 of 11

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Sync key

Copy of 1-0P-6.1 , Sections 1-4,Subsection 5.3, and Att.1 , to be provided to applicant.

PERFORMANCE STEPS

START TIME

o:==J Verify initial conditions are satisfied.

IProcedure Step 5.3.1

ISAT[]

UNSAT[]

I...;;;S~ta;;;.;.n:.;;;d;,;;:a_rd_s~__1Operator reviews initial conditions and initials the step

INotesiComments

~l Review precautions and limitations.

IProcedure Step 5.3.2

ISAT[]

UNSAT[]

05/14/08

IStandards

rates/comments

IOperator reviews precautions and limitations and initials step

Page: 4 of 11

[CJ Verify the desired electrical supply-breaker alignment.

Iu;;S;,:;;ta:::.:n~da~r~ds=---__115H11 and 15F3 are verified OPEN

INotes/Comments

~ Ensure transformer normal feeder breaker is closed.

I.;;;;:S~ta~n,;;;,;da~r~ds=---__1 Breaker 15F1 is verified CLOSED

INotes/Comments

~I Close the transfer bus supply breaker to the emergency bus.

ICritical Step

IProcedure Step 5.3.3

ISAT []

UNSAT []

I Procedure Step 5.3.4

ISAT[]

UNSAT[]

IProcedure Step 5.3.5

ISAT[]

UNSAT[]

IStandards

INotes/Comments

05/14/08

IOperator closes breaker 1-EP-BKR-15F3

Page: 5 of 11

6

Verify that no normal shutdown alarms are locked in if the

Procedure Step 5.3.6

emergency diesel generator was started due to an emergency start

signal.

ISAT[]

UNSAT[]

IStandards

INotes/Comments

IInitial conditions of JPM are reviewed and step is N/A'd

Place the 4160-volt emergency bus normal feed synchronizing

switch to ON.

Procedure Step 5.3.7

ICritical Step

I~S;.:;;ta~n.:.;;;d:.:;:ao:.;;rd;.;;:s~__115H11 synchronizer switch is turned to ON

INotes/Comments

05/14/08

ISAT []

UNSAT []

Page: 6 of 11

Verify emergency bus frequency is 60 hertz using the

SPEED/LOAD control switch.

Procedure Step 5.3.8

ISAT[]

UNSAT[]

Standards

Frequency is adjusted to 60 hertz using the SPEED/LOAD control

switch.

Notes/Comments

Operator may determine that frequency is close enough to 60 Hz, due to meter calibration

allowances, and choose NOT to adjust.

9

Adjust emergency diesel generator voltage (incoming) slightly

Procedure Step 5.3.9

higher than the reserve station service bus voltage (running) using

the EXCITER VOLTAGE CONTROL switch.

ICritical Step

Standards

Notes/Comments

ISAT []

UNSAT []

Incoming voltage is adjusted to 1 to 2 volts higher than the running

volta e suin

the SPEED/LOAD CONTROL switch.

05/14/08

Annunciator F-H5, 480V OR 4KV EMERG BUS VOLTS HIILO, may alarm at this time.

Cue applicant that the OATC will handle the AR for this alarm.

Page: 7 of 11

10

Adjust the speed of the emergency diesel generator until the

Procedure Step 5.3.10

synchroscope behaves in the following manner.

Moves slowly in the fast direction

Completes one rotation within the required time

ISAT []

UNSAT []

Standards

Speed is adjusted so that the synchroscope is moving slowly in the

"fast" direction and com letes one rotation in ~ 20 seconds

Notes/Comments

Speed may not require adjustment.

11

When the synchroscope indicates "one minute before 12 o'clock,"

Procedure Step 5.3.11

close the reserve station service supply breaker to the emergency

bus.

ICritical Step

ISAT []

UNSAT [ ]

IStandards

1_1--,-5_H_1_1_is_c_lo_s_e_d

_

rotes/comments

05/14/08

Page: 8 of 11

~ Adjust the power factor to 1.0 (kvar=O).

IProcedure Step 5.3.12 I

1SAT []

UNSAT []

IStandards

INotes/Comments

IPower factor is adjusted to 1.0 using the VOLTAGE CONTROL switch.

~ Place the synchronizing switch in the OFF position.

I..,;;;S~ta;:;.;n,;;;;da:;;:;,r.;;:,ds~__115H11 sync switch is placed in OFF position

[NotesiComments

ITCjlf operable, ensure MOP DEFEAT switch is in AUTO.

IProcedure Step 5.3.13 I

ISAT[]

UNSAT[]

IProcedure Step 5.3.14 I

ISAT[]

UNSAT[]

I....;;;S~ta:::.n:.;;:d~ar-=d.;;Ls

IOperator verifies MOP DEFEAT switch is in AUTO

INotesiComments

05/14/08

Page: 9 of 11

o::LJ Go to section 5.5 to unload the emergency diesel generator.

I.,;;S~ta~n~d~a_rd_s~__1Operator states that task is complete

IProcedure Step 5.3.15 I

ISAT [1

UNSAT [1

Demonstration

Cues

INotes/Comments

STOP TIME

05/14/08

Assume another operator will unload the diesel.

>>>>> END OF EVALUATION <<<<<

Page: 10 of 11

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

SIMULATOR SETUP

N518

Transfer an emergency bus from an emergency diesel generator to a reserve station service

transformer on the backboards watchstation (1-0P-6.1, 1-0P-6.2).

CHECKLIST

__ Recall 100% power IC

Start 1H diesel in MANUAL LOC

Load F transfer bus onto diesel

__ Open 15F3 and 15H11

PLACE SYNC KEY IN THE BREAKER FOR 15H2. PUT IT BACK HERE BETWEEN CANDIDATES.

Booth Instructions

If called respond as the operator at the EDG respond that you are ready for them to transfer load

from the EDG to the RSST (all conditions normal, personnel clear of area, etc.).

05/14/08

Page: 11 of 11

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

Residual Heat Removal System is in service.

Reactor Coolant Pumps "A" and "C" are in operation.

Unit is in Mode 4 and RCS temperature is stable at approximately 301°F.

Charging pumps and LHSI pumps have been aligned per 1-0P-3.3, Unit Shutdown from Mode 4 to

Mode 5, in preparation for going below 280°F within the next hour.

The STA will calculate the estimated time to boiling in accordance with 1-GOP-13.1 once the unit

enters Mode 5.

Feed flow to SGs is being supplied by Condensate with the B feed pump breakers in test.

RHR SYSTEM LO FLOW, Annunciator E-A8, has just alarmed.

INITIATING CUE

You are requested to respond in accordance with 1-AP-11, Loss of RHR.

02/21/08

d

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

R514 (Modified)

Respond to a Loss of RHR (1-AP-11).

TASK STANDARDS

Attempts to restore RHR are made; Steam Dumps are controlled to control RCS temperature.

KIA REFERENCE:

KIA 005A2.03 (2.9/3.1)

ALTERNATE PATH:

TASK COMPLETION TIMES

Validation Time =

20 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

02/21/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 11

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

R514 (Modified)

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the Reactor Operator level.

INITIAL CONDITIONS

Residual Heat Removal System is in service.

Reactor Coolant Pumps "A" and "C" are in operation.

Unit is in Mode 4 and RCS temperature is stable at approximately 301°F.

Charging pumps and LHSI pumps have been aligned per 1-0P-3.3, Unit Shutdown from Mode 4 to

Mode 5 in preparation for going below 280°F within the next hour.

02/21/08

Page 3 of 11

The STA will calculate the estimated time to boiling in accordance with 1-GOP-13.1 once the unit

enters Mode 5.

Feed flow to SGs is being supplied by Condensate with the B feed pump breakers in test.

RHR SYSTEM LO FLOW, Annunciator E-A8, has just alarmed.

INITIATING CUE

You are requested to respond in accordance with 1-AP-11, Loss of RHR.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Blank copy of 1-AP-11 to be provided to applicant.

PERFORMANCE STEPS

START TIME

Check RCS Level decreasing - NO.

Procedure Step

Alternate Path Step, Candidate transitions to procedure Step 5

1 RNO

per RNO based on no loss of inventory.

ISAT[]

UNSAT[]

Standards

INotes/Comments

02/21/08

Pressurizer level, VCT level, RCS makeup rate, Containment Sump

and/or PDTT level/ um in

fre uenc

are verified unchan ed.

Page 4 of 11

Verify that the Residual Heat Removal System isolation valves are

Procedure Step

o en - YES.

5a

ISAT[]

UNSAT[]

IStandards

INotes/Comments

IRHR inlet valves 1-RH-MOV-1700 and 1701 are verified open.

Verify that at least one Residual Heat Removal System outlet valve

Procedure Step

is 0 en -YES.

5b

ISAT[]

UNSAT[]

IL..::S:::ta:=n::::d:=a:::rd:::s=--__1RHR outlet valve 1-RH-MOV-1720A is verified open.

INotes/Comments

02/21/08

Page 5 of 11

Check One RHR pump running - NO.

Procedure Step

6

ISAT[]

UNSAT[]

Standards

Determines 1-RH-P-1A has a sheared shaft and the other RHR

pump is available.

Stops 1-RHR-P-1A.

Notes/Comments

No cue is needed, the Initial Conditions given and control room

indications provide adequate information to access System status.

5

If electrical power is available, then attempt to restore RHR flow.

Alternate Path Step: Based on Initial Conditions provided

candidate will attempt to restore flow per the RNO of the Step,

and once the determination is made that NO RHR pumps are

available the candidate will transition forward to Step 11 based

on a loss of ALL RHR pumps.

Procedure Step

6c1 - 6c3

and

6c5

jSAT[]

UNSAT[]

Standards

Places 1-RH-FCV-1605 controller in manual and reduces demand

to zero (0).

Adjusts HIC for 1-RH-HCV-1758 demand to zero (0).

Determines venting not required since there are no indications of

air entrainment.

Places Control switch for 1-RH-P-1 B to start.

Transitions to procedure Step 11 based on RHR pump breaker

failing to close.

Notes/Comments

Step 6c4 of the procedure has the operator restore flow by repositioning

RHR control valves. Since an RHR pump could not be started this step

does not need to be performed since it will not accomplish anything.

02/21/08

Page 6 of 11

Record time to boiling from 1-GOP-13.0

Procedure Step

11 a

L--

ISAT []

UNSAT []

IStandards

Demonstration

Cues

Notes/Comments

Step marked N/A QR STA notified to determine time to boiling

If candidate requests SRO concurrence to mark step N/A, THEN

concur with candidate.

IF candidate requests that the STA calculate a time to boil THEN

acknowledqe that the STA will perform that action.

Calculating time to boil is not required since the RCS is NOT in Mode 5

with the RCS vented or soon to be vented, however the candidate may

feel that it is prudent and initiate the action. 1-AP-11 is written for

various plant conditions so the step would apply for those situations such

as Mode 5 drained to mid-loop, etc.

Evaluate the need to implement EPIP-1.01, Emergency Manager

Controllin

Procedure.

Procedure Step

11 b

ISAT[]

UNSAT[]

I....S..ta...n,;,;;d..a..,rd;;,;s

1 Notifies Annex (WCCS) or other operator to evaluate EPIP-1.01.

Demonstration

Cues

INotes/Comments

02/21/08

Operations shift manager or unit supervisor will perform this step.

Page 7 of 11

Monitors Containment Radiation.

Procedure Step

11 c

ISAT []

UNSAT []

IStandards

IChecks recorder and/or monitors 1-RM-RMS-159 and 160.

Notes/Comments

Since a loss of RCS inventory is NOT occurring 1-RM-RMS-159 and 160

will be essentially stable at the pre-event value.

Initiate Attachment 11 for Containment closure.

Procedure Step

12

ISAT[]

UNSAT[]

IStandards

Demonstration

Cues

INotes/Comments

02/21/08

!Identifies need to perform Attachment 11 .

Inform the operator that an additional operator has been assigned to

erform Attachment 11.

Page 8 of 11

Verifies 1-RC-L1-1 05 energized.

Procedure Step

13

ISAT []

UNSAT []

IStandards

Demonstration

Cues

INotes/Comments

I Directs operator to energize 1-RC-L1-1 05.

Inform the operator that an additional operator will energize

1-RC-L1-105.

Start Available Containment Air Recirc Fans.

Procedure Step

14

ISAT []

UNSAT []

I__

S_ta_n_d_a;,,;;rd_s~__1 Checks all 3 CARFs are operating.

INotes/Comments

02/21/08

Page 9 of 11

Maintain core-cooling using forced circulation.

Procedure Step

15a -15c

I-=C....:..:ri:...:..:ti:...:..:c=al~S=--:t:..:..e£:...p

1SAT []

UNSAT []

Standards

Verbal-Visual

Cues

Notes/Comments

STOP TIME

02/21/08

Verifies RCP 1A and 1C running.

Raises demand on 1-MS-PC-1464B to establish Core Exit

TCs STABLE or DECREASING.

Control feed flow to SGs to maintain 23-75% level.

Once CETs are verified stable or decreasing assume that another

o erator will com lete the

rocedure.

The only critical step of THIS standards is to increase dumping

steam. Steam dumps should be operated (using a bump and wait

technique) until Core Exit TCs are stable or decreasing.

Since SG levels are at normal operating level and will swell once Steam

Dumps are throttled open level will be high and the operator will not have

need to make any adjustments.

>>>>> END OF EVALUATION <<<<<

Page 10 of 11

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

SIMULATOR SETUP

R514 (Modified)

Respond to a Loss of RHR (1-AP-11).

CHECKLIST

__ Recall the IC 180 (Mode 4 with temperature -301

0 F).

__ Do Simspray (remember startup 2, since this is a shutdown scenario).

__ Place TEST magnet on control switches for B feed pump breakers.

__ Ensure malfunction is entered and simulator is in freeze prior to candidate entering the

Simulator.

Booth operator actions

Respond as operator to check breaker for 1B RHR pump if requested; call back in 2 minutes and report

that there is nothing obviously wrong with the breaker, but there is an acrid odor coming from it. If asked

to locally close the breaker tell him you will get the necessary brief, procedure, and equipment and call

him once you are ready. If requested you will get support from electrical maintenance also.

IF asked as ANNEX/SM respond that you will evaluate EPIP-1.01 (and VPAP-2802, and make any

required notifications, etc.).

If asked as AnneX/HP, respond that you will coordinate evacuation of CNTMT.

Respond as extra operator to energize 1-RC-L1-1 05.

02/21/08

Page 11 of 11

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

The Unit is operating at 100% power, steady state.

Turbine 1st stage pressure channeI1-MS-PT-1447 has failed low.

Immediate actions of 1-AP-3, Loss of Vital Instrumentation have been performed.

INITIATING CUE

You are requested to continue performance of 1-AP-3 up to and including completion of Step 10.

03/04/08

e

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

R664 (modified)

Respond to failure of non-controlling 1sl Stage Pressure Channel.

TASK STANDARDS

Steam dumps were transferred to steam-pressure mode lAW 1-AP-3; upon failure, steam dumps

were taken to OFFIRESET as required by 1-AP-38.

KIA REFERENCE:

041-A4.04 (2.7/2.7)

ALTERNATE PATH:

YES

TASK COMPLETION TIMES

Validation Time =

12 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time=

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

03/04/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 9

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

R664 (modified)

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the Reactor Operator level.

INITIAL CONDITIONS

The Unit is operating at 100% power, steady state.

Turbine 1

51 stage pressure channel 1-MS-PT-1447 has failed low.

Immediate actions of 1-AP-3, Loss of Vital Instrumentation have been performed.

INITIATING CUE

03/04/08

Page 3 of 9

You are requested to continue performance of 1-AP-3 up to and including completion of Step 10.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Copy of 1-AP-3, signed off through Step 3, to be provided to applicant.

PERFORMANCE STEPS

START TIME

03/04/08

Page 4 of 9

NOTE: Although not required based on the initial conditions provided, operator may review Steps 1-3 to

verify all step performance requirements are met and ascertain pertinent information such as the

positions of SGWLC transfer switches, etc.

Verify systems affected by pressurizer level channels - NORMAL.

Procedure Step

4a - 4d of 1-AP-3

ISAT []

UNSAT []

03/04/08

Standards

rotes/comments

Verifies operable pressurizer level channels are selected

(all channels 1459, 1460, 1461 indicate normal; switch may be

checked in 461/460 position but doesn't matter since all

channels are normal).

Verifies letdown in service (flow indicated, 12008 liS orifice).

Verifies pressurizer level control in auto (1-RC-LC-1459G and

1-CH-FCV-1122 in auto).

Verifies control group heaters not tripped (annunciator NOT lit

and white liqht ON for control qroup heaters).

Page 5 of 9

2

Both 1s stage pressure channels normal-NO; transfer steam

dumps to steam pressure mode.

Alternate path Step, operator performs Step 5 RNO based on

Initial conditions of 1-MS-PT-1447 failed low.

ICritical Step

Procedure Step

5a-59 RNO of 1-AP-3

ISAT []

UNSAT []

Standards

Place both STEAM DUMP INTLK switches to OFF/RESET.

Place STEAM DUMP CONTROLLER to MANUAL.

Place MODE SELECTOR switch to Steam PRESS.

Ensure Steam Dump demand is ZERO (observes controller

output and may also check meter on Vertical Panel).

Return STEAM DUMP CONTROLLER to AUTO.

Verify Steam Dump demand is ZERO (observes controller

output and may also check meter on Vertical Panel).

Place both STEAM DUMP INTLK switches to ON.

Notes/Comments

ONLY THESE SUBSTEPS ARE CRITICAL. Steam dumps will be at

zero demand for these plant conditions, so no actions will be performed

beyond looking at the subject indications; thus the steps to ensure

demand is at zero, and subsequently verify demand remains at zero are

not critical to successful performance of the Task.

03/04/08

Page 6 of 9

Verify operable channels selected for SGWLC instruments.

Procedure Step

6 of 1-AP-3

ISAT []

UNSAT []

Standards

Checks all of the following indicating normal (with the exception of

1-MS-PT-1447):

Turbine 1

5t Stage Pressure (Blue Channel, 1-MS-PT-1446).

All selected Steam Flow Channels (Blue channel).

All selected Feed Flow cannels (Blue Channel).

Note: Since all channels were checked previously operator may just

observe the vertical panel and note that there are no other instrument

failures.

03/04/08

Notes/Comments

The malfunction that causes 1-MS-TCV-1408A to open is on a set time

delay; Operator will most likely not complete the above step since they

may notice the failed steam dump and take actions of 1-AP-38.

Page 7 of 9

4

Respond Excessive Load Increase (1-AP-38 immediate actions)

Alternate path step, the malfunction requires the candidate to

stop performance of the current procedure, implement IOAs of

1"AP*38 from memory, and in order to terminate the transient,

take manual actions per the RNO of 1-AP"38.

ICritical Step

Procedure Step

1-3 RNO of 1-AP-38

ISAT[]

UNSAT[]

Standards

Demonstration

Cues

Notes/Comments

STOP TIME

03/04/08

Verify ALL steam dumps closed - NO 1-MS-PCV-1408A is

open.

Place both STEAM DUMP INTLK switches to OFF/RESET.

Verifies steam dumps (1-MS-TCV-1408A) go closed.

Checks SG PORVs closed - YES.

Verify turbine load normal- YES/NO (see note).

Verify Reactor Power ~ 100% and stable - YES/NO (see note).

JPM is complete once operator states the immediate operator actions

of 1-AP-38 are com lete.

The only critical step of this element is Placing ONE of the STEAM

DUMP INTLK switches to OFF/RESET since this will terminate the

transient and reactor power will eventually return to the pr6*event

value.

Depending on when the operator identifies the malfunction and

completes the required actions power may be high enough to warrant

ramping. If Reactor Power is slightly greater than 100% because it has

not returned to the pre-event value when checked the operator may elect

to ramp.

>>>>> END OF EVALUATION <<<<<

Page 8 of 9

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

SIMULATOR SETUP

R664 (modified)

Respond to failure of non-controlling 1st Stage Pressure Channel

CHECKLIST

RecalllC 167.

__ Do Simspray.

Ensure rod banks and TavefTref recorder are correct.

__ Provide copy of 1-AP-3 with immediate action steps signed off.

Note: The malfunction (1-MS-TCV-1408 goes open), is set to trigger on time delay automatically

after the operator completes transferring steam dumps to steam pressure mode and will

close once the switches are taken to OFF/RESET.

03/04/08

Page 9 of 9

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

The Unit is at 100% power, steady state, with NO equipment out of service.

Pressurizer relief tank pressure is below the 8 psig minimum specified in Operator logs.

Nitrogen System is not supplying the power-operated relief valve nitrogen accumulators.

Equipment Status Log has been reviewed to verify station configuration supports the performance of

1-0P-5.7, Operation of the Pressurizer Relief Tank (PRT).

INITIATING CUE

You are requested to add nitrogen to the Pressurizer Relief Tank in accordance with 1-0P-5.7,

Operation of the Pressurizer Relief Tank (PRT), and raise pressure to 10 psig.

02/25/08

f

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

R640

Add Nitrogen to the PRT (1-0P-S.7).

TASK STANDARDS

Task was performed as directed by the procedure referenced in the task statement.

KIA REFERENCE:

007 - A1.02, (2.7/2.9)

ALTERNATE PATH:

N/A

TASK COMPLETION TIMES

Validation Time =

13 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

StopTime=

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

02/25/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 9

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

R640

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the Reactor Operator level.

INITIAL CONDITIONS

The Unit is at 100% power, steady state, with NO equipment out of service.

Pressurizer Relief Tank pressure is below the 8 psig minimum specified in Operator logs.

Nitrogen System is not supplying the power-operated relief valve nitrogen accumulators.

Equipment Status Log has been reviewed to verify station configuration supports the performance of

1-0P-5.7, Operation of the Pressurizer Relief Tank (PRT).

02/25/08

Page 3 of 9

INITIATING CUE

You are requested to add nitrogen to the Pressurizer Relief Tank in accordance with 1-0P-5.7,

Operation of the Pressurizer Relief Tank (PRT) and raise pressure to 10 psig.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Blank copy of 1-0P-5.7, to be provided to applicant.

PERFORMANCE STEPS

START TIME

Review precautions and limitations.

Procedure Step

5.4.2

ISAT[]

UNSAT[]

I....S;,;;ta-.n...d...a_rd..s'------__ 1 Precautions and limitations have been reviewed.

INotes/Comments

02/25/08

Page 4 of 9

Verify that nitrogen is aligned to the supply header.

Procedure Step

5.4.3

ISAT []

UNSAT []

IStandards

rotes/comments

IProvided by Initial conditions.

Reduce the demand on Containment Nitrogen Supply Header

1-SI-HIC-100 to 0%.

Procedure Step

5.4.4

ISAT[]

UNSAT[]

IStandards

INotes/Comments

02/25/08

11-SI-HIC-100 demand is reduced to 0%.

Page 5 of 9

Open Nitrogen Supply To CNTMT 1-SI-TV-100.

Procedure Step

5.4.5

ISAT[]

UNSAT[]

____---JL..-

_

ICritical Step

Standards

OPEN pushbuttons for the solenoids 1-SI-TV-100A AND 100B are

de ressed SIMULTANEOUSLY.

Notes/Comments

The note prior to this step describes the logic (2/2) and explains that in

order to open the valve BOTH pushbuttons must be used. If

pushbuttons are pushed one-at-a-time, for example, the valve will NOT

open.

Open Pressurizer Relief Tank Nitrogen Isol. 1-RC-HCV-1550.

Procedure Step

5.4.6

ICritical Step

ISAT[]

UNSAT[]

IL..,;;S~ta=n.:.;;d;,;;;a~rd;;,;;s~__11-RC-HCV-1550 placed in open.

INotes/Comments

02/25/08

Page 6 of 9

Open N2 to PRZR Relief Tank Isol. 1-SI-HCV-1898.

Procedure Step

5.4.7

I_C_ri_ti_c_al_S_t_eL-P

1SAT []

UNSAT []

I...;;S;.:.;ta~n;,;;:d~a-.;;rd;,:;;s~__11-SI-HCV-1898 placed in open.

INotes/Comments

Stop pressurizing the Pressurizer Relief Tank at the desired

ressure.

ICritical Step

Procedure Step

5.4.8a and 5.4.8b

ISAT[]

UNSAT[]

Standards

Desired pressure of 10 (+/- 1 psig) is reached in the PRT and the

following valves are closed:

1-SI-HCV-1898 is closed.

1-RC-HCV-1550 is closed.

Notes/Comments

It is only critical that ONE of the valves is closed, as closing either

one isolates the flow path.

02/25/08

Page 7 of 9

Restore N2 header alignment.

Procedure Step

5.4.8c.1 and 5.4.8c.2

ISAT []

UNSAT []

Standards

Alignment restored by performing the following:

CLOSE push-buttons for the solenoids 1-SI-TV-100A and/or 1008

are depressed.

1-SI-HIC-100 demand is raised to 100%.

INoteslComments

>>>>> END OF EVALUATION <<<<<

STOP TIME

02/25/08

Page 8 of 9

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

Add Nitrogen to the PRT (1-0P-5.7).

CHECKLIST

Recall Ie 170.

__ Do Simspray.

Ensure rod banks and Taveffref recorder are correct.

02/25/08

Page 9 of 9

Dominion

North Anna Power Station

CONTROL ROOM JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

Recirculation Spray System is in operation due to a valid Containment Depressurization Actuation

(CDA) signal.

Increasing radiation is indicated on Recirculation Spray Heat Exchanger Service Water Outlet

Radiation Monitor 1-RM-SW-126.

Trend recorder 1-RM-RR-100 indicates increasing radiation for radiation monitor 1-RM-SW-126.

High and High-High alarms are illuminated on radiation monitor 1-RM-SW-126.

Control room annunciator 1K-D2, RAD MONITOR SYSTEM HI RAD LEVEL is illuminated.

Control room annunciator K-D4, RAD MONITOR SYSTEM HI-HI RAD LEVEL is illuminated.

High Volume Slowdown of Service Water Reservoir is NOT in service.

INITIATING CUE

You are requested to respond to the high radiation indicated,on Recirculation Spray Heat Exchanger

Service Water Outlet Radiation Monitor, 1-RM-SW-126, in accordance with 1-AP-5, Attachment 10.

02/25/08

Dominion

North Anna Power Station

IN-PLANT JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

R775

Respond to a Recirculation Spray Heat Exchanger Service Water Radiation Monitor alarm (1-AP-5).

TASK STANDARDS

CDA was reset, 1-RS-P-2B was stopped, and SW was isolated to the "C" RSHX.

KIA REFERENCE:

073-A4.01 (3.9/3.9)

ALTERNATE PATH:

TASK COMPLETION TIMES

Validation Time =

15 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

02/25/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 14

Dominion

North Anna Power Station

(Evaluation)

OPERATOR PROGRAM

R775

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the Reactor Operator level.

INITIAL CONDITIONS

Recirculation Spray System is in operation due to a valid Containment Depressurization Actuation

(CDA) signal.

Increasing radiation is indicated on Recirculation Spray Heat Exchanger Service Water Outlet

Radiation Monitor 1-RM-SW-126.

Trend recorder 1-RM-RR-100 indicates increasing radiation for radiation monitor 1-RM-SW-126.

High and high-high alarms are illuminated on radiation monitor 1-RM-SW-126.

02/25/08

Page 3 of 14

Control room annunciator 1K-D2, RAD MONITOR SYSTEM HI RAD LEVEL is illuminated.

Control room annunciator 1K-D4, RAD MONITOR SYSTEM HI-HI RAD LEVEL is illuminated.

High Volume Blowdown of Service Water Reservoir is NOT in service.

INITIATING CUE

You are requested to respond to the high radiation indicated on Recirculation Spray Heat Exchanger

Service Water Outlet Radiation Monitor, 1-RM-SW-126, in accordance with 1-AP-5, Attachment 10.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Blank copy of 1-AP-5, Attachment 10 (ONLY) to be provided to applicant.

PERFORMANCE STEPS

START TIME

EVALUATOR'S NOTE

This JPM has been formatted for ease of use. Steps in the LEFT column match the

steps of Attachment 10 of 1-AP-5. The pages listed in the right column correspond to

the pages of Attachment 10 of 1-AP-5.

02/25/08

Page 4 of 14

Check 1-RM-SW-126 to determine if the alarm is the result of an

Page

obvious radiation monitor malfunction.

1 of 4

ISAT[]

UNSAT[]

Standards

Evaluator's Note

Verbal-Visual

Cues

INoles/Comments

This Step marked NIA.

May Check drawer light indication, meter reading not pegged, trend on

recorder, etc. to confirm Radiation Monitor is NOT failed.

Cue may not be necessary; Initial Conditions of the JPM provide

information supporting that the monitor is functioning properly, cue is

only necessary if candidate re-checks indication to confirm information

provided in the Initial Conditions.

WHEN indications are described by the operator, (drawer light

indication, meter reading not pegged, trend on recorder, etc.), THEN

confirm the operators observations that the Radiation Monitor is NOT

failed.

Secure Service Water Reservoir High Volume Slowdown, if in

Page

service.

2 of 4

ISAT []

UNSAT []

Standards

This Step marked NIA.

Operator determines Service Water Reservoir High Volume Slowdown

is NOT in service as provided in the Initial Conditions.

Notes/Comments

No cue is needed since information is provided in Initial Conditions.

02/25/08

Page 5 of 14

2b

Request the Health Physics Department to sample the affected

Page

Recirculation Spray Heat Exchanger and to check radiation levels

2 of 4

in the quench spray basement area.

ISAT[]

UNSAT[]

IStandards

Verbal-Visual

Cues

rotes/comments

IOperator requests HP to perform sampling and check radiation levels.

Health Physics reports that the service water sample from 1-RS-E-1C,

C Recirc Spray Heat Exchanger, has abnormally high activity AND that

the radiation level in the Quench Spray basement has increased

siqnificantly.

Request Station Management to determine if the affected heat

Page

exchan er should be isolated.

2 of 4

ISAT[]

UNSAT[]

Standards

Verbal-Visual

Cues

rotes/comments

Operator contacts Shift Manager or SRO (e.g. Operations Supervisor,

o erations Mana er, 0

erations Mana er ON-Call, etc. for

uidance.

Inform the operator that Station Management directs 1-RS-E-1 C, C

Recirc S ra

Heat Exchan er, be isolated.

02/25/08

Page 6 of 14

Refer to Tech Spec 3.6.7 for the Recirc Spray System

re uirements.

Page

2 of 4

ISAT[]

UNSAT[]

Standards

Verbal-Visual

Cues

INotes/Comments

Operator identifies the need to refer to Tech Spec 3.6.7.

Inform the operator that the SRO will perform this action.

~ Reset both trains of CDA.

ICritical Step

IPage

3 of 4

!SAT[]

UNSAT[]

02/25/08

Standards

Verbal-Visual

Cues

Notes/Comments

Both SPRAY ACTUATION RESET switches are placed in the RESET

osition.

IF the operator identifies the expected response (1 K-H6, CDA

INITIATED annunciator CLEAR), THEN inform him that 1K-H6 appears

as they see it now.

Checking of annunciator status following switch manipulation is not

critical; Cue information is only provided in the event the operator states

that he would expect the subject annunciator to clear.

Page 7 of 14

~TO isolate 1-RS-E-1A.

IStandards

IStep is marked N/A.

!page

3 of 4

ISAT[]

UNSAT[]

Notes/Comments

No cue is needed since information is provided in Initial Conditions.

~TO isolate 1-RS-E-1B.

IPage

3 of 4

ISAT[]

UNSAT[]

IStandards

I_S_te--,-p_i_s_m_a_rk_e_d_N_/_A_.

_

Notes/Comments

No cue is needed since information is provided in Initial Conditions.

02/25/08

Page 8 of 14

4d1

To isolate 1-RS-E-1 C, do the following:

Page

Request the Safeguards operator to place the key-lock switches for

3 of 4

1-SW-MOV-103C and 1-SW-MOV-104C in the DEFEAT position.

I_C_ri_ti_ca_I_S_t_epL--

1SAT []

UNSAT []

02/25/08

Standards

Verbal-Visual

Cues

Notes/Comments

Safeguards operator is requested to place the key-lock switches for

1-SW-MOV-103C and 1-SW-MOV-104C in the DEFEAT

osition.

Safeguards operator has placed the key-lock switches for

1-SW-MOV-103C and 1-SW-MOV-104C in the DEFEAT position.

IF identified by the operator, THEN confirm receipt of the following

annunciators:

1K-E3, SER WTR SYS LOGIC CABS UNITS 1 AND 2 DOOR

OPEN

1J-F8, UNIT 1 SW KEY LOCK SWITCH IN DEFEAT

Identifying expected annunciators is not critical; Cue information is only

provided in the event the operator states that he would expect the

subject annunciators.

Page 9 of 14

\\Page

3 of 4

EI Stop 1-RS-P-2B.

I_C_ri_ti_c_al_S_t_e__p

1SAT []

UNSAT []

I..,;;S;,:,;ta~n.:.;;:d;,:;;ao:.;;rd;,;;:s,--__ 1Control switch for 1-RS-P-2B is momentarily placed in STOP.

Verbal-Visual

Cues

rotes/comments

Operator will expect pump to be running (RED light LIT, GREEN light

NOT LIT, normal amperage indication) based on initial conditions; IF

operator indicates he is checking light indication to determine pump

status, THEN confirm RED light LIT, GREEN light NOT LIT, when

controls for 1-RS-P-2B are identified.

WHEN the operator identifies the expected change in pump status

following the simulated control switch manipulation, THEN inform the

operator that light indication and amperage meter reading for the pump

are as they see them now.

IPage

3 of 4

~ Stop 1-SW-P-7 (sample pump).

I-=.C_ri....:...ti....:...ca....:...I_S::....:t....:...epL--

1SAT []

UNSAT []

IStandards

IControl switch for 1-SW-P-7 taken to STOP position.

Notes/Comments

There are no light indications for the sample pump.

02/25/08

Page 10 of 14

E]Close 1-SW-MOV-103C.

ICritical Step

!page

3 of 4

ISAT[]

UNSAT[]

02/25/08

Standards

Verbal-Visual

Cues

rotes/comments

CLOSE pushbutton for recirculation spray heat exchanger isolation

valve 1-SW-MOV-103C is de ressed.

Operator will expect valve to be OPEN (RED light LIT, GREEN light

NOT LIT) based on initial conditions; IF operator indicates he is

checking light indication to determine valve status, THEN confirm RED

light LIT, GREEN light NOT LIT, when pushbutton for 1-SW-MOV-103C

is identified.

WHEN the operator identifies the expected change in valve status

following the simulated push-button manipulation, THEN inform the

operator that indication lights for the valve is as they see them now.

Page 11 of 14

IPage

3 of 4

~ Close 1-SW-MOV-104C.

I--'-C_ri_ti_c_al_S.:-t_e......p

1SAT []

UNSAT []

Standards

Verbal-Visual

Cues

INotes/Comments

CLOSE pushbutton for recirculation spray heat exchanger isolation

valve 1-SW-MOV-104C is de ressed.

Operator will expect valves to be OPEN (RED light LIT, GREEN light

NOT LIT) based on initial conditions; IF operator indicates he is

checking light indication to determine valve status, THEN confirm RED

light LIT, GREEN light NOT LIT, when pushbuttons for 1-SW-MOV-

104C is identified.

WHEN the operator identifies the expected change in valve status

following the simulated push-button manipulation, THEN inform the

operator that indication liqht for the valve is as they see them now.

EJTO isolate 1-RS-E-1D.

IPage

4 of 4

ISAT []

UNSAT []

IStandards

I--=S-'-te:..Lp---'i.=.-s---'m.;...:acc..rk-'-e:....:d---'N--=/..:....A::-.

_

Notes/Comments

No cue is needed since information is provided in Initial Conditions.

02/25/08

Page 12 of 14

Submit a Work Request to initiate repairs.

Page

4 of 4

ISAT (]

UNSAT []

Standards

Verbal-Visual

Cues

rotesiComments

Operator identifies the need to generate a Work Request.

Inform the operator that the SRO will perform this action.

Return to the procedure in effect.

Page

4 of 4

ISAT[]

UNSAT[]

Verbal-Visual

Inform the operator that another operator will complete the procedure.

Cues

Notes/Comments

JPM concludes when operator identifies need to return to procedure step

in effect or informs the SRO that he has completed Attachment 10.

>>>>> END OF EVALUATION <<<<<

STOP TIME

02/25/08

Page 13 of 14

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

SIMULATOR SETUP

R775

Respond to a recirculation spray heat exchanger service water radiation monitor alarm (1-AP-5).

CHECKLIST

__ NONE - JPM is intented to be done in the plant but may be done dead simulator by

modifying cues from "as they see it now" to "confirm applicants description of status".

02/25/08

Page 14 of 14

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

Unit 1 is operating at 30% power holding for chemistry.

Unit 2 is in Mode 5 for scheduled refueling outage.

Circulating Water Pump 1-CW-P-1A is OOS for oil replacement.

CW PP 1A-1 B-1C-1 D AUTO TRIP Annunciator 1B-A5, has just been received.

INITIATING CUE

You are requested to respond to plant conditions in accordance with 1-AP-13.

03/04/08

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

R517 (modified)

Respond to Annunciator 1B-A5, CW PP 1A-1 B-1 C-1 D AUTO TRIP.

TASK STANDARDS

Immediate Operator Action (Step 1) performed without reference to procedure. Liquid waste

releases secured in accordance with 1-AP-13.

KIA REFERENCE:

075-A2.02 (2.5/2.7)

ALTERNATE PATH:

TASK COMPLETION TIMES

Validation Time =

15 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

03/04/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 11

Dominion

North Anna Power Station

SIMULATOR JOB PERFORMANCE MEASURE

(Evaluation)

OPERATOR PROGRAM

R517 (Modified)

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

The trainee has completed the applicable course knowledge training at the reactor operator level.

INITIAL CONDITIONS

Unit 1 is operating at 30% power holding for chemistry.

Unit 2 is in Mode 5 for scheduled refueling outage.

Circulating Water Pump 1-CW-P-1A is OOS for oil replacement.

CW PP 1A-1 B-1 C-1 D AUTO TRIP Annunciator 1B-A5, has just been received.

03/04/08

Page 3 of 11

INITIATING CUE

You are requested to respond to plant conditions in accordance with 1-AP-13.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Blank copy of 1-AP-13 to be provided to applicant (AFTER PERFORMANCE OF STEP 1).

PERFORMANCE STEPS

START TIME

Verify that at least two circulating water pumps are running - YES.

Procedure Step

1

ISAT []

UNSAT []

03/04/08

Evaluator's

Note

Standards

rotes/comments

Provide blank copy of 1-AP-13 to candidate after completion of

Step 1, or at the discretion of the Evaluator candidate may use the

copy that is normally available in the book or spare copy file.

Candidate checks panel and determines Two (2) CirCUlating Water

Pump are running, (observes breaker indication, motor amps, discharge

valve position, etc.).

Page 4 of 11

Check Turbine Load Control.

Procedure Step

2a and 2b

ISAT []

UNSAT []

Standards

[Notes/Comments

Checks EHC Panel and verifies the following:

Turbine Valve Position Limiter Light - NOT LIT.

Turbine Load Control, IMP-IN Liqht - LIT.

Verify Condenser Vacuum < 3.5" Hg and stable - YES.

Procedure Step

3

ISAT[]

UNSAT[]

03/04/08

Standards

Demonstration

Cues

Notes/Comments

Verifies that Condenser vacuum stable at < 3.5 " Hg using recorder on

vertical

anel and/or PCS.

IF candidate states that vacuum is degrading and 1-AP-14 should be

implemented based on the RNa, THEN tell the candidate that another

operator will implement 1-AP-14, continue with 1-AP-13.

Vacuum may be lowering on the order of thousands of an inch if viewed

on the PCS screen, this is for all intensive purposes stable. If the

candidate considered vacuum degrading based on the plant conditions it

may be desirable to follow-up at the conclusion of the JPM (using the

same PCS screen it will show that although several minutes have

elapsed since the time the JPM started, vacuum is essentially

unchanged).

Page 5 of 11

Check operating CWP amps less than 340 amps - YES.

Procedure Step

4

ISAT[]

UNSAT[]

Standards

rotes/comments

Verifies operating CWP (1 Band 1D) amps less than 340 amps.

Check bearing cooling system support.

Procedure Step

5

ISAT[]

UNSAT[]

Standards

INotesiComments

03/04/08

Verifies the following:

Circ Water Intake Tunnel Full Light - LIT.

At least one CWP operating (1 Band 10 CWPs running).

Page 6 of 11

Determine if securing liquid waste releases required - YES.

Procedure Step

6

ICritical Step

ISAT[]

UNSAT[]

Standards

Contacts HP and informs them of CWP status and requests

determination as to if releases need to be secured.

Notes/Comments

HP will advise the operator that the Liquid Release Permit in effect

requires a minimum of 3 CWPs running on Unit 1. If the operator asks

HP to clarify if liquid releases need to be secured HP will concur. The

permit is not normally available in the Control Room; the operator must

obtain the information from HP and based on that information the

operator implements Step 7 of the procedure, otherwise the operator

would go to Step 8 per the RNO and bypass the actions to secure

releases.

03/04/08

Page 7 of 11

7

Verify SG BJowd

Alternate.path

blowdown tri

Procedure Step

7a

I_C_ri_ti_ca_I_S"'---t_eL-P

1SAT []

UNSAT []

Standards

Closes SG Blowdown Trip Vavles on H Safeguards Panel

(per RNO). -7 1-BO-TV-100A, 100C, and 100E.

Closes SG Blowdown Trip Vavles on J Safeguards Panel

(per RNO). -7 1-BO-TV-100B, 1000, and 100F.

Verifies with Unit 2 OATC that Unit 2 Slowdown Trip Valves are

closed.

Notes/Comments

It is only critical to close ONE set of SG Blowdown Trip Valves (H

panel or J panel) as closing either of the valves, which are in series

isolates the flow path.

Blowdown trip valve pushbuttons are located in the lower left hand

corner of the Safeguards panels.

Closing of the valves will actuate the Blowdown system trouble

annunciator; thus this is an expected annunciator.

Locally close BO tank isolation valves.

Procedure Step

7b

ISAT[]

UNSAT[]

Standards

INotes/Comments

03/04/08

Operator dispatched to close the following valves:

1-BO-1005

2-BO-182

Page 8 of 11

Stop the following pumps to prevent clarifier overflow.

Procedure Step

7c

ICritical Step

Standards

ISAT []

UNSAT []

1-LW-P-6A and 1-LW-P-68 are stopped.

1-LW-P-1A and 1-LW-P-1B are verified stopped.

1-BR-P-5A and 1-BR-P-5B are verified stopped.

Notes/Comments

It is only critical to stop 1-LW-P-6A and 1-LW-P-68 as the other

pumps are not running.

Locally secure Containment Matt Sump Pumps.

Procedure Step

7d1 and 7d2

ISAT []

UNSAT []

Standards

INotes/Comments

03/04/08

Operator dispatched to perform the following:

Open SOV breakers 1-EP-DB-2 bkr 6 & 7 AND 2-EP-DB-5

bkr 6 &7.

Verify Pumps are stopped.

Page 9 of 11

11

Verify Liquid waste release secured.

Procedure Step

Alternate Path Step, operator will prace valve in HAND

7e

CONTROL per Step 7e RNO based on Initial Condition of varve

in auto.

ICritical Step

ISAT []

UNSAT []

Standards

Operator places 1-LW-PCV-115 control switch in HAND and verifies

valve closed (per RNa).

Demonstration

At this time another operator will complete the rest of the procedure.

Cues

Notes/Comments

JPM is complete once operator moves forward past Step 7.

>>>>> END OF EVALUATION <<<<<

STOP TIME

03/04/08

Page 10 of 11

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

SIMULATOR SETUP

R517 (Modified)

You are requested to respond to plant conditions in accordance with 1-AP-13

CHECKLIST

__ Recall IC #172 (30% power)

Place clearance info stickers on 1-CW-P-1A control switch AND discharge MOV.

Ensure TavefTref recorder on proper range and check rod bank update.

Booth Operator Actions:

If dispatched to investigate trip of 1-CW-P-1C then wait approximately 3 minutes and respond that

you see nothing obviously wrong with the pump but the breaker does have an over-current target

dropped.

At Step 6 respond as HP that the Liquid Release Permit in effect requires a minimum of 3 CWPs

running on Unit 1. If asked to confirm that releases need to be secured concur with the operator.

If called at Step 7 respond as Unit 2 and confirm that all SG Blowdown Trip Valves on Unit 2 are

closed.

Respond as operator to perform Step 7b of the procedure to close valves 1-BO-1 005 and 2-BO-182

(no manipulations are necessary since these actions are invisible to the OATC) - call back in

- 5 minutes with actions complete.

Respond as operator to perform Step 7d of the procedure to secure Matt Sump Pumps by opening

SOV breakers 1-EP-OB-2 BKR 6 & 7 AND 2-EP-DB-5 BKR 6 & 7 AND verifying Pumps are stopped

(no manipulations are necessary) - call back in - 5 minutes with actions complete if JPM is still in

progress.

03/04/08

Page 11 of 11

Dominion

North Anna Power Station

IN-PLANT JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

Instrument air has been lost.

INITIATING CUE

You are requested to open the Residual Heat Removal Heat Exchanger Cooling Water Return

Valves 1-CC-TV-103A and 1-CC-TV-103B locally in accordance with 1-AP-28, Loss of Instrument

Air, Attachment 3.

03/04/08

.

i-

Dominion

North Anna Power Station

IN-PLANT JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

N925

Open the residual heat removal heat exchanger cooling water return valves using a jumper

(1-AP-28).

TASK STANDARDS

1-CC-TV-103A and 1-CC-TC-103B have been jumpered open.

Work was performed in compliance with the Radiation Work Permit; exposure to surface and

airborne contamination was minimized; and ALARA principles were applied.

KIA REFERENCE:

008-A2.05 (3.3/3.5)

ALTERNATE PATH:

N/A

TASK COMPLETION TIMES

Critical Time = NO

Validation Time =

20 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

03/04/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 13

Dominion

North Anna Power Station

(Evaluation)

OPERATOR PROGRAM

N925

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

Before being Slvaluated on the task, the trainee must have completed the Reactor Operator's course

checkout during which the objectives listed below would have been addressed.

INITIAL CONDIT~ONS

Instrument air has been lost

INITIATING CUE

You are requested to open the Residual Heat Removal Heat Exchanger Cooling Water Return

Valves 1-CC-TV-103A and 1-CC-TV-103B locally in accordance with 1-AP-28, Loss of Instrument

Air, Attachment 3.

03/04/08

Page 3 of 13

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Key to Appendix R storage cabinet (simulate)

Adjustable wrench (simulate)

Nitrogen jumper rig (training rig staged at valves)

Nitrogen or air bottle (simulate)

Copy of 1-AP-28, Attachment 3, to be provided to applicant.

PERFORMANCE STEPS

START TIME

Note: JPM has been formatted for ease of use. Steps in left column correspond to step numbers

of Attachment 3, page number of the attachment is given in the right hand column~

03/04/08

Page 4 of 13

Attachment 3

Pa e 1 of 3

IL..:C......:.r......:.iti......:.c-,--8_1S-=--te.-e.L-p

1SAT []

UNSAT []

Standards

Verbal-Visual

Cues

rotes/comments

Operator explains where to obtain the following:

key to unlock appendix R locker

jumper rig

nitrogen/air bottle

adiustable wrench.

Tell me where you would get the required key.

Show me where you would obtain the jumper rig.

Explain to me how you would obtain a nitrogen/air bottle.

Tell me where you would go to obtain an adjustable wrench.

After the above have been done, give the following cue:

You may assume that you have obtained they key, the jumper rig,

nitroqen/air bottle, and adjustable wrench.

Isolate the instrument air supply to the trip valves.

Attachment 3

Pa e 2 of 3

ISAT[]

UNSAT[]

IStandards

Verbal-Visual

Cues

INotes/Comments

03/04/08

ILocal air supply valves for 1-CC-TV-103A and 103B are closed.

Confirm actions once operator identifies components and describes

action of closing valves.

Page 5 of 13

Connect the regulator to the nitrogen bottle.

Attachment 3

Pa e 2 of 3

IL-C_r_it_ic_8_1S_t_e..L..P

1SAT []

UNSAT []

03/04/08

Evaluator's Note

Standards

Verbal-Visual

Cues

Notes/Comments

The training jumper rig is stored in a box under the desk next to the

valves. The jumper rig should be used to aid in describing the task

from this point forward.

Jumper rig is connected to the nitrogen bottle as follows:

Remove cap from nitrogen bottle

Thread the brass bottle connection on the jumper rig into the

bottle stop connection and tiohten.

Tell trainee to use training jumper rig to facilitate Task explanation.

SEE NOTES

Have operator describe using attachment 3 and the training jumper rig

Once operator has described how to connect the regulator to the bottle

then confirm that rio is connected as described.

Bottle should be located in the vicinity of the CC valves such that jumper

rig can reach both valves. The hoses on the training rig are slightly

shorter than the actual rig since it is not intended to be used in

plant, thus the exact location the trainee simulates placing the

bottle is not critical. If the candidate notes the shorter hoses,

acknowledge and have them continue with task simulation.

Page 6 of 13

NOTE: Steps 3c and 3d may be performed in any order as long as BOTH are performed; although order

is specified procedurally to follow rules of usage, doing them out of order would have no consequence as

it relates to the Task of opening the valves.

Connect the jumper rig to 1-CC-TV-103A by performing the

followin :

ICritical Step

Attachment 3

Pa e 2 of 3

ISAT[]

UNSAT[]

Standard

Using the adjustable wrench, disconnect

copper tubing from the end of 1-CC-TV-1 03A

SAT []

UNSAT []

actuator bv turninq counter-clockwise.

Standard

Using the adjustable wrench, removes the 90°

elbow (tubing-to-pipe thread adapter) from the

SAT []

UNSAT []

bushing of 1-CC-TV-103A actuator by turning

counter-clockwise.

Standard

Remove the quick disconnect adapter from the

jumper rig and thread into1-CC-TV-1 03A

SAT []

UNSAT []

actuator bushina bv turnina clockwise.

Standard

Connect one jumper rig hose to 1-CC-TV-103A SAT []

UNSAT []

actuator bv matinq quick disconnect.

03/04/08

Verbal-Visual

Cues

rotes/comments

Have operator describe using attachment 3 and the training jumper rig

then confirm that ri

is connected as described.

Page 7 of 13

Connect the jumper rig to 1-CC-TV-1 03B by performing the

followin :

ICritical Step

Attachment 3

Pa e 2 of 3

ISAT []

UNSAT []

Standard

Using the adjustable wrench, disconnect

copper tubing from the end of 1-CC-TV-1 03B

SAT []

UNSAT []

actuator by turninq counter-clockwise.

Standard

Using the adjustable wrench, removes the 90°

elbow (tubing-to-pipe thread adapter) from the

SAT []

UNSAT []

bushing of 1-CC-TV-103B actuator by turning

counter-clockwise.

Standard

Remove the quick disconnect adapter from the

jumper rig and thread int01-CC-TV-103B

SAT []

UNSAT []

actuator bushinq by turninq clockwise.

Standard

Connect one jumper rig hose to 1-CC-TV-103B

SAT []

UNSAT []

actuator bv matinq quick disconnect.

Verbal-Visual

Cues

INotes/Comments

03/04/08

Have operator describe using attachment 3 and the training jumper rig

then confirm that ri

is connected as described.

Page 8 of 13

Adjust regulator to full counterclockwise direction.

Attachment 3

Pa e 2 of 3

ISAT []

UNSAT []

'--------------------

ICritical Step

Standards

Backs regulator off by adjust regulator to full counter-clockwise

direction.

Verbal-Visual

Cues

Have operator demonstrate using training jumper rig then confirm

action.

Notes/Comments

Failure to perform this action could over-pressurize the valve actuators

causing damage to the actuator and possible failure of the valves, thus

this step has been deemed critical.

Open Nitrogen/air bottle isolation valve.

Attachment 3

Pa e 2 of 3

I,-C_r_if_lc_a_1S_t_e-'-p

J SAT []

UNSAT []

I..=S=ta=n=d;;,;a=r,;;;,ds=-

IOpen bottle stop by turning in the counter-clockwise direction.

Verbal-Visual

Cues

Have operator describe using attachment 3 then confirm action.

IF operator expresses a pressure observed on the high-pressure gauge

of the jumper riQ, THEN confirm that pressure is as expressed.

INotes/Comments

03/04/08

Page 9 of 13

Open BOTH Nitrogen/air jumper rig shut-off valves.

Attachment 3

Pa e 2 of 3

I_C_r_iti_c_81_S_t_e.L-P

,SAT []

UNSAT []

Standards

Verbal-Visual

Cues

INotes/Comments

03/04/08

Opens BOTH Nitrogen/air jumper rig shut-off valves by turning in the

counter-clockwise direction.

Have operator demonstrate using training jumper rig then confirm

action.

Page 10 of 13

Slowly increase the regulator setpoint until the RHR Heat

Exchan er CC Outlet valves 1-CC-TV-103A and 1038) are 0

ICritical Step

ISAT []

UNSAT []

'---------'--------------------

Evaluator's Note

Valve position indicators for these valves are located on the

underside of the actuator - USE CAUTION if going underneath

valves to have a good visual of the indicators. Trainee may contact

control room to confirm valve position change (indication lights on

Vertical panel) and may also choose to observe valve stem for 90°

rotation any of these means is adequate to confirm that valves opened.

Standards

Increases regUlator output by turning in the clockwise direction until

valves are observed to be 0 en.

Verbal-Visual

Cues

Have operator demonstrate regulator operation using training jumper rig

AND describe how he would tell that the valves are open, then confirm

that the valves are open (may be done by pointing to position indicator

of valves if desired, or as noted above, if operator chooses to contact

the control room then confirmation from the control room that red lights

are LIT and qreen liqhts are NOT LIT for the subiect valves).

Notes/Comments

Multiple means may be used to confirm valve position change, any of

which satisfy the critical step requirement for opening the valves - see

evaluators note above.

03/04/08

Page 11 of 13

Attachment 3

Pa e 2 of 3

Standards

Verbal-Visual

Cues

INotes/Comments

STOP TIME

03/04/08

ISAT [1

UNSAT [1

The control room acknowledges that 1-CC-TV-103A and 103B have

been jumpered open.

A jumper log entry will be made.

Control room directs you to resume normal duties (JPM is complete at

this point or when candidate expresses they have completed

attachment 3)

>>>>> END OF EVALUATION <<<<<

Page 12 of 13

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

Rig staged in box underneath desk next to valves

03/04/08

Page 13 of 13

Dominion

North Anna Power Station

IN-PLANT JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

The Unit is in Mode 1 and Power to 1-1 vital bus has been lost.

1-1 vital bus and inverter have been inspected and approved for use by Electrical Department.

The 1-1 inverter and regulating transformer were recently untagged and are available for use.

Equipment status has been reviewed and station configuration will support placing the inverter in

service.

Loaded testing is not required.

No circuit breakers were found trip.

Inverter Trouble annunciator was not defeated.

There are 3 circulating water pumps in operation.

INITIATING CUE

You are requested to re-energize vital bus 1-1 from inverter 1-1 and to energize the bypass

transformer in accordance with 1-MOP-26.60, Vital Bus 1-1, Subsection 5.4, Reenergizing Vital Bus

1-1 from Inverter 1-1.

03/04/08

I

J

Dominion

North Anna Power Station

IN-PLANT JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

N30

Re-energize a 120-volt vital bus from its inverter (1-MOP-26.60).

TASK STANDARDS

Vital bus 1-1 has been energized from inverter 1-1 and its bypass transformer is energized.

KIA REFERENCE:

057-AA1.01 (3.7/3.7)

ALTERNATE PATH:

TASK COMPLETION TIMES

Validation Time =

25 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

Stop Time =

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature 1

Date

EVALUATOR'S COMMENTS

03/04/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 13

Dominion

North Anna Power Station

(Evaluation)

OPERATOR PROGRAM

N30

READ THE APPLICABLE INSTRUCTIONS TO THE CANDIDATE

Instructions for Simulator JPMs

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

be performed for this JPM, including any required communications. I will provide initiating cues

and reports on other actions when directed by you. Ensure you indicate to me when you

understand your assigned task. To indicate that you have completed your assigned task return

the handout sheet I provided you.

Instructions for In-Plant JPMs

I will explain the initial conditions, and state the task to be performed. All steps, including any

required communications, shall be simulated for this JPM. Under no circumstances are you to

operate any plant equipment. I will provide initiating cues and reports on other actions when

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

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

PREREQUISITES

Before being evaluated on the task, the trainee must have completed the reactor operator's course

checkout during which the objectives listed below would have been addressed.

INITIAL CONDITIONS

The Unit is in Mode 1 and power to 1-1 vital bus has been lost.

1-1 vital bus and inverter have been inspected and approved for use by Electrical Department.

The 1-1 inverter and regulating transformer were recently untagged and are available for use.

Equipment status has been reviewed and station configuration will support placing the inverter in

service.

03/04/08

Page 3 of 13

Loaded testing is not required.

No circuit breakers were found trip.

Inverter Trouble annunciator was not defeated.

There are 3 circulating water pumps in operation.

INITIATING CUE

You are requested to re-energize vital bus 1-1 from inverter 1-1 and to energize the bypass

transformer in accordance with 1-MOP-26.60, Vital Bus 1-1, Subsection 5.4, Reenergizing Vital Bus

1-1 from Inverter 1-1.

EVALUATION METHOD

Demonstration if conducted in the simulator or in a laboratory (use DEMONSTRATION cues)

Verbal-visual if conducted in the station or on a dead simulator (use VERBAL-VISUAL cues)

TOOLS AND EQUIPMENT

Copy of 1-MOP-26.60, Section 1-4, Subsection 5.4, and Att. 4 to be provided to applicant.

PERFORMANCE STEPS

START TIME

03/04/08

Page 4 of 13

Initial conditions are satisfied.

Procedure Step

5.4.1

ISAT[]

UNSAT[]

IStandards

IInitial Conditions of JPM are checked.

Notes/Comments

This information is specified in the JPM IC sheet so no cue is needed.

Review Precautions and Limitations.

Procedure Step

5.4.2

ISAT[]

UNSAT[]

I....:;S;;.:;:ta~n.:.:;d:.;;;:a~rd~s:.....-__1 Procedure precautions and limitations are reviewed.

INotes/Comments

Verify that the Electrical Department has approved the bus to be re-

Procedure Step

ener ized.

5.4.3a - 5.4.3d

ISAT[]

UNSAT[]

03/04/08

IStandards

rotes/comments

I Initial conditions of JPM are checked to verify bus can be re-energized.

Page 5 of 13

Ensure that the AUTO RE-TRANSFER switch is in OFF.

NOTE TO THE

EVALUATOR

Standards

Verbal-Visual

Cues

ISAT []

UNSAT []

Have operator explain where switch is located and how it would be

checked. DO NOT 0 en cabinet.

Refer to Attachment 4 of

rocedure

Operator explains that switch is located inside top, right cabinet and

that the switch would be down if it was OFF.

Explain how you would perform this step.

Assume another operator has verified that the auto re-transfer switch is

OFF.

Notes/Comments

Step 5.4.3f is N/A per the Initial Conditions (loaded testing is NOT

required)

4

Open breaker #19 on SOV panel 1-EP-CB-19A if the following

Procedure Step

conditions exist.

5.4.4

One or two circulating water pumps are running and Vital SOV

panel 1-EP-CB-19A is de-enerqized.

ISAT[]

UNSAT[]

I...;;;S;,;;;ta;;:;,n~d;;;;;a.:.;rd:.;;;s~__1Operator N/As step based on Initial Conditions (3 CWPs running).

rotes/comments

03/04/08

Page 6 of 13

NOTE: It is not necessary for the candidate to open door for 1-EP-CB-12A panel. The breaker and

position (ON) is well labeled; trainee should describe actions.

Ensure that the DC vital bus 1-1 (1-EP-CB-12A) breaker #13 is

closed.

Procedure Step

5.4.5

ISAT []

UNSAT []

I~S~ta~n~d:;;:,a:.;;rd;,;;;s~__11-EP-CB-12A, breaker #13 is verified to be ON (closed).

Verbal-Visual

Cues

rotes/Comments

Once described by the operator confirm that the breaker is ON.

Enable annunciators if required.

Procedure Step

5.4.6

ISAT []

UNSAT []

IStandards

INotes/Commenls

IOperator N/As step based on Initial Conditions.

Clear associated danger tags, if required.

Procedure Step

5.4.7

ISAT []

UNSAT []

1t...,;;S;;,:,ta~n.:.;;d~a_rd::;;;sL..-__1Operator N/As step based on Initial Conditions.

INoles/Commenls

03/04/08

Page 7 of 13

Energize and align the inverter for normal operation.

Procedure Step

5.4.8a - 5A.8f

I-:.C_ri_ti_c-r-al_S_t_epL--

1SAT []

UNSAT []

Standards

The following actions are performed in

sequence:

NokJ-

5.4.8a ~ Depress the PRECHARGE push-

SAT []

UNSAT []

button

5.4.8b ~ When the precharge light is lit, then

release the PRECHARGE push-button.

SAT []

UNSAT []

5.4.8c ~ Close the DC input breaker.

SAT []

UNSAT []

5.4.8d ~ Close the inverter output breaker.

SAT []

UNSAT []

5.4.8e and 5A.8f ~ allow inverter to warm-up

SAT []

UNSAT []

Verbal-Visual

Cues

5A.8a&b ~ After about 5 seconds tell operator Precharge light is lit.

5A.8c ~ When manipulation is described by the Operator confirm that

the DC input breaker is as it appears now.

5.4.8d ~ When manipulation is described by the Operator confirm that

the Inverter Output breaker is as it appears now.

5.4.8e ~ When operator describes that they would expect output

voltage to slowly ramp up and stabilize, then tell them Output voltage is

as it appears now.

5.4.8f ~ When operator describes that they would expect frequency to

ramp up and stabilize, then tell them frequency is as it appears now.

Notes/Comments

Steps 5.4.8e and 5.4.8f are not critical as they will occur without

any action needed.

03/04/08

Nok 1. '

NOTE: IF desired by the evaluator, the second bullet may be performed out of order (following

c,?mplE!tion of the JPM) for convenience - see cues and comments below.

~~..

-~

Close the vital bus panel's isolation breaker, the main feeder

breaker from the transformer switch, and re-install the tam er seal.

Procedure Step

504.9a - 504.9b

IL..:C:....::...r =iti:....:.c..=8-=--1S=-t=e.L:..p

1SAT []

UNSAT []

Standards

Close the following:

1-EP-CB-001 breaker taken to CLOSE

SAT []

UNSAT []

(ON).

1-EP-CB-4A breaker 35 taken to CLOSE

SAT []

UNSAT []

(ON).

Verbal-Visual

Cues

Assume that another operator has provided SVs.

When identified by the operator tell them 1-EP-CB-001 (knife

switch located adjacent to inverter) breaker is as they see it

now.

IF desired for efficiency, THEN tell the operator they may assume

1-EP-CB-4A breaker 35 is closed and continue with the task (after

the inverter &transformer is energized have the trainee identify

the panel).

OR if desired to perform at this time, THEN

When identified by the operator, THEN confirm 1-EP-CB-4A

(panel located behind control room) breaker 35 is closed.

504.9.b -7 When identified by the operator: Tell Operator that another

operator will install the tamper seal.

03/04/08

Notes/Comments

This substep may be verified after inverter is &transformer have

been energized at the discretion of the evaluator.

Substep 5.4.9.b is not critical to this element as installing the

tamper seal is administrative and nature and does not affect the

outcome of the Task.

Page 9 of 13

10

Transfer the vital bus load to the inverter by performing the

Procedure Step

following action:

5.4.10

Place the manual bypass switch in the INVERTER TO LOAD

position.

ICritical Step

ISAT[]

UNSAT[]

Standards

5.4.10 -7 Vital bus 1-1 manual bypass switch is

SAT []

UNSAT []

rotated to the INVERTER TO LOAD position.

03/04/08

Verbal-Visual

Cues

rotes/comments

Assume that another operator has provided SVs.

5.4.10 -7 When identified by the operator: Tell Operator that the manual

bypass switch is as it appears now.

Page 10 of 13

11

Transfer the vital bus load to the inverter by performing the

Procedure Step

following action:

5.4.11

Depress the INVERTER to LOAD pushbutton.

ICritical Step

Standards

5.4.11 ~ Inverter to LOAD pushbutton

de ressed.

ISAT []

UNSAT []

SAT []

UNSAT [ ]

Verbal-Visual

Cues

[Notes/Comments

Assume that another operator has provided SVs.

5.4.11 ~ When identified by the operator: Tell Operator that the

Inverter Supplyinq Load Liqht is as it appears now.

Verify that the vital bus is energized and is indicating about 120

volts.

Procedure Step

5.4.12

ISAT []

UNSAT []

I....S_ta...n...d..a...rd;;;;s'----__ 1 Operator checks vital bus voltage is approximately 120 volts.

03/04/08

Verbal-Visual

Cues

INotes/Comments

Tell Operator Vital bus voltage is as it appears now.

Page 11 of 13

13

If the vital bus bypass transformer was also de-energized, perform

Procedure Step

the following actions:

5.4.13a - 5.4.13d

I_C_ri_ti_c_81_S_t_e.L-P

1SAT []

UNSAT []

Standards

5.4.13a ~ 1-EE-BKR-1H1-4 C3L,

SAT []

UNSAT []

Vital Bus 1-1 Bypass transformer circuit

breaker is closed.

5.4.13b ~ 1-VB-INV-01, AC input to

SAT []

UNSAT []

regulator is ON.

5.4.13c ~ Allow Voltage regulating

SAT[]

UNSAT []

transformer to warm-up until output voltage is

114-125 volts.

5.4.13d ~ 1-VB-INV-01, Bypass source AC

SAT[]

UNSAT []

input breaker is ON.

Verbal-Visual

Cues

Assume that another operator has provided SVs.

5.4.13a ~ When identified by Operator confirm that breaker is as it

appears now.

5.4.13b ~ When identified by Operator confirm that breaker is as it

appears now.

5.4.13c ~ When operator identifies requirement tell them the

Transformer has warmed up and desired output voltage is indicated.

5.4.13d ~ When identified by Operator confirm that breaker is as it

appears now.

Tell the Operator that another operator will complete the

procedure.

IF not previously done, THEN have candidate identify 1-EP-CB-4A

(panel located behind control room) breaker 35.

Notes/Comments

5.4.13c ~ Allow Voltage regulating transformer to warm-up until output

voltage is 114-125 volts is NOT critical to this element as this will occur

without any action by the operator.

>>>>> END OF EVALUATION <<<<<

STOP TIME

03/04/08

Page 12 of 13

None

03/04/08

SIMULATOR, LABORATORY, IN--PLANT SETUP

(If Required)

Page 13 of 13

Dominion

North Anna Power Station

IN-PLANT JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

INITIAL CONDITIONS

The OATe attempted to trip UNIT 2 and the reactor DID NOT trip.

INITIATING CUE

You are requested to trip the UNIT 2 reactor locally in accordance with Attachment 4, Remote Reactor

Trip, of 2-FR-S.1, Response to Nuclear Power Generation/ATWS.

02/28/08

Dominion

North Anna Power Station

IN-PLANT JOB PERFORMANCE MEASURE EVALUATION

OPERATOR PROGRAM

N1047

Trip the reactor by opening the reactor trip breakers or the rod-drive motor generator breakers

locally (2-FR-S.1, 2-AP-20).

TASK STANDARDS

The reactor was tripped by locally tripping MG set supply breakers in 307 Switchgear.

KIA REFERENCE:

029-EA1.12 (4.1/4.0) (Note: This task is categorized as Safety Function 1 per ES-401-2)

ALTERNATE PATH:

YES

TASK COMPLETION TIMES

Validation Time =

10 minutes

Actual Time =

minutes

PERFORMANCE EVALUATION

Start Time =

_

StopTime=

_

Rating

Candidate (Print)

Evaluator (Print)

Evaluator's Signature /

Date

EVALUATOR'S COMMENTS

02/28/08

[ ] SATISFACTORY

[ ] UNSATISFACTORY

Page 2 of 8

Dominion

North Anna Power Station