ML022690280

Operating Test Number:

b

"Describe method of evaluation:

"-Administrative

1. ONE Administrative JPM, OR

Topic/Subject

2. TWO Administrative Questions

Description

(KA #)

"'A.

1

Determine Rod Misalignment Using Thermocouples (AOP-001)

CONDUCT OF

OPERATIONS

(2.1.19)

Perform a Manual Power Range Heat Balance Calculation

(OST-1204)

(2.1.25)

"A.

Review an Equipment Clearance (OPS-NGGC-1 301)

EQUIPMENT

CONTROL

(2.2.13)

"A.

RADIATION

CONTROL

(2.311)

?

5

6 Xzto(,c

t @-'-V s

p

"A.

4

Activate the Emergency Response Organization - Dialogic

EMERGENCY

System (PEP-310)

PLAN

(2.4.43)

NUREG-1021, Revision 8, Supplement 1

Administrative Topics Outline

FORM ES-301-1

Facility:

HARRIS

Date of Examination:

26-Aug-02

Examination Level:

Operating Test Number:

"Describe method of evaluation:

"-Administrative

1. ONE Administrative JPM, OR

Topic/Subject

2. TWO Administrative Questions

Description

I(KA #)

"A,1

Perform Review of Daily Surveillance Requirements Log

LA.JJ-,

-irnT

nc

I(OST-1021)

OPERAIONS

OPERATIONS

EQUIPMENT

CONTROL

RADIATION

CONTROL

(2.1.18)

Perform a Manual Power Range Heat Balance Calculation

(OST-1204)

(2.1.25)

Review an Equipment Clearance (OPS-NGGC-1 301)

(2.2.13)

Question Topic - License Requirements for Conducting a Waste

Release with Inoperable Instrumentation and Administrative

Controls Ensuring Requirements Met (2.3.6)

Question Topic - Selection Process for Individuals Performing

Emergency Entries into Radiation Fields Resulting in Exceeding

Permissible Exposure Limits (2.3.4)

Perform an Emergency Action Level Classification and

Recommend Protective Actions (PEP-1 10)

4

PLAN

(2.4.41 / 2.4.44)

NUREG-1021, Revision 8, Supplement 1

2

"A.

3

"A.

ES-301

Control Room Systems and Facility Walk-Through Test Outline

FORM ES-301-2

Facility:

HARRIS

Date of Examination:

26-Aug-02

Examination Level:

Operating Test Number:

2002-301

B.1

Control Room Systems

Safety

System/JPM Title

Type

Function

Code*

(KA #)

a.

NAS

3

Respond to a Failed High Pressurizer Pressure Channel (AOP-019)

(010.A2.03)

b.NAS

6

LOOP While Paralleling EDG from MCB for Testing (OP-155)

(064A4.01)

C.

DS

8

Secure One Train of CCW to the RHR HXs (OP-145)

(008A2.01)

d.

DASL

5

Manually Align Containment Spray (PATH-l)

(026A4.01)

e,

DASL

2

Transfer to Hot Leg Recirculation (EPP-011)

(006A4.05)

f.

DSL

4P

Start an RCP Following Maintenance (OP-1 00)

(003A4.06)

g.

NS

7

Power Range NI Gain Adjustment (OP-1 05)

(015A4.02)

B.2

Facility Walk-Through

a.

DL

1

Local Actions for a Dropped Rod Recovery (AOP-001)

(003AA1.02)

b.

b.DRL

2

Manually Align Charging Due to a Loss of IA (AOP-017)

(004A2.11)

C.

c.DL

5

Start Up a Hydrogen Recombiner (OP-125)

(028A4.01)

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate path, (C)ontrol Room, (S)imulator,

(L)ow-Power, (R)CA

NUREG-1021, Revision 8, Supplement 1

ES-301

Control Room Systems and Facility Walk-Through Test Outline

FORM ES-301-2

Facility:

HARRIS

Date of Examination:

26-Aug-02

Examination Level:

SRO-I

Operating Test Number:

2002-301

B.1

Control Room Systems

Safety

System/JPM Title

Code*

Function

a.

NAa

Respond to a Failed High Pressurizer Pressure Channel (AOP-019)

NAS

3

(010.A2 .03)

b.NAS

6

LOOP While Paralleling EDG from MCB for Testing (OP-155)

(064A4.01)

(0264A4.01)

Secure One Train of CCW to the RHR HXs (OP-1 45)

DS08A.)

d.

DS

Manually Align Containment Spray (PATH-l)

(0264.01

e.DASL

2

Transfer to Hot Leg Recirculation (EPP-011)

(006A4.05)

f.DSL

4P

Start an RCP Following Maintenance (OP-100)

(0034P

(003A4.06)

Power Range NI Gain Adjustment (OP-105)

(01 5A4.02)

B.2

Facility Walk-Through

a.

a.DL

1

Local Actions for a Dropped Rod Recovery (AOP-001)

(003AA1.02)

b.

DRL

2

Manually Align Charging Due to a Loss of IA (AOP-017)

(004A2.11)

C.

c.DL

5

Start Up a Hydrogen Recombiner (OP-125)

DL40

I (028A4.01)

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)Iternate path, (C)ontrol Room, (S)imulator,

(L)ow-Power, (R)CA

NUREG-1021, Revision 8, Supplement 1

ES-301

Control Room Systems and Facility Walk-Through Test Outline

FORM ES-301-2

Facility:

HARRIS

Date of Examination:

26-Aug-02

Examination Level:

SRO-U

Operating Test Number:

2002-301

B.1

Control Room Systems

Safety

System/JPM Title

Code*

Function

(KA#)

a.

Respond to a Failed High Pressurizer Pressure Channel (AOP-019)

NAS(

3

(0l0.A2 .03)

b.

b.NAS

6

LOOP While Paralleling EDG from MCB for Testing (OP-1 55)

(064A4.0l)

C.

d.

e.

f.

g.

B.2

Facility Walk-Through

a.

a.DL

1

Local Actions for a Dropped Rod Recovery (AOP-001)

(OO3AA1.02)

b.

b.DRL

2

Manually Align Charging Due to a Loss of IA (AOP-017)

(004A2.1l)

c.

c.DL

5

Start Up a Hydrogen Recombiner (OP-125)

(028A4.01)

Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator,

(L)ow-Power, (R)CA

NUREG-1021, Revision 8, Supplement 1

JPM SRO-A.1-1

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM SRO-A. 1.1

Perform Review of Daily Surveillance Requirements

Log

CANDIDATE:

EXAMINER:

Page 1 of 8

Rev Date 07/25/02

JPM SRO-A.1-1

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Perform Review of Daily Surveillance Requirements Log

None

ALTERNATE PATH:

FACILITY JPM NUMBER:

KA:

2.1.18

NEW

IMPORTANCE:

3.0

KA STATEMENT:

TASK STANDARD:

Ability to make accurate, clear and concise logs, regards,

status boards, and reports.

Four of five (4/5) errors on attached log sheet are identified.

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

v'

PERFORM

1

IN PLANT

SIMULATE

REFERENCES:

OST-1021, Daily Surveillance Requirements, Daily Interval, Mode

1 and 2

VALIDATION TIME:

20

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 8

Rev Date 07/25/02

TASK:

NA

No

Date

JPM SRO-A.l-1

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

"

Complete OST- 1021, Attachment 4, for the 0300 readings using values expected at

100% power.

"* Substitute the following incorrect data:

"* Accumulator CLAB Previous Day Level @ 68% (both 924 and 926) with 0300

readings at 78% and 79%, while indicating sampling is NOT required.

"* RWST Level Channel 993 @ 91%.

"* Pressurizer Pressure channels 455 @ 2220 psig, 456 @ 1960 psig, 457 @ 2230

psig while indicating acceptance criteria is met and channel check is SAT.

"* Containment Temperature channel TCV97540 as "NA", 7542 @ 121'F, 7541 @

11 60F while indicating acceptance criteria is met.

"* EDG Room Temperature channel TDG6903A @ @ 11 80F and TDG6903B @

121°F

OST-1021, "Daily Surveillance Requirements, Daily Interval, Mode 1 and 2,"

Attachment 4, "Daily Surveillance Requirements Log"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

The plant is operating at 100% power.

The Daily Surveillance Logs (OST-1021, Attachment 4) for 0300 have been

completed.

INITIATING CUE(S):

You are to review OST-1021, Attachment 4, noting all errors.

Page 3 of 8

Rev Date 07/25/02

JPM SRO-A.l-1

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH COMPLETED OST-1021,

ATTACHMENT 4.

NOTE: ONLY THOSE ITEMS IN THE LOGS WHICH ARE INCORRECT ARE

IDENTIFIED IN THIS JPM.

1

Attach 4

Cold Leg Accumulator

Identifies that level has

Critical to

Sheet 1

CLA B requires sampling

increased more than

identify error that

due to increase in level of >

9% and requires

sampling is

9%

sampling

required.

2

Attach 4

RWST Level Channel 993 is

Identifies that level

Critical to

Sheet 2

below minimum required

is below minimum

identify BOTH

level of 92% AND Channel

required

level is below

Check is NOT sat

Identifies that

minimum

Channel Check is

required AND

not sat

channel check is

not sat

3

Attach 4

Pressurizer Pressure is

Determines channel

Critical to identify

Sheet 3

incorrectly logged for

456 should be marked

that channel 456

Channel 456

NA in reading OR

should either be

should be included in

logged as NA or

should be included

calculation

in the calculation.

If required, the

attached followup

question must also

be correctly

answered to

consider this error

identification as

SAT.

NOTE: IF REQUIRED TO DETERMINE REASON FOR DECLARING

PRESSURIZER PRESSURE INCORRECTLY LOGGED IN JPM STEP 3 ABOVE,

USE THE ATTACHED FOLLOWUP QUESTION.

4

Attach 4

Containment Temperature

Identifies that

Critical to

Sheet 8

Channel TI-7542 exceeds

temperature exceeds

identify that

limit of 1200F

maximum limit

temperature is

above maximum

allowed.

Page 4 of 8

Rev Date 07/25/02

JPM SRO-A.1-1

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEP

UNSAT

5

Attach 4

Diesel Generator Room 261

Identifies that

Critical to

Sheet 10

temperature TDG6903B

temperature exceeds

identify that

exceeds limit of 1200F

maximum limit

temperature is

above maximum

allowed.

NOTE: FOUR OF THE ABOVE FIVE ERRORS (4/5) ARE REQUIRED TO BE

IDENTIFIED TO DEMONSTRATE SATISFACTORY PERFORMANCE OF THE

JPM.

TASK COMPLETE

STOP TIME:

Page 5 of 8

Rev Date 07/25/02

JPM SRO-A.1-1

HARRIS

JPM FOLLOWUP QUESTION

QUESTION:

When determining that the Pressurizer Pressure reading was incorrectly logged, what was

your reasoning for making this determination?

EXPECTED RESPONSE:

Channel 456 falls well outside the range of conditions for the other channels and for plant

conditions.

If the channel is inoperable, the value should NOT be logged. "NA" should be inserted

with a note included stating that the channel has been declared inoperable.

If the channel is not declared inoperable until after taking the reading, the value of

channel 456 should be used in the calculation to determine if acceptance criteria is met.

In this case, both the channel check and the acceptance criteria would NOT be met and

the initials should have not been included stating that both are met.

RESPONSE:

UNSAT

Page 6 of 8

Rev Date 07/25/02

JPM SRO-A.1-1

HARRIS

JPM ATTACHMENT

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

OST-1021, Attachment 4, Sheets 1-15

Page 7 of 8

Rev Date 07/25/02

JPM SRO-A.1-1

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is operating at 100% power.

The Daily Surveillance Logs (OST-1021, Attachment 4) for 0300 have been

completed.

INITIATING CUE(S):

You are to review OST-1021, Attachment 4, noting all errors.

Page 8 of 8

Rev Date 07/25/02

JPM RO-A.1-1

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM RO-A. 1.1

Determine Rod Misalignment Using

Thermocouples

CANDIDATE:

EXAMINER:

Page 1 of 8

Rev Date 07/21/02

JPM RO-A.1-1

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Determine Rod Misalignment Using Thermocouples

ALTERNATE PATH:

None

FACILITY JPM NUMBER:

NEW

KA:

2.1.19

IMPORTANCE:

NA

KA STATEMENT:

TASK STANDARD:

Ability to use plant computer to obtain and evaluate

parametric information on system or component status.

Determines Shutdown Bank A Rod C9 is misalignment is

NOT verifiable using incore thermocouples

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

v'

PERFORM

1'

IN PLANT

SIMULATE

REFERENCES:

AOP-001, Malfunction of Rod Control and Indication System

VALIDATION TIME:

10

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 8

Rev Date 07/21/02

TASK:

4.4

No

Date

JPM RO-A.1-1

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

Provide candidate with values from JPM Attachment which contains list of thermocouple

temperatures in alphanumeric order after candidate states how information will be

obtained.

AOP-001, "Malfunction of Rod Control and Indication System"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

The plant is operating at 100% power.

AOP-001, "Malfunction of Rod Control and Indication System," is being performed in

response to suspected indications that Shutdown Bank A Rod C9 may be misaligned

by more than 12 steps.

INITIATING CUE(S):

You have been directed to determine whether the Core Exit Thermocouples support

the indication of a misaligned rod per AOP-00 1, Attachment 1, "Indications of

Misaligned Rod."

Page 3 of 8

Rev Date 07/21/02

JPM RO-A.1-1

HARRIS

START TIME:

DENOTES CRITICAL STEP

Page 4 of 8

Rev Date 07/21/02

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH CURRENT COPY OF AOP-001,

ATTACHMENTS 1 AND 2

NOTE: EXAMINER'S ANSWER KEY IS INCLUDED, WHICH INDICATES

THE INFORMATION THAT THE CANDIDATE SHOULD DETERMINE.

PROCEDURE STEPS LISTED ON THIS JPM IDENTIFY THOSE STEPS AS

LISTED ON THE ATTACHMENTS.

Att 1

Greater than 100F difference

Refers to AOP-001,

between thermocouples

Attachment 2

adjacent to the misaligned rod

and the average of symmetric

thermocouples (Perform

Attachment 2)

2

Att 2 - 1

Determine thermocouple

Using core grid

Critical to

location(s) adjacent to the

map, determines

determine

misaligned rod using core

thermocouple

adjacent

grid map (Sheet 1), and

adjacent to Rod C9

thermocouple

circle locations(s) in Table

is in location C8

location to allow

above. These thermocouple(s)

Circles location C8

determining

are affected.

on table

which

thermocouples

are symmetric.

Only

determination is

critical.

JPM RO-A.1-1

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

3

Att 2 - 2

Record values for all operable

Records following

affected and symmetric

values for affected and

thermocouples using the

symmetric

RVLIS Console or ERFIS.

thermocouples:

Symmetric thermocouples are

.

C08 (aff) - 6020F

those in the same row.

a

H13 (sym)- 6080F

N08 (sym) - 608'F

H03 (sym) - 609'F

CUE

(PROVIDED AFTER CANDIDATE STATES THEY MUST OBTAIN

THERMOCOUPLE TEMPERATURES FROM RVLIS CONSOLE OR ERFIS)

PROVIDE TEMPERATURES WHICH CANDIDATE REQUESTS BASED ON

THERMOCOUPLE LOCATION FROM JPM ATTACHMENT.

4

Att 2 - 3

Determine the average of

Determines average of

Critical to

symmetric thermocouples,

symmetric

correctly

for each affected

thermocouples -

determine the

thermocouple.

608.33T

average of the

symmetric

thermocouples

for comparison to

the affected

thermocouple.

5

Att 1

Determine if Core Exit

Determines Core Exit

Critical to

Thermocouples support

Thermocouples do'

determine that

indication of misaligned rod

NOT support

the thermocouple

indication of

indications do not

misaligned rod due to

support

difference between

indication of a

affected thermocouple

misaligned rod.

and symmetric

thermocouple being

<10F ( 6.330F)

TASK COMPLETE

STOP TIME:

Page 5 of 8

Rev Date 07/21/02

JPM RO-A.1-1

HARRIS

JPM RO-A.1.1 ATTACHMENT

INCORE THERMOCOUPLE TEMPERATURES

(Thermocouples are listed in alphanumeric order)

THERMOCOUPLE

TEMP

THERMOCOUPLE

TEMP

LOCATION

(in °F)

LOCATION

(in °F)

A08

ABANDONED

H09

622

B05

590

Hil

618

B1O

588

H13

608

C08

602

H15

603

C12

605

J02

604

D03

608

J10

615

D05

611

J12

ABANDONED

E04

606

K03

604

E07

610

K05

611

E08

619

K08

615

El0

618

Kl1

ABANDONED

E12

614

L06

615

E14

604

LOB

614

F03

ABANDONED

L12

609

F05

614

L14

ABANDONED

F09

614

M03

606

Fll

615

M09

618

F13

608

M11

617

G01

ABANDONED

N04

609

G02

604

N06

610

G06

611

N08

608

G08

621

N10

608

G15

603

P07

607

H03

609

P08

604

H05

616

R07

613

Page 6 of 8

Rev Date 07/21/02

JPM RO-A.1-1

HARRIS

ANSWER KEY FOR JPM RO-A.1-1

Attachment 2

Sheet 2 of 2

Affected and Symmetric Thermocouple Locations

NOTE

810, E07, K08, and P08 have no symmetric locations.

GRID

I

II

____I1l

IV

TRAIN

A

B

A

B

A

B

A

B

A08*

H 15

G01*

G15

R07

S

L

BE5

214

L14"

Y

0

_C08_

H13

N08

H03

M

C

0

X

C12

N04

M03

M

A

E04

D05

E12

M11

L12

E

T

Hll

E08

LOB

H05

T

I

F05

F11

E10

K1"*

K05

L06

R

0

F03*

F13

N10

N06

K03

I

N

G06

F09

J10

C

S

G08

H09

G02

J02

P07

M09

J12*

Thermocouples abandoned by EC 47997

1. Determine thermocouple location(s) adjacent to the misaligned rod using core grid map

(Sheet 1), and circle locations(s) in Table above. These thermocouple(s) are affected.

2. Record values for all operable affected and symmetric thermocouples using the RVLIS

Console or ERFIS. Symmetric thermocouples are those in the same row.

Affected TC #1 _C08_(62) Symmetric TC(s) H13 608-- N08

0

6 8) -H0 3 (609)

"* Affected TC #2

Symmetric TC(s)

(AVERAGE = 608.33)

"* Affected TC #3

._

Symmetric To(s)

"* Affected TC #4 __

Symmetric TC(s)

3. Determine the average of symmetric thermocouples, for each affected thermocouple.

Page 7 of 8

Rev Date 07/21/02

JPM RO-A.1-I

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is operating at 100% power.

AOP-001, "Malfunction of Rod Control and Indication System," is being performed in

response to suspected indications that Shutdown Bank A Rod C9 may be misaligned

by more than 12 steps.

INITIATING CUE(S):

You have been directed to determine whether the Core Exit Thermocouples support

the indication of a misaligned rod per AOP-00 1, Attachment 1, "Indications of

Misaligned Rod."

Page 8 of 8

Rev Date 07/21/02

JPM COM-A. 1-2

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-A. 1-2

Perform a Manual Power Range Heat Balance

Calculation

CANDIDATE:

EXAMINER:

Page 1 of 12

Rev. Date 07/21/02

JPM COM-A. 1-2

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Perform a Manual Power Range Heat Balance Calculation

ALTERNATE PATH:

None

FACILITY JPM NUMBER:

NEW

KA:

2.1.25

IMPORTANCE:

4.6

KA STATEMENT:

TASK STANDARD:

Ability to obtain and interpret station reference materials

such as graphs, monographs, and tables which contain

performance data.

Heat balance has been calculated within allowable tolerance

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

PERFORM

IN PLANT

.-

SIMULATE

REFERENCES:

"* OST-1204, Power Range Heat Balance, Manual Calculation, Daily

Interval, Mode 1 (Above 15% Power)

"* Steam Tables

VALIDATION TIME:

30

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 12

Rev. Date 07/21/02

TASK:

4.4

No

Date

JPM COM-A.1-2

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

"* Provide candidate with Attachment which contains collected data and required forms

to fill out.

"* Examiner's Answer Key is also included as Attachment.

"* OST-1204, Power Range Heat Balance, Manual Calculation, Daily Interval, Mode 1

(Above 15% Power)

"* Steam Tables

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

The plant is operating at approximately 100% power. ERFIS is out-of-service and is

expected to be out for an extended period of time.

OST-1204, Power Range Heat Balance, Manual Calculation, Daily Interval, Mode 1

(Above 15% Power) is to be performed to meet the periodic surveillance requirement

for Technical Specification 4.3.1.1, Table 4.3-1, Item 2a.

Steam Generator Blowdown is isolated.

I&C Technicians have collected all necessary data for the calculation.

INITIATING CUE(S):

You have been directed to perform OST-1204, Power Range Heat Balance, Manual

Calculation, Daily Interval, Mode 1 (Above 15% Power), by completing Attachment

5, "Calorimetric Worksheet," and Attachment 6, "Certifications and Reviews."

NOTE: The Examiner will provide you with completed Attachments 1-4 and copies

of Attachments 5 and 6 for you to complete.

Page 3 of 12

Rev. Date 07/21/02

JPM COM-A. 1-2

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH COMPLETED ATTACHED copy of OST

1204, ATTACHMENTS 1-6.

NOTE: FOLLOWING JPM STEPS DESCRIBE HOW ATTACHMENTS 5 AND 6

OF OST-1204 ARE TO BE FILLED OUT.

EXAMINER'S ANSWER KEY IS INCLUDED. BOLDED ITEMS ARE

CONSIDERED TO BE THE CRITICAL STEPS REQUIRED TO

SUCCESSFULLY COMPLETE THIS JPM.

PROCEDURE STEPS LISTED ON THIS JPM IDENTIFY THOSE STEPS AS

I ,ITIT*f AN THE ATTACHMENTS.

I__

_

I

Ir

______________________ _______________________________________________________

I-

___________________

Calculate Steam Generator

Exit Enthalpies:

Steam Tables Lookup:

Saturated Steam,

Liquid Enthalpies

1) Fills in SG Pressures

from Att 3 as SG A

- 900, SG B - 890,

SGC-900

2) Looks up liq

enthalpy for SG

pressures as SG A

526.7, SG B

525.0+0.2

(interpolation

required), SG C

526.7

3) Looks up steam

enthalpy for SG

pressures as SG A

- 1196.4, SG B

1196.7+0.2

(interpolation

required), SG C

1196.4

Critical to

accurately

determine steam

enthalpy to

determine power

level.

Note liquid

enthalpy value is

NOT critical

since it will be

multiplied by

zero in next step.

Page 4 of 12

Rev. Date 07/21/02

1

Att. 5

la

1

L

-

--

JPM COM-A. 1-2

HARRIS

3PM

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

2

Att. 5 -

.

Calculate SG Exit

Determines SG exit

Critical to

lb

Steam Enthalpies

enthalpies, by

accurately

multiplying liq

calculate exit

enthalpy by zero and

enthalpy to

then substracting from

determine power

steam enthalpy (same

level.

value as steam

enthalpy), as SG A -

Note that

1196.4, SG B -

tolerance is

1196.7+0.2, SG C -

carried forward.

1196.4

3

Att. 5 - 2

Feedwater Enthalpy (Steam

Using temperature

Critical to use

Tables Lookup)

value of feedwater,

temperature and

determines enthalpy of

not pressure of

sat liquid at 4400F to

feed to determine

be 419.0

enthalpy.

4

Att. 5 - 3

Enthalpy Rise Across the

Determines enthalpy

Critical to

Steam Generators

rise across SGs, by

accurately

subtracting FW

calculate

enthalpy from SG exit

enthalpy rise to

enthalpy, as SG A -

determine reactor

777.4, SG B -

power.

777.7+02, SG C

777.4

Note that

tolerance is

carried forward.

5

Att. 5 - 4

Steam Generator Powers

1) Fills in FW Flows

Critical to

from Att 3 as SG A

accurately

- 4.246, SG B -

calculate SG

4.223, SG C - 4.255

power to

2) Determines SG

determine reactor

powers, by

power.

multiplying FW

Flows by SG

Note that

enthalpy rise, as SG

tolerance is

A - 3300.84, SG B -

carried forward

3284.23+0.85, SG C

and adjusted due

- 3307.84

to multiplication.

Page 5 of 12

Rev. Date 07/21/02

JPM COM-A. 1-2

HARRIS

Page 6 of 12

Rev. Date 07/21/02

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

6

Att. 5 - 5

Calculate Total Reactor

Determines total

Critical to

Power

reactor power, by

accurately

adding the SG powers

calculate total

and subtracting RCP

reactor power to

heat input, as

determine reactor

9850.60+0.85

power.

Note that

tolerance is

carried forward.

7

Att. 5 -- 6

Convert Mbtu/hr to MWth

Converts to thermal

Critical to

power, by dividing

accurately

total reactor power by

convert to

a conversion factor, as

determine reactor

2886.96+0.25

power.

Note that

tolerance is

carried forward

and adjusted for

division.

8

Att. 5 - 7

Calculate Percent of Rated

Determines percent

Critical to

Thermal Power

reactor power, by

accurately

dividing thermal power convert to

by rated thermal

determine percent

power, as 99.6+0.1

reactor power.

Note that

tolerance is

carried forward

and adjusted for

division.

JPM COM-A. 1-2

HARRIS

12

Att 6

Check OST performed for

Checks periodic

periodic surveillance

surveillance

13

Fill in plant conditions

Fills in plant conditions

as 100% power, Mode 1

14

Sign / date completion of

Signs and dates

OST

completion of OST

TASK COMPLETE

STOP TIME:

Page 7 of 12

Rev. Date 07/21/02

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

9

Att. 5 - 8

Power Range NI

1) Fills in highest and

Critical to

Surveillance

lowest indicated PR

accurately

channels from Att 3

determine

as 100 and 99.5

difference

2) Determines

between

difference between

indicated and

actual power to

calculated power,

determine if PR

by subtracting

NI channels

calculated from

require

indicated, as

adjustment.

Highest Indicated

0.4+0.1% and

Note that

Lowest Indicated -

tolerance is

(-)0.1+0.1%

carried forward.

10

Att 5 Perf

Sign Attachment 5 as

Signs Attachment 5

Performer

11

Calculation Verified

Requests verification of

calculation

INDEPENDENT VERIFICATION IS COMPLETED.

421 TF.

JPM COM-A. 1-2

HARRIS

ANSWER KEY FOR JPM COM-A1-2

Attachment 5

Sheet 1 of 2

Calorimetric Worksheet

1.

Calculate Steam Generator Exit Enthalpies

a. Steam Tables Lookup: Saturated Steam, Liquid Enthalpies

SG Pressure

SG A:

900

psia

SG B:

890

psia

SG C:

900

psia

Liq. Enthalpy (h!)

526.7

btu/lbm,

Stm. Enthalpy (h,)

1196.4

btu/Ibm

-4 525.0+/-0.2 btu/lbm, 1196.7+/-0.2

btu/lbm

_>

526.7

b. Calculate SG Exit Steam Enthalpies

Stm. Enthalpy

SG A:

1.00 x

1196.4

.

SG B:

1.00 )196.7+/-0.2+

SG C:

1.00 x

1196.4

+

btu/lbm,

Liq. Enthalpy

(h,)

o.oo , 526.7

0.00 525.0+/-0.2

0.00 x 526.7

1196.4

btu/lbm

Exit Enthalpy

(h~t)

1196.4

btu/Ibm

1196.7+/-0.2 btu/ibm

1196.4

btu/ibm

2.

Feedwater Enthalpy (Stm Tables Lookup)

FrW (TempiPress)

h 440

1080

VW Avg -F

Fa Psia

FW Enthalpy

(hw*)

419.0

hr.

btu/ibm

3.

Enthalpy Rise across the Steam Generators

Exit Enthalpy

(h~i+/-)

1196.4

SC A:

______

SG B:

1196.7+/-0.2

SG C:

1196.4

FW Enthalpy

(h49)

419.0

A Enthalpy

(Ahsa)

777.4

= 777.7+/-0.2

777.4

ANSWER KEY FOR JPM COM-A1-2

Page 8 of 12

Rev. Date 07/21/02

btu/lbm

JPM COM-A. 1-2

HARRIS

ANSWER KEY FOR JPM COM-A1-2

Attachment 5

Sheet 2 of 2

Calorimetric Worksheet

4.

Steam Generator Powers

FW Flow

(MPPH)

4.246

QO A:

Qý ~4.223

Qý c4.255

x

A Enthalpy

(btu/lbm)

777.4

x

777.7+/-0.2

x

777.4

%*G

(Mbtu/hr)

3300.84

Mbtu/hr

3284.23+/-0.85

Mbtu/hr

3307.84

Mbtu/hr

5.

Calculate Total Reactor Power

3300.84

3300.23+/-0.85

+

-A

QSQA

QsoB

6.

Convert Mbtu/hr to MWm

9850.60+/-0.85

Mbtu/hr

3.4121 Mbtu/hr/MWmh

Z886.96+/-0.25

7.

Calculate Percent of Rated Thermal Power

2886.96+/-0.25

Mw",

x

100

2900 MW,,

99.6+/-0.1

% RTP

8.

Power Range NI Surveillance

100.0

Highest PR NI (M

99.5

Lowest PR NI (M

Performed By:

Verified By:

99.6+/-0.1

Calc'd Power (%)

99.6+/-0.1

Calc'd Power (W)

CANDIDATE SIGN

N/A

ANSWER KEY FOR JPM COM-A1-2

Page 9 of 12

Rev. Date 07/21/02

3307.84

Qs c

- 42.31

QRCP

9850.60+/-0.85

QRX

Mbtu/hr

mWm

0.4+/-0.1

-0.1+/-0.1

JPM COM-A. 1-2

HARRIS

ANSWER KEY FOR JPM COM-A1-2

Attachment 6

Sheet 1 of 1

Certifications and Reviews

This OST was oerformed as a:

Periodic Surveillance Requiremeent:

Post Maintenance Operability Test:

Redundant Subsystem Test:

x

Plant Conditions:

OST Completed By:

100% power

CANDIDATE SIGN

Mode:

1

Date: CURRENT

Time: CURRENT

OST Performed By:

Name (Print)

Initials

Name (Print)

Bob Jones

S

Samuel Snead

CANDIDATE INITIAL / PRINT NAME

General Comments/Recommendations/Corrective Actions! Exceptions:

Pages Used:

0ST Completed with

NO EXCEPTIONS /

EXCEPTIONS:

Date:

Unit SCO

After receiving the final review signature, this

should be submitted to Document Services.

OST becomes a QA RECORD and

ANSWER KEY FOR JPM COM-A1-2

Page 10 of 12

Rev. Date 07/21/02

Initials

BJ

JPM COM-A. 1-2

HARRIS

JPM ATTACHMENT

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

OST-1204, Attachments 1-6

Page 11 of 12

Rev. Date 07/21/02

JPM COM-A.1-2

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is operating at approximately 100% power. ERFIS is out-of-service and is

expected to be out for an extended period of time.

OST-1204, Power Range Heat Balance, Manual Calculation, Daily Interval, Mode 1

(Above 15% Power) is to be performed to meet the periodic surveillance requirement

for Technical Specification 4.3.1.1, Table 4.3-1, Item 2a.

Steam Generator Blowdown is isolated.

I&C Technicians have collected all necessary data for the calculation.

INITIATING CUE(S):

You have been directed to perform OST- 1204, Power Range Heat Balance, Manual

Calculation, Daily Interval, Mode 1 (Above 15% Power), by completing Attachment

5, 'ýCalorimetric Worksheet," and Attachment 6, 'Certifications and Reviews."

NOTE: The Examiner will provide you with completed Attachments 1-4 and copies

of Attachments 5 and 6 for you to complete.

Page 12 of 12

Rev. Date 07/21/02

JPM COM-A.2

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-A.2

Review an Equipment Clearance

CANDIDATE:

EXAMINER:

Page 1 of 8

Rev. Date 07/21/02

JPM COM-A.2

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Review an Equipment Clearance

None

ALTERNATE PATH:

FACILITY JPM NUMBER:

IP-164 (Modified)

KA:

2.2.13

IMPORTANCE:

3.8

KA STATEMENT:

TASK STANDARD:

Knowledge of clearing and tagging procedures.

Identifies both discrepancies on clearance as listed in JPM.

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

%'

PERFORM

'WI'

IN PLANT

SIMULATE

REFERENCES:

"* OPS-NGGC-1301, Equipment Clearance

"* S-1311, Simplified Flow Diagram Boron Recycle System

"* OP-109, Boron Recycle System

"* CAR 2166 B-401, Sheet 3587

VALIDATION TIME:

30

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Date

Page 2 of 8

Rev. Date 07/21/02

TASK:

3.6

No

Signature

JPM COM-A.2

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

"* Provide candidate with Attachment which is the completed clearance form

"* OPS-NGGC-1301, "Equipment Clearance"

"* S-1311, "Simplified Flow Diagram Boron Recycle System"

"* OP-109, "Boron Recycle System"

"* CAR 2166 B-401, Sheet 3587

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

The unit is operating at 30% power.

The internals for 3BR-153, Recycle Evaporator Feed Pump 1&2B Discharge Check

Valve, must be replaced. Recycle Evaporator Feed Pump 1 &2B has been secured and

Pump I&2A is aligned for operation.

Mechanical Maintenance has submitted a clearance request. The clearance has been

manually generated.

INITIATING CUE(S):

You are to review the Equipment Clearance Tag Sheet for 3BR-153 and identify

EVERY discrepancy.

NOTE: Individual tags have NOT been generated and are NOT part of the review

process.

Page 3 of 8

Rev. Date 07/21/02

JPM COM-A.2

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH ATTACHED PACKAGE, WHICH

INCLUDES CLEARANCE AND DRAWINGS S-1311 AND CAR 2166 B-401,

SHEET 3587.

ALSO, IF ASKED, PROVIDE A COPY OF OPS-NGGC-1301 AND OP-109 (OR

MAKE SURE COPIES ARE AVAILABLE).

NOTE: JPM IS WRITTEN FOLLOWING THE GUIDELINES OF OPS-NGGC

1301, STEPS 9.2.1.10,9.2.1.13, and 9.2.1.25. NO SPECIFIC ORDER FOR

PERFORMANCE OF THE JPM IS REQUIRED PROVIDED THE CANDIDATE

IDENTIFIES THE DISCREPANCIES. JPM STEPS ARE WRITTEN IN THE

GENERAL FLOWPATH THAT THE PUMP MUST BE TAGGED FIRST,

FOLLOWED BY DISCHARGE PATH, SUCTION PATH, AND THEN DRAINS

AND VENTS.

I

9.2.1.10.a

For systems where a pump or

Determines that

fan is affected by the

clearance correctly has

clearance, the clearance

pump secured (initial

should be installed in the

conditions) and control

following sequence to prevent

switches have info tag

damage to equipment:

hung before tagging

Secure pump/fan and

power to pump

hang a tag on its control

switch.

2

9.2.1.10.b

Remove the power source

Determines that

Critical to

for the pump/fan prime

breaker for pump is

determine that

mover (open breaker,

tagged out of sequence

sequence for

remove fuse, shut steam

as it is to be tagged

tagging pump

supply valve and so forth)

prior to closing any

breaker is not

and place tag on the power

valves

correct to ensure

source.

pump protection.

3 .9.2.1.10.c Reposition valves from

Determines that

control switches, as required

clearance correctly does

by the clearance, and place

not identify any motor

tags on the control switches.

operated valves

Include tags for switches in

requiring tagging

alternate locations if

______ _________ applicable.

____________________________

Page 4 of 8

Rev. Date 07/21/02

JPM COM-A.2

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

4

9.2.1.10.d

Remove power source

Determines that

(electrical, air, hydraulic, and

clearance correctly does

so forth) from valves, if

not identify any motor

applicable, and tag the power

operated valves

source removed,

requiring tagging

"*5

9.2.1.10.e

Reposition manual valves as

Determines that

Critical to isolate

required by the clearance

discharge valve is

all boundary

and place tag on

correctly tagged

isolations.

handwheels of the valves

prior to suction

covered by the clearance,

valve, but

For pumps, shut the

incorrectly tagged

discharge valve before

prior to pump

shutting the suction valve,

breaker being tagged

(noted previously in

JPM Step 3)

& Determines that

3BR-157, REFP

1&2B Recire

Return to RttT Isol

(and Reach Rod), is

NOT included on

clearance, but

should be included

6

9.2.1.13

For devices having a remote

Determines that all

operator, such as a valve

valves on clearance that

reach rod, where both valve

have reach rods have

and reach rod have a

clearances hung

handwheel and are accessible,

correctly on both the

the clearance should be

valve handwheel and the

written such that both

reach rod

mechanical devices are

tagged.

7

9.2.1.25

Whenever possible, an

Determines that drain

atmospheric drain and/or vent

and vent paths are

between the work area and

included as part of

sources of pressure to the

clearance

work area should be tagged in

the open position with the

cap/flange removed to release

pressure in systems and to

accommodate thermal

expansion and contraction.

Page 5 of 8

Rev. Date 07/21/02

JPM COM-A.2

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

8

Inform clearance preparer of

Informs clearance

discrepancies

preparer of 2

discrepancies

"* Incorrect order of

discharge valve!

pump breaker

"* Missing boundary

isolation valve

NOTE: IF CANDIDATE CREATES A SAFETY HAZARD OR THE

PROBABILITY OF EQUIPMENT DAMAGE BY IDENTIFYING ADDITIONAL

ERRORS, THIS WOULD CONSTITUTE A FAILURE OF THE JPM.

TASK COMPLETE

STOP TIME:

Page 6 of 8

Rev. Date 07/21/02

JPM COM-A.2

HARRIS

JPM ATTACHMENT

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

OPS-NGGC-1301, Attachments 3-4

S-1311

CAR 2166 B-401, Sheet 3587

Page 7 of 8

Rev. Date 07/21/02

JPM COM-A.2

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The unit is operating at 30% power.

The internals for 3BR-153, Recycle Evaporator Feed Pump 1&2B Discharge Check

Valve, must be replaced. Recycle Evaporator Feed Pump I&2B has been secured and

Pump 1 &2A is aligned for operation.

Mechanical Maintenance has submitted a clearance request. The clearance has been

manually generated.

INITIATING CUE(S):

You are to review the Equipment Clearance Tag Sheet for 3BR- 153 and identify

EVERY discrepancy.

NOTE: Individual tags have NOT been generated and are NOT part of the review

process.

Page 8 of 8

Rev. Date 07/21/02

JPM SRO-A.3

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM SRO-A.3

Radiological Controls

CANDIDATE:

EXAMINER:

Page 1 of 8

Rev. Date 07/21/02

JPM SRO-A.3

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Offsite Dose Calculation Manual

Radiological Controls

ALTERNATE PATH:

FACILITY JPM NUMBER:

NA - Questions

KA:

1) 2.3.6

2) 2.3.4

IMPORTANCE:

KA STATEMENT:

TASK STANDARD:

1) Knowledge of the requirements for reviewing and

approving release permits

2) Knowledge of radiation exposure limits and

contamination control, including permissible levels in

excess of those authorized

NA - Questions

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

PERFORM

V.

IN PLANT

SIMULATE

REFERENCES:

OP-120.06.02, Waste Evaporator Condensate Tanks

PEP-330, Radiological Consequences

OWP-RM, Radiation, Effluent, and Explosive Gas Monitoring"

VALIDATION TIME:

15

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE RATING:

FINISH TIME:

UNSAT

COMMENTS:

EXAMINER:

Signature

TASK:

1) 3.1

2)3.1

Offsite Dose Calculation Manual

NA

vi

No

Date

Page 2 of 8

Rev. Date 07/21/02

JPM SRO-A.3

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

NOTE: ENSURE THE FOLLOWING REFERENCES ARE AVAILABLE FOR USE

IN ANSWERING THE ATTACHED QUESTIONS:

OP- 120.06.02, "Waste Evaporator Condensate Tanks"

PEP-330, "Radiological Consequences"

OWP-RM, "Radiation, Effluent, and Explosive Gas Monitoring"

Page 3 of 8

Rev. Date 07/21/02

JPM SRO-A.3

HARRIS

START TIME:

EXAMINER'S ANSWER KEY

QUESTION #1

Radwaste is making preparations to discharge the Waste Evaporator Condensate Tank

(WECT) when it is determined that FT-6119, WMT / WECT Discharge Flow, is

inoperable.

What are the license requirements that must be met to allow the WECT to be discharged

with FT-6119 inoperable?

ANSWER:

ODCM 3/4.3.3.10, Radioactive Liquid Effluent Monitoring Instrumentation, Table 3.3

12, Action 38 requires that the flow rate be estimated at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

during the actual release (information can also be determined by referencing OWP

RM-14)

OP- 120.06.02 requires that the flow rate be estimated at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months during

the actual release and that the estimated flow be documented on Attachment 5, Waste

Evaporator Condensate Tank Discharge Flow Instrument Inoperable Log

(Required response underlined and bolded)

REFERENCES:

OP- 120.06.02, "Waste Evaporator Condensate Tanks"

OWP-RM, "Radiation, Effluent, and Explosive Gas Monitoring"

Offsite Dose Calculation Manual

KA / IMP / STATEMENT:

2.3.6 / SRO 3.1 / Knowledge of the requirements for reviewing and approving release

permits

STOP TIME:

Page 4 of 8

Rev. Date 07/21/02

JPM SRO-A.3

HARRIS

START TIME:

EXAMINER'S ANSWER KEY

QUESTION #2

The plant experienced a loss of coolant accident and cold leg recirculation operations

were established per EOP EPP-010, "Transfer to Cold Leg Recirculation." Prior to the

accident RHR Pump lB-SB had been out-of-service due to a damaged bearing. RHR

Pump IA-SA has just failed.

An emergency entry for repairs is to be made into the RHR Pump 1A-SA room. HP

reports general area radiation levels in the room are approximately 20 Rem/hour.

Maintenance estimates that it will take a 3-person team approximately 90 minutes to

make the necessary repairs.

The Maintenance Manager has supplied a list of 5 personnel that are available on site

and qualified to perform the repairs. The 5 persons are:

1)

Anita Andrews is a 47-year-old married female, states she is not pregnant, she

has volunteered to make the entry, and she is fully aware of the radiological risks

involved. She has worked at the Harris plant for 22 years, the last 9 as a member

of the Maintenance department.

2)

Bob Ballew is a 32-year-old married male, he has volunteered to make the entry,

and he is fully aware of the radiological risks involved. He has worked at the

Harris plant as a member of the Maintenance department since he left another

nuclear utility 3 years ago.

3)

Charles Cotton is a 51-year-old single male and although he has not volunteered

to make the entry, he is fully aware of the radiological risks involved. He is the

most knowledgeable of the 5 persons, having been a member of the Maintenance

department for his entire 28 years at the Harris plant.

4)

David Deaver is a 37-year-old married male, he has volunteered to make the

entry, and he is fully aware of the radiological risks involved. He has worked at

the Harris plant for 15 years, the last 11 years as a member of the Maintenance

department since he left Operations.

5)

Frank Furstenburg is a 56-year-old single male, he has volunteered to make the

entry, and he is fully aware of the radiological risks involved. Although he has

only worked at Harris for the past 2 years, both years were spent in the

Maintenance department, and he has experience in these situations, having made

a similar entry 17 years ago at another nuclear utility.

Which 3 of these 5 persons should be selected to make the emergency entry, AND why

should these 3 be picked?

Page 5 of 8

Rev. Date 07/21/02

JPM SRO-A.3

HARRIS

ANSWER:

Anita Andrews, Bob Ballew, and David Deaver should be selected to make this

entry. In events where exposure levels exceeding 25 TEDE would be required all

personnel must be volunteers (eliminating Charles Cotton), they should have a full

awareness of the risks involved (all meet this requirement), and exposure under these

conditions should be limited to once in a lifetime (eliminating Fred Furstenburg).

Although it is preferable to use personnel over the age of 45, age should only be

considered where all other factors are equal. Females should not be considered if they

are declared pregnant, which Anita Andrews has not done.

(Required response underlined and bolded)

REFERENCES:

PEP-330, "Radiological Consequences"

KA / IMP / STATEMENT:

2.3.4 / SRO 3.1 / Knowledge of radiation exposure limits and contamination control,

including permissible levels in excess of those authorized

STOP TIME:

Page 6 of 8

Rev. Date 07/21/02

JPM SRO-A.3

HARRIS

CANDIDATE QUESTION SHEET

QUESTION #2

(TO BE RETURNED TO EXAMINER UPON COMPLETION)

The plant experienced a loss of coolant accident and cold leg recirculation operations

were established per EOP EPP-010, "Transfer to Cold Leg Recirculation." Prior to the

accident RHR Pump 1B-SB had been out-of-service due to a damaged bearing. RHR

Pump 1A-SA has just failed.

An emergency entry for repairs is to be made into the RHR Pump 1A-SA room. HP

reports general area radiation levels in the room are approximately 20 Rem/hour.

Maintenance estimates that it will take a 3-person team approximately 90 minutes to

make the necessary repairs.

The Maintenance Manager has supplied a list of 5 personnel that are available on site and

qualified to perform the repairs. The 5 persons are:

1)

Anita Andrews is a 47-year-old married female, states she is not pregnant, she has

volunteered to make the entry, and she is fully aware of the radiological risks

involved. She has worked at the Harris plant for 22 years, the last 9 as a member

of the Maintenance department.

2)

Bob Ballew is a 32-year-old married male, he has volunteered to make the entry,

and he is fully aware of the radiological risks involved. He has worked at the

Harris plant as a member of the Maintenance department since he left another

nuclear utility 3 years ago.

3)

Charles Cotton is a 51-year-old single male and although he has not volunteered

to make the entry, he is fully aware of the radiological risks involved. He is the

most knowledgeable of the 5 persons, having been a member of the Maintenance

department for his entire 28 years at the Harris plant.

4)

David Deaver is a 37-year-old married male, he has volunteered to make the

entry, and he is fully aware of the radiological risks involved. He has worked at

the Harris plant for 15 years, the last 11 years as a member of the Maintenance

department since he left Operations.

5)

Frank Furstenburg is a 56-year-old single male, he has volunteered to make the

entry, and he is fully aware of the radiological risks involved. Although he has

only worked at Harris for the past 2 years, both years were spent in the

Maintenance department, and he has experience in these situations, having made a

similar entry 17 years ago at another nuclear utility.

Which 3 of these 5 persons should be selected to make the emergency entry, AND why

should these 3 be picked?

Page 7 of 8

Rev. Date 07/21/02

JPM SRO-A.3

HARRIS

CANDIDATE QUESTION SHEET

QUESTION #1

(TO BE RETURNED TO EXAMINER UPON COMPLETION)

Radwaste is making preparations to discharge the Waste Evaporator Condensate Tank

(WECT) when it is determined that FT-6119, WMT / WECT Discharge Flow, is

inoperable.

What are the license requirenents that must be met to allow the WECT to be discharged

with FT-6119 inoperable?

Page 8 of 8

Rev. Date 07/21/02

JPM RO-A.3

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM RO-A.3

Radiological Controls

CANDIDATE:

EXAMINER:

Page 1 of 7

Rev. Date 07/27/02

REGION II

INITIAL LICENSE EXAMINATION

Radiological Controls

ALTERNATE PATH:

I

FACILITY JPM NUMBER:

NA - Questions

KA:

1) 2.3.2

2) 2.3.10

KA STATEMENT:

TASK STANDARD:

IMPORTANCE:

NA

1)2.5

2) 2.9

1) Knowledge of the facility ALARA program.

2) Ability to perform procedures to reduce excessive levels

of radiation and guard against personnel exposure.

NA - Questions

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

PERFORM

Vt'

IN PLANT

SIMULATE

REFERENCES:

AP-545, Containment Entries

AP-504, Administrative Controls for Locked and Very High

Radiation Areas

VALIDATION TIME:

15

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE RATING:

FINISH TIME:

UNSAT

COMMENTS:

EXAMINER:

Date

Page 2 of 7

Rev. Date 07/27/02

JPM RO-A.3

HARRIS

TASK:

1'

No

Signature

JPM RO-A.3

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

NOTE: ENSURE THE FOLLOWING REFERENCES ARE AVAILABLE FOR USE

IN ANSWERING THE ATTACHED QUESTIONS:

AP-545, "Containment Entries"

AP-504, "Administrative Controls for Locked and Very High Radiation Areas"

Page 3 of 7

Rev. Date 07/27/02

JPM RO-A.3

HARRIS

START TIME:

EXAMINER'S ANSWER KEY

QUESTION #1

You are one member of a 5-member team performing an Emergent Entry into

Containment with the plant in Mode 1. The following conditions have been established:

"* The estimated gamma dose rate in the area is 100 mRem/hour.

"* The estimated neutron dose rate in the area is 4 mRem/hour.

"* A heat stress evaluation has NOT been performed and all personnel will be wearing

ice vests.

"* The HP Supervisor has limited the total gamma dose received by the team to

1 man-Rem and the total neutron dose received by the team to 0.03 man-Rem.

Assuming each team member's initial annual TEDE for the year is 100 mRem, WHY is

your Maximum Allowable Stay Time inside Containment only 45 minutes?

ANSWER:

Although the gamma dose rate would permit each team member to work for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ,

and the neutron dose rate would permit each team member to work for 1.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months , since

a heat stress evaluation has NOT been performed each member's stay time is limited

to 45 minutes.

(Required response underlined and bolded)

REFERENCES:

AP-545, "Containment Entries"

KA / IMP / STATEMENT:

2.3.2 / RO 2.5 / Knowledge of the facility ALARA program

STOP TIME:

Page 4 of 7

Rev. Date 07/27/02

JPM RO-A.3

HARRIS

START TIME:

EXAMINER'S ANSWER KEY

QUESTION #2

You require access into a Locked High Radiation Area (LHRA) to hang a clearance on a

valve. HP approval has been obtained to enter the area.

How is a key to the LHRA obtained?

ANSWER:

The HP Technician assigned to perform job coverage must check out an LHRA key

and maintain positive control of the key, returning it to the Lead HP Technician upon

exiting the LHRA.

(Required response underlined and bolded)

REFERENCES:

AP-504, "Administrative Controls for Locked and Very High Radiation Areas"

KA / IMP / STATEMENT:

2.3.10 / RO 2.9 / Ability to perform procedures to reduce excessive levels of radiation

and guard against personnel exposure.

STOP TIME:

Page 5 of 7

Rev. Date 07/27/02

JPM RO-A.3

HARRIS

CANDIDATE QUESTION SHEET

QUESTION #2

(TO BE RETURNED TO EXAMINER UPON COMPLETION)

You require access into a Locked High Radiation Area (LHRA) to hang a clearance on a

valve. HP approval has been obtained to enter the area.

How is a key to the LHRA obtained?

Page 6 of 7

Rev. Date 07/27/02

JPM RO-A.3

HARRIS

CANDIDATE QUESTION SHEET

QUESTION #1

(TO BE RETURNED TO EXAMINER UPON COMPLETION)

You are one member of a 5-member team performing an Emergent Entry into

Containment with the plant in Mode 1. The following conditions have been established:

"* The estimated gamma dose rate in the area is 100 mRem/hour.

"* The estimated neutron dose rate in the area is 4 toRem/hour.

"* A heat stress evaluation has NOT been performed and all personnel will be wearing

ice vests.

"* The HP Supervisor has limited the total gamma dose received by the team to

1 man-Rem and the total neutron dose received by the team to 0.03 man-Rem.

Assuming each team member's initial annual TEDE for the year is 100 mRem, WHY is

your Maximum Allowable Stay Time inside Containment only 45 minutes?

Page 7 of 7

Rev. Date 07/27/02

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION II

SAM NUNN ATLANTA FEDERAL CENTER

61 FORSYTH STREET, SW, SUITE 23T85

ATLANTA, GEORGIA 30303-8931

MEMORANDUM TO:

FROM:

SUBJECT:

APPLICANT

Gary M. Fulks

Mark 0. Christopherson

Timothy A. English

William S. Saunders

Edward L. Wills, Jr.

August 22, 2002

Kathleen O'Donohue, Senior Operations Engineer

George T. Hopper, Senior Operations Engineer

Michael E. Ernstes, Chief

Operator Licensing and Human Performance Branch

EXAMINATION ASSIGNMENTS - SHEARON HARRIS N

PLANT - EXAM NO. 50-400/2002-301

DOCKET NO.

EXAMINATI

55-22617

55-21791

55-22319

55-22620

55-22621

JUCLEAR

ON TYPE

SRO Upgrade

SRO Instant

Facility and Location:

Facility Contact:

NRC Chief Examiner:

Written Examinations to be Prepared

Date of Operating Tests:

Date of Written Examinations:

Time of Written Examinations:

cc:

D. Trimble, IEHB

J. Goshen, NRR

J. Brady, Shearon Harris

Senior Resident Inspector

B. Michael, DRS

OL Exam File

Shearon Harris Nuclear Plant, New Hill, NC

Terry Toler, (919) 362-3493

Kathleen O'Donohue

by (RO): Shearon Harris Nuclear Plant

(SRO): Shearon Harris Nuclear Plant

August 26 , 28, 2002

August 29, 2002

8:00 a.m.

JPM RO-A.4

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM RO-A.4

Activate the Emergency Response Organization

- Dialogic System

CANDIDATE:

EXAMINER:

Page 1 of 8

Rev. Date 08/09/02

JPM RO-A.4

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Activate the Emergency Response Organization - Dialogic System

ALTERNATE PATH:

FACILITY JPM NUMBER:

None

NEW

KA:

2.4.43

IMPORTANCE:

NA

KA STATEMENT:

TASK STANDARD:

Knowledge of emergency communications systems and

techniques

The Emergency Response Organization has been notified of

a plant emergency using the Dialogic System

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

PERFORM

IN PLANT

SIMULATE

REFERENCES:

PEP-3 10, Notifications and Communications

VALIDATION TIME:

15

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 8

Rev. Date 08/09/02

TASK:

2.8

Yes

Date

JPM RO-A.4

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

Telephone System

PEP-3 10, "Notifications and Communications," Attachment 6, "Emergency Response

Organization Activation - Dialogic System"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

"A Site Area Emergency has been declared. It is currently 1030 on Saturday morning.

"A Public Address System announcement directing on-site members of the ERO to

activate the Emergency Response Facilities has been made.

INITIATING CUE(S):

You have been directed to initiate activation of the remainder of the ERO using PEP

310, "Notifications and Communications," Attachment 6, "Emergency Response

Organization Activation - Dialogic System."

NOTES:

1. USE A SPEAKERPHONE TO ALLOW DIALOGIC RESPONSES TO BE

HEARD BY EXAMINER.

2. IF USING AN E&E CENTER PHONE (SIMULATOR OR EOF), DIAL A "9"

PRIOR TO THE NUMBER.

Page 3 of 8

Rev. Date 08/09/02

JPM RO-A.4

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH A CURRENT COPY OF PEP-310,

ATTACHMENT 6

NOTES:

1. PROCEDURE STEPS CORRESPOND TO STEPS IN ATTACHMENT 6. CUES

LISTED (IF USED) SHOULD BE READ DIRECTLY AS WRITTEN AS

AUTOMATIC RESPONSES TO OPERATOR ACTIONS.

2. UNDERLINED CUES ARE REQUIRED TO BE GIVEN, EVEN IF JPM IS

ACTUALLY PERFORMED.

1

1

Scenario Determination -

Selects scenario

Critical to

Select the appropriate

number "23" based on

determine correct

scenario number from the

a Site Area Emergency

scenario number to

provided options

occurring during off

ensure proper

normal hours

activation.

(weekend)

__

_

CUE

FOR JPM PURPOSES ONLY, USE THE FOUR-DIGIT CODE 2509 (SIMULATOR),

2510 (EOF), OR 2511 (CONTROL ROOM). IF USING AN E&E CENTER PHONE

(SIMULATOR OR EOF), DIAL A "9" PRIOR TO THE NUMBER.

2

2A

Connecting to the System

Picks up a plant

Critical to connect

extension and dials

to system to

Dial 2452 on a plant

"2452" or picks up a

establish operation.

extension or dial 362-

Southern Bell line and

2452 if using a Southern

dials "362-2452"

Bell line

CUE

"HELLO"

3

2B

Immediately enter 4357

Enters "4357#"

Critical to establish

followed by the "#" key.

immediately upon

proper connection

hearing "hello"

to system.

response

Page 4 of 8

Rev. Date 08/09/02

JPM RO-A.4

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

CUE

"ENTER THE SCENARIO NUMBER YOU WISH TO WORK WITH."

4

2C

Enter the appropriate

Enters "2509" or

Critical to enter

scenario number followed

"2510" or "2511",

proper scenario

by the "#" key

depending on location

number to ensure

correct notification.

CUE

"YOU ENTERED 2509 (2510/2511). IS THAT CORRECT? PLEASE PRESS 9 FOR

YES, 6 FOR NO."

5

2D

If correct, enter 9

Enters "9"

Critical to validate

proper plant

conditions.

CUE

"THE SELECTED SCENARIO HAS BEEN COMPLETED. DO YOU WANT TO

QUEUE IT? PLEASE PRESS 9 FOR YES, 6 FOR NO."

6

2E

Enter 9

Enters "9"

Critical to direct

system to begin

making calls.

CUE

"YOU WILL QUEUE SCENARIO 2509 (2510/2511) AS A DRILL. ARE YOU SURE

THIS IS WHAT YOU WANT TO DO? PLEASE PRESS 9 FOR YES, 6 FOR NO:'

7

2F

Enter 9

Enters "9'

Critical to direct

system to begin

making calls.

CUE

"PRESS 1 TO STOP SCENARIO MONITOR OR PRESS 2 TO SPEAK OF THE

STATUS. THE SELECTED SCENARIO IS ACTIVE, GOODBYE."

8

2G

Hang up and prepare for

Hangs up phone

Note: The previous

system activation verification

message should be

(System will soon dial

disregarded as this

telephones in the SIM (362-

a system default

1497 or 362-6257), EOF

message not

(362-3650 or 362-3651), or

associated with

MCR (362-7992 or 362-

the ERO activation

.717997)).

1

process at Harris.

Page 5 of 8

Rev. Date 08/09/02

JPM RO-A.4

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

CUE

PHONE LINE RINGS.

9

3A

System Activation

Picks up line that rings

Critical to answer

Verification -

and says anything

phone to provide

When one of the Direct Bell

(voice activated)

verification of

lines rings, answer the

system start.

telephone

CUE

"THIS IS THE HARRIS NUCLEAR PLANT DIALOGIC SYSTEM. PLEASE

ENTER A 2 PLUS YOUR SOCIAL SECURITY NUMBER."

CUE

FOR JPM PURPOSES ONLY, THE SOCIAL SECURITY NUMBER TO BE USED

IS "987-65-4321" (SIMULATOR), "987-65-4320" (EOF), OR "123-45-6789"

(CONTROL ROOM).

"*10

3B

Enter 2-followed by

Enters "2987654321"

Critical to enter

appropriate SSN

(SIMULATOR),

number to verify

"2987654320" (EOF),

actual event

or "2123456789"

occurring requiring

(CONTROL ROOM)

notification.

CUE

"YOU ENTERED 2-987-65-4321 (SIMULATOR), 2-987-65-4320 (EOF), 2-123-45

6789 (CONTROL ROOM). IS THAT CORRECT? PLEASE PRESS 9 FOR YES, 6

FOR NO."

"*11

3C

If correct, enter 9

Enters "9"

Critical to verify

system.

CUE

"THIS IS A DRILL. I REPEAT, THIS IS A DRILL. NO FACILITIES WILL BE

ACTIVATED FOR THIS DRILL. I REPEAT, NO FACILITIES WILL BE

ACTIVATED FOR THIS DRILL. ARE YOU FIT FOR DUTY?"

"*12

3D

Enter 9

Enters "9"

Critical to respond

with 'yes' response

to start system.

Page 6 of 8

Rev. Date 08/09/02

JPM RO-A.4

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

7

UNSAT

CUE

"PLEASE ENTER YOUR ETA IN MINUTES."

"*13

3E

Enter 00

Enters "00"

Note that any

number entry will

work for this entry.

Critical to enter any

number to initiate

dialing system.

CUE

"YOU WILL BE FILLING THE POSITION OF MAIN CONTROL ROOM.

GOODBYE."

14

3F

If the computer functioned as

Notifies SEC-CR that

expected, notify the SEC-CR

Dialogic is calling in the

that Dialogic is calling in the

ERO

15

4

Completion -

Signs and dates

Previous step

Inform SEC-CR of the results

completion of

actually informed

of the system activation

notification

SEC-CR verbally.

TASK COMPLETE

STOP TIME:

Page 7 of 8

Rev. Date 08/09/02

JPM RO-A.4

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A Site Area Emergency has been declared. It is currently 1030 on Saturday morning.

A Public Address System announcement directing on-site members of the ERO to

activate the Emergency Response Facilities has been made.

INITIATING CUE(S):

You have been directed to initiate activation of the remainder of the ERO using PEP

310, "Notifications and Communications," Attachment 6, "Emergency Response

Organization Activation - Dialogic System."

NOTES:

1) USE A SPEAKERPHONE TO ALLOW DIALOGIC RESPONSES TO BE

HEARD BY EXAMINER.

2) IF USING AN E&E CENTER PHONE (SIMULATOR OR EOF), DIAL A "9"

PRIOR TO THE NUMBER.

Page 8 of 8

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM SRO-A.4

Perform an Emergency Action Level

Classification and Recommend Protective

Actions

CANDIDATE:

EXAMINER:

Page 1 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Perform an Emergency Action Level Classification and Recommend

Protective Actions

None

ALTERNATE PATH:

FACILITY JPM NUMBER:

NEW

KA:

2.4.41 / 2.4.44

IMPORTANCE:

4.1/4.0

Knowledge of the emergency action level thresholds and

classifications. / Knowledge of emergency plan protective

action recommendations.

General Emergency determined due to three (3) fission

product barriers breached (EAL 2-1-4) AND PARs

completed satisfactorily.

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

REFERENCES:

SIMULATOR

V

IN PLANT

PERFORM

V'

SIMULATE

"* Emergency Action Level Flowpath

"* PEP- 110, Emergency Classification and Protective Action

Recommendations

VALIDATION TIME:

15

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

FINISH TIME:

MINUTES

NOTE: Performance Rating based on 20% for satisfactory classification during

simulator scenario, 20% for satisfactory classification during JPM, and 60% for

satisfactory protective action recommendation during JPM. Include documentation

from applicable simulator scenario as part of this JPM package.

PERFORMANCE RATING:

COMMENTS:

EXAMINER:

Page 2 of 14

Rev. Date 08/09/02

TASK:

KA STATEMENT:

TASK STANDARD:

NA

Yes

UNSAT

Signature

Date

JPM SRO-A.4

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

PEP- 110, "Emergency Classification and Protective Action Recommendations,"

Attachment 3, "Protective Action Recommendations Process"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

Following a small break Loss of Coolant Accident which occurred 25 minutes ago, the

crew has been performing the actions of EOP-FRP-C. 1, "Response to Inadequate Core

Cooling." In response to all Core Exit Thermocouples being between 1300'F and

14000F, the crew has initiated Safety Injection and opened all PRZ PORVs. EOP

FRP-C. 1 has directed an evaluation of the EAL Network using Entry Point U.

The following plant conditions are noted:

"* Core Exit Thermocouples are still exceeding 1250 0F.

"* The PRT has ruptured and Containment Pressure is 4.3 psig and increasing slowly.

"* Containment Isolation has been verified.

"* SG Narrow Range Levels are all off-scale low with NO MFW or AFW flow

available.

"* All SG Safety Valves and PORVs are currently closed.

"* SG Tube Leakage prior to the Reactor Trip and Safety Injection was 55 gpd.

"* The most recent RCS 1-131 dose equivalent sample was 63 gtCi/cc.

"* The GFFD is inoperable and has been out-of-service for approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

"* Core damage assessments are NOT yet available.

"* Emergency dose projections are NOT yet available.

Page 3 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

RADIATION MONITORING PANEL INDICATIONS

NOTE: Assume all radiation monitors NOT included in this list are indicating at or near

their normal value.

MONITOR

DESCRIPTION

READING / ALARM STATUS

RM-lCR-3589-SA

Cnmt Hi Range Accident

Slowly Increasing, but currently

Monitor

Normal (Green)

RM-1CR-3590-SB

Cnmt Hi Range Accident

Slowly Increasing, but currently

Monitor

Normal (Green)

RM-ILT-3502-SA

Cnmt Leak Detection Noble

4E-5 pCi/cc and slowly increasing

Gas Channel

above Alert (Yellow) level

RM-1LT-3502-SA

Cnmt Leak Detection

Slowly Increasing, but currently

Particulate Channel

Normal (Green)

INITIATING CUE(S):

You are to classify this event.

Page 4 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

START TIME:

DENOTES CRITICAL STEP

Page 5 of 14

Rev. Date 08/09/02

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: ENSURE AN EAL FLOWPATH AND CURRENT COPY OF PEP-110 ARE

AVAILABLE.

NOTE: THERE IS ALSO A LARGE LAMINATED COPY OF THIS WHICH MAY

BE USED.

NOTES:

1. PROCEDURE STEPS ARE NOT LISTED SINCE ATTACHMENT 3 OF PEP

110 IS A FLOWCHART WHICH DOES NOT CONTAIN NUMBERING OF

STEPS.

2. NOT REQUIRED TO REFERENCE PEP-110.

3. THE FOLLOWING JPM STEPS ARE DECISION POINTS REQUIRED TO BE

MADE TO OBTAIN THE CORRECT EAL CLASSIFICATION AND ARE

ADDRESSED FOR THIS REASON, ALTHOUGH NOT ALL ARE

CONSIDERED CRITICAL STEPS.

4. THIS JPM HAS TWO (2) TIME CRITICAL ELEMENTS. THE FIRST TIME

CRITICAL ELEMENT STARTS WHEN THE JPM STARTS AND ENDS WHEN

THE CLASSIFICATION IS COMPLETED. THE SECOND TIME CRITICAL

ELEMENT STARTS WHEN THE CANDIDATE BEGINS TO PERFORM THE

PROTECTIVE ACTION RECOMMENDATIONS AND ENDS WHEN THE

PROTECTIVE ACTION RECOMMENDATIONS ARE COMPLETED.

PLACES TO ENTER THE START AND STOP TIMES FOR THE TIMES ARE

INCLUDED.

JPM SRO-A.4

HARRIS

1PM

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

FIRST TIME CRITICAL ELEMENT START TIME:

1

Enters EAL Network at

Enters EAL Network

NOTE: Given in

proper location

at Entry Point "U" and

initial conditions

indicates RCS

due to being

Breached on FPB

directed to this

Status Board

entry by EOP-FRP

C.1.

Critical to identify

RCS as

BREACHED.

An incorrect entry

here would result in

determining RCS

intact instead of

breached.

2

Indicate RCS Breached on

Indicates RCS Breached

FPB Status Board

on FPB Status Board

3

Initiates monitoring of

Directs Unit-SCO to

NOTE: Crew

Critical Safety Functions

initiate monitoring

should be already

monitoring due to

being in EOP

Network.

4

Any Rad Mon in EAL Table

<NO> Determines no

1 in High Alarm

Rad Monitors in EAL

Table 1 in High Alarm

5

Was Entry at Point "T"

<NO> Determines

NOTE: Given in

entry was made at

initial conditions.

Point "U"

Critical to reach

determination that

Fuel is

JEOPARDIZED.

An incorrect

decision here

would result in

determining Fuel

intact instead of

jeopardized.

6

GFFD Increased > 1.0E5 cpm <NO> Determines

NOTE: Given in

in 30 Mins

GFFD is out-of-service

initial conditions.

Page 6 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEST

ETEP

UNSAT

7

RCS Activity (1-131 Dose

<NO> Determines RCS

NOTE: Given in

Equivalent) > 300 uCi/cc

Activity < 300 tCi/cc

initial conditions.

(63 gCi/cc)

8

Core Cooling CSF Red

<YES> Determines

Critical to identify

Core Cooling CSF is

Fuel as

RED due to CETs

JEOPARDIZED.

being > 12000F

An incorrect

decision here

would result in

determining Fuel

intact instead of

jeopardized.

9

Indicate Fuel Jeopardized on

Indicates Fuel

FPB Status Board

Jeopardized on FPB

Status Board

10

EOP-PATH-2 Entered

<NO> Determines EOP

PATH-2 was NOT

entered

11

Cnmt Leak Det Rad Mon

<NO> Determines Cnmt

NOTE: Given in

Noble Gas Chnl > 8E-3

Leak Det Rad Mon

initial conditions.

JtCi/cc

Noble Gas Chnl < 8E-3

giCi/cc (4E-5 tCi/cc)

12

Was Entry at Point "U"

<YES> Determines

NOTE: Given in

entry was made at Point

initial conditions.

"U"

13

Was Entry at Point "V"

<NO> Determines entry

NOTE: Given in

was made at Point "U"

initial conditions

"*14

Is Cnmt Phase A or Vent

<YES> Determines

NOTE: Safety

Isolation Required?

Phase A and Vent

Injection actuated

Isolation required due

in EOP-FRP-C. 1 if

to Safety Injection

not previously.

signal

Critical to prevent

changing decision

for RCS and Fuel

to intact.

An incorrect

decision here

would result in

RCS and Fuel

being considered

intact.

Page 7 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

15

Primary-to-secondary leakage

<NO> Determines

NOTE: SG tube

in any SG > 10 gpm

primary-to-secondary

leakage given in

leakage in all SGs < 10

initial conditions as

gpm

55 gpd.

16

SG Pressure > 1230 psig

<NO> Determines SG

NOTE: Given in

pressure < 1230 psig due

initial conditions.

to all SG Safeties and

PORVs being closed

17

Cnmt > 3 psig

<YES> Determines

NOTE: Given in

Cnmt pressure > 3 psig

initial conditions.

(4.3 psig)

Critical to identify

Containment as

JEOPARDIZED.

An incorrect

decision here

would result in

Containment being

considered intact

instead of

jeopardized.

18

Indicate Cnmt Jeopardized on

Indicates Cnmt

FPB Status Board

Jeopardized on FPB

Status Board

"*19

3 FPBs Breached I

<YES> Determines all

NOTE: Incorrect

Jeopardized

3 FPBs are breached

response to this

decision would

result in improper

classification due to

only 2 FPBs being

considered

breached.

Critical to allow

determination of

proper EAL

classification and

Page 8 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

20

General Emergency EAL 2-

Determines General

Critical to

1-4 exceeded

Emergency EAL 2-1-4

determine proper

exceeded

EAL classification

and allow

determination of

NOTE: MUST BE

FIRST TIME CRITICAL ELEMENT STOP TIME:

COMPLETE WITHIN 15

MIN TO COMPLETE SAT.

CUE

IF CANDIDATE DOES DETERMINE EAL

NOTE: Although

CLASSIFICATION TO BE GENERAL

conditions are

EMERGENCY, PROVIDE CANDIDATE WITH

different in

ATTACHMENT 'A' (WIND SPEED AND

Attachment B,

DIRECTION) AND DIRECT CANDIDATE TO

same process and

NOW DETERMINE PROTECTIVE ACTION

responses are used

RECOMMENDATIONS BASED ON THIS EVENT.

in remainder of

JPM.

COND. CUE

IF CANDIDATE DOES NOT DETERMINE EAL

CLASSIFICATION TO BE GENERAL

EMERGENCY, PROVIDE CANDIDATE WITH

ATTACHMENT 'B' (CUE SHEET) AND DIRECT

CANDIDATE TO DETERMINE PROTECTIVE

ACTION RECOMMENDATIONS BASED ON THIS

ATTACHED EVENT.

NOTE: ENSURE A CURRENT COPY OF PEP-110, ATTACHMENT 3, IS

AVAILABLE.

NOTE: THERE IS ALSO A LARGE LAMINATED COPY OF THIS WHICH MAY

BE USED.

SECOND TIME CRITICAL ELEMENT START TIME:

"*21

General Emergency

<YES> Determines

NOTE: If using

Declared?

General Emergency

Attachment B

declared based on just

conditions, this

determined EAL

should be YES due

to given conditions.

Critical to allow

determination of

Page 9 of 14

Rev. Date 08/09/02

JPM SRO-A,4

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEP

IUNSAT

22

Substantial core damage is

<NO> Determines NO

NOTE: Conditions

imminent or has occurred

substantial core

all given in initial

damage is imminent or

conditions.

has occurred due to not

having any core

NOTE: If using

damage assessment

Attachment B

damage, CETs being <

conditions, this

23000%, and the core

should be NO due

being uncovered for <

to Core Damage

30 minutes.

being less than 1%

Additionally, Note 4 on

melt, CETs being <

PAR Flowchart does

23000F, and the

NOT apply due to no

core being

direct pathway from

uncovered for < 30

the containment to the

minutes.

environment.

Critical to allow

determination of

23

Determine wind direction

Determines wind

NOTE: Wind

direction from 2200

direction is always

given "from".

Critical to

determine proper

evacuation and

sheltering

subzones.

24

Determine evacuation areas

Determines evacuation

NOTE: Based on 2

subzones to be A,B,C

mile radius and

wind direction

using 2 miles

radius / 5 mile

downwind table.

Critical to

determine proper

evacuation

subzones.

Page 10 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEP

UNSAT

25

Determine shelter areas

Determines shelter

NOTE: Based on 5

subzones to be

miles downwind

D,E,F,G,H,I,J,K,L,M,N

and wind direction

using 2 miles

radius / 5 mile

downwind table.

Critical to

determine proper

sheltering

subzones.

NOTE: MUST BE

SECOND TIME CRITICAL ELEMENT STOP TIME:

COMPLETE WITHIN 15

MIN TO COMPLETE SAT.

TASK COMPLETE

STOP TIME:

Page 11 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

CANDIDATE ATTACHMENT B

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

A GENERAL EMERGENCY has been declared following a large break loss of

coolant accident.

The following conditions are noted:

"* Core Exit Thermocouple temperatures are all between 15000F and 16000F

following the core being uncovered for 18 minutes.

"* Radiochemistry analysis indicates that approximately 0.2% of the fuel volume has

melted.

"* RHR is injecting through the RCS cold legs.

"* Containment Spray is operating with Containment Pressure at 18 psig.

"* Containment hydrogen concentration is 5.5%.

"* Wind Direction is 2200.

"* Wind Speed is 18 mph.

INITIATING CUE(S):

Determine the Protective Action Recommendations for these conditions.

Page 12 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

CANDIDATE ATTACHMENT A

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

WIND DIRECTION AND SPEED

"* Wind Direction is 2200.

"* Wind Speed is 18 mph.

Page 13 of 14

Rev. Date 08/09/02

JPM SRO-A.4

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

Following a small break Loss of Coolant Accident which occurred 25 minutes ago, the

crew has been performing the actions of EOP-FRP-C. 1, "Response to Inadequate Core

Cooling." In response to all Core Exit Thermocouples being between 1300'F and

14000F, the crew has initiated Safety Injection and opened all PRZ PORVs. EOP

FRP-C. 1 has directed an evaluation of the EAL Network using Entry Point U.

The following plant conditions are noted:

"* Core Exit Thermocouples are still exceeding 1250'F.

"* The PRT has ruptured and Containment Pressure is 4.3 psig and increasing slowly.

"* Containment Isolation has been verified.

"* SG Narrow Range Levels are all off-scale low with NO MFW or AFW flow

available.

"* All SG Safety Valves and PORVs are currently closed.

"* SG Tube Leakage prior to the Reactor Trip and Safety Injection was 55 gpd.

"* The most recent RCS 1-131 dose equivalent sample was 63 jiCi/cc.

"* The GFFD is inoperable and has been out-of-service for approximately 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

"* Core damage assessments are NOT yet available.

"* Emergency dose projections are NOT yet available.

RADIATION MONITORING PANEL INDICATIONS

NOTE: Assume all radiation monitors NOT included in this list are indicating at or near

their normal value.

MONITOR

DESCRIPTION

READING / ALARM STATUS

RM-1CR-3589-SA

Cnmt Hi Range Accident

Slowly Increasing, but currently

Monitor

Normal (Green)

RM-1CR-3590-SB

Cnmt Hi Range Accident

Slowly Increasing, but currently

Monitor

Normal (Green)

RM-ILT-3502-SA

Cnmt Leak Detection Noble

4E-5 MCi/cc and slowly increasing

Gas Channel

above Alert (Yellow) level

RM-1LT-3502-SA

Cnmt Leak Detection

Slowly Increasing, but currently

Particulate Channel

Normal (Green)

INITIATING CUE(S):

You are to classify this event.

Page 14 of 14

Rev. Date 08/09/02

JPM COM-B.I.c

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-B.1.c

Secure One Train of CCW to the RHR HXs

CANDIDATE:

EXAMINER:

Page 1 of 6

Rev Date 07/21/02

JPM COM-B. .c

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Secure One Train of CCW to the RHR HXs

None

ALTERNATE PATH:

FACILITY JPM NUMBER:

RO-B. 1.e (NRC Exam - Dec 2000)

KA:

008A2.01

IMPORTANCE:

3.3

KA STATEMENT:

TASK STANDARD:

Ability to operate and / or monitor in the control room:

CCW indications and controls.

Train 'A' CCW is supplying the RHR HX and the non

essential loop.

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

%'

PERFORM

.4

IN PLANT

SIMULATE

REFERENCES:

OP-145, Component Cooling Water

VALIDATION TIME:

15

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 6

Rev Date 07/21/02

TASK:

3.1

No

Date

JPM COM-B.1.c

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

Initialize to an IC where RHR Train 'A' is in operation (IC-2).

Ensure both 'A' and 'B' CCW pumps are operating.

Ensure the following valves are open: 1CC-147, 1CC-167, 1CC-113, and 1CC-127.

Ensure the following valves are closed: 1CC-99 and 1CC-128.

Adjust CCW flows <MRF CCW030 25> and <MRF CCW048 48>.

FREEZE the simulator

When candidate is ready, place simulator in RUN

OP-145, "Component Cooling Water," Section 8.14

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

The plant is in Mode 4. Train 'B' RHR has been removed from service.

Both trains of CCW are in operation, with Train 'A' CCW supplying only the essential

loop and Train 'B' CCW supplying the essential and non-essential loops.

INITIATING CUE(S):

You are to secure CCW Pump 'B' in accordance with OP-145, Section 8.14.

Page 3 of 6

Rev Date 07/21/02

JPM COM-B. L.c

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH COPY OF OP-145, SECTION 8.14.

2

8.14.2.1.1

If the RHR train to be

Closes 1CC-167,

Critical to

taken out of service is

CCW FROM RHR

establish flow

being supplied by the same

HEAT

limitations within

CCW pump as the Non-

EXCHANGER B-

the capability of a

Essential loop then

SB

single pump

perform the following

Verifies the valve

steps:

closed by position

Verification is not

For the RHR HX to be

indicating lights

critical

taken out of service,

Shut 1CC-167, CCW

FROM RHR HEAT

EXCHANGER B-SB

3

8.14.2.1.2

Verify total system flow

Verifies total system

is less than 12,650 gpm

flow is less than 12,000

gpm by adding the

indication on FI-652.1

and FI-653.1

4

8.14.2.1.3

Verify open, the following

Places 1CC-99

Critical to allow

valves:

control switch in

supplying the non

"* 1CC-99, CCW HEAT

OPEN

essential loop

EXCHANGER A TO

Places 1CC-128

from the running

NONESSENTIAL SUP

control switch in

ccw pump

"* 1CC-113, CCW HEAT

OPEN

EXCHANGER B TO

Verifies all valves

Only critical to

NONESSENTIAL SUP

now open by

open ICC-99 and

"* 1CC-127, CCW

observing position

1CC-128

NONESSENTIAL

indicating lights

RETURN TO HEADER

B

"* 1CC-128, CCW

NONESSENTIAL

RETURN TO

HEADER A

Page 4 of 6

Rev Date 07/21/02

JPM COM-B.1.c

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEP

UNSAT

5

8.14.2.1.4

At the MCB, stop the

0

Places CCW Pump

Critical to

desired CCW Pump A-SA

1B-SB control

establish a single

or B-SB

switch in STOP

running CCW

Verifies the pump

pump

stops by observing

breaker indicating

Verification is not

lights

critical

6

8.14.2.1.5

Verify Train B flow stops

Verifies flow stops by

via FI-653.1 and that

observing FI-653.1

pressure remains greater

decreases to zero and

than 62 psig as per PI-650

pressure remains >62

psig on PI-650

7

8.14.2.2

If the RHR train to be taken

Determines RHR train is

out of service is the only

not the only flowpath for

flowpath for the CCW

the CCW pump and does

pump, perform the following

not perform Step

steps:

8.14.2.2

TASK COMPLETE

STOP TIME:

Page 5 of 6

Rev Date 07/21/02

JPM COM-B. L.c

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is in Mode 4. Train B' RHR has been removed from service.

Both trains of CCW are in operation, with Train 'A' CCW supplying only the essential

loop and Train 'B' CCW supplying the essential and non-essential loops.

INITIATING CUE(S):

You are to secure CCW Pump Win accordance with OP-145, Section 8.14.

Page 6 of 6

Rev Date 07/21/02

JPM COM-B. 1.b

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-B. 1.b

LOSP While Paralleling EDG from MCB for

Testing

CANDIDATE:

EXAMINER:

Page 1 of 7

Rev Date 07/21/02

JPM COM-B. l.d

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-B.1.d

Manually Align Containment Spray

CANDIDATE:

EXAMINER:

Page 1 of 6

Rev Date 07/21/02

JPM COM-B. id

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Manually Align Containment Spray

ALTERNATE PATH:

Starts Containment Spray and aligns valves

FACILITY JPM NUMBER:

CR-106

KA:

026A4.01

IMPORTANCE:

KA STATEMENT:

TASK STANDARD:

4.3

4.5

Manually operate in the control room: CSS controls.

Containment Spray has been actuated and all RCPs have

been stopped.

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

%1

PERFORM

1'

IN PLANT

SIMULATE

REFERENCES:

EOP-PATH-1

VALIDATION TIME:

10

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 6

Rev Date 07/21/02

TASK:

No

Date

JPM COM-B. 1.d

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

"* Initialize to a 100 percent condition.

"* Defeat Hi-3 Containment Pressure Signal such that Containment Spray and Phase B Isolation

are not actuated. <ZRPK:519A, ZRPK:519B>

"* Defeat the manual Containment Spray actuation switches on the MCB. <ICOR ZRPK:505A,

ZRPK:505B, ZRPK:506A, ZRPK:506B>

"* Insert an RCS break of sufficient size to sustain containment pressure greater than 10# and

follow PATH-1 to Step 10-- CNMT PRESSURE REMAINED BELOW 10 PSIG. <IMF

RCS 18A 80>

"* Maintain RCPs operating.

"* Place simulator in FREEZE

"* When candidate is ready, place simulator in RUN

EOP-PATH-1 and EOP-PATH-1 Guide

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

An RCS break has occurred inside containment and a reactor trip and SI have been

initiated.

PATH-1 is being implemented.

INITIATING CUE(S):

Step 10, CNMT PRESSURE REMAINED BELOW 10 PSIG, of PATH-1 has just

been reached.

Perform Step 10 of PATH-1.

Page 3 of 6

Rev Date 07/21/02

JPM COM-B. 1.d

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH COPY OF EOP-GUIDE-1, PAGE 13 (STEP

10).

10

CNMT pressure has remained

Checks pressure on

less than 10 psig

MCB indicaters, ERFIS,

or Recorder Panel and

determines pressure has

exceeded 10 psig

2

10.a

Verify Containment Spray

Determines Containment

(RNO)

actuated

Spray Pumps A-SA and

B-SB NOT running

and/or checks ALB

001/4-1 Containment

Spray Actuation NOT lit

3

10.a

Manually actuate

Places two (2)

Note: May attempt

(RNO)

Containment Spray

different

Actuation Hand

combinations of

Switches in ACTUATE

hand switches, two

position

at a time.

4

10.a

Manually actuate

Places Pumps in

Critical to start

(RNO)

Containment Spray

START:

pumps and position

"* Containment Spray valves to provide

Pump A-SA

spray flow

"* Containment Spray

Pump B-SB

Places valves in OPEN:

"* 1CT-50, Cnmt

Spray Pump A-SA

Discharge

"* 1CT-88, Cnmt

Spray Pump B-SB

Discharge

"* 1CT-12, Cnmt

Spray Chemical

Addition

"* ICT-11, Cnmt

Spray Chemical

Addition

Page 4 of 6

Rev Date 07/21/02

JPM COM-B. 1.d

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

5

10.a

Verify Phase B Isolation

Places valves in

NOTE: This is

(RNO)

Valves shut

CLOSE:

NOT considered a

"* 1CC-207, CCW to

critical step, and

RCPs

may NOT be

"* ICC-208, CCW to

performed since the

RCPs

procedure does NOT

1CC-249, RCP

direct performance.

Thermal Barriers

This step will be

Return

performed in Step

"* 1CC-251, RCP

12 of PATH-1 when

Thermal Barriers

Attachment 6 is

Return

performed.

"* 1CC-297, RCP

Bearing Oil Coolers

Candidates may

Return

perform this step at

"* 1CC-299, RCP

this time, but it is

Bearing Oil Coolers

NOT required to be

Return

performed.

6

10.b

Stop all RCPs

Places all RCPs to

Critical to stop all

(RNO)

STOP

RCPs due to

isolating CCW

cooling flow to

RCPs

TASK COMPLETE

STOP TIME:

Page 5 of 6

Rev Date 07/21/02

JPM COM-B. 1.d

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

An RCS break has occurred inside containment and a reactor trip and SI have been

initiated.

PATH- 1 is being implemented.

INITIATING CUE(S):

Step 10, CNMT PRESSURE REMAINED BELOW 10 PSIG, of PATH-1 has just

been reached.

Perform Step 10 of PATH-1.

Page 6 of 6

Rev Date 07/21/02

JPM COM-B.1.e

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-B. 1.e

Transfer to Hot Leg Recirculation

CANDIDATE:

EXAMINER:

Page 1 of 7

Rev Date 07/21/02

JPM COM-B. L.e

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Transfer to Hot Leg Recirculation

ALTERNATE PATH:

Train B high head flow is re-established through cold leg

injection due to failure of hot leg injection valve to open

FACILITY JPM NUMBER:

CR-066

KA:

006A4.05

IMPORTANCE:

KA STATEMENT:

TASK STANDARD:

3.8

3.9

Operate in the control room: Transfer of ECCS flowpaths

prior to recirculation.

Hot leg recirculation has been established.

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

10

PERFORM

1'

IN PLANT

SIMULATE

REFERENCES:

EOP-EPP-01 1, Transfer Between Cold Leg and Hot Leg

Recirculation

VALIDATION TIME:

15

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 7

Rev Date 07/21/02

TASK:

No

Date

JPM COM-B. 1.e

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

Establish the following conditions:

"* Post-LOCA, the plant is aligned for cold leg recirculation per EPP-010, with SI-341

open and SI-340 closed.

"* A and B CSIPs are operating.

"* A and B RHR pumps are operating.

"* RCS pressure is approximately 0 PSIG.

"* Insert a failure for 1SI-86 to normal so it will not open <IOR XA11063 NORMAL>

"* Place simulator in FREEZE.

"* When candidate is ready, place simulator in RUN.

EOP-EPP-01 1, "Transfer Between Cold Leg and Hot Leg Recirculation"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

The plant has experienced a LB LOCA.

It has been 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months since the LOCA occurred and the plant is aligned for cold leg

recirculation per EOP-EPP-010, "Transfer to Cold Leg Recirculation."

INITIATING CUE(S):

You have been directed to perform a transfer to hot leg recirculation per EOP-EPP

011, "Transfer Between Cold Leg and Hot Leg Recirculation."

Page 3 of 7

Rev Date 07/21/02

JPM COM-B. 1.e

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH COPY OF EOP-EPP-011.

Check charging line isolated

Determines charging

line is isolated by

checking charging flow

FI-122.1 indicating 0 or

by checking valves 1CS

235 and ICS-238 closed

2

Check SI aligned for Cold

Determines aligned for

Leg Recirculation

Cold Leg Recirculation

by checking valves or by

checking flow on FI

943 and FI-940

3

3.a

Align RHR Pumps For Hot

Places control power to

Critical to isolate CL

Leg Recirculation:

ON and then places

recirc to allow

Shut low head SI to cold

valve to CLOSED:

alignment for HL

leg valves 1SI-340 and

1SI-341, Low Head

recirc

1SI-341

SI Train B to Cold

Leg Cont Pwr &

Only critical to shut

Vlv Pos AND Low

valve SI-341 since

Head SI Train B to

SI-340 is already

Cold Leg

closed.

Verifies closed:

1SI-340, Low Head

SI Train A to Cold

Leg

4

3.b

Open low head SI to hot

Places control power to

Critical to provide

leg valve 1SI-359

ON and then places

flowpath for HL

valve to OPEN:

recirc

lSI-359, Low Head

SI Trains A & B to

Cold Leg Cont Pwr

& Vlv Pos AND

Low Head SI

Trains A & B to

Cold Leg

Page 4 of 7

Rev Date 07/21/02

JPM COM-B. L.e

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

5

4

Check CSIP injection flow

Determines valves

path:

OPEN by checking

"* Alternate high head SI to

position:

cold leg valve - OPEN:

1SI-52, Alt High

iSI-52

Head SI to Cold Leg

"* Any BIT outlet valve -

1SI-3, Boron Inj

OPEN: 1SI-3 or 1SI-4

Tank Outlet

1SI-4, Boron Inj

Tank Outlet

6

5.a

Align both CSIPs for hot leg

Places CSIP A in

Critical to prevent

recirculation

STOP

damage to pump due

Stop Train A CSIP

to no flowpath

7

5.b

0

Shut alternate high

Places control power to

Critical to isolate CL

head SI to cold leg

ON and then places

recirc to allow

valve: 1SI-52

valve to CLOSE:

alignment for HL

1SI-52, Alt High

recirc

Head SI to Cold

Leg Cont Pwr &

Vlv Pos AND Alt

High Head SI to

Cold Leg

8

5.c

Open alternate high

Places control power to

Critical to provide

head SI to hot leg valve:

ON and then places

flowpath for HL

1SI-107

valve to OPEN:

recirc

1SI-107, Alt High

Head SI to Hot Leg

Cont Pwr & VIv

Pos AND Alt High

Head SI to Hot Leg

9

5.d

Start Train A CSIP

Places CSIP A in

Verification of

START and verifies

current and flow is

current on EI-221 and

NOT critical

flow on FI-940

Critical to provide

flow

"*10

5.e

Stop Train B CSIP

Places CSIP B in STOP Critical to prevent

damage to pump due

to no flowpath

11

5.f

Shut BIT outlet valves:

Places valves to

1SI-3 and 1SI-4

CLOSE:

"* 1SI-3, Boron Inj

Tank Outlet

"* 1SI-4, Boron Inj

Tank Outlet

Page 5 of 7

Rev Date 07/21/02

JPM COM-B. L.e

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEP

UNSAT

12

5.g

Open high head SI to hot

Places control power to

1SI-86 FAILS TO

leg valve: 1SI-86

ON and then places

OPEN

valve to OPEN:

1SI-86, High Head

SI to Hot Leg Cont

Pwr & Vlv Pos

AND High Head SI

to Hot Leg

"*13

5.g.1

Open BIT outlet valves:

Places valves to OPEN:

Critical to provide

(RNO)

1SI-3 and 1SI-4

1SI-3, Boron Inj

flowpath for CL

Tank Outlet

recirc since HL

1 1SI-4, Boron Inj

flowpath cannot be

Tank Outlet

established

14

5.g.2

Consult the Plant

Consults Plant

(RNO)

Operations Staff to

Operations Staff

evaluate use of

Attachment 1 to open

High Head SI to Hot Leg

Valve while continuing

with this procedure

THE UNIT SCO WILL CONTACT THE TSC, AND DIRECTS YOU TO CONTINUE

WITH THE PROCEDURE UNTIL A RECOMMENDATION IS RECEIVED.

"*15

5.h

Start Train B CSIP

Places CSIP B in

Verification of

START and verifies

current and flow is

current on EI-222 and

NOT critical

flow on FI-943

Critical to provide

flow

TASK COMPLETE

STOP TIME:

Page 6 of 7

Rev Date 07/21/02

CUE

JPM COM-B. 1.e

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant has experienced a LB LOCA.

It has been 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months since the LOCA occurred and the plant is aligned for cold leg

recirculation per EOP-EPP-010, "Transfer to Cold Leg Recirculation."

INITIATING CUE(S):

You have been directed to perform a transfer to hot leg recirculation per EOP-EPP

011, "Transfer Between Cold Leg and Hot Leg Recirculation."

Page 7 of 7

Rev Date 07/21/02

JPM COM-B. 1.f

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-B. 1.f

Start an RCP Following Maintenance

CANDIDATE:

EXAMINER:

Page 1 of 6

Rev. Date 07/21/02

JPM COM-B. 1.f

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Start an RCP Following Maintenance

ALTERNATE PATH:

None

FACILITY JPM NUMBER:

CR-005

KA:

003A4.06

IMPORTANCE:

KA STATEMENT:

TASK STANDARD:

2.9

2.9

Operate in the Control Room: Reactor Coolant Pump

parameters

RCP A has been started

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

%'

PERFORM

IN PLANT

SIMULATE

REFERENCES:

OP- 100, Reactor Coolant System

VALIDATION TIME:

10

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 6

Rev. Date 07/21/02

TASK:

No

Date

JPM COM-B.1.f

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

"* Initialize the simulator to a Mode 3 hot standby condition, 557 OF and 2235 psig <IC

7>

"* Secure RCP A

"* Allow simulator to run until plant conditions are stable, then FREEZE

"* When candidate is ready, place simulator in RUN

OP-100, "Reactor Coolant System," Section 5.1

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

The plant is in Mode 3, 557°F and 2235 psig.

RCP A has been out of service for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for maintenance. Maintenance has been

completed and the RCP is ready for operation

INITIATING CUE(S):

You have been directed to start RCP A in accordance with OP- 100, "Reactor Coolant

System," Section 5.1. All initial conditions have been completed.

Page 3 of 6

Rev. Date 07/21/02

JPM COM-B.1.f

HARRIS

START TIME:

DENOTES CRITICAL STEP

Page 4 of 6

Rev. Date 07/21/02

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH COPY OF OP-100, SECTION 5.1.

1

5.1.2.1.a

Verify the following before

Verifies RCS pressure >

pump start:

325 psig (May not

0

If jogging RCPs per GP-

check - not applicable to

001, RCS pressure > 325

start)

psig

2

5.1.2.1.b

9

No. 1 seal Ap > 200 psid

Verifies RCP A seal Ap

>200 psid. (PI-156A1)

3

5.1.2.1.c

Seal injection flow is

Verifies RCP A seal

between 8 and 13 gpm at

injection flow indication

a temperature between

(FI-130A) and VCT

60'F and 1300F

outlet temp indication

(TI- 116.1) in limits

4

5.1.2.1.d

No. 1 seal leakoff is in

Verifies RCP A seal

the normal operating

leakoff meets

range of Attachment 3.

Attachment 3 require

ments (FR-154A)

5

5.1.2.2

Start the RCP oil lift pump

Places RCP A oil lift

Critical to meet

pump switch to start

interlock for

starting pump

6

5.1.2.3

Verify the amber permissive

Verifies amber permis

light on the lift pump control

sive light on the RCP A

switch is lit indicating proper

oil lift pump switch is lit

lift oil pressure has been

achieved

7

5.1.2.4

Allow the RCP oil lift pump

Verifies a minimum of 2

to run for a minimum of 2

minutes has passed since

minutes before starting an

starting the pump

RCP

8

5.1.2.5

Start the RCP

Places RCP A switch to Critical to close

start

breaker for RCP

JPM COM-B.1.f

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEP

UNSAT

5.1.2.6

Verify the following normal

operating parameters:

Running amps: Hot 460

to 540 amps, Cold 715

amps

"* RCS flow: >98%

"* No. 1 seal Ap: > 200 psid

"* No. 1 seal leakoff: in the

normal operating range of

Attachment 3

"* Motor winding

temnnerature: .c300°F

Verifies parameters are

in the normal band

"* Running amps

"* RCS flow

"* No. 1 seal Ap

"* No. 1 seal leakoff

"* Motor winding

temperature

10

5.1.2.7

After at least 1 minute, stop

Verifies one minute has

the RCP oil lift pump

passed and places RCP

A oil lift pump switch to

off

TASK COMPLETE

STOP TIME:

Page 5 of 6

Rev. Date 07/21/02

9

JPM COM-B. 1.f

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is in Mode 3, 557°F and 2235 psig.

RCP A has been out of service for 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for maintenance. Maintenance has been

completed and the RCP is ready for operation

INITIATING CUE(S):

You have been directed to start RCP A in accordance with OP- 100, "Reactor Coolant

System," Section 5.1. All initial conditions have been completed.

Page 6 of 6

Rev. Date 07/21/02

JPM COM-B. 1.g

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-B.1.g

Power Range NI Gain Adjustment

CANDIDATE:

EXAMINER:

Page 1 of 8

Rev Date 07/21/02

JPM COM-B.I.g

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Power Range NI Gain Adjustment

ALTERNATE PATH:

None

FACILITY JPM NUMBER:

NEW

KA:

015A4.02

IMPORTANCE:

KA STATEMENT:

TASK STANDARD:

3.9

3.9

Operate in the Control Room: NIS Indicators

Gain has been adjusted within limits for PR Channel N-44

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

V*

PERFORM

S

IN PLANT

SIMULATE

REFERENCES:

OP-105, Excore Nuclear Instrumentation

VALIDATION TIME:

20

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 8

Rev Date 07/21/02

TASK:

No

Date

JPM COM-B.1.g

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

"* Initialize to a 100% equilibrium condition

"* Place Rod Control in MAN

"* Place Meter Rate on front of PR channel NI-44 to Fast

"* Unlock gain pot on the front of PR channel NI-44

"* Slowly adjust the gain to 1.56 (verify that it indicates approximately 3% - 3.5% below

the other 3 PR channels)

"* Ensure any alarms caused by this adjustment are acknowledged

"* Lock gain pot

"* Place Meter Rate on front of PR channel NI-44 to Slow

"* Place Rod Control in AUTO

"* FREEZE the simulator

"* When candidate is ready, place simulator in RUN

OP-105, "Excore Nuclear Instrumentation," Section 8.3 and Attachment 2

(Provide marked up copy of Attachment 2 to candidate)

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

The plant is at 100% equilibrium conditions.

Following maintenance on PR Channel N-44, all required testing has been completed

and the channel is ready to be returned to service. A calorimetric has just been

performed per OST-1004, "Power Range Heat Balance, Computer Calculation, Daily

Interval, Mode 1 (Above 15% Power)."

The calculated power is 99.8%. Indicated power on PR channel N-44 at the time of

the calorimetric was at its current value. Rod Control is in Automatic.

INITIATING CUE(S):

You are to perform the Power Range NI Gain Adjust for PR channel N-44 in

accordance with OP-105, "Excore Nuclear Instrumentation," Section 8.3 and

Attachment 2.

Page 3 of 8

Rev Date 07/21/02

JPM COM-B. 1.g

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE:

"* PROVIDE CANDIDATE WITH COPY OF OP-105, SECTION 8.3, AND

ATTACHED MARKED UP COPY OF ATTACHMENT 2 OF OP-105.

"* ALL IDENTIFIED PROCEDURE STEPS ARE FROM ATTACHMENT 2.

ACTIONS ARE ONLY TO BE PERFORMED ON PR CH N-44.

1

Record the as found setting of

Records setting as 1.56

the GAIN potentiometer on

(1.54 to 1.58)

the front of Power Range

Drawer B

2

Determine the difference,

Calculates difference to

Determined by

including sign, between the

be 3.6

subtracting indicated

calculated power and the

(3.3 to 3.9)

value of 96.2% from

indicated reactor power at the

99.8% calculated

time data was obtained as

power.

follows:

CALC PWR - N44 IND

PWR = N44 DIFFERENCE

3

Determine the desired

Calculates desired N-44

Determined by

indication, including sign, of

indication to be 99.8%

algebraically

NIS as follows:

summing N-44

difference from Step

N44 PRESENT IND + N44

2 (JPM Step 2) and

DIFFERENCE = N44

N-44 present

DESIRED IND

indicated value

4

Calculation in Steps 2 and 3

Requests independent

independently verified,

verification of

calculation

CUE

INDEPENDENT VERIFICATION HAS BEEN COMPLETED.

5

Before each channel

Verifies no PR trip

adjustment, verify that there

bistables energized on

are no PR trip bistables

TSLB-3 or TSLB-4,

energized on TSLB-3 or

with exception of PR

TSLB-4, except for trip

High Flux Lo Setpoint,

bistables that are manually

which is manually

blocked

Page 4 of 8

Rev Date 07/21/02

JPM COM-B.1.g

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEP

UNSAT

6

On Drawer A, place the

Places Meter Rate

METER RATE switch in

switch to Fast position

FAST

7

7

Before adjustment of GAIN

Places Rod Bank

Critical to prevent

potentiometer for N-44, the

Selector switch in

inadvertent rod

ROD BANK SELECTOR

Manual position

motion due to power

switch should be placed in

mismatch circuit

MANUAL to prevent

undesired rod movement

during the adjustment

CUE

IF CANDIDATE DIRECTS RO TO PLACE RODS IN MANUAL, DIRECT

CANDIDATE TO PERFORM ACTION TO PLACE ROD CONTROL IN MANUAL.

8

Before adjustment of GAIN

Verifies Feed Reg

potentiometer for N-44, the

Bypass Valve

Feed Reg Bypass Valve

Controllers are already

Controllers should be placed

in Manual position

in manual to prevent

undesired valve motion

during adjustment

9

If a RATE TRIP signal

Resets any Rate Trip

occurs, before going to the

signals generated before

next channel, reset the RATE

completing task for

TRIP signal.

channel N-44

CUE

IF CANDIDATE ASKS, THE UNIT-SCO DIRECTS RESETTING THE POWER

RATE TRIP.

"*10

10

At each power range

Unlocks and slowly

Critical to establish

drawer B, unlock and

adjusts Gain pot in

proper indication

slowly adjust GAIN

CW direction until

and operation of

potentiometer until the

indicated power is

channel N-44

indicated power is within

within 0.2% of value

0.2% of the DESIRED IND

previously determined

from Step 3

in Step 3 (JPM Step 4)

11

If there is insufficient fine

N/A's step since

gain adjustment using the

adequate adjustment

drawer B gain potentiometer,

exists

perform the following:

Page 5 of 8

Rev Date 07/21/02

JPM COM-B. 1.g

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

12

Lock GAIN potentiometer in

Locks Gain pot on N-44

place

in place

13

Independent verification is

Requests independent

required

verification

CUE

INDEPENDENT VERIFICATION HAS BEEN COMPLETED.

14

13

Record the as left GAIN

Records as left Gain pot

potentiometer setting

setting (within + 0.02 of

actual)

15

14

On Drawer A, place the

Places Meter Rate

METER RATE switch in

switch in Slow position

SLOW.

16

Independent verification is

Requests independent

required

verification

CUE

INDEPENDENT VERIFICATION HAS BEEN COMPLETED.

17

15

Record the new indicated

Records the new N-44

power (on drawer A)

indicated power

"*18

16

Verify that new indicated

Verifies that N-44

Critical since 2% is

power is within 2% of

indicated power is

limit for performing

desired indication from

within 2% of desired

gain adjustment

Step 3 above,

indication

19

17

Place ROD BANK

Places Rod Control back

May reference OP

SELECTOR switch in the

in automatic

104 to place rods in

desired position

AUTO

20

18

Place Feed Reg Bypass Valve

Leaves Feed Reg Bypass

Controllers in the desired

Valves in manual

position

TASK COMPLETE

STOP TIME:

Page 6 of 8

Rev Date 07/21/02

JPM COM-B.1.g

HARRIS

JPM ATTACHMENT

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

OP-105, Attachment 2, Sheets 1-6

Page 7 of 8

Rev Date 07/21/02

JPM COM-B.I.g

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is at 100% equilibrium conditions.

Following maintenance on PR Channel N-44, all required testing has been completed

and the channel is ready to be returned to service. A calorimetric has just been

performed per OST-1004, "Power Range Heat Balance, Computer Calculation, Daily

Interval, Mode 1 (Above 15% Power)."

The calculated power is 99.8%. Indicated power on PR channel N-44 at the time of

the calorimetric was at its current value. Rod Control is in Automatic.

INITIATING CUE(S):

You are to perform the Power Range NI Gain Adjust for PR channel N-44 in

accordance with OP-105, "Excore Nuclear Instrumentation," Section 8.3 and

Attachment 2.

Page 8 of 8

Rev Date 07/21/02

JPM COM-B.2.b

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-B.2.b

Manually Control Charging Due to a Loss of IA

CANDIDATE:

EXAMINER:

Page 1 of 6

Rev Date 07/21/02

JPM COM-B.2.b

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Manually Control Charging Due to a Loss of IA

ALTERNATE PATH:

None

FACILITY JPM NUMBER:

IP-084

KA:

004.A2.11

KA STATEMENT:

TASK STANDARD:

IMPORTANCE:

4.2

3.6

Correct, control, or mitigate the consequences on CVCS

caused by the following malfunction: Loss of IAS

Charging flow is being controlled locally

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

PERFORM

IN PLANT

'

SIMULATE

'

REFERENCES:

AOP-017, Loss of Instrument Air

VALIDATION TIME:

10

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 6

Rev Date 07/21/02

TASK:

No

Date

JPM COM-B.2.b

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

AOP-017, "Loss of Instrument Air"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All in plant

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

NOT operate any equipment without my permission. I will provide initiating cues and

reports on other actions when directed or asked 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 provide you.

INITIAL CONDITIONS:

The plant is at 100 percent power.

An instrument air header has ruptured on the RAB 236-foot elevation. The header has

been isolated but FCV-122, Charging Flow Control Valve, has failed open.

The Control Room has isolated charging (ICS-235 and 238 are shut). Pressurizer

level is 55 percent.

INITIATING CUE(S):

You have been directed to locally control charging flow per AOP-017, "Loss of

Instrument Air," Section 3.1, Step 6.b (RNO).

Page 3 of 6

Rev Date 07/21/02

JPM COM-B.2.b

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH CURRENT COPY OF AOP-017, SECTION

3.1

1

6.b.(1)

Locally control charging flow

Contacts Control Room

(RNO)

by shutting at least one of the

and requests 1CS-235

following:

and /or be closed 1CS

"* 1CS-235, Charging Line

238

Isolation

"* ICS-238, Charging Line

Isolation

CUE

THE CONTROL ROOM REPORTS BOTH 1CS-235 AND 1CS-238 ARE CLOSED

(ALSO GIVEN ON INITIATING CUE).

2

6.b.(2)

Locally shut 1CS-228,

Rotates valve

Critical to isolate

(RNO)

Charging Line FCV Inlet

handwheel in CW

failed open FCV

Isolation Valve

direction until no

122 to allow control

further movement

of charging flow

is obtained

Informs Control

Room that 1CS-228

is closed

CUE

THE HANDWHEEL FOR 1CS-228 HAS BEEN ROTATED IN CW DIRECTION

AND NO FURTHER MOVEMENT CAN BE OBTAINED.

3

6.b.(3)

Verify open the following:

Contacts Control

Critical to ensure

(RNO)

o

1CS-235, Charging Line

Room and requests the

both valves are open

Isolation

following valves both

to allow charging

0

1CS-238, Charging Line

be opened:

flow to RCS

Isolation

1CS-235

1CS-238

CUE

THE CONTROL ROOM REPORTS BOTH 1CS-235 AND 1CS-238 ARE OPEN.

Page 4 of 6

Rev Date 07/21/02

JPM COM-B.2.b

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

4

6.b.(4)

(CONTINUOUS ACTION)

Throttles open ICS-

Critical to provide

(RNO)

Locally throttle 1CS-227,

227 by rotating

required charging

Norm Charging Line FCV

handwheel in CCW

flow to RCS

Bypass, to obtain desired

direction until directed

charging flow

to stop opening by

Control Room

CUE

THE HANDWHEEL FOR 1CS-227 IS BEING ROTATED IN CCW DIRECTION.

THE CONTROL ROOM DIRECTS YOU TO STOP OPENING VALVE AND

MAINTAIN CURRENT POSITION.

5

6.b.(4)

Maintain current position of

Stops opening ICS

(RNO)

lCS-227, Norm Charging

227 when directed

Line FCV Bypass

by Control Room

Informs Control

Room that 1CS-227

is being throttled to

required position

TASK COMPLETE

STOP TIME:

Page 5 of 6

Rev Date 07/21/02

JPM COM-B.2.b

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is at 100 percent power.

An instrument air header has ruptured on the RAB 236-foot elevation. The header has

been isolated but FCV-122, Charging Flow Control Valve, has failed open.

The Control Room has isolated charging (1CS-235 and 238 are shut). Pressurizer

level is 55 percent.

INITIATING CUE(S):

You have been directed to locally control charging flow per AOP-017, "Loss of

Instrument Air," Section 3.1, Step 6.b (RNO).

Page 6 of 6

Rev Date 07/21/02

JPM COM-B.1.a

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-B. 1.a

Respond to a Failed High Pressurizer Pressure

Channel

CANDIDATE:

EXAMINER:

Page 1 of 8

Rev Date 07/21/02

JPM COM-B.1.a

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Respond to a Failed High Pressurizer Pressure Channel

ALTERNATE PATH:

Pressurizer PORV fails to reseat following actuation

FACILITY JPM NUMBER:

NEW

KA:

010.A2.03

IMPORTANCE:

4.2

KA STATEMENT:

TASK STANDARD:

Ability to correct, control, or mitigate the consequences of

the following PRZ PCS malfunction: PORV failures

Master PRZ Controller is in MANUAL, controlling pressure,

with PORV Block Valve 1RC-1 13 closed.

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

%1

PERFORM

V.

IN PLANT

SIMULATE

REFERENCES:

AOP-019, Malfunction of RCS Pressure Control

VALIDATION TIME:

10

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 8

Rev Date 07/21/02

TASK:

4.1

No

Date

JPM COM-B. L.a

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

"* Initialize to a 100% power IC.

"* FREEZE the simulator.

"* Enter malfunction to fail PRZ Pressure Channel 444 high and cause PORV to fail to

reseat <IMF PRS03F 0.1 10> <PT:444 2500 90>.

"* When candidate is ready, place simulator in RUN.

"* AOP-019, "Malfunction of RCS Pressure Control"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

The plant is operating at 100% power.

INITIATING CUE(S):

You are the Reactor Operator. Respond to any plant conditions.

Page 3 of 8

Rev Date 07/21/02

JPM COM-B. L.a

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

1

3.0.1

(IMMEDIATE ACTION)

Determines bubble

Check that a bubble exists in

exists due to plant

the PRZ

conditions

2

3.0.2

(IMMEDIATE ACTION)

Determines PORV

Critical to isolate the

Verify all PRZ PORVs and

444B failed to fully

PORV to prevent

associated block valves

close as pressure

RPS and/or ESF

properly positioned for

lowers

actuation on low

current PRZ pressure and

Attempts to close

pressure.

plant conditions

PRZ PORV 444B by

placing control

Only critical to close

switch in CLOSE

PORV isolation

Closes PRZ PORV

valve.

444B isolation

valve, RC-113

3

3.0.3

(IMMEDIATE ACTION)

Takes manual control

Critical to close the

Check both PRZ spray

of pressurizer spray

spray valves to

valves properly positioned

valves by either:

prevent RPS and/or

for current PRZ pressure

0

Placing master

ESF actuation on

and plant conditions.

controller PK-444A

low pressure.

in manual, or

Placing spray

Only critical to

valves in manual

cause spray valves

to close, not perform

both actions.

CUE

CONTINUE IN PROCEDURE (PROVIDE CANDIDATE WITH COPY OF AOP

019).

4

NA

Obtain procedure

Obtain current copy of

AOP-019, Sections 3.0

and 3.1

5

3.0.4

Go to Section 3.1, Pressure

Refers to Section 3.1

Control Malfunctions While

Operating With a Pressurizer

Bubble.

Page 4 of 8

Rev Date 07/21/02

JPM COM-B. 1.a

HARRIS

3PM

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEP

U

UNSAT

6

3.1.1

Refer to PEP-i1t0,

Informs SRO of need to

Emergency Classification

refer to PEP-I 10

and Protective Action

Recommendations, and enter

the EAL Network at entry

point X.

CUE

OTHER OPERATORS WILL PERFORM EAL NETWORK CHECKS.

7

3.1.2

(CONTINUOUS ACTION)

Monitors PRZ pressure

Monitor PRZ pressure by

by observing one or

observing other reliable

more of the following:

indication.

PI-455.1

PI-456

PI-457

8

3.1.3

Check plant in Mode 1 or 2.

Determines plant in

Mode 1 by conditions

9

3.1.4

(CONTINUOUS ACTION)

Determines PRZ

Check PRZ pressure

pressure is controlled

controlled.

using PK-444A in

MANUAL

10

3.1.5

(CONTINUOUS ACTION)

Determines pressure is

Check PRZ pressure 2335

< 2335 psig

psig or less.

11

3.1.6

Check all of the following

Determines PRZ

Critical to ensure 1

PRZ PORV block valves

PORV block valves

hour TS requirement

open or Refer to Technical

open:

for closed block

Specification 3.4.4 and

1RC-117

valve is met.

implement action where

1RC-115

appropriate:

Determines PRZ

"* 1RC-117 (for PCV-

PORV block valve

445A SA)

1RC-113 closed.

"* 1RC-115 (for PCV-

Informs SRO of

445B)

need to refer to TS

"* 1RC-113 (for PCV-

3.4.4.

444B SB)

CUE

OTHER OPERATORS WILL REFER TO TECH SPECS.

Page 5 of 8

Rev Date 07/21/02

JPM COM-B.1.a

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

12

3.1.7

Check that a malfunction of

Determines that PT-444

one or more of the following

has failed high by

has occurred:

comparing it to other

"* PT-444

channels.

"* PK-444A

"* PRZ heater(s)

"* PRZ spray valve(s) or

controller(s)

13

3.1.8

Verify PK-444A in

Verifies PK-444A was

MANUAL.

placed in MANUAL as

part of Immediate

Actions.

"*14

3.1.9.a

Control PRZ pressure as

Adjusts PK-444A

Critical to maintain

follows:

output by depressing

control of PRZ

Adjust PK-444A

the UP or DOWN

pressure.

output as necessary, to

buttons as required to

attempt to restore and

control pressure

maintain PRZ

pressure.

"*15

3.1.9.b

(CONTINUOUS ACTION)

Checks both spray

Only critical to

"* Check both PRZ spray

valve controllers

control spray valve

valve controllers in

operating properly if

positions to control

AUTO and both spray

in auto

PRZ pressure if

valves operating as

.

Manually operates

spray valves are in

desired, OR

spray controllers as

manual control.

"* Verify both PRZ spray

needed by

valve controllers in

depressing LP or

NOTE: If spray

MANUAL and operate

DOWN buttons if

valve controllers

spray valves as

in manual

were previously

necessary to control

placed in manual

PRZ pressure

they are to remain in

manual.

16

3.1.9.c

(CONTINUOUS ACTION)

Checks heaters operating

"* Check all PRZ heaters

properly for pressure

operating as desired, OR

"* Manually operate

control switches for

heater groups as

necessary to control

PRZ pressure.

Page 6 of 8

Rev Date 07/21/02

JPM COM-B.L.a

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT/

STEP

UNSAT

3.1.10

Check at least one of the

following conditions present,

orgo to Step 18:

"* PRZ pressure is

uncontrolled

"* Status of a normal spray

valve or a PRZ heater

bank is uncontrolled

"* Determines

pressure, spray

valves, and heaters

are controlled

"* Goes to Step 18

TASK COMPLETE WHEN DETERMINATION

MADE THAT RCS PRESSURE, HEATERS, AND

SPRAYS ARE UNDER CONTROL.

STOP TIME:

Page 7 of 8

Rev Date 07/21/02

17

JPM COM-B. L.a

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant is operating at 100% power.

INITIATING CUE(S):

You are the Reactor Operator. Respond to any plant conditions.

Page 8 of 8

Rev Date 07/21/02

JPM COM-B.2.a

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-B.2.a

Local Actions for a Dropped Rod Recovery

CANDIDATE:

EXAMINER:

Page 1 of 8

Rev Date 07/21/02

JPM COM-B.2.a

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Local Actions for a Dropped Rod Recovery

ALTERNATE PATH:

None

FACILITY JPM NUMBER:

IP-153

KA:

003AAl.02

IMPORTANCE:

KA STATEMENT:

TASK STANDARD:

2.9

2.9

Operate the demand position counter and pulse/analog

converter

Local actions have been completed for rod recovery

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

PERFORM

IN PLANT

SIMULATE

'

REFERENCES:

AOP-001, Malfunction of Rod Control and Indication System

VALIDATION TIME:

15

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 8

Rev Date 07/21/02

TASK:

No

Date

JPM COM-B.2.a

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

Keys 33-36

AOP-001, "Malfunction of Rod Control and Indication System," Section 3.1

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All in plant

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

NOT operate any equipment without my permission. I will provide initiating cues and

reports on other actions when directed or asked 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 provide you.

INITIAL CONDITIONS:

The plant was at 50% power when control bank D rod H2 dropped to the bottom of the

core.

Plant conditions have stabilized and the problem with rod H2 is fixed.

The crew is ready to retrieve the dropped rod.

INITIATING CUE(S):

Rod H2 is ready to be retrieved.

The SCO has directed you to obtain the correct key(s) and perform the local actions

associated with the retrieval of the dropped rod in accordance with AOP-001,

"Malfunction of Rod Control and Indication System," Section 3. 1.

Page 3 of 8

Rev Date 07/21/02

JPM COM-B.2.a

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH COPY OF AOP-001, SECTION 3.1

CUE

THE CONTROL ROOM INFORMS YOU THEY ARE READY FOR YOU TO

PERFORM STEPS 3.1.12,3.1.13, AND 3.1.14.

1

3.1.12

Obtain the key for the Control

Obtains keys 33-36

Rod Disconnect Switch Box

(keys 33-36)

2

3.1.13

Position lift coil disconnect

Unlocks cabinet

Only critical to open

switches for rods in the

and places the

disconnect switches

affected bank as follows:

disconnect switches

for affect rods

"* Dropped rod - ROD

for CBD group 1

CONNECTED (down)

rods B8, H14, and

Critical to ensure

"* All other rods - ROD

P8 and group 2

only rod H2 moves

DISCONNECTED (up)

rods F6, F10, K10,

during retrieval

and K6 in the up

position

Ensures rod H2 in

CBD group 1 is in

the down position

CUE

THE DISCONNECT SWITCHES FOR CBD GROUP 1 RODS B8, H14, AND P8, AND

FOR GROUP 2 RODS F6, FlO, K10, AND K6 ARE IN THE UP POSITION. THE

DISCONNECT SWITCH FOR CBD ROD H2 IS IN THE DOWN POSITION.

3

Inform Control Room of

Notifies Control Room

disconnect switch positions

of disconnect switch

alignment

4

3.1.14

Record the Pulse-To-

Opens the P/A

Only critical to

Analog (P/A) converter

converter cabinet,

record P/A reading

reading for the affected

selects Control Bank D,

bank:

and records the

Critical to ensure

"* Bank

reading for Control

proper response

"* P/A Reading

Bank D

after resetting P/A

converter later

CUE

CONTROL BANK D HAS BEEN SELECTED AND THE INDICATION IS 165.

Page 4 of 8

Rev Date 07/21/02

JPM COM-B.2.a

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

j UNSAT

5

Inform Control Room of Step

Informs Control Room

completion

that Steps 3.1.12, 3.1.13,

and 3.1.14 are complete

CUE

THE CONTROL INFORMS YOU THAT ROD H2 HAS BEEN RETRIEVED AND

YOU ARE TO PERFORM STEPS 3.1.23 AND 3.1.24.

6

Determine light status on

Determines light status

Card A105

on Card A105

CUE

THE LIGHT STATUS ON CARD A105 IS THE TOP, MIDDLE AND BOTTOM

LIGHTS ARE ALL LIT.

7

3.1.23

Repeatedly Press the "Master

Depresses the Master

Cycler +1" button as needed

Cycler +1 button and

to produce the following light

determines the light

status on Card A 105:

status on Card A105

"* Top light - LIT

"* Middle light - NOT LIT

"* Bottom light - LIT

CUE

THE LIGHT STATUS ON CARD A105 IS THE TOP AND MIDDLE LIGHTS ARE

LIT AND THE BOTTOM LIGHT IS NOT LIT.

8

3.1.23

Repeatedly Press the

Depresses the

Critical to ensure

"Master Cycler +1" button

Master Cycler +1

Master Cycler light

as needed to produce the

button and

display is correct

following light status on

determines the

Card A105:

light status on

Top light - LIT

Card A105

Middle light - NOT LIT

Determines light

Bottom light - LIT

status is correct

CUE

THE LIGHT STATUS ON CARD A105 IS THE TOP AND BOTTOM LIGHTS ARE

LIT AND THE MIDDLE LIGHT IS NOT LIT.

9

Inform Control Room that

Informs Control Room

Master Cycler indicates

that Master Cycler

correctly

indicates correctly

Page 5 of 8

Rev Date 07/21/02

JPM COM-B.2.a

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

10

3.1.24

Close all lift coil disconnect

Places the

Only critical to

switches opened in step 13.

disconnect switches

connect disconnect

for CBD group 1

switches

rods B8, H14, and

P8 and group 2

Critical to ensure

rods F6, FlO, K10,

movement of rods

and K6 in the down

following

position

completion of rod

Closes and locks

retrieval

cabinet

CUE

ALL DISCONNECT SWITCHES ARE IN THE DOWN POSITION.

11

Inform Control Room that

Informs Control Room

disconnect switches are in

that disconnect switches

connect position

are in connect position

CUE

THE CONTROL ROOM DIRECTS YOU TO PERFORM THE RNO STEPS OF

STEP 3.1.26.

"*12

3.1.26.

Perform the following at the Positions the Bank

Critical to ensure

a

Pulse-To-Analog (P/A)

Display Selector Switch proper operation of

(RNO)

Converter:

to the Bank D position

P/A converter and

Position the Bank

rod insertion limit

Display Selector Switch

monitor

to the bank recorded in

step 14

CUE

BANK DISPLAY SELECTOR SWITCH IS IN THE BANK POSITION INDICATED

BY THE CANDIDATE (EXPECTED POSITION IS 'D').

"*13

3.1.26.

Position and Hold the

Positions and Holds the Critical to ensure

b

Auto-Manual switch in

proper operation of

(RNO)

MANUAL

P/A converter and

rod insertion limit

monitor

CUE

AUTO-MANUAL SWITCH IS BEING HELD IN THE MANUAL POSITION.

Page 6 of 8

Rev Date 07/21/02

JPM COM-B.2.a

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

CUE

WHEN REQUESTED BY CANDIDATE BEFORE DEPRESSING THE DOWN

PUSHBUTTON, THE P/A READING IS 330 STEPS.

"*14

3.1.26.

Repeatedly Press either

Depresses UP

Critical to ensure

c

the UP pushbutton or

pushbutton until P/A

proper operation of

(RNO)

the DOWN pushbutton

reading indicates 165

P/A converter and

as needed to make the

rod insertion limit

display match the P/A

monitor

reading recorded in step

14

CUE

(COUNT NUMBER OF TIMES CANDIDATE DEPRESSES DOWN BUTTON AND

SUBTRACT FROM 330 TO DETERMINE THIS VALUE)

AFTER DEPRESSING THE DOWN PUSHBUTTON REPEATEDLY, THE P/A

READING IS THE VALUE DETERMINED BY COUNTING THE NUMBER OF

TIMES THE BUTTON WAS DEPRESSED AND SUBTRACTING THE NUMBER OF

TIMES DEPRESSED FROM 330 (FINAL EXPECTED VALUE IS 165 STEPS).

15

3.1.26.

Release the Auto-Manual

Releases Auto-Manual

d

switch

(RNO)

CUE

THE AUTO-MANUAL SWITCH HAS BEEN RELEASED.

16

3.1.26.

Position the Bank Display

Positions Bank

e

Selector Switch to

Display Selector

(RNO)

DISPLAY OFF

Switch to DISPLAY

OFF and closes

cabinet

Informs Control

Room that RNO

steps of Step 3.1.26

are complete

CUE

BANK DISPLAY SELECTOR SWITCH IS IN THE DISPLAY OFF POSITION.

17

Inform Control Room that

Informs Control Room

RNO steps of Step 3.1.26 are

that RNO steps of Step

complete

3.1.26 are complete

TASK COMPLETE

STOP TIME:

Page 7 of 8

Rev Date 07/21/02

JPM COM-B.2.a

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant was at 50% power when control bank D rod H2 dropped to the bottom of the

core.

Plant conditions have stabilized and the problem with rod H2 is fixed.

The crew is ready to retrieve the dropped rod.

INITIATING CUE(S):

Rod H2 is ready to be retrieved.

The SCO has directed you to obtain the correct key(s) and perform the local actions

associated with the retrieval of the dropped rod in accordance with AOP-001,

"Malfunction of Rod Control and Indication System," Section 3.1.

Page 8 of 8

Rev Date 07/21/02

JPM COM-B.2,c

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

JPM COM-B.2.c

Start Up a Hydrogen Recombiner

CANDIDATE:

EXAMINER:

Page 1 of 8

Rev. Date 07/21/02

JPM COM-B.2.c

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

Start Up a Hydrogen Recombiner

ALTERNATE PATH:

None

FACILITY JPM NUMBER:

IP-020

KA:

028A4.01

IMPORTANCE:

4.0

KA STATEMENT:

TASK STANDARD:

Operate the Hydrogen Recombiner controls

Electric Hydrogen Recombiner A is in operation with the

proper power setting

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

PERFORM

IN PLANT

1

SIMULATE

V

REFERENCES:

OP-125, Post Accident Hydrogen System

VALIDATION TIME:

20

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 8

Rev. Date 07/21/02

TASK:

4.0

No

Date

JPM COM-B.2.c

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

OP-125, "Post Accident Hydrogen System"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

I will explain the initial conditions and state the task to be performed. All in plant

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

NOT operate any equipment without my permission. I will provide initiating cues and

reports on other actions when directed or asked 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 provide you.

INITIAL CONDITIONS:

The plant has sustained a LOCA.

RCS pressure is 350 psig and core exit T/Cs are > 12000F.

INITIATING CUE(S):

EPP-FRP-C. 1, "Response to Inadequate Core Cooling," directs starting up a hydrogen

recombiner.

The Unit SCO directs you to start up Electrical Hydrogen Recombiner A using OP 125, "Post Accident Hydrogen System," Section 5.1.

Page 3 of 8

Rev. Date 07/21/02

JPM COM-B.2.c

HARRIS

START TIME:

DENOTES CRITICAL STEP

Page 4 of 8

Rev. Date 07/21/02

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

NOTE: PROVIDE CANDIDATE WITH CURRENT COPY OF OP-125, SECTION

5.1

CUE

ALL INITIAL CONDITIONS FOR SECTION 5.1 ARE COMPLETED.

1

5.1.2.1.a

Perform the following

Refers to SPTOP or

calculation:

MCB containment

Measure the contain-

pressure indications to

ment pressure after a

determine containment

LOCA using one of the

pressure

following:

"* SPTOP

"* PI-950 SA, PI-952

SA, PI-951 SB, P1

953 SB

CUE: CONTAINMENT PRESSURE IS 5 PSIG.

2

5.1.2.1.b

Determine the pre-

Refers to DSR OST

LOCA containment

1021 to determine last

temperature from OST-

known containment

1021 records

temperature prior to

LOCA

___

I

____

I

_______

____

PRE-LOCA CONTAINMENT TEMPERATURE WAS 900F.

CUE

3

5.1.2.1.c

Determine Pressure

Refers to Attachment 8

Factor (Cp) from

of OP-125 and

Attachment 8.

determines Cp value of

1.25 (1.24 to 1.26)

JPM COM-B.2.c

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

4

5.1.2.1.d

Calculate required

Refers to Attachment 8

Critical to

Electric Hydrogen

of OP-125 and

determine value to

Recombiner (EHR)

calculates EHR power

set EHR final

power by multiplying

to be 51.1 KW (51.6 to

setting

Cp x Reference Power

52. 1)

as shown on Attach-

NOTE: Using

ment 8.

values for EHR B

in error will result

in range of 49.8 to

50.8 (actual value

of 50.3)

5

5.1.2.2.a

At the EHR Control Panel

Verifies Power In

A-SA, perform the

Available white light is

following:

lit

Verify lit, Power In

Available, white light

CUE

'POWER IN AVAILABLE' WHITE LIGHT IS LIT.

6

5.1.2.2.b

Set the Power Adjust

Rotates Power Adjust

potentiometer at zero

pot fully CCW to zero

(000).

CUE

'POWER ADJUST' POT HAS BEEN ROTATED FULLY TO ZERO POSITION.

7

5.1.2.2.c

Place the Power Out

Places Power Out

Critical to provide

switch to on

switch to on position

output from EHR

CUE

'POWER OUT' SWITCH IS IN ON POSITION.

8

5.1.2.2.d

Verify lit the red light on

Verifies red light lit on

the switch plate

switch plate

CUE

RED LIGHT ON SWITCH PLATE IS LIT.

9

5.1.2.2.f 1

Turn the Power Adjust

Rotates Power Adjust

potentiometer clockwise

pot CW until Power Out

until 5 KW is obtained

Meter indicates 5 KW

on the Power Out meter.

CUE

'POWER ADJUST' POT HAS BEEN ROTATED IN CW DIRECTION AND

'POWER OUT' METER READS 5 KW.

Page 5 of 8

Rev. Date 07/21/02

JPM COM-B.2.c

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

10

5.1.2.2.g

Maintain 5 KW for 10

Maintains current

minutes.

position on Power

Adjust pot for 10

minutes

CUE

10 MINUTES HAVE ELAPSED.

11

5.1.2.2.h

Turn the Power Adjust

Rotates Power Adjust

potentiometer clockwise

pot CW until Power Out

until 10 KW is obtained

Meter indicates 10 KW

on the Power Out meter

CUE

'POWER ADJUST' POT HAS BEEN ROTATED IN CW DIRECTION AND

'POWER OUT' METER READS 10 KW.

12

5.1.2.2.i

Maintain 10KW for 10

Maintains current

minutes.

position on Power

Adjust pot for 10

minutes

CUE

10 MINUTES HAVE ELAPSED.

13

5.1.2.2.j

Turn the Power Adjust

Rotates Power Adjust

potentiometer clockwise

pot CW until Power Out

until 20 KW is obtained

Meter indicates 20 KW

on the Power Out meter.

CUE

'POWER ADJUST' POT HAS BEEN ROTATED IN CW DIRECTION AND

'POWER OUT' METER READS 20 KW.

14

5.1.2.2.k

1

Maintain 20 KW for 5

Maintains current

minutes.

position on Power

Adjust pot for 5 minutes

CUE

5 MINUTES HAVE ELAPSED.

Page 6 of 8

Rev. Date 07/21/02

JPM COM-B.2.c

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT/

[STEP

STEP

UNSAT

"*16

5.1.2.2.1

Turn the Power Adjust

Rotates Power Adjust

Critical to establish

potentiometer

pot CW until Power

proper power

clockwise until the

Out Meter indicates

output from EHR

required power setting

51.1 to 52.1 KW (Value

calculated in Step

determined in JPM

5.1.2.1.d (JPM Step 4)

Step 4)

is obtained on the

Power Out meter.

CUE

'POWER ADJUST' POT HAS BEEN ROTATED IN CW DIRECTION AND

'POWER OUT' METER READS 51.1 to 52.1 KW (Value determined in JPM Step 4).

TASK COMPLETE

STOP TIME:

Page 7 of 8

Rev. Date 07/21/02

JPM COM-B.2.c

HARRIS

CANDIDATE CUE SHEET

(TO BE RETURNED TO EXAMINER UPON COMPLETION OF TASK)

INITIAL CONDITIONS:

The plant has sustained a LOCA.

RCS pressure is 350 psig and core exit TICs are > 1200 0F.

INITIATING CUE(S):

EPP-FRP-C. 1, "Response to Inadequate Core Cooling," directs starting up a hydrogen

recombiner.

The Unit SCO directs you to start up Electrical Hydrogen Recombiner A using OP 125, "Post Accident Hydrogen System," Section 5.1.

Page 8 of 8

Rev. Date 07/21/02

JPM COM-B. L.b

HARRIS

REGION II

INITIAL LICENSE EXAMINATION

LOSP While Paralleling EDG from MCB for Testing

ALTERNATE PATH:

FACILITY JPM NUMBER

EDG output breaker 126 fails to open on LOSP and must be

manually opened

NEW

KA:

056AA2.14

IMPORTANCE:

4.6

KA STATEMENT:

TASK STANDARD:

Determine as related to a Loss of Offsite Power: Operational

status of EDGs

EDG B output breaker 126 has been manually opened

PREFERRED EVALUATION LOCATION:

PREFERRED EVALUATION METHOD:

SIMULATOR

"

PERFORM

IN PLANT

SIMULATE

REFERENCES:

OP-155, Diesel Generator Emergency Power System

VALIDATION TIME:

15

MINUTES

TIME CRITICAL:

CANDIDATE:

START TIME:

PERFORMANCE TIME:

PERFORMANCE RATING:

FINISH TIME:

MINUTES

UNSAT

COMMENTS:

EXAMINER:

Signature

Page 2 of 7

Rev Date 07/21/02

TASK:

4.4

No

Date

JPM COM-B. 1.b

HARRIS

TOOLS / EQUIPMENT / PROCEDURES NEEDED:

Initialize the simulator to a 100% power condition.

StartEDGB.

SEE INSTRUCTIONS AFTER STEPS 13 AND 18 TO ENTER ADDITIONAL

MALFUNCTIONS.

"* STEP 13 - Prevent EDG B breaker 126 from automatically opening on subsequent

LOSP (allowing manual operation to open) <ICOR ZCR31748 FAILASIS>.

"* STEP 17 - <IMF EPS01> To cause a loss of offsite power to the plant.

Place simulator in FREEZE.

When candidate is ready, place simulator in RUN.

OP- 155, "Diesel Generator Emergency Power System"

READ TO OPERATOR

INSTRUCTIONS TO CANDIDATE:

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 or asked 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 provide you.

INITIAL CONDITIONS:

The plant is operating at 100% power.

Emergency Diesel Generator lB-SB has been started and is ready to be paralleled to

the grid.

INITIATING CUE(S):

You have been directed to parallel EDG lB-SB to the grid in accordance with OP-155,

"Diesel Generator Emergency Power System," Section 5.3. All initial conditions of

Section 5.3.1 have been completed.

Exercising the Voltage and Governor Controls is required.

Page 3 of 7

Rev Date 07/21/02

JPM COM-B. 1b

HARRIS

START TIME:

DENOTES CRITICAL STEP

PROC

STEP

1

5.3.2.1

CUE

2

CUE

5.3.2.2

3

5.3.2.3

4

5.3.2.4.a

5

5.3.2.4.b

ELEMENT

STANDARD

NOTES

SATA/

UNSAT

NOTE: PROVIDE CANDIDATE WITH COPY OF OP-155, SECTION 5.3

Notify Load Dispatcher EDG

Request Unit SCO

lB-SB will be loaded

notify Load Dispatcher

DISPATCHER HAS BEEN NOTIFIED.

Review Precautions

Reviews precautions

4.0.0.021, 4.0.0.022,

4.0.0.024 and 4.0.0.025

before paralleling

(IF ASKED WHEN REVIEWING PRECAUTION 4.0.0.021) UPP-1A IS ALIGNED

TO ITS NORMAL SOURCE.

Place DIESEL GEN B-SB

Turns EDG B sync

Critical to permit

SYNCHRONIZER control

scope on

closure of EDG

switch to SYNC

breaker 126

Position DIESEL GEN B-SB

Adjust EDG B Auto

AUTO VOLTAGE ADJUST

Voltage Adjust until

control switch to RAISE or

EDG voltage indicates

LOWER as necessary to

6.6 KV

perform the following:

Lower voltage to 6.6 KV

Raise voltage to 7.2 KV

Adjust EDG B Auto

Voltage Adjust until

EDG voltage indicates

7.2 KV

6

5.3.2.4.c

Position DIESEL GEN B-SB

Adjust EDG B Auto

AUTO VOLTAGE ADJUST

Voltage Adjust until

control switch to RAISE or

EDG voltage matches

LOWER as necessary to

6.9KV Bus 1B-SB

perform the following:

voltage (0 A VOLTS)

Adjust EDG voltage to

match the associated

Emergency 6.9KV Bus

voltage as indicated by

zero differential voltage

on EI-6953B SB , B

SYNC A VOLTS

Page 4 of 7

Rev Date 07/21/02

JPM COM-B. L.b

HARRIS

PROC

ELEMENT

STANDARD

NOTES

SAT /

STEP

UNSAT

7

15.3.2.5.a

8

5.3.2.5.b

9

5.3.2.5.c

10

5.3.2.6

11

5.3.2.7

"*12

5.3.2.8

13

5.3.2.9

Position DIESEL GEN B-SB

GOVERNOR CONTROL

switch to RAISE or LOWER

as necessary to perform the

following:

"* Lower frequency to 59

HZ

"* Raise frequency to 61 HZ

Position DIESEL GEN B-SB

GOVERNOR CONTROL

switch to RAISE or LOWER

as necessary to perform the

following:

Adjust EDG speed until

the synchroscope is

rotating slowly in the

FAST direction

(CLOCKWISE)

Check synchronizing lights

are cycling (OUT when the

synchroscope is at the 12

o'clock position) in agreement

with the synchroscope

rotation

As necessary, position

DIESEL GEN B-SB AUTO

VOLTAGE ADJUST

control switch to adjust EDG

voltage to zero differential

voltage on EI-6953B SB , B

SYNC A VOLTS

When the synchroscope

reaches the 12 o'clock

position and the

synchronizing lights are

TOTALLY DARK, place

the DIESEL GEN B-SB

BREAKER 126 SB control

switch to CLOSE

Check DIESEL GEN B-SB

Adjust EDG B Governor

Control until EDG B

frequency is indicating

59 HZ

Adjust EDG B Governor

Control until EDG B

frequency is indicating

61 HZ

Adjust EDG B Governor

Control until EDG B

sync scope is indicating

slow CW movement

Verify sync lights

cycling properly in

agreement with sync

scope

Readjust EDG B Auto

Voltage Adjust until

EDG voltage matches

6.9KV Bus 1B-SB

voltage (0 A VOLTS)

Place EDG B breaker

126 to close position

when sync scope

indicates 12 o'clock

position and sync lights

are totally dark

Verify EDG B breaker is

I

~

I BREAKER 126 SB is closed I closedI

Critical to close

EDG breaker 126

to permit EDG to

pickup load

Page 5 of 7

Rev Date 07/21/02

JPM COM-B. L.b

HARRIS